ML20211C539
| ML20211C539 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 02/01/1985 |
| From: | Noonan V NRC - COMANCHE PEAK PROJECT (TECHNICAL REVIEW TEAM) |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20211C348 | List: |
| References | |
| FOIA-85-312 NUDOCS 8606120337 | |
| Download: ML20211C539 (1) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION g,. - [ g ;p WASHINGTON, D. C. 20555
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MEMORANDUM FOR: Darrell G. Eisenhut' Director ' Division of Licensing FROM: Vincent S. Noonan, Director Comanche Peak Project
SUBJECT:
SUMMARY
OF CURRENT ACTIONS IN THE COMANCHE PEAK PROCEEDING During the week of January 14, 1985, the following were highlights of major items associated with' Comanche Peak proceeding: On January 16, the Board issued a memorandum clarifying its Welding , Issues Order of December 18, 1984. The Boards' action was generally favorable to staff's request for clarification. The applicant's announced that Thomas Dignan of Ropes and Gray has been retained as counsel to supplement the efforts of Bishop, Liberman, Cook, Purcell and Reynolds. A notice of appearance has not yet been filed. The Board granted the applicant's request to delay hearings on intimidation, originally scheduled for the week of January 22. A conference call among the Board and parties will be held in the near future to discuss hearing scheduling matters. If you would like to be briefed in more detail on any of the above items, please contact me. L
. , rector
' omanche P ak F ject cc: H. Denton E. Case J. Scinto S.
E. Jordan Trt.by / J. Gagliardo C. Haughney TRT Staff 8606120337 860606 PDR FOIA CARDE85-312 PDR 3g f0/A B S~ # 3/D P A!/as
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MEMORANDUM FOR: Darrell G. Eisenhut, Director Division of Licensing FROM: Vincent S. Noonan, Director Comanche Peak Project
SUBJECT:
COMANCHE PEAK ACTION ITEMS - SCHEDULE DATE Enclosed is the third update to the tabulation of Comanche Peak Action Items. This updates the tabulation of December 5, 1984, and provides scheduled actions in the areas of Technical Review Team, Licensing and Inspection. An update of legal actions will be provided separately. Significant issues are noted below: The first TRT SSER (Electrical and Test Programs) was issued on February 1, 1985. The second TRT SSER (Civil and Misc areas) should be ready for issue within two weeks. TRT SSERs in other disciplines (Coatings, Mechanical, and 0A) should all be issued by the end of February. Extensive OELD review, corrections and changes resulting from this review, and limited typing support will cumulatively make this target difficult. j - The F0IA response effort is placing considerable demands on Task Forces resources. ~ Completion of the Sumary Dispositions is expected by late February. Completion of Intimidation and Contention 5 Panel actions is expected by the end of February. The staff expects to be able to resume the hearing process by mid-March. I will be pleased to discuss this with you at y r request.
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Enclosure:
As stated l cc: See next page t=otA ts - 31 a
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cc: R. Martin, RIV H. Livermore, RIII (TRT) D. Hunter, RIV J. Calvo, TRT L. Shao, TRT R. Keimig, TRT C. McCracken, TRT B. Hayes, 01 R. Herr, OI E. Christenbury, OELD J. Scinto, OELD J. Knight, DE G. Bagchi DE R. Bernero, DSI H. Thompson, DHFS T. Speis, DST B.J. Youngblood, DL T. Novak, DL R. Wessman, DL A. Vietti, DL R.C. Tang DL W. 011u, TIDC J. Taylor, IE E. Jordan, IE J. Axelrad, IE T. Ippolito, AEOD J. Gagliardo, IE S. Treby, OELD l l l
- a. .
A. TRT Actions Item Lead Responsible Completion Date , Complete Remaining J. Zudans 2/15 A11eger Feedback Effort Response to ASLB memo of R. Keimig 2/15 10/1/84 on " Concerns of Marinos Start-up OA Program for Handling J. Zudans 2/15 Future CPSES Allegations Implemented Transmit Proposed Enforcement Tang /Saffell Actions to Region IV (a) Elect./TestProg. 2/15
-(b) Mech./ Civil /QA Coatings 3/15 Misc.
Action Items from the A. Vietti (lead) 2/15 J. Ellis Mtg of 11/7/84 Bangart, Livermore, Shao, Calvo FOIA Reporting of A. Vietti (lead) 3/29 Task Force Records Task Force Members TDI Diesel Affidavit Hunter /Mizuno 3/8 (DELDAction) OI Reports Review Chandler / Berry 2/22 per ASLB memo
B. SSER Completion Actions
- 1. TRT SSERs Compli.
Draft Ready OELD Review To DL Mgt To Printer Civil /Struct 1/23 2/6 2/12 2/15
& Misc 2/1 2/11 2/22 2/28 Mech / Piping )
(47 Sections 1 QA/QC , 1/25 2/15 2/22 2/28
'1 (69 Sections)
Coatings (TRT & 2/8 2/15 2/22 2/28 NRRStaff)
- 2. CYGNA SSER Lead: G. Bagchi 2/5 2/15 2/22 2/28
- 3. Staff SSER -
Licensing Matters Lead: J. Stefano 2/28 3/8 3/15 3/22
- 4. Concluding SSER Lead: V.. Noonan TBD TBD TBD TBD C. Panel Actions Completion Date
- 1. Intimidation Panel Gagliardo (a) Preliminary Brief for 2/15 Contention 5 Panel (b) Final Report 3/4 (c) Prepare Board Submittal 3/15
Completion Date
- 2. Contention 5 Panel Jordan (a) Site Visit 2/7 (b) Final Report 2/28 (c) Prepare Board Submittal TBD D. Hearing Items - NRR Staff Support
- 1. Motions for Summary Disposition on Piping a'nd Pipe Supports Scheduled Motion Subject Assigned Submittal to OELD QA for pipe support Teledyne/D. Landers 2/12/65 design process Pipe support stability MEB/D. Terao 2/15/85 (Applicant's response incomplete)
Cinched U-bolts ETEC/H. Fleck, P. Chen 2/8/85 ASME/AWS Welding Codes MEB/D. Terao 11/2/84-C Upper lateral restraint D. Jeng and Brookhaven 1/31/85-C (Applicant's response raised 1 newissue) J i Use of generic stiffness in EGCB/J. Fair 11/15/84-C piping analysis. (Applicant's responseincomplete) t Richmond inserts (Applicant's EGCB/J. Fair 12/1/84-C response incomplete) , Wall-to-Wall and floor-to- ETEC/H. Fleck, P. Chen 2/8/85 ceiling piping supports 1 U-bolts as 2-way restraints EGCB/J. Fair 12/1/84-C Force distribution in ETEC/H. Fleck, P. Chen 2/8/85 axial restraints Damping factors (Waiting EGCB/J. Fair 11/13/84-C on applicant's response) X
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Scheduled Motion Subject Assigned Submittal to OELD Safety factors EGCB/J. Fair 11/15/84-C Friction due to small EGCB/J. Fair 11/15/84-C thermal movements Local displacements and ETEC/J. Brammer, P. Chen 2/8/85 stresses (applicant's response incomplete) Section property EGCB/J. Fair 11/15/84-C values Effects of gaps on se'smic i EGCB/J. Fair 11/15/84-C response of pipe support
- 2. Hearinps on above Motions Staff reviewers Estimated for Summary Dispostion and consultants 8 man-wks listed above
- 3. Staff affidavits of CYGNA MEB/D.Terao 2/8/85 IAP (Phase 1 and 2) SGEB/F. Rinaldi 11/15/84-C
- 4. Review of CYGNA IAP Terao Estimated (Phase 4) Contractor - 6 man-wks (awaitingCYGNAsubmittal) Tech Reviewers - 18 man-wks
- 5. Support OELD in preparation Unassigned Estimated of staff testimony, responding Leader - 18 man-wks
, to ASLB Memorandum and i Orders and in preparation of Proposed Partial Initial Findings t
LICENSING ACTION ITEMS A. SER and SSER Unresolved Review Items NRR Staff Scheduled Open Items Assigned Completion
- 1. Preservice and inservice MEB/C. Hammer Resolved, relief inspection and testing granted per 10 CFR program for pumps and valves 50.55a.
(not required for licensin as interim relief granted)g
- 2. Safe shutdown system; ASB/P. Hearn Waiting on Applicant's associated circuits response due 3/15/85
- 3. Fire protection per CHEB/J. Stang Waiting on Applicant's Appendix R Response due 3/15/85
- 4. Handling of heavy loads ASB/P. Hearn Reviewing Applicant's Response dated 1/22/85 Target 2/22/85
- 5. Impact of paint debris on CHEB/C.McCracken 2/28/85 containment sump and long term core cooling (must consider results of Coatings TRT Group)
- 6. Safety Parameter Display HFEB/Lipinski Reviewing Applicant's System Response dated 1/7/85 Target 2/22/85
- 7. Integrated leak rate CSB/C. Li Resolved by CSB memo test methodology dated 1/17/85
- 8. CYGNA Independent EQB/G. Bagchi 2/28/85 Assessment Program (Phase MEB/D. Terao 1 and 2)
- 9. CYGNA Independent EQB/G. Bagchi 2/28/85 Assessment Program MEB/D. Terao (Phase 3) EG8G Reviewers
- 10. CYGNA Independent EQB/G. Bagchi TBD Program (Phase 4) MEB/D. Terao CYGNA will issue 5/3/85 4
NRR Staff Scheduled Open Items Assigned Completion
- 11. Impact of MSLB on qualified EQB/H. Garg Waiting on Applicant's equipment outside et al. response to NRC RAI containment 12/21/84
- 12. FSAR Amds 50 thru 53 QUAB/J. Spraul Waiting on Applicant's changes to Operating QA response to NRC RAIs Program 1/7/85 and 1/24/85 Confirn:atory Items ,
TMI11.D.1Perfobance
- 1. MEB/G. Hammer Under staff review Testing of relief and Target 3/1/85 safety valves (awaiting applicant response)
- 2. TMI II.E.1.1 Test of ASB/P. Hearn Under staff review turbine driven AFW pump Target 3/1/85 to operate without ac power
- 3. TMI II.E.4.2 Capability EQB/R. Wright Waiting on Applicant's of containment purge valves response to NRC RAI to close in accident 11/9/84 conditions (EQB Evaluation of 10/24 has open items -
needApplicant'saction) , 4. Environmental qualification EQB/H. Garg Staff reviewing l of mechanical equipment Applicant's response l of 1/10/85; i Target 2/22/85
- 5. Natural circulation test RSB/S. Diab Staff reviewing Applicant's response in FSAR Amd. 54 Target 2/22/85 License Conditions l 1. Confonnance with R.G.1.97 LCSB/J. Joyce (Interimreport l
Revision 2, Generic Letter complete) Staff I 82-33 waiting on Applicant's Response; Target 6/85 (final report) l l 6
i NRR Staff Scheduled Open Items Assigned Completion
- 2. Procedures Generation PSRB/J.Clifford Target 3/85 Package (license condition established prior to OL)
B. Technical Specifications
- 1. Reactor System Branch RSB/S. Diab, B. Mann, Staff waiting on questions regarding C. Moon Applicant's response relationship between to NRC RAI 10/6/84 stated and measu' red process variables.(awaiting) applicant's response C. Board Notifications
- 1. Cross index of Board LBil/ unassigned 3-man wks.
Notifications to SER and SSER Sections
- 2. Issue forthcoming Board LB#1/S. Burwell Ongoing Notifications LB#1/A. Vietti i
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M 31125 . g' . 12 . Ye COMANCHE PEAK STEAM ELECTRIC STATION ' '" REGION IV ACTION NECESSARY FOR COMPLETION PRIOR TO RIEL LOAD (1985)_ Responsibility _ Feb March __ April May
- c' -
Deseff9tidm ;tua;tt'on of
- 3 1. complete Eva Preop. Test Results Res.Insp.(0ps) Licensee Dependent .
!?
! 2. Complete Operation Staff Inspection Res.Insp.(0ps) ,
- 3. Complete Inspection of Licensee Dependent io Maintenance Procedures Res.Insp.(0ps) ,
ts 4. Complete Open Inspection Items on Preop. Testing QA Res.Insp.(0ps) . e
- s
- 5. Close Out of Open Inspec- Res.Insp.(Ops / Con) '
tion Findings Region Based Insps. Ongoing Function - Performed as Required , u
'lR - " 6. Complete Pre OL Issuance Re-quirements of 2514 Program Licensee Dependent i (TestProcedureReview) Res.Insp.(Ops) .
s
" 7. Close Out of Remaining HEDs Res.Insp.(0ps) Licensee Dependent .
(HumanFactors)
- 8. Emergency Preparedness
' je Appraisal Significant Deft- Licensee Dependent RIV(Baird) ciency Ites close Out '
- ?
, 9. Radiation Protection and Radwaste Open Items RIV(Murray) Licensee Dependent .
(6) Close Out
- 10. Issue IE Procedure 94300 Letter Res.Insp.(0ps) ;
l I
o DEFINITION OF INTIMIDATION, HARASSMENT AND DISCRIMINATION Intimidation or Harassment: Incidents, statements or other actions that are reasonable likely to influence employees to refrain from performing safety-related work in accordance with requirements or identifying or reporting quality discrepancies or safety problems. In determining whether the incident, statement or actions was reasonably likely to influence employees, a number of factors will be considered including: 1)thenatureof the statement or action; 2) the intent of the person making the statement or taking the action; 3) the perception of the recipient of the statement or
~~ '
action; and 4) the positions of and relationship between the person making the statement or taking the action and the recipient. Discrimination: The showing of prejudice in the treatment of employees for performing safety-related work or reporting quality discrepancies or safety problems to their management or to the NRC. The showing of prejudice may include adverse actions such as discharge or other actions that relate to the terms, conditions, and privileges of employment. l l l I ll SN % ~~ 3 l d n'/a 2
1 i l l FORMAT FOR ANALYSIS OF INTIMIDATION AND DISCRIMINATION AT COMANCHE PEAK
- 1. Description of the intimidation / discrimination incident including:
a) Name, position, and duties of person subject to intimidation; b) Name, position and duties of person alleged to have intimidated; c) Names and positions of other porsons either subject to or involved in the incident; d) Area of work involved - welding, coatings, etc.; e) Date and place of incident; f) the nature of the statement or action; g) the intent of the person making the statement of taking the action; h) the perception of the recipient of the statement or action; ar.d
- 1) the positions of and relationship between the person making the statement or taking the action and the recipient.
- 3. The effect of the statement on the recipient including any specific failures to report safety problems and the basis for the conclusion that the effect occurred.
- 4. Reference to documents where incident is described such as Investigation Reports, deposition, hearing transcripts, etc. (title, dated, pages).
p C- fiage l'of 3 7 C; CPSES CONTENTION 5 DATA BASE INPUT SHEET ws ea t ITEM TO BE CONSIDERED DATA TO BE ENTERED ** g REFERENCE INFORMATION: k TRACKING NO: (For IE HQ Use) _______ YOUR NAME: (Last Name First) GROUP OR ORGANIZATION: 3'EIsr6_ E R_ _ _ _ _ _ T______________________________ SPECIFIC INFORMATION RELATED TO THE SCOPE AND DEPTH OF YOUR REVIEW: PRINCIPAL CONTENTION 5 AREA RELATED TO YOUR REVIEW:
- 7 SUBJECT OF YOUR REVIEW:
TOPICAL AREA:
- If not on list, enter area here: P Q6 g g g A rr o g t___ T y g T y g g._________
ACCIDENT PREVENTION / MITIGATION SYSTEM: gC5 -~ If not on list, enter system here: _ __ ___________________________ SPECIFIC COMP 0NENT OR ACTIVITY:
- I C._ _
If not on list, enter activity here: _______________________________ CPSES UNIT INCLUDED IN YOUR REVIEW: (Enter 1, 2 or B) J PRINCIPAL CONTRACTOR INVOLVED WITH YOUR REVIEW:
- TQ g.4 If not on list, enter contractor here: _______________________________
NATURE (TYPE) 0F YOUR REVIEW: R If not on list, enter nature here: [______________________________ SCOPE OF YOUR REVIEW: . APPR0X. EFFORT EXPENDED IN MANH0VRS, NOT INCL. 00C.: QQl6 REPRESENTATIVE TYPE OF ITEM CONSIDERED IN YOUR REVIEW:* If not on list, enter type here: QQ@de_rgsT_RESgtT,5_____________ l Size of sample observed / examined during your review: QQl2 Estimated total population avail. during your review: a q.g y Randomness of sample:(Enter R if random, B if biased) 3 If biased, enter basis here: Ag-L_LgG&yray_____________________ REFERENCE DOCUMENTS THAT DESCRIBE YOUR FINDINGS: pg _ y 9 5/ g 4-- 7 9 y f3 g g p _ g 4{ --]_ d -- 3 l_ _ _ _ _ _ (Separate.each document with a ";") _______________________________
- Enter Alpha Code From Appropriate List ,
**Please print using one character per underlined space. Please do not exceed allocated spaces.
/7/- 2 /
D0 J/lV L-!' Page 2 of 3
, CPSES CONTENTION 5 DATA SHEET SPECIFIC INFORMATION RELATED TO THE DEFICIENCIES IDENTIFIED OR EVALUATED DURING YOUR REVIEW ,
TOTAL NUMBER OF DEFICIENCIES YOU REVIEWED: dQQ1 DESCPIPTION OF EACH SPECIFIC DEFICIENCY YOU REVIEWED: Brief summary of deficiency: DR_ L W EL._IN DM-GO B _EM Va-b1D
- RE (Use a separate page 2 for each deficiency) 2 6 I R _ N 0 7 _ V E g r p 3 _E-D K E.fI _ I g p g O d g .
Ly_AcrcEED____________________ Specific location of the deficiency: bl&_____________________________ Date deficiency occurred: $3 gg O (Use YY-MM-DD Fonnat) Date NRC learned of deficiency: g o - Q 1 - J f (Use YY-MM-DD Format) Who first " discovered" deficiency:* f LUse N if NRC, L if Licensee, A if Alleger, 0 if Other) If other, enter source here: Number of known similar deficiencies: d363---~~-~~~-~----~~~--------- REGULATORY OR OTHER REQUIREMENT / COMMITMENT NOT MET: Applicable 10 CFR 50 Appendix B Criterion: Q g (Use arabic 01 thru 18, else NA if not applicable) Other requirement or commitment: _______________________________
--~-------------~~~~~--~~------
EFFECT ON ABILITY OF COMPONENT OR SYSTEM TO FUNCTION: Your opinion of the degree of seriousness of deficiency This specific deficiency considered alone:* 6-When considered with other known deficiencies:* G-Supporting information or basis: _______________________________ CORRECTIVE ACTIONS TAKEN OR PLANNED: V (Use Y if Yes, N if No, U if Unknown / Uncertain) Specific actions to correct deficiency: (Brief summary of specific corrective actions, [-~(([~(((((([~_(([~[~((((_-(([__~ if known.) _______________________________ Broad QA/QC actions: Tg sc_O _yC_ Qg.3[I.g.u/_ CG E.R_ PTS _ TO _ D6-(Actions to identify potential similar deficiencies Tg_Rgr y g_ rg_ O n g.R _ 3 E sr_ o g nc nst g_ due to QA/QC causes, and, to prevent recurrence S _ V ER E._ O i G.R L O d K E D _ _ _ _ _ _ _ _ _ _ _ _ _ _ of similar deficiencies in the future.) ______,_________________________ ADDITIONAL COMMENTS (If any, enter Y, and use page 3) N(UseYifYes,NifNo)
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.- C-5 DATA SHEET INSTRUCTIONS GENERAL: Each reviewer must complete a C-5 Data Sheet for each topical area reviewed, regardless of whether deficiencias were fcund by the review.
REFERENCE INFORMATION: YOUR NAME: Print last name, one character per underline, and then first and middle initials. GRCUP OR ORGANIZATION: (Insert code from the following list. If not listed, enter name of group or organization represented in performing your review.) CAT A Coatings C Document Control D Intimidation Panel I Mechanical Design il 01 Reports 0 RI NDE Van 1 RII Special Inspection 2 RIV Inspection / Enforcement 4 TRT Civil Structural / Mechanical S TRT Electrical E TRT Preop /Startup Test T TRT QA/QC Q SPECIFIC INFORMATION RELATED TO SCOPE: PRINCIPAL CONTENTION 5 AREA: From the following list, identify the Contention 5 area related to your review. Concrete Work A Steel B Expansion Joints C Welding D Materials Used E Working Conditions F Mortar Blocks G Fracture Toughness Testing H l Unit 2 Vessel Placen.ent I l Inspection and Testing J Labor Qualifications K QA Training and Organization L TOPICAL AREA: Enter the code for the topical area reviewed. If the review did not relate to a listed topical area, enter the "Other" code (OTH) and, on the next line, state the area reviewed. Containment (C0N) Design and As-Built Verification (DABV) Electrical (E) Environmental Protection (ENV) Fire Prevention and Protection (FPP) Geotechnical/ Foundation (GF) l Inservice Inspection (II) FotA %5'3'*
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+ , 2 Instrumentation (I)
Low Level Radioactive Waste Storage (LLRW) Mechanical Components (MC) Nondestructive Examination (NDE) Quality Assurance / Quality Control (QAQC) Reactor Coolant (RC) Safety-Related Piping (SRP) Structural Concrete (SC) Structural Steel and Supports (SSS) Welding (W) 10 CFR 21 (DN) 10 CFR 50.55(e) (CD) Other (Specify area reviewed) (OTH) ACCIDENT PREVENTION / MITIGATION SYSTEM: Enter the code for any of the following systems reviewed. Auxiliary Building HVAC System (ABHV) Auxiliary Feedwater System (AFWS) Boron Thermal Regeneration Subsystem (BTRS) Chemical and Volume Control System (CVCS) Chilled Water System (CHWS) Combustible Gas Control System (CGCS) Ccmponent Cooling Water System (CCWS) Containment Isolation System (CIS) Containment Spray System (CSS) Containment Ventilation Systems (CVS) Control Room Air-conditioning System (CRAS) Demineralized and Reactor Makeup Water System (DRMW) Diesel Generator Building Ventilation System (DGBW) Diesel Generator System (DGS) Fuel Building Ventilation System (FBVS) Instrumentation and Control System (I&CS) Liquid Waste Processing System (LWPS) e Main Steam, Reheat, and Steam Dump System (SRSD) Plant Gas System (PGS) Post Accident Sample System (PASS) Primary Plant Ventilation System (PPVS) Prccess Sampling System (PSS) Radiation Monitoring System (RMS) Reactor Coolant System (RCS) Residual Heal Removal System (RHR) Safeguards Building HVAC System (SBHV) Safety Injection System (SIS) Spent Fuel Pool Cooling and Cleanup System (SFPC) Steam Generator Feeddater System (SGFS) Uncontrolled Access Area Ventilation System (UAAV) Vents and Drains System (VDS) Other (Specify) (OTH)
e
, 3 SPECIFIC COMPONENT OR ACTIVITY: Where possible, identify a specific component from the following list or identify a specific activity:
Accumulators / Reservoirs (AR) Annunciators (A) Batteries / Chargers / Inverters (BCI) Blowers / Compressors (BLCO) Bolting (B) Circuit Breakers (CB) Communications Equipment (CE) Control Rods and Drives (CRD) Diesels D) Electrical Cables EC) Fuel Elements FE) Electrical Ger.erators (EG) Cranes and Other Handling Equipment (C0HE) Heat Exchangers (HX) Instrumentation and Controls (IC) Motors (H) Other Electrical (OE) Other liechanical (0M) Other Structural (0S) Penetrations /Eatches/Manways (PHM) Pipes / Fittings (PF) Pumps (P) < QA Program (QA) Radiation Protection /Radwaste (RPRW) Reactor Vessel (RV) Recombiners (R) Shock Suppressors and Supports (SSS) Steam Generator (SG) Transformers (TR) Turbines (TV) Valves (V) Valve Operators (V0) Ventilation Equipment (VE) Other Vessels (0V) Welds (W) Other (Specify) (OTH) CPSES UNIT: Enter 1, 2, or B (both) if the reactor unit (s) to which the review pertained is known. If unknown, enter B. PRINCIPAL CONTRACTOR: If the principal contractor (for the Contention 5 Area, Topical Area, Accident Prevention / Mitigation System, or Specific Component or Activity reviewed) is listed below, enter the appropriate code. If unlisted, print the contractor's name. If unknown, enter the code UNK. Texas Utilities Ger.erating Company (TUGC) Brown and Root (BR) Gibbs ano kill (GH) Westinghouse (W)
. 4 ,
NATURE OF REVIEW: Note whether your review Ws mainly of: Records R) Work in Progress P) Completed Work W Interviews (1l, A Combination (C) If none of the above, state what it was. APPR0XIMATE EFFORT EXPENDED: Estimate the length (man-hours) of the review, excluding documentation. REPRESENTATIVE TYPE OF ITEM CONSIDERED IN YOUR REVIEW:
. State what was sampled (pipe sup welds, bolts, precedures, etc.) ports, If inQAtherecords, semple list below, enter the code. If not listed, enter the name of the itern, Pipe Supports (PS)
QA Records (QAR) Welds (WELD) Bolts (BOLT) Procedures (PROC) Reinforcing Steel (REIN) Lab Reports (LAER)
. If you sampled more than one item, use a supplemental data sheet for all but the first. Staple supplemental data sheets to the main data sheet.
. Estimate the size of your sample and of the population from which it was selected.
. On the reverse side of the data sheet, state whether the population size refers to a component, a system, a builcing (or portion therecf), an activity, the work of a given contractor, or any other major aspect of the plant. Also, state whether you believe it to be the only such population in the plant. (For example, you might have examined 20 of 500 pipe support welds in a given piping systen and know whether similar pipe support welds exist in other piping systems.)
. If the sanple was biased, state what caused the bias (e.g., allegation or previous inspection findings).
REFERENCE DOCUMENTS: List all docurents that describe your review or its findings. Use the following types of format:
"IR 445/84-01" "MEMG y_ y-m m-d d" "LTR y_ y3 m-d f_
c 1
'.' 5
, SPECIFIC It!F04ttt. TION RELATED TO CEFICIENCIES:
If no deficiencies W re identified in a sanple, do not complete page 2 for that sample. _00_ corplete a page 2 for each type of deficiency fo9nd in each sample. TCTAL l!Uf48ER OF DEFICIENCIES REVIEWED: Enter the number of this type of deficiency found in the sample. DESCRIPTION OF EACH SPECIFIC DEFICIENCY:
. Describe the major aspects of the deficiency within the allotted space. Abbreviate and do not use a complete sentence. For example:
~
FZR level indication invalid; repajr not verified,; test improperly altered, er ' Wrong CILRT std used; 3 elu penetrations isolated during test. - t
. State the area of the plant, building, rocm, and system in which the deficiency occurred, if possible. If the deficiency cannot be related to a loc.ation (e.g., a QA Program deficiency), enter tiA.
. E.1ter the year, month, cod day, if known, that the deficiency cccurred. (flot when it was discovered.)
. Specify when NRC becamE aware of the deficiency,
. State whether the deficiency was discovered by:
NP.C N) Licensee L1 Alleger A) ; Other 0) If "Other," state who (company or person) discovered it, if known.
. Estimate the number of similar deficiencies known (or strongly believed) to have eccurred cutside your sampled population.
REGULATORY OR OTHER REQUJREt!EN?iC0l4MITiiENT:
. If the deficiency was caused by a specific QA/QC weakness, specify the related section(s) (below) of Part 50, Appendix B. (Use Arabic, not Roman, numerals to identify the eighteen QA criteria, as shown).
01 Organization 02 Quality Assurance Program 03 Cesign Control 04 Procurement Document Control 05 Instructions, Procedures, and Crawings 06 Document Control
. . . _ _ _ . = _ . ._ _ _ .
1 e
~
6 07 Control of Purchased Material, Equipment, and services 08 Identification and Control of Materials, Parts, and Components 09 Control of Special Processes . 10 Inspectiun 11 Test Control 12 Control of Measuring and Test Equipment 13 Handling, Storing, and Shipping 14 Inspection, Test, and Operating Status 15 Nonconforming Materials, Parts, or Components 16 Corrective Action 17 Quality Assurance Records 18 Audits
. Specify all other criteria (e.g., regulatory requirement, design purpose, code, standard, and design document) used to establish the above deficiency.
j EFFECT ON ABILITY OF COMP 0NENT OR SYSTEM TO FUNCTION: Characterize the seriousness of this deficiency, alone, as likely to have little (L), uncertain (V), or great (G) effect on the ability of the component or system to perform its intended function for its design lifetime. Then characterize its likely effect (L U, G) when i occurring in conjunction with other known deficiencies. If the effect I would be increased significantly by other known deficiencies, identify
- those deficiencies under " Supporting information or basis."
) i 1 i
TECHNICAL REVIEW TEAM BRIEFING CUALITY ASSURANCE CONCERNS JANUARY 17, 1985 INTRODUCTION ROLE OF THE TRT TRT REVIEW AREAS ELECTRICAL /INSTRUENTATION CIVIL /ECHANICAL QA/0C . C0ATINGS TEST PROGRAPS STATUS OF TRT REVIEW EFFORT DISCUSSION OF QA/0C CONCERNS TUGC0 C0ftENTS CONCLUSION $~ IO foin as-sta n'/ss [
~_ _ _ . _ . _ - - -
i TECHNICAL REVIEW TEAM (TRT) . Project Director V.S. Noonan, NRR Assistant R. Wessman Staff A. Vietti R.C. Tang J. Zudans I I I I 'T i . I Electrical / Civil / Mechanical QA/QC Leader Coatings Leader Test Programs Instrumentation Leader Leader Leader J. Calvo, NRR L. Shao, RES H. Livermore, R-III C. McCracken, NRR R. Keimig, R-I E 3 A y y
' - - - L.- - --/ N ._. .g, _
i
- Technical Issues -
Technical Issues - Programmatic and - Technical Issues - Technical Issues Generic technical
- Allegations - Allegations issues and - Allegations - Allegations allegations
- QA/QC Related - QA/QC Related - QA/QC Related - QA/QC Related to E, I&C to Civil / Mech. - Integrate QA/QC to Coatings to Test Programs from other groups
- Interface with other groups on QA/QC
-- m , a
p.
~
~
TYPICAL TRT INVESTIGATIVE ACTIONS 1 er 5 APPLICANT RECORDS REVIEW INTERVIEWS WITH ALLEGERS , REVIEW OF AFFIDAVITS AND DOCUENTS PROVIDED BY ALLEGERS, INTERVIEWS WITH APPLICANT AND B&R STAFF REVIEW 0F DEPOSITIONS REVIEW OF 0FFICE OF INVESTIGATIONS REPORTS ,
~~
- REVIEW OF REGIONAL INSPECTION RECORDS
~
INSPECTION OF PLANT SYSTEMS AND C0FFONENTS
~* -
AS-EUILT VERIFICATION PROGRAM TEEDBACKINTERVIEWSWITHALLEGERS ASSESSENT OF SAFETY SIGNIFICANCE E' F
/
h
,n - e -,--- , , - ., ,
PROGRAM PLAN INCLUDE DETAILED PLANS AND SCHEDULES FOR ADDPESSING QA/0C ISSUES. ADDRESS ROOT CAUSE AND GENERIC IlPLICATIONS, ADDRESS COLLECTIVE SIGNIFICANCE OF DEFICIENCIES ON A PLANT THAT IS NEARLY C0FPLETE, PROPOSE ACTIONS TO PREVENT RECURRENCE. CONSIDER USE OF MANAGEMENT PERSONNEL WITH FRESH PERSPECTIVE CONSIDER USE OF INDEPENDENT CONSULTANT TO PROVIDE OVERSIGHT .
- = - - _ - _ -- - . _ _ _ _ . - - - . - _ -
i 4 O. SIN %RY OF TRT FINDINGS LIMITED TRT REVIEW INDICATES: 1 EXAMPLES INDICATING CPSES NOT ALWAYS CONSTRUCTED IN ACCORDANCE WITH DESIGN REQUIREENTS. FAILUPE OF QC PROGPAM TO DETECT CONSTRUCTION ERRORS. FAILURE OF MANAGE E NT TO RECOGNIZE AND CORRECT THESE BASIC DEFICIENCIES. SIGNIFICANT AREAS: MANAGEENT C0ltITENT AS-BUILT DEFICIENCIES QC INSPECTION QC PERSONNEL QUALIFICATION AND TRAINING ONSITE FABRICATION DOCUENT CONTROL 9 4
0A/0C OVERVIEW FIVE ONSITE SESSIONS OF TM) WEEKS EACH PERSONNEL - AT PEAK ACTIVITY 20 CONSULTANTS AND FOUR NRC INDIVIDUALS (ALL ENGINEERS), OVER 300 YEARS EXKRIENCE IN GENERAL ENGINEERING (NUCLEAR AND NON-NUCLEAR) INCLUDING QA/0C 124 ALLEGATIONS, ISSUES, CONCERNS CATEGORIES: DESIGN PP0 CESS DOCLENT C0hTROL RECORDS TRAINING /0UALIFICATION . REPAIR, REWORK, MAINTENANCE ONSITE FABRICATION HOUSEKEEPING NCRs MATERIALS QC INSPECTION 0A SC0R EARLY ASSESSENTS IDENTIFIED SYMPTOMATIC CA/QC PROBLEMS NECESSITATING AN ADDITIONAL CATEGORY AS BUILT i
- 1. QUALITY ASSUPANCE PROGRAM NO PERIODIC MANAGEENT ASSESSENT OF OVERALL EFFECTIVENESS OF THE 0A PROGRNi AUDIT FUNCTION - UNDER STAFFED REPETITIVE NCRs WERE ISSUED INDICATING A NEED TO RETPAIN CONSTRUCTION PERSONNEL EXAMPLES OF INCOMPLETE AND INADEQUATE WORKMANSHIP AND INEFFECTIVE OC INSPECTION OC INSPECTORS WEPE IN POSITIONS OF REVIEWING THEIR OWN ,
WORK RECOPDS 10 CFR 50.55(E) REPORTING SYSTEM DEFICIENCIES EXIT INTERVIEWS FOR DEPARTING EMPLOYEES WERE INADEQUATELY STRUCTURED AND INEFFECTIVE CORRECTIVE ACTION SYSTEM WAS POORLY STRUCTURED Af0 IflEFFECTIVE
2, OC INSPECTION FUEL POOL LINER TRAVELER IRREGULARITIES: PREENTERING " SAT" INSPECTION RESULTS CHANGING INSPECTION DATES QUESTIONABLE INS KCTOR SIGNATURES CHANGED PROCEDURE NUMBER FOR ANOTHER INSPECTOR CHANGED INS KCTION DATE FOR ANOTHER INSPECTOR , MISSING OC SIGN 0FFS FOR STEP 1 MISSING SIGNATURES INADEQUATE DESCRIPTION OF RESOLUTION OF PIPE kHIP PESTRAINT WELD DEFECTS DEFICIENCIES IN LETTERS OF SEPT, 18 AND NOV. 29,1984 , s t
6 0
- 3. T-SHIRT INCIDENT
- 4. INSPECTIONS OF AS-BUILT PIPE SUPPORTS a ELECTRICAL SUPPORTS WCHANICAL FORTY-Th0 PIK SUPPORTS ERE INSKCTED BY TRT, FORTY-SIX DEFICIENCIES WERE IDENTIFIED ON TWENTY-SIX OF THE PIK SUPPORTS, TYPES OF PIPE SUPPORT DEFICIENCIES INVOLVED:
- PROCEDURE INADEQUACY
- HARDWARE LOOSE OR MISSING
- AS-BUILT DPAWING DID NOT VATCH INSTALLATION
- COMPONENT IDENTIFICATION
- WELDS
- OC RECORDS .
- VATERIAL IDENTIFICATION i
- SIX P!PE SUPPORT DEFICIENCIES HAD FREQUENT OCCUPRENCE, ELECTRICAL FIVE ELECTRICAL SUPPORTS E RE INS KCTED BY TRT, NINE DEFICIENCIES EK IDENTIFIED ON THREE OF THE ELECTRICAL SUPPORTS, TY KS,0F ELECTRICAL SUPPORT DEFICIENCIES INVOLVED:
- HARDWARE
- CONFIGURATION
- ELDS NOTE ALL PIK SUPPORTS AND ELECTRICAL RACEWAY SUPPORTS INS KCTED BY TRT HAD BEEN PREVIOUSLY ACCEPTED BY SITE OC, 1
k Table 1
! Pipe Supports -
Unit 1 Supports inspected by TRT As-Built group
- 42 l Class 1 4 i Class 2 14 Class 3 24 Hangers with nonconformances 26
- Total deficiencies 46 Procedure adequacy 5 Hardware-related 16 As-Built 8 Component identification 2 Weld-related 10
- QC record 1
! Material IDERTIFICATION 4 i Different types of deficiencies 25
- Welds inspected without paint by TRT 305
, Welds inspected with paint by TRT 89 Welds needing repair 10 Supports involving weld repair 6 All 42 pipe supports inspected by TRT had been previously final QC accepted. Wenczeldec- 1
i Table 1 (cont'd) i . Pipe Supports Unit _ 1 _ _ _ i l Quantity l Bldg System inspected
- Containment Safety injection (SI) 1
,! Containment Reactor Coolant (RC) 6 Containment Residual Heat Removal (RHR) 2 Fuel Handling Component Cooling (CC) 11 Safeguards Residual Heat Removal (RHR) 1 Safeguards Containment Spray (CT) 8 l l Safeguards Demineralized Water (DD) 1 Safeguards Auxilary Feedwater ( AF) 8 ! Auxiliary Chemical Volume & Control (CS) 1 l Safeguards Main Steam (MS) 2 !. Safeguards Chilled Water (CH) 1 l (small bore) Wenczeldec--2
i . Table 2 Pipe Supports Unit _ 1 _ Types of Deficiencies
- _
Deficiency Hanger No. # Deficiencies Category 1 1 No locking device on threaded f asteners RC-1-901-702-C82S 2 Hardware CS-1-085-003-A42K l 2 Min. edge distance (on base plate) violated CC-X-039-006-F43R 1 Hardware
! 3 Baseplate hole-location dimensions out of CC-X-039-007-F43R 4 As-Built tolerance CC-1-126-010-F33R CC-1-126-011-F33R CC-1-126-012-F33R 4 Spherical bearing / washer gap excessive CC-1-12b-015-F43R 4 Hardware
- R0-1-052-016-041K l RC-1-052-020-C41K
! MS-1-416-001-S33R 5 Spherical bearing contamination SI-1-090-006-C41K 2 Hardware ! MS-1-416-002-S33R 6 Snubber adapter plate-insufficient thread MS-1-416-002-S33R 3 Procedure j engagement SI-1-090-006-041K i
- I CT-1-013-012-S32K l 7 Insufficient threaded eng'mt, threaded rod RC-1-901-702-082S 1 Hardware l~ (sight holes) l'
- All 42 pipe supports inspected by TRT had been previously final QC accepted. wenczeldec-0 l
Table 2 (cont'd) Pipe Supports Unit 1 - Categories of Problerns* Problem Category Hanger # # of Problems Problem Type 8 Snubber / Strut load pin locking device AF-1-001-014-S33R 1 Hardware broken or missing 9 Load side of pipe clamp halves not AF-1-001-001-S33R 2 Procedure parallel . AF-1-001-014-S33R l 10 Pipe clearances w/suppoit out of CC-1-126-013-F33R 2 Hardware tolerance AF-1-001-702-S33R 11 Pipe clamp locknut loose AF-1-035-011-S33R 1 Hardware 12 Snubber / sway strut misalignment CC-1-126-014-F43R 2 Hardware RC-1-052-020-C41R 13 Snubber cold set dimension does CS-1-085-003-A42K 1 As-Built not match drawing 14 Snubber orientation does not match CT-1-005-004-S22K 2 As-Built drawing CT-1-013-010-S22K 15 Component type /model # installed Sl-1-090-006-C41K 2 Component ID does not match drawing RC-1-052-020-C41R l 16 NO IDENTIFICATION FOR SUPPORT MATERIALS, CT-1-013-014-S32R 4 Matl. ID PARTS, AND COMPONENTS CC-1-126-012-F33R CC-X-039-005-F43R AF-1-035-011-S33R l l
- All 42 pipe supports inspected by TRT had been previously final QC accepted.
j wenczeldec- 4
Table 2 (cont'd) Pipe Supports Unit _ 1 Types of Deficiencies
- Deficiency _ Hanger No. # Deficiencies Category 17 BRP column line dimension does not Support not affected 1 As-Built match BRHL dimension 18 Weld porosity excessive AF-1-001-001-S33R 1 Weld-related 19 Weld undercut excessive AF-1-001-702-S33R 1 Weld-related 20 Weld length undersized AF-1-001-001-S33R 1 Weld-related 21 Weld leg or effective throat AF-1-001-001-S33R 3 Weld-related undersized RH-1-006-012-C42R CC-X-039-007-F43R 22 Weld called out on drawing does not CC-1-126-013-F33R 1 Weld-related exist in field 23 Welds added in field are not reflected AF-1-001-702-S33R 1 Weld-related on drawing numerous welds 24 Excessive grinding resulting in min. AF-1-037-002-S33R 2 Weld-related thickness violations (weld clean-up) CT-1-013-014-S32R 25 No QC buy-off on weld data card CC-1-126-013-F33R 1 QC Record 46 Total Problems identified by TRT
\ l
- All 42 pipe supports inspected by TRT had been previously final QC accepted.
werczcldec-5
Table 3 Summary _of Field __R_eview of Pipe Support Welds l l l ! Total number of pipe supports inspected
- 42 l Number of supports requiring weld repair 6 i i
Percent of total inspected requiring repair 14 % j Total welds inspected on 42 supports 394
- Number of inspected welds which require repair 10
- Number of welds repaired (as of Oct. '84) on the 6 9 l
defective supports I Welds requiring repair, percent of total welds inspected 2.5% i All 42 pipe supports inspected by TRT had been previously final QC accepted wenczeldec 6
; Table 4 l Summary of Additional Support inspections Area: Room 77N, Elevation 810'-6" Unit #1, Safeguards Building i
) No. of Supports No. of Supports Deficiency inspected Deficient % Deficient Excessive 92 5 5.4 % Spherical Bearing Clearance Load Pin Locking 92 14 15.2 % l Device Missing Pipe Clamp Halves 40 9 22.5 % Not Parallel Snubber Adapter 19
- 13 To Be l Plate Bolts With Determined l
Less Than Full i Thread Engagement i
- Bolts had less than full thread engagement.
wencze!Jec-7 O
~
i Table 5 Summary _ of Additional Suppor[t Inspections _ Area: Cable Spread Room 133, Elevation 807'-0" Unit #1, Auxiliary Building I i Deficiency Bolts Inspected # Deficient % Deficient i j Hilti Kwik Bolt 24 3 12.5 % Does Not Meet . Minimum Embedment**
** Taking into account the " allowed" slippage of the bolt for a distance of one nat thickness due to the torquing and the minimum specified embedment, the above Hilti bolts violated the "ef fective" embedmont requirements.
l (Ref. " Installation of 'Hilti' Drilled-in Bolts" 35-1195-CEl-20,
- Rev. 3, Para. 3.1.4.1) 1 i
wenczeldec--8 l _ _ _
l .
! Table 6 .
Summary __ of Electrical Support inspection - Unit #1 Support welds inspected 59 Supports inspected by TRT As-Built Group 5 Supports with problems (3/5 = 60%) 3 Supports accepted (2/5 = 40%) 2 Types of Deficiencies __ Hardware-related, other than welding 6 l Unauthorized configuration change 1 l Weld-related types of problems (categories) 2 I l Welds requiring rework 41 l Welds made in field but not recorded on drawing 80 j Beam stiffeners added but not recorded on drawing 40 l Building / Area Supports . Cable Spread Room CTH 12646 i C 130-21-250-3 i C 120-21-194-3 Auxiliary Building CTH 6742 l
- Containment CTH 5824 wenczeldec-9
Table 7 l
~
Summary - of General Types of Deficiencies i j (pipe supports and/or electrical supports) j
- Undersize welds
- Weld undercut and porosity
- Weld insufficient fill and surf ace a Grinding of base metal material
- Excess welds not shown on drawing
- Absence of QC weld buy-offs
= insufficient thread engagement
- Absence of locking devices
- Minimum edge distance violation
- Excessive gap in spherical bearing interf aces - strut and snubber
- Shock arrester model numbers do not match drawings wenczeldec- 10 i
i
l Table 7 (cont'd) - l Summary of General Types of Deficiencies l (pipe supports and/or electrical supports) l i e Component support bolt holes out of location
- Spherical bearing contamination
- Thread engagement not verified .
l
- Pipe clamp halves not parallel l = Pipe clearance with supports out of tolerance
- Loose pipe clamp locknuts l
I
- Snubber / sway strut misalignment
- Snubber cold set out of tolerance
- Snubber orientation not on drawing j
- Electrical hanger welds not on drawing
!
- Beam stiffeners not shown on drawing I
- Material IDENTIFICATION LkCKING wenczeldec- 1 1
_ _ _ _ _ _ _ _ _ _ _ --- - - - , - ,+ e . - - - - < . -- - - -- e
TABLE 8 TRT CONCLUSIONS ON AS-BUILT EFFORT
- 1) QC INSECTIONS AE IEFFECTIVE
- 2) CRAFT CONSTRUCTION IS FAULTY
- 3) HARDWAE IS NOT KR AS-BUILT DRAWINGS
- 4) HARDWAE POTENTIALLY NOT REPESENTED CORECTLY IN TE FINAL STESS ANALYSIS
Figure 1. Hardware Examples L oad 90't. Onc Nut On'y , No Lock Nut # . 1i 4
.___., Q Lead Pi-e::', Spring Wit" Ccite
,. - g",, ,' Pm LorL + r
,- v
~-
, Threct Dev?ce
.7 !#. S g-*
M $ Hole l$l ,A a 'e!
~
s Sway Stru: C
-k $
0 I s i - Snubbe- J1 7 n , ,e _ c ;.; l Adopter Picte %J h_rge p;pe Ocmp Topoed Hofe / 4 ) Extension Kt s Ni i _ _H ', Plote [Og / -
/f
. p,u ,g Not Tcpped' F;pe i Cla m p One Not 0-'". k4 /
4 Ne Lock Nt' 1 Spheico'
' Bea-Ing u \ 'c _ 1 m (g l g4 f !M n \\\\\\n\ ni u, I Snubber i Extension Kit i
= :: =,
6 F"' ( 7 e '[ t [ "
5, DOCLK NT CONTR0_L POTENTIAL EXISTS FOR THE DCC SATELLITES T0 ISSUE DEFICIEhT DOClMNT PACKAGES TO CPAFT PERSONNEL DRAWING CONTROL INADECCATE PRIOR TO JULY 1984 RECURRING DEFICIENCIES IDEATIFIED BY INTERNAL AND EXTERNAL AUDITS BEMEN SEPTDEER 1981 TO AUGUST 1983 FIELD DISTRIBUTION CHANGED FROM FILE CUST0DIANS TO SATELLITES , RECURRING DEFICIENCIES C0hTINUED FROM AUGUST 1983 TO APRIL 1984 TREND REVERSED WHEN TOP MANAGEE NT PARTICIPATED IN COPRECTIVE ACTION PROCESS PROCEDURES GOVEPNING 10 CFR 50.55(E) DEFICIENCY REPORTING INADEQUATE CONSIDERATION OF REPORTING CYGNA AUDIT FINDINGS TO NRC DCC CONTROL COPY STNPS NOT ADEQUATELY PROCEDURALIZED
- 6. TRAINING /0UALIFICATION TkENTY PERCENT OF THE TRAINING RECORDS REVIEWED CONTAINED N0 VERIFICATION OF EDUCATION OR WORK EXPERIENCE PESULTS OF LEVEL I CERTIFICATION TESTS USED FOR SOE LEVEL 11 CERTIFICATIONS AFTER FAILING A CERTIFICATION TEST, A CANDIDATE COULD TAKE THE IDENTICAL TEST AGAIN, CERTIFICATIONS NOT ALWAYS SIGNED OR DATED WHITE-OlfT USED ON CERTIFICATION TESTS SEVEN INSPECTORS HAD QUESTIONABLE QUALIFICATIONS NO LIMIT CR CONTROL ON THE NUFBER OF TIES AN EX/F,INATION COULD BE TAKEN N0 GUIDELINES FOR THE USE OF WAIVERS FOR ON-THE-JOB TRAINING RECERTIFICATION WAS ACCOMPLISHED BY A SIFPLE "YES" FROM A ,
SUPERVISOR N0 FORPAL ORIENTATION TPAINING FOR DCC PERSONNEL PRIOR TO AUGUST 1983 RESPONSIBILITY FOR ADMINISTRATION OF THE NON-ASE TPA!NING PROGRAM NOT CLEARLY ASSIGNED TO A SINGLE INDIVIDUAL OR GROUP NON-ASE PERSONNEL CAPABILITIES LOOSELY DEFINED BY LEVELS (I,II,Ill) EXEPPTION PROVISION IN ANSI N45,2,6, WHICH ALLOWED SUBSTITUTION OF PREVIOUS EXPERIENCE OR DEM)NSTPATED CAPABILITY, WAS THE NOPFAL PEIH0D FOR OUALIFYING INSPECTION PERSONNEL PATHER THAN THE EXCEPTION ADDITIONAL PROBLEMS IN NON-AS E CERTIFICATION TESTING NO REQUIREENT FOR ADDITIONAL TRAINif6 BETWEEN A FAILED TEST AND THE RETEST NO TIE LIMITATION BETWEEN A FAILED TEST AND A RETEST l TWO DIFFERENT SCORING ETH00S TO GRADE TESTS N0 GUIDELINES ON HOW A TEST GUEST 10N SHOULD BE DIS 00AllFIED NO PROGRAM FOR PERIODICALLY ESTABLISHING NEW TESTS EXCEPT WHEN PROCEDURES CHANGE NO DETAILS ON HOW THE ADMINISTRATION OF TESTS SHOULD BE M)NITORED
- 7. VALVE INSTALLATION
- _ TEE WAS A LACK 0F C0kTROL TO PREVENT THE LOSS, DAMAGE, AND INTERCHANGE OF PARTS WHEN VALVES WEE i D_lSASSERLED PRIOR TO 1ELDING THE VALVE BODY IN THE LINE (PIPING INSTAlt.ATION) l l
)
l l l l
/
- 8. ON SITE FABRICATION (IRON FAB SHOP)
SCRAP AND SALVAGE IN LAYDOWN YARD WAS NOT IDENTIFIED AND DID NOT HAVE RESTRICTED ACCESS INDETERMINATE BULK MATERIALS MINGLED WITH CONTROLLED SAFETY AND NON-SAFETY MATERIALS IN LAYDOWN YARD f%TERIAL REQUISITIONS DID NOT COPFLY WITH THE APPLICABLE PROCEDURES SHOP FOREEN NOT FAMILIAR WITH TEE PROCEDURES THAT CONTROLLED THE WORK UNDER THEIR RESPONSIBILITIES , FAFRICATION AND INSTALLATION PROCEDURES DID t0T INCLUDE INF0fdAT10N TO ENSURE THAT B a R FABRICATED THREADS CONFORE D TO DESIGN SPECFICIATIONS OR TO AN APPLICABLE STANDAPD QC SITE SURVEILLANCES OF MATERIAL STORAGE NOT DOCUENTED WORK IN FAB SHOP PERF0PtED IN RESPONSE TO EPIDS AND SKETCHES INSTEAD OF HANGER PACKAGES, TRAVELERS AND CONTROLLED DRAWINGS
O
- 9. HOUSEKEEPING AND SYSTEM _ CLEANLINESS SWIPE TESTS ON REACTOR VESSEL PROCEDURE FP-55-08 REQUIRES WO SWIPE TESTS ON !
THE REACTOR VESSEL THE TRT QUESTIONS THE ADEQUACY OF ONLY TWO TESTS TO ASSURE THE CLEANLINESS OF THE VESSEL 4 PROTECTIVE COVERINGS l WELDING ACTIVITY ADJACENT TO SNUBBERS NOT - COVERED WITH A PROTECTIVE DEVICE POTENTIAL VIOLATION OF PROCEDURE CP-CPM-14.1
10, NONCONFORMANCE EPORTS (NCRs) USE OF APPROXIMATELY 40 DIFFERENT FORMS FOR ECORDING DEFICIENCIES INADEQUATE INSTRUCTIONS FOR HANDLING VOIDED NCRs USE OF NCRs AS A TPACKING DOCUENT NOT DEFINED IN PROCEDUES INCCNSISTENCY IN REPORTING OF NONCONFORMANCES CONTPDL OF OBSOLETE NCR F0 PTS TWOTUGC0NCRFORMSINUSEBYCONSTRUCTION N0 IDENTIFICATION OF CAUSE OF NONCONFORPANCE OR STEPS TO PPSENT ECURPENCE NO EVIDENCE OF QUALITY ASSURANCE PANAGEENT IPNOLVEMENT
v
~
- 11. MATERIALS PIPE SUPPORT MATERIAL TRACEABILITY FAILURE PRIOR TO OCTOBER 1981 PROBLEM IDENTIFIED IN ASE CODE SURVEY FAILED TO REPORT 0A BREAKDOWN AS PER 10 CFR 50,55(E)
t ///L./(5~ Olla-F1~ cmccR4cc& < > Def{ciencydescription C6A-77%)d5 ZDJiff dF cg>>7)ha m p,J7-1 Reference document e2rA12WJ SSEAN / ryfle) 7 ~~ foZ AblESA+^1MJ P601 Affir-i2t>JAL. strd^ A tt&CA472.JS - Number of similar deficiencies Sample size Samp1e bias ScsPE of Jah/EsriGMfkod mach sxsApst 77tAJ AufcM7bJS Effect upon ability of component or system to perform function , s Area of work: Concrete work Mortar blocks Steel Fracture toughness testing Expansion joints U-2 vessel placement - Welding Inspection and testing / Materials used / Labor qualifications / Working conditions QA training and organization / Specify other areas Responsible contractor c Estimate month and year deficiency occurred i Describe QA/QC related cause(s) Describe corrective action (s) Spccific 9t?2 A LL E L A-mE,dGMF-A}r R&d.tEdY Ev' M04 Nhfr
-7'D AB-r+1WE C6An%)d 5 f A'-d>s1 4 /--lJ 7' Lbi&L 9/108A6Lf A8 A-f/AWrk? < 1}h&Afz')La; t~st2EcTWE A c n M J a Jit.L At s 7- 86 BOR 06A u>s15 .
Broad (QA/QC related). Su8f7AJTWE dA-lQC AABAK$dLdn) Jac4 rw>tr- A f A Jc d M-ft s AfftfAr\CCS Do Al~6 7 ^ E x / E 7~ 7W-A- 7~~ BB12d2Ed .2 0 No AY SG $6 N~ A//'&th;0 aA-Thd6S ACE A C&Go"l'M<&%f. SSgg.) /AcKPir TEJr PRocitAm - me si .sva.muriATr#
-2 DsA a.vAi.ip;cArna rstr;ac. - sw MMEaupre.
~3 CoffTi&U T}lACEA6lLiry- C AslY AJJdltE TRA CEA-8itity 6F Att ct'An%':S
~ Y OAMS PAccEDUCES- IdADE LUME, iupicicAn/G 6/; vad. vat.iFsf/ R/.thdl
- 5 MSPECTM L AcA'J ~ EJG ME6C'od C PiJPJJrtilall 3sm&T1hsts 1%ppsydg
-4 coknucs exempr i.s c - 80 AutaMmspssp n ckrcx Aa ,wav>een
- 7 TRA-iwme s da%ificenM- TOApbod>VTE Ta sAriJFy Au REo.*iREMNTS f*0/A ES ~ 3 ' A '
Jh-2/ . n'/m >
c ! .- Deficiency description [dAri M S 84CtcP{1~ 7517~ PA6CAAnth7'P) Reference document A&6 -/F,< sf ?-d i > 2- / 3 ? , 44 , 9 9,. 5, 9 " cc .c r d rnsus.r USK- / l 112 M-/.T rourw;rn onri45 peciciexa s ' itAf/n A&icM7~ Number of similar deficiencies Sample size ' minnre Erf ^ Sample bias - -
~
Effect upon ability of component or system to perform function . Area of work: Concrete work Mortar blocks Steel Fracture toughnesis testing Expansion joints U-2 vessel placement - Welding Inspection and testing l
' Materials used Labor qualifications Working conditions QA training and organization Specify other areas i Responsible contractor Estimate month and year deficiency occurred Describe QA/QC related cause(s)
Describe corrective action (s) Specific Broad (QA/QC related). b
t 4
?h( Draft 2 Itl9f Ek
- 1. Allegation Group: Protective Coatings 1: Backfit Test Program
- 2. Allegation Number: Parts of AQ0-18, 19, 20, AQO-21, 37, 46, 47, 54, 55, 56.
- 3. Characterization: It is alleged that:
Visual defects were not identified during backfit inspections. (AQ0-18) Backfit inspection procedures are vague. (AQ0-19) Adhesion testing of the protective coatings was not performed properly. . (AQ0-20) Adhesion test data were not corrected for calibration error. (AQ0-21) Area stated to have satisfactory documentation, in fact, had primer coatings exceeding the allowed thickness. (AQ0-37a) The maps for the Backfit Program.were incorrect. (AQ0-37b) Documentation for the Backfit Program was forged and falsified. (AQ0-37c)
. QC Inspectors completed Inspection Reports (IR.) without performing the inspections. (AQ0-37d) s Unacceptable substrate conditions were observed through Tooke Gauge tests.
(AQ0-4$) G
1 1 o Adhesion test dollies used during the Backfit Program were observed to haverugtadheringtothepaint(underside)atthecompletionofthetest. (AQO-46/) 25 adhesion tests were performed in violation of written instructions. . (AQ0-47) 1 During the Backfit Program, only the first unsatisfactory reading was recorded, adversely affecting the trend analysis. (AQ0-54) Areas identified during the Backfit Program requiring coatings removal did not have the coatings removed. (AQ0-55) Original documentation for the Backfit Program was destroyed by QC manage-ment. (AQ0-56) ,.
/1w&CAn'l%U 4 ~. Assessment of S h y 2:mm1 m am:
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In order to ass ss the i idividual allege ions characterized above, the TRT reviewed the b ckground and scope of t e Backfit Test Program and res 1T4 irdependently evaluated the program t staas present'ed below. The TR assessment of the indivi' dual allegati ns follows in Section 4.d bel .
- a. Backfit, Test Progrz.m Backoround and Scope l IfBackgrond: In 198:., Region IV of the NRC conc ucted an insp ction of pfotective oatings at Comanche Pea .. As a. result of this inspection
( Inspectio Report 81-1 5), a Notice of Violation was issued reg rding the 1 ailure of TUEC to foll aw quality a$surance progran procedures for the nspectio of protectiv a coatings. Specifically, From late S e.tember 1979 hrough ctober 1981, d cument'ation for protective oatings nspections was n t mai tained or was in omplete. In response to th's Not'ce of Violation,
)
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1 9
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Theallegerindi ctly ; relates this all tio to forging an r f alsification fBTPdohuments(alle d by another perso which i ; i ssessed in llegation #37(c) abo .
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lly letter dated August 24, 19 , the TRT dire : tor orwarded the . Pranscr ed NRC interviiew w' h this alleger t:0 Region IV OI fo their r i .
- 5. Conclusions and Staff Position
- a. Specific Allegations Concerning BTP TRT conclusions concerning specific allegations related directly or indirectly to the coatings Backfit Test Program (BTP) are as follows:
(1) Allegations 18,20, 37(a), 46(b), 47 were substantiated; however, for-the reasons stated in the corresponding assessments presented in the section above, TRT does not consider them to be a significant technical
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concern in regard to the BTP. Allegation 21 was also substantiated and as discussed in detail in Section 4(b)above,TRTfindsthatcorrectingadhesiontestresultsfor/$cometer - calibration error has only a small effect on liner and concrete test failure rates, but could significantly change the test failure rate for miscellaneous steel. For the liner plate, the failure rate only changed from TUEC's uncorrected 2.3% (20/869) to TRT's corrected rate of 4.3% (36/834) or to TUEC's corrected rate of 5.9% (51/869). For the concrete, the change was from a zero% uncorrected failure rate to TRT's corrected
' 6.8% (8/116) rate or to TUEC's corrected rate of 3.1% (65/2128). For l miscellaneous steel, however, the-test failures rate could change from I less than 1% (26/4714) uncorrected to as much as 19% corrected based on a limited sample analysis by TRT. l
{ ! 1
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I 1 l
(2) Allegations 37(c), 54 and 55 were partially substantiated . On ;
~
allegation 37(c) TRT could not draw a conclusion as to forging or falsification of documents but did find two instances of technically inconsistent inspection documents which could involve only a small area of ' liner coating. Allegations 54 and 55 are not considered to have any ; significant effect since the amount of area not reworked due to coating thickness out of tolerance is believed to be small. HoweverguEC's estimated 5% miscellaneous steel coating areblNe di to - indeterminate quality may be low when correction of adhesion test results ' is made as' discussed above. (3) Allegations 19,37(b)and46(a)werenotsubstantiatedandtherefore O ft-Je no concern. (4) Allegation 37(d qd0 ac_e_, TR T' bd not snves tg P55th C teckmed w ons w . SiQeM) was found (5) Allegation 56 was not investigated by TRT since it involves to be indeter wrongdoing and there was insufficient information available to assess its potentialextentand)ffectoncoatingquality. This allegation has been referred to NRC Region IV OI for their review. Even though TRT found that most of the above allegations were of small technical significance with respect to the BTP overall pass / fail rate, many of them, as indicated in the individual assessments, relate directly ! to TRT generic concerns about other aspects of the TUEC coating QA program and are addressed in other Coatings SSER sections. l 5.b Evaluation of Backfit gram Test Results i j T evalu ed t BTP inspect on an test fi ld da directlypdeter il depen ently, it n practi 1 mits, the mo t of coated afeas ested a id t e extent to which tested oatings pass d their DFT and a' esion te t ac tance criteria. 6
.o !
Deficiency description (dA rM CS 9AA d <>,A-c ,'i=-ickn~ad 7,c.,sriac i t Reference document & A-n\;cJ 5J54 - 2. ~~
- s Number of similar deficiencies Sample size Sample bias - -
Effect upon ability of component or system to perform function . Area of work: Concrete work ' Mortar blocks Steel Fracture toughness testing 1 Expansion joints U-2 vessel placement - . Welding Inspection and testing , Materials used Labor qualifications . Working conditions QA training and organization ! Specify other areas , Responsible contrac'or t ' Estimate' month and year deficiency occurred ' Describe QA/QC related cause(s) ! Describe corrective action (s) Specific ' i t Broad (QA/QC related). l i
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,_ . . . - . .. . . . . - . . . .-. - -. .....- - -...-...a
- ~
Draft 2 / CP6 BNL-01, etc. 4/5 'o4 ta/2inf54(W. Wells) SSER
- 1. Allegation Group: Coatings No. 2 - Design kasis Accident (DBA) Qualifica-tion Testing
- 2. Allegation Number: Parts of AQO-01, AQ0-02, AQO-03, AQO-04, AQO-05, AQO-06, AQ0-09, AQO-10, AQO-11, AQO-12, AQO-13, and AQO-15
- 3. Characterization: It is alleged that some protective coating systems applied at the Comanche Peak Steam Electric Station (CPSES) are not DBA qualified. Examples are:
Imperial coatings (Southern Imperial Coatings of New Orleans) applied in the sequential order #11S/1201/11S/1201 or #11S/1201/11/1201, in accordance with B&R Procedure CCP-40, Paragraph 4.3.1.2. (AQ0-01)
. Repair coatings system applied in sequences which are different from the original application sequences, as discussed in nonconformance report (NCR) #C83-01752, June 23,1983. (AQO-02)
. Carboline Phenoline 305 (P-305) applied over another manufacturer's epoxy coating, in accordance with design change authorization (DCA)
#17,142, Revision 2. (AQO-03)
. Carboline Carbo Zinc 11 (CZ-11) topcoated with Imperial 1201, in accordance with DCA #12,374, Revision 1. (AQO-04) 4 P-305 applied over Ameron Dimetcote 6 (D-6), in accordance with CPSES Procedure #CCP-30A, Revision 2, Paragraph 1.3.1 (AQO-05)
\)
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.. . Imperial Nutec 115 surfacer applied over f. eign objects embedded in concrete, in accordance with CPSES Procedure #CCP-40, Revision 5, Paragraph 4.1.1.3. (AQO-06) ,
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/
/
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b
,e
. . Inorganic zinc prirrer applied in three coats. (AQO-09)
. Coatings applied to surfaces prepared by power tool cleaning which were smoothed or polished and thus do not have adequate surface profile. (AQO-10)
. Primer applied to a thickness of 0.5 mils, in accordance with DCA #18,489, Revision 1. (AQ0-11)
. Imperial coating system 11S/1201/115/1201 applied at a thickness of 102 mils, in accordance with CPSES Procedure CCP-40, Revision 5, Paragraph 4.3.1.2. (AQ0-12)
. Coatings applied in the reactor core cavity which will be subjected to higher levels of neutron and gamma exposure than coatings in other areas. (AQO-13)
CZ-11 or Carboline 191 primer (191P) applied over P-305, and P-305 applied over Imperial 1201, in accordance with CPSES Procedure CCP-30, Revision 11, Paragraph 4.4.3.0. (AQO-15)
- 4. A}sessmentofSafety/Shificance: The implied safe.tySconcern of these legations is tha.[protactive coating systems in ide t ie primary contain-ent structure wh ch hava not been qualified by BA te ing could fai uring service nd interfere with the functio ngofepgineeredsafeguar i tystems. An e aluation of the significance fthissa[fetyconcernis reported in ( TER). TF e Technical Review eam (TRT) evaluation f the
. puality assu ance aspects of these allegat ons follows.
I l i Review of D A Qualifica". ion Test Data I requirements per inent asses'/ ng these allest ations, the TR reviewed the, i t DBA testing of protec ive coating m/aterials j used !inside p/rimary c ntain-l a \ t AS-31 men The CPS FSAR and Technic,al Specificati st7ucturesatCPSES. commitfiexYs Utilities Electr4n Cempany (TUEC) to comp \ tar (ce with American i
,n -
g s . !
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inc1 ded incorrect and c fusing instructions in regar to repairs where
/ coa ings overlap, and at the RPICs did not clarify he situation.
(Fu ther discussion of the adequacy of CPSES procedu es is prov;ded in 1 SS R writeup Coatings No. 4.) TU IC has stated tha the overlap )ing of coating sy tems, althou h the re'sultant systems ve not been specifically DBA ualified, is ptandard practice in the nu lear industry. The TRT concu s with this statement, pr ovided that suc areas are lirr ited to the smal 'est practical aize, and [ tr at such overlap are performec in accordance w ith " standard good coating pr actices" and t e manufacturers ' instructions, and are careful y ir spected, and p ovided that there is adequate t!echnical justifi cation for tre overlapping systems and the application met ods employed. Tte TRT evalua ed overlapping systems used at C )SES and determin ed that tteir limited se was not an it of concern. I 4owever, the TRT etermined I ttat applying inorganic zinc ove an oating is not tec nically X, a ceptable ar that there is con iderable evid nce that this syst m will { n t perform atisfactorily. TUE estimated th t the surface area coated wi h inorga c zinc on top of ep y ranges fro are feet; th TRT con urs with this estimat . n2,500to6,500sq\ Th adequa y of design evaluations and justif- cations for coatings systems at PSES i discussied elsewhere in his repor;. Because of the rel itivel( mino sur ace areas involved in thes overla systems, the TRT conc ded , that, thi item is without adverse consequenc s.
, 5. Conclusion and Staff positions: The specific nonstandard coating systems described in these allegations represent a small percentage of the total i
area coated within the CPSES containment buildings. The significance of the size of this area is discussed in SSER writeup Coatings No. 6, and an evaluation of the safety significance of potential coating failure (both for this area and for the major coated areas) is reported in (LATER). 4
O i l i Based upon the TRT's broader investigation of TUEC's design and engineering for the major coating systems at CPSES, as well as the investigations of ( specific allegations, the TRT concludes that perfo kmanceaofmm.m desig.n and f engineering functions for coatings was inadequate.,/ngiIieering review and } evaluation #was evidenced by the deficiencies in the DBA data base and in [
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design control activities and documentation, and can be generally charac- f terized as a failure to make accurate technical assessments and valid ! t engineering judgments in regards to coati . The TRT found that this 4, engineering performance clearly demonstrated that some personnel assigned by TUEC to perform coatings engineering functions were either not capable or qualified to perform these functions, and that there was implementation 4 of engineering review and checking measures which should have detected and corrected poor engineering performan e. The result of these deficiencies is that TUEC has not demonstrated that the coating systems applied at CPSES are DBA qualified, in accordance ~with ANSI N101.2 and N512. These deficiencies have also resulted in deficient
' coating work that could have been prevented by proper design and effective engineering evaluation.
The generic implication of these conclusions is that TUEC's quality assurance program failed to implement effective design control of safety-related coatings, and to detect and remedy that deficient implementation, thus rendering the overall effectiveness of the QA program and of basic engineering functions indeterminate. Ob ,
- 6. Actions Required: Priortofivefercentofful A
ower, TUEC shall comply with th following requir merts. (a) otain directl from 0 L complet DBA test eport data which emonstrates that all .ajor saf ty-related ating s stems us d at
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CPSES are ualified i accordncewithANSIN101.2andN512.$-Where
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such tes report data. do no exist, a new RNLDBAtestshalfbe erfor ed and reporte.. ch such test rep shall be comt lete in L a espects including compete data on test methods, sample
N msw $Y~W G.FWL&S Deficiency description d1)4-77Wf r4 cEA8/L/Ty' t Reference document (#)prik)65 JJSg 3
> Number of similar deficiencies Sample size Sample bias -
Effect upon ability of component or system to perform function - Area of work: Concrete work Mortar blocks Steel Fracture toughness testing Expansion joints U-2 vessel placement - Welding Inspection and testing Materials used Labor qualifications Working conditions QA training and organization Specify other areas Responsible contractor Estimate' month and year deficiency occurred - Describe QA/QC related cause(s) Describe corrective action (s) Specific Broad (QA/QC related). 4
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_m ,~ _ e SSER-COATINGS 3 DRAFT 3 - 19 Oct. 84 - c WILLIAM C. WELLS
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- 1. Allegation Group:
ID Coatings 3 Traceability
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- 2. Allegation Numbers: Parts of Q0-34, ,AQ0-36, and AQ0-62.
s
- 3. Characterization: It is alleged that:
W - The requirements of American National Standards Institute (ANSI) Standard i
^
N45.2.2 - 1978 were not met for coating material storage M AQ0-34) A ? The traceability of coating materials was not always maintaine p. (AQO-36)
' --- - - 4 l- ').
Some paint used at Comanche Peak Steam Electric Station (CPSES) in Service Level I areas was contaminated with grease and oi (AQO-62)
- 4. A.ssessment of A fety Significance:M implied Q ht.vx l thveroofthese alle 'tions a i that coating mater' is used inside of eprimaLyconta' en I
P- - -
)
ding / a CPSES rhich are Jbuil ttraceabiftoori nal qualifihatiorf teste l mate ial are not qualifie . Non-qualifi ed co ings could fa 1 uring o ! following a paw &We gn basis accident BA) and interfere with the 1 l SSER-COATINGS 3 1 COMANCHE PEAK
. / 1 l
I obser ed differe s r irregulari 'es .,uch as tho ocu nted in th s K
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shoul d be the oughly investigat d to as ure th traceabili y to e origi al quali ficat n tested t atch h not bee los ttiroughdeficie ~ s in - ing, handlin' , o use.
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manuf ct
- 5. Conclusions and. Staff Positions: .
ased upon reviews of individual allegations described above, the TRT concludes that: F hQ3-29 WW( , .
- 0)StWhY' 3 T' ? ^
T:.-:3 JLilegation cf noncomplianc'd with ANSI N45.2.2 is Ar-reir/=t- [mpli ce with hat standard is not required by the CPSES FSAR M '3 c,a82iLL 3.,44 yulnag Therefore, this allegation -is- 'it"ce' Wert: :=r:qce=es., safety %phA gLn2 $3onadu s c W ' - wM significance;.ie generic implications.
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""' " + allegation that the traceability of coatings materials was not
- a A g always maintained is correct. The primary significance of this allegation is that, at present,)appli2coatingslin areas included in the backfit program 1, are of indetenninate traceability.
.- = - - - - - ...-
Aq 3 - bL 1.00-:624@ allegation that coating materials which were contaminated with A grease were applied at CPSES has not been supported by the TRT's investiga-tion. In the one instance,-dtsettesed-ebovDwhere " grease" contamination was observed, the material was returned 'ot the vendor and the TRT found no l SSER-COATINGS 3 17 COMANCHE PEAK
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evidence to indicate that any gf this contaminated material was applied.
.Q % \ di ad/hx7k N Therefore t is al gation 4: :S +ai H wi+ W t 9fer:: conseqtrenc:: cr ety sig ificanceP TL4 $M4 M O 4 .
However, in the investigation of the subject of contaminated materials in , general, the TRT found instances of coatin A
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s which we.c) ra " d d.%... hed r unknown contaminants or which exhibited other unusual and - A unexplained properties. The TRT found that in these other cases, the operation and documentation of the Nonconformance Reporting System at CPSES was inadequat,e to demonstrate the cause of the irregularities, to provide adequate technical justification for use-as-is dispositions for the deficient materials, or to address and correct whatever fault in the manufacturing, handlin'g, or materials control processes produced the deficient materials. Q'l A h 13 vet 1.n01u Aude._ gena;6hims MAtMu/&gMikoct0>5
;c rc.ic. ef TtlEC's material control and traceability
[j, . t TWUAA403rW p systeyscrib d 250-l0 the' TRT con udes that: , k The material
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control system, as it is implemented currently at CPSES, provides general [ control and assurance of traceability for most coating materials, but is not adequately rigorous to assure traceability for all coating materials. The primary area of concern, as discussed above, is that materials storage and issuance routines do not include the necessary controls to assure segregation of "Q" and "Non-Q" materials and to prevent the use in Service Level I areas of materials designated "Non- The TRT was not able to identify specific incidents wherein .this lack of rigorous control had resulted in misuse of SSER-C0ATINGS 3 18 COMANCHE PEAK
. [ f s' - .
i s .
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materials; however, procedural changes are required to prevent such incidents . in the future. The subject of procedures aind required changes is discussed A N% . further% in SSER Coatings 4.
/ ^ .I The TRT determined that the material control system was not adequately implemented prior to_ November 1981. USNRC Region IV Inspection Report 50-445/81-15; 50-446/81-15 has identified violations concerning inadequate -
inspection and documentation practices for coating work prior to November - ; 1981, which resulted in loss of material traceability. The TRT has determined that the corrective action performed by TUEC to date (i.e. the Backfit Inspection Program) has not restored material traceability. As detailed belou, it will be necessary for TUEC to investigate this area further in order to quantify the extent of the problems and to permit an assessment of its significance.
- 6. Achions Reouired*
I J M ec.ause of the encies in coatin nspection records nd, ma rial contro record noted above, because f TUEC's co espond ' ice to th TRT which tated, ' raceabili does not exi t in all ses for c tings I auplied pri r to Nove ber 1981 TUEC shall con uct an nvestigatio to
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i t e amount aind loc lon of surface a as f r which mater' 1 jentify/
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I / t ceab'lity does no-, exist, and shall provid this information,to the NRC. l SSER-COATINGS 3 19 COMANCHE PEAK l ___-___
- m m "59/ w w w
- l i*
s
- Deficiency description (ddTid68 /ddC6/c/g6.8 l
1 q Reference document 2674 "DM6f ff84 - / '
~ * '
)
I Number of similar deficiencies Sample size Sample bias - { Effect upon ability of component or system to perform function l Area of work. i Concrete work Mortar blocks Steel Fracture toughness testing Expansion joints U-2 vessel placement - i Welding Inspection and testing Materials used Labor qualifications Working conditions QA training and organization Specify other areas . t Responsible contrac'or t Estimate' month and year deficiency occurred - Describe QA/QC related cause(s) _ Describe corrective action (s) Specific I Broad (QA/QC related). l l a
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CPSES NRC TRT DRAFT 1 SSER - C0ATINGS 4 8 NOV 84 CQATINGS PROCEDURES W. C. WELLS PAGE 1
- 1. Allegation Group: Coatings 4 - Coatings Procedures
- 2. Allegation Number: Parts of AQO-01, AQO-02, AQO-03, AQO-04, AQ0-05, '
AQO-06, AQ0-07., AQ0-08, AQ0-09, AQO-10, AQO-11, AQO-12, AQO-15, AQO-17, h 4 0 -l E AQO-19, AQO-20, AQ0-23, AQO-24, AQ0-31, AQO-34, AQO-36, AQO-38, AQ0-39, , AQ0-40, AQO-41, AQO-42, AQ0-43, AQ0-44, AQ0-45, AQ0-48, AQ0-49, AQ0-51, AQ0-58, and AQO-62. l
- 3. Characterization: It is alleged that:
l t A - Comanche Peak Steam Electric Station (CPSES) coating work procedures and related instructions allowed the use of coating systems and application methods that were not Design Basis Accident (DBA) qualified. Specific 3 allegations are: ,
- CPSES procedure CCP-40;" paragraph 4.3.1.2, allows application of Imperiai ;
coatings in the sequential order #11S/1201/11S/1201 or #11S/1201/11/1201. (A00-01) ,
- CPSES Nonconformance Report (NRC) #C83-01752, June 23,1983, and Table A2 in Appendix A of CPSES specification 2323-AS-31 allow repair coatings to be applied in sequences different from the original application ;
sequences. (AQ0-02) r
- CPSES Design, Change Authorization (DCA) #17,142, revision 2, allows application of Carboline Phenoline 305 (P-305) over another manufacturer's ,
epoxy coating. (AQO-0,3)_
. - CPSES DCA #12,374, revision 1 allows Carboline Carbo Zinc 11 (CZ-11) to be topcoated with Imperial 1201. (AQO-04)
- CPSES procedure #CCP-30A, revision 2, paragraph 1.3.1 allows application ~
of P-305 over Ameron Dimetcote 6 (D-6). (AQO-05)
. CPSES NRC TRT ' DRAFT 1 SSER - COATINGS 4 8 NOV 84 5 C0ATINGS PROCEDURES - W. C. WELLS PAGE 2
- CPSES procedure #CCP-40, revision 5, paragraph 4.1.1.3 allows application
. of Imperial Nutec 115 surfacer over foreign objects embedded in concrete.
(AQ0-06)
- Inorganic zinc application in three coats is allowed. (AQO-09) ,
- CPSES DCA #18,489, revision 1 allows primer to be applied to a thickness of 0.5 mils. (AQO-11) .
- CPSES procedure #CCP-40, revision 5, paragraph 4.3.1.2 allows the Imperial coating system 11S/1201/11S/1201 to be applied to a thickness of 102 mils. (AQO-12)
- CPSES procedure #CCP-30, revision 11, paragraph 4.4.3.0 allows CZ-11 or Carboline 191 primer (191P) to be applied over-P-305, and P-305 to be _ _
applied over Imperial 1201'. {AQO-15). B - CPSES coating work procedures and related documents include instruc- ~ tions which'are technically incorrect. Specific allegations are:
- CPSES #C83-01986 provides a repair disposition for cracking and flaking of concrete coatings which will not remedy the cause of the deficiencies. (AQ0-07)
- CPSES procedure #CCP-30, Rev. 11, allows inorganic zinc primer to be applied over zine residue which will cause adhesion problems and prevent galvanic action. (~AQO.-08)
- TUGC0 procedure QI-QP-11.4-5, revision 27, paragraph 3.2.2.3 permits acceptance of non qualified and technically inadequate power tool cleaning methods for surface preparation. (AQO-10)
- The method used at CPSES to remedy high dry film thickness (DFT) of -
CZ(.-11 will e sult in poor adhesion of the topcoat. (AQO-38)
DRXFT 1 o CPSES NRC TRT 8 NOV 84 SSER - COATINGS 4 COATINGS PROCEDURES W. C. WELLS PAGE 3
- Applied P-305, one and two years old was topcoated with new p-305 with little or no surface preparation. (AQ0-39)
- Residues resulting from power tool cleaning of surfaces were removed by improper methods. (AQO-40) .
- A foreign cleaning solution was used to wipe surfaces immediately prior to repairs. (AQ0-41) ,
- The methods used at CPSES to verify the cure of inorganic zinc primers are not adequate, and inorganic zinc primers are not properly cured prior to topcoating. (AQ0-43)
- The " nick e test" for verifying the cure of inorganic zinc primers
, ~ prior to topcoating was not performed properly.- (AQO-44) _ C - Backfit inspection procedures and methods were inadequate. Specific allegations are:
- Q.C. Inspectors were not allowed to identify visual defects during backfit inspections. (AQ0-18)
- TUGC0 procedures QI-QP-11.4-23 and QI-QP-11.4-24 are very vague regarding the way that backfit inspections are to be conducted, (AQO-19)
- Adhesion tests of protective coatings were not properly performed.
(AQ0-20) _ _ _
- Excessive thinning- of P-305 resulted in a weak and brittle film and made it impossible to obtain a Tooke gauge reading. (AQ0-51)
D - Coatings were applied to surfaces where they should not have been applied. Specific allegations are: e
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F ' cPSES NRC TRT DRAFT 1 ) SSER - COATINGS 4 8 NOV 84
' W. C. WELLS CQATINGS PROCEDURES '
PAGE 4 j l
- Q Coatings have been placed over rusty, scaly unprepared metal surfaces ,
inside pipe supports made of tube stee,1 without end-caps. AQO-24)
- Imperial 11S and 1201 were applied over duct tape and foam rubber on Richmond Inserts. (AQO-42) ,
- Coatings were applied over joints which were filled with foam. (AQO-48) l
.- Overspray was allowed in areas which had been inspected previously.
(AQ0-49) E - Quality Control Inspections were inadequate. Specific allegations are:
~
- Tests of the cleanliness of compressed air used for spray application
. of coatings were invalidated'due to the practices of production personnel.
(AQO-17) .
- The coatings Q.C. program at CPSES is inferior to such programs at other nuclear power plant project. (AQO-23)'
- QC management interpreted an SSPC-SP-6 blast requirement given on a CPSES DCA as "do the best you can" and told the QC inspectors "not to worry" about difficult access areas. (AQO-31)
- Repairs of defects have been accomplished with no reinspection of the defects. (AQ0-45) . _ _ _
. - CPSES OC inspection procedures require that inspections be performed with i'. adequate light. (AQO-58)
F - Procedures were inadequate to assure coating materials traceability. Sracific allegations are: 1
" 1
. cPSES NRC TRT DRAFT 1 SSER - COATINGS 4 8 NOV 84 i COATINGS PROCEDURES W. C. WELLS PAGE 5 .
- The requirements of ANSI /ASME N45.2.2-1978 were not met for material-storage. (AQO-34)
- The traceability of coatings materials was not always maintained.
(AQO-36) .
- Some paint used at CPSES in Service Level I areas was contaminated with grease and oil prior to application and was applied anyway. (AQO-62) ,
- 4. h essment of Safet'y Sionificance: The implied safety signif ance of thes allegations is that the use of improper procedures f performing ;
and ins cting coating work could result in defective f ished work. I 9 Defective at.ings could fail during service and int fere with the func-tioning of en ineered safeguard systems. An eval tion of the signifisance of this safety neern is reported in {...... R). The Technical Review Team (TRT) evaluat1 n of the quality assuran e aspects of these al.lega-tions, as characterize above, is discuss below. TheTRTreviewedtheprochdresand nstructions which governed the per- l formance and inspection of pr ec ve coating work at CPSES to determine ! the acceptability of those pro res and instructions and to verify the , I inclusion of appropriate qua itat and qualitative acceptance criteria for determining that impor ant activit' s have been satisfactorily accom- l plished. The TRT reviewed the measures tablished at CPSES to control the review, approval, and issuance of instr tions and procedures and revisions thereto, h,e TRT also observed coat g work activities and-reviewed coating ork records to determine whethe important activities had been accom ished in accordance with the governi g procedures and instruction . The TR also performed a detailed review of procedures rela d to specif.ic alley tions, grouped in several generic or functional areas. his review ingluded an-evaluation of the adequacy of the written procedures as well
CPSES NRC TRT ORAFT 1 S'SER - COATINGS 4 8 NOV 84 v' C0ATINGS PROCEDURES W C. WELLS
. PAGE 39 N
Howe .r, in the TRT's generic review of TUEC's system for c rol of coatin materials, as reported in SSER - Coatings 3, the T determined that the ocedurally addressed system was inadequate rigorous in several resp ts. Brown & Root proc ure CP-CPM 8.1, revision , " Receipt, Storage, and Issuance of Items," rovides requirement for control of stored coating materials prior to isst nce to the pai department. However, once , materials have been issue from the site warehouse to the paint department, the only storage control req ire nts are these provided by CCP-30, CCP-30A, and CCP-40. These pr edures address storage temperature ranges f and location of Q materials in th aint storage warehouse segregated from non-Q materials and litt else. Th e procedures do not address any physical inventory con rol measures or equirements for moving materials
~ {
in and out of the p nt warehouse. They not describe controls to assure )
- the continued seg egation of Q and non-Q mat fals when they are moved in and out of the arehouse and are transported to nd from different.loca-tions on sit TUGC0 pr edure QI-QP-11.4-17, revision 6, " Surveillance Storage and Handli of Protective Coatings," provides for monthly stora inspection of s rage facilities by Q.C. but imposes no requirements for ma frequent ch cks to verify physical control is maintained in the interim and con-rol by Q.C. of materials during transport on the job site or storage at other job site locations.
. 5. Conclusions and Staff Positions: Based upon the reviewing of individual allegations described above, the TRT concludes that:
A. Allegations concerning DBA qualifications (AQO-01, AQO-02, A00-03, AQO-04, AQO-05, AQO-06, AQO-11, AQO-12, and AQO-15): A detailed evaluation of these allegations as related to DBA qualification of coatings is provided in SSER - Coatings 2. The individual items cescribed by the allegations are not significant because they concerned
1 CPSES NRC TRT DRAFT 1 , y SNR-COATINGS 4 8 NOV 84 C0ATINGS PROCEDURES . W. C. WELLS
' - PAGE 40 only minor surface areas, or because they were properly corrected by TUEC, or because they were not substantiated. However, it should be noted that SSER-2 also address TRT technical concerns related to DBA qualification of coat'ings which' remain and are beyond the specific scope of these individual allegations. .
The significance of these allegations from a procedural perspective is that TUEC's failure to properly address special case coating systems for . overlaps and repairs, has resulted in applied coating materials that are both not qualified systems, and not technically viable. B. Allegations concerning procedures and instructions which provide technically incorrect directions, (AQO-07, AQO-08, AQO-10, AQO-38, AQ0-39, AQO-40, AQ0-41, AQO-43, and AQO-44): AQO-07: While TRT found the disposition and repair for the NCR involved in this particular allegation to be generally acceptable, the TRT.found that TUEC's procedures governing application of concrete materials as detailed above, were not in compliance with the manufacturer's instruc-tions. The significance of this finding is that such materials as applied at CPSES may not perform adequately in service or under DBA conditions. AQO-08: This allegation was not substantiated.
'AQ0-10: The TRT found that TUEC's procedures for power tool cleaning sur-faces for touch up work, and inspection of this work were inadequate to assure acceptable roughening of the surface. The significance of this-finding is that materia E applied to these areas may not exhibit adequate adhesion.
AQ0-39: This allegation was not substantiated. AQO-40: The,,TRT found that TUEC's procedures for removal of debris from power too'l cleaned surfaces were inadequately rigorous, but unlikely to result in undetected defects in applied' coatings. This allegation is therefore not significant.
. CP.SES NRC TRT DRAFT 1 SSER - C0ATINGS 4 8 NOV 84 / W. C. WELLS
( ' COATINGS PROCEDURES PAGE 41 AQO-41: The TRT found that the use of the foreign cleaning agent as it
. occurred at CPSES did not have any adverse effect upon applied coatings, and that current procedures. adequately control future use of such materials. Therefore this allegation is not significant.
AQO-43 and AQO-44: The TRT found that the concerns raised by these allegations did not result in improper curing of inorganic zine at CPSES. Therefore these allegations are not significant. , C. Allegations concerning Backfit Inspections (AQO-18, AQO-19, AQO-20, andAQO-51): AQ0-51: This allegation was not substantiated. AQ0-18, AQ0-19, and AQ0-20: As discussed above demonstrate that baciffjt. ,, inspection procedures were-inadequate in certain respects, however the TRT did not find that these inadequacies would have any significant effect upon the data generated by the Backfit Program (see Coatings SSER-1). D. Allegations concerning coatings applied to areas where they should not have been applied (AQ0-24, AQO-42, AQ0-48, and AQO-49): l i The TRT found that the areas described in AQO-24, AQO-42, and AQO-48 have been entered into the CEL and therefore these allegations are not signifi-cant. AQO-19 was not substantiated. However, the TRT found that inade-quate procedural address of protective measures to be taken for items not to be coated resulted in defects which could have been avoided and created l. I the possibility of unnecessary damage to other plant items. (The TRT did not find evidence that such damage occurred.)
~
E. Allegations concerning the performance of Q.C. inspections (AQO-17, AQO-23, AQ0-31, AQO-45, and AQO-58): l 1
. CRSES NRC TRT DRAFT 1 l SSER - C0ATINGS 4 8 NOV 84 ,
W. C. WELLS
/ COATINGS PROCEDURES -
PAGE 42 l AQ0-17: Was substantiated in regards to the insertion of filters during j air acceptance tests, which invalidates those test results. The TRT did l l not find any evidence t_ hat .this resulted in defects in the work. However, ! this allegation is significant in'that it represents interference with the j proper performance of a Q.C. inspection activity and therefore renders . l recorded results for air acceptance tests, and possibly other inspections,
-indeterminate.
AQO-23: This allegation was not substantiated. AQ0-31: This allegation was not substantiated. AQ0-45: Was substantiated in regards to inadequate procedural address of reinspection for repair work. The significance of this finding is that there may be undetected and uncorrected defects-in repaired areas, although l - the TRT did not observe any such cases. The TRT found that TUEC's provi- ' L> sions for a final engineering walkdown inspections are not an acceptable remedy for this concern. AQO-58: Was substantiated in regards to inappropriate instructions and requirements for illumination during visual inspections. The significance j of this finding is that visual inspections may not have been performed properly and there may be undetected defects in the applied coatings. F. Allegations concerning traceability (AQO-34, AQO-36, and AQ0-62): A detailed evaluation of_the significance of these allegations is provided in SSER - Coatings 3. The significance of these concerns in regards to procedures is that inadequately rigorous procedural address of coating material control measures may have resulted in unnecessary loss of traceability. The significence of all of the allegations discussed above, excluding those which were not substantiated, in regards to the TRT's evaluation of TUEC's procedures and instructions gover'ning coating work activities at
CPSES NRC TRT DRAFT 1 SSER ' COATINGS 4 8 NOV 84 / . COATINGS PROCEDURES - W. C. WELLS
. PAGE 43 CPSES, is that those procedures were inadequate and inappropriate in many respects. This allowed the performance of defective work in certain instances, which result;ed in an unnecessarily large area of exempt coating work as entered in the CEL. This also resulted in inadequate performance of inspections in certain instances where the proper performance of those ,
inspections could have prevented or corrected that defective work. The TRT concludes that these procedural deficiencies demonstrate that review and approval of procedures and instructions by TUEC was inadequate to , detect and correct these deficiencies. Inadequate performance of proce-dures review and approval activities demonstrates that the personnel who performed those activities were not qualified to make the correct' technical and quality evaluations of those procedures. This conclusion has the gen-eric implication that inadequate review and approval of procedures may have occurred in areas other than coatings and may have resulted in inap-propriate or inadequate procedures and possible defects as a result fn_ ! other areas or TUEC's construction program.
- 6. Actions Required:
- 1. The TR
/
und deficiencies in procedures and instru ions for coating work and relate nspection activities that rendered them inappropriate or inadequate for deter ning satisfactory accompl,ist ent of important activities. For example. (a) Texas Utilities Generating o. (SUGCO) procedures QI-QP-11.4-1, revision 20, QI-QP-11.4-5, revi fron 9, and QI-QP-11.4-26, revision 6, provide inadequate and inapp priate i tructions regarding lighting to
, be used during visual ins ctions of coati work. This would result in the inability of the i pectors to properly de et and identify defects in the work. -
(b) TUGC0 pr edure QI-QP-11.4-5, revision 27, provides or acceptance of surfaces w ch have been power tool cleaned using inappropr te methods. TUEC dat.a on file supports the acceptability of power tool cleaning only
/
1 Def fciency description _ d&WS DJffcnM .r- M-cy))%tre, pgj __ g Reference document drM)wJ JJEA- Q,fJ,f4 ' Number of similar deficiencies Sample size
~
Sample bias - Effect upon ability of component or system to perform function . Area of work: Concrete work Mortar blocks Steel Fracture toughness testing Expansion joiitts U-2 vessel placement - Welding Inspection and testing Materials used Labor qualifications Working conditions QA training and organization Specify other areas Responsible contractor Estimate month and year deficiency occurred Describe QA/QC related cause(s) Describe corrective action (s) Specific
~ . _ _ . .
Broad (QA/QC related). t i l
Draft 3 / CP5A Parts of BNL-14, 25, etc. 30
.- October M , 1984 S'SER ,
- 1. Allegation Group: Protective Coatings Category No. Sa, (Inspection Reports) ~
- 2. Allegation Number: Parts o AQ0-14,25 49, 50, 52, 53, 57, and 59 p 3. .Characte'rization: It is alleged that: -
3
. "fn'spection Reports (irs) can be dispositioned by anyone (AQ0-14b.)
Instead of writing NCRs, irs must be written as unsatisfactory (AQ0-14b.) Nothing prevents items identified on unsatisfactory irs froni becoming lost, and the problem is not being resolved (AQ0-14b.) P
* [ A seal coat was accepted by QC per'sonnel prior to the finish coat
.. being applied when the seal coat should have been rejected (AQ0-25).
Coating material is oversprayed into areas that were previously inspected, a practice that is allowed, and is commonplace (AQ0-49).
l t l Coatings have been applied without the benefit of quality control inspection (AQ0-50~and'52). QC inspectors denied opportunity of writing Request for Information (AQO-53)
. / on Clarification (RFIC)
Coatings were applied over filth (AQ0-57).
/ ubstandard S coatings were accepted by QC inspectors (AQO-59).
- 4. Assessment of Safety Significance: The implied safety concerAqf these I / 'N T ailure in al u$te inspection reports coulT[esult legations is that inadeq/ethatallhfotectiv\
to demonstrat' e coatings inside the/reactor coptainmentbuildingwer'/
\
applied in accordance wit specified
/ -'
. requirements. An evalu tion of the\ significance o this safety concern I
Theteamevaluationoftequalityassurancle is reported in (later) - I aspects of the allegat! ions related to coating ins ection reports as cha racterized above i discussed below. l l l tive Toaddresstheallegltionsconcerningdispositio'nofIRsforprotec h coaings,theTRTcnductedagenerlicexaminationoftheIRsystem in this area. TheTRTJreviewedTUGC0jProcedureCPQP-18,whichindic3tes-that > irs are the pr/imary method useld to documen' satisfactory and l
\ '
' unsatii sfactory coa' ting inspections. The TRT examination of many irs showsthatcoatin/g problems usuallyi l occur i during onsite applicatiolns a
\ /
Atimewhenrepairsca!neasilybe/ i inspection. identified, documented,
\ / !
and made\ ;U-1hrotpgh the ' tem. existing IR sys\ IR's/that document probisms that cannotbecorrectedusingstandardre(p(irspr/ ocedures are then doc ;mented mJ by an NCR. Accordingly, as discussed below in AQ0-14 theTRTfin(dsthe existing IR system and its implementation to be satisfactory.
, . l I
l pre ared that not d unsa isfactory cond;iti s, which were later rrected. Nor e indicated hat QC i spectors accep d substa ldard coatin s. The irs are well docu ented and also referenc the satisfactory irs Only one of the QC ins ectors invo ved in writir g these Rs was stil war king a Comanche Pe ik. TRT in<erviewed the remainin QC inspect < lr, but .he ga e'no indication that C inspectors ha.1 accep ed substanda d work. The RT 1so interview'd nine urrent on-the-job QC inspections at (PSES, all of whom stated that nspectors do not ac subs ~tandard work.
- 5. Conclusion and Staff Positions: Based on the TRT review of the TUEC inspe'cTion report system and their implementation of it, as-well as on the TRT investigation of alleged improper use of irs, unacceptable seal coat, overspray, coatings applied without QC i.nspections, coatings applied over filth and acceptance of substandard coatings, the TRT l
concludes that reviews of all issues involved indicated in each case that , proper documents existed and corrective action was initiated. ' Allegations AQ0-50, 52, and 57 were substantiated, but had proper documentations and appropriate corrective action. The TRT concludes that these allegations have neither safety s'ignificance nor generic
' implica tions .
- 6. Actions Recu4 red: $cc. CO 8 "4 5 WC D Ifd W " A dik as R
- e. used %r fauner rc. Asm p[ t n 5 P tToY1 .Nd){ o $5
( A SySt./7)' oten ial Violationsj
- 7. F : None ,
V
~
- 1. Allegation Grouo: ProtectiveCoatingsCategory(5b)-{NonConformance Reportsi (NC.h
- 2. Allegation No.: AQO-7, -14
- 3. Characterization: It is alleged that:
[ Disposition of NCR C 83-01986 which dispositions cracking and flak-ing of concrete coatings will not remedy the problem. (AQ0-7) L 3 [ After an NCR is written, anyone can sign off on it. (AQ0- )
-. n 2 5 " un9 MT4a ry y NCRs cannot be written, and that irs must be written with %2cfc'. }
(AQ0-14b)
# A past QC supervisor voided.many NCRs. (AQ0-14c)
- 4. ' Assessment of Safety Significance: The implied safety concern of these allega ions is that dis as 1andappropriate,en$eeringapproval f coatin NCRs are not dequatel performed lnevaluatonofthelsi ifi-cance of this safe y concern s reporte in (later). he team eva uation of the quality ssurance aspects of e allegations rdlated to p gotective coatin NCRs s characterized ve is discussed belo
7- ) 1
, I coa ed surface after pl cement of shims which would equire rework after installation.
Thh' alleger consi red his N :R " voided" by all wing localiz ad repair ra :her than sand lasting an:f entirely re-co ting the hang $'s and sh ims, and cont ry to site procedures and NSI standards. The TRT consi ers the dispos itioned rep r to be technicall ade ate and onsiste t with the site racedures referenced in the NCR an with ANSI nd ds.
- 5. Conclusion and Staff Positions: -
TRT conclusion is that the allegations;f re not substantiated. The overall NCR system is in compliance with T M O
. H oweve t', McR :ystem 'N*::1Nacsies.ncY 'thic.k (L\$$
notd tMt ::= ,.,., I dW <^~ W +0f M ,S I procedgal to anSuTriC.tcws
~ :-fc., ..
Dreagirements.
& Men $ E- W ' " " Qhe 5', '.
e
....sn Q p g DEKoua)iT\]ce nn u u.C u trum. b%u were some,gd4c~r=ri;;b Md o,t'E. d.c$e M t'dAL ca_ts w4 5 y M-5 R C,,tt,e qct \i'., E a.hd '3, Y,R , --
l e ,b:f t c Proh\.6M if\ V oIV$n \ a,ik d de-Is&io'in si t' Hg. ca.u ? C _t'f , l r M c.:N E d d sc6 TC 9m WAT gg - c u Me/Ac.f 'cT r .:;v.-;= n fenw4.x -J.e
- 6. Action Required:'for M Nt WN tTt o t'\ 6' dd Vt.rse To p.t.a. s,
~
t 5 d. 5 5 M Cd \vi Qti / QC, $sER d.aTec< t s 6D. Ahc
,We s_ih3kC'JJ.
fa e .u b AI dr.%1 l-M iju..d A tc c.D.;. t wa.nt .2.i cJTit' Q TCMdg4.
\
- 1) UEC shall revise their Quarterly Trend Analysis Reports issued in a ,n accordance ,with TUGC0 proce' dure CP-QP-17.0 403 treat protective l / -i '
f / \ .' [ coating NCRs separatelf from other,c1vil engindering'NC vide' analyse / /
,/ 2 / / V, s that/are more yresentative of protective coating
/ ,
~~
trdnds. v l l l
- . Draft 1 - 9/20/84 I AQO-3, -11, etc./CP4
> 1 i
SSER , ('- j
- 1. Allegation Group: Protective Coatings No. Sc, Design Change Authorization (DCA) .
.).-
pjy ;j '
- f. t ) r -s> p>
- 2. -31 Allegation Number: AQO-11, t -24,
-26, t -27,t -28,t -29,e. -30,/.
,s
- 3. Characterization: It is alleged that:
(1) A design change authorization (DCA) allows primer coat of 0.5 mils without design basis accident (DBA) qualification,
, (2) Protective coatings e4 placed over rusty, scaly unprepared metal ts surfaces inside pipe supports, (3) DCAs are not controlled, (4) DCAs are originated by Engineering without QA/QC input, (5) DCAs are written instead of ,
(6) DCAs are written to overcome problems, (7) DCAs are used to downgrade surface preparation and specification AS-31, and (' (8) Protective coatings are not removed when outside the acceptable l
> range.
l t
- 4. Assessment of Safety,Sfinificance: The impli,edsTfety significance of
)
th se allegation is that improper use and /process {ng of DCAs ich l allow
/ /
t chnically u ustified cEan ca result ,n l ges in /coating requir ments/ i nadequate q'tialification,fapplicatfon and inspec ion of protectiv c inside reactor cgnin nt building [. aluation of the
~ .
., Protective Coating No. Sc b st you can"; when difficult acces areas were involved, QC </
nanageme t a legedly stated to QC inspec ors, "i you cannot get to an area do not w arry about it." The TRT review of DCAs f allegation Q0-30 indicates t at from time to t ime Engineering did cha ge or downgrade surface prepara+1on from SP-;0 to SP-6. Virtually all heDCAsreviewedappliedtoindccessibleare is. f A' legation AQO-31 is si nilar to QAO-3 . Reviewofthidallegationb TRT ar d' discussions with Q QE personnel did not substantiate that QC manage-me nt stated to QC inspe ctors, "if you.! cannot get to an area do not wprry at out it." QC inspect rs did have q 'estions about DCA 13, 140 Revis ion 1 frvolving what areas re considered to be inaccessibl e and what sho uld be QC inspected. DCA 13140, Revision 2 clarified this issue by incluc ing dedinitivecriteriafrdetermining hether an area was to be consic ered inaccessible. AD The TRT finds that or allegations A00-30 and -31, thtt use of a best-4 A eff art, use-as-is, nd downgrading o specification relquirements fa .r I ina :cessible areas are accepted ind trypractice.fRTreviewof the exe npt log indic ed that virtually a\ l the inaccessible areas docil mented by )CAs were placed on the exempt log. L Base on exe pt log estimates, the tota sarea do graded is not over 3 percen the total coated surface. l l, 5.* Conclusion and Staff Positions: TRT conclusion is that all of the ! allegations reviewed were substantiated, except for AQO-26. However, the allegations have neither safety significance nor generic implications.
- 6. fetions Required: None.
i
- 7. Potent. 1 Vio ati6ns: 4one.
V *
- 8. Att chments: None.
V
r i Daftciency description MIM68 zC XSyp/T Ld6 .._ . Reference document ~~ ' Number of similar deficiencies Sample size Sample bias - - Effect upon ability of component or system to perform function . Area of work: Concrete work Mortar blocks Steel - Fracture toughness testing Expansion joints U-2 vessel placement - Welding Inspection and testing Materials used Labor qualifications ' Working conditions QA training and organization Specify other areas { j Responsible contrac'or t ; Estimate' month and year deficiency occurred ! Describe QA/QC related cause(s) i Describe corrective action (s) , Specific l I Broad (QA/QC related). e $ L 4 l t
b
- 1. Allecation Group: Protective Coatings jb Coatings Exempt Log (CEL)
- 2. Alleoation Numbers: No allegations were specifically directed at the CEL.
- 3. Characterizations: In its investigation of tne allegations concerning deficiencies in the CPSES protective coatings work, the TRT noted that the number and area of the coated items entered into CEL was a convenient mea-sure of plant coatings with unacceptable or indeterminate quality. The TRT also noted that many of the items referred to in the protective coat-ings allegations were entered into the CEL, and further that the combined area of items in the CEL was a significant b$hYof the total coated area. The TRT therefore conducted a generic review of the operation of the CEL at CPSES.
- 4. AslessmentofSa nificance: The im lie safety significance o a
'CEl of excessiv size ir that poor quali y coat gs are more likely to fa:1 under acci ent conc itions. Failed coatings ,could interfere 'th t e e y sesced operation of 4 4 :. J sa feguard system . An eva' uation of the s gnifica nce of this safety concern i s reported in (later).
The CEL was es :ablished by TUEC Procedure No. CP REP-16.4, " Pro ective Coat-in';s Exemption Log," to " provide the method for naintaining ic, ntificat{on of items and/orareasthatdonotme4 rt project ating requir1 ments." I co , ducting its review, ;he TRT examiled this prccedure, inter /iewedsev]nral t J l TUEC civil ent ineering and QA persor{nel regardir g CEL operatyon and ex mined a number of documents b r which some of the large.r areas (larder than IC 00 feet2 ) wire placed in the log. These docun entsincludebTUECmeoran-l l , dt m QTQ-416; DCA 17, 14 3; NRC-C-84 00710; DCA 61 14, Rev. 1; DCA 12,3 , Rev. 1; OCA 6,106; and NRC-C 1488, Rev. 4. l The TRT fo nd several de icienc'es in TUEC Protec re No CP-EP-16. . OO 11/13/84 1 COMANCHE PEAK INPUT CONT
i , ate was wel elo 5% for the miscel ane ps steel categories. Also, ccording t intervlews between TRT nd TUEC 1 QA personnel, a umber o i discrepant areas we.re still not fi lly dispositioned by ei her rework or entry nto the C EL. , A third tem which 1as not been neludedid CEL invo ves C coating which were' not DBA qual fied (seeg n :t'q.s-SS 2 :ve). ;R On 3d"on-stan example is inorgani c zinc coati gs applied over organic T!.t.ftopcoat in over-lap are s surrounding repairs t protective,' coatings o er steel. By letter ated A'ugust 21, 1984, EC estimate d this over'ap area to be betweel 2,500 feet 2 and 6,500 eet 2. Availa le documents 'donotindicatewhether' the 6,100 ft2 of inaccess ble or lir .ited access a eas desc bed in TUEC's letter TX -4262 dated Augtst 21, 3 1984 .n relation to llegati n AQO-31 were tered i to the CEL. DCA 13140, Rev..2 downgrades th requi ements for these areas, ut does not specfy hat the areas should e aced in the CEL.
- 5.
Conclusion:
The TRT concludes on the basis of the items listed above that the operation of the CEL system was deficient in several respects. The CEL procedure, CP-EP-16.4, did not provide adequate guidance and direction to assure that areas with coatings of unacceptable or indeterminate quality were either reworked or entered into the CEL. The TRT further concludes that several sizable areas with coatings of , i j .indeterminatep quality have not been included in the CEL. h I 4 :' ?:d '- tL Z L. These areas include 54,500 ft 8 which may have failed the af2 nW.Seo
~Athattest-according to the TRT audit of the BTP, and 2,500 ft2 to , 6,500 ft of non-standard coatings which were not DBA qualified. The 2
total area which should be added to the CEL is therefore approximately I 60,000 ft 2. Before including this additional area, the CEL identified approximately 55,000 ft2 of unqualified or indeterminate coatings. This value is . already considered high by the TRT, and it would be more than doubled by 11/13/84 3 COMANCHE PEAK INPUT CONT
~_ -
e including the additional 60,000 ft2 . The total of 115,000 ft* is approxi-mately 20% of the total coated aru in Unit _1 containment. The overall conclusion of the TRT is that this value is excessive compared to values at other nuclear plants. The implication of the 20% CEL value is that the remaining 80% of the coat-ings are of satisfactory quality. However, such a conclusion is not valid until the resolution of other TRT concerns such as assurance of DBhquali-fication of coatings and their traceability is reached. (See Coatings SSERs-2 and -3). 6.t Actions Required: TV s all amend the CEL procedure CP- -16. to provide more specific guida e and direction on entering items nto the L. The procedure should ke it c' ear that all discrepant it ms which medt the 3 following criter a shall be automatically included n the CEL: (; ) dis-positioned "use as-is" by (RCs, (b) have been dow raded from .@ Level I by DCAs or(c)determinednottomeetpr[jectcoatingr quirements
> - -by the civil er ineer base d on vendor equipment pecification. he pro-cedure should tiso requir- each CEL entry to be signed and date by the t
civil engineer ng represe ltative with a notatio of the documen) by which the item was p aced in t e log. Also, TUEC sho Jid provid a updated estimates o the additional tems to be entered into t ,e exempt log. These entries an be useful in lanning future f inspections of coatings in connection with inspecting for deb lis that could restrict sump inlets.
- 7. potentialVicflations: None l.
- 8. Attachments: None
- 9. eference Dfcuments:
(1 TUEC rocedure CP-EP 16.4, "Pr tective Coatings Exemptior s Log" . 11/13/84 4 COMANCHE PEAK INPUT CONT,
r I Defi'ciency drscription Mll6f rg [ W/Mg g g;_A4g,/p/ @ Q _ 1 Reference document fo>mMGJ Sf6R-7 ~ ' '
> Number of similar deficiencies Sample size Sample bias -
Effect upon ability of component or system to perform function l Area of work: Concrete work Mortar blocks Steel Fracture toughness testing Expansion joints U-2 vessel placement - Welding Inspection and testing Materials used Labor qualifications Working conditions QA training and organization Specify other areas Responsible contractor Estimate' month and year deficiency occurred Describe QA/QC related cause(s) Describe corrective action (s) Specific Broad (QA/QC related). , e 1 4
i t AQ-22,AQ-32,AQ-33,AQ-35, and Parts of AQ-61 Draft 1 . 10/27/84
.5-l
._ SSER . j 5
- 1. Allegation Group: Prot [ctiveCoatings7-Trainingandqualificationof
, coatings inspectors and painters. s .
- 2. Allegation Numbers: AQ-22, AQ-32, AQ-33, AQ-35, and parts of AQ-61. ,
- 3. Characterization: It is alleged that:
a r r
- Coatings inspectors must perform backfit program adhesion testing .
- without first completing training. (AQ-22) , ;
- Reading list contents have been changed after inspectors sign the
, list. (AQ-32)
- A lead coatings inspector lacked the qualifications to properly {
perform his duties. '(AQ-33) l i
- Some per. sons providing training to prospective inspectors are not ;
properly qualified. (AQ-61a) ;
) .
O
-2
- Level II inspectors " sign-off" for training conducted by Level I inspectors. (AQ-61b) e .vn , d 6th
- Workmanship is poor because painters lack the qualifications s~
necessary to produce quality work, and painter certification documentation is deficient. (AQ-25) .
- 4. Assessment of SafetyfMgnificance:
- Th e general conc rn of th se allegations is that the methods used in.the CF SES quality a surance program for pro ective coatin s to evaluate th prior experiente, provide adequate.trai ning, and certify the ability of I -
ficance of these coatings perso inel are not adequate. The implied sign t I a' legations is that inadequate qualification of personrel could result in I ir Adequate ap lication andiinspection rotective coatings. Defective An coLtingscoul j fail during postulted accidents or during service.
- k I f ev51uationoMthesignificanceofthis ' safety concern is reported in (l.ATER.........).TheTchnicalReviewTeam(TR l l is qu ality assurance aspects'of these allegations, as characterized above, d- scussed b low. ;
r . (
? .
Review of ecuirements for Training and Qualification: I f general and specif c features of coa ;ings inspecti n and i Th TRT e!valuated l app icat on personnel qualificatio systems, and the b sis of each
- spec Q allegation.
0 o -
/
t ,.' 1 F rther, most cer ificatlons state that th employee has " experience w 'ith I zines, phe olines, ep ]xies, latexes, le following p oduct ty)es: namels, and t inners," and do not des ibethetyp/t of experience. he RT found th such expe,rience is sta d when paint-ars have not had
.s~
experience th these gelneric coatin s prior to their hiring at CPS S, I I and the ci d experience consists o providing supp3rt to and observing certified applicators at.CPSES. The TRT found that, with the exc ption of the defic'encies noted above, the C ES system of quali ying pplicators is effect ve and in accordance . w requirements and the general practices used for n lear ating work. '
- 5. Conclusions and Staff Positions:
The TRT examined important features of 'the systems used at CPSES to qualify coatings inspection personnel and painters, and the merits of ' specific allegations involving qualification systems. The TRT has concluded that AQ0-22 is partially substantiated, and that personnel'have performed Backfit Program adhesion testing without first. receiving all of the appropriate training in the cethods and requirements i l ' of performing this inspection. The TRT has further concluded that this deficiency tends to cause . data errors in a conservative direction, and so should not have a significant adverse impact upon Backfit program data. k_
1 . The TRT has concluded that allegation #AQ0-32 is unsubstantiated. The TRT has concluded that allegation fAQ0-33 is substantiated, but was , not able to assess the significance of this deficiency. -
.i-The TRT has concluded that allegations #AQO-61(a) and #AQ0-61(b) are substantiated. The TRT has concluded that the CPSES coatings quality control program lacks sufficient controls to assure the capability of .
~
instructors or the accurate assessment of capability demonstrated during training. ~
- The TRT has concluded that allegation eAQ0-35 was partially substantiated bf the evidence examined, however the TRT considers the specific ~
deficiencies noted to be without significance to completed work. Requirements for the correction of deficiencies are given below. . The TRT's evaluation of the general features of CPSES coatings inspection personnel qualification systems has concluded that, as implemented, the system lacks controls sufficient to assure the required capability of personnel performing functions ascribed to Level I, Level II, and Level. III personnel by ANSI N45.2.6-1978. , The TRT's evaluation of the general features of the CPSES painter qualification system has concluded that, with the exception of specific noted deficiencies, the system is adequate to satisfy all requirements.
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COMANCHE PEAK CIVIL / STRUCTURE AND MECHANICAL / PIPING TEAM L. SHA0', GROUP LEADER CIVIL / STRUCTURE MECHANICAL / PIPING , D. JENG, SUB-GROUP LEADER S. H00', SUB-GROUP LEADER J. DEAVERS, PARAMETER W. P. CHEN, ETEC
~
C. H0FMAYER, INEL V. FERRARINI, EAS T. LANG0WSKI, ETEC D. HANSEN, INEL
~
R. HUBBARD, SANDSTONE, INC'. R. LIPINSKI, liRC R. PHILLEO, PARAMETER D. LANDERS, TELEDYNE J. MALONSON, TELEDYNE R. MASTERSON, EAS C'. RICHARDS', Al E'. THOMPSON', ETEC
1 ] CIVIUSTRUCTURAL AND ECHANICAUPIPING TEAM
- e 6 STRUCTURAL ENGINEERS AND 10 ECHANICAL ENGINEERS i
i i e EXPERTS IN: i (A) CONCRETtDESIGNANDCONSTRUCTION
- (s) PIPING DESIGN AND CONSTRUCTION l
i (c) PIPE SUPPORTS DESIGN AND CONSTRUCTION
- (o) WELDING AND INSPECTION i
I l . I l
i l 9 . ! t t
- ALLEGATIONS
! 57 CIVIL /STRUCTUPAL ELATED ALLEGATIONS i I l lill ECHANICAL/ PIPING ELATED ALLEGATIONS { ; I i 4 I i L 4 e 1
)
k i I 1
SCOPE OF CIVIL /ECHANICAL ALLEGATIONS FIFTY-SEVEN (57) ALLEGATIONS IN CIVIL / STRUCTURAL AREA. THE ALLEGATIONS PERTAIN TO THE FOLLOWING SIX BROAD AREAS:
- 1. DESIGN DEFICIENCY
- 2. TESTING OR INSPECTION IRREGULARITIES 4
f 3', INCORRECT CONSTRUCTION PRACTICES 4., O INADEQUATE REPAIRS 5', UNCORRECTED'lUNSAFECONDITIONSINTHEC0ffLETED STRUCTURES i 6',' PREMATURE STRUCTURAL LOADINGS l l l
SCOPE OF MECHANICAL / PIPING ALLEGATIONS . ONE HUNDRED FORTY SEVEN ALLEGATIONS IN MECHANICAL /
~
PIPING AREA, ALLEGATIONS PERTAIN TO THE FOLLOWING I4 BROAD AREAS: e WELDING e PIPING e SUPPORTS k[. , e OTHERS O I l l l
BASIC APPROACH ,. o REVIEW ALL RELATED DOCUMENTS SUCH AS ALLEGER TESTIMONIES, ASLB HEARING RECORDS, NEWSPAPER ARTICLES, INTERVIEW RECORDS, ETC. TO FORMULATE ALLEGATIONS. o THROUGH INTERVIEWS WITH ALLEGERS AND INFORMAL MEETINGS AND DISCUSSIONS WITH THE APPLICANT AND THEIR CONTRACTORS, DEVELOP THE NECESSARY BACKGROUND INFORMATION. o EVALUATE AND ANALYZE ALLEGATIONS IN RELATION TO CONSTRUCTION, ANALYSIS, DRAWINGS, SPECIFICATIONS, CODES, PROCEDURES, FSAR AND OTHER COMMITTED DOCUMENTS. o DETERMINE THE VALIDITY OF ALLEGATIONS ONCE THE ALLEGATION IS FOUND TO BE VALID, DETERMINE WHETHER IT HAS POTENTIAL SAFETY SIGNIFICANCE AND GENERIC IMPLICATION. . o THE VIOLATION THAT HAS POTENTIAL SAFETY SIGNIFICANCE IS TERMED AN OPEN ISSUE. o OPEN ISSUES WERE TRANSMITTED TO THE APPLICANT FOR ACTION. o DISCUSS FINDINGS WITH ALLEGERS.
DEFINITION OF " LACK 0F SAFETY SIGNIFICANCE" LACK OF " SAFETY SIGNIFICANCE" PERTAINING TO OR AS A RESULT OF A GIVEN DEFICIENCY, OR VIOLATION OF APPLICANT'S COMMITMENTS, CODES, OR FSAR REQUIREMENTS MEANS THAT WHILE AN ACTIVITY OR ITEM DOES NOT FULLY CONFORM TO ALL APPLICANT'S COMl11TMENTS, OR APPLICABLE CODES OR FSAR REQUIREMENTS, TRT CONCLUDES ON A TECHNICAL BASIS THAT THE STRUCTURE OR COMPONENT WILL NEVERTHELESS FUNCTION PROPERLY WITHOUT INTERFERRING WITH SAFETY', 4
A OPEN ISSUE e ALLEGATION IS VALID j e THERE IS VIOLATION
- e THERE IS POTENTIAL SAFETY SIGNIFICANCE t
l l 1 l i l
l POTENTIAL OPEN ISSUES ,, i 1, CIVIL / STRUCTURES 1,1 UNABLE T0 JUSTIFY REINFORCING STEEL OMITTED IN REACTOR CAVITY 1,2 FALSIFICATION OF CONCRETE COMPRESSION STRENGTH TEST RESULTS 1,3 MAINTENANCE OF AIR GAP BETWEEN CONCRETE STRUCTURES 1.4 SEISMIC DESIGN OF CONTROL ROOM CEILING ELEMENTS l','5 UNAUTHORIZED CUTTING 0F REBAR IN,THE FUEL HANDLING BUILDING
- 2. MECHANICAL AND PIPING l','1 INSPECTION OF CERTAIN. TYPE OF SKEWED FILLET HELDS 1,'2 PIPING DESIGN CONSTRUCTION BETWEEN CATEGORY I AND NON CATEGORY.I BUILDINGS 1,3 UNAUTHORIZED CUTTING OF EQUIPMENT RESTRAINT ANCHOR BOLTS IN THE REACTOR BUILDING 1,4 UNCONTROLLED PLUG WELDS
~
1,5 PIPE INSTALLATI0W s _ ,
A . 4 CIVIL / STRUCTURAL CATEGORY NO. 6 - UNABLE TO JUSTIFY REIIFORCING STEEL OMITTED IN REACTOR CAVITY WALL i POTENTIAL OPEfl ISSUE A PORTION OF REINFORCING STEEL WAS OMITTED IN A REACTOR CAVITY CONCRETE WALL PLACEMErlT BETWEEN ELEVATION 812' - 0" AND 819' - 01/2",* ACTION REQUIRED BY TUEC TUEC SHOULD PROVIDE AN ANALYSIS THAT VERIFIES Tile ADEQUACY OF THE REINFORCING STEEL Ill THE AS-BUILT CONDITION OF THE REACTOR CAVITY WALL. 1 l
_ _ _ _ _ m. A ~_ - . _ _ ---- - -- . O CIVll/ STRUCTURAL CATEGORY N0, 8 - FALSIFICATION OF CONCRETE COMPRESSION STRENGTil TEST RESULTS POTENTiALOPENISSUE ALLEGATION ON FALSIFICATION OF CONCRETE COMPRESSIVE STRENGTH TEST REstlLTS COULD NOT BE PROVED VALID OR INVALID. CONCRETE STRENGTH LOWER THAN THAT SPECIFIED IN THE DESIGN MAY REDUCE THE LOAD RESISTING CAPACITY OF STRUCTURES, ACTION REQUIRED BY TUEC TUEC SHOULD DETERMINE AREAS WHERE SAFETY RELATED CONCRETE WAS PLACED DURING THE PERIOD FROM JANUARY 1976 TO FEBRUARY 1977 AND CONDUCT APPROPRIATE RAND 0M SCmIDT HAMER TESTS ON THE CONCRETE IN AREAS WHERE SAFETY IS CRITICAL, l
. r -
I CIVIL / STRUCTURAL CATEGORY NO. 11 - MAINTENANCE OF AIR GAP BETWEEN CCNCRETE STRUCTURES l POTENTIAL OPEN ISSUE l BASED ON THE REVIEW 0F AVAILABLE INSPECTION REPORTS AND RELATED DOCUMENTS, FIELD OBSERVATIONS AND DISCUSSIONS WITH TUEC ENGINEERS, THE TRT CANNOT DETERMINE WHETHER l AN ADEQUATE AIR GAP HAS BEEN PROVIDED BETWEEN CONCRETE STRUCTURES. l l ACTION REQUIRED BY TUEC PROVIDE DOCUMENTS OR INSPECTION RESULTS TO DEMONSTRATE THAT ADEQUATE SEPARATION BETHEEN ALL CONCRETE STRUCTURES !IAS BEEN PROVIDED. PERFORM ANALYSIS TO DEMONSTRATE THAT THE AS BUILT CONDITIONS DO NOT SIGNIFICANTLY INCREASE THE SEISMIC RESPONSES OF CATEGORY I STRUCTURES AND COMPONENTS.
0 CIVIL / STRUCTURAL CATEGORY NO.14 - SEISMIC DESIGN OF CONTROL ROOM CEILING ELEMENTS POTENTIAL OPEN ISSUE FIELD RUN CONDUIT, THE SUSPENDED CEILING ELEMENTS, AND THE LIGHTING FIXTURES INSTALLED IN THE CONTROL ROOM CEILING ARE CLASSIFIED AS NON-SEISMIC OR SEISMIC CATEGORY II AND MAY FALL AS A RESULT OF A SEISMIC EVENT.
- ACTION REQUIRED BY TUEC .
PROVIDE OR MODIFY SEISMIC CALCULATIONS ON SEISMIC CATEGORY II AND NON-SEISMIC ELEMENTS IN THE CONTROL ROOM CEILING TO DEMONSTRATE THAT THEIR FAILURES WILL NOT AFFECT SAFETY RELATED COMPONENTS OR CAUSE INJURY TO OPERATORS.
CIVIL /STRbCTURAL CATEGORY !!0. 15 - UNAUTHORIZED CUTTING OF REEAR IN THE FilEL HAf0 LING BUILDING POTENTIAL OPEN ISSUE UNAUTHORIZED CUTTING 0F REBAR ASSOCIATED WITH THE INSTALLATION OF THE TROLLEY PROCESS AISLE RAILS IN THE FUEL HANDLING BUILDING MAY HAVE OCCURRED. LOSS OF THE REBAR MAY REDUCE THE LOAD RESISTING CAPACITY OF THE CONCRETE FLOOR SLAB.* '.- ACTION REQUIRED BY TUEC PROVIDE Tile FOLLOWING INFORMATION REGARDING DRILLING 0F RE3AR: (1) INFORMATION THAT DEMONSTRATES THAT ONLY THE UPPERMOST # 18 BAR WAS CUT, OR (2) DESIGN CALCULATIONS THAT DEMONSTRATE THAT STRUCTURAL INTEGRITY IS l MAINTAINED IF # 18 BARS IN THE UPPERMOST AND T!!E LOWERMOST LAYERS
- ARE CUT.
ECHANICAL AND PIPING CATEGORY NO. 31 - INSPECTION OF CERTAIN TYPE OF SKEED FILLET ELDS IN NF SUPPORTS POTENTIAL OPEN ISSUE THERE WAS A LACK 0F PROPER INSPECTION DOCUENTATION FOR SKEWED FILLET WELDS WHEN WELDING A PIPE STANCHION TO A PIPE STANCHION', OR A PIPE STANCHION TO A CURVED PLATE FOR CLASS 2.AND 3 NF SUPPORTS'. IMPROPER INSPECTION TECHNIQUES
~
COULD RESULT IN UNDERSIZED FILLET WELDS. ACTION BY TUEC PROVIDE THE FOLLOWING: (1) REVISE B&R WELD INSPECTION PROCEDURES CP-0AP-12.1 AND 01-0AP-11.1-28TOPROFERLYADDRESSALLTYPESOFSKEWED FILLET WELDS, INCLUDING PIPE TYPE CONNECTIONS.~~ (2) PROVIDE EVIDENCE TO VERIFY THAT PREVIOUS INSPECTION OF - THESE TYPES OF SKEED FILLET WELDS WAS PERFORED TO THE
~
APPROPRIATE INSPECTION TECHNIQUES.
E CHANICAL AND PIPING CATEGORY N0', l4 - UNCONTROLLED PLUG WELDS POTENTIAL OPEN ISSUE
~
H0LES IN UNIT 1 & 2 PIPE SUPPORTS, CABLE TRAY SUPPORTS AND BASE PLATES WHICH HAD BEEN MISDRILLED DURING FABRICATION HAVE BEEN REPAIRED IN AN
~
UNCONTROLLED MANNER BY PLUG WELDS. ' l ACTIONS REQUIRED BY TUEC TUEC SHALL PERFORM ONE OF THE FOLLOWING
- 1. PROVIDE A PROPOSED PLAN OF RESOLUTION INCLUDING A SAMPLING INSPECTION OF ALL AREAS OF THE PLAN HAVING PLUG WELDS WHICH INCLUDES CABLE TRAY SUPPORTS', PIPE SUPPORTS AND BASE PLATES 2',
PERFORM BOUNDING ANALYSIS TO ASSESS THE GENERIC SAFETY SIGNIFICANCE . OF UNCONTROLLED PLUG WELDS,
E CHANICAL AND PIPING CATEGORY NO. 11 - PIPE INSTALLATION P0TENTIAL OPEN ISSUE
~
TEMPORARY SUPPORTS FOR THE UNIT L l00P fl MAIN STEAM LINE SETTLED DURING CONSTRUCTION. THE LINE WAS SUBSEQUENTLY REPOSITIONED USING THE MAIN POLAR CRANE AND COE ALONGS. ASSESSENTS OF EFFECTS ON QUALITY OF THE MAIN STEAM AND FEEDWATER LINES HAVE NOT BEEN PERFORED FOR THE FULL SEQllENCE OF EVENTS INVOLVED'. ACTION REQUIRED BY TUEC (1) PERFORM AN ASSESSENT OF THE STRESSES Ill THE AFFECTED PIPING (2) PERFORM NDE OF AREAS WHERE STRESSES EXCEED ALLOWABLES (3) REVIEW RECORDS OF HYDR 0 STATIC TESTING TO VERIFY QUALITY OF AFFECTED PIPING (14) PROVIDE ASSESSENT OF EFFECTS ON OTHER SAFETY RELATED PIPING WHICH WAS INVOLVED IN SIMILAR INCIDENTS OF SETTLEENTS OF TEMPORARY SUPPORTS. . e a __ ._____m. _____ _
m ECHANICAL AND PIPING CATEGORY N0'.18 - UNAUTHORIZED CUTTING 0F EQUIPENT RESTRAINT ANCHOR l BOLTS IN THE REACTOR BUILDING l P0TENTIAL OPEN ISSUE UNAUTHORIZED CUTTING 0F THE BASE PLATE ANCHORING BOLTS ON THE UPPER LATERAL SUPPORTS FOR THE STEAM GENERATOR MAY HAVE OCCURRED'. THE CUTTING 0F THESE BOLTS MAY REDUCE'THE LOAD CAPACITY OF THE LATERAL SUPPORT',' ACTION REQUIRED BY TUEC PROVIDE EVIDENCE SUCH AS ULTRASONIC EASUREENT RESULTS TO VERIFY THE INSTALLED LENGTH OF BOLTING'. SHOULD UNAUTHORIZED BOLT CUTTING BE VERIFIED', TUEC SHALL: (1) REPLACE SHORTENED BOLTS WITH BOLTS OF PROPER LENGTH', OR PROVIDE ANALYSIS TO JUSTIFY THE ADEQUACY OF SHORTENED BOLTS AS INSTALLED'. (2) PROVIDE JUSTIFICATION OR PROPOSE EASURES TO ENSURE THAT N0 SIMILAR CONCERN EXISTS FOR BOLTINif.'
.m '
ECHANICAL/ PIPING CATEGORY N0'. 36 - PIPING DESIGN CONSIDERATIONS BETWEEN CATEGORY 1 AND NON-CATEGORY 1 BUILDINGS, P0TENTIAL OPEN ISSUE PIPINGSYSTEMSSUCHAS-MAINSTEAM'lAUXILIARYSTEAMANDFEEDWATERAREROUTED FROM ELECTRICAL CONTROL BUILDING (SEISMIC CATEGORY I) TO TURBINE BUILDING (NON-
~
SEISMIC CATEGORY 1) WITHOUT ANY ISOLATION. EACH SEISMIC CATEGORY I PIPING SYSTEM SHOULD BE ISOLDATED FROM ANY NON-SEISMIC CATEG0P,Y I PIPING SYSTEM BY
~ ~
SEPARATIONlBARRIERORCONSTRAINT. IFNOT'lTHEEFFECTOFTHEFAILUREOFNON-SEISMIC CATEGORY I STRUCTURES AND PIPING ON SEISMIC CATEGORY I PIPING SYSTEMS
~
MUST BE CONSIDERED.' ACTIONS REQUIRED BY TUEC TUEC SHALL PROVIDE DOCUENTATION THAT PIPING SYSTEMS G0ING BETWEEN CATEGORY I AND NON-CATEGORY I BUILDINGS MEET THE STATED FSAR CRITERIA'.
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Document Namat SSER-[ELECTRICALi\ x . Requestor's ID: ! LINDA Author's Name: Chet Poslusny Document Ccaments: 1/10/85 REVISED IN CRESS RETURN THIS SHEET WITH PEVISIONS e y d J[ . g. v
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- 1. Allegation Category: Electrical and Instrumentation 1, Electrical l
Cable Terminations '
- 2. Allegation Number: AE-13, AE-16, AE-18, AE-22, AE-26, AQE-12,AQE-36, and parts of AQE-39 and AQE-46.
- 3. Characterizationi It is alleged that:
Terminal lugs of improper size and type were utilized on cables in various panels and that improper cable splices existed within certain panels (AE-13). Loose bus bar and ground wire connections existed in a safeguards panel (AE-16). Cables were being butt spliced inside panels in violation of procedures (AE-18). Cable butt splices existed in panels without authorization or without being documented on drawings (AE-22). Cable termination connections were loose and improper-sized lugs were i being used on cable terminations (AE-26). Cable terminations not in conformance with drawings were accepted by quality control (QC) personnel (AQE-12). Vendor-installed terminal lugs were excessively bent and correspond-ing nonconformance reports (NCRs) were improperly dispositioned
- (AQE-36).
Certain quality assurance / quality control (QA/QC) matters related to cable terminations were improperly impicmented. i . L _)
The general concerns expressed in these allegations are within the scope of the above a'llegations and are addressed below as appropriate (parts of AQE-39, and AQE-46).
- 4. Assessment of Safety Sidnificance: The implied safety significance is that improper installation of butt splices and cable connections, disagreement of tne in'tsllation with as-built drawings, or improperly dispositioned NCRs could place the quality of the installation in question.
Sample of Safety-Related Termination Installation. Since many of the alleged conditions identified in AE-13, AE-16, AE-26, parts of AQE-39 and AQE-46 were located in equipment containing nonsafety related cabling, the NRC Technical Review Team (TRT) also sampled safety-related installations to determine whether similar conditions existed within them. Sixteen safety-related items (control panels, annunciator cabinets, termination cabinets, motor control centers, and switchgear) were inspected for the following items: Proper size lugs used relative to cable size and screw size (AE-13). Tightness of bus bar and ground wire connections and terminal lugs on terminal blocks (AE-16). Gereral werkmanship for such items as shaved lugs, proper washers, and bend radii (AE-26). The TRT found no unacceptable conditions with the terminations inspected, ircluding those asscciated with AE-13. AE-16, AE-26 and Parts of AQE-39 and AQE-46. Butt Salices. Allegations AE-13, AE-18, and AE-22 concerned butt splices in panels that could be in violation of regulatory requirements and site procedares. The practice of butt splicing cables in panels was allcwed on a limited basis, as specifed in Section 8.1.5.2.4 cf Amendment 44 to the 1
i Final Safety Analysis Report (FSAR). The NRC staff reviewed Texas Utili-ties Electric Company's (TUEC's) justification for permitting butt splices inside panels (correspondence from M. Srinivasan, NRC Power Systems Branch to B. J. Youngblood, NRC Licensing Branch, July 30, 1984), and concluded that the practice is acceptable on a limited basis, subject to the fol-luwing conditions: That adequate provisions be included in the installation procedures to verify operability of those circuits for which splices are being used, That the wire splices used are qualified for anticipated service conditions, and That splices are staggered within the panel so that they are not adjacent to each other in the same wire bundle and pressing against one another. The TRT inspected butt splices in safety-related panels to determine whether they were installed in accordance with the requirements stated in Texas Utilities Generating Company (TUGCO) procedure QI-QP-11.3-28, Revision 21, " Class 1E Cable Terminations." The TRT also interviewed one alleger to clarify one allegation concerning-butt splices. The TRT found the splices to be in conformance with all procedural requirements set forth by TUGC0 which did not include the three conditien; for acceptability stated above, which the NRC considers inportant to assure the adequacy of these splices, with the following exception. All splices inspected were missing the " nuclear heat-shrinkable cable insula-tion sleeves," as required by paragraph 3.2.15 of the procedure for 600-volt control and instrumentation connections. Due to this recurrent condition, the TRT reviewed the QC inspection reports'for 12 butt splices and found the following:
4 Nine of these splices were documented on the inspection form designated in paragraph 3.3 of the procedure for post-installation inspections instead of on the correct form designated for witnessing-type inspections. It should be noted that all splices were required to be witnessed by QC personnel per paragraph 3.1.d of the procedure. Six of the nine incorrect forms contained handwritten notes by the inspector indicating that he had witnessed the splice; however, no reference was added to indicate that the installation of the heat-shrinkable sleeves was required to be witnessed. The remaining three of the nine incorrect forms did not indicate that the splices had been witnessed. For three splices which were documented on the correct forms, the forms all contained an "N/A" (not applicable) handwritten by the inspector on the line indicating that the installation of the heat-shrinkable sleeve was witnessed. Nuclear heat-shrinkable sleeves are commonly required only in "high radia-tion" areas, and their absence constitutes a condition of nonconformance. The butt splices inspected by the TRT were found inside control, annuncia-
, tor, relay, and termination cabinets which were not located in "high radiation" areas. Thus, the requirement to cover the splices with nuclear heat-shrink?51e 71eeves did not apply to them. However, as indicated l above, the TRT determined that the QC electrical inspectors did not know when installation of the heat-shrinkable sleeves was required to be witnessed. Should butt splices exist in enclosures in "high radiation" areas, the absence of these sleeves would constitute a condition of nonconformance. This lack of awareness of where the heat-shrinkable sleeves should be installed, as reflected in the QC inspection form, when coupled with the high percentage of missed and/or improperly documented inspections requiring witnessing, indicated that craft and inspection personnel lacked familiarity with .iese procedural requirements. This
apparent lack of familiarity may be indicative of poor training. (See Electrical and Instrumentation Category 6, " Electrical QC Inspector Training / Qualification.") ! Nonconformance of Cable Terminations with Drawings. Allegation AQE-12 involves QC inspectors " buying off" terminations that did not conform to drawing requirements. In view of the lack of specific information con-cerning this allegation, the TRT selected 380 cables, involving 1600 individual terminations, and inspected them in detail with respect to drawing requirements. This inspection revealed that six cables (five of which are safety-related) were not terminated in accordance with current drawings. These six cables are: (1) E0139880 in panel CP1-ECPRC8-14, (2) E0110040 in panel CP1-ECPRTC-16, (3) E0118262 in panel CP1-ECPRTC-16, (4) NK139853 in panel CP1-ECPRCB-02 (non-safety),
~. (5) EG104796 in panel CP1-ECPRTC-27, and (6) EG021856 in panel CPX-ECPRCV-01.
Terminal Luas. Allegation AQE-36 involved vendor-installed Amp Product
.. . Corporation (APC) terminal lugs in ITT Goold-Brown Bcveri, 6.9 kV switch-gear being excessively bent in the area between the ring and the barrel, l The TRT discovered 16 NCRs (E-84-01066 through E-84-01031) issued early in April 1984, which documented this condition. The TRT review of TUEC action taken regarding these NCRs revealed the following:
The NCRs described the APC lugs either as being bent in excess of 60 degrees or twisted. l l The documented record of a telephone conversation between TUEC and l the representative of the lug manufacturer (reference letter V8R-16624) stated that lugs bent to 90 degrees one. time were to be considered acceptable; that lugs bent to 120 degrees could be accept-able after utilizing an engineering evaluation by the end-user; and ' l O
that although lugs bent to 120 degrees would not maintain their full mechanic'al strength, they would maintain their electrical character-istics. This acceptance criteria for field bent lugs was changed by APC due to the dispositioning of NCR E-84-00972 regarding the General Electric (GE) motor control center (MCC) thermal overload relay replacement program. The TRT findings regarding the disposition of these NCRs were as follows: The disposition block of the NCR form stated that many of the lugs were " determined not to pose an equipment serviceability problem." However, there was no reference to or evidence of an engineering evaluation, as required by the lug manufacturer prior to a change in the acceptance criteria on NCR E-84-00972. Only the " bent" condition of the lugs was addressed by both the vendor representative and TUEC engineering. Neither the mechanical strength nor the electrical characteristics were ever addressed with respect to " twisted" lugs. The TRT determined that these NCRs were improperly dispositioned in that the full scope of the identified problem was not addressed and the "use-as-is" dispositions were not adequately justified. 5, Conclusions and Staff Positions: The TRT concludes that concerns exist in the following areas relative to cable terminations: The adequacy of butt splices in safety-related panels concerning operability, qualification for service conditions, and reldtive loca-tion of splices to each other (AE-13, AE-18 & AE-22). The acceptability of vendor-installed terminal lugs in ITT Gould-Brown Boveri switchgear (AQE-36). Safety-related terminations which are not in conformance with current drawings (AQE-12).
The adequacy of QC inspections and supporting documentation, parti-cularly with respect to termination activities requiring witnessing by QC personnel.
- 6. Actions Required: TUEC shall accomplish the following actions prior to fuel load:
, (a) Reevaluate and redisposition all NCRs related to vendor-installed l terminal lugs in ITT Gould-Brown Boveri switchgear, taking into con-
! sideration the effects of twisted as well as bent lugs, and perform and document the results of engineering analyses to justify any resulting "use-as-is" dispositions.
(b) Develop adequate installation and inspection procedures to reinspect all existing butt splices to ensure (1) the operability of those l circuits which contain butt splices in panels, (2) that the wire
' splicing materials and methods used are' qualified for anticipated f service conditions, and (3) that splices are staggered within the panel so that they are not adjacent to each other in the same bundle.
(c) Reinspect all safety-related and associated terminations in the con-trol room and in the termination cabinets in the cable spreading room to verify that their locations are in accordance with all current design documents. Should the results of this reinspection reveal an unacceptable level of nonconfermance to design documents, the secpe l of this reinspection effort shall be expanded to include all safety-related anc' associated terminations at Comanche Peak Steam Electric Station (CPSES). (d) Clarify procedural requirements and provide additional QC inspector training with respect to the areas in which nuclear heat-shrinkable sleeves are required on splices and ensure that (1) such sleeves are j installed where required, (2) all QC inspections requiring witnessing i for splices h.we been performed and properly documented, and (3) l l
,-.-g. , _ , - , - , _ - _ -c
4 all butt splices are properly identified on the appropriate design drawings and are physically identified within the appropriate panels. (e) Evaluate the adequacy of the QC inspection program as related to the deficiencies identified above to establish root causes and appro-priate corrective actions. These actions shall be integrated with
! other actions addressed under QA/QC Category 8, "As Built."
^
- 7. Potential Violations: '
(a) Contrary to 10 CFR 50, Appendix B, Criteria VII, X, and XV, vendor-installed or field deficiencies in switchgear wiring were not identi-fied during either source inspection or receipt inspection; and, when subsequently identified during in process inspections, were not adequately addressed and dispositioned. (b) Contrary to 10 CFR 50, Appendix B, Criterion V, safety-related cable terminations were not installed in accordance with current drawings. i (c) Contrary to 10 CFR 50, Appendix B, Criterion X, designated hold points pertaining to witnessing of cable splicing were not properly inspected
. . and documented.
1
- 8. Attachments: None.
! 9. Reference Documents: i 1. Comanche Peak Steam Electric Station (CPSES) FSAR, Section 8. i
- 2. Procedure QI-QC-11.3-28, Revision 21, " Class 1E Cable Terminations."
l l 3. Nonconformance Reports E-84-01066 through E-84-01081.
- 4. QC Inspection Reports: ET-1-0005396 ET-1-0005395 a s s , ,, .,.,e-s. - , + . . , . . . ~ s , ,, 4 ,..
l ET-1-0005394 ET-1-0007162 ET-1-0005393 ET-1-0006776 ET-1-0014790 ET-50419 ET-51218 ET-51217 ET-33666 ET-33669
- 5. Orawings: 2323-El-0171-02, Revision CP-1 2323-El-0171-04, Revision 11 2323-El-0172-16, Revision CP-2 ,
2323-El-0172-27, Revision CP-3 2323-El-0174-12, Revision CP-1 2323-El-0172-02, Revision CP-1 ' 2323-E-1-0174-01, Revision 18 2323-El-0174-03, Revision CP-4 2323-El-0159, Revision CP-3
- 6. Design Change Authorization OCA-19264, Revision 2
- 7. Correspondence from M. Srinivasan, NRC, to B. J. Youngblood, NRC, July 30, 1984.
- 8. IEEE Std. 420-1973, "IEEE Trial-use Guide for Class IE Control Switchboards for Nuclear Power Generating Stations."
- 9. NRC Regulatory Guide 1.75 Revision 2 " Physical Independence of Electric Systems."
- 10. NRC Investigative Report 50-445/82-29 and 50-446/82-15, December 21, 1982.
f I
- 11. NRC Investigative Report 50-445/81-04 and 50-446/81-04, May 5, 1981.
- 12. NRC Inspection Report 50-445/83-24 and 50-446/83-15, August 19, 1983.
+
- 13. TUGCO, et al., Hearing before ASL8, September 15, 1982, page 4871-4877.
- 14. Confidential Affidavit of GAP Witness (Paragraph 6), June 27, 1984,
- 15. GAP Notes of April 1984 (Confidential), GAP Witness H, Paragraphs 6 and 16.
- 16. NRC Inspection Report 50-445/80-16.
- 17. CASE letter to NRC, Region IV, August 4, 1982.
- 18. Deposition of GAP Witness H (In Camera) TUEC's Discovery Deposition, Volume II, July 20, 1984, Pages 339-564.
- 19. Initial Deposition, Telephone Conversation with GAP Witness H, July 31, 1984. ,
- _ . . - . 20. NRC Special Review Team Report, July 13, 1984.
~
- 21. TUGC0 Office Memorandum # TUG-2134, " Transmittal of Final Report on Issues Resulting From Interviews with Electrical Inspectors,"
May 22, 1984.
- 22. Deposition of GAP Anonymous Witness, July 25, 1984, Pages 58,503-58,591.
- 23. Depe,ition of GAP Witness, July 16, 1984, Pages 53,003-53,263.
- 24. NRC RIV Summary of Comanche Peak Open Issues Tracking System, July 13, 1984.
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- 11 ~
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- 25. NRC Constructidn. Appraisal Team (CAT) Inspection Report 50-445/83-18, 50-446/83-12, April 11, 1983. -
- 26. TUGCO',-et al., Hearing before the ASLB, NRC Staff Testimony
" Regarding the Findings of CAT; (June 13, 1983, Pages 7733-7755; June 15,' 1983, Pages 8160, 8231, 8261-8263; June 16, 1983, Pages 8358, 8357, 8368-8373. -
27._ NRC Interview with SRT Alleger A-3, September 6, 1984, Pages 17-27, 30-43, 75-79, 91, 92.
- 10. This statement ;irepared by:
W. Marini ~Date TRT Technical Reviewer ' Reviewed By:
, J. Calvo, Group Leader Date Approved By: '
. V. Noonan,
, Project Director : Date I a Y s b e s
-pk
.~. .. - . - _ _
Docn= ant Mm==- - SSER[2 ELECTRICAL] 4 Requestor's ID: LINDA Author's Name: A. Vietti/kb Document Comuments: 1/10/85 REVISIONS 1 1/2 space N e i I e sg 4 % A me 4 e 4 U e a 4 , . . , , , , _ . , . - . . . . , . . . . - .. . , _ . . . . - , . , , , , ,n-,,._, . .,....-. . . . , . . ,- , , - - - . , . - . . - . - - -
- 1. Allegation Category: Electrical and Instrumentation 2, Electrical Cable Tray and Conduit Installation
- 2. Allegation Number: AE-10, AE-14, AQE-27, AE-29, AE-31 and AH-14.
- 3. Characterization: It is alleged that, in general, there were problems with:
Cable tray suppcrt installation without required design changes (AH-14). Addition of higher sides to cable trays due to overfill (AE-29). Inadequate clearance of process pipes from cables in cable trays (Q&A specification 2323-ES-100, not met) (AE-31). Loose conduit fittings (AQE-27). The adequacy of training of personnel installing conduit supports (AQE-10). The cable tray attachments (clamps) to the seismic supports without approved cesign changes (AE-14, AH-14). Inadequate spacing of the seismic supports for cable trays.(AH-14). Inadequate material traceability for cable tray supports (AH-14).
- 4. Assessment of Safety Significance: The implied safety significance of these allegations is-that the quality of the installation of cable trays and their supports or conduit fittings could be in question.
The NRC Technical Review Team (TRT) determined that the first two concerns (AH-14 and AE-29) related to whether the positions of Regulatory Guide 1.29,
" Seismic Design Classification," as augmented by Final Safety Analysis Report (FSAR) Section 3.2, were considered by the Texas Utilities Electric Company (TUEC) during design of the support systems for both safety-related and nonsafety-related cable trays.
The TRT examined cable tray support installation notes and detail drawings, design change authorizations (DCAs), work packages, physical configuration drawings, and other documents pertinent to its sampling of 29 supports in the Safeguards, Auxiliary, and Control Buildings. The TRT
found no deviations from the acceptable criteria for the installation of supports. Welds were not included in this examination; the inspection of electrical cable tray support welds is addressed under QA/QC Category 8, "As Built." The TRT also evaluated a sample of cable trays in the cable spreading room to assess the concern about the higher cable tray sides. This evaluation and its conclusions are presented in Electrical Instru-mentation Category 7, " Electrical Cable Installation." 1 The third concern (AE-31) related to process pipe-to-caale-tray clearances l not meeting the Gibbs & Hill (G&H) electrical specification 2323-ES-100, as amended by DCA 13045 and DCA 15917. The TRT conducted a walkdown inspection of approximately 2500 feet of cable tray in the auxiliary building and identified 16 cases that appeared not to meet installation l guidelines set forth by the acceptable specification above. However, after an examination of the DCAs pertaining to each of the 16 cases, the TRT determined that the DCAs will satisfactorily correct deviations from specifications in the installations for all 16 cases. The fourth concern (AQE-27) was the "use-as-is" disposition on a non-conformance report (NCR) which reported two 49se conduit elbow fittings on the south and east end of the Unit 1 diesel generator. The TRT
. inspected the Unit 1 diesel generator conduit and found two loose fittings. However, the TRT dete mined that .in the unlikely event of failure of the cables in the loose fittings, the functional capability of the diesel generators would not be affected because those cables were l
not important in the operation of the diesels. The fifth concern (AQE-10) was the lack of training of personnel installing conduit supports. The TRT interviewed craft personnel, craft supervisors, and training personnel to determine the availability and effectiveness of the training program, and found that there was a training program for newly hired personnel or transfers into the installation. This training program included periodic briefings on procedure changes. The interviews revealed that the training program was not effective because 7 of the 11 crew
members interviewed were not cognizant of Manual 2323-S-0910, " Conduit and Junction Box Supports," which is the primary reference manual for installa-tion of supports. Although these seven crew members indicated that they had no need to use this manual in their job assignments, the TRT could not substantiate this assertion, Hence, the lack of awareness of this proce-dure by craft personnel'may be indicative of poor training in the area of procedural requirements. Similar findings in other construction crafts are addressed under QA/QC Category 8, "As Built." The sixth concern (AE-14, AH-14) was that cable tray attachments (clamps) to the seismic supports were not installed according to design. The TRT inspected 60 cable tray attachments in the Safeguards Building and found no unacceptable cable tray attachments in the sample. The seventh and eighth concerns (AH-14) were that the designed spacing of the seismic cable tray supports was not adhered to during construction and that the supports did not have proper material traceability. The TRT conducted a walkdown inspection of seismic cable tray supports in the Safeguards and Auxiliary Buildings, a.id compared the installed cable tray support spacing with the designed support spacing, including identifica-tion of material traceability for the supports. Two deviations in support spacing were located out of 40 examples inspected. The TRT asked TUEC engineering to provide the analyses for these two deviations because they were outside the designed support spacing. A review of TUEC's documenta-tion of analyses indicated that the spacing maintained was adequate to meet regulatory requirements.
- 5. Conclusion and Staff Positions: Based on the review of engineering drawings and direct inspection of the installation, the TRT found no indication of construction which was contrary to commitments made in the ,
FSAR Section 3.2, as related to AH-14, AE-29. The TRT determined that DCAs 13045 and 15917 will satisfactorily correct the process pipe-to-cable tray clearance deviations from specification 2323-ES-100 for every case identified during the walkdown inspection (AE-31). The TRT found
no problems with cable tray attachments (clamps) to seismic supports (AH-14, AE-14). The TRT determined that the cable tray support spacing meets design requirements and has prope- identification for material traceability, except for two deviations concerning support spacing wnich were previously analyzed by TUEC. These analyses were found to be jg acceptable by TRT (AH-14). With regard to loose conduit fittings hE-27),theTRTconcludesthatthedeficiencyraisedbytheNCRhasno safety significance; therefore, the NCR was properly dispositioned. The TRT concludes that the concern highlighted by AQE-10 may be indicative of poor training in the area of procedural requirements.
- 6. Actions Required: Prior to fuel load TUEC shall accomplish the following action:
Evaluate the adequacy of craft personnel training in the use of installa-tion manuals to establish root causes and appropriate corrective actions. This action shall be integrated with other actions concerning craft personnel training addressed under QA/QC Category 8, "As Built."
- 7. Potential Violations: None.
- 8. Attachments: None. -
- 9. Reference Documents:
- 1. Regulatory Guide 1.29, " Seismic Design Classification."
- 2. Comanche Peak, Units 1&2, FSAR Section 3.2.
- 3. G&H Specification No. 2323-ES-100, Revision 2, " Electrical Erection Specification."
- 4. RIV Inspection Report 50-445/83-52.
- 5. DCA 13045 and DCA 15917.
- 6. G&H Specification 2323-5-0910, " Conduit and Junction Box Supports."
- 7. Drawing 2323-El-602-01-S, " Safeguard Bldg Cable Tray Support Plan."
- 8. Drawing 2323-El-701-01-S, " Auxiliary Bldg Cable Tray Support Plan."
- 9. Drawing 2323-S-0901 sheet (sh) 1, " Cable Tray Supports."
- 10. Drawing 2323-S-0902-sh 2, " Cable Tray Supports."
- 11. Drawing 2323-S-0903-sh 3, " Cable Tray Supports."
- 12. Drawing 2323-S-0904-sh 5, " Cable Tray Supports."
- 13. Drawing 2323-5-0916-sh 15, " Cable Tray Supports."
- 14. Drawing 2323-5-0930-sh 28, " Cable Tray Supports Alternate Heavy Duty Tray Clamp Details."
- 15. Drawing FSE-00187, " Safeguard Bldg Cable Tray Support Plan El 810'-6 inches."
- 16. Drawing FSE-00188, " Auxiliary Bldg Cable Tray Support Plan El 810'- 6 inches."
- 17. Drawing FSE-00214, " Auxiliary Bldg Cable Tray Support Flan EL 807'-0 inches."
- 18. Drawing FSE-00159-sh 1317, " Safeguard (SiGD) Bldg Cable Tray Hanger Assembly (Assy)."
- 19. Drawing FSE-00159-sh 925, "SFGD Bldg Cable Tray Hanger Assy."
- 20. Drawing FSE-00159-sh 1109, "SFGD Bldg Cable Tray Hanger Assy."
- 21. Drawing FSE-00159-sh 1080, "SFGD Bldg Cable Tray Hanger Ar.y."
- 22. Drawing FSE-00159-sh 1070, "SFGD Bldg Cable Tray Hanger Assy."
i
- 23. Drawing FSE-00159-sh 1047, "SFGD Bldg Cable Tray Hanger Assy."
- 24. Drawing FSE-00159-sh 5553, "SFGD Bldg Cable Tray Hanger Assy."
- 25. Drawing FSE-00159-sh 904, "SFGD Bldg Cable Tray Hanger Assy."
- 26. Drawing FSE-00159-sh 1076, "SFGD Bldg Cable Tray Harger Assy."
- 27. Drawing FSE-00159-sh 912, "SFGD Bldg Cable Tray Hanger Assy."
- 28. Drawing FSE-00159-sh 1048, "SFGD Bldg Cable Tray Hanger Assy."
- 29. Drawing FSE-00159-sh 1313, " Aux Bldg Cable Tray Hanger Assy."
- 30. Drawing FSE-00159, sh 12454, " Aux Bldg Cable Tray Hanger Assy."
- 31. Drawing FSE-00159, sh 5326, " Aux Bldg Cable Tray Hanger Assy."
- 32. Drawing FSE-00159, sh 1316, " Aux Bldg Cable Tray Hanger Assy."
- 33. Drawing FSE-00159, sh 13062, " Aux Bldg Cable Tray Hanger Assy."
- 34. Drawing FSE-00159, sh 13193, " Aux Bldg Cable Tray Hanger Assy."
- 35. Drawing FSE-00159, sh 5335, " Aux Bldg Cable Tray Hanger Assy."
l 36. Drawing FSE-00159, sh 4237, " Aux Bldg Cable Tray Hanger Assy." l
- - . - . . - - - _ - . . _ . . - , . _ . - , - - , - . . - , - - _ . - - --._-,.m e. , % --, -
1
- 37. Drawing FSE-00159, sh 4210 " Aux Bldg Cable Tray Hanger Assy."
- 38. Drawing FSE-00159, sh 1296, " Aux Bldg Cable Tray Hanger Assy."
- 39. Drawing FSE-00159, sh 3918, " Aux Bldg Cable Tray Hanger Assy."
- 40. Drawing FSE-00159, sh 6477, " Aux Bldg Cable Tray Hanger Assy."
- 41. Drawing FSE-00159, sh 4114, " Aux Bldg Cable Tray Hanger Assy."
- 42. Drawing FSE-00159, sh 4115, " Aux Bldg Cable Tray Hanger Assy."
- 43. Drawing FSE-00159, sh 4116, " Aux Bldg Cable Tray Hanger Assy."
- 44. Drawing FSE-00159, sh 4117, " Aux Bldg Cable Tray Hanger Assy."
- 45. Drawing FSE-00159, sh 4352, " Aux Bldg Cable Tray Hanger Assy."
- 46. Drawing FSE-00159, sh 4368, " Aux Bldg Cable Tray Hanger Assy."
- 47. NRC OI Report 4-83-013, November 3, 1983, Page 8, Paragraph 3 and 4.
- 48. NRC Inspection Report 50-445/83-52, February .?l, 1984.
- 49. NRC Report of Inquiry No. Q4-83-023, September 20, 1983.
- 50. NRC Report of Inqui? No. Q4-83-021, August 29, 1983.
- 51. GAP Notes of April 1984 (Confidential) Paragraph 33, GAP Witness Anonymous and Paragraph 4, GAP witness C.
- 52. NRC Special Review Team Report, July 13, 1984.
- 53. TUGC0 Office Memorandum # TUG-2134, " Transmittal of Final Report on Issues Resulting From Interviews with Electrical Inspectors,"
May 22, 1984.
- 54. NRC RIV Summary.of Comanche Peak Open Issues Tracking System,
. July 13, 1984.
- 55. NRC Interview with SRT A11eger A-3, September 6, 1984, Pages 49-50.
- 10. This statement prepared by:
G. Myers, Date TRT Technical Reviewer Reviewed by: J. Calvo, Group Leader Date Approved by: V. Noonan, Project Director Date
- - - - . , --. - -- - . - , - -.-- - - , , ,. -n . , ,-e--,-
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- 1. Allegation Category: Electrical and Instrumentation 3, Electrical Equipment Separation 4
- 2. Allegation Number: AQE-6, AQE-11, AE-15, AE-20, AQE-49, AE-51, AE-53, AQE-54 and Part of AQE-44.'
- 3. Characterization: It is allegcd that:
Installation of safety related cables and conduits inside the reactor control panels in the main control room did not conform to the cable separation criteria (AE-15). Separation between independent safety-related cable trays and con-duits, and between them and consafety-related trays and conduits in the cable spreading room did not conform to the positions set forth in Regulatory Guide (RG) 1.75, " Physical Independence of Electric l- . Systems." It is also alleged that the separation requirements in Gibbs & Hill (G&H) specification 2323-ES-100, " Electrical Erection Specification," applicable to the cable installation in the cable spreading room, was inconsistent with the separation criteria in the Institute of Electrical and Electronics Engineers (IEEE) Standard 384-1974, "IEEE Trial-Use Standard Criteria for Separation of Class 1E Equipment and Circuits," as augmented by RG 1.75 (AE-20). Ladder type cable trays did not qualify as acceptable barriers; therefore, the 1-inch minimum separation criteria between separate trays.and conduits routed under the trays are not. applicable (AQE-54). Nonconformance Report (NCR) E-84-007095 was dispositioned to achieve the required separation between conduits ESB1-4 and C14K30975 without approved conduit bending equipment (AE-53). e
,,_,,,.-,--.-.-,--,----r--
-v' ' =' ' ' " ' " " ' ' ' ' ' ' " " " ' ~ ~ ~ * " ~ ~ " ' " ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ' ' ~ ~ ~ ~ ~
l Post-construction inspection of electrical equipment and raceways in l the Fuel Handling Building concerning a cable separation problem was dispositioned "use-as-is" (part of AQE-44). Conduit 22G06343, located in the Control Room Building at the 854-foot elevation, was about 3 feet below cable tray T130CCP38 and thought to violate separation criteria (AE-51). Inspection of the separation of cables did not follow established procedures (AQE-6); quality control (QC) inspection acceptability regarding separation of equipment may have been compromised to meet the needs of production management (AQE-11); and, in numerous cases rework was done to obtain proper separation (AQE-49). These three allegations, in very general terms, raise concerns with cable separation, but do not specifically identify the location of problem areas in the facility. The following discussion will focus on the specific installation concerns of cable separation raised by the allegations. However, the concerns highlighted by AQE-6, AQE-11 and AQE-49 were pursued during the review and inspection of cable separation installations in the various areas of the plant inspected. Therefore, the NRC Technical Review Team (TRT) findings concerning cable separation disposed of both specific and general concerns raised by the allegations. Quality assurance / quality control (QA/QC) matters raised by allegation AQE-6 are addressed under Electrical and Instrumentation Category 8, " Electrical Procedures."
- 4. Assessment of Safety Significance: The implied safety significance of these allegations is that lack of separation may result in a loss of redundancy during design basis accidents and a loss of capability to mitigate the consequences of accidents or to achieve safe shutdown.
l l l
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Control Room Panels (AE-15, AE-20, AQE-6, AQE-11, and AQE-49). The cri-teria governing the separation of cables insidd panels are stated in Section 5.6.2 of IEEE Standard 384-1974, which is endorsed by RG 1.75. Sections 7.1.2.2 and 8.3.1.4 of the Final Safety Analysis Report (FSAR) commit Texas Utility Electric Company (TUEC) to these criteria. t Section 5.6.2 of IEEE Standard 384 states, in part, that the minimum separation distance between redundant Class 1E equipment and wiring internal to the control switchboards (panels) can be established by analysis of the proposed installation. Where the control switchboard materials are flame retardant and analysis is not performed, the minimum separation distance shall be 6 inches. In the event these separation distances are not maintained, barriers shall be installed between re-dundant Class 1E equipment and wiring. The criterion spee.ifying a 1-inch separation between redundant conduits which are considered enclosed raceways is stated in Section 5.1.3 of IEEE Standard 384. The TRT examined the electrical erection specifications, cable and raceway separation engineering drawings, design change authorizations (DCAs), work packages, and other documents pertinent to the separation of cables, conduits, and devices inside the main control room panels. The TRT also inspected cables, flexible conduits. terminations, and devices inside six safety-related panels to determine that this- equipment was installed in accordance with established separation requirements. In addition, the TRT inspected the separation of cable trays and rigid conduits entering the bottom of the panels from the cable spreading room. The TRT found that the minimum 6-inch air gap or fire retardant barrier between redundant Class IE panel-mounted devices (including their cable or wire connections) and nonsafety-related devices and their connections was maintained in all six panels inspected, except for an instance where a fire-retardant barrier had been removed. The devices involved were FI-2456A, PI-2453A, PI-2475A, and IT-2450, associated with train A, and
FI-2457A, PI-2454A, PI-2476A, and IT-2451, associated with train B. These devices were located in auxiliary feedwater panel CP1-EC-PRCB-09. The TRT also found (in panel CP1-EC-PRCB-03, adjacent to the six panels inspected) another instance of redundant safety-related field wiring not being separated by either the 6-inch minimum distance or by a barrier. The field wiring was associated with devices HS-5423 (train B) and HS-5574 (nonsafety related). The TRT found no deficiencies in the separation of cable trays and rigid conduits entering the bottom of the control room panels. l The TRT found several instances where (1) redundant safety-related flexi-ble conduits inside the panels were in direct contact with each other and (2) safety and nonsafety-related flexible conduits inside the panels were in direct contact with each other. The TRT also found various cases where safety and nonsafety-related cables were in direct contact with safety-related cables within flexible conduits associated with the other redundant train inside the panels. These are identified in Table 1. Table 1 Safety or Nonsafety-Related Cables in Contact with Other Safety-Related Conduits in Control Room Panels
- 1. Control Panel CP1-EC-PRCB-02: Containment Spray System Cable No. Train Related Instrument EG139373 8 (green) Undetermined E0139010 A (orange) Undetermined 9
I 1 Table 1, continued
- 2. Control Panel CP1-EC-PRCB-07: Reactor Control i
l Cable No. Train Related Instrument EG139383 8 (green) Reactor manual trip switch E0139311 A (orange) Undetermined E0139310 A (orange) Undetermined EG139348 8 (green) Undetermined
- 3. Control Panel CP1-EC-PRCB-06: Chemical and Volume Control System Cable No. Train Related Instrument EG139335 8 (green) LCV-112C E0139301 A (orange) Undetermined E0139305 A (orange) LCV-1128 NK139605 Nonsafety CSALB-LAB (in bundle)
- 4. Control Panel CP1-EC-PRCB-09: Auxiliary Feedwater Control System Cable No. Train Related Instrument E0139753 A (orange) FK-2453A E0139754 A (orange) FK-2453B EG139756 8 (green) FK-2454A EG139288 8 (green) FK-24548 EG145780 8 (green) FK-2454A .
EG145781 B (green) FK-2460A A0138622 A (orange Assoc.) HS-2452a/H NK139647 Nonsafety HS-2383 1 __
Table 1, continued
- 5. Control Panel CP1-EC-PRCB-08: Feedwater Control Cable No. Train Related Instrunent EG140309 8 (green) PK-2324 EG139757 8 (green) PK-2328 l NK13' < Nonsafety HS-211A The TRT uiscussed with TUEC and G&H representatives the apparent violation of the required 1-inch separation between separate flexible conduits and 6-inch separation between separate cables and cables within flexible con-duits inside the panels. TUEC and G&H representatives indicated that redundant flexible conduits in contact with each other were permitted, as indicated in the cable and raceway separation typical details drawings, but cables in contact with cables within flexible conduit were not per-mitted. However, the TRT brought to the attention of the TUEC and G&H representatives that this type of conduit installation is permitted by Section 5.6.2 of IEEE Standard 384 if such installation can be substan-tiated by analysis. The TRT considered the apparent discrepancies described above to be a deviation from the engineering drawings and inconsistent with regulatory requirements.
Cable Spreading Room (AE-20, AQE-6, AQE-11, and AQE-49). The criteria governing the separation of redundant safety-related cable trays and con-duits in the cable spreading room appear in Section 5.1.3 of IEEE Standard 384-1974, as augmented by RG 1.75. IEEE Standard 384 states, in part, that the minimum separation distance between redundant Class 1E cable trays in the cable spreading area can be determined by analysis of the proposed cable installation or, where the conditions of Section 5.1.1.3 (which defines an acceptable tray system) are met, there shall be 1 foot between trays separated horizontally and 3 feet between trays separated vertically. Where the minimum separation distance cannot be met, the redundant circuits shall be run in enclosed raceways ttat qualify as 1 l
barriers, or other barriers shall be provided between redundant circuits. The minimum distance between these redundant enclosed raceways and between barriers and raceways shall be 1 inch. The TRT compared these criteria to the requirements set forth in G&H electrical erection specifications and engineering drawings, concerning cable tray and conduit separation in the cable spreading room, and identified no deviations. The TRT also examined DCAs, work packages, and other documents pertinent to this issue. In addition, the TRT directly inspected the installation of numerous cable raceways and five termination cabinets in the cable spread-ing room. The TRT found no deviations from separation requirements in the cable raceways and termination cabinets inspected. Fuel Handling Building Area (Part of AQE-44, AQE-6, AQE-11 and AQE-49). The TRT inspected the cable separation installation in the Fuel Handling Building area and found that most of the cable trays and conduits were designated as nonsafety related. The only safety-related electrical equip-ment installation in the fuel building area that needed to satisfy separ-ation requirements was associated with the spent fuel system. The TRT l - found that redundant spent fuel system equipment was located in separate adjacent rooms, except for a common control panel. After examining the separation of cable raceways in the fuel building area and terminations and the cables, wires, and devices inside the common control panel, the TRT found no deviations from separation requirements, i Potential Harsh Environment Areas (AQE-6, AQE-11, and AQE-49). The TRT examined cable separation installations in those areas of the plant where a high-energy line break could compromise the independence of redundant safety-related equipment. TUEC's damage study group performed studies to determine the need to protect equipment, including cable raceways, that
- could be affected by a high-energy line break. Jet shields were installed to protect safety-related raceways, as required. In the areas where the
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i l installation of jet shields was not possible, the affected cable raceways were to be rerouted. The TRT inspected two typical jet shield installations located in the chemical and volume control system (CVCS) piping and valve area and steam generator blowdown area and found that cable separation in these two areas . was in accordance with IEEE Standard 384-1974, as augmented by RG 1.75. - t Remote Shutdown and Transfer Switch Panel Areas (AE-15, AE-53, AQE-6, 1 AQE-11, and AQE-49). The TRT reviewed engineering drawings and electrical erection specifications pertinent to the separation of the safety-related equipment located inside the remote shutdown and transfer switch panels. The TRT also inspected the cables, wires, and devices (including their cables and wire connections) inside these two panels and cables entering the top of the panels to determine whether this equipment was installed in accordance with established separation requirements. The TRT found no deviations from separation requirements in these two panels. NCR E-84-007095 concerns the separation between two specific conduits (AE-53) located in the Unit 1 safeguard area established by bending the conduits with unapproved bending equipment. The TRT determined that both conduits dispositioned "use as is" in the NCR were nonsafety-related and concurred with the "use as is" disposition. - , 1 l Electrical Erection Specification for Separation Criteria (AQE-6, AQE-54, and AE-51). The criteria set forth in IEEE Standard 384-1974, as aug-mented by RG 1.75 and Sections 7.1.2.2 and 8.3.1.4 of the FSAR, have been expressed in specific terms in G&H specification 2323-ES-100, " Electrical l Erection Specification." It is alleged that the requirements set forth in this specification governing the separation between independent trays and rigid conduits is inconsistent with the criteria stated in IEEE Standard 384-1974, as augmented by RG 1.75, particularly when ladder type trays and conduits were used as barriers to maintain a 1-inch minimum separation between separate trays and conduits routed under the trays.
9-During its assessment of this allegatf ori, the TRT found a requirement in the electrical erection specification that permitted nonsafety related rigid conduits to have a minimum separation of 1 inch from the top of open safety related trays. These requirement appear inconsistent with the aforementioned standard and guide. The TRT determined that no inforeation was included in the FSAR that supported the 3-inch separation between trays and conduits which is at variance with the requirements of IEEE Standard 384-1974 and RG 1.75. However, the TRT reviewed an existing G&H analysis, including test results, which was used to establish the requirements set forth in specification 2323-ES-100 for a separation of 1 inch between conduits and trays (G&H memorandum EE-863, January 17, 1984, " Cable Tray Ccnduit Separations"). In essence, the analysis concluded that rigid conduits constituted an acceptable barrier by themselves between the cables inside the conduit and cables inside ladder or open-type trays. Based on the review of electrical specifications, engineering drawings and analyses, inspection reports, precedures, and other pertinent docu-ments and on direct inspection of the installation of cables, conduits, cable trays, terminations and panels in the main control room, cable spreading room, Fuel Handling Building area, potential harsh environment areas, and remote shutdown and transfer switch panel areas, the TRT deter-miped that in general the requirements set forth in IEEE Standard 384, as augmented by RG 1.75 and Chapters 7 and 8 of the FSAR, were satisfied in the areas inspected, except for the following items: The TRT could find no evidence that an analysis was performed to support the practice that allowed certain separate safety- and nonsafety-related flexible conduits inside control room panels to be in direct contact with each other or to be separated by less than 1 inch, as required by Section 5.6.2 of IEEE Standard 384 (AE-15). 9
The TRT determined that the installation of certain safety- or nonsafety-related cables inside control room panels, which were in direct contact with safety related flexible conduits associated with the other redundant trains (see Table 1), was inconsistent with engineering drawings and regulatory requirements (AE-15 and AQE-6). Because acceptability of the flexible conduit as a barrier was not established by analysis, as required by Section 5.6.2 of IEEE Standard 384, the cables must be separated from the conduits inside the panels by a minimum distance of 6 inches, as required by Section 5.6.2 of IEEE Standard 384. The TRT determined that the missing barrier (used to separate redun-dant devices in auxiliary feedwater panel cpl-EC-PRCB-09) and the field wiring not being separated by the required 6 inches (inside panel CP1-EC-PRCB-03) were the only two instances of Class IE panel-mounted devices in violation of the separation criteria which require
. ' corrective action.
, The TRT found no evidence that the existing G&H analysis for estab-l lishing the criteria for a 1-inch separation between rigid conduits and cable trays, as stated in G&H Electrical Erection specification 2323-ES-100, had been evaluated by the NRC staff for Comanche Peak. This analysis should have been referenced in the FSAR.
- 5. Conclusions and Staff Positions: The TRT concludes that the installations reviewed, in general, meet established separation requirement, except for certain safety- and nonsafety-related cables and flexible conduits inside '
control room panels which did not meet minimum separation requirements * (AE-15). The TRT found no evidence that the lack of separation was justified by analysis. The TRT also concludes that in the absence of analysis to support the lack of minimum separation between separate flexible conduits inside the main control room panels, the existing design arrangement is in violation of regulatory requirements. Furthermore, the lack of separation in the installation of certain cables and flexible e
conduits is also inconsistent with TUEC's engineering drawings and documents (AQE-6). The lack of analysis to substantiate the adequacy of separation in the above cases may be an indication of weakness in the QA/QC program concerning design control. This area is addressed in QA/QC Category 1, " Design Process." The 14T concludes that the unjustified installation of cables and flex-ible conduits inside panels that do not meet minimum separation require-ments has potential generic implications. I In regard to the criteria for 1-inch separation between rigid conduits and cable trays stated in G&H specification 2323-ES-100 (AQE-54 and AE-51), the TRT concludes that the analyses performed by G&H to support acceptabil- > ity of these criteria require NRC evaluation. The present FSAR contains no reference to this analysis. The TRT also concludes that the missing barrier in the auxiliary feedwater panel and the field wiring not being separated by the required 6 inches are two isolated instances of nonconformance and do not have generic implications. The TRT findings on cable separation may be indicative of poor QC per-sonnel training in procedural requirements for installation and inspection. This subject is further addressed under Electrical and Instrumentation Category 6, " Electrical QC Inspector Training and Qualifi-cations." Similar findings in other installations are addressed under QA/QC Category 8, "As Built." -
- 6. Actions Required: TUEC shall accomplish the following actions prior to fuel load:
(a) Reinspect all panels at Comanche Peak Steam Electric Station, in addition to those in the main control room for Units 1 and 2, that i contain (1) redundant safety-related conduits, or (2) safety and I nonsafety-related conduits. TUEC shall either correct each violation
of the separation criteria or demonstrate by analysis the accept-ability of the conduit as a barrier for each case where the minimum separation is not met. This analysis shall be accomplished in accordance with the requirements specified in Section 5.6.2 of IEEE Standard 384-1974. Furthermore, in the event that the acceptability of the conduit as a barrier cannot be demonstrated, TUEC shall correct the engineering drawings and related documents to indicate the revised minimum separation of conduits inside the panel for each case. (b) Either correct each of the violations of separation criteria con-cerning separate cables and cables within flexible conduits found in contact with each other inside main control room panels (Table 1) or demonstrate by analysis the adequacy of the flexible conduit as a barrier. TUEC shall also reinspect all remaining panels in the con-trol room and other areas of the plant containing separate cables and cables within flexible conduit and shall take the same corrective actions as those outlined in Table 1. This analysis shall be accomplished in accordance with Section 5.6.2 of IEEE Standard 384-1974. In the event that the acceptability of the concuit as a barrier cannot be demonstrated, TUEC shall separate cables and cables within flexible conduits by a minimum distance of 6 inches, as required by Section 5.6.2 of IEEE Standard 384. Fur-thermore, TUEC shall correct all appropriate drawings and documents to indicate the revised minimum separation. (c) Take corrective measures to provide a barrier in auxiliary feedwater panel CP1-EC-PRCB-09 separating redundant flow and pressure instruments. (d) Take corrective action to ensure that the required minimum separation of the redundant field wiring identified inside panel CP1-EC-PRC8-03 is maintained either by distance or by an acceptable barrier.
(e) Submit to the NRC the analysis substantiating the acceptability of the criteria stated in G&H electrical erection specification govern-ing the separation between separate conduits and cable trays. This analysis shall be supported with the necessary documentation in sufficient detail to perform an independent evaluation of how these criteria were established based on the analysis. (f) Evaluate the adequacy of the QA/QC program as related to the defi-ciencies identified above to establish root causes and appropriate corrective actions. These actions shall be integrated with other actions addressed under Electrical and Instrumentation 6, " Electrical QC Inspector Training and Qualifications," QA/QC Category 8, "As Built," and QA/QC Category 1, " Design Process."
- 7. Potential Violations: Contrary to the requirements set forth in Section 5.6.2 of IEEE Standard 384-1974, there is no evidence that analyses were performed to demonstrate the acceptability of flexible conduit as a barrier inside panels installed when the minimum distance between separate flexible conduits or between separate cables and flexible conduits cannot be met.
. 8. Attachments: None.
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- 9. Reference Documents:
- 1. Regulatory Guide 1.75, Revision 2. " Physical Independence of Electric Systems."
- 2. IEEE-384-1974, "IEEE Trial- Use Standard Criteria for Separation of Class 1E Equipment and Circuits."
- 3. Comanche Peak, Units 1 and 2 FSAR, Section 7.1.2.2, " Independence of Redundant Safety-Related Systems" and Section 8.3.1.4, " Independence of Redundant Systems."
- 4. G&H Specification No. 2323-ES-100, Revision 2 " Electrical Erection Specification."
- 5. G&H Drawing No. 2323-El-1702-02, Revision 2, " Cable and Raceway Separation Typical Details."
- 6. Drawing No. 2323-El-1701, Revision 11, " Conduit cable Tray Legend, General Notes and Typical Details."
.. 7. G&H Specification 2323-MS-38H, " Fire-Retardant Barriers and Materials'." .
- 8. Nonconformance Report No. E-84-007095.
- 9. Design Change Authorization No. 8830, October 22, 1983,
" Specification 2323-ES-100, Revision 4."
- 10. Design Change Authorization No. 13,435, Revision 2, " Specification 2323-ES-100, Revision 1."
- 11. G&H Memorandum EE-863, January 17, 1984, " Cable Tray Conduit Separation."
t
- 12. NRC Investigative Report 50-445/81-04 and 50-446/81-04, May 5, 1981.
- 13. Deposition of GAP-Witness H (In Camera) TUEC's Discovery Deposition, Volume II, July 20, 1984, Page 419; Page 10 and 12 of Affidavit.
- 14. Deposition of SRT Witness A-5., July 17, 1984, Pages 55032-55033. ,
- 15. GAP Notes of April 1984 (confidential), Paragraph 7, GAP Witness H.
- 16. Confidential Affidavit of GAP Witness H, July 16, 1984, Pages 10-11. !
- 17. Pre-filed Testimony before ASLB, May 24, 1982, Page 80. ,
- 18. Enclosure to NRC OI Report, 4-84-006, March 7, 1984, Pages 57-59.
Deposition of A-7.
- 19. NRC Special Review Team Report, July 13, 1984.
- 20. Initial Deposition, Telephone Conversation with GAP Witness H, July 31, 1984.
- 21. TUGC0 Office Memorandum # TUG-2134, " Transmittal of Final Report on
, Issues Resulting From Interviews with Electrical Inspectors" May 22, 1984.
- 22. NRC Inspection Report 50-445/84-10, June 21, 1984.
- 23. Deposition of GAP Anonymous Witness, July 25, 1984, Pages !
58503-58591.
- 24. TUGCO, et al, Hearing before the ASLB, GAP Witness F, September 9, ;
1984 (In Camera), Pages 14719-14722. i 4 s
- 25. NRC Construction Appraisal Team (CAT) Inspection Report 50-445/83-18, 50-446/83-12, April 11, 1983.
- 26. TUGCO, et al, Hearing before the ASLB, NRC Staff Testimony Regarding the Findings of CAT; (June 13, 1983, Pages 7733-7755; June 16, 1983, Pages 8358, 8367, 8368-8373.
- 27. TUGC0 Procedure No. QI-QP-11.3-29. Revision 15, January 18, 1984,
" Electrical Separation."
- 28. TUGC0 Procedure No. QI-QP-11.3-29.1, Revision 15, February 15, 1984,
" Verify Electrical Separation."
- 29. TUGC0 Procedure No. QI-QP-11.3-40, Revision 18, May 18, 1984, "Postconstruction Inspection of Electrical Equipment and Raceways."
- 30. NRC Interview with SRT A11eger A-3, September 5,'1984, Pages 53-56, 62-64, 83.
- 10. This statement prepared by:
. A. Johnson, Date TRT Technical Reviewer H. Li, Date TRT Technical Reviewer Reviewed by: ,
J. Calvo, Group Leader Date Approved by: V. Noonan, Project Director Date
Document Name: SSER AE-17 Requestor's ID: LINDA Author's Name: A. Vietti/kb Document Comments: 1/10/85 Redraft Electrical 4 REVISED 9/29 HQ) O
/
4
- 1. Allegation Category: Electrical and Instrumentation 4, Control Room s
Ceiling Fixture Supports
- 2. Allegation Number: AE-17 1
- 3. Characterization: It is alleged that the field run conduit, drywall, and lighting installed in the area above ths equipment panels in the control room were classified as nonseismic, and as such were only supported by wires.
- 4. Assessment of Significance: The implied safety significance is that the seismic qualification of certain equipment located above the ceiling in the control room could be indeterminate and consequently its behavior during a seismic event could not be predicted.
The central concern of this allegation is whether Texas Utilities Electric ' Company (TUEC) considered the positions of Regulatory Guide (RG) 1.29,
" Seismic Design Classification," as augmented by' Final Safety Analysis Report (FSAR) Section 3.2.1.2, " Seismic' Category II," during the oesign of tb.e support systems in the control room for the nonsafety-related field run conduit, for the suspended drywall ceiling, and for the lighting fixtures. '
Regulatory Guide 1.29 states that nonsafety-related structuras, systems, or components whose failures could reduce the functioning of any plant feature to an unacceptable safety level or could re: ult in incapacitating injury to occupants of the control room shuuld be aesigned and constructed so that the safe shutdown earthquake (SSE) would.not casse such failure. FSAR Section 3.2.1.2 provides TUEC's commitments tu these positions, and designates as seismic Category II the nonsafety-related equipment that will be encompassed by the positions of RG 1.29. Field Run Conduit. The NRC Technical Review Team (TRT) examined conduit seismic installation notes and detail drawings, design change author-izations (DCAs), work packages, physical configurstion drawings and other 4 m_i
1 r documents pertinent to this issue. The TRT also inspected conduit installation in the area above the control room ceiling and determined that the safety-related conduit was fastened by seismic Category I supports typical of those used in other areas of the facility. The nonsafety-related conduit was secured by supports which were of a dif-ferent design than those for safety-related conduit. None of the non-safety-related conduits examined by the TRT were greater than 2 inches in diameter. In addition, they were not supported by seismic Category I supports and did not have seismic Category II cable restraints. The TRT determined that engineering drawing 2323-5-0910, " Conduit and Junction Box Supports," did not require seismic Category II cable restraints for nonsafety related conduits less than or equal to 2 inches in diameter, but required it for conduits greater than 2 inches in diameter. The TRT also examined similar nonsafety-related conduit installations in other seismic Category I areas of Unit 1 and found that seismic Category II stainless steel cable restraints were used as backup to the nonseismic dead weight supports for the conduits greater than 2 inches in diameter. The TRT staff also found that the installation of nonsafety-related conduit less than or equal to 2 inches in diameter in the control room was consistent-with that used throughout the plant. Suspended Drywall Ceiling. The TRT found that the suspended ceiling above the central part of the control room was made of drywall sheets arranged to form a sloping wall around that area. These drywall sheets were fastened to a metal framework (metal batten) supported by thin-walled channels (1-1/2-inch by 1/2-inch) attached to the primary building concrete. The metal framework was also attached to the concrete by a system of 1/8-inch stainless steel cables such that if the thin-walled channel supports failed daring a seismic event, the weight of the framing and drywall Would be assumed by the Cabling. i i 1 9
, ,p , s. ,--,----e- ---y,---,an ,- -- , - ., - - - - - - - - - . - - - -
F
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Lighting Fixtures. The TRT reviewed the installation of the lighting fixtures over the control panels'and central part of the control room and found that they were supported from an intermediate substructure of "unistrut" by light-weight conduit. The substructure was likewise supported by light-weight conduit from the primary building ceiling. The conduit used is typical of that supporting the light fixtures in suspended ceiling applications. Parallel with each lighting support conduit are two 1/8-inch stainless steel cables which would assume the load if the support conduit or its attachment were to fail. Other individual light and reflector assembly fixtures, separate from those supported by the intermediate "unistrut" substructure, were secured by a similar type of conduit and backup cable design arrangement with the cable attached to the edge of the light reflecto: assembly. Based on the review of enginedring drawings and direct inspection of the installation, the TRT determined that.the positions of RG 1.29, as augmented by FSAR Section 3.2.1.2, were met by the installation,of the
. fixtures located in the area above the panels and central part of the control room. -
As discussed above,- the nonsafety-related conduit in the area above the control room suspended ceiling was not fastened by seismic Category I supports and/or seismic Category II cable restraints. With regard to the suspended drywall ceiling, it appeared that the installation met TUEC commitments to the positions of RG 1.29. However, the' final resolu-tion of this technical issue, including the nonsafety-related conduit ' support system, will depend on the review and approvaJ by the TRT of an-analysis to be provided by TUEC concerning the adequacy of the seismic support system installation in the control room. The TRT inspected selected seismic Category I areas of the plant, reviewed associated engineering drawings, and determined that only nonsafety-related conduits of less than or equal to 2 inches in diameter were not fastened . by seismic Category II cable restraints.
- 5. Conclusions and Staff Positions: The TRT concludes that the installation of the nonsafety-related conduit in the control room appears to be inconsistent with the positions of RG 1.29. Accordingly, this part of the allegation is of concern. With regard to the suspended ceiling and lighting supports, the acceptability of the installation will depend on the approval by the TRT of the analysis to be provided by TUEC concerning the adequacy of the seismic Category II restraints in the control room.
This technical issue, including the nonsafety-related conduit support system, will be resolved after the review of TUEC's seismic analysis substantiating the adequacy of the overall seismic support system installa-tion in the control room. The results of the TRT review of TUEC's analysis will be reported in a supplement to this SSER. Based on the review of other seismic Category I areas of the plant, the TRT concludes that the acceptability of the installation will depend on TRT approval of TUEC's analysis of the adequacy of the seismic support installation for nonsafety-related conduits in areas of the plant other than the control room. The TRT further concludes that the lack of analysis to substantiate the adequacy of the seismic design installations inspected may be an indica-tion of weakness in the QA/QC program concerning design control. This area is addressed under the QA/QC Category 1, " Design Process."
- 6. Action Required: TUEC shall perform the following actions prior to fuel load:
(a) Provide the TRT with analyses that substantiate (1) the adequacy of the overall seismic support system installation for all the items located above the ceiling in the control room, including nonsafety-related conduit, suspended ceiling, and lighting and (2) the adequacy of the seismic support system installation for nonsafety-related conduit in seismic Category I areas of the plant other than the i control room. This action shall be integrated as appropriate with
other actions addressed under Civil and Structural Category 14,
" Seismic Design of Control Room Ceiling Elements."
(b) Evaluate the adequacy of the QA/QC program related to the deficiencies
- identified above to establish root causes and appropriate actions.
These actions should be integrated with other actions addressed under the QA/QC Category 1, " Design Process."
- 7. Potential Violations: None.
- 8. Attachments: None.
- 9. Reference Documents:
- 1. Regulatory Guide 1.29, " Seismic Designs Classification."
- 2. Comanche Peak, Units 1 & 2 FSAR, Section 3.2.1.2, " Seismic Category II."
- 3. OCA No. 4693, Revision.10.
- 4. ' TUSI Drawing 2323-5-0910, " Conduit'and Junction Box Supports."
- 5. CASE letter of May 11, 1983 to NRC IE and OELD.
- 6. NRC Inspection Report 50-445/83-24 and 50-446/83-15, August 19, 1983.
- 7. NRC Inspection Report 50-445/82-26, 50-446/82-14, February 15, 1983.
- 8. NRC RIV Summary of Comanche Peak Open Issues Tracking System, July 13, 1984.
- 9. NRC Construction Appraisal Team (CAT) Inspection Report 50-445/83-18, 50-446/83-12, April 11, 1983.
- 10. TUGCO, et al, Hearing before the ASLB, NRC Staff. Testimony Regarding the Findings of CAT, June 16, 1983, Pages 8358, 8367, 8368-8373.
6-
- 10. This stateraent prepared by:
G. Myers, Date TRT Technical Reviewer Reviewed by: J. Calvo, Group Leader Date Approved by: V. Noonan, Project Director Date e 9 e O e 9 _____ _ _ _ _ _m _ . - , - w
. D<x.m m..; ??ama-hLECTRICALNO.5 ,
Requestor's ID: LINDA Author's Name: A. Vietti/kb Document Comments: 1/10/85 Redraft I space W e 9
- 1. Allegation Category: Electrical and Instrumentation 5, Electrical Nonconformance Report (NCR) Activities
- 2. Allegation Number: AQE-1, AQE-2, AQE-3, AQE-4, AQE-5, AQE-25, AQE-33, AQE-34,AQE-35,AQE-37,AQE-38,AQE-40,AQE-41,AQE-42,AQE-45,AQE-47, AQE-48, AE-24, and parts of AE-22, AE-27, AQE-12, AQE-36 and AE-50.
- 3. Characterization: It is alleged that the validity of the generation and disposition of electrical nonconformance reports (NCRs) was suspect.
- 4. Assessment of Safety Significance: The implied safety significance of these allegations is that the quality of the electrical installation could be indeterminate.
These allegations pertain to various concerns involving the NCR program, and include: Prevalent "use-as-is" dispositions of NCRs (AQE-33, AQE-47, AQE-34, AQE-35, Parts of AE-27 and AQE-36). Inaccurate evaluation in the generation of NCRs to indicate workman-ship not compromised (AQE-48). The closing out of NCRs by unqualified inspectors (either inten-tionally or under coercion) (AQE-4). Pressure not to generate NCRs (AQE-42). The traceability of "Q" items (non-Q fuse blocks were installed where Q blocks were required) (AQE-35). Restraint cable (mechenical) crimp gage calibration (AQE-41). Failure to follow procedures, specifications and dra' wings (AQE-25, AQE-40, part of AQE-12). ,
1 i Splicing of safety-related electrical cables in violation of regula- ; tory requirements (part of AE-50). Questionable dispositions for NCRs involving inadequate thread engagement on a conduit fitting and damaged cable (AQE-45). Electrical cable tray fell, damaging cables entering the control room (AE-24). No documentation available for butt splices in panels (part of AE-22). Conduit replaced in Fuel Handling Building was dispositioned as repaired rather than replaced (AQE-3). In addition to these general concerns, several allegations contained specific information about questionable NCR dispositions, which includes: Improper documentation was kept for the removal and pulling of damaged cables (AQE-1, AQE-2, AQE-5). Disposition of NCR on terminal block rework was questionable (AQE-37). . Excessively bent terminal lugs in motor control centers (part of AQE-36). Unauthorized solenoid repair (AQE-38). Loose elbow termination conduit fittings found on the Unit 1 diesel generators (part of AE-27). The NRC Special Review Team (SRT) also had concerns with respect to the Texas Utilities Electric Company (TVEC) management response to the'so-
called "T-shirt" incident because of its potential effect on the morale of QC electrical inspectors, which in turn could have affected their workmanship. (For detailed discussion of the "T-shirt" incident, see QA/QC Category 6, "QC Inspection," AQ-46.) The Final Safety Analysis Report (FSAR), Section 17.1 " Quality Assurance During Design and Construction," commits TUEC to a quality assurance (QA) program, as required by 10 CFR 50, Appendix B. FSAR Section 17.1.10,
" Inspection," outlines the inspection plans which will ensure that construction tasks conform to procedures, drawings, specifications, codes, standards, and other documentation. These plans are augmented by TUGC0 procedure CP-QP-16.0, which established the methods for generating and dispositioning reported items of nonconformance. The NRC Technical Review Team (TRT) reviewed pertinent TUEC documentation to determine that the procedures and instructions for generating and dispositioning reported items of nonconformance were adequate as related to the concerns raised by the allegations.
The TRT reviewed a random sample of 75 electrical NCRs and conducted numerous interviews with QA/QC and engineering personnel. (See also Electrical and Instrumentation Category 6, " Electrical QC Inspector Training / Qualifications.") The TRT reviewed 25 of the 75 electrical NCRs to determine if the QC inspectors who " closed out" the NCRs were quali-fled to do so. The TRT found that in all 25 cases the QC electrical inspectors were qualified and their certification files were current (AQE-4). Equipment installation matters raised by these allegations are addressed under: l Electrical and Instrumentation Category 1, " Electrical Cable Termi-nations," for parts of AE-22, AQE-12 and AQE-36. O
4 Electrical and Instrumentation Category 2, " Electrical Cable iray and Conduit Installation," for the alleged loose conduit fittings for part of AQ-27.
~
Electrical and Instrumentation Category 7, " Electrical Cable Installa-tion," for the alleged splicing of safety-related cables in raceways and cable damage where trays contained trash and hazardous debris, for part of AE-50 and AQE-5. The TRT interviewed a TUEC electrical engineer and a lead quality engi-neer (QE) about the "use-as-is" disposition of electrical NCRs (AQE-33, AQE-47, AQE-34, AQE-35 and parts of AE-27, and AQE-36). The TRT deter-mined that for an NCR to receive a "use-as-is" disposition, an independent verification inspection by an electrical engineer had to be made for each reported item of nonconformance. Based on that inspection, and on an evaluation with regard to procedures, specifications, drawings (including applicable codes and standards), and other related documentation, a ,
"use-as-is" disposition could be applied. Final approval of such a disposition required two QE signatures. The TRT also reviewed the 75 NCRs to determine if there were any with the disposition "use-as-is" with the explanation "not addressed in ES-100," as alleged. The TUEC engineer also indicated that should an NCR be received with this type of disposi-tion, it would be " kicked back" and would require more justification.
The TRT determined that if the nonconformance indeed was not addressed in ES-100, then a document, such as a procedure or other specification, that did address this nonconformance item would be required to be refer-enced in the NCR. Of the 75 NCRs examined, the TRT could identify no "use-as-is" dispositions which deviated from applicable design require-ments, except for those identified in Electrical and Instrumentation Category 1, " Electrical Cable Terminations," and Electrical and Instru-mentation Category 2, " Electrical Cable Tray and Conduit Installation," 9 # t
regarding NCRs identifying bent terminal lugs in motor control centers (part of AQE-36), and reporting two loose conduit elbow fittings (part of AE-27), respectively. These TRT findings were discussed with the allegers, one of whom disagreed with the TRT findings as related to AQE-34 and AQE-35 and provided additional information. The TRT is currently evaluating this new information and will report its findings in a supplement to this SSER. The TRT also interviewed a TUEC electrical engineer about NCR disposi-tions with respect to " replace versus repair" (AQE-3) and " compromised workmanship" (AQE-48). The TRT determined that replacing a reported item instead of repairing it as originally di. positioned would require a revision to the original NCR. The disposition of the NCR for replacement would be based on an engineering evaluation. The TRT determined that on a case-by-case basis where workmanship might have been compromised, the inspecting engineer would apply engineering judgment to determine that the quality of sorkmanship did not degrade the installation below an acceptable level. From the 75 NCRs examined the TRT could not find any evidence of unacceptable installation. (See also Electrical and Instru-mentation Category 8, " Electrical Procedures," regarding correction of installation deficiencies for lighting terminations. The TRT searched the records for the number of NCRs and inspection reports written and for the amount of cable pulled for a 57-day period prior to and a 57-day period following the so-called "T-shirt" incident. This search was conducted to determine if the incident had any effect on the workmanship of the electrical QC inspectors. The TRT could find no evidence that inspectors were affected by the incident as a result of management reaction to it. l The TRT interviewed the quality control (QC) supervisor of the calibra-tion lab and reviewed pertinent procedures that were followed to ensure I that construction tools which required periodic calibration were, maintained (AQE-41). The TRT found that lab controls, procedures, and I
tool traceability, if properly implemented, would ensure that tool cali-bration was maintained. Adequate procedures also existed to ensure that corrective actions would be taken if a tool did not meet calibration specifications and tolerances. The TRT reviewed NCR documentation on tool calibration and found it to have been dispositioned in accordance with procedures that ensured the integrity of the construction (See also QA/QC
~
Category 6, "QC Inspection," for the disposition of the specific concern raised by AEQ-41.) The TRT interviewed QC and purchasing personnel and an electrical general foreman for construction, and reviewed pertinent documentation to determine the adequacy of traceability of safety-related (noted as "Q") items (AQE-35). The TRT determined that procedures and controls, if properly followed, were adequate to ensure the traceability of "Q" items and that they would preclude the possibility of substituting "non-Q" for "Q" items. The TRT reviewed a large number of installation documents and found all the required traceability documentation. In regard to AQE-42, the TRT's interviews with QC personnel could not substantiate the allegation that an individual was pressured not to issue NCRs. (See also QA/QC Category 6, "QC Inspection," AQ-35.) To address the specific technical concerns raised in the above allega-tions, the TRT examined the NCR log books, interviewed allegers, and selected a random sample of NCRs pertaining to specific items of concern. The TRT determined that: The allegation'(AQE-36) of excessise bending of AMP Product Corporation compression lugs in ITT Gould-Brown Boveri switchgear was substantiated. This issue is addressed in Electrical and Instrumentation Category 1, " Electrical Cable Terminations." The allegations of improper documentation of cable removal (AQE-1 a and AQE-2); repair rather than replacement of flex conduit
(AQE-3); damaged cable as a result of a fallen cable tray (AQ-24); failure to follow procedures and specifications (AQE-25 and AQE-40); damaged cable due to inadequate thread engagement on a conduit (AQE-45); and rework of terminal blocks (AQE-37) could not be substantiated, since in its review of a random sample of 75 NCRs on these issues the TRT could not identify any inconsistencies or deficiencies that would raise a safety question. These findings were discussed with some of the individuals responsible for raising these concerns, one of whom disagreed with the TRT determination concerning AQE-37 and provided additional information. The TRT is currently evaluating this new information and will report the results in a supplement to this SSER. The alleger clarified AQE-38 during an interview with the TRT, indicating that the concern related to the repair of an off-the-shelf solenoid (glueing the connecting terminal to the solenoid coil and resoldering the coil lead to the terminal). The alleger believed that the solenoid was used in a safety-related system but the alleger could not remember which system. Moreover, the alleger indicated that there was no written record of the repaired solenoid. The TRT could not substantiate the concern raised by this
- allegation.
The allegation for the loose elbow termination conduit fittings in the diesel generator rooms for Unit 1 (Part of AE-27) has merit. The TRT examined the NCR log book and found the specific NCRs for this item. The TRT also inspected the diesel generator rooms of Unit 1 and found two loose elbow conduit fittings. This issue is addressed in Elactrical and Instrumentation Category 2,
" Electrical Cable Tray and Conduit Installation."
- 5. Conclusions and Staff Positions: Based on the reviews of the pertinent documentation, examination of NCRs, and the information obtained from the ,
interviews, the TRT concludes that adequate procedures, controls, and W
1 process checks exist for the generation and disposition of reported items of nonconformance as related to the concerns raised by the above allegations. The TRT also concludes that of the allegations identified at the outset of this section, only a few specific instances were found which raised questions co~ncerning the adequacy of safety-related items. These are discussed above and are discussed further in other sections of the report. The results of this evaluation will be further assessed as part of the overall programmatic review of all NCRs addressed under QA/QC Category 5, "Nonconformance Reports," and under QA/QC Category 6, "QC Inspection." Therefore, the final acceptability of this evaluation will be predicated on the satisfactory result of the overall programmatic review on these subjects. Any adjustments to these conclusions will be reported in a supplement to this SSER. The results of the TRT review of new informa-tion concerning allegations AQE-34, AQE-35 and AQE-37 will also be reported in a supplement to this SSER. '
- 6. Action Required: None.
- 7. Potential Violations: None.
- 8. Attachments: None. -
- 9. Reference Documents:
- 1. Comanche Peak, Units 1 and 2 FSAR, Section 17.1.10, " Inspection."
- 2. TUGC0 QA Plan Manual for CPSES.
- 3. TUGC0 Quality Procedure Manual.
- 4. Brown and Root Quality Assurance Manual.
- 5. Brown and Root Quality Assurance Procedures Manual.
- 6. TUGC0 Office Memorandum, TUQ-2134, dated May 22, 1984.
- 7. SRT Final Report (SRT-10), July 13, 1984.
- 8. NRC OI Report 4-83-013, November 3, 1983, Page 8, Paragraph 1, 2, 3, 4, and 5.
- 9. NRC Investigative Report 50-445/81-04 and 50-446/81-04, May 5, 1981.
- 10. GAP Notes of April 1984 (Confidential), Paragraph 16, GAP Witness H.
- 11. GAP Notes of April 1984 (Confidential), Paragraph 33, GAP Witness Anonymous.
- 12. Limited Appearance of Anonymous GAP Witness before the ASLB, September 16, 1982, Pages 5551-5552, and 5556-5557.
- 13. NRC RIV Inspection Report 50-445/83-03, 50-446/83-01, March 28, 1983.
- 14. Comments of Anonymous GAP Witness, Meeting with NRC and Sent to CASE, December 13 and 20, 1982.
- 15. Deposition of SRT Witness A-5, July 17, 1984, Pages 55,102-55,103.
- 16. TUGC0 Office-Memorandum # TUG-2134, " Transmittal of Final Report on Issues Resulting From Interviews with Electrical Inspectors," May 22, 1984.
- 17. Deposition of GAP Anonymous Witness, July 25, 1984, Pages 58,503-58,591.
- 18. Deposition of GAP Witness, July 16, 1984, Pages 53,003-53,263.
- 19. NRC Construction Appraisal Team (CAT) Inspection Report 50-445/83-18, 50-446/83-12, April 11, 1983.
- 20. TUGCO, et al, Hearing before the ASLB,-NRC Staff Testimony Regarding the Findings of CAT; (June 13, 1983, Pages 7733-7755; June 15, 1983, Pages 8160, 8231, 8261-8263, 8291; June 16, 1983, Page 8358.
- 21. NRC Interview with SRT Alleger A-3, September 6, 1984, Pages 30-37, 39-40, 42-44, 63-72, 75-79.
l 4 10 - l
- 10. This statement prepared by:
, - i em,", Date b* h; TRT Technical Reviewer Reviewed By:
J. Calvo, Date Group Leader Approved By: V. Noonan, Date Project Director 1 e o l t l
. - .-. - . _~ _ - .- . Docn- t F---- -a .
SSER ELECTRICAL 6f , Requestor's ID: LINDA Author's Name: A. Vietti/kb Document Comments: AQE-8,ETC.(WAS SSER-Electrical 10-NEWNAME) (REVISED 9/29 HQ) I
=
1 4 l I i . I l I t I (
1
- 1. Allegation Category: Electrical and Instrumentation 6, Electrical Quality Control (QC) Inspector Training / Qualifications ;
1
- 2. Allegation Number: AQE-8, Parts of AQE-4 and AQE-12.
- 3. Characterization: It is alleged that some electrical QC inspectors were inadequately qualified, that they received help in passing certification tests, and that their previous experience was inadequate to fulfill the job requirements.
- 4. Assessment of Safety Significance: The implied safety significance of these allegations is that the lack of training or qualification of electrical QC inspectors could result in inadequate inspections of safety-related components.
The allegations question whether the positions of American National Standards Institute (ANSI) Standard N45.2.6-1978, " Qualifications of Inspection, Examination, and Test Personnel for the Construction Phase of Nuclear Power Plants," as augmented in the Final Safety Analysis Report (FSAR) Section 17.1.2, " Quality Assurance Program," were con-sidered by Texas Utility Electric Company (TVEC) in the development of the quality assurance (QA) program at the Comanche Peak Steam Electric Station (CPSES). Regulatory Guide (RG) 1.58; Revision 1, " Qualification of Nuclear Power Plant Inspection, Examination, and Testing Personnel," endorses the positions of ANSI N45.2.6-1978. RG 1.58, Revision 1, and ANSI N45.2.6-1978 set forth positions stating l the education and experience requirements for the various capability levels of inspectors (I, II, and III). Both documents, however, state that these requirements are not absolute when other factors may provide reasonable assurance that a person can competently perform a particular task. They require that all records or qualifications shall be maintained by TUEC in an individual's personnel file. l l O
In assessing these allegations, the NRC Technical Review Team (TRT) examined Texas Utilities Generating Company (TUGCO) procedures, QC inspector training and certification files, testing program requirements, on-the-job training (0JT) requirements, and recertification program requirements. The TRT also conducted interviews with the training coordinator, two Level I QC electrical technicians, four Level II QC electrical inspectors, one Level III quality engineer (QE), one Level II lead QC electrical inspector, one lead QE, and the QE Supervisor. Procedures. The TRT found that TUGC0 Procedure CP-QP-2.1, " Training of Inspection Personnel," commencing with Revision 8 (July 1981), contained education and experience requirements consistent with RG 1.58, Revision 1, and ANSI N45.2.6-1978. Revision 7 (June 1981) of the above procedure, Section 3.1.d, "Tecnnical Training" contained the statement: Minimum training, educatien, and experience requirements will be defined in technical training outlines prepared for specific inspection activities (civil, electrical, etc.). ' After a discussion with the training coordinator and an examination of the technical training outlines, the TRT discovered that the education and experience requirements were never defined, and that only the training requirements had been defined. After examining other related procedures, the TRT found the following deficiencies. Training and Certification Files. The TRT examined in detail six elec-l trical QC inspectors' training and certification files.(two Level I and { four Level II). The examination revealed the following two instances where TUGC0 Procedure CP-QP-2.1, Revisions 8 through 15, RG 1.58, Revi-sion 1, and ANSI N45.2.6-1978 requirements for qualification were not being met: l i
(a) There was no documentation of a high school diploma or General Equivalency Diploma (GED) for one of the inspectors selected. The file on this inspector contained only a telephone conference note that a call had been made in 1982 requesting information from a high school. (b) There was no documentation to waive the remaining 2 months of the required 1 year of experience for a Level I technician before the individual became a Level II inspector after successfully passing the required examinations. The TRT also found one case where a Level I QC technician had not passed the required color vision examination to be administered by an independent professional eye specialist. A makeup test using colored pencils was administered by a QC supervisor, was passed, and then a waiver was given. A TUGC0 procedure allowed for a waiver on a case-by-case basis. In addi-tion to the above, the TRT staff also found two cases where the experience requirements to become a Level I technician were met only marginally. In one case no documentation was found in the training and certification files substantiating that the person met the experience requirements or providing the basis for determining that the person could, with reasonable assurance, competently perform the particular task without having the required related experience. - Testing Program Requirements. The TRT examined the testing, retesting and scoring methods applicable to Level II qualification and found some guide-line inconsistencies and procedural deficiencies. Specifically, they included: (a) No time limit or additional training requirements between a failed test and a retest. In practice the time varied from a few days to months. (b) No controls to assure that the same test would not be ,qiven if the taker previously failed it. 4
(c) No consistency in scoring. Two different scoring techniques were used to average the results when two tests were taken. Combined test scores could vary slightly, depending on which technique was used. These slight variations could make the difference between passing or failing the tests - - a condition resulting solely from the scoring technique used. Seven out of 25 tests used one test scoring technique instead of the other. (d) No guidelines .or procedures to control the disqualification of ques-tions from the test. In one instance a question was disqualified after the test was administered, thus allowing two people to pass the exam that they would have otherwise failed. (e) No program for establishing new tests (except when procedures changed). The same tests had been utilized for the last 2 years. On-The-Job (0JT) Training Requirements. The TRT examined the OJT train-ing for QC electrical inspectors and found sufficient documentation in the training and certification files that adequate OJT was being obtained. Numerous cases were found where a portion (10%-20%) of the required OJT was being waived only after applicants successfully passed the Level II examinations. Recertification Program Requirements. The TRT examined the recertification program and found that there was no required documentation to assure that recertification requirements were being met. The present system only requires a simple "yes" or "no" answer from an inspector's lead QC inspec-tor that the individual had been active in the area in the last 6 to 12 months and was knowledgeable about current procedure requirements. The lead QC inspectors did not maintain any written record of a subordinate inspector's activity. Interviews. The TRT interviewed 11 people, including the training coordi-nator and Level I QC technicians on up to the QE supervisor. The con-sensus of those interviewed was that the training program was adequate and
-S- ,
had improved over the last couple of years. Some thought additional OJT would have been more beneficial in lieu of " book time." Based on reviews of the QC inspector training and qualification aspects of the electrical QA program, the TRT determined that current procedures in effect beginning with Revision 8 of the CP-QP-2.1 meet the requirements of ANSI N45.2.6-1978, as augmented in the FSAR and endorsed by RG 1.58, Revi-sion 1. Prior to Revision 8, TUGC0 procedures did not define the education and experience recommended in the above regulatory documents. TUGC0 was not committed to these requirements until April 30, 1981. The TRT review of the training and certification files determined that some supportive documentation as required by procedures and regulatory positions was lacking. The TRT determined that the testing program lacks guidelines and procedural requirements covering, but not limited to, such items as test question dis-qualifications, scoring, retests, and the prolonged use of the same tests. b The TRT also determined that the inspector recertification program lacks programmatic controls to assure that the recertification requirements in the different electrical quality instructions are being met.
- 5. Conclusions and Staff Positions: Based on its review of the pertinent documentation and its interviews, the TRT concludes that there is evidence to indicate that the electrical QC inspector qualification program lacked programmatic controls, which may be indicative that the required level of qualification was not obtained for some electrical QC inspectors. Spe-cifically, the lack of programmatic controls to assure that suitable proficiency is achieved and maintained (as required by 10 CFR 50, Appen-dix B) was found in:
D
The supportive documentation of qualifications, as required by pro- I cedures and regulatory requirements in the training and certification. The testing program for Level II qualification. { l The recertification program requirements in electrical quality instructions. The TRT concludes that the lack of these programmatic controls in the l electrical QC inspector qualification program is of concern. Since the training and certification program is the same for all disci-plines (except ASME), the TRT concludes that the deficiencies in procedural I requirements and guidelines in the testing program and the lack of documen-tation in isolated cases have generic implications to the other construc-tion disciplines. The implications of the TRT's findings concerning electrical QC inspector training and qualification will be further assessed as part of the overall programmatic review of QC inspector training and qualification, which is addressed under QA/QC Category 4, " Training and Qualification."
. 6. Action Required: TUEC shall accomplish the following prior to fuel load:
(1) Evaluate the testing program for QC electrical inspector qualifica-tions and develop a testing program which optimizes administrative guidelines, procedural requirements, and test flexibility (e.g., computer generated tests) to assure that suitable, proficiency is achieved and maintained. These guidelines and/or procedures shall include such items as scoring, retests, and question disqualification. (2) Justify the allowance in the procedure for administering separate (waiver) vision tests in lieu of examinations administered by an independent professional eye specialist.
(3) Review all electrical QC inspector training, qualification, certifi-cation and recertification files against the project requirements as documented in the FSAR and provide the information in such a form that each requirement is clearly shown to have been met by each inspector. If an inspector is found to not meet the training, qualification, certification, or recertification requirements, TUEC shall then review the records to determine the adequacy of inspec-tions made by the unqualified individuals and provide a statement on the impact of the deficiencies noted on the safety of the project. (4) Integrate these actions, as appropriate, with other actions addressed under QA/QC Category 4, " Training and Qualifications." i
- 7. Potential Violations: TUGC0 procedures (CP-QP-2.1 Revision 15 and CP-QP-2.3 Revision 4) and NRC staff positions (RG 1.58 - Revision 1, and ANSI N45.2.6-1978) require that all documentation which demonstrates that an individual has comparable or equivalent competence to the required education and experience be included in the training and certification files. Contrary to 10 CFR 50, Appendix B, Criterion XVII and the above requirements, TUEC failed in several instances to include this supportive documentation in the-training and certification files.
- 8. Attachments: None.
- 9. Reference Documents:
- 1. Comanche Peak, Units 1 and 2 FSAR, Section 17.1.2, " Quality Assurance Program."
- 2. ANSI N45.2.6-1978, " Qualifications of Inspection, Examination, and Testing Personnel for the Construction Phase of Nuclear Power Plants."
- 3. RG 1.58, Revision 1, 1980, " Qualification of Nuclear Power Plant Inspection, Examination, and Testing Personnel."
8-
- 4. TUGC0 Procedure CP-QP-2.1, Revisions 7, 8, and 15, " Training of Inspection Personnel."
- 5. TUGC0 Procedure CP-QP-2.3, Revision 4, " Documentation Within QA/QC Personnel Qualification File."
B 6. TUGC0 Procedure QI-QP-2.3, Revision 8, " Qualification of Electrical Inspection and Test Personnel."
- 7. Inspection Report 82-11.
- 8. NRC Investigative Report 50-445/81-04 and 50-446/81-04, May 5, 1981.
- 9. Pre-filed Testimony before ASLB, May 24, 1982, Page 80.
- 10. NRC OI Report 4-83-013, November 3, 1983, Page 8, Paragraph 4.
- 11. NRC Special Review Team Report, July 13, 1984.
- 12. TUGC0 Office Memorandum #TUC-2134, " Transmittal of Final Report on Issues Resulting from Interviews with Electrical Inspectors," May 22, 1984.
- 13. Deposition of GAP Witness, July 16, 1984, Pages 53,003-53,263.
- 14. NRC RIV Summary of Comanche Peak Open Issues Tracking System, July 13,
- 1984. .
- 10. This Efatement/Fepared by:
q',* gg i C ::': . Date TRT Technical Reviewer Reviewed By: J. Calvo, Date Group Leader Approved By: V. Noonan, Date Project Leader
Document Name: - SSERQLECTRICALYj Requestor's ID: ORDAZ Author's Name: A. Vietti/kb Document Comments: AE-19 etc.-(REV. IC/03,HQ) e O 9 0
- 1. Allegation Category: Electrical and Instrumentation 7, Electrical Cable Installation
- 2. Allegation Number: AE-19, AE-28, AE-30, AE-50, Parts of AQE-5 and AE-29 and Special Review Team SRT-10
- 3. # Characterization: It is alleged that:
Cable trays were overloaded (AE-19). Cables were not " trained" in a workmanlike manner in the cable spread-ing room and in junction boxes 1058 and 1059 (AE-28). Higher siderails were added to cable trays due to tray overfill con-ditions (Part of AE-29). Cable density / compaction problems may exist due to tray overfill conditions (AE-30). Cables were spliced in cable trays in the cable spreading room in violation of regulatory requirements (AE-50). A nonconformance report pertaining to trash in cable trays, damaged cable, and improperly trained cable was improperly closed (Part of AQE-5). The Special Review Team Report on July 13, 1984, identified the issue of overloaded cable trays due to the installation of "thermolag" material (SRT-10).
- 4. Assessment of Safety Significance: The implied safety significance is that improperly trained cables, improper cable splices and overloaded cable trays could place the quality of the installation in question.
Cable Splices in Raceways. Allegation AE-50 involved the alleged splicing of safety-related cables in raceways in violation of regulatory require-ments. The NRC Technical Review Team (TRT) reviewed NRC Region IV (RIV) inspection report 83-03 (November 8, 1982) and found that the RIV , investigation of the two cables specifically identified by the alleger ' 9
i
^
P adequately addressed this allegation. The RIV investigation determined that cne cable no longer performs a safety-related function, and the other cable had become a " spare" and was removed from the raceway. Tne TRT . determined that similar-appearing items in the same area were not splices, but were, in fact, acceptable methods of repairing minor cable jacket ; damage. The TRT concurs with the RIV determination but notes that regulatory requirements discourage the use of splices in raceways, as stated in position 9 of Regulatory Guide (RG) 1.75, " Physical Independence of Electric Systems." If splices are made, the resulting design should be justified by analysis. This area is further addressed under the TRT QA/QC Category 8, "As Built." The TRT examined the cable spreading room, identified two cables installed in raceway, which to the untrained eye could appear to have been spliced, ' and inspected them in their as-installed condition. The TRT also reviewed the applicable installation / inspection records. This inspection and review revealed that there were cable jacket repairs and that they were properly identified, repaired, and documented in accordance with applicable procedures. Poor Workmanship. Allegations AE-28 and Part of AQE-5 involved instances of improper cable " training" (or dressing), poor workraanship in cable installation, and cables installed in raceways containing trash and hazard-ous debris. The issues of improper " training" of cables and poor workman-ship in junction boxes 1058 and 1059 were inspec'ted by'the TRT. The TRT findings agree with the previous NRC RIV determination that these cables, which are nonsafety-related, were properly trained and that they exhibited an acceptable degree of workmanship. These findings were discussed with the alleger who indicated that the junction box numbeis may not have been i correct and provided additional information concerning the location of the i boxes in the plant. The TRT is currently evaluating this new information I and will report the results in a supplement to this SSER. The alleger did not identify which trays contained trash and hazardous debris at the time of cable installation, so the TRT randomly inspected approximately 2,000 feet of cable trays containing safety-related cables and found no
e instances of improper training, trash, hazardous debris, or poor workmanship. Tr_ay Overfill _. Allegations AE-19, and AE-30 involved various concerns related to cable trays possibly being overfilled. The alleger specifically identified tray T130CC007 in the cable spreading room. The TRT inspection of this tray fevealed the follcwing: (a) Siderails w~re e installed on this tray, adding approximately 2 inches tc its. height. When inspected, no cables extended above the level of the siderails, y;. (b) Per nonconforniance report (HCR) E-82-1073R1, eight spare cables were removed frcm this tray in January 1983, in conjunction with the removal of 42 spare cabl'se fecm tray T130ECC82 because the tray was identifled overloaded. (c) Calculation of the actual weight of cables currently installed in this tray indteited leading of approximately 22 pounds per square foot, comna;ed with (he ma.ximum allowable value of 35 pounds per scuare foot, as- specified in seismic supporting requirements. (d) Calculation of the square area fill of cables currently installed in thic tray indicates an actual fill of 28%, compared with the maximum recor. mended valua of 40%, as stated in IEEE Standard 422, " Guide for the Cecign and Installation of Caole Systems in Power Generating Stations." The TRT selected nine additional sections of tray con-taining large quantitles cf cables. These quantities ranged from 57 to 300 cables per tray section. The square area fill and weight per square foot values for these trays were reviewed fcr conformance with the stated maximum values, The results of this review were as follows: (1) All nine trays were loaoed at less than 28 pounds per square foot. (2) Seven of the trays had square area fill less than 40%.
';' s.
(3) The two remaining trays had s,quare area fills of 41% and 42%; however, Section 8.3.3.1 of;the Final Safety Analy' sis Report (FSAR) justifies exceeding the 40% value if cables do not extend above the siderails of the tray, and do not violate seismic supporting requirements. The NRC staff considers this justification acceptable. This review revealed that all trays sampled comply with seismic supporting
~
requirements and, because n'o cables extended above the tray side-rails, that no deficiencies existed within'the sample selected. Added Loads on Trays. Part of Allegation AE-29 and concern SRT-10 involved the addition of higher siderails and "thermolag" material to existing cable trays, conditions which could cause trays to become physically overloaded. Regarding the higher siderails, the TRT discovered that siderails were fabricated using 6-inch high by 16 gauge galvanized sheet metal. As such, the addition of this material would increase tray loadir.g by approximately 2 pounds per foot. Using the above sample of cable trays, which the TRT considers representative of some of the most highly loaded trays at Comanche Peak Steam Electric Station (CPSES), Unit 1, this added height would bring
. . the most highly loaded tray to approximately 30.5 pounds per square foot, compared with the maximum allowable value of 35 pounds per square foot.
1 Regarding the "thermolag" material, the TRT reviewed procedure CP-EI-4.0-49, Revision 1, " Evaluation of Thermolag (TSI) Fire Barrier Material on Class 1E Electrical Raceways." From this review the TRT determined that the procedure was adequate if properly followed to assure that, should over-loading occur due to the addition of thermolag material, these instances would be identified, evaluated, and if necessary, corrected prior to the installation of the-thermolag. The TRT then selected two raceways (one cable tray and one conduit) with thermolag installed and reviewed the evaluations performed in accordance with the above procedure. The TRT l fund that the requirements of the procedure had been met, and therefore,
determined that the addition of tray siderails and thermolag material poses no hazard to the structural integrity of the raceway system.
- 5. Conclusions and Staff Positions: Based on the inspection of the cable ;
installations for cable splices in cable trays, workmanship, cable tray l fill, added load on cable trays by thermolag material, and review of pertinent criteria, procedures, RIV inspection reports, installation / inspection reports, and NCRs, the TRT concludes that the various aspects of the cable installation on raceway fill reviewed and inspected meet established installation requirements. Therefore, the TRT concludes that these allegations could not be substantiated. The results of the TRT review of new information concerning allegation AE-28 will be reported in a supplement to this SSER.
- 6. Actions Required: None.
- 7. Potential Violations: None.
- 8. Attachments: None.
- 9. Reference Documents:-
- 1. Region IV Inspection Report 50-445/83-03, 50-446/83-01, March 28, 1983.
- 2. Nonconformance Report E-82-1073, R1.
- 3. IEEE Standard 422, " Guide for the Design and Installation of Cable Systems in Power Generating Stations."
- 4. Regulatory Guide 1.75, " Physical Independence of Electric Systems."
- 5. CPSES FSAR, Section 8.
b
- 6. Procedure CP-EI-4.0-49, Revision 1, " Evaluation of Thermolag (TSI)
Fire Barrier Material on Class 1E Electrical Raceways."
- 7. NRC Special Review Team Report (SRT-10), July 13, 1984.
- 8. GAP Notes of April,1984 (Confidential), Paragraph 5, GAP Witnesses A and H.
- 9. NRC OI Report 4-83-013, November 3, 1983, Pages 8-9.
- 10. Limited Appearance of Anonymous GAP 3 Witness before the ASLB, September 16, 1982, Pages 5551-5552, and 5556-5557.
- 11. Comments of Anonymous GAP Witness, Meeting with NRC and Sent to CASE, December 13 and 20, 1982.
i
- 12. NRC Inspection Report 82-01.
- 13. TUGC0 Office Memorandum #TUC-2134, " Transmittal of Final Report on Issues Resulting from Interviews with Electrical Inspectors," May 22, 1984. .
- 14. Deposition of Anonymous GAP Witness, July 25, 1984, Pages 58,503-58,591.
c 15. NRC RIV Summary of Comanche Peak Open Issues Tracking System, July 13, 1984. ,
- 16. NRC Construction Appraisal Team (CAT) Inspection Report 50-445/83-18, 50-446/83-12, April 11, 1983.
- 17. TUGCO, et al., Hearing before the ASLB, NRC Staff Testimony Regarding the Findings of CAT; June 13, 1983, Pages 7733-7755; June 15, 1983, Pages 8160, 8231, 8261-8263.
- 18. NRC Interview with SRT Alleger A-3, September 6, 1984, Pages 27-30.
- 10. This statement prepared by:
W. Marini, Date TRT Technical Reviewer Reviewed by: J. Calvo, Date Group Leader Approved by: V. Noonan, Date Project Director w i e e
~ . -
i
/
Document Nama-SSER-jELECTRICAL8 Requestor's ID: ORDAZ Author's Name: A. Vietti/kb Document C:mments: 1/8/85 eg 4 e G 9
- 1. Allegation Category: Electrical and Instrumentation 8, Electrical Procedures
- 2. Allegation Number: AQE-23, AQE-32, AQE-39, AQE-44, AQE-46, AQE-52 and Parts of AQE-6, AE-18 and AE-20.
- 3. Characterization: It is alleged that:
Requirements were deleted in the procedural revision for post-construction inspection of electrical equipment and raceways and electrical QC inspectors were directed by a supervisor not to follow procedures (AQE-23 and Part of AQE-6). The number of required inspections was reduced in the inspection procedure for reverification of seismic electrical equipment mounting details (AQE-32). Revisions to the procedure for post-construction inspection of electrical equipment and raceways were made to accommodate numerous problems with loose terminations found in the lighting system termi-nal boxes during past inspections (AQE-39 and AQE-46). Revision 15 to the procedure for post-construction inspection of electrical equipment and raceways omitted requirements for inspections of large pieces of equipment, such as 6.9 kilovolts (KV) motors (AQE-52). A cable separation problem identified in the Fuel Handling Building was dispositioned "use-as-is," contrary to procedure (AQE-44). Insulated butt splices were being used inside panels in violation of the in process inspection procedure for cable terminations (Part of AE-18).
Separation criteria between redundant cable trays and conduits in the cable sprea' ding room were not consistent with the requirements of the in process inspection procedures for verifying electrical separation (Part of AE-20).
- 4. Assessment of Safety Significance: The implied safety significance is that the quality of the electrical installation may be in question because requirements were deleted from procedures, required inspections were re-duced in frequency, and installation was being done contrary to procedures.
The NRC Technical Review Team (TRT) examined nine in process inspection procedures used during plant construction, one post-construction inspec-tion and walkdown procedure, and four turnover inspection procedures for fi'nal acceptance of station systems, structures, and equipment by TUEC startup and operations. The TRT reviewed in place procedures, historical procedure files, inspection reports (irs), IR deficiency logs, post-construction deficiency lists, electrical equipment punch lists, electrical separation deficiency reports, test release / return to contractor custody /startup release to operations forms, construction operation travelers,- startup work authorizations, .and systems / area
. testing, drawing, walkdown results/ review forms. The TRT also interviewed QC management personnel and allegers. The TRT examined the above documents for programmatic weaknesses in the electrical procedures which may have negated quality assurance / quality control (QA/QC) inspection activities during construction of the plant.
Procedures for Post-Construction Inspection of Electrical Equipment and Raceways (AQE-23, AQE-52 and Part of AQE-6). The TRT review of proce-dure QI-QP-11.3-40, " Post-Construction Inspection of Electrical Equipment and Raceways," revealed that most deficiencies identified by QA/QC personnel during post-construction and walkdown inspections of electrical equipment and raceways was based on this procedure, which provides ade-quate guidance for electrical equipment and raceway inspections.
-v
I
. l The TRT found that this post-construction walkdown procedure had under-gone 18 revisions. Before Revision 15, QC inspectors were using this procedure. extensively to reinspect in process inspection activities (e.g.,
Sections 3.1.1 through 3.1.4 of Revision 14, requiring verification of cable, cable tray, conduit, and equipment installation, which were re-written under Sections 3.1.1 and 3.1.2 of Revision 15, entitled, " Raceway Inspection" and " Equipment Inspection"). Revision 15, Section 3.1.2, covers requirements for inspection of large Class 1E equipment. There-fore, 6.9 kv motors, considered to be large equipment, would have been covered by the procedure, if classified IE. However, since they are not Class 1E, they are excluded from inspections. Some of the revisions of this procedure came as a result of the many test deficiency change requests (TDCRs) based on TUGC0 procedure CP-SAP-3,
" Custody Transfer of Station Components." These deficiencies evolved from the startup performance testing of components and systems that B&R and other contractors had turned over to TUGCO. Other revisions were made to include the experience gained during the reinspection of'the in process inspection activities.
After a review of QI-QP-11.3-40 and CP-SAP-3, as well as other pertinent . electrical in process inspection and startup administrative procedures, the TRT did not find any omissions in requirements for inspection of electrical equipment and raceways (AQE-23, Part of AQE-6). Procedures for Lighting Termination and Wiring (AQE-39 and AQE-46). The TRT found that safety-related lighting terminations an,d wiring were required to be inspected under TUGC0 in process procedures QI-QP-11.3-23,
" Class 1E Conduit Raceway Inspections," QI-QP-11.3-26, " Electrical Cable Installation Inspections," QI-QP-11.3-28, " Class 1E Cable Terminations,"
and QI-QP-11.3-40, " Post-Construction Inspection of Electrical Equipment and Raceways."
l l The TRT founc that the inspections of emergency lighting and associated terminations were being performed under Revision 15 or earlier revisions of procedure QI-QP-11.3-40, even though the procedure was not specifically addressing the emergency lighting inspections. Revision 16 of this pro-cedure was made specifically to address raceway lighting inspections j (Section 3.3.1). The TRT found that the loose terminations within the lighting termination boxes occurred as a result of an installation deficiency by craft personnel involving the Thomas and Betts RP-12 crimp-type insulated connectors. A document change notice (DCN) was issued changing the engineering instruc-tion used by craft personnel (EE-8) to improve installation of lighting terminations; thereafter the number of deficiency reports in lighting termination boxes was greatly reduced. (See also QA/QC Category 8, "As Built," for conclusions regarding craft personnel training.) The TRT found that the revisions to procedure QI-QP-11.3-40 regarding emergency lighting inspections were justified to eliminate unnecessary inspection requirements. Other Electrity1 Procedures (AQE-32, AQE-44 and Parts of AE-18 and AE-20). After a review of procedure QI-QP-11.14-12, " Reverification of Seismic Electrical Equipment Mounting Details," the TRT could find no requirements in Revision 0 through 4 that established a fixed frequency for reverifica-tion of inspections concerning bolt tightening of seismic electrical equipment mountings. However, the procedure provided for reverification of inspections on a " case-by-case" basis (AQE-32). The TRT also reviewed the following in process inspection procedures with respect to electrical equipment separation and the use of butt splices in panels (parts of AE-20 and AE-18):
4 (a) Procedure QI-QP-11.3-29, " Electrical Separation," (b) Procedure QI-QP-11.3-29.1, " Verify Electrical Separation," (c) Procedure QI-QP-11.3-28, " Class 1E Cable Tenninations." The TRT determined that in process inspection procedures QI-QP-11.3-29 and QI-QP-11.3-29.1, and post-construction procedure QI-QPk11.3-40, were used to identify deficiencies in the Fuel Handling Building and that these procedures allow the "use-as-is" disposition of nonconformance reports (NCRs). The subject of "use-as-is" disposition of NCRs (AQE-44) is dis-cussed in Electrical and Instrumentation Category 5, " Electrical Noncon-formance Report (NCR) Activities." The separation of electrical equipment and installation of terminations in accordance with procedures, drawings, and specifications are discussed in Electrical and Instrumentation Category 1, " Electrical Cable Termina-tions," for part of AE-18 and Ele:trical and Instrumentation Category 3,
" Electrical Equipment Separation," for part of AE-20.
In a TRT review of other electrical procedures, the TRT found no omissions in requirements for inspection of electrical equipment. . 5. Conclusions and Staff Positions: Based on its review of procedures for ; in process inspections, post-construction, and turnover inspections, the 1 TRT concludes that no significant concerns existed with electrical procedures. Ho<ever, equipment installation problems as related to.nonconformance with procedures are being addressed in the hardware-related E&I categories. The TRT, therefore, concludes that these electrical procedure ' lated allegations could not be substantiated. However, the results of this evaluation will be further assessed as part of the overall programmatic review concerning post-construction verification program addressed under l QA/QC, Category 8, "As Built." Therefore, the final acceptability of this evaluation will be predicated on the satisfactory results of the overall l
programmatic review on this subject. Any adjustments to these conclusions will be reported in a supplement to this SSER.
- 6. Actions Required: None.
- 7. Potential Violations: None.
- 8. Attachments: None.
- 9. Reference Documents:
- 1. TUGC0 Procedure No. CP-QP-11.3, Revision 4, August 12, 1983,
" Electrical Inspection Activities."
- 2. TUGC0 Procedure No. QI-QP-11.3-23, Revision 11, March 6, 1984,
" Class 1E Conduit Raceway Inspections."
- 3. TUGC0 Procedure No. QI-QP-11.3-26, Revision 22, June 8, 1984,
" Electrical Cable Installation Inspections."
- 4. TUGC0 Procedure.No. QI-QP-11.3-28, Revision 21, June 8, 1984,
" Class 1E Cable Terminations." -
- 5. TUGC0 Procedure No. QI-QP-11.3-29, Revision 15, January 18, 1984,
" Electrical Separation."
- 6. TUGC0 Procedure No. QI-QP-11.3-29.1, Revision 15, February 15, 1984, " Verify Electrical Separation."
- 7. TUGC0 Procedure No. QI-QP-11.3-38.1, Revision 1, February 21, 1984, " Installation of Class IE Electrical Equipment."
,,__,.c - - -
7-
- 8. TUGC0 Procedure No. QI-QP-11.3-40, Revision 18, May 18,1984, "Postconstruction Inspection of Electrical Equipment and Raceways."
- 9. TUGC0 Procedure No. QI-QP-11.3-50, Revision 10, February 8,1984, "Cabic Grip Support Installation Inspection."
t
- 10. TUGC0 Procedure No. QI-QP-11.14-12, Revision 4, July 28, 1983,
" Reverification of Seismic Electrical Equipment Mounting Details."
- 11. TUGC0 Startup Administrative Procedure No. CP-SAP-3, Revision 12, June 21, 1983, " Custody Transfer of Station Components."
- 12. TUGC0 Startup Administrative Procedure No. CP-SAP-6, Revision 9, March 10, 1983, " Control of Work on Station Components After Release from Construction to TUGCO."
- 13. TUGC0 Startup Administrative Procedure No. CP-SAP-21, Revision 2, February 29, 1984, " Conduct of Testing."
- 14. CPSES Station Administration Manual, Procedure No. STA-802, Revision 1, January 10, 1984, " Final Acceptance of Station Sys-tems, Structures and Equipment."
- 15. NRC Investigative Report 50-445/81-04 and 50-446/81-04, May 5, 1981.
- 16. Pre-filed Testimony before ASLB, May 24, 1982, Page 80.
- 17. GAP Notes of April 1984 (Confidential), Paragraph 6, GAP Witness H.
- 18. Confidential Affidavit of GAP Witness (Paragraph 6) of June 27, 1984.
- 19. GAP Notes of April 1984 (Confidential), Paragraph 7, GAP Witness H.
- 20. GAP Notes of April 1984 (Confidential), Paragraph 25, GAP Witness I.
8-
- 21. Confidential Affidavit of GAP Witness H, July 16, 1984, Pages 10-11.
- 22. NRC Special Review Team Report, July 13, 1984.
- 23. Deposition of SRT Witness A-5, July 17, 1984, Pages 55,000-55,164.
- 24. TUGC0 Office Memorandum # TUG-2134, " Transmittal of Final Report on Issues Resulting From Interviews with Electrical Inspectors," May 22, 1984.
1
- 25. Deposition of GAP Anonymous Witness, July 25, 1984, Pages 58,503-58,591.
- 26. Deposition of GAP Witness, July 16, 1984, Pages 53-003-53,263.
- 27. NRC Construction Appraisal Team (CAT) Inspection Report 50-445/83-18,
!. , 50-446/83-12, April 11, 1983.
- 28. TUGCO, et al, Hearing before the ASLB, NRC Staff Testimony Regarding the Findings of CAT; June 13, 1983, Pages 7733-7755; June 15, 1983, Pages 8160, 8231, 8261-8263; June 16, 1983, Pages 8358, 8367,
, 8368-8373.
- 29. NRC Interview with SRT A11eger A-3, September 6, 1984, Pages 9-12, 17-27, 30-40, 48-83.
- - - - - -,,,,n-.,, - - ---_,,,,, ,, .---.--,,r_-.---,, - -,--- - . - --- -- - , . -,,_- --,, --
9
- 30. This statement prepared by:
A. Johnson, Date TRT Technical Reviewer H. Li, Date TRT Technical Reviewer Reviewed by: J. Calvo, Date Group Leader Approved by:
, , V. Noonan, Date
._, Project Director O
O t. i i l F
na ,.. .-- + v4,: [ ELECTRICAL 9; Requestor's ID: ORDAZ Author's Name: A. Vietti/kb Document Comments: 1/9/85 AQE-7 and AQE-43 from CPI (REVISION 9/29-HQ) J l 4 4S 5 O E 1 e i 1 i 1
- 1. Allegation Category: Electrical and Instrumentation 9, Electrical Inspection Reports, Inspection Item Removal Notices and In-Process Inspections.
- 2. Allegation Number: AQE-7 and AQE-43
- 3. Characterization: It is alleged that the per procedure number of required in process inspections was not being conducted and that inspection reports (irs) were being written without re-inspections to close out inspection item removal notices (IRNs).
- 4. Assessment of Safety significance: The implied safety significance of these general allegations is that a reduction of in process inspections and an omission of re-inspections could compromise the quality of the installation of safety-related components.
In-Process Inspections (AQE-7). The NRC Technical Review Team (TRT) examined current and past inspection procedures in the electrical area to determine the number of in process inspections required. The TRT found that Texas Utilities Generating Company (TUGCO) procedure QI-QP-11.3-28, " Class IE Cable Terminations," was the only electrical inspection procedure which defined a specific number of required in process inspections. Through Revision 4 (dated July 16, 1980), the procedure required a minimum of 10 in process inspections per shift; revision 5 of the procedure (August 7, 1980) changed the quantity required to "a weekly" in process inspection. i The TRT interviewed quality control (QC) personnel to learn the basis for the substantial revision to the procedure. However, the individuals responsible for this revision were no longer employed at Comanche Peak Steam Electric Station (CPSES) and could not be contacted. Current QC personnel could only speculate that an increase in level of confidence was the basis for the reduction in inspections. The TRT interviewed the project engineering manager to determine the the amount of Class 1E cable
, , , _ _ , , - , . _ _ _ - __m. _ _.. . _ . - . _
termination activity at the time the procedure was revised. From the discussion, the TRT determined that there was less cable termination activity in early 1980 (before the procedure was revised) than in late 1980 to mid-1981, when cable termination activity was approaching its peak. Comparing the number of NCRs for cable termination activity for 2 years before revision 5 with the results of the quality assurance (QA) trend reports for 1980 (third and fourth quarters) and 1981 (first and second quarters), the TRT determined that the number of NCRs for cable termination activity remaineif the same during this period, despite the much smaller number of in process inspections. This may be indicative that the fewer inspections under revision 5 were much more thorough than those before revision 5. However, the TRT could not substantiate the improvement of the quality of the installation in view of the problems found with the electrical terminations discussed in Electrical and Instrumentation Category 1, " Electrical Cable Terminations." Inspection Reports and Inspection Item Removal Notices (AQE-43). The TRT examined TUGC0 procedure CP-QP-18.0, " Inspected Item Removal Notice Form," for its adequacy to control the inspection process. The TRT determined that this procedure was adequate to assure that reinspections were performed, when required, to verify that the item subject to the IRN was still in conformance with the requirements. The TRT also interviewed two paper flow group (PFG) coordinators, a PFG IR clerk,-and a lead QC electrical inspector, and examined 20 irs and IRNs. The TRT determined that because of the checking and paper pro-cessing involved with irs and IRNs, a PFG coordinator,would not be able to recognize that a' signed-off inspection report had been completed without reinspection actually occurring. After discussing this issue with QC inspectors, the TRT determined that an inspection could be made 1 without an inspection report in hand and after that inspection a report could be completed away from the inspection site, from which the inference could be made that an inspection had not been made. The TRT found that there are no requirements in the procedures that inspection i l l
1 reports be in-hand before re-inspections are conducted; hence, it can be construed that inspections may have been performed also without all required documentation in-hand. The TRT contacted the alleger, who provided no additional information about the allegation. Further, the alleger acknowledged'when making the allegation and again during discussions with the TRT that this allegation was based on hearsay information.
- 5. Conclusions and Staff Positions: Based on its review of the pertinent documents and interviews, the TRT concludes that the allegations about changing the frequency of in process inspections for cable terminations were unsubstantiated. However, cable termination problems that could be related to the concerns highlighted by these allegations are discussed in Electrical and Instrumentation Category 1, " Electrical Cable Terminations."
The results of this evaluation will be further assessed as part of the overall programatic review of TUEC's deficiency identification program in process inspections addressed under QA/QC Category 5, "Nonconformance Reports." Therefore, the final acceptability of this evaluation will be predicated on the results of the overall programmatic review of this sub-ject. Any modifications to these conclusions will be reported in a supplement to this SSER.
- 6. Actions Required: The actions required in Electrical and Instrumentation Category 1, " Electrical Cable Terminations," will address the concerns with regard to reduction in cable termination inspections discussed above.
- 7. Potential Violations: None.
- 8. Attachments: None.
- 9. Reference Documents:
- 1. TUGC0 Procedure CP-QP-18.0, " Inspection Report."
- 2. Brown and Root (B&R) Procedure CP-CPM-6.10, " Inspection Item Removal Notice Form."
- 3. NRC Investigative Report 50-445/81-04 and 50-446/81-04, May 5, 1981.
- 4. NRC Special Review Team Report, July 13, 1984.
- 5. TUGC0 Office Memorandum # TUG-2134, " Transmittal of Final Report on Issues Resulting From Interviews with Electrical Inspectors" May 22, 1984.
- 6. NRC Construction Appraisal Team (CAT) Inspection Report 50-445/83-18, 50-446/83-12, April 11, 1983.
- 7. TUGCO, et al, Hearing before the ASLB, NRC Staff Testimony Regarding I
the Findings of CAT; June ?.3,1983, Pages 7733-7755; June 15,1983, Pages 8160, 8231, 8261-8263; June 16, 1983, Pages 8358, 8367, 8368-8373.
- 8. NRC Interview with SRT A11eger A-3, September 6, 1984, Pages 8, 21, 42-45, 48-79, 81-83.
- 10. This statement prepared by:
g, Q'Q) 'J . S el = r TRT Technical Reviewer Date Reviewed by:
- J. Calvo, Date i - Group Leader l
Approved by: V. Noonan, Date Project Director I t l _ _ _ . - , - - . - .-,m. , - - - - - - - - - =
- P-" '" -- * - - - -
Re: F01A-85-312
.. APPENDIX A-2 Contention 5 Panel Background Reading
- 1. Case Proposed Findings on Intimidation - 9/4/84 ANO 8409070160
- 2. Applicants Proposed Findings on Intimidation - 9/4/84 ANO 8409050518
- 3. SIT Report - 2/15/83 ANO 8302250237
- 4. Order Subseouent to the Prehearing Conference of 4/30/80 - 6/16/80 ANO 8401260285 '
- 5. LBP'84- Memorandum Reopening Discovery; Misleading Statement 12/18/84 AND 8412190262
- 6. Letter to M.D. Spence, TUGC0 re: Comanche Peak'Special Review Team Report ANO 8407250034
- 7. CYGNA 3 scope ANO 8407311061
*
- 8 .- SER CPSES Units 1 & 2 50-445/446 - 12/1/84 (CYGNA phases I. II)
- 9. NRC Staff Comments on Supplement to Applicants Plan to Respond to Memorandum and Order Quality Assurance for Design - 4/6/84
~
ANO 8404110592
- 10. NRC Staff Comments on Applicant's Plan to Respond to Memorandum and Order (Quality Assurance for Design) - 3/9/84 AN0 8403140055
- 11. ASLB - Supplement to Applicant's Plan tv Respond to Memorandum and Order (Quality Assurance for Design) - 3/14/84 ANO 8403150032 ,
- 12. ASLB- Applicant's Plan to Respond to Memorandum and Order (Quality Assurance for Design) 2/3/84 ANO 8402070227
**13. Letter to: TUEC (Spence) Reply to 50-445 (84-32) 50-446 (84-11), from:
Hunter 14 Letter to: TUGC0 - R.J. Gary, from: DeYoung RE: Construction Appraisal Insp.50-445-83-18, 50-446-83 4/11/84 (CAT) ANO 3305120445
- 15. Transcript - Hearing Board's Acceptance of Applicant's Plan - 4/27/84 l ANO 8505020224
- 16. CYGNA Briefing Summary - 12/84 AN0 8505060080
- 17. Memorandum - (Clarification of Open Issues) - 3/16/84 ANO 8403190002
**18. Evaluation of CYGNA's Comanche Peak Independent Assessment Program (Phase 3)
- 19. ComanchePeah,CesignOAASLBDecision- 12/28/83 AN0 8312300060
- 20. SALP Repnrt - 1/31/83 ANO 8302170s53
- 21. SALP Report - 5/30/84 ANO 8406050518 -
- 22. EGAG Intimidiation Report - 9/84 ANO 8409190092
Re: F01A-85-312 a
, APPENDIX A-2 (Continued)
All0 850114028
- 23. TRT QA/QC Letter to TUGC0 1/8/85
- 24. TRT Draft Electrical SSER's
- 25. 50.55(e) Report Items .
l l 26. Applicant Organization Charts ANO 8410020131
- 27. TRT Elec'trical/ Civil, Structural, Test Findin'gs Letter to TUGC0 (9/13/84) ANO 8412070315
- 28. TRT Coatings, Misc. Letter to TUGC0 11/29/84 AN G 12070315
** 29. Draft SSER on CYGNA Phases 1, 2, 3
- 30. NDT Inspection Report 7/11/83 (Attachment placed in PDR)
- 31. Letter fron: CYGNA to V. Noonan 1/18/85 Open Items ANO 8501230032
** 3 2. 01 Report 4-84-6 on Intimidation 3/7/84
- 33. Letter from CYGNA to J. George 1/18/85 ANO 8501300530
- 34. Staff Exhibit 180 ANO 8205260114
- 35. SALP 4/82 ANO 8205110432
- 36. . Trend Reports.
- 37. Exhibits 181, 182 , 185 , 188, 192 , 194 , 196 Ari0 12180309
- 38. Staff's Proposed Findings 2/24/83 ANO 8302280398 l
- 39. Vendor List
- 40. TUGC0 Program Plan 10-34 ANO 8410120227 41 . TUGC0 Program Plan 11-84 ANO 8411260053 ,
! 42. NP,C comments on Program Plan 1/24/85 ANO 8502010314 l
- 43. List of 0! Cases in Region IV
- 44. Prehearing Briefing 11-9-84
- Documents 24.25,30,36,39,44 to be placed in PDR folder 85-312 under the name of B. Garde
** Documents 8,13,18,43,29 and 32 to be addressed in further response
___j
r -
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A
~
is THIS DOCUNENT WAS PRODUCED BY THE , N U. S. NUCLEAR RECULATORY COMNISSION'S l DOCUNENT CONTROL SYSTEM d 50-946 i s OPERATED BY ,n TECHNASSOCIATES, INC./ PRC UNDER CONTRACT NO. NRC-IO-84-211 I FOR THE DIVISION OF TECHNICAL INFORMATION AND DOCUNENT CONTROL
. OFFICE OF ADNINISTRATION C
e f:r3cu) l
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. f 1/ 6/Z5 PACE 1
- ()
- U. - S. NUCLEAR CECULATORY CDMNISSIDN
. PRELIMINARY TITLE LIST REPDRT 8 i.
50-446 Comanche Peak Steam Electric Station. Unit 2 DTC AA1: DIN: RA1: Eli TRDEFR EUTTUCC DEFR-791113 0002190053 Suppl to 790917 deficiency rept te omission of shear tie FILE /P: 8002190353 rothforcing steel in reac tor containment hids. Addl FICHE: 04016 327 04016 327 reassignments made & training being performed to prevent TASK: recurrence.!mplementation audit deadline is 791229 CARY.R.J. Tevas Utilities Electric Co. (forme 791113 1p. TRDEFR EUTTUCC DEFR-791114 791th10474 Second interim deficiency rept te electrical cable tray FILE /P: 7911210965A hengers w/ light partial p enetration welds where f ull FICHE: 01377 195 01377 196 penetration welds reguired. Caused by incorrect TASK: interpretation of weld symbols. Weld procedure revised. e Tesas Utilities Electric Co. iforme 791114 2pp. t 9 $ D e O h n 9 9 I e l.' h g e. 8 I I 8 6
^ ~
dy 4/h. 1/ 6615 PAGE I
- Dh U. G. NUCLEAR RECULATORV CDMNISSION 1' 3 FCELIMINARY TITLE LIOT REPORT
() q 4 50-OC6 Comanche Peak Stea.a Electric Station. Unit 2 - __._._ ..... ... _...____ e
!. DTC AAi: DIN: RA1: SN THDEFR EUTTU0C cEFft-BOO 104 000122043S Deficiency r ep t: en 780404. design change isewed permitting FILE /P: DOO1220427A
. wall lhtenness variations w/ potential for locallaed pipe FICHE: 01700 236 01780 237
- stresses.f6 ping found in violation of original requirements. TASK:
Coolgn changes rescinded, o
- Tesas utilities Electric Co. (forme COO 114 23 7 TRDEFR EUTTUGC DEFR-ROO114
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0003190094 Interim deficiency rept re violation of piping ein well FILE /P: BOO 3190070A thittnese.Addl changes implemented requiring thet future FitHE: 04257 095 04257 096 maids violating min well thickness be repaired. Corrective TASM: acticns will be acceeptisSed bg not functaonal testing. o Tomas utilities Electric Co. (ferme 900!!4 2pp. TKDET H EUTTUCC DEFR-900123-01 E001310272 Clarifies D00114 Itr re vietation of piping min wall FILE /P: B001310272 thic)nssa. reported per 10CFR50.55(e), Attached rept antended FICHE: 01941 219 01841 219 to ta class 171ed as interie.Will subut t reogressive repts me TA5K: s wolds era dispositioned theaugh ingineating review. GjR Y. R J. Tesis Utilities Electric Cn. (eerse 900123 2pp. TRDEFR EUTTUCC DEFR-900321 UOO4010299 D= fis iepry rep t: en G33228.04 insp revealed control'toerJ FILE /P: eOO4010295A etidad coi.nectiens not meeting seismic design crittria.Cause FICHE: 44348 195 04})8 196 i=nstated.Controi kaa-d supellera & AE reviewi.ng as-built TA5K: yeld configurations.Recork will be com>Ieted 4 s 800301.
- Tesas utilitiet Electrii *o. (ferme 900321 2pp.
TRDEFR EUTTUCC DEFR-900415 . 4 COO 4220a2J Interim deficiencg tept to piping ejn wall thirknest. Review FILE /P: B004220123 of weld a base metal repair records is continuing.Another FICHE: Oa661 197 04661 197 pr*Erses rest will be subastted tv S00623. TABM: r CARY.R.J. lesas Utilities Electric Co. (force 900414 1p. , , s 6
r? I ,3h i e 1/ 6/G3 PACE 2 9 [ U. . S. NUCLE AR T:EC"JLATORY COMMISSION
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- PRELIMINARY TITLE LIST REFDRT ,
50-C4 ' Comanche Pean Steam Electric Station. Unit 2 _ - _ _ _ _ _ _ _ _ DTC AA1: DIN' RA1: SN TRCEFR EUTTUCC DEFR-900415-01 B0051 r., an*.wria deficiency rept supplementing 800114 L 23 repts re FILE /P: 0005140234 violation piping min wall thienness.Twent, safety- FICHE: 04952 208 04952 200
- rotated sgo w/ welds evaluated by physical or witrasonic TAGM:
methods.Five sgo were within Tech Specs. CARY.R.J. Texas Utilities Electric Co. (forme 800415 Ip. 9
- TEDEFR'EUTTUCC DEFR-900421 DOO42h0254 Deficience rept te concrete honeyceeb ing in steam generator FILE /P: 0004290250A compartment walls op Unit 2 reactor containment 41d3 FICHE: 04704 119 04704 121 Censultent sorvey showed no critical internal defects.Util TAGM:
to repair condition w/ dry-pack mortar.grovt & concrete, o Tomas Utilities Electric Co. (forme B00421 3pp. . TRDEFR EUTTUCC DEFR-900421-01 0004290271 Interim deficiency rept re installation of drilled-in FILE /P: B004290271 onpansion anchors. Matter was corrected 770616 by revieton to FICHE: installation procedure. Formal rept to be filed bg 901235. TASM: C AR Y. R. J. Temas Utilities Electric Co. (forme 900421 1p. TRDEFR EUTTUCC CEFR-900421-02 0000290437 Interim deficiency rept re installation & insp of welded FTLE/P: 9004290430A
'c en4u t t supports.Hajor support was fabricated w/o formalised F ICHE: 04706 055 04706 055 instructiens & ins, records for number of smaller welded TASM:
supports were not directly traceable to as-built conditlens. CARY.R.J. Tesas Utilities Electeic Co. (forme B00421 13. TRDErR EUTTUCC DEFR-800421-03 c. U006060570 Ceficiency rept ce apparent distf erency in installation & FIL E(P: 8006060570 ens, regelrements for Clast 5 non nuclear safety-related FICHE: 05256 146 05256 146 piping supports. Formal rest should be subeltted by 800715. TAbM: CARY.R.J. Tomas estilitids Electric CD. iforme 9004)k 19 3-l
# 1/ s/!S PAGE 3
- U. S. NUCLEAR REQULATOH'Y CDMMISSIDN g PZELININARY TITLE LIST REPORT 50-Ogo Comanche Peak Steam Electric Station. Unit 2 *
=- - s 3* DTC AA1: DIN: RA1: Sti 4
TREEFR CUTTUCC DEFR-DOO502 4 9006230156 Deficiency rept te welded control board connections.vydating FILE /P: 8006233156 800321 rept. Wort wi!! he completed by 800701. FICHE: 05429 179 05429 179 TASK:
- C AR Y.'R. J. Tesas Utilities Electric Co. (forme 900502 1p.
e TRDEFR EUTTUGC DEFR-BOO 619
- e B0062'0242 Supplemental deficiency rept re 1991-03 2300 NW installation FILE /P: 9006240242 piping min wall. Engineering review & disposition of min FICHE: 05433 350 05433 350 wall, violations at welds & base metal defects is continuing. TASK:
- Anticipates submitting nest progress rept by 801219.
CARY.R.J. Tesas Utilities Electric Co. (forme 000619 1p, e TRDEFR EUTTUCC DEFR-BOO 626 e E007000062 Final deficiency rept re Unit 2 reactor vessel outlet FILE /P: 9007003362 nsa t tes w/short safe-ends. Investigation determined that FICHE: 05672 349 05672 349 estter not reportable per 10CFR50. 55(el.Suppor ting records TASK: s cvoilable at site. C R Y. R. J. Tesas Utilities Electric Co. (forme 000626 1p. TRDEFR EUTTUCC DETR-BOO 714 e 8007210352 Updates 800421 deficiency rept te discrepancies involving FILE /P: B007210352 installation & insp requirements f or Class 5 non-nuclear FICHE: 05916 357 05916 357 4 screeg-related piping supports.FSAR is being revised. Final TASK:
- nwyt will se forwarded by 800922.
CARY.R.J. Tesas Utilities Electric Co. (forme 9007I4 1p.
. TRDEFA EUTTUCC DEFR-BOO 725 B000050004 Interim deficiency rept re installation of welded conduit FILE /P: B000050304 cepports. Major support fabrirated w/o formalised instruction FICHE: 06145 024 06145 026 *
& insp records not directly traceable to as-built TASK:
sccnditions. Engineering drawings developed & insp revised. CARY.R.J. Texas Utilities Electric Co. (forme 800725 3pp. ,
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O. NUCLEAR RECULAICm V COMNISSION
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PPELIMINARY TITLE LIST REPORT
' 50-446 Comanche Peat Steam Electric Station. Unit 2 e
DTC AA1: DIN: RA1: SN
- TRDEFR EUTTUCC DEFR-BOO 909 0008'190370 Deficiency rept te use of architectural concrete in floor FILE /P: 9009190370 ola'bs when determining embedment length of Hitti bolts. FICHE: 06366 048 06366 050 Survey of bolts is being conducted. Bolt installation TASM:
procedure was revised to reflect embedment lengths. CARY.R.J. Texas Utilities Electrac Co. (forme 800008 3pp. f
, TRDEFR EUTTUCC DEFR-900919 8001230301 Deficiency rept te discrepancies in installation & insp FILE /P: 9009230301 reguirements for Class V safety-related piping supports. FICHE: 06601 113 06601 114 Ccused by inadequate documentation to ascertain that TASM:
supports satisfg design & seismic load requirements. , CARY.R.J. Texas Utilities Electric Co. (forme 800918 2pp. T , , f TRDEFR EUTTUCC DEFR-901010 NOIR 4C 6010170502 Deficiency rept te Roto-lock insert locntng tab installed at FILE /P: 9010170502 f acility. Problem shovId not be classified as potentially FICHE: 06737 242 06737 242 reportable deficiency. Supporting documentation available at TASM: plant site. CARY.R.J. Temas Utilities Electric Co. (forme 808010 1p. TRDEFR EUTTUCC DEFR-901013 N0!R4C 8010170479 Deficiency rept re Plascite 7122 coating. Ongoing evaluation FILE /P: 0010170479 of lining problem will be completed & formal rept forwarded FICHE: 06737 125 .06737 125 by 801114. TASK:
.CARY.R.J. Tomas Utilities Electric Co. (forme 001013 1p.
m TRDEFR EUTTUCC DEFR-801015 N0!R4C S010200416 Deficiency rept re thread engagement of sway struts. FILE /P: B010200416 Candition not reportable under 10CFR50. 55e. as reported on FICHE: 06756 204 06756 204 800919. TASM:
. CARY.R.J. Texas Utilities Electric Co. (forme 801015 1p.
it crus rn.c a gg 5 U. S. NUCLEAR CECULATDRY CDn1169tDN {.
- h FCELIMINARY TITLE LIST EEPORT g f e 50-4a6 Comanche resh steam Electric Station. Unit 2
____..v_ ** DTC AA1: DIN. R A1: SN 4 TREFrR EUTTUCC DEFR-001021 HOIR4C e 9010260354 Interim deficiency rept to deretts in installation of Hittia FILE /P: 0010280354 FICHE: 06012 344 06912 346
.M it concrete anchor holts. tdentified anchor belts have been TASK:
rseoved.Gupport will be reworked &/or relocated to meet regu) red design criteria. Followup rept provided by 010123. C AR Y. R. J. Tomas Utilities Electric Co. iforme 801021 3pp. . TRDEFR EUTTUCC DEFR-901071-01 NOIR 4C 1 8080280350 Deficiency rest te diesel generator pipe supports.Deficiencg FILE /P: 8010290358 is being evaluated te f ormulate currective action. Forma! FICHE: 06812 347 06812 347 rept' will be provided 6g 910116. TASK: CARY.R.J. Tesas Utilities Electric Co. iforme 901021 1p. 1RDEFR EUT1UCC DEFR-801029 HUIR1C 001fC30505 Final deficiency rept te Plasite 7122 lining in ave water FILE /P: Rott033905 syslptping. Condition is not reportable per 10CFR50.55e. FICHE: 06861 139 06061 139 TASK: g Sxpporting documentation available at plant site. CARY.R.J. Temas Utilities Electric Co. iforme 901029 1p.
- TRDEFR EUTTUCC DFFR-BC1210 N0!R4C 9012100245 Deficiency rept. superseding B00421 submittal.re installation FILE /P: 8012100245 of drilled-in espansion anchors. initially reported on FICHE: 07272 353 07272 354 791107. Installation procedure was revised to reflect min TASM:
bpacing requirements between various anchor types. C ARY. R. J. Texas Utilities Electric Co. iforme 801210 2pp. TRDEFR EUTTUCC DEFR-801216 MOIPdC B012290169 Interim deficiency rept te violation of piping min wall FILE /P: B012290169 FICHE: 07343 361 07343 351 thickness. Engineering review & disposition of min wall TASM: violations at welds continuing. Nest progress rept to be l # oubmitted by 910615. CARY. R. J. Texas Utilities Electric Co. iforme B01216 1p. ,
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f"a c h',{It g 1/ 6/05 . PACE 1 i U. - S. NUCLEAR RECULATDR/ CONNISSION
. PRELINIrlARY TITLE LIST REPDRT '
f. 50-446 Comanche resh 8 team Electric Station. Unit 2
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DTC AA1: DIN: RA1: SN TRDEFR EUTTUCC DEFR-810112 NOIR 4C 0101200246 Interim deficiency rept re afg deficiency of component FILE /P: 8101200246 supports associated w/ausiliary piping sys diesel FICHE: 07487 091 07487 091 generators. initially reported 800926. Evaluation w!!! be TASK: completed by 010731. CARY.R.J. Tesas Utilities Electric Co. (forme 810112 1p. I TRDEFR EUTTUCC DEFR-810112-01 NOIR 4C C101200253 Interim deficiency rept re unauthorized field mods to FILE /P: 8101200253 Hilti-Kwik concrete anchor bolts. initially reported 801001. FICHE: 07487 089 07487 090 Dalts have not been modified in unauthorized manner. TASK: Follow-up rept will be submitted by 810417. CARY.R.J. Texas Utilities Electric Co. (forme 810112 2pp. i f TRDEFR EUTTUCC DEFR-810218 NCIR4C 8102250206 Interim deficiency rept. originally reported in 810120 telcon FILE /P: 8102250206 to RQ Taylor.re use of cable lubricant Yellow 77. Lubricant FICHE: 07755 174 07755 174 (ambustible in dry state. Evaluation continues & completion TASK: enticipated by 810515. CARY.R.J. Tesas Utilities Electric Co. (forme 810218 1p.
, TRDEFR EUTTUCC DEFR-810218-01 NOIR 4C Gj02250257 Interim deficiency rept. originally reported in 810120 telcon FILE /P: 8102250257 to CR Taylor.re compressive streng th of pipe support FICHE: 07755 172 07755 172 baseplate grouting matl at elevated temps. Investigation TASK:
ccmpleted & deficiency determined not reportable.
, ,CARY.R.J. Tesas Utilities Electric Co. (forme 810218 1p.
., TRDEFR EUTTUCC DEFR-810218-02 NOIR 4C p103100666 Final deficiency rept re compressive strength of pipe FILE /P: 8103183666 support baseplate grouting matt subjected to elevated temps. FICHE: 07954 182 07954 182 initially reported 810120. Condition found not reportable TASK:
under 10CFR50.55(e). C AR Y, R. J. Temas Ut111 ties Electric Co. (porme 810218 1p.
1/ 6/85 PACE 2 r7 1( U. B. NUCLEAR REQULATORY COMMISSION h ,f
'l PRELIMINARY TITLE LIST REPORT 50,-446 Comanche Peak Steam Electric Station. Unit 2 a
f, DTC AA1: DIN: RA1: St4 TRDEFR EUTTUCC DEFR-810313 NIEIRPS2 8103240474 Interim deficiency rept.origiially reported 810217 re FILE /P: 8103240474
;Wastinghouse valves that failed to close completely under FICHE: 07982 263 07982 265
= pro-operational test conditions. Westinghouse investigating. TA9K:
Prehlem lie s wi th in Licii torgue operators. Hods scheduled. CARV.R.J. Texas Utilities Electric Co. (forme 810313 3pp. TRDEFR EUTTUCC DEFR-810415 NOIR 4 8104210337 Interim deficiency rept re unauthorized field mods of FILE /P: 8104210337 Hitti-Mwik concrete anchor bolts. initially reported on FICHE: 08300 340 08308 341 801001. Anomalies will be identified & dispositioned per TASK: prs'c edut os for conforming items by 811201. CARY.R.J. Texas Utilities Electric Co. (forme 810415 2pp. TRDEFR EUTTUCC DEFR-810421 NOIR 4 C10j270369 Interim deficiency rept re possible use of short heating FILE /P: 8104270369 ventilation & air conditioning bolts. initially reported on FICHE: 08369 091 08369 091 810324. Engineering evaluation continuing. Resolution by TASK: g 810626. CARY R.J. Texas Utilities Electric Co. (forme 810421 1p.
. TRDEFR EUTTUCC DEFR-810424 NOIR 4 8105040437 Interim deficiency rept re heating ventilation & air FILE /P: 8105040437 conditioning cooling sys. initially reported on 810330. FICHE: 08438 160 08438 161 Engineering studies f or re-evaluation of ags d esign f or TASK:
CPSES to be complesed by 810630. DARY R.J. Ionas Utilities Electric Co. (forme 810424 2pp. TRDEFR EUTTUCC DEFR-810504 NIE4RP C105120298 Deficiency rept re failure of 6.9 kV circuit breaker. FILE /P: 8105120298 initially reporten on 810400. Condition is not reportable per FICHE: 08517 317 08517 317 10CFR50.55e. Records supporting determination are available TASK: for NRC review at plant site. CARY.R.J. Texas Utilities Electric Co. (forme 810504 1p. ,
4 1/ 6/05 PACE 3 U. ' S. NUCLEAR RECULATORY COMMISSION
- PRELIMINARY TITLE LIOT REPORT 50-446 Comanche Peak Steam Electric Station. Uni t 2
, DTC AA1: DIN: RA1: SN i TRDEFR EUTTUCC DEFR-810513 HIEIRPI 8105190236 Interim deficiency rept re use of potentially combustible FILE /P: 8105190236 Yellow 77 cable lubricant. initially reported on 810120. FICHE: 08558 133 08550 133 Evaluation will be completed by 810831. TASK: CARY.R.J. Tesas Utilities Electric Co. (forme 810513 1p. t TRDEFR EUTTUCC DEFR-810521 NIE4RP 810$h60465InterimreptreWestinghousevalvesfailure to close FILE /P: 8105260165 cempletely under preoperational test conditions. initially FICHE: 08595 359 08595 360 reported on 810217. Westinghouse has modified 4-inch valves TASK: for use as prototypes. Final rept to be submitted by 811016. CARY.R.J. Tesas Utilities Electric Co. fforme 810521 2pp.
, l TRDEFR EUTTUCC DEFR-810603 NIE4RP 8106090606 Final deficiency rept te violation of piping min well FILE /P: 8106090606
}hickness initially reported on 790522. Revisions to ' FICHE: 08744 055 08744 058 rebrication & documents completed. Final stress analyses are TASK:
targeted for completion prior to hot functional testing. CARY.R.J. Tesas Utilities Electric Co. (forme 810603 4pp. 4 TRDEFR EUTTUCC DEFR-810608 NIE4RP 8106150401 Deficiency rept re defective Bahnson Syc Co heating. FILE /P: 8106150101 ventilation & air conditioning supports initially reported FICHE: 08778 361 08778 362 en 810324. Bahnson procedures have been revised to include TASK: documentation of concrete anchor bolt site.
.CARY.R.J. Texas Utilities Electric Co. (forme 810600 2pp.
I TRDEFR EUTTUCC DEkR-810619 NIE4RP B109150365 Deficiency rept re vol control tank level control sys. FILE /P: 8109150365 originally reported on 810522. Postulated event sequence FICHE: 09740 005 09740 005 evaluation indicates that malfunction would not cause safety TASK: hogard. Reportable under Part 21 but not under IOCFR50.55e.
- CAR Y. R. J. Tesas Utilities Electric Co. (forme 810619 1p.
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; PRELIMINARY TITLE LIST REPDRT 50-446 Cemanche Peak Steam Electric Station. Unit 2 DTC AA1: DIN: RA1: SN E*
TRDEFR EUTTUCC DEFR-810623 NIE4RP B106290356 Interim deficiency rept re heating / ventilation / air- FILE /P: 8106290356 c an d i,t i on i n g cooling sys. initially reported on 810330.Cause FICHE: 08068 189 08868 189 tattributed to design evolution. Corrective actions to be TASK:
'ccepleted as described in 810424 interim rept.
C AR Y,. R. J. Tesas Utilities Electric Co. (forme 810623 Ip. . TRDEFR EUTTUCC DEFR-810701 NIE4RP 8107280100 Final deficiency rept re specified mati for pipe spool FILE /P: 8107280100 fienges. initially reported on 810604. Natter considered not FICHE: 09171 345 09171 345 rep'ortable under 10CFR50.55(el. TASK: CAR .R.J. Tevas Utilities Electric Co. (forme 810701 1p. TRDEFR EUTTUCC DEFR-810701-01 NIE4RP C107200115 Finas deficiency rept re use of Yellow 77 cable lubricant. FILE /P: 8107200115 initially reported on BIO 110. Natter considered not FICHE: 09173 041 09173 041 repo,rtable under 10CFR50.55(el. TA8K: g CARY.R.J. Texas Utilities Electric Co. (forme 810701 1p. e TRDEFR EUTTUCC DEFR-810701-02 NIE4RP 8107200616 Final deficiency rept re seismic instrument tubing support. FILE /P: 8107280#16 initially reported 810604. Engineering documents will be FICHE: 09177 294 09177 296
/ evaluated & revised. Completed installations will be TASK: '
surveyed.Noncompliant conditions will be reworted. 9ARY. R. J. Tesas Utilities Electric Co. (forme 810701 3pp. TRDEFR EUTTUCC DEFR-810729 NIE4RP . e
- 8100110468 Interim deficiency rept re alignment difficulties in diesel FILE /P
- 8108110468 generator pipe supports. originally reported on 800926. Weld FICHE: 09330 241 09330 242 program initiated & supporting documentation compiled to TASK:
- certify compliance w/ASNE code.
7CARY.R.J. Texas Utilities Electric Co. (forme 810729 2pp. e ' 4 4
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- 0; S. NUCLEAR RECULATORY CDNHISSION 8 ..
PREllHINARY TITLE LIST REPORT i. I 50-446 Comanche Peak Steam Electric Station. Unit 2 DTC AA1: DIN: RA1: SN , , TRDEFR EUTTUCC DEFR-810831 HIE 4RP 8101090407 Final deficiency rept re pull-out performance of Hitti FILE /P: 8109090187 Kwik-Dolt anchors, initially reported 801217. Co nd i t i o n is not FICHE: 09657 296 09657 296 significant deficiency & is not reportable per TASK: 10CFR50.55(e). , C A,R Y, R. J. Tesas Utliities Electric Co. (forme 810831 1p. o TRDEFR EUTTUCC DEFR-810831-01 NIE4RP 810Y160004 Interim deficiency rept re failure of Westinghouse valve FILE /P: 8109160384 to close completely under preoperational test conditions, FICHE: 09576 059 09576 059 initia*1g reported 810217. Evaluation of other valves for TASK: closure sroblem continuing. Final rept by 811016. CARY,R.J. Texas Utilities Electric Co. (forme 810831 1p. , f TRDEFR EUTTUCC DEFR-810831-01 NIE4RP 01 0109160004 Interim deficiency rept re failure of Westinghouse valve FILE /P: 8109160004 to close completely under preoperational test conditions, FICHE: 09576 059 09576 059 I .' initially reported 810217. Evaluation of other valves for TASK: closure problem continuing. Final rept by 811016. CARY,R.J. lesas Utilities Electric Co. (forme 810831 1p. , TRDEFR EUTTUCC DEFR-810928 NIE4RP d110060262 Final deficiency rept re failure of Westinghouse gate valve FILE /P: 8110060262 to completely close under preoperational test conditions, FICHE: 10045 254 20045 256 initially reported on 810217. Westinghouse has issued Field TASK: Cha ig e Notices 10515 & 10537 detailing corrective actions. CARY.R.J. Tenas Utilities Electric Co. (forme 810928 3pp. , s. TRDEFR EUTTUCC DEFR-810928 NIE4RP 01
;8110060262 Final deficiency rept te failure of Westinghouse gate valve FILE /P: 8110060262 to completely close under preoperational test conditions. FICHE: 10045 254 10045 256 initially reported on 810217. Westinghouse has issued Field TASK:
Change Notices 10515 & 10537 detailing corrective actions. CARY,R.J. Texas Utilities Electric Co. (forme 810928 3pp. l I) . i
1/ 6/85 PACE 6 sJ -
- U. S. NOCLEAR RECULATOdY CONNISSION
! e b
PREllHINARY TITLE LIST REPDRT 50.446 Comanche Peak Steam Electric Station. Unit 2 e
- h. DTC AA1: DIN: RA1: SN TRDEFR EUTTUCC DEFR-811002 NIE4RP 8110140155 Modified deficiency rept re diesel generator pipe support FILE /P: 8110140155 clignhent initially reported 800926. Hanufacturer did not FICHE: 10159 310 10159 312
'cemply w/ASNE stress attawables. Calculations & ueld insp TASK: e precedures revised.
CARY#R.J. Texas Utilities Electric Co. (forme 811002 3pp. 9 TRDEFR EUTTUCC DEFR-811204 NIE4RP C112160285 Final deficiency rept re unauthorized field mods to Hitti- FILE /P: 8112160285 Kwit concrete anchor bolts during installation. initially FICHE: 11245 243 11245 248 reported on 001001. Bolts removed or cut off & driven into TASK:
- c onc'r e t e structures.
CARY.R.J. Texas Utilities Electrie. Co. (forme 811204 6pp. TRDEFR EUTTUCC DEFR-811231 NIE4RP 8701J30126 Interim deficiency rept to eight underspecified 3/4-inch FILE /P: 8201130126 ausiliary feedwater og s valves. initia!!y repor ted on 811207. FICHE: 11564 281 11564 281 Evaluation ongoing. Completion anticipated by 820305. TASK: s C AR Y. R. J. Tenen Utilities Electric Co. (forme 811231 1p. s . e i 9 e f e i e '. , t O e i lZ.
't .We.
1 b 1/ 6/85 PACE 1 , / U- S. NUCLEAR RECULA10RY COMMISSION PRELIMINARY TITLE LIST REPDRT 8 50-4 6' Comanche Peak Steam Electric Station. Unit 2 , DTC AA1: DIN: RA1: SN , TRDEFR EUTTUCC DEFR-820219 NE R4R 8203Q10023 Deficiency rept re mat! procured by AFC0 Steet. Deficiency FILE /P: 8203010323 determined not reportable per 10CFR50.55(e). FICHE: 12070 135 12070 135 TASK: CARY,R.J. Texas 9tilities Electric Co. (forme 820219 1p. , TRDEFR EUTTUCC DEFR-820219 NE R4R 01 8203d10023 Deficiency rept ce mati procured by AFC0 Steel. Deficiency FILE /P: 8203010323 datermined not reportable per 10CFR50.55(e). FICHE: 12070 135 12070 135 TA9K: CARY,R.J. Texas Utilities Electric Co. ( f orme 820219 1p. TRDEFR EUTTUCC DEFR-820219-01 NE R4R 8203010158 Interim deficiency rept re Borg Warner valves which may be FILE /P: 8203010158
' effected if installed between 22 1/2 & 157 1/2 verticale FICHE: 12070 156 12070 156 dnitially reported 820122. Evaluation continuing. Completion TASK:
'espected 820319.
g CHAY,R.J. Texas Utilities Electric Co. (forme 820219 1p. TRDEFR EUTTUCC DEFR-820302 NE R4R 8703160062 Final deficiency rept te musiliary feedwater sus valves FILE /P: 8203160362
, ' undersp ecified in pressure / temp ratings. initially reported FICHE: 12300 282 12300 283 811207. Condition not reportable under 10CFR50. 55( e ). TASK:
CARY. R. J. Texas Utilities Electric Co. (forme 820302 2p p. 1 s, TRDEFR EUTTUCC DEFR-820302 NE R4 8203170383 Final deficiency rept to underspecified musiliary feedwater FILE /P: 8203170383 sus valves. initially reported 811207. Investiga tion concluded FICHE: 12318 006 12318 006 that deficiency not reportable per 10CFR50.55e. TASK: CARY.R.J. Texas Utilities Electric Co. (forme 820302 1p. l l 53 , i
1/ 6/05 PACE 2 r d., ,
, U. S. NUCLEAR RECULATORY CONNISSION
{! PRELIMINARY TITLE LIST REPORT
- b 50-446 Comanche Peak Steam Electric Station. Unit 2 1
__i_._ f, _ ___-- i DTC AA1: DIN: RA1: SN TRDEFR EUTTUCC DEFR-820310 NE R4 8203260164 Interim deficiency rept re orifice plates supplied outside FILE /P: 8203260164
;e f tolerance. initially reported 811120. Evaluation in FICHE: 12423 333 12423 333 progress. Completion projected by 820611. TASK: a b
C AR Y,.R. J. Tesas Utilities Electric Co. (forme 820310 1p. 4 TRDEFR EUTTUCC DEFR-820318 NE R4 e 1 8204050005 Final deficiency rept re Borg Warner valves originally FILE /P: 8204050305 reported 020122.Four valves identified as having been FICHE: 12518 207 12518 209 installed between 22 1/2 degrees & 157 1/2 degrees. Valves TASK: 9 will'be returned to vendor for rework. GARY,R.J. Texas Utilities Electric Co. (forme 820318 3pp. TRDEFR EUTTUCC DEFR-820323 NE R4R e E204050056 Interim deficiency rept re design of horizontal fire FILE /P: 8204050056 dempe.rseinitially reported on 820225. Evaluation projected FICHE: 12521 107 12521 107 for c'ompletion by 820601. TASK: A 8 CARY.R.J. Texas Utilities Electric Co. (forme 820323 1p.
.' 9 TRDEFR EUTTUCC DEFR-820507 NE R4 4
8205130264 Interim deficiency rept re Westinghouse RCS wide range FILE /P: 8205130264 pressure measurements, initially reported 820400. FICHE: 13068 360 13068 360 Evaluation continuing & should be completed by 820715. TASK: 1 CkRY,R.J. Texas utilities Electric Co. (forme 820507 1p. 4 TRDEFR EUTTUCC DEFR-820514 NE R4R G 8205240562 Interim deficiency rept to Pacific Pump multi-vane diffuser FILE /P: 8205240562 cracking, initially reported 820414. Evaluation in progress. FICHE: 13214 286 1321'4 286 Nast rept will be provided by 820907. TASK: I DARY R.J. Texas Utilities Electric Co. (forme 820514 1p. ,
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i i 1/ 6/05 PACE 3 i 6 U. S. NUCLEAR RECULATORY CONNISSION
. PRELIMINARY TITLE LIST REPDRT '
50-446 Comanche Peak Steam Electric Station. Unit 2
= - - - - - - - - - - - - - - - - - - - - -----.- _ -- .-_ __ ----
DTC AA1: DIN: RA1: SH TRDEFR EUTTUCC DEFR-820528 NE R4R
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D206070356 Interim deficiency rept re design of horizontal fire FILE /P: 8206070356 dampers. initially reported on 020323. Air Balance horizontal FICHE: 13363 121 13363 123 dampers cleaned. Blade locks secured & damaged closer springs TASK: replaced. Completion espected by 820001. C A,RY. R. J. Texas Utilities Electric Ce. (forme 820528 3pp. i TRDEFR EUTTUCC DEFR-020611 NE R4 8 . 0206'210550 Deficiency rept ce orifice plates string outside specified FILE /P: 8206210550 tolerance. initially reported 011217. All orific e plates FICHE: 13567 010 13567 011
' effecting plant safety will be procured from different TASK:
supplier. Corrective actions to be complete by 820901. CARY.R.J. Texas Utilities Electric Co. (forme 820611 2pp. 9 i j TRDEFR EUTTUCC DEFR-020715 NE R 4 0207200151 Interim deficiency rept to Westinghouse RCS wide range FILE /P: 8207200151 pressure measurements. initially reported 020400. Evaluation FICHE: 13915 244 13915 244 TASK:
.in progress.Next rept will be provided by 820917.
C ARY. R. J. Texas Utilities Electric Co. (forme 820715 1p. TRDEFR EUTTUCC DEFR-820723 NE R4R
)
Q200030210 Final deficiency rept re void in esterior wall of steam FILE /P: 8200030210 generator compartment. Deficiency not reportable under FICHE: 14159 350 14159 350 I 10CFR50. 55e. R ecords suppor ting determination available for TASK: review at site. CARY.R.J. Texas Utilities Electric Co. (forme 820723 1p.
,, TRDEFR EUTTUCC DEFR-820723 NE R4R 01 i g8200030210 Final deficiency rept re void in esterior well of steam FILE /P: 8200030210 generator compartment. Deficiency not reportable under FICHE: 14159 350 14159 350 ' 10CFR50.55e. Records supporting determination available for TASK:
review at site, i CARY.R.J. Tesas Utilities Electric Co. (forme 820723 1p. ! + b I /3 .
,, (, 1/ 6/U5 PAGE 4
. *g U. S. NUCLEAR REiULATORY CDNNIBSION
!i 4 h.'
, y PRELIMINARY TITLE LIST REPDRT i
50-446 Comanche Peak Steam Electric Station. Unit 2 a ! ,I . DTC AA1: DIN: RA1: GN l TRDEFR EUTTUCC DEFR-820004 NE R4R 4 l 8200160269 Interim deficiency rept re diesel generator auxiliary skid. FILE /P: 8200160269 l Initially reported on E20709. Evaluation continuing. Final FICHE: 14347 042 14347 042 Fept espected by 021010. TASK: 4 ts C ARY.*R. J. Texas Utilities Electric Co. (forme 820004 1p. 4 TRDEFR EUTTUCC DEFR-820024 NE R4 0209030264 Followup to 820723 deficiency rept te esterior wall of steam FILE /P: 8209030264 gendrator compartment wall. Void located in Unit 1 not FICHE: 14723 039 14723 039 Un i t,.2. TASK: 4 s CARY,R.J. Texas Utilities Electric Co. (forme 820024 1p. 4 TRDEFR EUTTUCC DEFR-820025 NE R4R 4 8209030135 Interim deficiency rept re Pacific pump multi-vane diffusor FILE /P: 8209030135 crack,ing. Initially reported on B20414. Evaluation should be FICHE: 14721 307 14721 307 coupleted by 021100. TASK: g
- C A.R Y, R. J. Texas Utilities Electric Co. (forme 820025 1p.
e i TRDEFR EUTTUCC DEFR-820900 NE R4R e 8209160093 Deficiency rept re defective governor drive coupling on FILE /P: 8209160093
,' diesel generatore.Init. ally reported on 820912. Drive FICHE: 14891 287 14891 280 8
coupling elements will be replaced w/ neoprene since TASK: ipsprene rapidly deteriorates & ultimately f ai ls. CARY,R.J. Texas Utilities Electric Co. (forme 820908 2pp, t TRDEFR CUT 1UCC DEFR-820914 NE R4 B209270149 Interim deficiency rept re defective Limitorgue pinion keys. FILE /P: 8209270149 Initi. ally reported on 820018. Evaluation comple tion FICHE: 14995 143 14995 143 8 espected by 021021. TASK: t CARY,R.J. Texas Utilities Electric Co. (forme 820914 1p. , 4 4
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}I 3 1/ 6/05 PACE 5
/ U. , S. NUCLEAR RECULATORY CONNISSIDH 7 PRELININARY TITLE LIST REPORT i 50-4 6* Comanche Peak Steam Electric Station, Unit 2
----- ------ - --...------------ _= _ .------ --.-------- - ._
9 DTC AA1: DIN: RA1: SN i TRDEFR EUTTUCC DEFR-820914 NE R4R 8209270152 Interim deficiency rept ce solid state protection sus FILE /P: 8209270152 undhtectable failure. Initially reported on B20018. Evaluation FICHE: 14995 142 14995 142 centinuing. Nest rept espected by 821130. TASK: CARY,R.J. Texas Utilities Electric Co. (forme 820914 1p. t i TRDEFR EUTTUCC DEFR-820915 NE R4 8207270087 Final deficiency rept ce Westinghouse RCS wide-range FILE /P: 8209270387 pressure measurements. Initially reported on 820408. Problem FICHE: 14996 245 14996 245 not reportable per 10CFR50.55(e). TASK: CARY,R.J. Texas Utilities Electric Co. (forme 820915 1p.
- TRDEFR EUTTUCC DEFR-820920 NE R4'R I
8210040318 Interim deficiency rept re conduit supports. Initially FILE /P: 8210040318 reported on 820823. Evaluation continuing. Completion FICHE: 15586 167. 15586 167 anticipated by 821022. TASK: CARY,R.J. Texas Utilities Electric Co. (forme 820920 1p. TRDEFR EUTTUCC DEFR-821006 NE R4R 8210260375 Deficiency rept te overtorquing of sa f e ty-relie f valves. FILE /P: 8210260375 IInitially reported on 820910. Evaluation in pro 2ress & FICHE: 15803 362 15803 362 will be completed by 821130. TASK: QARY,R.J. Tesas Utilities Electric Co. (forme 821006 1p. c TRDEFR EUTTUCC DEFR-821012 NE R4R 8210250338 Interim deficiency rept re defective Limitorque pin' ion i FILE /P: 8210250338 keys. Initially reported on 820010. Natter not reportable per FICHE: 15790 331 15790 331 10CFR50.55(e) based on investigation. TASK:
,CARY,R.J. Texas Utilities Electric Co. (forme 021012 1p.
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a, u, us r .sw- u 8d '8 r U. S. NUCLEAR REQULATORY CONNISSIDN t G O
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PRELIMINARY TITLE LIST REPORT 50 ,446 Comanche _ -Peak _ - - - Steam _ . - - - - Electric
- - - - - - - - - Station.
- . - - - - - - - Unit
-----2 e
'g DTC AA1: DIN: R A1: GN 4
TRDEFR EUTTUCC DEFR-821014 NE R4R e 0210250346 Interim deficiency rept re linear indications identified in FILE /P: 8210250346 diesel generator aus111 erg skid. Initially reported on FICHE: 15790 336 15790 336 C20709. Evaluation continuing. Nest rept espected by 821217. TASK:
- h CARY.R.J. Tesas Utilities Electric Co. (forme 821014 1p.
e TRDEFR EUTTUCC DEFR-821020 NE R4R e 8211020510 Final deficiency rept re reinsp of conduit supports. FILE /P: 8211020510 Initially reported on 820023. Investigation determined matter FICHE: 15889 301 15889 301 not reportable per 10CFR 50. 55 ( e ). R ec o r d s supporting TASK:
- determination available at site.
C ARY. R. J. Texas Utilities Electric Co. (forme 821020 1p. e TRDEFR EUTTUQC DEFR-821025 NE R4R e 0211020274 Interim deficiency rept re pipe restraint weld indications. FILE /P: 8211020274 In i t i,a l l y reported on 820930. Inves tigation continuing. Final FICHE: 15882 138 15882 138 reptfespected by 830103. TASK:
- g C ARY. R. J. Texas Utilities Electric Co. (forme 821025 1p.
e e
, TRDEFR EUTTUCC DEFR-821029 NE R4R e
8211090126 Final deficiency rept re embedded rotafoam & pigwood in FILE /P: 8211090126 cuelliary bidg concrete floor slabs. Initially reported on FICHE: 16003 299 16003 299 821020. Deficiency determined not reportable under TASK:
- 1pCFR50.55(e).
CARY. R. J. Texas Utilities Electric Co. (forme 821029 1p. e I TRDEFR EUTTUCC DEFR-821123 NE R4
.~
0310130278 Final deficiency rept re pipe wall thickness of reactor FILE /P: 8310130278 coolant pressuriser surge line. Initially reported on 821101. FICHE: 20723 197 20723 197 Dsfi(lency not reportable per 10CFR50.55(e). TASK: '
# CARY.R.J.
Texas Utilities Electr'ic Co. (forme 021123 1p. e e e e g 1 l l
0 J, , i'*: a p"
- I) 1/ 6/05 PACE 7 i U. S. NUCLEAR RECULATORY COMMISSION
, PRELIMINARY TITLE LIST REPORT 8 5.
50-446 Comanche Peak Steam Electric Station. Unit 2 DTC AA1: DIN: R A1: SN TRDEFR EUTTUCC DEFR-821216 NE R4R 8212200267 Interim deficiency rept te linear indications in diesel FILE /P: 8212280267 genvrator musiliary skid. Initially reported on 820709. FICHE: 16561 310 16561 310 Completion of evaluation espected by 840113. TASK: CARY,R.J. Texas Utilities Electric Co. (forme 821216 1p. - T8DEFR EUTTUCC DEFR-821216 NE R4R 01 8212h00267Interimdefitlencyreptre linear indications in diesel FILE /P: 8212780267 generator ausiliary skid. Initially reported on 820709. FICHE: 16561 310 16561 310 Completion of evaluation espected by 840113. TA8K: CARY,R.J. Tomas Utilities Electric Co. (forme 821216 1p. TRDEFR EUTTUCC DEFR-821216-01 NE R4R 0301060271 Interim deficiency rept re linear indications in members of FILE /P: 8301060271 diesel generator availlary skid. Initially reported on FICHE: 16679 160 16679 160 820709. Evaluation continuing. Completion anticipated by TASK: b40113. CARY.R.J. Texas Utilities Electric Co. (forme 821216 1p. TRDEFR EUTTUCC DEFR-821216-01 NE R4R 01 Op01060271 Interim deficiency rept re linear indicaticn- in members of FILE /P: 8301060271 diesel generator auxiliary skid. Initially reported on FICHE: 16679 160 16679 160 820709. Evaluation continuing. Completion anticipated by TASK: 840113.
, ,CARY,R.J. Texas Utilities Electric Co. (forme 821216 1p.
,, TRDEFR EUTTUCC DEFR-821227 NE R4R B301040545 Final deficiency rept te pipe whip restraint weld FILE /P: 8301040545 indications. Initially reported on 820930. Condition FICHE: 16646 224 16646 224 determined not reportable per 10CFR50.55(e). TASK:
.. CARY R.J. Texas Utilities Electric Co. (forme 821227 1p.
I l '1 -
1/ 6/05 P AGc' 8 9( , N U. S. NUCLEAR RECULATDRV CONNISSION l l PREL1HINARY TITLE LIST REPORT 50 ,446 Comanche Peak Steam Electric Station. Uni t 2 4. __4_s_..__ _.________..____.. = ____ ___. ___._ ____ _ ,
'I . DTC AA1: DIN: RA1: GN 4
TRDEFR EUTTUCC DEFR-821227-01 NE R4R 0301100073 Interim deficiency rept to potential defect in piston skirt FILE /P: 8301100073 c'estings. Initially reported on 821201. Completion of FICHE: 16697 187 16697 187 svolustion espected by 840206. TASM:
- h C ARYe R. J. Tenae Utilities Electric Co. (forme 821227 ,
1p. g $' I 9 9 9 a 9 ' 1 f 1 , i h I 1 . l 5 a , i ! T 9 I
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- i' U. - S . NUCLEAR RECULATDRY COMMISSION PRELIMINARY TITLE LIOT REPORT '
l. 50-446 Comanche Peat Steam Electric 8tation, Unit 2 DTC AA1: DIN: R A1: SN TRDEFR EUTTUCC DEFR-830113 NE R4 8301210122 Interim deficiency rept re Pacific Pump multi-vane diffuser FILE /P: 8301210122 cratting. Initially reported on 820414. Applican t awaiting FICHE: 16879 063 16879 063 W stinghouse rept. Completion by 830301 anticipated. TASK: I CARY,R.J. Temas Utilities Electric Co. (forme 830113 1p. f TRDEFR EUTTUCC DEFR-830215 NE R4 8302280295 Interim deficiency rept te Borg-Warner check valve FILE /P: 8302280295 malfunction. Initially reported on 830120. Caused by broken FICHE: 17312 350 17312 359 tact weld s e c ur.in g stud connecting valve disc to operating TASK: erm. Valves will be repaired by 830601. CARY,R.J. Texas Utilities Electric Co. (forme 830215 2pp. 1
, TRDEFR EUTTUCC DEFR-830225 NE R4R 8303000063 Interim deficiency rept re position indication of EMD gate FILE /P: 8303000063 valves supplied by Westinghouse, Initially reported on FICHE: 17457 229 17457 230 030125. Af f ected valves modified per manuf acturer TASK:
recommendations. Corrective actions to be complete by 830408.
- CARY,R.J. Texas Utilities Electric Co. (forme 830225 2pp.
TRDEFR EUTTUCC DEFR-830225 NE R4 8]O3080188 Final deficiency rept re procurement & installation of FILE /P: 8303000188 nenmetallic insulation. Initially reported on 830126. Natter FICHE: 17457 359 17457 359 nst reportable per 10CFR50.55(e). TASK: CARY,R.J. Texas Utilities Electric Co. (forme 830225 1p.
,., TRDEFR EUTTUCC DEIR-830228 NE R4R p303000334 Final deficiency rept re radiation monitoring sys. Initially FILE /P: 8303090334 reported on 830201. Inves t iga tion c omple te. Nat t er no t FICHE: 17442 342 17442 342 reportable per 10CFR50.55(el. TASK:
.CARY,R.J. Tesas Utilities Electric Co. (forme 830228 1p.
i E .
PAuc 1/ 6/H3 d
'8 ,
l' U. S. NUCLEAR RECULATORY COMMISSION i e i d PRELIMINARY TITLE LIST REPORT 2 50,446 Comanche Peak Steam Electric Station. Unit 2 4
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'g , DTC AA1: DIN: RA1: SN e
TRDEFR EUTTUCC DEFR-030228-01 NE R4R e 8303080378 Interim deficiency rept te cracked Pacific Pump multi-vano FILE /P: 8303080378
.dif*vser producing linear indications. Initially reported on FICHE: 17453 267 17453 267 820414. Deficiency not reportable p er 10CFR 50. 55( e l. TASK: *-
h CARYsR.J. Texas Utilities Electric Co. (forme 830228 1p. TRDEFR EUTTUCC DEFR-830329 NE R4 8304050406 Interim deficiency rept te vendor installed HVAC sys. FILE /P: 8304050406 Initially reported on 830301. Evaluation continuing. FICHE: 17838 066 17838 066 Cempletion of evaluation anticipated by 830516. TASK:
- s' CARY.R.J. Tomas Utilities Electric Co. (forme 830329 1p.
t TRDEFR EUTTUCC DEFR-830407 NE R4 e 8307p60391 Interim deficiency rept re new fuel storage racks. Initially FILE /P: 8307260391 reported verbally on 830310. Evaluation w!!! he completed FICHE: 19733 168 19733 168 by 830601. TASK: g CLEMENTS.B.R. Tomas Utilities Electric Co. (forme 830407 1p. e
. TRDEFR EUTTUCC DEFR-830421 NE R4R 8304260362 Interim deficiency rept re welding of brackets on vendor- FILE /P: 8304260362 supplied valves & guality of bracket-to-actuator barrel. FICHE: 18198 017 18198 018 Initially reported on 830324. Brackets & welds will be TASK:
esplaced. dARY.R.J. Tomas Utilities Electric Co. (forme 830421 2pp. TRDEFR EUTTUCC DEFR-830511 NE R4 8305200298 Interim Deficiency Rept SDAR-106 re HVAC hangers fabricated FILE /P: 8305200298 at variance w/ design. Initially reported on 830301. completion FICHE: 18516 273 18516 273 et evaluation anticipated by 830705. TASK: CARY.R.J. Texas Utilities Electric Co. (forme 830511 1p. e . t 4 8
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, li 1/ 6/85 PACE 3 e
U/ S. NUCLEAR RECULATDRY CONHISSION
. PRELIMINARY TITLE LIST REPORT '
50-446 Comanche Peak Steam Electric Station. Unit 2 DTC AA1: DIN: R A1: SN
. TRDEFR EUTTUCC DEFR-830531 NE R4 8306090043 Interim deficiency rept re new fuel storage racs support FILE /P: 8306090043 andhors installed w/o proper authorisation. Initially FICHE: 18793 285 19793 286 reported on 830407. Approved anchoring design implemented. TASK:
No. evidence that deficiency is generic. CARY,R.J. Temas Utilities Electric Co. (forme 830531 2pp, f TRDEFR EUTTUGC DEFR-830531 NE R4 01 8306b90043 Interim deficiency rept re new fuel s torage rack support FILE /P: 8306090043 onchors installed w/o proper authorisation. Initially FICHE: 19793 285 18793 286 rsported on 830407. Approved anchoring design implemented. TASK: Ns evidence that deficiency is generic. CARY R.J. Tenas Ut111 ties Electric Co. (forme 830531 2pp. t j TRDEFR EUTTUCC DEFR-830602 NE R4 8306130440 Interim deficiency rept te letdown HX anchors. Initially FILE /P: 8306130440 reported on 830709. Evaluation continuing. Investigation FICHE: 18821 211 19821 211 pill be completed by 830708. TASK:
- CARY,R.J. Temas Utilities Electric Co. (forme 830602 1p.
TRDEFR EUTTUCC DEFR-830621 NE R4 0706300055 Final deficiency rept re adhesive bond on Westinghouse NLP FILE /P: 8306300055 (loop power suppig) printed circuit cards. Initially FICHE: 19121 018 19121 018 reported on 830601. Condition not reportable under TASK: 10CFR50.55(e).
. CARY.R.J. Texas Utilities Electric Co. (forme 830621 1p.
,, TRDEFR EUTTU0C DdFR-830621-01 NE R4 p306300074 Final deficiency rept re Class 1 supp ort mat t w/o complete FILE /P: 8306300074 NDE required for NF2500. Initially reported on 830525. Item FICHE: 19121 002 19121 002 not reportable under 10CFR50.55(e). TASK:
CARY. R. J. Texas Utilities Electric Co. (forme 830621 1p. l . I
l 4 7 . 1/ 6/85 PACE 4 U. 8. NUCLEAR REQULATORY CONNISSIDN
-
- f3 ' O-
- f. +1
, y PRELIMINARY TITLE LIST REPDRT i
50-446 Comanche Peak Steam Electric Station. Unit 2 4
!- DTC AA1: DIN: RA1: SN e
TRDEFR EUTTUCC DEFR-830621-02 NE R4 4 8306300000 Final deficiency rept to Jam nuts on rigid struts not FILE /P: 830630C088 i edequately installed to prevent rotation of strut barrel. FICHE: 19048 345 19048 345 initially reported on 830526. Item not reportable under TASK: 4. i l 10CFR50.55(el. CAR Y,'R. J. Texas Utilities Electric Co. (forme 830621 1p. 9 TRDEFR EUTTUCC DEFR-830621-03 NE R4 j tl 8306300167 Deficiency rept re nonsafety-related components in cooling FILE /P: 8306300167 wstor Class V piping. Controls will be added to existing FICHE: 19122 065 19122 066 levo) transmitters by 830801 to sense depletion of surge TASK: 1 tanh. . CARY,R.J. Texas Utilities Electric Co. (forme 830621 2pp. 4 TRDEFR EUTTUCC DEFR-830704 NE R4 0 8307150100 Interim Deficiency Rept SDAR-106 re HVAC hangers faericated FILE /P: 8307150100 at variance w/ design documents. Initially repor ted on 830301. FICHE: 19536 126 19536 126 Evaluation continuing w/ completion espected by 830001. TASK: % 4 CAfY,R.J. Tesas Utilities Electric Co. (forms'830704 1p. TRDEFR EUTTUCC DEFR-830707 NE R4 4 8307150294 Interim deficiency rept re letdown HX anchors. Initially - FILE /P: 8307150294 tbported on 830506. Anchor bolts found bound in end of FICHE: 19532 203 19532 204 slotted holes prohibiting movement.Hounting configuration TASK: 8 rpvised. CARY,R.J. Temas Utilities Electric Co. (forme 830707 2pp. 4 TRDEFR EUTTUCC DEFR-830712 NE R4 8307220259 Deficiency rept re bolting matl used for cable tray clamps. FILE /P: 8307220259 , Strutt. oral drawings specify high strength botting matts. FICHE: 19684 211 19684 212 Bolto used were mild steel type. Design change issued. TASK: 8
; Rework performed as required.
SPENCE.N.D. Texas Utilities Electric Co. (forme 830712 2pp. , 4 4, 1 24 .
M+ ' $E
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$ 1 i 1/ 6/05 PACE 5 i U. S. NUCLEAR RECULATORY COMMISSION O
. PRELIMINARY TITLE LIST REPORT '
i. O 50-446 Comanche Peak Steam Electric Station, Unit 2 DTC AA1: DIN: R A1: SN O TRDEFR EUTTUCC DEFR-830729 NE R4 0 - 830D090744 Final deficiency rept re HVAC hangers fabricated at variance FILE /P: 8300090744 w/ design documents. Investigation concluded mat ter not FICHE: 19964 014 19964 014 0 reportable per 10CFR50.55te). Records supporting TASK: determination available at site. SPENCE.M.D. Texas Utilities Electric Co. (forme 830729 1p. TRDEFR EUTTUCC DEFR-830009 NE R4 8308220270 Deficiency rept te inadequate overpressure protection for FILE /P: 8308220270 spent fuel pool cooling HXs for component cooling water. FICHE: 20107 039 20107 041 D Pressure relief piping & valve component configuration TASK: evaluated. CARY,R.J. Texas Utilities Electric Co. (forme 830009 3pp. i TRDEFR EUTTUCC DEFR-830825 NE R4 8309020390 Confirms deficiency verbally reported on 830729 re high temp FILE /P: 8309020390 conditions in reactor vessel support & neutron detector well FICHE: 20249 356 20249 356 0 ,? ereas. Evaluation continuing w/ completion espec ted by 830909. . TASK: CARY,R.J. Texas Utilities Electric Co. (forme 830025 1p. TRDEFR EUTTUCC DEFR-830906 NE R4
- O i p309160192 Interim deficiency rept te high temp conditions in reactor FILE /P
- 8309160192 vessel support & neutron detector well areas. Initially FICHE: 20387 253 20387 253
- reported on 830729. Completion anticipated by 830930. TASK:
CARY,R.J. Texas Utilities Electric Co. (forme 830906 1p.
,., TRDEFR EUTTUCC DEFR-830907 NE R4 y 8309160218 Interim deficiency rept re Borg-Warner check valves. Valves FILE /P: 8309160218 of similar design disassembled inspected & repaired.Due to FICHE: 20391 097 20391 098 O number of affected valves involved, corrective actions will TASK:
not be completed prior to fuel load. CARY,R.J. Texas Utilities Electric Co. (forme 830907 2pp. 9 o I 1 5* -
4, ,i l 1/ 6/85 PACE 6 U. S. NUCLEAR RECULATDRY COMMISSION
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. 't PRELIMINARY TITLE LIST REPDRT 50-446 Comanche Peak Steam Electric Station. Unit 2 *
-- ,-----.--- ----.--..... _ ----- ---- -- ------ ------.--- -- e
- l. DTC AA1: DIN: RA1: SN TRDEFR EUTTUCC DEFR-830907 NE R4 01 4
8309160218 Interim deficiency rept te Borg-Warner check valves. Valves FILE /P: 8309160218
,et similar design disassemblede lnspected & repaired.Due to FICHE: 20391 097 20391 098
',n umb e r of affected valves involved. corrective actions will TASK:
- not,be completed prior to fuel load.
CAR Vj R. J. Teams Utilities Electric Co. (forme 830907 2pp. TRDEFR EUTTUCC DEFR-830926 NE R4 C3tOl30268 Interim deficiency rept re temp in es cess of FSAR parameters FILE /F: 8310130268 esperienced in annulus between reactor vessel insulation & FICHE: 20723 215 shield wall. cooling increased by reducing chi!!ad water 20723 216 TASK: 9 temp *L installing addl cooling coll. CAR Y. O. L. Temas Utilities Electric Co. (forme 830926 2pp. g TRDEFR EUTTUCC DEFR-831017 NE R4 g 8310280003 Final deficiency rept ce premature corrosion of valves in FILE /P: 8310280003 ove water sys Initially reported on 830919. Investigation FICHE: 20933 330 20933 330 cemplete. Item not reportable under 10CFR50.55(e).
- TASK: 9 G ARY. R. J. Tesas Utilities Electric Co. (forme 831017 1p.
TRDEFR EUTTUCC DEFR-831116 NE R4 e 8311280243 Deficiency rept re defective breaker support brackets in FILE /P: 8311280243 480-volt switchgear. Thirty-sis brackets contain suspect FICHE: 21281 052 21281 053 watos.Replatements tentatively scheduled for shipment in TASK:
- Dsc 1983.
CAR Y. R . J. Tesas Utilities Electric Co. (forme 831116 2pp. e TRDEFR EUTTUCC DEFR-831228 NE R4 e 8401100004 Deficiency Rept SDAR-123 re Barton recommended calibr checks FILE /P: 8401100004 for Westinghouse supplied pressure tran smi t t er s. Revi s ed FICHE: 21761 206 21761 207 setpoint will be incorporated into equipment list for TASK:
- pressuriser pressure safety injection sys by 840601.
JCAR Y. R. J. Tesas Utilities Electric Co. (forme 831228 2pp. e 4
, .e
D f'.?'I , U. S. NUCLEAR RECULATORY CONNISSION 1/ 6/85 PAGE 1 i
,, PRELIMINARY TITLE LIST REPORT :
50-446 Comanche Peak Steam Electric Station. Unit 2
---_ =
=
DTC AA1: DIN: RA1: SN TRDEFR ENVTRANA DEFR-840109 HIEU 10
'8401170186 Part 21 rept re loose flesible coupling drive hubs. mfg by FILE /P: 8401170186 LeveJoy Coupling & installed by Transamerica Delaval.on FICHE: 21828 269 21828 273 shwfts in overspeed governor fuel transfer pump drive.Insp TASK:
of hubs in listed facilities recommended.Utils notified. BOYER.R.E. Transamerica Delaval, Inc. 840109 Spp. TRDEFR EUTTUCC DEFR-840110 NE R4 8401230410 Deficiency rept te linear indications in emergency diesel FILE /P: 8401230410 , gdnerator musiliary sk ids. 8 kids will be scrapp ed. Replacement FICHE: 21880 342 21880 343 structures will be fabricated at Jobsite per site TASM: engineering drawings by Sep t 1984 , GARY R.J. Terms Utilities Electric Co. (forme 840110 2pp. TRDEFR ENVWEST DEFR-840117 NIED 15 840lb10352 Part 21 rept re potential undetectable failure of test FILE /P: 8401310352 switch in Westinghouse so!!d state protection sys. Minor FICHE: 22019 307 22019 311 wiring change finalised & being forwarded to affected TA8K:
' plants. Diagrams & list of affected plants encl.
'R AFE. E, P. Westinghouse Electric Corp.
840117 5pp. TRDEFR EUTTUCC DEFR-840118 NE R4 8401270275 Interim Deficiency Rept SDAR-124 re installation of chlorine FILE /P: 8401270275 y sensors not conforming t o CDC 4. 5 & 19.FSAR commitments to FICHE: 21976 007 21976 009 Reg Quiden 1.78 & 1.95 & NUREO-0737. Item III.D.3.4. Sensor TASM: 3.D.3.4 relocated & mods to provide adequate calibr instituted. o CARY.R.J. Tomas Utilities Electric Co. (forme 840118 3pp. e TRDEFR EUTTUCC DEFR-840130 NE R4 8402[40333 Inte-im deficiency rept re defective Delaval piston skirt FILE /P: 8402140333
- 7 castings for diesel generators. Piston skirt castings will be FICHE: 22221 240 22221 241 replaced w/ casting provided by supplier by Nag 1984. TASK:
C AR Y. R. J. Temas Utilities Electric Co. (forme 840130 2pp. 0 i I 27 .
y ,(3 1/ 6/05 PACE 2
-[-ll U. S. NUCLEAR REQULATDRY CONNISSION h[
'; PRELIMINARY TITLE LIST REPDRT i
50-446 Comanche Peak Steam Electric Station. Unit 2 u
- 3. DTC AA1: DIN: RA1: GN TRDEFR EUTTUCC DEFR-840130 NE R4 01 C402140333 Interim deficiency rept re defective Delaval piston shirt FILE /P: 8402140333
' castings for diesel generators. Piston skirt castings will be FICHE: 22221 240 22221 241
' replaced w/ casting provided by supplier by Nag 1984. TASK: a ts C ARY! R. J. Texas Utilities Electric Co. (forme 840130 2pp.
TRDEFR EECFALC DEFR-840201 NRRD 08 0402070393 Part 21 rept reguenting investigation of design reliability FILE /P: 8402070393 of 'emergenc y diesel generators supplied by Transamerica FICHE: 22096 057 22096 119 D214 val.Inc Engine problems have been esperienced since TASK: a delivery of first vessel in May 1981.Related info encl. MOLINA.J.C. Falcon Carriers. Inc. 840201 63pp. TRDEFR EUTTUCC DEFR-840207 NE R4 8402170202 Interim deficiency rept re laminations & delaminations in FILE /P: 8402170282 ccbip trag support column in cable spread room. Initially FICHE: 22297 162 22297 162 reported on 840111. Evaluation continuing. Nest rept espected TASK: g by 840309. C A. R Y. R. J. Texas Utilities Electric Co. (forme 840207 1p. e TRDEFR EUTTUCC DEFR-840208 NE R4 8402220420 Deficiency Rept SDAR-126 re defective diesel generator FILE /P: 8402220120 engine push rods. Defective push rods will be removed & FICHE: 22340 172 22340 173 ocrapped & replacements requisitioned & installed before TASK: pperation. CARY.R.J. Texas Utilities Electric Co. iforme 840208 2pp. TRDEFR EUTTUCC DEFR-840213 NE R4 8402220033 Final deficiency rept re stainless steel tubing observed FILE /P: 8402220033 crocked. Investigation complete. Matter not reportable under FICHE: 22338 255 22330 255 10CFR50.55te). TASK: ' t CARY.R.J. Tomas Utilities Electric Co. (forme 840213 1p. , t 1 I 26 8
as 'i's e h' i 3 1/ 6/05 PACE 3 s
/ U S. NUCLEAR RECULATORY COMMISSIDN PRELIMINARY TITLE LIST REPDRT 50-4 6 Comanche Peak Steam Electric Station. Unit 2 DTC AA1: DIN: RA1: SN TRDEFR EUTTUCC DEFR-840213-01 NE R4 C402Q20171 Final deficiency rept te section modulus used in design of FILE /P: 8402220171 pipe supports using tube steel. Initially repor ted on 840118. FICHE: 22340 137 22340 137 Candition determined not reportable per 10CFR5 0. 55( e ). TASK:
CARY.R.J. Texas Utilities Electric Co. (forme 840213 1p. TRDEFR EUTTUCC DEFR-840213-02 NE R4 8402220545 Deficiency rept te fa!!ed inverters in NSSS. Caused by FILE /P: 8402220545 grounded secondary winding of inverter ferroresonant output FICHE: 22333 132 22333 133 transformers. Transformers will be returned to manufacturer TASK: for repair. CARY.R.J. Temas Utilities Electric Co. (forme 840213 2pp. TRDEFG ENVTRANA DEFR-840215 NIEu 09 C402220530 Part 21 rept te defective DSR & DSRV standby diesel FILE /P: 8402220530 gsnerator turbocharger thrust bearing lubrication. Deficiency FICHE: 22332 182 22332 186 not corrected by ogs mod.New recommendation will be sent to TASK: customers by 040330. BOYER.R.E. Transamerica Delaval. Inc. 840215 5pp. l TRDEFR EUTTUCC DEFR-840215 NE R4 Op02200268 Deficiency rept re error in tolerandes used in calibr of FILE /P: 8402280268 cdhesion tester. Initially reported on 840116. Condition not FICHE: 22399 07I 22399 071 reportable under 10CFR50.55(e). Evaluation continuing & TASK: completion anticipated by 840515. CARY.R.J. Texas Utilities Electric Co. (forme 840215 1p.
- c. TRDEFR EUTTUCC DEFR-840220 NE R4 p402200493 Deficiency Rept SDAR-131 re lugs found w/ bad crimpe. FILE /P: 8402280493 Initially reported on 840124. Evalua tion continuing & FICHE: 22407 076 22407 076 cnepletion anticipated by 840330. TASK:
CARY.R.J. Tesas Utilities Electric Co. (forme 840220 1p.
- I z9 .
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1/ 6/05 PACE 4
#{, , fI U. S. NUCLEAR REIULATORY CONNISSION
. I' a g PRELIMINARY TITLE LIST REPDRT 50,-446 Comanche Peak Steam Electric Station, Unit 2 I. DTC AA1: DIN: RA1: SN TRDEFR ENVTERRY DEFR-040222 NIEO 06 0403210032 Part 21 rept re failure of auxiliary feedwater pump drive FILE /P: 8403210032 turbines.0 impel NPS-4 T&T valve,to close.Enct Itr dtd 840203 FICHE: 22706 327 22706 332
- sent to Itsted utils.CE notified of affected units in BWR TASK:
p l ant s. THERDUX,R.R. Terry Corp. 840222 6pp. TRDCFR ENVNPS DEFR-840224 NIED 03 8403070256 Followup Part 21 rept re defective mechanical snubber FILE /P: 8403070256 ccastan springs supplied by Pacific Scientific.Affected FICHE: 22536 279 22536 200 utile listed. Purchasers have been notified L advised to work TASK: directly w/ Pacific Scientific in disposition. HOVI.L. NPS Industries. Inc. 840224 2pp. TRDEFR EUTTUCC DEFR-G40306 NE R4 8401160213 Interim Deficiency Rept SDAR-125 re laminations & FILE /P: 0403160213 delaminations in cable trag support column in cable spread FICHE: 22635 231 22655 231 room 1 Initially reported on 840111. Evaluation c ontinuing. TASK: s Caspletion espected by 840515. EARY.R.J. Tesas Utilities Electric Co. (forme 840306 1p. [ ( TRDEFR EUTTUCC DEFR-840329 NE R4 8404090280 Interim Deficiency Rept SDA9-131 re defective lug crimps on FILE /P: 8404090200 field routed cable.Eguipment supplied by Reliance will be FICHF: 22939 351 22739 362 inspected for proper terminal & connector pin crimping. TASK:
- Equipment rework will be completed by 840531.
CLEMENTS.B.R. Texas Utilities Electric Co. (forme 840329 2p p. . T~ TROEFR EUlTilCC DEFR-040330 NE R4 l7
- s 8403100154 Interim dsficiency rept to discrepancy w/ installation of FILE /P: 8404100154 ,
curtain five dampers w/o proper provisions for thermal FICFE. 22963 238 22963 239 espansion. Initially reported on 840309. Completion of TACP.: , g ovolustion espected by 840615. CLEMENTS.E.H. Texas Utilities Electric Co. (forme 840330 sp, , g. t.
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30 9
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, i U. 9 flVCLEAR FLCULATORY COMMIB91DN PRELININARY TITLE LIST REP 09T , i. 50-446 Cemenr%s Peak Steam Electric Station. Unit 2 = DTC AAt: DIN. RA1: SN TRDEFR EUTTUCC DEFR-040413 NE R4 a404 00003 Interim deficiency rept re vendor documentation of GA FILE /P: 8404200003 inspector eye esem recorde. Initially toported on 840215. FICHE: 24120 134 24120 134 [vstsation completion essected by 040515 TASK: CLEMENTS,B.R. Temas Utilities Electric Co. (forme 840413 1p. t TRDEFR EUTTUCC DEFR-840417 NE R4 C40N260218 Interim deficiency rept re Iaminations & delaminations in FILE /P: 8404260218 cable trag support column. Initially reported on 840tti. Item FICHE: 24207 266 24207 266 ) not reportable under 100FR50.55te). Supporting documentation TASK: I ovailable onsite, , Ct.EMEPITS. B. R. Tenas Utilities Electric Co. iforme 840417 1p. 1HDEFR EUTTUCC DEFR-940417-01 NE R4 i ) ! I i 0004260457 Interim deficiency rept ce discrepancy in diesel generator FILE /P: 8404260957 1 turbocharger thrust bearing lubriration. Initially reported FICHE: 24203 001 24203 001 ! ' 'en 040321. Evaluation cent 11uing. Completion espected by TASK- i
'C40507. l CLEMENTS.B.R. Texas Utilities Electric Co. (Forme 840417 1p. i 8 I TRDEFR EUTTUCC DEFR-040425 NE R4 i I
t 9405070127 Deficiency rept to stock mati supplied by Taylor-Forge. FILE /P: 8405070127 ) Initially reported on 8403~0. Item not reportable per FICHE: 24336 000 24336 000 10CFR50.55(e). TASK: CLEMENTS.B.R. Tomas Utilities Electric Co. (forme 940425 1p. g TRDEFR EUTTU9C DEFR-040504 NE R4 e r. 7 0405140199 Interim deficiency rept re discrepancy in diesel generator FILE /P: 8405140199 turbocharger thrust bearing lubrication. Initially reported FICHE: 24460 009 24460 00% en 840321. Evaluation continuing.Next rept will be submitteJ TASK: by 040716.
., CLEMENTS.B.R. Texas Utilities Electric Co. (forme 840504 1p. ,
(. e 1 31 - i 1 I e
1/ 6/05 PAGE O g
) U. S. NUCLEAR REQULATORY CONNISSION g
f; ( PRELIMINARY TITLE LIST REPDRT s 50.446 Comanche Peak Steam Electric Station. Unit 2 g __Lst.____.- , I. DTC AA1: DIN: RA1: SN e TRDEFR EECMANSC DEFR-840507 NIED 05 e 8405150147 Part 21 rept te Lehigh Testing Laba methodology for testing FILE /P: 8405150147 Micro 1 Lot fiberglass pipe insulation. Vendor has discontinued FICHE: 24469 102 24469 106
'utilising lab to conduct chemical analyses. TASK: e is HIRBERT.R.P. Nanville Service Corp. 840507 5pp.
e TRDEFR EECMANSC DEFR-840507-01 NIED 02
- e 8405150424 Part 21 rept re Lehigh Testing Lab testing of insuletion FILE /P: 8405150415A cetts by improper method. Pipe insulation may c ontain FICHE: 24470 042 24470 051 fluorides in escess of allowed levels.Manville no longer TASK: '
usin's Lehigh Testing Lab for chemical analyses. MIRBERT.R.P. Manville Service Corp. 840507 10pp. e TRDEFR EUTTUCC DEFR-840511 NE R4 e 8405p10215 Interim Deficiency Rept SDAR-12D re discrepancy in vendor FILE /P: 8405210215 documentation of GA inspector eye eram records. Evaluation FICHE: 24510 180 24518 100 cantinuing.Ne st rept will be s u b'mi t t e d by 840629. TASK: g 9 CLEMENT 8.8.R. Tesas Utilities Electric Co. (forme 840511 1p.
- e.
TRDEFR EUTTUCC DEFR-840511 NE R4 01 e 8405210215 Interim Deficiency Rept SDAR-12D re discrepancy in vendor FILE /P: 8405210215 documentation of GA inspector eye exam records. Evaluation FICHE: 24518 100 24510 180 9 cantinuing.Ne st rept will be submitted by 840629. TASK: [LEMENTS.B.R. Tomas Utilities Electric Co. (forme 840511 1p. e , . TRDEFR EUTTUCC DEFR-840511-01 NE R4 l . e 0405210231 Deficiency Rept SDAR-129 re error in tolerances used in FILE /P: 8405210231 ( calibr of adhesion tester. Initially reported on 840116. FICHE: 24518 224 24518 224 Investigation incomplete. Nest rept will be submitted by TASK:
- 7 840801.
CLEMENTS.B.R. Tesas Utilities Electric Co. (forme 840511 1p. ,
; 32.
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i 4 1/ 6/05 PACE 7 8 U/ S. NUCLEAR RECULATDRY COMMISSION
- PRELIMINARY TITLE LIST REPORT f*
50-446 Comenche Peak Steam Electric Station. Unit - DTC AA1: DIN: R A1: SN TRDEFR EUTTUCC DEFR-840511-01 NE R4 01 8405h10231 Deficiency Rapt SDAR-129 re error in tolerances used in FILE /P: 8405210231 cal'ibe of adhesion tester. Initially reported on 840116. FICHE: 24518 224 24518 224 Investigation incomple te. Ne s t rept will be submitted by TASK: 840001. CLEMENT 8.B.R. Tenas Utilities Electric Co. (forme 840511 1p. 1 TRDEFR ENVRDCK DEFR-840511 NIEu 07 840[100332Part21reptte possible insulation damage to Rockbestos FILE /P: 8409100323A electrical cables. Initially reported on 840203. Review of FICHE: 26420 263 26420 269 records to identify all affected cable will be completed by TACK: 040518. Purchasers sill be notified of problem by 840525. LITTLEHALES.O. Rockbestos Co. 840511 7pp. f TRDEFR EUTTUwC DEFR-849522 NE R4 8406010222 Final Deficiency Rept SDAR-134 re rodent damage to Class IE FILE /P: 8406010222 psbles. Initially reported on 840426 Condition determined not FICHE: 24754 336 24754 336 reportable under 10CFR50.55(el. TASK: CLEMENTS,B.R. Tenas Utilities Electric Co. (forme 840522 1p. TRDEFR EUTTUCC DEFR-840522 NE R4 01 OA06010222 Final Deficiency Rept SDAR-134 re rodent damage to Class IE FILE /P: 8406010222 cables. Initially reported on 840426. Condition determined not FICHE: 24754 336 24754 336 reportable under 10CFR50.55(el. TASK:
.CLEMENTS.B.R. Tenas Utilities Electric Co. (forme 840522 1p.
- TRDEFR ENVROCK DdFR-84G522 NIED 09 i ;8406010313 Supplemental Part 21 rept re possible insulation damage 'to FILE /P: 8406010313 i electrical cables afg by Rockbestos Co. Initially reported on FICHE: 24756 349 24756 353 i C40511.Certain reels on production records not shipped or TASK:
shipped on non-Clast IE purchase orders. ' LITTLEHALEB.O. Rockbestos Co. 840522 5pp. t l 1 33.
1/ 6/05 PACE D
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U. G. NUCLEA3 RECULATORY COMM10SIDN
$ PREL1HINARY TITLE LIST REPCR T 50,-446 Comanche Feat Steam Electric Station.
- - - Un i _t *J
. DTC AA1: DIN: RAl: SN TRDCFR'EUTTOGC CEFM-84G528 t4RRL 8405710005 Interim deficiency rept ce problems w/ assured fire damper F1LE/P: 84'05310005 closure.Each closuse being eramined to determine safety FICHE: 24723 143 24723 143 '
*ispect & reportasilitg. TASK:
h CEUROC.J.D. Teams Utilities Electric Co. (force 840528 1p. 19DEFR EUTTDOC UEFR-040529 NE R4 D406050401 Final Deficiency Rept SDAR-133 re unauthorised thermalag FILE /P: 8406'050401 installation between cable & fire barrier envelope. Initially FICHE: 24804 206 24804 296 reported en 040502 condit ten not r esortable per TASK ICCFR50.55(el. CLEMENTS,B.R. Tesas Utilitiss Electris Co. (forme B40529 1p. TRDEFR EUTTUCC DEFR-040604 NC R4 8404120519 Interim Significant Deficiency Rept SDAR-132 re installation' FILE /P: 0406120519 of curtain fire danpers w/o proper provision for thermal FICHE: 24891 093 24891 093 espa'nsion. Initially reported on 840309. Evaluation. TA5K: s cantinuing. Nest rept will be submitted by 840813. CLEMENTS.B.R. Tenas Utilities Electric Co. (forme 840604 1p.
/ TRDEFR EUTTUCC DEFR-840627 NE R4 8407090144 Final deficiency rept re falsification of vendor inspector FILE /P: 0407090144 ego exams. Initially reported on 840215. Investigation FICHE: 25443 200 25443 280 camplete. Item not reportable per IOCFR50.55(e). TASK:
bLEMENTS.B.R. Texas Utilities Electric Co. (forme 840627 1p.
, TRDEFR EUTTUCC DEFR-340702 NE R4 C407090106 Final Significant Deficiency Rept SDAR-138 re possible FILE /P: 8407090186 insulation damage in certain rests of Rockbestos Class IE FICHE: 25443 150 25443 150 multi-conductor cable. Initially reported on 840606. Matter TASK:
#not reportable under IOCFR50.55(e).
CLEMENTS.B.R. Texas Utilities Electric Co. (forme 840702 1p. ,
*i e
1 34 '
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1/ 6/05 PACE 9 U. , S. NUCLEAR REOULATORY COMMISSIDH PRELIMINARY TITLE LIST REPORT , 50-446*Comenche Peak Steam Electric Station, Unit 2 DTC AA1: DIN: R A1: SN
- TRDEFR EUTTUCC DEFR-840702-01 NE R4 8407Q90190 Interim Significant Deficiency Rept SDAR-123 re calibr FILE /P: 8407090190 technique of pressure transmitters. Corrective action will be FICHE: 25443 245 25443 245 ccmpleted by 841231. TASK:
CLEMENTS,B.R. Texas Utilities Electric Co. (forme G40702 1p. s
, TRDEFR EUTTUCC DEFR-840702-02 NE R4 8407,090200 Interim Significant Deficiency Rept 8DAR-137 re FILE /P: 8407090200 inconsistency in draft Tech Spec & FSAR accident analysis. FICHE: 25442 344 25442 344 Initially reported on 840604. Based on investigation matter TASK:
not reportable per 10CFR59.55(el. CLEMENT 8,B.R. Texas Utilities Electric Co. (forme 840702 1p. TRDEFR EUTTUCC DEFR-840702-03 NE R4 0407090255 Interim Significant Deficiency Rept 8DAR-136 re temp FILE /P: 8407090255 envelope requirements on environ quellfications of equipment FICHE: 25450 190 25450 190 autside containment for high energy line break s. Initially TASK: reported on 840604.Next rept by 840831. CLEMENTS.B.R. Texas Utilities Electric Co. (forme 840702 1p. TRDEFR EUTTUCC DEFR-840711 NE R4 8407200247 Final Deficiency Rept SDAR-139 re indeterminate fluoride FILE /P: 8407200247 Icontent of Nanville insulation. Initially reported on 840612. FICHE: 25697 234 25697 234 Cendition not reportable under 10CFR50.55(e). TASK: CLEMENTS.B.R. Tesas Utilities Electric Co. (forme 840711 1p. TRDEFR EUTTUCC DEFR-840712 NE R4 8407250340 Significent Deficiency Rept SDAR-133 re diesel generator FILE /P: 8407250348 t turbo charger thrust bearing lubrica tion. Inves tiga tion FICHE: 25754 162 25754 162 determined item not reportable per 10CFR50.55(e). TASK: CLEMENT 9.B.R. Temas Utilities Electric Co. (forme 840712 1p. O I t 35-
1/ 6/85 PACE 10 U. S. NUCLEAR RECULATORY CONNISSION "1 P I k ' j PRELININARY TITLE LIST REPORT e 50-446 Comanche Peak Steam Electric Station. Unit 2
- __- . _ _ _ _ . _ . . _. --- ___..______.- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . . _ _ _ _ _ _ _ i
,i . DTC AA1: DIN: RA1: SN TRDEFR ENVTRANA DEFR-840713 NIE0 09 8'07170143 Part 21 rept re potential defect in Bendin HPI pumps of DSR FILE /P: 8407170143 .'r e DSRV standby diesel ge'nerator. Caused by mati defect in FICHE: 25608 002 25608 007 ' delivery valve holder. Evaluation completed on 840713.No TASK:
corwective action required. 00YER.R.E. Transamerica Delaval. Inc. 840713 6pp. TRDEFR ENVTRANA DEFR-840713-01 HIEC 00 8'072 0101 Part 21 rept te potential def ect in Betts Spring Co valve FILE /P: 8407200101 spring on DSR or DSRV standby siesel generator. Caused by FICHE: 25692 305 25692 310 surface imperfection.No corrective action required. TASK: Eviluation completed on 840713. BOYER.R.E. Transamerica Deleval. Inc. 840713 6pp. TRDEFR EUTTUCC DEFR-840720 NE R4 C407310001 Interim deficiency rept to installation of curtain fire FILE /P: 8407310001 demp,ers w/o proper provisions for thermal espansion. FICHE: 25849 156 25849 156 Initially reported on 840309. Evaluation in progress.Next TASK: s rept espected by 840813. C,LEMENTS.B.R. Texas Utilities Electric Co. (forme 840720 1p. TRDEFR EUTTUCC DCFR-840731 NE R4 8400090044 Interim Significant Deficiency Rept SDAR-129 re error in FILE /P: 8408090044 tolerances used in calibr of adhesion tester. Evaluation FICHE: 25992 132 25992 132 continuing. Completion anticipated by 840901. TASK: kLEMENTS.B.R. Texas Utilities Electric Co. (forme 840731 1p. TRDEFR EUTTUCC DEFR-840006 NE R4 , 8408160510 Final Deficiency Rept SDAR-129 re error in tolerances used FILE /P: 8408160510 in c,alibr of adhesion tester. Initially reported on 840116. FICHE: 26107 360 261'07 360 Investigation complete. Natter not reportable under TASK: ' f 10CFR50.55(el. CLEMENT 8.B.R. Texas Utilities Electric Co. (forme 840806 Ip, , , I 36 .
4 s ,, g
.t.. -p- ;
, ' 1/ 6/85 PACE 11 s U. S. NUCLEAR RECULATORY COPHISSION PRELIMINARY TITLE LIST REPORT i.
50-446 Comanche Peak Steam Electric Station. Unit 2 DTC AAl: DIN: RAl: SN TRDEFR EUTTUCC DEFR-840809 NE R4 8408160185 Interim Deficiency Rept SDAR-140 re qualification of main FILE /P: 8408160185 steam relief valves for actual loading conditions. Initially FICHE: 26106 328 26106 328 reported on 840710. Evaluation in progress & should be TASK: completed by 840831. CLEMENTS,B.R. Texas Utilities Electric Co. ( forme 840800 1p. i TRDEFR EUTTUCC DEFR-840013 NE R4 840D2bO295 Interim Significant Deficiency Rept 8DAR-132 re installation FILE /P: 8408200295 of curtain fire dampers w/o proper provisions for thermal FICHE: 26140 101 26140 105 espansion.Initia!!v reported on 840330. Review revealed 50 TASK: dampers required rework or mod. Nest rept by 840817. FIKAR.L.F. Texas Utilities Electric Co. (forme 840813 5p p. i
; TRDEFR EUTTUCC DEFR-040016 NE R4 8408200468 Final deficiency rept te flooding levela in electrical FILE /P: 8408280468 control bids resulting from fire euppression. Initially FICHE: 26282 098 26282 099 r,'eported on 840717. Engineering resolutions to isolate TASK:
effected drains will be implemented by 840830. CLEMENT 8,B.R. Texas Utilities Electric Co. (forme 840816 2pp. TRDEFR EUTTUCC DEFR-840816-01 NE R4 0900290125 Interim Deficiency Rept BDAR-142 re ungualified Limitorque FILE /P: 8408290125 electric motors. Initially reported on 840720. Evaluation will FICHE: 26297 343 26297 343 he completed by 040921. TASK:
. ,CLEMENTS.B.R. Texas Utilities Electric Co. (forme 840816 1p.
s ., TRDEFR EUTTUCC DEdR-840820 NE R4 . Q408280375 Final deficiency rept te defective diesel generator valve FILE /P: 8408200?75 springs. Initially reported on 840720. Condition not FICHE: 26282 278 26282 278 ( reportable.under 10CFR50.55(el. TASK: CLEMENTS.B.R. Texas Utilities Electric Co. (forme 840820 1p. I D . I
D gyc -; 1/ 6/05 PACE 12 U. S. NUCLEAR RECULATDRY CONNISSION [l' PRELIMINARY TITLE LIST REPDRT 50-446 Comanche Peak Steam Electric Station. Unit 2 _a_s__ __-- _ _ _ _ _ _ . _ _ . _ _ . _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . - ____
;, DTC AA1: DIN: R A1: Std TRDEFR EUTTUCC DEFR-040820-01 NE R4 0:00200304 Interim deficiency rept to mat! def ec t in diesel generator FILE /P: 8408200304
'fus!' injection pump delivery valve holder. Initially reported FICHE: 26202 103 26202 103
'en 840720. Evaluation will be completed by 840921. TASK:
h , CLEMENTS.B.R. Teams Utilities Electric Co. (forme 840020 1p. TRDEFR EUTTUCC DEFR-840030 NE R4 04091bO309 Interim Deficiency Rept SDAR-140 re several main steam FILE /P: 8409130309 relief valves not qualified for actual loading conditions. FICHE: 26465 224 26465 224 Campletion anticipated by 041009. TASK: CLEMENTS.B.R. Texas utilities Electric Co. (formt 840830 1p. TRDEFR EUTTUCC DEFR-080030-01 NE R4 0403130392 Interim Deficiency Rept SDAR-145 re piping matl that does FILE /P: 8409133392 not meet ultrasonic test requirements for NB-2500 ASNE Class
- FICHE: 26465 211 26465 211 1 cpplications. Initially reported on 840015. Up on completion TASK: 5 of investigation. matter determined not reportable.
CLENENTS.B.R. Tesas Utilities Electric Co. (forme 840830 1p. TRDEFR EUTTUCC DEFR-040030-02 NE R4 C409130428 Interim Deficiency Rept SDAR-136 re temp envelope FILE /P: 8409130428 requirements on environ qualification of equipment outside FICHE: 26465 134 26465 134 containment or high enerag line breaks. Initially reported on TASK: 840604. Westinghouse program developed to address issue. DLEMENTS.B.R. Texas Utilities Electric Co. (forme 840030 1p. TRDEFR ENVWEST DEFR-040914 NIED 06 C410290226 Part 21 rept re capacitor terminations used in CE ferro- FILE /P: 8410290211A resonant transformers utillied in Westinghouse vital 7.5 KVA FICHE: 27173 237 271Y3 241 inverters. Initially reported on 840913. Technical bulletin TASK: f issued w/ instructions for proper connection of capacitors.
- RAHE.E.P. Westinghouse Electric Corp. 840914 3pp. ,
38 .
4
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1/ 6/05 PAGE 13
;, U. S. NUCLEAR RECULATGRY COMMISSION
- ". PRELIMINARY TITLE LIGT REPDRT
- 50-4 6 Cominche Peak Steam Electric Station. Unit 2
, DTC AA1: DIN: RA1: SN , TRPEFR EUTTUCC DEFR-840921 NE R4 8410(00663 Final Deficiency Rept SDAR-144 re mat! defect of delivery FILE /P: 8410100663 valve holder in diesel generator fuel injection pump. FICHE: 26897 277 26897 277 Initially reported on G40720. Inves tigation concluded matter TASK: not *eportable per 10CFR50.55(e). CLEMENTS,B.R. Temas Utilities Electric Co. (forme 840921 1p. TRDEFR EUTTUCC DEFR-840921-01 NE R4 8410100729 Final Deficiency Rept SDAR-142 re unqualified Limitorgue FILE /P: 8410100729 electric motors. Initially reported on 840720. Investigation FICHE: 26897 319 26897 319 csncluded matter not reportable per 10CFR50.55(e). TASK: CLEMENTS.B.R. Texas Utilities Electric Co. iforme 840921 1p.
- TRDEFR EUTTUCC DEFR-840924 NE R4 8410090500 Deficiency Rent SDAR-147 re Conas penetration connector that FILE /P: 8410090500 ccme off during removal of protective endcap.Initiallg FICHE: 26800 211 26800 211 rsported on 840824. Evaluation still in progsens.Next rept TASK:
will be submitted by 841109. CLEMENTS,B.R. Texas Utilities Electric Co. (forme 840924 1p. TRDEFR EUTTUCC DEFR-840924 NE R4 01 8410090500 Deficiency Rept SDAR-147 re Conas penetration connector that FILE /P: 8410090500 I ccme off during removal of protective endcap. Initially FICHE: 26800 211 26080 211 reported on 840B24. Evaluation still in progress.Next ept TASK: will be submitted by 841109. CLEMENTS,B.R. Texas Utilities Electric Co. (forme B40924 1p.
- c. TRDEFR ENVWEST DEFR-840926 NIE0 09 8410090096 Part 21 rept re CE ferro-resonant transformers utill ed in FILE /P: 8410090096 T vital 7.5 kVA inverters. Caused by insufficient securing of FICHE: 26875 135 26875 136 transformer reactor ctr leg leading to insulation breakdown TASK:
& transformer failure.
, RAHE.E.P. Westinghouse Electric Corp. 840926 2pp.
3C' l . 1
'9I 2 M f S.
1/ 6/05 FACE 14 U. NUCLEAR. RECULATORY CDMNISSION i f e
. d, PRELIMINARY TITLE LIST REPORT 50-446' Comanche Peat Steam Electric Station. Unit 2 s
..s!._ .- . _______ _____.______________.______________________ __ _ i
; DTC AA1: DIN: RA1: SN s
TRDEFR ENVWEST DEFR-840926-01 NIED 01 4 8410090120 Part 21 rept re motor deficiency on Limitorque operators. FILE /P: 8410090120 dus to lact o f certification. Replacement parts currently FICHE: 26875 148 26875 149 cn arder for affected motors. TASK: 4 l R AKI lt. P. Westinghouse Electric Corp. 840926 2p p. i 4 TRDEFR ENVTRANA DEFR-841002 NIED 07 C410090056 Part J1 rept re potential defect concerning improperly FILE /P: 8410090356 tsrgued fuel lever cap sciews & possible unpinned levers. FICHE: 26872 173 26872 177 All f,uel control shafts will be inspected for properly TASK: 4 targued fuel lever cap screws. BOYER.R.E. Transaierica Delaval. Inc. 841002 5p p. TRDEFR EUTTUCC DEFR-841012 NE'R4
=
8410260267 Interim Deficiency Rept BDAR-154 re safe shutdown analysis FILE /P: 8410260267 ovo'luations not considering potential fire in HVAC. Initially FICHE: 27160 226 27160 226 reported on 840913. Evaluation continuing. Nest rept.espected TASK: s % by 841106. CLEMENTS.B.R. Tomas Utilities Electric Co. (forme 841012 1p. TRDEFR EUTTUCC DEFR-841012-01 NE R4 s 8410290042 Interim Deficiency Rept SDAR-156 re safety class of FILE /P: 8410290342 instrument lines w/ piping downstream of root valve. Initially FICHE: 27172 357 27172 357 reported on 840918. Evaluation continuing. Completion espected TASK:
- by 841127.
CLENENTS.B.R. Texas Utilities Electric Co. (forme 841012 1p. 4 TRDEFR EUTTUCC DER-841012 NE R4
' 0410290306 Interim Deficiency Rept SDAR-153 re transmitters w/ potential FILE /P: 8410290306 lostage path between sensor module & housing for moisture. FICHE: 27173 018 27173 018 Initially reported on 840913. Evaluation continuing Nest rept TASK:
- yspected by 841120.
CLEMENTS.B.R. Texas Utilities Electric Co. (forme 841012 1p. , O
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. 1/ 6/85 PACE 15
, ; U. S. NUCLEAR RECULATORY COMMISSION e
.. PRELIMINARY TITLE LIST REPORT
. a 50-446. Comanche Peak Steam Electric Station. Unit 2 DTC AA1: DIN: R A1: SN 1RDEFR EUTTUCC DEFR-841012-03 NE R4 0410300039 Interim Deficiency Rept SDAR-152 re ventilation erhaust FILE /P: 8410300039 dchpers possibig failing to close. Initially reported on FICHE: 27185 029 27185 029 840913. EvaluatArn continuing. Completion espected by 841120. TASK:
CLEMENTS.B.R. Texas Utilities Electric Co. (forme 041012 1p.
- TRDEFR EUTTUCC DEFR-841031 NE R4 8411130642 Interim Deficiency Rept SDAR-136 re temp envelope FILE /P: 8411130642 r6guirements on environ gualification of equipment outside FICHE: 27462 044 27462 044 containment for high energy line breabs. Initially reported TASK:
en 840604. Next rept will be submitted by 850401. CLEMENTS.B.R. Texas Utilities Electric Co. (forme 841031 1p.
, TRDEFR ENVRUMC DEFR-841106 NIED 21 8411190524 Port 21 rept re failure of fire dampers to close under FILE /P: 8411190524 normal duct pressure. Caused by failure of test methods FICHE: 27549 242 27549 247 utilised for closure under air flow to accurately depict TASK:
)ctual field :enditions. List of affected plants encl.
HILL.T.D. Ruskin Manufacturing C o. 841106 6pp. TRDEFA EUTTUCC DEFR-841100 NE R4 8411210222 Deficiency Rept SDAR-147 re Conas penetration connectors. FILE /P: 8411210222 yInitially reported on 840824. Evaluation continuing. Ne s t rep t FICHE: 27606 075 27606 075 will be submitted by 841207. TASK: CLEMENTS,B.d. Tenas Utilities Electric Co. (forme 041100 1p. TRDEFR EUTTUCC DEFR-841119 NE R4 s 04120'50162 Deficiency & Part 21 Rept SDAR-156 re Rosemount transmitters FILE /P: 8412050162 f w/ potential leakage path between sensor module & housing. FICHE: 27778 000 27778 009 Instruments removed & will be installed prior to plant TASK: aperation. CLEMENTS,B R. Tesas Ut!Ilties Electric Co. (forme 841119 2pp. l - 1 4-
s
"{[ 7 fl U. S. NUCLEAR RECULATORY COMMISSION 1/ 6/85 PACE 16 k h
/ PRELIMINARY TITLE LIST REPDRT 50,446 Comanche Peak Steam Electric Station. Unit 2 r_7-- _-_ _--.---------_ - i s
DTC AA1: DIN: RA1: SN s TRDEFR EUTTUCC DEFR-841119-O! HE R4 8312050235 Deficiency Rept SDAR-158 re ITT Darton differential pressure FILE /P: 8412050235 s
.cwitches esperiencing setpoint shifts in escess of specs FICHE: 27778 361 27778 361 than operated at temps above 225 F. Condition not reportable TASK:
por itOCFR50. 55(el. s CLEMENTS.D.R. Tesas Utilities Electric Co. (forme 041119 1p. s
?
TRDEFR EUTTUCC DEFR-841119-02 NE R4 8412050321 Deficiency Rept SDAR-156 re safety glass of instrument lines FILE /P: 8412050321 s 6/ piping downstream of root valve. Initially reported on FICHE: 27778 362 27778 362 C40918. Condition not reportable per 10CFR50. 55(e). TASK: d s CLEMENTS B.R. Tesas Utilities Electric Co. (forme 041119 1p. s TRDEFR EUTTUCC DEFR-841120 NE R4 8412q30287 Deficiency Rept SDAR-152 re ventilation enhaust dampers FILE /P: 8412050287 s desig,ned/ installed to f all closed & divert radioactive retsases to operator rooms. Initially reported on 840913. FICHE: 27778 353 27778 353 g TASK: Ccapletion espected by 841221. s CLEMENTS. B. R. Tesas Utilities Electric Co. (forme 841120 1p. TRDEFR EUTTUCC DEFR-841204 NE R4 s 8412180628 Deficiency Rept SDAR-148 re preoperational testing FILE /P: 8412180628 octivities at facilities. Initially reported on 840829. FICHE: 27974 135 Ccmplete investigation concluded that condition not
. 27974 135 TASK:
ryportable p e r 10CFR 50. 55 ( e ).
- CLEMENTS,B.R.
Tesas Utilities Electric Co. (forme 041204 1p. e TRDEFR EUTTUCC DEFR-841205 NE R4 s. 8412130410 Deficiency Rept SDAR-147 re Conas penetration connector that FILE /P: 8412130410 t ccm3 off during removal of protective endcap. Initially FICHE: 27903 200 27903 200 reported on 840024. Condition determined to be not reportable TASK: w por 10CFR50.55(e). CLEMENTS B.R. Tesas Utilities Electric Co. (forme 841205 1p.
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1/ 6/05
- U. S. NUCLEAR REGULATDRY CONNISSION .
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PRELIMINARY TITLE LIST REPORT r 50-445 Comanche Peat Steam Electric' Station. Unit 2 DTC AA1: DIN: RA1: SN
- TRDEFR EUTTUCC DEFR-841210 NE R4 Ob122,00015 Deficiency Rept SDAR-159 re voltage balance relays outside FILE /P: 0412200315 sys(s for operating time. Initially reported on 841115. FICHE: 20031 305 20031 305 Candition determined not reportable per 10CFR50.55(e). TASK:
CLEMENTS.B.R. Tesas Utilities Electric Co. (forme 841210 1p. TRDEFR EUTTUCC DEFR-841217 NE R4 C501p40060 Interim Significant Defic iency Rept SDAR-152 re ventilation FILE /P: 850104C068 omhaust dampers designed / installed to fail closed. Initially FICHE: reported on 841213. Completion anticipated by 850206. TASK: CLEMENTS.B.R. Texas Utilities Electric Co. (forme 841217 1p. i i T I l . I
1 4 N
- THIS DOCUMENT WAS PRODUCED BY THE U. S. NUCLEAR REGULATORY COMMISSION'S c
DOCUMENT CONTROL SYSTEM i i
.' 50 .495 1
OPERATED BY TECHNASSOCIATES, INC./ PRC ,
,. UNDER CONTRACT NO. NRC-10-84-211 FOR THE DIVISION OF TECHNICAL INFORMATION AND DOCUMENT CONTROL ,
OFFICE OF ADMINISTRATION l - p; p f ( 2) '
1/ 6/05 PACE 1 C;3- U. S. NUCLEAR C.EOULATORY CDMN1SSION 7 T PRELIMINARY TITLE LIST REPORT h>.
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- 1. DTC AA1: DIN: R A1: SN TRDEFR EUTTUCC DEFR-791113 8002190053 Suppl to 790917 deficiency rept re omission of shear tie FILE /P: 8002190353
'rainforcing steel in reac tor containment b1dg. Addl F1CHE: 04016 327 04016 327 ' rcossignments made & training being performed to prevent TASK:
recherence. implementation audit deadline is 791220. CARY,R.J. Tomas Utilities Electric Co. (forme 791113 1p. TRDEFR EUTTUCC DEFR-791114 7911210474 Second interim deficiency rept te electrical cable tray FILE /P: 7911210465A hengers w/ light partial penetration welds where full F1CHE: 01377 195 01377 196 psnetration welds required. Caused by incorrect TASK: int'erpretation of weld symbols. Weld procedure revised. e Tomas Utilities Electric Co. (forme 791114 2pp. 1
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1/ 6/US PAGE 1 e j U. S. NUCLEAR REIULATORY CONNISSION CP
! PRELIMINARY TITLE LIST REPORT a
gp-445 Comanche Peak _ Steam ____6_ _ Electric Station. Unit 1
;, DTC AA1: DIN: RA1: SN TRDEFR EUTTUCC DEFR-800104 B001220435 Deficiency rept:en 780404. design change issued permitting FILE /P: 8001220427A ws11 thickness variations w/ potential for localised pipe FICHE: 01708 236 01789 237 utrosses. Piping found in violation of original requirements. TASK:
- D9 sign changes rescinded, e
- Terms Utilities Electric Co. (forme 000114 2pp.
TRDEFR EUTTUCC DEFR-800114 a 0003190004 Interim deficiency rept re violation of piping min wall FILE /P: OOO3190370A thickness.Addl changes implemented requiring that future FICHE: 04257 095 04257 096 a wstds violating min wall thickness be repaired. Corrective TASK: actions will be accomplished by hot functional testing. e Texas Utilities Electric Co. (forme B00114 2pp. e t TRDEFR EUTTUGC DEFR-BOO 123-01 e ' 0001310272 Clarifies 800114 Itr re violation of piping min' wall FILE /P: 8001310272 thickness. reported per 10CFR50.55(e). Attached rept intended FICHE: 01041 219 01841 219 to be' classified as interie.Will submit progre ssive repts as TASK: g w31ds are dispositioned through engineering review. C AR Y. R. J. Texas Utilities Electric Co. (forme 800123 2pp.
~
' TRDEFR EUTTUCC DEFR-BOO 321 4 0004010299 Deficiency rept:en 800220.0A insp revealed control board FILE /P: 8004010295A wstded connections not meeting seismic design criteria.Cause FICHE: 04348 195 04348 196 - unstated. control board suppliers & AE reviewing as-built TASK: wild configurations. Rework will be completed by 800501.
/ Texas Utilities Electric Co. (forme 800321 2pp.
g. TRDEFR EUTTUCC DEFR-800415 0004220423 Interim deficiency rept re piping min wall thickness. Review FILE /P: 8004220423 of weld & base metal repair records is continuing.Another FICHE: 04661 197 04661 197
,prsgr'ess rept will be submitted by 000620. TASK:
CARY. R. J. Texas Utilities Electric Co. (forme 800415 1p. s
' ~
=
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1/ 6/05 PACI 2 i j U. S. NUCLEAR REtOLATORY CONNIS3IDH , O PRELIMINARY TITLE LIST REPDRT 50 ,445 Comanche Peat Steam Electric Station. Unit 1
% . -- - _ _ _ i
. . DTC AA1: DIN: R A1: SN ,
TRDEFR EUTTUCC DEFR-800415-01 o 0005140234 Interim deficiency rept supplementing 800114 & 23 repts re FILE /P: B005140234
. violation of piping min wall thickness. Twenty safety- FICHE: 04952 ' 288 04952 288 related sys w/ welds evaluated by physical or ultrasonic #
TASK: mathpds.Five sus were within Tech Specs. C AR Y. R. J. Tesas Utilities Electric Co. (forme 000415 1p. TRDEFR EUTTUCC DEFR-800421 . 6004290254 Deficiency rept re concrete honeycombing in steam generator FILE /P: 8004290250A 4 ccmpartment walls of Unit 2 reactor containment b!dg. FICHE: 04704 119 04704 121 Censultant survey showed no critical internal defects.Util TASK: to gepair condition w/ dry-pack mortar. grout & concrete. e Tesas Utilities Electric Co. (forme 800421 3pp. TRDEFR EUTTUCC DEFR-800421-01 0004290271 Interim deficiency rept re installation of drilled-in FILE /P: 8004290271 espansion anchors. Hatter was corrected 790616 by revistor to FICHE: installation procedure. Formal rept to be filed by 801215. TASK: ' C AR Y R . J. Tesas Utilities Electric Co. (forme 000421 1p. e - TRDEFR EUTTUCC DEFR-800421-02 0004290437 Interim deficiency rept re installation & insp of welded FILE /P: B004290430A 9enduit supports.Hajor support was fabricated w/o formalised FICHE: 04706 055 04706 055 instructions & insp records for number of smaller welded TASK: ' supports were not directly traceable to as-built conditions.
. d RY. R. J. Tesas Utilities Electric Co. (forme 800421 1p.
TRDEFR EUTTUCC DEFR-BOO 421-03 0006060570 Deficiency rept re apparent discrepancy in installation & FILE /P: 0006060570 insp requirements for Class 5 non-nuclear safety-related FICHE: 05256 146 05256 146 piping supports. Formal rept should be submitted by 800715. TASK: '
~
- C AR Y. R. J. Tesas Utilities Electric Co. (forme D00421 1p.
=
4 9
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# #Us enue a i 4 U. S. NUCLEAR CECULATDHY COMNISSION 8
D f# C PRELlHINARY TITLE LIST REPC3T , 50-405 Comanche Peak Steam Electric Station. Unit 1 4' q _ - --= ------------- ...__ - - - - - - - - . - - - - ---- ,
,, DTC AA1: DIN: RA1: Std 4
THDEFR EUTTUCC DEFR-800502 4 8006230156 Deficiency rept re welded control board connections. updating FILE /P: 0006230156 000328 rept. Work will be completed by 800701. FICHE: 05429 179 05429 179 TASK: 9 C ARY.'R. J. Tesas Utilities Electric Co. iforme 000502 1p. 4 TRDEFR EUTTUCC DEFR-800619 4 0006240242 Supplemental deficiency rept re 1991-93 2300 MW installation FILE /P: 8006240242 piping min wall. Engineering review & disposition of min FICHE: 05433 350 05433 350 uoll, violations at welds & base metal defects is continuing. TASK: 4 Anticipates submitting nest progress rept by 801219. C AR Y. R. J. Tesas Utilities Electric Co. iforme 800619 Ip. 4 TRDEFR EUTTUCC DEFR-800714 4 0007210352 Updates 800421 deficiency rept ce discrepancies involving FILE /P: B007210352 in&tallation & insp requirements for Class 5 non-nuclear FICHE: 05916 357 05916 357 sofotg-related piping supports.FSAR is being revised. Final TASK: g 4 rept will be forwarded by 800922. C AR Y. R. J. Tesas Utilities Electric Co. iforme 800714 1p. e e TRDEFR EUTTUCC DEFR-BOO 725
- e 8000050004 Interim deficiency rept re installation of welded conduit FILE /P: 0000050004 oupports.hajor support fabricated w/o formalised instruction FICHE: 06145 024 06145 026
& insp records not directly traceable to as-built TASK: 8 conditions. Engineering drawings developed & insp revised.
CARY.R.J. Tesas Utilities Electric Co. (forme 800725 3pp. 4 TRDEFR EUTTUCC DEFR-800808
. g 8008190370 Deficiency rept re use of architectural concrete in floor FILE /P: 0000190370 sicbs when determining enhedment length of Hilti bolts. FICHE: 06366 048 06366 050 Survig of bolts is being conducted. Bolt installation TASK: I
, procedure was revised to reflect embedment lengths.
'CARY.R.J. Tesas Utilities Electric Co. (forme 800008 3pp.
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1/ 6/05 PACE 4 e U; S. NUCLEAR RECULATDRY COMMISSION o PRELIMINARY TITLE LIST REPORT 50-445 Comanche Psah Steam Electric Station. Unit 1 DTC AA1: DIN: RA1: EN TRDEFR EUTTUCC DEFR-800918 8009230301 Deficiency rept re discrepancies in installation & insp FILE /P: 8000230301 re4utrements For Class V safety-related piping supports. FICHE: 06601 113 06601 114 Caused by inadequate documentation to ascertain that TASK: supports satisfy design & seismic load requirements. CARY.R.J. Texas Utilities Electric Co. iforme 800918 2pp. t TRDEFR EUTTUCC DEFR-800918 01 8009'230301 Deficiency rept ce discrepancies in installation & insp FILE /P: 8009230301 reguirements for Class V safety-related piping supports. FICHE: 06601 113 06601 114 Caused by inadeguate documentation to ascertain that TASK: sepports satisfg design & seismic load requirements.
, ., CARY.R.J. Tesas Utilities Electric Co. iforme 800918 2pp, i
, TRDEFR EUTTUCC DEFR-801010 NOIR 4C
- 8010170502 Deficiency rept te Roto-lock insert locking tab installed at FILE /P
- 8010170502 facility. Problem should not be classified as potentially FICHE: 06737 242 06737 242
,' reportable deficiency. Supporting documentation available at TASK:
plant site. C AR Y. R. J. Texas Utilities Electric Co. iforme 801010 1p. TRDEFR EUTTUCC DEFR-801010 NOIR 4C 01 0010170502 Deficiency rept re Poto-lock insert locking tab installed at FILE /P: 8010170502 Pacility. Problem should not be classified as potentially FICHE: 06737 242 06737 242 reportable deficiency. Supporting documentation available at TASK:
' plant site.
CARY.R.J. Texas Utilities Electric Co. iforme 801010 1p.
. TRDEFR EUTTUCC DdFR-801013 NOIR 4C 7 8010170479 Deficiency rept ce Plascite 7122 coating. Ongoing evaluation FILE /P: 8010170479 af lining problem will be completed L formal rept forwarded FICHE: 06737 125 06737 125 by 801114. TASK:
C ARY. R. J. Tesas Utilities Electric Co. (forme 801013 1p. l .
' 6
# "#"# E# #' D 3 i U. S. NUCLEAR RECULATDRY CONNISSIDN y 7 e
4 ' PRELIMINARY TITLE LIST REPDRT 50-445' Comanche Peak Steam Electric Station. Unit i e
,p4_,____.___-- __.___.= -
;, DTC AA1: DIN: RA1: SN e
+
TRDEFR EUTTUCC DEFR-801013 NOIR 4C 01 e
- 9010170479 Deficiency rept re Plascite 7122 coating. Ongoing evaluation FILE /P: 8010170479 et lining problem will be completed & formal rept forwarded FICHE: 06737 125 06737 125
,. by 801114.
TASK: *
' C ARY h. J. Texas Utilities Electric Co. (forme 801013 1p.
e TRDEFR EUTIUCC DEFR-801015 NOIR 4C e 8010200416 Deficiency rept re thread engagement of sweg struts. FILE /P: 8010200416 C Candition not reportable under 10CFR50.55e.as reported on FICHE: 06736 284 06756 204 000919. TASK:
- C ARY. R. J. Texas utilities Electric Co. (forme 801015 1p.
e TRDEFR EUTTUCC DEFR-801015 NOIR 4C 01 e 8010200416 Deficiency rept re thread engagement of sway struts. FILE /P: 8010200416 Can'dition not reportable under 10CFR50.55e.as reported on FICHE: 06756 284 06756 284 800919. TASK: g W CARY.R.J. Texas Utilities Electric Co. (forme 801015 1p.
, gB TRDEFR EUTTUCC DEFR-801021 NOIR 4C e
C0102OO354 Interim deficiency rept te defects in installation of Hitti- FILE /P: 8010280354 Kwin concrete anchor bolts. Identified anchor b alte have been FICHE: 06812 344 06012 346 ccmaved. Support util be reworked &/or relocated to meet TASK:
- required design criteria. Followup rept provided by 810123.
*CARY.R.J. Texas Utilities Electric Co. (forme 801021 3pp.
e TRDEFR EUTTUCC DEFR-801021 NOIR 4C 01
. e 8010200354 Interim deficiency rept te defects in installation of Hilti- FILE /P: 8010280354 Mwik concrete anchor bolts. Identified anchor bolts have been FICHE: 06812 344 06812 346 remsved.. Support will be reworked &/or relocated to meet TASK: #
.' required design criteria. Followup rept provided by 810123.
CARY.R.J. Texas Utilities Electric Co. (forme 801021 3pp. e e 9 9 i 7
- 1/ 6/25 PAGE 6 4' ?* U. S. NUCLEAR RECULATORY CDNNISSIDN
'w . *
, e PRELIMINARY TITLE LIST REPDRT
@O-44 Comanche Peak Steam Electric Station. Unit 1 8
, .. DTC AA1: DIN: RAl: SN e
TRDEFR EUTTUCC DEFR-801021-01 NOIR 4C
. 8 8010200350 Deficiency rept re diesel generator pipe supports. Deficiency FILE /P: 8010280350 to be'ing evaluated to formulate corrective action. Formal FICHE: J6812 347 06812 347
'rspt will be provided by 810136. TASK: 8 ts
,C A8Y R. J. Texas Utilities Electric Co. (forme 801021 1p.
. 4 TRDEFR EUTTUCC DEFR-801021-01 N0tR4C 01
. e 8010280358 Def aciency rept re diesel generator pipe supports. Deficiency FILE /P: 8010280358 is being evaluated to formulate corrective action. Formal FICHE: 06912 347 06812 347 rep $ will be provided by 810116. TASK: 8 C ARY. R. J. Texas Utilities Electric Co. (forme 801021 1p.
TRDEFR EUTTUCC DEFR-801029 NOIR 4C t 0011030505 Final deficiency rept re Plasite 7122 lining in svc water FILE /P: 8011030585 ego piping. Condition is not reportable per 10C FR50. 55e. FICHE: 06861 139 06861 139 Supporting documentation available at plant site. TASK: 8 CARY.R.J. Tesas Utilities Electric Co. (forme 801029 1p. t TRDEFR EUTTUCC DEFR-801029 N0!R4C 01 4 8011030585 Fin.1 deficiency rept ce Plasite 7122 lining in svc water FILE /P: 8011030585 sys piping. Condition is not repcrtable per 10CFR50.55e. FICHE: 06861 139 06061 139 Supporting documentation available at plant site. TASK: ' i CARY.R.J. Tesas Utilities Electric Co. (forme 801029 1p. TRDEFR EUTTUCC DEFR-801210 N0!R4C , 8052180245 Deficiency rept superseding 800421 submittalere installation FILE /P: 8012180245 et drilled-in espansion anchors. initially reported on FICHE: 07272 353 07272 354 , 791107. Installation procedure was revised to reflect min TASK: 1
,-spacing requirements between various anchor types.
. CAR Y. R. J. Tesas Utilities Electric Co. (forme 801210 2pp. ,
e e 4 i 8
1/ 4/H) PAGs /
+
t 2e I U. S. NUCLEAR EECULATORY CONHISSION e, PRELININARY TITLE LIST REPORT 50-445 Comanche Peak Steam Electric Station. Unit 1 . i-_- __ _ _ = _____._____._________ __._____ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - ,
;. DTC AAt: DIN: R A1: SN TRDEFR EUTTUCC DEFR-801210 NOIR 4C 01 9012180245 Deficiency rept. superseding B00421 submittal.re installation FILE /P: 8012100245
, df drilled-in espansion anchors. initially reported on FICHE: 07272 353 07272 354 793307. Installation procedure was revised to reflect min TASK: a spacing reguirements between various anchor types. CAR Ye R. J. Tesas Utilities Electric Co. iforme 801210 2pp. TRDEFR EUTTUCC DEFR-801216 NOIR 4C 0012290169 Interim deficiency rept re violation of piping min wa!! FILE /P: 8012290169 thickness. Engineering review & disposition of min wall FICHE: 07343 361 07343 361 violations at welds continuing.Ne s t progress r ep t to be TASK:
- submitted by 810615.
CARY.R.J. Tesas Utilities Electric Co. (forme 801216 1p. TRDEFR EUTTUCC DEFR-901216 N0!R4C 01
' 0012290169 Interim deficiency rept re violation of piping min wall FILE /P: 0012290169 thickness. Engineering review & disposition of min wall FICHE: 07343 361 07343 361 violations at welds continuing.Next progress rept.to be TASK: g submitted by 810615.
CARY.R.J. Tesas Utilities Electric Co. (forme 901216 1p. s . . 9 1
* . g 9
f r e = s 9
- 1/ 6/05 PACE 1 3.*- '.8 U. S. NUCLEAR EEOULATORY CDHNISSION
[e ( 4 s PRELIMINARY TITLE LIST REPORT e SD-445 Comanche Peak Steam Electric Station. Unit 1 _= _ _ _ _ DTC AA1: DIN: R A1: EN , TRDEFR EUTTUCC DEFR-810112 N0lR4C , 8101200246 Interim deficiency rept re afs deficiency of component FILE /P: 8101200246 supports associated w/ausiliary piping sgs diesel FICHE: 074G7 091 07487 091 , gensr,ators. initially reported 800926. Evaluation will be TASK: completed by 810731. CARY.R.J. Tesas Utilities Electric Co. (forme 810112 1p. , TRDEFR EUTTUCC DEFR-810112 N0!R4C 01 , C101200246 Interim deficiency rept te afg deficiency of component FILE /P: 8101200246 oupports associated w/ausiliary piping sys diesel FICHE: 07487 091 07407 091 , generators. initially reported 900926. Evaluation will be TASK: caspleted by 810731. E ARY R. J. Temas Ut!!! ties Electric Co. (forme 810112 1p. , TRDEFR EUTTUCC DEFR-810112-01 N0lR4C , 8101300253 Interim deficiency rept to unauthorized field mode to FILE /P: 8101200253 Hitti'-Kwik concrete anchor bolts. initially rep or ted 801001. FICHE: 07407 089 07487 090 , Balts have not been modified in unauthorized manner.' TASK: Fellow-up rept will be submitted by 810417. C ARY. R. J. Temas Utilities Electric Co. (forme 810112 2pp. , I TRDEFR EUTTUCC DEFR-810112-01 NOIR 4C 01 , 8101200253 Interim deficiency rept to unauthorised field mods to FILE /P: 8101200253 Hitti-Kwik concrete anchor bolts. initially reported 801001. FICHE: 07487 089 07487 090 , Datte have not been modified in unauthorized manner. TASK: Follow-up rept will be submitted by 010417. 4 CARY.R.J. Tesas Utilities Electric Co. (forme 810112 2pp.
- - TRDEFR EUTTUGC DEFR-810218 NOIR 4C ,
' C102250206 Interim deficiency rept. originally reported in B10120 telcon FILE /P: 8102250206 , to RC Taylor. re use of cable lubricant Yellow 77. Lubricant FICHE: 07755 174 07755 174 , cimbustible in dry state. Evaluation continues & completion TASK:
# anticipated by 810515.
CARY.R.J. Temas Utilities Electric Co. (forme 810218 1p. , C l .
' ic) :
's ' 1/ 6/Ud PAWE 2 U. S.
3 4 g'* PMcLEAR RECULATOHY C0t1 NIB 3 ION e i PRELIMINARY TITLE LIST REPDRT 50-445 Comanche Prah Steam Electric Station. Unit i e t- .
,, DTC AA1: DIN: R A1: Sr4 e
TRDEFR EUTTUCC DEFR-810218-01 NOIR 4C e CIC2250257 Interim deficiency rept. originally reported in 810120 telcon FILE /P: 8102250257 to CR. Taylor.re compressive attength of pipe support FICHE: 07755 172 07755 172
.boccplate grouting nati at elevated temps. Investigation TASK:
- campleted & deficiency determined not reportable.
CARY}R.J. Texas Utilities Electric Co. (forme 810218 1p. e TRDEFR EUTTUCC DEFR-810218-01 NOIR 4C 01 g C102250257 Interim deficiency rept. originally reported in B10120 telcon FILE /P: 8102250257 to CR Taylor. re compressive strength of pipe support FICHE: 07755 172 07755 172 boseptete grouting matl at elevated temps. Investigation TASK: 9 caqpleted & deficiency determined not reportab le. C AR Y. R. J. Tesas Utilities Electric Co. (forme 810218' 1p. 9 TRDEFR EUTTUCC DEFR-810218-02 N0!R4C e C103100666 Final deficiency rept te compressive strength of pipe FILE /P: 8103180566 support baseplate grouting mati subjected to elevated temps. FICHE: 07954 182 07954 182 initially reported 810120. Condition found not reportable TASK: g 9 undsr 10CFR50.55(e). CARY.R.J. Tesas Ut!!ities Electric Co. (forme 810218 1p.
- 4 TRDEFR EUTTUCC' DEFR-810218-02 NOIR 4C 01 9
C103180666 Final deficiency rept re compressive strength cf pipe FILE /P: 8103180666 support baseplate grouting mat 1 subjected to elevated temps. FICHE: 07954 182 07954 182 initially reported 810120. Condition found not reportable TASK: 9 undsr 10CFR50.55(el.
- 0.J Y. G. J. Tesas Utilities Electric Co. (forme 810218 1p.
1 TRDEFR EUTTUCC DEFR-810313 NIEIRPS2
. 9 C103.*50474 Interin Jeficiency rept. originally reported 810217.re FILE /P: 8103240474 W2stinghouse valves that failed to close completely under FICHE: 07982 263 07982 265 pre-operational test conditions. Westinghouse investigating. TASK: 9 Prebtem lies within Limitorgue operators. Nods scheduled.
(OARY. R. J. Temas Utilities Electric Co. (forme 810313 3pp.
- 4 4
e I i // '
<s ' U. S.
1/ 6/05 PACE 3
? ' NUCLEAR RE!ULATORY CDNMISSIDN Y e PRELININARY TITLE LIST REPORT 50-C45' Comanche Peah Steam Electric Station, Unit 1
- e
, DTC AA1: DIN: RA1: SN ,
TRDEFR EUTTUCC DEFR-810313 NOIR 4 01 0 C103240474 Interim deficiency rept. originally reported 810217.re FILE /P: 8103240474 Wastinghouse valves that failed to close completely under FICHE: 07982 263 07982 265
, pro-operational test conditions. Westinghouse investigating. TASM: #
Prablem lies within Limitorque operators. Nods scheduled. C AR Y'.;R. J. Tesas Utilities Electric Co. (forme 810313 3pp. e TRDEFR EUTTUCC DEFR-810415 NOIR 4 tid 210337 Interim deficiency rept re unauthorized field mods of FILE /P: 8104210337 Hitti-Ewik concrete anchor bolts. initially reported on FICHE: 08308 340 j BOIOOI. Anomalies will be identified & dispositioned per 08300 341 ! TASK: " ' precedures for conforming items by 811201. CARY.d.J. Teras Utilities Electric Co. (forme 810415 2pp.
. e TRDEFR EUTTUCC DEFR-810415 NOIR 4 01 ,
C104210337 Interim deficiency rept re unauthorized field made of FILE /P: 8104210337 Hitti-Mwik concrete anchor bolts. initially reported on FICHE: 08300 340 08300 341 801001. Anomalies will be identified & dispositioned per TASK: , procedures for conforming items by 811201. CARY.R.J. Texas Utilities Electric Co. (forme 810415 2pp.
. e TRDEFR EUTTUCC DEFR-810421 NOIR 4 ,
8104270369 Interim deficiency rept te possible.use of short heating FILE /P: 8104270369 ventilation & air conditioning bolts initially reported on FICHE: 08369 091 08369 091 C10324. Engineering evaluation continuing. Resolution by TASM: , 8t0626. CARY.R.J. Tesas Utilities Electric Co. (forme 810421 Ip. e TRDEFR EUTTUCC DEFR-810421 NOIR 4 01 , C104270369 Interim deficiency rept re possible use of short heating FILE /P: 8104270369 Ncntilation L air conditioning bolts. initially reported on FICHE: 08369 091 08369 091 810324. Engineering evaluation continuing. Resolution by TASM: , r 810626. f G ARY. R. J. Tomas Utilities Electric Co. (forme 810421 1p. D E O h
, Iif .e i
1/ O/Cd PAGE <
- e. j . U. S. NUCLEAR REGULATORY COMMISSIDN V t e 5 t PRELIMINARY TITLE LIST REPDRT 50-c45'Comancho Peak Steam Electric Station. Unit I e
,, DTC AAl: DIN: R A1: SN e
TRDEFR EUTTUCC DEFR-010424 NOIR 4 e C1:50:0437 Interim deficiency rept re heating. ventilation & air FILE /P: 9105040437 ccnditioning cooling sys. initially reported on 810330. FICHE: 00430 160 00430 161 Engineering studies for re-evaluation of age design for TASK:
- CPSES to be completed by 010630.
C ARY.h. J. Tesas utilities Electric Co. iforme 810424 2pp. e TRDEFR EUTTUCC DEFR-010424 N0!R4 01 e C105000437 Interim deficiency rept re heating. ventilation & air FILE /P: 8105040437 ccnditioning cooling sys. initially reported on 810330. FICHE: 00430 160 00430 161 Engineering studies for re-evaluation of sys design for TASK:
- CPSES to be completed by 010630.
CARY.R.J. Temas Utilities Electric Co. iforme 810424 2pp. e TRDEFR EUTTUCC DEFR-010504 NIE4RP e 8105120290 Deficiency rept ce failure of 6.9 kV circuit breaker. FILE /P: 8105120290 initially reported on 010400. Condition is not reportable per FICHE: 00517 317 00517 317 IOCFR50.55e. Records supporting determination are available TASK: g For NRC review at plant site. CARY.R.J. Texas Utilities Electric Co. iforme 810504 1p. e W TRDEFR EUTTUCC DEFR-010504 NIE4RP 01 se 8105120290 Deficiency rept re failure of 6.9 hV circuit breater. FILE /P: 0105120299 initially reported on 010400. Condition is not reportable per FICHE: 00517 317 00517 387 10CFR50.55e. Records supporting determination are available TASK:
- fgr NRC review at plant site.
E6RY.R.J. Texas Utilities Electric Co. iforme 810504 1p. e TRDEFR EUTTUCC DEFR-810513 NIEIRPI 9 C105190236 Interim deficiency rept re use of potentially combustible FILE /P: 0105190236 Yollow 77 cable lubricant. initially reported on 010120. FICHE: 00550 133 00550 133 Evolvation will be completed by 010031. TASK:
- DAR Y. R. J. Texas Utilities Electric Co. iforme D10513 ip.
- w
, 6 e
, 1.3 -
k .I . h 5 1/ 6/15 PAGE 5 U; E NUCLEAR REGULATORY CONNISSIDN PRELIMINARY TI,TLE LIST REPDRT 50-445 Comanche Peak Steam Electric Statiosi. Unit 1 - DTC AA1: DIN: RA1: SN
. TRDEFR EUTTUCC DEFR-BIOS 21 NIE4RP CIC5260465 Interim rept te Westinghouse valves failure to close FILE /P: 8105260165 completely under preoperational test conditions initially FICHE: 09595 359 08595 360 reported on B10217. Westinghouse has podified 4-inch valves TASK:
far use as prototypes. Final rept to be submitted by 911016. CARY.R.J. Tesas utilities Electric Co. iforme B10521 2pp. TRDEFR EUTTUCC DEFR-810521 NIE4RP 01 p155560465 Interim rept te Westinghouse valves failure to close FILE /P: 8105260465 completely under preoperational test conditions initially FICHE: 00595 359 08595 360 reported on 810217. Westinghouse has nodified 4-inch valves TASK: fcr use as prototypes. Final rept to be submitted be 911016. C ARY. R. J. Texas Utilities Electric Co. Sforme 810521 2pp. TRDEFR EUTTUCC DEFR-910603 NIE4RP C106090606 Final deficiency rept te violation of piping min wall FILE /P: 9106090606 thickness. initially reported en 790522. Revisions to FICHE: 08744 055 09744 058 fchrication & documents completed. Final stress analyses are TASM: hergeted for completion peior to hot func tional tes ting. CARY.R.J. Tesas Utilities Electric Co. (forme 810603 4pp. TRDEFR EUTTUCC DEFR-810603 NIE4RP 01 C}060906CA Final deficiency rept te violation of piping min wall FILE /P: 9106090606 t% iciness. initially reported on 790522. Revisions to FICHE: 08744 055 08744 050 fchrication & documents completed. Final stress analyses are TASK: torgeted for completion prior to bet functional testing.
,CARY.R.J. Teses Utilities Electric Co. iforme 810603 App.
TRDEFR EUTTUCC DEFR-910609 NIE4RP C106150401 Deficiency rept ce defective Bahnson Svc Co heating.
- FILE /P: 6106150401 ventitation & air canditioning supports. initially reported FICHE: 00778 361 00778 362 en 610324. Pahnson precedures have been revised to include TASK:
decurentation of concrete anchor bolt site. CARY.R.J Temas Utilities Electric Co. iforme 010600 2pp. s I '{
&# b/03 P het b 3 i . U. G. NUCLEAR REOULATORY COMNISSION L( PRELIMINARY TITLE LIST REPDRT 50-445 Comanche Peak Steam Electric Station. Unit 1 e s.---------------.--------------------------.-----..= --.--------. .
, , DTC AA1: DIN. R A1: SN
=
TRDEFR EUTTUCC DEFR-010600 NIE4RP 01 o 0106150401 Deficiency rept re defective Bahnson Svc Co heating. FILE /P: 8106150401 ventitation & air conditioning sup por t s. initia lly reported FICHE: 00770 361 C0770 362 an DIO324.Bahnson procedures have been revised to include TASK:
- documentation of concrete anchor bolt site.
CARY.R.J. Texas Utilities Electric Co. (forme 810600 2pp. e TRDEFR EUTTUCC DEFR-010619 NIE4RP 0109150365 Deficiency rept te vol control tank level control sys. FILE /P: 8109150365 originally reported on StO522. Postulated event seguence FICHE: 09740 005 09740 005 evaluation indicates that malfunction would not cause safety TASK-
- hasard. Reportable under Part 21 but not under 10CFR50.55e.
CARY.R.J. Texas Utilities Electric Co. (forme 810619 1p. s TRDEFR EUTTUCC DEFR-010619 NIE4RP 01
=
01091,50365 Deficiency rept re vol control tank level control sys. FILE /P: 8109150365 eriginally reported on 010522. Postulated event seguence FICHE: 09740 003 09740 005 ovalu'ation indicates that malfunction would not cause safety TASK: g hasard. Reportable under Part 21 but not under 10CFR50.55e. CARY.R.J. Tesas Utilities Electric Co. (forme 810619 1p. e % TRDEFR EUTTUCC DEFR-010623 NIE4RP m I 0106290356 Interim deficiency rept re heating / ventilation / air- FILE /P: 8106290356 conditioning cooling sys. initially reported on 010330.Cause FICHE: 00060 109 00060 109 attributed to design evolution. Corrective actions to be TASK:
- cropleted as described in 010424 interim rept.
CARY.R.J. Tomas Utilities Electric Co. (forme 810623 1p. O TRDEFR EUTTUCC DEFR-010623 NIE4RP 01
. e 9106290356 Interim deficiency rept re heating / ventilation / air- FILE /P: 8106290356 conditioning cooling sys. initially reported on 010330.Cause FICHE: 00060 109 08060 109 attributed to design evolution. Corrective actions to be TASK:
- Scopleted as described in 010424 interim rept.
MARY. R. J. Texas Utilities Electric Co. (forme 910623 1p. e e t I IS
1,
- J e 1/ 6/85 PACE 7
- I U. S. NUCLEAR REQULATORY COMMISSION M t o PRELIMINARY TITLE LIST REPORT 50-445 Comanche Peak Steam Electric Station, Unit 1
= ---
DTC AA1: DIN: RA1: SN , TRDEFR EUTTUCC DEFR-810701 NIE4RP 9 8107280108 Final deficiency rept re specified matl for pipe spool FILE /P: 8107280108
.flenges, initially reported on 810604. Matter considered not FICHE: 09171 345 09171 345 reportable under 10CFR50.55(el. TASK: #
C AR Y R . J. Texas Utilities Electric Co. (forme 810701 1p. TRDEFR EUTTUCC DEFR-810701 NIE4RP 01 , 81072 0100 Final deficiency rept te specified mati for pipe spool FILE /P: 8107280100 flanges. Initially reported on 810604. Natter considered not FICHE: 09171 345 09171 345 , rensrtable under 10CFR50.55(e). TASK: CARY.R.J. Texas Utilities Electric Co. (forme 810701 1p. , TRDEFR EUTTUGC DEFR-810701-01 NIE4RP , 8107280115 Final deficiency rept re use of Yellow 77 cable lubricant, FILE /P: 8107280115 initially reported on 810110. Natter considered not FICHE: 09173 041 09173 041 , reportable under 10CFR50.55(e). TASK: CARY,R.J. Tesas Utilities Electric Co. (forme 810701 1p. , TRDEFR EUTTUCC DEFR-810701-01 NIE4RP 01 8107280115 Final deficiency rept re use of Yellow 77 cable lubricant. FILE /P: 8107280115 initially reported on 810110. Matter considered not FICHE: 09173 041 09173 041 , repartable under 10CFR50.55(e). TASK:
- I CARY.R.J. Texas Utilities Electric Co. (forme 810701 1p.
TRDEFR EUTTUCC DEFR-810701-02 NIE4RP 0107280616 Final deficiency rept re seismic instrument tubing support, FILE /P: 8107280616 initially reported 810604. Engineering documents will be FICHE: 09177 294 09177 296 , evaluated & revised. Completed installation- will be TASK: isurveyed.Nencompliant conditions will be reworked. CARY.R.J. Texas Utilities Electric Co. (forme 810701 3pp. 8i l
, 16 .
it crus reut u
.? p
- U. S. NUCLEAR RECULATORY CDMNISSIDN e
.t. ,
PRELIMINARY TITLE LIST REPORT t 4 50-4,45 Comarche Peak Steam Electric Station. Unit 1
; - DTC AA1: DIN: RA1: SN s
TRDEFR EUTTUCC DEFR-810701-02 f41E4RP 01 s C107280616 Final deficiency rept re seismic instrument tubing support. FILE /P: 8107280616
' initially reported 810604 Engineering documents w!!! be FICHE: 09177 294 09177 296 'evoluated & revised. Completed installations will be TASK:
sur@eged.Noncompliant conditions will be reworked. C AR Yl R. J. Tesas Utilities Electric Co. (forme 810701 3pp. TRDEFR EUTTUGC DEFR-810729 NIE4RP 8100110468 Interim deficiency rept re alignment difficulties in diesel FILE /P: 8108110168 gen'erator pipe supports. originally reported on 800926. Weld FICHE: 09330 241 09338 242 program initiated L supporting documentation c omp iled to TASK: certify compliance w/ASNE code. CARY.R.J. Tesas Utilities Electric Co. (forme 810729 2pp. . TRDEFR EUTTUCC DEFR-810729 NIE4RP 01 9 8108110468 Interim deficiency rept re alignment difficulties in diesel FILE /P: 8108110468 gsnerator pipe supporte. originally reported on 800926. Weld FICHE: 09338 241 09338 242 program initiated & supporting documentation compiled to T/.SK: g certify compliance w/ASNE code. CARY.R.J. Tesas Utilities Electric Co. (forme 810729 2pp. TRDEFR EUTTUCC DEFR-810831 NIE4RP 8109090407 Final deficiency rept re pull-out per f ormance of Hitti FILE /P: 8109090487 Kwin-Bolt anchors. initially reported 801217. Condition is not FICHE: 09657 296 09657 296 ' significant deficiency & is not reportable per TASK: 20CFR50.55(el. C ARY. R. J. Texas Utilities Electric Co. (forme 810831 1p. . TRDEFR EUTTUCC DEFR-810831 NIE4RP 01 O U109090407 Final deficiency rept re pull-out p er f ormanc e of Hilt! FILE /P: 8109090187 Mwik-Dolt anchors. initially reported 801217. Condition is not FICHE: 09657 296 09657 296 ' significant deficiency & is not reportable per TASK: s10CFR50.55(e). CARY.R.J. Tesas Utilities Electric Co. (forme 810831 1p. , ,
' /?
p p' U. S. 1/ 6/05 PACE 9 NUCLEAR RECULATORY COMMISSION k i O PRELIMINARY TITLE LIST REPORT __-5,0-4,45 Comanche Peak Steam Electric Station. Unit 1 DTC AA1: DIN: RA1: SN , TRDEFR EUTTUCC DEFR-810831-01 NIE4RP , 8109160004 Interim deficiency rept re failure of Westinghouse valve FILE /P: 8109160084 to close completely under preoperational test conditions. FICHE: 09576 059 09576 059
'nitially i reported 810217. Evaluation of other valves for TASK:
- c l os'u r e problem continuing. Final rept by 011016.
C AR Y.* R. J. Tesas utilities Electric Co. (forme 810831 sp.
, THDEFR EUTTUCC DEFR-810831-01 NIE4RP 01 ,
8109160004 Interim deficiency rept re failure of Westinghouse valve FILE /P: 8109160004 to close completely under preoperational test conditions. FICHE: 09576 059 09576 059 initia!!g reported 810217. Evaluation of other valves for TASK:
- c l e's u r e problem continuing. Final rept by 811016.
C AR Y. R. J. Texas Utilities Electric Co. (forme 810831 1p. TRDEFR EUTTUCC DEFR-810928 NIE4RP g 0110060262 Final deficiency rept re failure of Westinghouse gate valve FILE /P: 8110060262 to completely close under preoperational test conditions. FICHE: 10045 254 10045 256 , initially reported on 810217. Westinghouse has issued Field TASK: - Chcnge Notices 10515 & 10537 detailing corrective actions. C RY.R.J. Texas Utilities Electric Co. (forme 810928 3pp. TRDEFR EUTTUCC DEFR-810928 NIE4RP 01 , , 8110060262 Final deficiency rept re failure of Westinghouse gate valve FILE /P: 8110060262 to completely close under preoperational test conditions. FICHE: 10045 254 10045 256 initially reported on 810217. Westinghouse has issued Field , TASK: Chsnge Notices 10515 & 10537 detailing corrective actions. CARY.R.J. Tesas Utilities Electric Co. (forme 880920 3pp. TRDEFR EUTTUCC DEFR-811002 NIE4RP 8110140155 Modified deficiency rept re diesel generator pipe support FILE /P: 8110140155 cli g nmente lni tially repor ted 800926. Hanufacturer did not FICHE: 10159 310 10159 312 . cempty w/ASME stress allowables. Calculations & weld insp TASK: *
; procedures revised.
CARY.R.J. Tesas Utilities Electric Co. (forme 811002 3pp. , e e e
, 18 ~
si orua rewc au e, ?, , U. S. NUCLEAR RECULATORY CONNISSIDN o lr ,1 I PRELININARY TITLE LIST REPDHT 50-4C5' Comanche Peak Steam Electric Station. Unit I e
., DTC AA1: DIN: RA1: SN e
TRDEFR EUTTUCC DEFR-811002 HIE 4RP 01 e C110140155 Nodified deficiency rept re diesel generator pipe support FILE /P: 8110140155 clignment. initially reported 800926. Nanufacturer did not FICHE: 10159 310 10159 312 j camply w/ASME stress allowables. Calculations & weld insp TASK: * { prgcedures revised. l CARY.A.J. Tesas Utilities Electric Co. (forme 811002 3pp. l l l 1 l 1 TRDEFR EUTTUCC DEFR-811204 NIE4RP 8112160205 Final deficiency rept re unauthorized field mods to Hitti- FILE /P: 8112160285 kwin. concrete anchor bolts during installation. initially FICHE: 11245 243 11245 248 reperted on 001001. Bolts removed or cut off & driven into TASK:
- cancrete structures.
CARY.R.J. Tesas Utilities Electric Co. (forme 811204 6pp. e TRDEFR EUTTUCC DEFR-811204 NIE4RP 01 e 8112100205 Final deficiency rept re unauthorized field mods to Hitti- FILE /P: 8112160295 M w i'k concrete anchor bolts during installation. initially FICHE: 11245 243 11245 248 repseted on 001001.Dotts removed or cut off & driven into TASK:
- j g
cancrete structures. 1 C AR Y. R. J. Texas Utilities Electric Co. (forme 811204 6pp. f TRDEFR EUTTUCC DEFR-811231 NIE4RP e i C201130126 Interim deficiency rept to eight underspecified 3/4-inch FILE /P: 8201130126 ausiliary feedwater ogs valves initially repor ted on 811207. FICHE: 11564 281 11564 281 Evaluation ongoing. Completion anticipated by 820305. TASK:
- CdRY.R.J. Texas Utilities Electric Co. (forme 811231 1p.
e TRDEFR EUTTUCC DEFR-811231 NIE4RP 01
- e E201130126 Interim deficiency rept te eight underspecified 3/4-inch FILE /P: 8201130126 ausiliary feedwater ogs valves. initially reported on 811207. FICHE: 11564 281 11564 281 Evaluation ongoing. Completion anticipated by 820305. TASK:
- DARY. R. J. Tomas Utilities Electric Co. (forme 911231 1p.
e e e e i 19 . I
. ?.
' U. S. NUCLEAR KECULATDRY COMMISSION 1/ 6/85 PAGE 1
& i e i PRELIMINARY TITLE LIST REPORT
$0 435 Comanche Feat Steam Electric Station. Unit 1 r,- ___
DTC AA1: DIN: R A1: SN , TRDEFR EUTTUCC DEFR-820219 NE R4R , 8203010023 Deficience rept re matt procured by AFC0 Steel. Deficiency FILE /P: 8203010323
'dotermined not reportable per 10CFR50.55(el. FICHE: 12070 135 12070 135 '
ts TASK: CARY.R.J. Temas Utilities Electric Co. (forme 820219 1p. ,
- TRDEFR EUTTU0C DEFR-820219 NE R4R 01 8203010023 Deficiency rept re mati procured by AFC0 Steel. Deficiency FILE /P: 8203010323 determined not reportable per 10CFR50.55(el. FICHE: 12070 135 12070 135 s' TASK:
CARY.R.J. Tomas Utilities Electric Co. (forme 820219 1p. TRDEFR EUTTUCC DEFR-820219-01 NE R4R 820$010158 Interim deficiency rept te Borg Warner valves which may be FILE /P: 8203010158 eptetted if installed between 22 1/2 & 157 1/2 vertical. FICHE: 12070 156 12070 156 initiatig reported 820122. Evaluation continuing. completion TASK: espected 820319. CpAY. R. J. Tesmo Utilities Electric Co. (forme 820219 1p. TRDEFR EUTTUCC DEFR-820219-01 NE R4R 01 8203010158 Interim deficiency rept to Borg Warner valves which may be FILE /P: 8203010158 offected if installed between 22 1/2 & 157 1/2 verticale FICHE: 12070 156 12070 156 fnitial. initially reported 820122. Evaluation c ontinuing. TASK: Completion espected by 820319. GRAY.R.J. Tesas Utilities Electric Co. (forme 820219 1p.
~
TRDEFR EUTTUCC DEFR-820302 NE R4R 820316,0062 Final deficiency rept re ausiliary feedwater sys valves FILE /P: 82031eS:62 i underspecified in pressure / temp ratings. initially reported FICHE: 12300 282 12300 283 TASK: g C11207. Condition not reportable under 10CFR50. 55(el. CARY.R.J. Tomas Utilities Electric Co. (forme 820302 2pp. I 20 .
, as usua rn.s e 4 9. U. S. NUCLEAR RECULATORY COMMISSION
( ' PRELIMINARY TITLE LIST REPORT 50-445 Comanche Peak Steam Electric Station. Unit 1 __-a_- - -- .--- ---= - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ,
;, DTC AA1: DIN: RA1: SN TRDEFR EUTTUCC DEFR-820302 NE R4R 01 8203160062 Final deficiency rept re auxiliary feedwater sus valves FILE /P: 82031603A2 underspecified in pressure / temp ra ting s. initia lly reported FICHE: 12300 20J 12300 283 '011207. Condition not reportable under 10CFR50.55(e). TASK:
A C Ahy. R. J. Tomas Utilities Electric Co. (forme 820302 2pp. TRDEFR EUTTUCC DEFR-820302 NE R4 E203170303 Final deficiency rept re underspecified aualliary feedwater FILE /P: 8203170383 sgo valves. initially reported 811207. Investigation concluded FICHE: 12318 006 12318 006 tho,t deficiency not reportable per 10CFR50.55e. TASK: C ARY. R. J. Texas Utilities Electric Co. (forme 820302 1p. TRDEFR EUTTUCC DEFR-820302 NE R4 01 8203170303 Final deficiency rept re underspecified auxiliary feedwater FILE /P: 8203170303 ogs. valves. initially reported 811207 Investigation concluded FICHE: 12318 006 12318 006 that' deficiency not reportable per 10CFR50.55e. TASK: g CARY.R.J. Tesas Utilities Electric Co. (forme 820302 1p. TRDEFR EUTTUCC DEFR-820310 , NE R4 C203260164 Interim deficiency rept re orifice plates supplied outside FILE /P: 8203260164 of tolerance. initially reported 011120. Evaluation in FICHE: 12423 333 12423 333 progress. completion projected by 820611. TASK: CARY.R.J. Texas Utilities Electric Co. (forme 820310 1p. TRDEFR EUTTUCC DEFR-820318 NE R4 8204050005 Final deficiency rept re Borg Warner valves originally FILE /P: 8204050005 reported 820122.Four valves identified as having been . FICHE: 12518 207 12518 209 installed between 22 1/2 degrees & 157 1/2 degrees. Valves TASK: y will be returned to vendor for rework. C ARY. R. J. Texas Utilities Electric Co. (forme 820318 3pp. e
'?
1/ 6/85 PACE 3 U. S. NUCLEAR RECULATDRY COMNISSION { ( .
; PRELIMINARY TITLE LIST REPORT 507 445 Comanche Peak Steam Electric Station. Unit 1 ,
DTC AA1: DIN: rat: SN , TRDEFR EUTTUCC DEFR-820318 NE R4 01 ,, C204050005 Final deficiency rept to Borg Warner valves originally FILE /P: 8204050005 reported 820122.Four valves identified as having been FICHE: 12518 207 12518 209
' installed between 22 1/2 degrees & 157 1/2 degrees. Valves TASK:
- willsbe returned to vendor for rework.
C AR Y'. R. J. Tesas Utilities Electric Co. (forme 820318 3pp.
. TRDEFR EUTTUCC DEFR-820323 NE R4R -
8204050056 Interim deficiency rept re design of horizontal fire FILE /P: 8204050056 dem'pers. initially reported on 820225. Evaluation projected FICHE: 12521 107 12521 107 for, completion by 820601. TASK: CARY.R.J. Temas Utilities Electric Co. (forme 820323 1p. TRDEFR EUTTUCC DEFR-820507 NE R4 . 8205130264 Interim deficiency rept re Westinghouse RCS wide range FILE /P: 8205130264 pressure measurements. initially reported 820408. FICHE: 13068 360 13068 360 Evaluation continuing & should be completed by 820715. TASK: l C AR Y. R. J. Tesas Utilities Electric Co. (forme 820507 1p.
- 1 TRDEFR EUTTUGC DEFR-820507 NE R4 01 1
8205130264 Interim deficiency rept re Westinghouse RCS wide range FILE /P: 8205130264 pressure measurements. initially reported 820408. FICHE: 13068 360 13068 360 Evaluation continuing & should be completed by 820715. , TASK: , i CARY.R.J. Tesas Utilities Electric Co. (forme 820507 1p. TRDEFR EUTTUGC DEFR-820514 NE R4R , 8205240562 Interim deficiency rept re Pacific Pump multi-vane diffuser FILE /P: 8205240562 crecting. initially reported 820414. Evaluation in progress. FICHE: 13214 286 132k4 206 Nast rept will be provided by 820907. TASK: , CARY.R.J. Tesas Utilities Electric Co. (forme 820514 1p. t t e
, 2%' c ,
W
J. l, U. S. NUCLEAR REQULATORY CONNISSIDH PRELIMINARY TITLE LIST REPORT i e 50-4C5 Comanche Peak Steam Electric Station. Unit 1 _ ,s_._ . . _ _ _ _ _ _ _ _ _ . . _ _ _ _ .. _ _
;, DTC AA1: DIN: R A1: SN e
TRDEFR EUTTUCC DEFR-820514 NE R4R 01 e D2052:0562 Interim deficiency rept to Pacific Pump e.ulti-vano diffuser FILE /P: 8205240562 crecking. initially reported 820414. Evaluation in progress. FICHE: 13214 206 13214 286 TASM: e Nest rept will be provided by 820907. t. CARY R.J. Texas Ut:11 ties Electric Co. (forme 820514 1p. e TRDEFR EUTTUCC DEFR-820528 NE R4R e 8206070356 Interim deficiency rept re design of horizontal fire FILE /P: 8206070356 dampers. initially reported on 820323. Air Balance horizontal FICHE: 13363 121 13363 123 TASM:
- dampers cleaned. Blade locks secured & damaged closer springs replaced. Completion espected by 820001.
C AR Y. R. J. Texas utilities Electric Co. (forme 820528 3pp. e TRDEFR EUTTUCC DEFR-820528 NE R4R 01 4 8206070356 Interim deficiency rept re design of horizontal fire FILE /P: 8206070356 dampers.initia!!g reported on B20323. Air Balance horizontal FICHE: 13363 121 13363 123 e dampdrs cleaned.8 lade locks secured & damaged closer springs TABM: replaced. Completion espected by 820001. , CARY.R.J. Texas Utilities Electric Co. (forme 820528 3pp. e TRDEFR EUTTUCC DEFR-820611 NE R4 e 8206210550 Deficiency rept re orifice plates sizing outside specified FILE /P: 8206210550 tolerance. initially reported 811217. All orifice plates FICHF: 13567 010 13567 011 affecting plant safety will be procured from dif f erent TASM: supplier. Corrective actions to be complete by 820901. dARY.R.J. Texas Utilities Electric Co. (forme 820611 2pp. e TRDEFR EUTTUCC DEFR-820611 NE R4 01 . 4 8206210550 Deficiency rept te orifice plates sizing outside specified FILE /P: 8206210550 tolerance. initially reported 811217.A11 orifice plates FICHE: 13567 010 13567 011 offecting plant safety will be procured from different TASM: supplier. Corrective actions to be complete by 820901.
# CARY.R.J. Texas Utilities Electric Co. (forme 820611 2pp.
. 4+
4 e i
1/ 6/05 PAGE 5 U. S. NUCLEAR RECULATDRY CDPHISSION , PRELIMINARY TITLE LIST REPDRT
@0-4,45 Comanche Peak Steam Electric Station. Unit i
-. DTC AA1: DIN: RA1: SN ,
TRDEFR EUTTUCC DEFR-820715 NE R4 , 8207200151 Interim deficiency rept re Westinghouse RCS wide range FILE /P: 8207200151 proosUre measurements. initially reported 820400. Evaluation FICHE: 13915 244 13915 244 ,
'i n progress. Nest rept will be provided by 820917. TASM:
?.
C AR Y.*R J. Texas Utilities Electric Co. (forme 820715 1p. , TRDEFR EUTTUCC DEFR-820715 NE R4 01 , 8207200151 Interim deficiency rept to Westinghouse RCS wide range FILE /P: 8207200151 pressure measurements. initially reported 820408. Evaluation FICHE: 13915 244 13915 244 , in y,rogress. Nest rept will be provided by 820917. TASK: CARY.R.J. Tenas Utilities Electric Co. (forme 820715 1p. ,; TRDEFR EUTTUCC DEFR-820804 NE R4R , 8200160269 Interim deficiency rept re diesel generator auntliary skid. FILE /P: 8208160269 Initially reported on B20709. Evaluation continuing. Final FICHE: 14347 042 14347 042 g rept~espected by 821018. TASM: CARY.R.J. Temas Utilities Electric Co. (forme 820804 1p. , TRDEFR EUTTUCC DEFR-820804 NE R4R 01 4 8200160269 Interim deficiency rept te diesel generator musiliary skid. FILE /P: 8208160269 Initially reported on B20709. Evaluation continuing. Final FICHE: 14347 042 14347 042 I rept espected by 821018. TASK: [ARY.R.J. Tesas Utilities Electric Co. (forme 820804 1p. TRDEFR EUTTUCC DEFR-820024 NE R4 8209030264 Followup to 820723 deficiency rept to enterior wall of steam FILE /P: 8209030264 generator compartment wall. Void located in Uni t 1 not FICHE: 14723 039 14723 039 3 Unit 2. TASM: 1 C ARY. R. J. Teams Utilities Electric Co. (forme 920824 1p. _. t E i
4 1/ 6/CS PACE 6 p't' 3 U. S. NUCLEAR RECULATORY COHNISSION { 1 O i PRELIMINARY TITLE LIOT REPORT e 10-og5 Comanche Peak Steam Electric Station. Unit 1
=_ -.....
- ' DTC AA1: DIN: rat: SN e
TRDEFR EUTTUCC DEFR-820025 t4E R4R e 8209030135 Interim deficiency rept to Pacific pump multi-vane dif f usor FILE /P: 8209030135 crcching. Initially reported on 820414. Evaluation should be FICHE: 14721 307 14721 307
' completed by 821108. TASK: t
- rs C AR Y.* R. J. Tesas Utilities Electric Co. (forme 820825 1p.
TRDEFR EUTTUCC DEFR-820025 NE R4R 01 B20903'0135 Interim deficiency rept to Pacific pump multi-vane diffusor FILE /P: 8209030135 crcching. Initially reported on 820414. Evaluation should be FICHE: 14721 307 14721 307 com,pleted by 821100. TASK: CARY.R.J. Tesas Utilities Electric Co. (forme 820825 1p. TRDEFR EUTTUOC DEFR-820900 NE R4R B209160093 Deficiency rept to defective governor drive coupling on Fi!5/P: 8209160093 diosel generators. Initially reported on 820912. Drive FICHE: 14891 287 14891 288 coupling elements will be replaced w/ neoprene since TASK: g locprene rapid 1g deteriorates & ultimately fails. C ARY. R. J. Texas Utilities Electric Co. (forme 820908 2pp. TRDEFR EUTTUCC DEFR-820908 NE R4R 01 8209160093 Deficiency rept re defective governor drive coupling on FILE /P: 8209160093 diesel generators.Initia!!g reported on B20912. Drive FICHE: 14B91 287 14891 298 coupling elements will be replaced w/ neoprene since TASK: toeprene rapidig deteriorates & ultimately fails. CARY.R.J. Tesas Utilities Electric Co. (forme 820908 2pp. TRDEFR EUTTUCC DEFR-820914 NE R4
. 9 8209270149 Interim deficiency rept we defective Limitorgue pinion l eg s. FILE /P: 8209270149 Initially reported en B20018. Evaluation comple tion FICHE: 14995 143 14995 143 ' '
ospected by 821021. TASK: t CARY.R.J. Texas Utilities Electric Co. (forme 820914 1p. , , 9 9 i V
'i
- 1/ 6125 PAGE 7
% U. S. NUCLEAR CECULATORY CONNISSION
[ :l t e PIEllHINARY TITLE LIOT CEPORT 50-CG5 Comanche Peak Steam Electric Station. Unit 1 *
;, DTC AA1: DIN: RA1: SN TRDEFR EUTTUCC DEFR-820914 NE R 4 01 ,
B209270149 Interim deficiency rept re defective Limitorgue pinion noys. FILE /P: 8209270149 Initially reported on 820018 Evaluation comple tion FICHE: 14995 143 14995 143 nepected by 821021. TASK: # CARY,R.J. Texas utilities Electric Co. (forme 820914 1p. TRDEFR EUTTUCC DEFR-820914 NE R4R , 8209270152 Interin deficiency rept re solid state protection sgs FILE /P: 8209270152 uncetectable failure. Initially reported on B20818. Evaluation FICHE: 14995 142 14995 142 ccntinuing. Nest rept espected by 821130. , TASM: CARY.R.J. Texas Utilities Electric Co. (forme 820914 1p. TRDEFR EUTTUCC DEFR-820914 NE R4R 01 , B209270152 Interim deficiency rept to solid state protection sus FILE /P: 8209270152 redetectable failure. Initially reported on 820818. Evaluation FICHE: 14995 142 14995 142 ccasinuing.Ne st rep t e spected by 821130. TASK: # C ARY. R. J. Tesas Utilities Electric Co. (forme 820914 1p. 4 TRDEFR EUTTUCC DEFR-820915 NE R4 4 8209270087 Final deficiency rept te Westinghouse RCS wide-range FILE /P: 8209270387 prcosure measurements. Initially reported on 820408. Problem FICHE: 14996 245 14996 245 wot reportable per 10CFR50.55tel. TASK: 8 dARY.R.J. Tesas utstities Electric Co. (forme 820915 1p. 1 TRDEFR EUTTUCC DEFR-820915 NE R4 01 , 8209270007 Final deficiency rept to Westinghouse RCS wide-range FILE /P: 8209270007 pressure measurements. Initially reported on B20400 Problem FICHE: 14996 245 14996 245 nat r'eportable per 10CFR50.55(el. TASK: , I CARY.R.J. Texas Utilities Electric Co. (forme 820915 1p. e e h l
. 26 ' "
so u. us a .sw. u
, U. S. NUCLEAR RECULATORY CDMNISSION i ,
O t PRELINIP4ARY TITLE LIST REPCIT 50-Cc5 Comanche Peak Steam Electric Station. Unit 1 4 DTC AA1: DIN: RA1: 6H g TRDEFR EUTTUCC DEFR-820920 NE R4R e B210040318 Interie deficiency rept re conduit supports. Initially FILE /P: 8210040318 rOgCFttd en 820823 Evaluation continuing. Completion FICHE: 15586 167 15586 167 anticipated by B21022. TASM: # CARY.'f.J Texas Utilities Electric Co. (forme 820920 1p. e TRDEFR EUTTUCC DEFR-820920 NE R4R 01 O B210040318 Interim deficiency rept te conduit supports. Initially FILE /P: 8210040318 tc7crted on 820023 Evaluation centinuing. Completion FICHE: 15586 167 15586 167 anticipated by B21022. TASM:
- CARY.R.J. Texas Utilities Electric Co. (forme 820920 1p.
e TRDEFR EUTTUCC DEFR-821006 NE R4A e 0210260375 Dettetency rest ce overtorgving of safety-relief valves. FILE /P: 8210260375 Initially reported on 820910. Evaluation in progress & FICHE: 15803 362 15803 362 will to completed tg 821130. TASK: g CARY.R.J Tomas Utilities Electric Co. (forme 821006 1p.
, t TRDEFR EUTTUCC DEFR-821006 NE R4R 01 0
8210260375 Deficiency rest ce overtorguing of saf ety-relief valves. FILE /P: 8210260375 laitially reported on 820910. Evaluation in progress & FICHE: 15803 362 15803 362 will be completed hg 821130. TASM:
- CARY.R.J. Texas Utilities Electric Co. (forme 821006 1p.
9 TRDEFR EUTTUCC DEFR-821012 NE R4R . . El B210250338 Interim deficiency rept re defective Limitorgue pinion FILE /P: 8210250338 tego. Initially reported on B20818. Natter not reportable per FICHE: 15790 331 15790 331 10CFC50.55tel based on investigation. TASK: El C AR Y. R. J. Temas Utilities Electric Co. (forme 821012 sp.
. 9 9
4
! m -
1/ s/;5 {* 7" . U. S. NUCLEAR RECULATORY CDMNISSIDN PACE 9 f( PRELININARY TITLE LIST CEPORT 30-pC5 Comanche Peak Steam Electric Station. Unit 1 DTC AA1: DIN: RA1: SN TRDEFR EUTTUCC DEFR-821012 NE R4R 01 8210250338 Interim deficiency rest we defective Limitorque pinion FILE /P: 8210250338
, tags. Initially reported en B20818. Natter not reportable per FICHE: 15790 331 15790 331 10CFR 50. 55 ( e ) based en investigation. TASK:
N CARY.R.J. Tesas Utili.:ss Electric Co. (forme 821012 1p. TRDEFR EUTTUCC DEFR-821014 NE R4R B210250346 Interim deficiency rept te linear indications identified in FILE /P: 8210250346 diesel generator musiliary skid. Initially reported on FICHE: 15790 336 15790 336 820709. Evaluation continuing. Nest rept espected by 821217. TASK: C ARY. R. J. Tesas Utilities Electric Co. (forme 821014 1p. TRDEFR EUTTUCC DEFR-B21014 NE R4R 01 B210250346 Interim deficiency rept te lineer indications identified in FILE /P: 8210250346 diesel generator musiliarg slid. Initially reported on FICHE: 15790 336 15790 336 820709. Evaluation continuing. Nest rept espected by 821217. TASK: C RY. R. J. Tesas Utilities Electric Co. (forme 821014 1p. TRDEFR EUTTUCC DEFR-B21020 *sE R4R 8211020510 Final deficiency rept te reins, of conduit supports. FILE /P: 8211020510 Initially reported on 820823. Investigation determined matter FICHE: 15889 301 150d9 301 pot reportable per 10CFR50.55(el. Records supporting TASK: Determination available at site. CARY.R.J. Tesas utilities Electric Co. (forme 821020 ty.
. TRDEFR EUTTUCC DEFR-921025 NE R4R B211020274 Interim depiciency rept to pipe restraint weld indications. FILE /P: 8211020274 Initially reported on B20930. Inves tigation continuing. Final FICHE: 15882 138 15d82 138 rept esperted kg 830103. TASK:
t CARY.R.J. Temas Utilities Electric Co. (forme B21025 1p. O I i Z7' ,
.. o. us . . . . - ..
/ U. C. NUCLE AR RECULATORY COMMISSION f
' (' . PRELIMINARY TITLE LI3T REPORT 4
50-C05 Comanche Peah Steam Electric Station. Unit 1
- . DTC AA1: DIN. RA1: SN e
4 TRDEFR EUTTUCC DEFR-821025 NE R4R 01 - 9 B211020274 Interim deficiency rept te pipe restraint weld indications. FILE /P: 8211020274 Initially rep orted on B20930. Inves tigation con tinuing. Final FICHE: 15882 138 15882 138 TASK:
- ycot espected by 830103.
A GARYeR.J. Tevas Utilities Electric Co. Eforme 821025 1p. e TRDEFR EUTTUCC DEFR-821029 NE R4R e 0211090126 Final deficiency rept re embedded rotafoam & pigwood in FILE /P: 8211090126 cuelliarg b1ds concrete floor slabs. Initially reported on FICHE: 16003 299 16003 299 821020. Dettelency determined not reportable under TASM: 10CFR 50. 55( e l . CARY.R.J. Texas Utilities Electric Co. (forme 821029 1p. e TRDEFR EUTTUCC DEFR-821029 NE R4R 01 e i 8211090126 Final deficiency rept te embedded rotafoam & plywood in FILE /P: 8211090126 austilary bids concrete floor slabs.Initis11g reported on FICHE: 16003 299 16003 299 9 021020. Deficiency determined not reportable under TASK: 4 10CFR50.55(el. CARY.R.J. Texas Utilities Electric Co. (forme 821029 1p. e e TRDEFR EUTTUCC DEFR-821123 NE R4 e B310130278 Final deficiency rept ce pipe wall thickness of reactor FILE /P: 8310130278 coolant pressuriser surge line. Initially reported on 821101. FICHE: 20723 197 20723 197 Deficiency not reportable per 10CFR50. 55(el. TASK: dARY.R.J. Tevas utilities Electric Co. (forme 821123 1p. .- TRDEFR EUTTUCC DEFR-821123 NE R4 01
- e C31:130278 Final deficiency rept te pipe mall thickness of reacter FILE /P: 8310130278 coolant pressuriser surge line. Initially repor ted on 821101. FICHE: 20723 197 207p3 197
Deficiency not reportable per 10CFR50.55(el. TASK:
# 1p.
CARY. R. J. Texas utilities Electric Co. (forme 821123
- e 1
0 l
1/ 6/95 PAGE 11 y }* U. Q. NUCLEAR RECULATDRY CONNISSIDN i P!ELIMINARY TITLE LIST REPORT 445 Comanche Peat Steae Electric Station. Unit 1
.. _ _. -._..___ . ..._____ - 1
- . DTC AA1: DIN; R A1: SN i
TRDEFR EUTTUCC DEFR-821227 NE R4R C301040545 Final deficiency rept re pipe whip restraint weld
~
FILE /P: 8301040545
'i ndications. Initially reported on B20930. Condition FICHE: 16646 224 16646 224
- Catermined not reportable per 10CFR50. 55(el. TASK:
N CARY.R.J. Tesas Utilities Electric Co. IFerme 621227 1p. TRDEFR EUTTUCC DEFR-821227 PE R4R 01 , C301040545 Final deficiency rept te pipe whip restraint weld FILE /P: 8301040545 i indications. Initially reported en 820930. Con d i t io n FICHE: 16646 224 16646 224 datermined not reportable per 10CFR 50. 55( e l. TASK: C ARY. R. J. Tesas Utilities Electric Co. (forme 821227 1p. TRDEFR EUTTUCC DEFR-821227-01 NE R4R 8301100073 Interie deficiency rept to potential defect in pisten shirt FILE /P: 8301100073 ccstings. Initially reported on 821201. Completion of FICHE: 16697 187 16697 187 ovaluation espected by 840206. TASM: CARY.R.J. Tesas Utilities Electric Co. (force 821227 1p. TRDEFR EUTTUCC DEFR-821227-01 PE R4R 01 8301100073 Interim deficiency rept to potential defect in pisten shirt FILE /P: 8301100073 ccstings. Initially reported en 821201. Ceeplet t en of FICHE: 16697 187 16697 187 ovaluatten espected hg R40206. TASM: CARY.R.J. Tomas Utilities Electric Co. iforme 821227 1p. TRDEFR EUTTUCC DEFR-821227-01 NE R4R O2 8301100073 Interim deficiency rept to potential defect in pisten shirt FILE /P: 8301100073 cestings.In.tially reported en 821201. Completion of FICHE: 16697 187 16497 187 ovaluation espected by 840206. TA9K: CARY.R.J. Tesas Utilities Electric Co. iforme 821227 1p. I l I 30-
3, U 1/ 6/05 PACE 1 3 , S. NUCLEAR RECULATORY COMMISSIOta ( r' 0 PRELInINARY TITLE LIST REPORT 50-4c9 Coms..che Peak Steam Electric Station. Unit i e
, _ , _ _ . . ~ - ~ _ _ . ~ _ _ _ _ _ _ . . _ _ ~
;, DTC AA1: DIN: R A1: SN e
TRDEFR EUTTUCC DEFR-830113 NE R4 e C301210122 Interam deficiency rept re Pacific Pump multi-vane diffuser FILE /P: 8301210122 crcching Inntiallg reported on B20414. App 1tcant awaiting FICHE: 16079 063 16879 063
.WeCttnghouse rept. Completion by 830301 ant ic ip a t ed. TASK: e CARhjR.J. Texas Ut116ttes Electric Co. (terme B30113 1p.
g TRDEFR EUTTUCC DEFR-830113 NE R4 01 e B301210122 Interim deficiency rept re Pacific Pump multi-vane diffuser FILE /P: 8301210122 cracking.Initia!!v reported on B20414. Applicant avatting FICHE: 16879 063 16879 063 Westinghouse rept. Completion by 830301 anticipated. TASM: 4 CAR . R. J. Tesas Utilities Electric Co. (forme 830113 1p. e TRDEFR EUTTUCC DEFR-830215 NE R4 B302280295 Interim deficiency rept re Borg-Warner chech valve e FILE /P: 8302280295 malfunction Initially reported on 830120. Caused by broken FICHE: 17312 358 17312 359 tachtweld securing stud connecting valve disc to operating TASK: 4
- cre. Valves wt!! he repaired by B30601.
CARY.R.J. Teams Utilities Electric Co. (forme B30215 2pp.
.' =
TRDEFR EUTTUCC DEFR-830215 NE R4 01 e B302280295 Interim deficiency rept re Borg-Warner check valve FILE /P: 8302280295 mattunction. Initially reported on 83G120. Caused by broken FICHE: 17312 358 17312 359 tact weld securing stud connecting valve disc to operating TASK:
- crm_ Valves will be repaired by B30601.
CARY.R.J. Temas Utilities Electric Co. (forme B30215 2pp. e TRDEFR EUTTUCC DEFR-830225 NE R4R e B303000063 Interim deficiency rept re position indication of EMD gate FILE /P: 8303080363 volves supplied by Westinghouse.Initia!!v reported en FICHE: 17457 229 17457 230 C30125. Af fec ted valves modified per manufacturer TASK:
- recommendations Correc tive actions to be complete by B30408.
CARY.R.J. Tesas Utilities Electric Co. (forme B30225 2pp. , 9 g
, en
. 's ' .
k $ 1/ 6/05 PA0E 2
, U.- S. NUCLEAR RECULATORY COrg11SSIOP4 PRELIMINARY TITLE LIST REPORT 50-4 5' Comanch e Peak Stese Electric Station. Unit 1 .
DTC AA1: DIN: RA1: SN TRDEFR EUTTUCC DEFR-830225 NE R4R 01 8303Qe0063 Interie deficiency rept te position indication of EMD gate FILE /P: 8303000063 v::nve s supplied by Westinghouse.Initia11, reported on FICE: 17457 229 17457 230 C30125. AFFected valves seedified per marefacturer TASK: rccommendations. Corrective actions to be complete hg 830408. CARY.R.J. Tesas Utilities Electric Co. Iforme 830225 2pp TRDEFR EUTTUCC DEFR-830225 NE R4 8303000189 Final deficiency rept te procurement & anstallatten of FILE /P: B303000198 noneetallic insulation. Initially reported on 830126. Ma t t er FICE: 17457 359 17457 359 sact reportante per 10CFR50.55(el. TASK: CARY.R.J. Tesas Utilities Electric Co. (forme 830225 ty. TRDEFR EUTTUCC DEFR-830225 NE R4 01 8303090199 Final deficiency rept te precurement & installation of FILE /Pr 830309019e uenmetallic insulatten.Initialle reported on 830126. Matter FICE: 17457 359 17457 359 not reportable per 10CFM50.55tel. TASK: l CARY.R.J. Tesas utilities Electric Co. (forme 833225 1p. TRDEFR EUTTUCC DEFR-B30228 NE R4R I By3080334 Final deficiency rept te radiation monitoring sys. Initially FIL W P: 8303090334
' reported en B30201. Investi gation c omplete. Met t er not FICE: 17442 342 17442 342 reportable per 10CFR50. 55(el. TASK:
CARY.R.J. Tesas Utilities Electric Co. (forme 830220 Ip.
, TRDEFR EUTTUCC DEFR-930229 NE R4R 01 8303000334 Final deficiency rept to radiation monitoring sys. Initially FILE /P: 8303090334 rcperted en 830201. Investigation complete. Matter not FICHE: 17442 342 17442 342 ccpertable per 10CFR50.55(el. TASK:
CARY.R.J. Tesas Utilities Electric Co. (forme 830228 1p. i 32.
9 (*
- U. D. NUCLEAR RECULATORY Cortt!SSION
(
' .(
; PRELIt11 NARY TITLE LIOT REPORT S
i 50-p';5 Comanc h e Peak Sieam Electric Station. Unit 1 1
%. . . . _ . . . - - - - . . - = = - - _
. DTC AA1: DIN; RA1: SM i
TRDEFR EUTTUGC DEFR-830223-OI NE R4R 8303000378 Iaterim deficiency rept re cracted Pacific Pump multi-vano FILE /P: 8303083378 diffuser producing linear indications. Initial 1g reported en FICE: 17453 267 17453 267 S20414. Deficiency not reportehle per 10CTR50.55tel. TASM: '. A GARYsR.J. Tesas Utilities Electric Co. (forme 830228 1p. l TRDE8 R EUTTUCC DEFR-830228-01 NE R4R 01 ) 5 0303080378 Interim deficiency rept re cracked Pacific Pump multi-vene FILE /P: 8303083378 diffuser producing linser indications. Initially reported on FICHE: 17453 267 17453 267 8204,14. Deficiency not reportable per 10CFR50. 5 5( e l. TASM: 1 CARV.R.J. Tesas Utilities Electric Co. iforme 830228 1p. TRDEFR EUTTUGC DEFR-830329 NE R4
*a 8334050406 Interim deficiency rept te vender installed HVAC sys. FILE /P: 8304050406 Inittelly reported on 833301. Ewaluation continuing. FICE: 17838 066 17838 066 Completten er evaluation anticipated by 830516. TASM: s 4 GARY.R.J. Tesas Utilities Electric Co. (forme 830329 Sp.
.? 4 TRDEFR EUTTUOC DEFR-830329 NE R4 01 4
8304050406 Interim deficiency rept re vender installed HVAC sys. FILE /P: 8304050406 Initially reported en 830301. Evaluation continuing. FICE: 17838 066 17838 066 Completion et evaluation anticipated by 830516. TASK: # [ARY.R.J. Texas Utilities Electric Co. (forme 830329 1p. 4
- TRDEFR EUTTU0C DEFR-830407 NE R4 g
8307260391 Interim deficiency rept re new fuel storage racks.Initia!!v FILE /P: 8307260391 rcocrted verbe11g en 830310. Evaluation wi;I be completed FICHE: 19733 168 19733 168 4 ha 8d0601. TASM: 8 CLEMENTS.B.R. Temas Utilities Electric Co. (forme 830407 1p. , G e 1 33 =
Y. [' ( 1/ c/85 PACE 4
. U.- S. NUCLEAR RECULATORY CONNISSIDN PRELIMINARY TITLE LIST REPORT '
50-445 Comanche Pean Steam Electric Station. Unit 1
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DTC AA1: DIN: RA1: SN TRDEFR EUTTUCC DEFR-830407 NE R4 01 B307260391 Interim deficiency rept re new fuel storage racts. Initially FILE /P: 8307260391 reyorted verbally on 830310 Evaluetten will be completed FICHE: 19733 160 19733 168 by 830601. TASM: CLEMENTS.B.R. Tesas Utilities Electric Co. trorme 830407 1p. I TRDEFR EUTTUCC DEFR-830421 NE R4R C304260362 Interim deficiency rept re welding of brackets an vender- FILE /P: 8304260362 cupplied valves & guality of brac k et-to-ac tuat or barre t. FICHE: 18198 017 18198 018 Initially reported on 830324. Brackets & welds will be TASM: replaced.- CARY.R.J. Tesas Utilities Electric Co. iforme 830421 2pp. j TRDEFR EUTTUCC DEFR-830421 NE R4R 01 j- C304260362 Interim deficiency rept te welding of brackets on vendor- FILE /P: 8304260362 copplied valves & goality of brec t et-to-actuator barrel. FICHE: 18198 017 18198 021 Initially reported on 830324. Brackets & welds will be TASM: replaced. CARY.R.J. Tesas Ut1 titles Electric Cc. (forme 830421 2pp. TMDEFR EUTTUCC DEFR-830421 NE R4R 02 Cg04260362 Interim deficiency rept te welding of brackets en vendor- FILE /P: 8304 60362 copplied valves & qualaty of brac k et-to-ac tuator barret. FICHE: 18198 017 18198 021 Initially reported on 833324. Brackets & welds will be TASK: replaced.
.CARY.R.J. Tenee Utilities Electric Co. iforme B30421 2pp.
. TRDEFR EUTTUCC DEFR-830511 NE R4 p305200278 Interde Deficiency Rept SDAR-106 re HVAC hangers fabricated FILE /P: 8305200298 et variance w/ design. Initially reported an 830301. Completion FICHE: 18516 273 18516 273 of evaluation anticipated tg B30705. TASM:
CARY.R.J. Teams Utilities Electric Co. (forme 830511 1p. 1 - 34
4 ) .
! s 1/ 6/25 PAGE 5 U. S. NUCLEAR REQULATORY CONNISSION PRELIMINARY TITLE LIST REPORT ,
50-C45 C onse c h e Pe a k Steen Electric Station. Unit 1 DTC AA1: DIN: RA1: SN -
, TRDEFR EUTTUCC DEFR-830511 NE R4 01 C3352OO298 Interim Deficiency Rept SDAR-106 re HVAC hangers fabricated FILE /P: B305200299 ot'wertence w/ design. Initially r*Forted on 830301. C omp l e t i on FICHE: 18516 273 18516 273 of % valuation anticipated by 830705. TASM:
CARY.R.J. Tesas Utilities Electric Co. (forme 930511 1p. . i ML, TRDEFR EUTTUCC DEFR-830511 /' NE R4 02 C3052OO299 Interim Deficiency Rept EDAR-106 re HVAC hangers fabricated FILE /P: 8305200299 on variance w/ design. Initiativ reported on B30301. Completion FICHE: 19516 273 19516 273 et evaluation anticipated by 830705. TASK: 4ARY.R.J. Tesas Utilities Electric Co. iforme 830511 1p. *
, TRDEFR EUTTUCC DEFR-830511 NE R4 03 C3052'0298 0 Interim Deficiency Rept SDAR-106 re HVAC hangers fabricated FILE /P: 8305200298 %
ct variance w/ design. Initially reported on 830301. Comp l e t i on FICHE: 18516 273 19516 273 of evaluation anticipated by B30705. TASM: CARY.R.J. Tesas Utilities Electric Co. iforme B30511 1p. TRDEFR EUTTUCC DEFR-830531 NE R4 C306090043 Interim deficiency rept te new fuel storage rack support FILE /P: 8306090043 fcnchors installed u/o proper autherfastion. Initially FICHE: 18793 295 16793 296 rcported en 930407. Approved anchoring design implemented. TASM: N3 evidence that deficiency is generic. CARY.R.J. Tesas Ut!!ities Electric Co. (forme 830531 2pp. TRDEFR EUTTU0C DEFR-830531 NE R4 01 C306090043 Interim deficiency rept re new fuel s torage rack support FILE /P: 9306090043 y cnchors installed w/o proper authorisation. Initially FICHE: 18793 295 19793 286 reported on 830407. Approved anchoring design implemented. TASM: , No evidence that deficiency is generic. CARY.R.J. Texas Utilities Electric Co. (forme 830531 2pp. I -
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J. } ,. , U. S. NUCLEAR RECULATORY CONNISSION , s-PRELIMIP4ARY TITLE LIST REPORT 50-CC$ Comanche Peak Steam Electric Station. Unit l'
;, DTC AA1: DIN: RA1: Sri ,
TRDEFR EUTTUCC DEFR-830602 NE R4 , C306130440 Interim deficiency rept to letdown HX anchors. Initially FILE /P: 8306133440
- togort ed on 830709. Evaluation continuing. Investigation FICHE: 18821 211 18821 211 ,
will be completed by 830708. TASK: ts C AR Y. R. J. Tesas Utilities Electric Co. iforme 830602 1p. , TRDEFR EUTTUCC DEFR-830602 NE R4 01 ,
- C306130440 Interim deficiency rept re letdown HX anchors.Initia11g FILE /P: 8306133440 l reycrted on 830709. Evaluation continuing. Investigation FICHE: 19821 211 19821 211 ,
will be completed by 830708. TASM: CARY.R.J. Tesas Utilities Electric Co. iforme 830602 1p. , TRDEFR EUTTUCC DEFR-830602 NE R4 02 , C306130440 Interim deficiency rept te letdown HX anchors. Initially FILE /P: 8306130440 rdocrted on 830709. Evaluation continuing. Investigation FICHE: 19821 211 19821 211 , will' he completed by 830708. TABM: CARY.R.J. Texas Utilities Electric Co. iforme 830602 1p. , TRDEFR EUTTUCC DEFR-830602 NE R4 03 8306130440 Interim deficiency rept te letdown HX anchors. Initially FILE /P: 8306130440 ecyseted on 830709. Evaluation continuing. Investigation FICHE: 19821 211 19821 211 will be completed by 830708. TASM: 5ARY.R.J. Tes.s utilities Electric Co. iforme 830602 1,. TRDEFR EUTTUCC DEFR-830621 NE R4 C3063DOO55 Final deficiency rept to adhesive bond on Westinghouse NLP FILE /P: 83063C0355 (leep power suppigt printed circuit cards. Initially FICHE: 19121 018 191,21 018 rep 6rted on 830601. Condition not reportable under TASK:
,10CFR50.55(el.
- C ARY. R. J. Tesas Utilities Electric Co. (forme 830621 1p.
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U. S. NUCLEAR RECULATORY COMMISSIDN p , P.TELININARY TITLE LIST REPORT 50-OC5' Comanche Peak Steam Electric Station. Unit 1 4 DTC AA1: DIN: RA1: SN TRDEFR EUTTUCC DEFR-830621 NE R4 01 B306300055 Final deficiency rept to adhesive bond on Westinghouse NLP FILE /P: 8306300355 tjocp. power suppigi printed circuit cards. Initially FICHE: 19121 018 19121 018 rcysrted on 830601. Condition not reportable under TASM: . 10CFR50.55(e). C AR Y'.,R. J. Texas Utilities Electric Co. (forme B30621 1p. TRDEFR EUTTUCC DEFR-830621-01 NE R4 8306300074 Final deficiency rept re Class 1 support matt w/o complete FILE /P: 8306300374 NDE required for NF2500. Initially reported on 830525. Item FICHE: 19121 002 19121 002 act' reportable under 10CFR50.55(e). TASK: - C art.' R. J. Temas Utilities Electric Co. (forme 830621 1p. TRDEFR EUTTUCC DEFR-830621-01 NE R4 01 B306300074 Final deficiency rept to Class 1 supp ort matt w/o complete FILE /P: 8306300374 NOG reguired for NF2SOO Initially reported on 830525. Item FICHE: 19121 002 19121 002 Rot reportable under 10CFR50.55(e). TASK:
- g C AR Y. R. J. Tomas Utilities Electric Co. (forme 830621 1p.
s O TRDEFR EUTTUCC DEFR-830621-02 NE R4 e B306300088 Final deficiency rept te Jam nuts on rigid struts not FILE /P: 8306300388 cdaguately installed to prevent rotation of strut barrel. FICHE: 19048 345 19048 345 Initta11g reported on 833526. Item not reportable under TASK:
- EOCFR50.55(e).
C ARY. R. J. Temas Utilities Electric Co. (forme 830621 1p. e TRDEFR EUTTUCC DEFR-830621-03 NE R4 e 8306300167 Deficiency rept re nonsafety-related components in cooling FILE /P: 8306300167 wat2r Class V piping. Controls will be added to esisting FICHE: 19122 065 19122 066 levol. transmitters by 830801 to sense depletion of surge TASK:
- tant.
9 AR Y. R. J. Texas Utilities Electric Co. (forme 830621 2pp. e w W wy 1 I 37 .
4, us us e n.% o p* U. S. NUCLEAR RECULATORY CDHNISSIDN , PIELIMINARY TITLE LIOT REPORT 30-405 Comanche Peak Steam Electric Station. Unit 1
- DTC AA1: DIN: RA1: SN TRDEFR EUTTUCC DEFR-830621-03 NE R4 01 C306300167 Deficiency rept re nonsafety-related components in cooling FILE /P: 8306303167 FICHE: 19122 065 19122 066 , water Class V piping. Controls uilt be aeded to esisting TASK:
lovel transmitters bg 830901 to sense depletion of surge tenh CAR /.R.J Texas Utilities Electric Co. (forme B30621 2pp. TRDEFR EUTTUCC DEFR-830704 NE R4 S307150100 Interim Deficiency Rept SDAR-106 re HVAC hangers fabricated FILE /P: 8307150100 ct ' variance w/ design documents. Initially repor ted on B30301. FICHE: 19536 126 19536 126 l i Evcluation continuing w/completten espected by B30901. TASK: CARY.R.J. Texas utilities Electric Co. (forme B30704 1p. TRDEFR EUTTUCC DEFR-830704 NE R4 01 l 8307150100 Interim Deficiency Rept SDAR-106 re HVAC hangers fabricated FILE /P: 8307150100 ct variance w/ design documents. Initially reported on 830301. FICHE: 19536 126 19536 126 Evaluation continuing w/ completion espected by 830001. TASK: CARY.R.J. Tesas Utilities Electric Co. (forme 830704 1p. TRDEFR EUTTUCC DEFR-B30704 NE R4 02 C307150100 Interin Deficiency Rept SDAR-106 re HVAC bangers fabricated FILE /P: 8307150100 at variance w/ design documents. Initially reported on 830301. FICHE: 19536 126 19536 126 Evaluation continuing w/ completion espected by B30001. TASK: I CARY.R.J Texas Utilities Electric Co. (forme 830704 17 TRDEFR EUTTUCC DEFR-830707 NE R4 C307150294 Interim deficiency rept re letdown HE anchors. Initially FILE /P: 8307150294 ccported en 830506. Anchor bolts found bound in end of FICHE: 19532 203 19532 204 olotted holes prohibiting movement.Neunting configuration TASK:
; revised.
CARY.R.J. Tesas Utilities Electric Co. (forme 830707 2pp. O I 3V-
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PRELIMINARY TITLE LIST REPORT
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50-c05 Comanche Peak Steam Electric Stetion. Unit 1
. - DTC AA1: DIN: RA1: SN
' s TRDEFR EUTTUCC DEFR-830707 NE R4 01 s
B307150294 Interim deficiency rept te letdown Ht anchors.Initia11g FILE /P: 8307150294 FICHE: 19532 203 19532 204 reycrted on B30506. Anc hor bolts found bound in end of TASr.: s olettes holes prohibiting movement. Mounting configuration revised. C ARYrR. J. Tesas Uttisties Electric Co. iforme 830707 2pp. s TRDEFR EUTTUCC DEFR-830712 NE R4 s B307220259 Deficiency rept te bolting matt used for cable trag clamps. FILE /P: 8307220259 Ctructural drawings specify high stran2th botting matts. FICHE: 19684 211 19684 212 s Balts used were mild steel type. Design change issued. TASK: Coverk performed as reguired. SPENCE.M.D. Tesas Utilities Electric Co. (forme 830712 2pp. s TRDEFR EUTTUCC DEFR-B30712 NE R4 01 s B307220259 Deficiency rept re botting matt used for cable trag clamps. FILE /P: 8307220259 FICHE: 19684 211 19684 212 Cte,uctural drawings specify high strength betting satts. TASK: Ocits.used were slid steel type. Design change issued. Cework performed as reguired. g SPENCE.M.D. Tomas Utilities Electric Co. (forme B30712 2pp. s
- TRDEFR EUTTUCC DEFR-830729 NE R4 m
B309090744 Final deficiency rept to HVAC hangers fabricated at variance FILE /P: 8309090744 FICHE: 19964 014 19964 014 w/dasign documents. Investigation concluded mat ter not TASK: repcetab le per 10CFR50. 55t el. Record s supporting Catceminatten available at site. 6, PENCE. M. D. Temas Utilities Electric Co. (forme B30729 1p. s TRDEFR EUTTUCC DEFR-830729 NE R4 01 s ' B309090744 Final deficiency rept to HVAC hangers fabricated at variance FILE /P: 8300090744 FICHE: 19964 014 19964 014 w/Casign documents. Investigation concluded mat ter not TASK: 4 repcrtan t e per 10CFR50.55tet. Records supporting
- catereination available at site.
~
JSPENCE.ML D. Temas Utilities Electric Co. (forme B30729 Ip. s e
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'. U. S. NUCLEAR RECULATORY CONHISSION I/ 6/85 PACE 10 PRELIMINARY TITLE LIST REPORT D
50-445 Comanche Peak Steam Electric Station. Unit 1 g DTC AA1: DIN: RA1: SN , g TRDEFR EUTTUCC DEFR-B30909 NE P4 B308220270 Deficiency rept we inadeguate overpressure protection for FILE /P: 8300220270 , cpent fuel peel costing HIs for component cooling water. FICHE: 20107 039 20107 041 Pressure relief piping & valve component configuration TASK: ovaluated. , CARY.R.J. Tesas Utilities Electric Co. iterme B30909 3pp. . TRDEFR EUTTUCC DEFR-830009 NE R4 01 8308220270 Deficiency rept te inadeguate overpressure protection for FILE /P: B309220270 , cpent fuel peel cooling HIs for component cooling water. FICHE: 20I07 039 20107 041 Pressure relief piping & valve component configuration TASK: ovaluated. , CARY.R.J. Tesas Utilities Electric Co. IForme 830909 3p p. TRDEFR EUTTUCC DEFR-830925 NE R4 C309020390 Confirms deficiency verbally reported on 830729 re high temp FILE /P: 8309020390 , condittens in reacter vesset support & neutron detector well FICHE: 20249 356 20249 356 creas. Evaluation continuing w/ completion espec ted by B30909 TASK: , CARY.R.J. Tesas Utilities Electric Co. trerme B30825 1p. i TRDEFR EUTTU0C DEFR-830906 NE R4 B309160192 Interim deficiency rept te high teop conditions in reacter FILE /P: 8309160192 vessel support & neutron detector well areas. Initially FICHE: 20387 253 20387 253 reported en B30729. Completion anticipated by 830930. TASK: C AR Y. R. J. Tesas Utilities Electric Co. iPorme B30906 1p. TRDE8'R EUTTUCC DEFR-830906 tK R4 01 B309160192 Interte deficiency rept re high temp conditions in reacter FILE /P: 83C9160192 vessel support & neuteen detector we!! areas. Initially FICHE: 20307 253 20387 253 reported on 830729. Ceep l e t t en an t ic ipa t ed b y 830930. TASA: CARY.R.J. Teses Utilities Electric Co. trerne B30906 1p.
- l .
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Q . L. 1/ 6/15 PACE 11 U. S. NUCLEAR RECULATORY COMMISSION
- i. PRELIMINARY TITLE LIST REPORT 30-443 Cesenche Peat Steam Electric Station. Unit 1 DTC AAt: DIN. rat: SN
- TRDEFR EUTTUCC DEFR-930907 NE R4 B309160219 Interim deficiency rest te Borg-Warner chect valves. Valves FILE /P: 8309160219 cf similar design disassembled. inspec ted & rep aired. Due to FICHE: 20391 OT7 20391 098 member of affected valves involved.cerrective actions will TASK:
not be completed prior to fuel load. C AR Y. R. J. Tesas Utilities Electric Co. (forme B30907 2p p. TRDEFR EUTTDOC DEFR-030907 NE R4 01 830 160218 Interim deficiency rept re Borg-Warner check valves. Valves FILE /P: 8309160218 cf sistler design disassembled. inspected & repaired.Due to FICHE: 20391 09/ 20391 098 neeber of affected valves involved.cerrective actions will TASM: oct be completed prior to fuel load. CARY.R.J. Temas Utilities Electric Co. (forme B30907 2pp. TRLEFR EUT100C DETR-G30926 NE R4 S311130268 Interim deficiency rept to temp in escess of FSAR parameters FILE /P: 8310833268 Ocperienced in annvive between reacter vessel insulation & FICHE: 20723 215 20723 216 bateld wa11.Coe11pg increased by reducing chilled water TA9K: temp & installing addl cooling coil. CARY.O.L. Tesas Utilities Electric Co. (forme B30926 2pp. TRDEFR FUTTl80C DEFR-830926 NE R4 01 Bbt:130268 Interim deficiency rept to temp in escess of FSAR parameters FILE /P: 8340130269 osperienced in annulus between reactor vessel insulation & FICHE: 23723 213 20723 216 cDield wall. cooling increased by reducing chilled water temp TA5M: G installing addl cooling coil. CARY.O.L. Tesas Utilities Electric Co. (forme 830926 2pp.
~~ TPDEFR EUTTUCC DEFR-831017 NE R4 5B310290003 Final deficiency rept te premature corrosion of valves in FILE /P: 8310"?O203 cyc water ses. Initially reported on 830919. Investigation FICHE: 20% f 330 20933 330 complete. Item not reportable under 10CFR50.55tel. TACK:
" C ARY. R. J. Tesas utilities Electric Co. (forme B31017 1p.
I 9/
1/ 4/05 PACE 12 O ) s U. S NUCLEAR REGULATORY COMMISSION 4
'- '6 PZEL1HINARY TITLE LIST CEPORT 50,-Cc3 Comanche Peak Steam Electric Station. Unit 1
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;, DTC AA1: DIN: RA1: SN TRDEFR EUTTUCC DEFR-831017 NE R4 01 C310280003 Final deficiency rept re premature corrosion of valves in FILE /P: 8310283003 ove mater sys. Initially reported on 830919. Investigation FICHE: 20933 330 20933 330
. complete. Item not reportable under 10CFR50.55(e). TASM:
h CARY.R.J Tesas utilities Electric Co. (forme '831017 1p. TRDEFR EUTTUCC DEF 1-831116 NE R4 C311280243 Deficiency rept to defective breaker support braclets in FILE /P: 8311280243 480-volt switchgear. Thirty-sis brackets contain suspect FICHE: 21281 052 21281 053 welds. Replacements tentatively scheduled for shipment in TASM: Dec'1983. CARY. R. J. Tesas Utilities Electric Co. (forme 831116 2pp. TRDEFR EUTTUCC DEFR-831116 NE R4 01 8311280243 Deficiency rept re defective breaker support brackets in FILE /P: 8311280243 480-volt switchgear. Thirty-sis trackets contain suspect FICHE: 21281 052 21261 053 welds. Replacements tentatively scheduled for shipment in TASM: Doc 1983. C ARY. R. J. Tesas Utilities Electric Co. (forme 831116 2pp. TRDEFR EUTTUCC DEFR-831228 NE R4 8401100004 Deficiency Rept SDAR-123 re Barton recommended calibr checke FILE /P: 8401100304 for Westinghouse supplied pressure transmittere. Revised FICHE: 21761 206 21761 207 ootpoint wit! he incorporated into equipment list for TASM: ' pressuriser pressure safety injection ogs by 840601. C ARY. R. J. Tesas Utilities Electric Co. (forme 831228 2pp. e TRDEFR EUTTUCC DEFR-831228 NE R4 01 t 8401100004 Deficiency Rept SDAR-123 re Barton recommended calibr checks FILE /P: 8401100304 for Westinghouse supplied pressure transmitters. Revised
~ FICHE: 21761 206 21761 207 cotpoint will be incorporated into equipment list for TASM: '
.pressuriser pressure safety injection sys by 840601.
- C ARY. R. J. Tesas Utilities Electric Co. (forme 831228 2pp.
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, f ', U. S. NUCLEAR REGULATDRY CDMNIGSIDN
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- 1 PRELIMINARY TITLE LIST REPDRT 50 ,445' Comanche Peah 8 team Electric Station, Unit 1 -
-- = , ___.._. - _ - _ _ . _ _ _ _ . - - _ _ _ _ _ _ _ _ _ _ _ _ _ , , _ _ _ _ _ _ _
f* DTC AA1: DIN: RA1: EN TRDEFR EUTTUCC DEFR-831228 NE R4 02 1401100004 Deficiency Rept SDAR-123 re Barton recommended calibr checks FILE /P: 8401100004
.far Westinghouse supplied pressure transmitters. Revised FICHE: 21761 206 21761 207 setpoint will be incorporated into equipment list for TABM: .
presturiser pressure safety injection sys by 840501. C AR Y. R. J. Tesas Utilities Electric Co. (forme 831228 2pp.
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PRELIMINARY TITLE LIST REPORT i. 50-445 Comanche Peak Steam Electric Station, Unit ! _ __ =--_. ._ DTC AA1: DIN: RA1: SH
.; TRDEFR EUTTUCC DEFR-840118 NE R4 8401270275 Interim Deficiency Rept SDAR-124 re installation of chlorine FILE /P: 8401270275 sedsors not conforming to CDC 4,5 & 19,FSAR commitments to FICHF: 21976 007 21976 009 Reg Guides 1. 78 & 1. 95 & NUREC-0737, It em III. D. 3. 4. Sen s or TASK: 3.D.3.4 relocated & mods to provide adequate calibr instituted.
CARY,R.J. Texas Utilities Electric Co. (forme 840118 3pp. TRDEFR EUTTU0C DEFR-840118 NE R4 01 0401270275 Interim Deficiency Rept SDAR-124 re installation of chlorine FILE /P: 8401270275 sensors not conforming to CDC 4,5 & 19,FSAR commitments to FICHE: 21976 007 21976 009 Reg Guides 1.78 & 1.95 & NUREC-0737, Item III.D.3.4. Sensor TASK: 3.D.3.4 relocated & mods to provide adequate calibr instituted. C AR Y, R. J. Tesas Utilities Electric Co. (forme 840118 3pp. i i- TRDEFR EUTTUCC DEFR-840207 NE R4 s 8402170202 Interim deficiency rept re laminations & delaminations in FILE /P: 8402170282 cable trag support column in cable spread room.InitialIV FICHE: 22297 162 22297 162
,beported on 840111. Evaluation continuing.Next rept espected TASK:
by 840309.
- C AR Y, R. J. Texas Utilities Electric Co. (forme 840207 1p.
'% TRDEFR EUTTUCC DEFR-840208 NE R4 Of02220420 Deficiency Rept SDAR-126 re defective diesel generator FILE /P: 8402220120 engine push rods. Defective push rods will be removed & FICHE: 22340 172 22340 173 scrapped & replacements requisitioned & installed before TASK:
aperation.
,CARY,R.J. Texas Utilities Electric Co. (forme 840208 2pp.
,, TRDEFR EUTTUCC DE'FR-840208 NE R4 01 p402220420 Deficiency Rept SDAR-126 re defective diesel generator FILE /P: 8402220420 engine push rods. Defective push rode will be removed & FICHE: 22' e 172 22340 173 scrapped & replacements requisitioned & installed before TASK:
operation. CARY,R.J. Teras Utilities Electric Co. (forme R40208 2pp.
- d. 1/ 6/05 PACE 2 p, ([' . U. G. NUCLEAR REQULATORY COMMISSION
** }i PRELIMINARY TITLE LIST REPORT 50.445 Comanche Peak Steam Electric Station, Unit 1 ,
I* DTC AA1: DIN: RA1: SN TRDEFR EUTTUCC DEFR-840213 NE R4 8402220033 Final deficiency rept re stainless steel tubing observed FILE /P: 8402220333
', crac k ed. Inves tigation complete. Mat ter not repor table under FICHE: 22338 255 22330 255 10CFR50.55(el. TASK:
ts CARY.R.J. Texas Utilities Electric Co. (forme 840213 1p.
, TRDEFR EUTTUCC DEFR-840213-01 NE R4 8402220171 Final deficiency rept to section modulus used in design of FILE /P: 8402220171 pipe supports using tube steel. Initially reported on 840118. FICHE: 22340 137 22340 137 Cs,ndition determined not reportable per 10CFR50.55(el. TASK:
CARY.R.J. Tomas Utilities Electric Co. (forme 840213 1p. TRDEFR EUTTUCC DEFR-840213-02 NE R4 8402220545 Deficiency rept re failed inverters in NSSS. Caused by FILE /P: 8402220545 grounded secondary winding of inverter fervorosonant output FICHE: 22333 132 22333 133 transformers. Transformers will be returned to manufacturer TASK: for repair. q ARY. R. J. Texas Utilities Electric Co. (forme 840213 2pp. TRDEFR EUTTUCC DEFR-840215 NE R4 8402280268 Deficiency rept to error i s. tolerances used in calibr of FILE /P: 8402200268 edhesion tester. Initially reported on 840116. Cond i tion not FICHE: 22399 071 22399 071 reportable under 10CFR50.55(e). Evaluation continuing & TASK: Icempletion anticipated by 840515. CARY.R.J. Texas Utilities Electric Co. (forme 840215 1p. TRDEFR EUTTUCC DEFR-840220 NE R4 8402280493 De fi ciency Rep t SDAR-131 re lugs found w/ bad crimps. FILE /P: 8402280193 Initially reported on 840124. Evaluation continuing & FICHE: 22407 076 22k07 076 completion anticipated by 840330. TASK: 1 CARY.R.J. Texas Utilities Electric Co. (forme 840220 1p. O
\ VS.
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,I 1/ 6/05 PACE 3
, , U. S. NUCLEAR REGULATORY COMMISSION
;, PRELIMINARY TITLE LIST REPDRT LO-445 Comanche Peak Steam Electric Statien, Unit 1
, DTC AA1: DIN: RA1: SN TRDEFR EUTTUCC DEFR-840220 NE R4 01 h
8402280493 Deficiency Rept SDAR-131 re logs found w/ bad crimps. FILE /P: 8402280193 Initially reported on 840124. Evaluation continuing & FICHE: 22407 076 22407 076
' ompletion anticipated by 840330.
c TASK: CARY,R.J. Texas Utilities Electric Co. (forme 840220 1p. TRDEFR EUTTUCC DEFR-840306 NE R4 8403160213 Interim Deficiency Rept SDAR-125 re laminations & FILE /P: 8403160213
, delsminations in cable trag support column in cable spread FICHE: 22655 231 22655 231 room. Initially reported on 840111. Evaluation c ontinuing. TASK:
Completion espected by 840515. CARY,R.J. Texas Utilities Electric Co. (forme 840306 1p. 9 I TRDEFR EUTTUCC DEFR-840306 NE R4 01 0403160213 Interim Deficiency Rept SDAR-125 re laminations & FILE /P: 8403160213
'delaminations in cable trag support column in cable spread FICHE: 22655 231 22655 231
' room. Initially reported on 840111. Evaluation c ontinuing. TASK:
. Completion espected by 840515.
CARY,R.J. Texas Utilities Electric Co. (forme 840306 1p. i TRDEFR EUTTUCC DEFR-840329 NE R4 d404090280 Interim Deficiency Rept SDAR-131 re defective lug crimps on FILE /P: 8404090200 field routed cable.Eguipment supplied by Reliance will be FICHE: 22939 361 22939 362 inspected for proper terminal L connector pin crimping. TASK: Equipment rework will be completed by 840531.
- CLENENTS.B.R. Texas Utilities Electric Co. (forme 840329 2pp.
<. ? , TRDEFR EUTTUCC DEFR-840329 NE R4 01 8404090200 Interim Deficiency Rept SDAR-131 re defective lug crimps on FILE /P: D4
' ' field routed cable. Equipment supplied by Reliance will be FICHE: 22.(,'90200 361 22939 362 inspected for proper terminal & connector pin crimping. TASK: l
,, Equipment rework will be completed by 840531.
( CLEMENTS D.R. Texas Utilities Electric Co. (forme 840329 2pp. I l. l i l
j, g ', , 1/ 6/05 P /.CE 4 p U. S. NUCLEAR RECULATDRY CDNNISSIDN t PRELIMINARY TITLE LIST REPDRT i 50-d45 Comanche Peak Steam Electric Station. Unit 1 , f* DTC AA1: DIN: RA1: SN TRDEFR EUTTUCC DEFR-840330 NE R4 8404100154 Interim deficiency rept re discrepancy w/ installation of FILE /P: 8404100154 gcurtain five dampers w/o proper provisions for thermal FICHE: 22963 238 22963 238 esp,ansion. Initially reported on 840309. Completion of TASK: eva(vation espected by 840615. CLEMENTS.E.H. Texas Utilities Electric Co. (forme 840330 1p.
, TRDEFR EUTTUGC DEFR-840330 NE R4 01
?
0404100154 Interim deficiency rept re discrepancy w/ installation of FILE /P: 8404100154 curtain five dampers w/o proper provisions for thermal FICHE: 22963 238 22963 238 espansion. Initially reported on 840309. Completion of TASK: evaluation espected by 840615. CLEMENTS.E.H. Tesas Utilities Electric Co. (forme 840330 1p. TRDEFR EUTTUGC DEFR-840330 NE R4 02 8404100154 Interim deficiency rept re discrepancy w/ installation of FILE /P: 8404100154 curtain five dampers w/o proper provisions for thermal FICHE: 22963 238 22963 238 espansion. Initially reported on 840309. Completion of TASK: evaluation espected by 040615. CLEMENTS.E.H. Texas Utilities Electric Co. (forme 840330 1p. TRDEFR EUTTUCC DEFR-840413 NE R4 i 8404200083 Interim deficiency rept re vendor documentation of GA FILE /P: 8404200083 inspector eye esam records. Initially rerorted on 840215. FICHE: 24120 134 24120 134 Evaluation completion espected by 840515. TASK: T CLEMENTS.B.R. Texas Utilities Electric Co. (forme 840413 1p.
. TRDEFR EUTTUCC DEFR-840417 NE R4 8404260218 Interim deficiency rept re laminations & delaminations in FILE /P: 8404260218 cable trag support column. Initially reported on 840111. Item FICHE: 24207 266 24dO7 266 not' reportable under 10CFR50.55(el. Supporting documentation TASK:
I available onsite. , CLEMENTS.B.R. Tesas Utilities Electric Co. (forme 840417 1p. h I f7.
4 ;' p . I 1/ 6/85 PACE 5
, U. S. NUCLEAR REGULATORY COMMISSION * 'a PRELIMINARY TITLE LIST REPDRT i 50-445' Comanche Peak Steam Electric Station. Unit 1 DTC AA1: DIN: RA1: SN TRDEFR EUTTUCC DEFR-840417-01 NE R4 8404460457 Interim deficiency rept re discrepancy in diesel generator FILE /P: 8404260457 tunbocharger thrust bearing lubrication. Initially reported FICHE: 24203 001 24203 001 on 840321. Evaluation continuing. Completion e sp ected by TASK:
840507 CLEMENTS.B.R. Texas Utilities Electric Co. (forme 840417 1p. TRDEFR EUTTUCC DEFR-840425 NE R4 8405d70127 Deficiency rept te stock mati supplied by Taylor-Forge. FILE /P: 8405070127 Initially reported on 840328. Item not reportable per FICHE: 24336 000 24336 000 10CFR50.55(el. TASK: CLEMENTS.B.R. Texas Utilities Glactric Co. (forme 840425 1p. TRDEFR EUTTUCC DEFR-040504 NE R4
- i. . g 8405140199 Interim deficiency rept te discrepancy in diesel generator FILE /P: 8405140199 turbocharger thrust bearing lu* ication. Initially reported FICHE: 24460 089 24460 089 en 840321. Evaluation continuing. Nest rept will be submitted TASK:
by 840716.
/ CLEMENTS.B.R. Texas Utilities Electric Co. (forme 840504 1p.
l TRDEFR EUTTUCC DEFR-840511 NE R4 Bf05210215 Interim Deficiency Rept SDAR-12D re discrepancy in vendor FILE /P: 8405210215 documentation of GA inspector eye eram records. Evaluation FICHE: 24518 100 24518 180 continuing.Ne xt rept w!!! he submitted by 840629. TASK: CLEMENTS.B.R. Texas Utilities Electric Co. (forme 840511 1p. TRDEFR EUTTUCC DEFR-840511 NE R4 01 p4052'10215 Interim Deficiency Rept SDAR-12D re discrepancy in vendor FILE /P: 8405210215 documentatfor of GA inspector eye exam records. Evaluation FICHE: 24" 100 24518 180 continuing. Nest rept will be submitted by 840629. TASK:
,,CLEMENTS.B.R. Texas Utilities Electric Co. (forme 840511 1p.
l
.. 1/ 6/85 PACE 6 6 < U. S. NUCLEAR RECULATOflY CONNISSION PRELIMINARY TITLE LIST REPORT 50-445 Comanche Peak Steam Electric Station. Unit 1 m I. DTC AA1: DIN: R A1: SN o
TRDEFR EUTTUCC DEFR-840511-01 NE R4 m 8405210231 De fi c iency Rep t SDAR-129 re error in tolerances used in FILE /P: 8405210231 calibr'of adhesion testee" Initially reported on 840116. FICHE: 24518 224 24518 224 Tnvestigation incomplete. Nest rept will be submitted by TASK:
- C40001.
CLEMENTS.B.R. Texas Utilities Electric Co. (forme 840511 1p. 9 e TRDEFR EUTTUCC DEFR-840511-01 NE R4 01 e E405210231 Deficiency Rept SDAR-129 re error in tolerances used in FILE /P: 8405210231 calibr of adhesion tester. Initially reported on 840116. FICHE: 24518 224 24518 224 Inves.tigation incomplete. Nest rept will be submitted by TASK: 9 840001. w, CLEMENTS.B.R. Tesas Utilities Electric Co. (forme 840511 1p. 9 TRDEFR EUTTUCC DEFR-040522 NE R4 e 8406080222 Final Deficiency Rep t~Ti iR-134 re rod ent damag e to Class IE FILE /P: 8406010222 cables. Initially reported on 840426. Condition determined not FICHE: 24754 336 24754 336 reportable under 10CFR50.55(el. TASK:
- CLEMENT 8.B.R. Tesas Utilities Electric Co. (forme 840522 1p.
e TRDEFR EUTTUCC DEFR-840522 NE R4 01 e 8406010222 Final Deficiency Rept SDAR-134 re rodent damage to Class IE FILE /P: 8406010222 ccbles. Initially reported on 840426. Condition determined not FICHE: 24754 336 24754 336 rcpertable under 10CFR50.55(el. TASK:
- T CLEMENTS.D.R. Texas Utilities Electric Co. (forme 840522 1p.
e . TRDEFR EUTTUCC DEFR-840528 NRRL e 8405310005 Interim deficiency rept re problems w/ assured fire damper FILE /P: 8405310005 closur.e.Each closure being esamined to determine safety FICHE: 24723 143 24723 143 impact'& reportability. TASK:
- bEORCE.J.B. Texas Utilities Electric Co. (forme 840528 1p.
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is ' U. S. NUCLEAR RECULATDRY CDMNISSION
,{ f'= eg j
N PRELIMINARY TITLE LIST REPDRT 50-4 4 5 'C omanc h e Peak Steam Electric Station, Unit I a
- , yz- --. -
DTC AA1: DIN: RA1: SN
- f. m TRDEFR EUTTUCC DEFR-840702 NE R4 s
8407090186 Final Significant Deficiency Rept SDAR-138 i-- possible FILE /P: 8407090186 insulation damage in certain reels of Rockbestos Cla:, IE FICHE: 25443 150 25443 150 gulti-conductor cable. Initially reported on 840606. Matter TASK: a not reportable under 10CFR50.55(el. CLEN(P4TS. B. R. Texas Utilities Electric Co. (forme H40702 1p. n TRDEFR EUTTUCC DEFR-840702 NE R4 01 9 C407090186 Final Significent Deficiency Rept SDAR-138 re possible FILE /P: 8407090186 insulation damage in certain reels of Rockbestos Class IE FICHE: 25443 150 25443 150 multi-conductor cable. Initially reported on 840606. Natter TASK: 9 not,feportable under 10CFR50.55(el. CLENENTS.B.R. Texas Utilities Electric Co. (forme 840702 1p. e TRDEFR EUTTUCC DEFR-840702-01 NE R4 e E407090190 Interim Significant Deficiency Rept SDAR-123 re calibr FILE /P: 8407090190 torhnique of pressure transmitters. Corrective action will be FICHE: 25443 245 25443 245 compteted by 841231. TASK:
- CLEMENTS.B.R. Tomas Utilities Electric Co. (forme 840702 1p.
, e TRDEFR EUTTUCC DEFR-840702-01 NE R4 01 e
8407090190 Interim Significant Deficiency Rept SDAR-123 re calibr FILE /P: 8407090190 technique of pressure transmitters. Corrective action will be FICHE: 25443 245 25443 245 csmpleted by 841231. TASt".:
- CEENENTS.D.R. Tomas Utilities Electric Co. (forme 840702 1p.
e TRDEFR EUTTUCC DEFR-840702-02 NE R4 e 8407090200 Interim Significant Deficiency Rept SDAR-137 re FILE /P: 8407090200 , inconsistency in draft Tech Spec & FSAR accident analysis. FICHE: 25442 344 25442 344 Initially reported on 840604. Based on investigation. matter TASK: not reportable per 10CFR50.55(e). JCLEMENTS.B.R. Texas Utilities Electric Co. (forme 840702 1p. O e 9 I l SI ~
b ? i 1/ 6/85 PAGE 9 i U. S. NUCLEAR RECULATORY CONHISSION t
..". PRELIMINARY TITLE LIST REPORT *
- 50-[4$ComanchePeak Steam Electric Station, Unit i
, DTC AA1: DIN: R A1: Sti TRDEFR EUTTUCC DEFR-840702-02 NE R4 01 C407090200 Interim Significant Deficiency Rept SDAR-137 re FILE /P: 8407090200
- inhonsistency in draft Tech Spec & FSAR accident analysis. FICHE: 25442 344 25442 344 Initially reported on 840604. Based on investigation, matter TASK:
not reportable per 10CFR50.55(e). CLEMENTS,B.R. Tesas Utilities Electric Co. (forme 840702 1p. TRDEFR EUTTUCC DEFR-840702-03 NE R4 84Q7090255 Interim Significant Deficiency Rept SDAR-136 re temp FILE /P: 8407090255 envelope requirements on envirt.1 qualifications of equipment FICHE: 25450 190 25450 190 eutside containment for high energy line break s. Initially TASK: reported on 840604.Next rept by 840831. CLEMENTS.B.R. Texas Utilities Electric Co. (forme 840702 1p. TRDEFR EUTTUCC DEFR-840702-03 NE R4 01 s C407090255 Interim Significant Deficiency Rept SDAR-136 re temp FILE /P: 8407090255 envelope requirements on environ qualifications of equipment FICHE: 25450 190 25450 190 autside containment for high energy line break s. Initially TASK: reported on 840604. Nest rept by 840831.
; CLEMENT 8.B.R. Texas Utilities Electric Co. (forme 840702 1p.
TRDEFR EUTTUCC DEFR-840711 NE R4 G*07200247 Final Deficiency Rept SDAR-139 re indeterminate fluoride FILE /P: 8407200247 Icontent of Hanville insulation. Initially reported on 840612. FICHE: 25697 234 25697 234 Candition not reportable under 10CFR50.55(el. TASK: CLEMENTS.B.R. Tesas Utilities Electric Co. (forme 840711 1p. TRDEFR EUTTUCC DEFR-840711 NE R4 01 E407200247 Final Deficiency Rept SDAR-139 re indeterminate fluoride FILE /P: 8407200247 I centent of Nanville insulation. Ini tially repor ted on 840612. FICHE: 256~- 234 25697 234 Candition not reportable under 10CFR50.55(el. TASK: ' CLEr.ENT8. B. R. Tesas tittlities Electric Co. (forme 840711 1p. f
U. S. NUCLEAR REQULATURY COMMISSION h, . PRELIMINARY TITLE LIST REPDRT QO-445
=----
Comanche Peak Steam Electric Station. Unit 1 3* DTC AA1: DIN: R A1: SN TRDEFR EUTTUCC DEFR-040712 NE R4 0407250348 Significant Deficiency Rept SDAR-133 re diesel generator FILE /P: 8407250348
, turbo charger thrust bearing lubrication. Investigation FICHE: 25754 162 25754 162 determined item not reportable per 10CFR50.55(el. TASK:
h CLENdNTS B.R. Tesas Utilities Esectric Co. (forme 840712 1p. TRDEFR EUTTUCC DEFR-840712 NE R4 01 C407250340 Significant Deficiency Rept SDAR-133 re diesel generator FILE /P: 8407250348 turbo charger thrust bearing lubrication. Investigation FICHE: 25754 162 25754 162 det, ermined item not reportable per 10CFR50.55(el. TASK: .. CLEMENTS.B.R. Texas Utilities Electric Co. (forme 840712 1p. TRDEFR EUTTUCC DEFR-840720 NE R4 E4073tOOO1 Interim deficiency rept to installation of curtain fire FILE /P: 8407310001 dtmpers w/o proper provisions for thermal e x p a n s i on. FICHE: 25049 156 25349 156 Initially reported on 840309. Evaluation in progress.Next TASK: .. rept espected by 040013. CL,EMENTS. B. R. Texas Utilities Electric Co. (forme 840720 1p. i TRDEFR EUTTUCC DEFR-840731 NE R4 0400090044 Interim Significant Deficiency Rept SDAR-129 re error in FILE /P: 8408090044 tolerances used in calibr of adhesion tester. Evaluation FICHE: 25992 132 25992 132 cantinuing. Completion anticilated by 840901. TASK: %: 1 CLEMENTS,B.R. Texas Utilities Electric Co. (forme 840731 1p. 4
. TRDEFR EUTTUCC DEFR-040731 NE R4 01 C400090044 Interim Significant Deficiency Rept SDAR-129 re error in FILE /P: 8400090044 .
toler.ances used in calibr of adhesion tester. Evaluation FICHE: 25992 132 25992 132 centinuing. Completion anticipated by 840901. TASK: -; 1 CLEMENTS.B.R. Texas Utilities Electric Co. (forme 840731 1p.
.e o
k' l 53 . g.
/ 1.
1/ 6/05 PACE 11 l U. S. NUCLEAR RECULATORY COMNISSION
. .. PRELIMINARY TITLE LIST REPORT s 50-445' Comanche Peak,8 team Electric Station, Unit I DTC AA1: DIN: R A1: ET TRDEFR EUTTUCC DEFR-840806 NE R4 C40Q160510 Final Deficiency Rept SDAR-129 re error in tolerances used FILE /P: 8408160510 in'lcalibr of adhesion tester. Initially reported on 840116. FICHE: 26107 360 26107 360 Investigation complete. Natter not reportable under TASK:
10CFR50.55fe). CLEMENTS B.R. Temas Utilities Electric Co. (forme 840806 1p. f TRDEFR EUTTUCC DEFR-840006 NE R4 01 C40pf60510 Final Deficiency Rept SDAR-129 re error in tolerances used FILE /P: 8408160510 in calibr of adhesion tester. Initially reported on 840116. FICHE: 26107 360 26107 360 Investigation complete. Natter not reportable under TASK: 10CFR50.55(e). CLEMENTS,B.R. Texas Utilities Electric Co. (forme 840806 1p. TRDEFR EUTTUCC DEFR-840008 NE R4 I s C400160185 Interim Deficiency Rept SDAR-140 re goalification of main FILE /P: 8400160185 oteam relief valves for actual loading conditions. Initially FICHE: 26106 328 26106 328 reported on 840710. Evaluation in progress & should be TASK: completed by 840831. CLEMENTS,0.R. Texas Utilities Electric Co. (forme 840800 1p. 4
, TRDEFR EUTTUCC DEFR-840808 NE R4 01 8400160185 Interim Deficiency Rept SDA9-140 re qualification of main FILE /P: 8400160185 Isteam relief valves for actual loading conditions. Initially FICHE: 26106 328 26106 328 reported on 840710. Evaluation in progress & should be TASK:
completed by 840831. CLENENTS,B.R. Texas Utilities Electric Co. (forme 840800 1p. TRDEFR EUTTUCC DEFR-840013 NE R4 c. C400200295 Interim Significant Deficiency Rept SDAR-132 re installation FILE /P: 8408200295 T of curtain fire dampers w/o proper provisions for thermal FICHE: 261 + 101 26140 105 espansion. Initially reported on 840330. Review revealed 50 TASK: ' dampers required rework or mod. Nest rept by 840817. FIKAR.L.F. Tesas Utilities Electric Co. (forme 840813 Spp. S l l Y l .
g 's *
,, 1/ 6/05 PACE 12 U. S. NUCLEAR CECULATORY cot 1NISS10N h':,
- PRELIMINARY TITLE LIST REPDRT 50-$45 Comanche Peak Steam Electric Station, Unit 1 s I*
DTC AA1: DIN; R A1: SN o TRDEFR EUTTUCC DEFR-840013 NE R4 01 o. C400200295 Interim Significant Deficiency Rept SDAR-132 re installation FILE /P: 8408203295
'of curtain fire dampers w/o proper provisions for thermal FICHE: 26140 101 26140 105
'espansion. Initially reported on 840330. Review revealed 50 TASK: #
d cmp'e r s required rework or mod.Next rept by 840817. FIKAR.L.F. Texas Ut!!ities Electric Co. (forme 840813 Syp. TRDEFR EUTTUCC DEFR-840816 NE R4 l M i 0408200468 Final deficiency rept re flooding levels in electrical FILE /P: 8408283168 centrol bldg resulting from fire suppression. Initially FICHE: 26282 098 26282 099 r ep o.r t e d on 840717. Engineering resolutions to isolate TASK: 9 off'ected drains will be implemented by 840830. CLEMENTS.B.R. Tesas utilities Electric Co. (forme 840816 2pp. i TRDEFR EUTTUCC DEFR-840816 NE R4 01 (i E400200468 Final deficiency rept re flooding levels in electrical FILE /P: 8408280468 control b1dg resulting from fire suppression. Initially FICHE: 26282 098 26282 099 reported on 840717. Engineering resolutions to isolate TASK: 9, affected drains will be implemented by 840830. l CLEMENTS B.R. Tesas Utilities Electric Co. (forme 840816 2pp. ' 4 TRDEFR EUTTUCC DEFR-840816-01 NE R4 s 8:00290125 Interim Deficiency Rept SDAR-142 re ungualified Limitergue FILE /P: 8408290125 electric motors. Initially reported on 840720. Evaluation will FICHE: 26297 343 26297 343 he completed by 840921. TASK: *- 1 CLEMENTS.B.R. Texas Utilities Electric Co. (forme 840816 1p. s
- TRDEFR EUTTUCC DEFR-840816-01 NE R4 01 g
8:00290125 Interim Deficiency Rept SDAR-142 re ungualified Limitorque FILE /P: 8408290125 . , electric motors. Initially reported on 840720. Evaluation will FICHE: 26297 343 26297 343 be completed by 840921. TASK: 8 I i
- CLEMENTS.B.R. Texas Utilities Electric Co. (forme 840816 1p.
t 6 4 l . t 4
4 "'t1*, . i p i U. 8. NUCLEAR RECULATORY CONHISSION 1/ 6/85 PACE 13 PRELIMINARY TITLE LIST REPDRT ' 50-445 Comanche Peat steam Electric Station. Unit 1 DTC AAt: DIN: R A1: SN
. TRDEFR EUTTUCC DEFR-840820 NE R4 8408280375 Final deficiency rept re defective diesel generator valve FILE /P: 8400280375 springs. Initially reported on 840720. Condition not FICHE: 26282 270 26282 278 reportable under 10CFR50.55(el. TA9K:
CL'NENTS.B.R. E Texas Utilities Electric Co. (forme 840820 1p. t TRDEFR EUTTUCC DEFR-840820 NE R4 01 ! 0408280375 Final deficiency rept ce defective diesel generator valve FILE /P: 8408200375 springe. Initially reported on 840720. Condition not FICHE: 26282 278 26282 278 reportable under 10CFR50.55(el. TASK: CLEMENTS.B.R. Texas Utilities Electric Co. (forme 840820 1p. j TRDEFR EUTTUCC DEFR-840820-01 NE R4 OC08280304 Interim deficiency rept re mati defect in diesel generator FILE /P: 8408200304 fuel injection pump delivery valve holder. Initially reported FICHE: 26282 103 26282 103
,bn 840720. Evaluation will be completed by 840921. TASK:
. CLENENTS.B.R. Texas Utilities Electric Co. (forme 840820 1p.
TRDEFR EUTTUCC DEFR-840830 NE R4 Ofo9130389 Interim Deficiency Rept SDAR-140 re several main steam FILE /P: 8409130389 relief valves not gualified for actual loading conditions. FICHE: 26465 224 26465 224 Ctepletion anticipated by 841009. TASK:
,CLEMENTS.B.R. Terms Ut!!! ties Electric Co. (forme 840830 1p.
,,, TRDEFR EUTTUCC DNFR-840830 NE R4 Of B'09130389 Interim Deficiency Rept SDAR-140 re several main steam FILE /P: 8409130309 relief valves not qualified for actual loading conditions. FICHE: 262', 224 26465 224 Completion anticipated by 841009. TASK:
CLENENTS,B.R. Texas Utilities Electric Co. (forme 840830 1p. l
.#.
- 1/ 6/05 PACE 14 U. S. NUCLEAR RECULATORY CDMMISSION
(" O
} PRELIMINARY TITLE LIST REPORT 5,0 ,c45 Comanche Peak Steam Electric Station. Unit 1 ,
O I. DTC AA1: DIN: RA1: SM O TRDEFR EUTTUCC DEFR-840830-01 NE R4 O C409130392 Interim Deficiency Rept SDAR-145 re piping matl that does FILE /P: 8409130392 hit me'et ultrasonic test requirements for ND-2500 ASME Class FICHE: 26465 211 26465 211 1 cpplications. Initially reported on 840815. Up on comple tion TASK: O' of investigation, matter determined not reportable. CLEMENTS.B.R. Tesas Utilities Electric Co. (forme 840830 1p.
?
TRDEFR EUTTUCC DEFR-840830-01 NE R4 01 . 3 C4C9138392 Interim Deficiency Rept SDAR-145 re piping matl that does FILE /P: 8409130392 nst meet ultrasonic test requirements f or NB-2500 ASME Clas s FICHE: 26465 211 26465 211 1 cppitcations. Initially reported on 840815.Upon completion TASK: 3 er investigation. matter determined not reportable. CLEMENTS.B.R. Texas Utilities Electric Co. (forme 840830 1p. J TRDEFR EUTTUCC DEFR-840830-02 NE R4
'a COC9130428 Interim Deficiency Rept SDAR-136 re temp envelope FILE /P: 8409130428 rcquirements on environ qualification of equipment outside FICHE: 26465 134 26465 134 containment or high energy line breaks. Initially reported on TASK: W 840604. Westinghouse program developed to address issue.
CLEMENTS.B.R. Texas Utilities Electric Co. (forme 840830 1p. TRDEFR EUTTUCC DEFR-840830-02 NE R4 of w 8:09130428 Interim Deficiency Rept SDAR-136 re temp envelope FILE /P: 8409130428 requirements on environ qualification of equipment outside FICHE: 26465 134 26465 134 containment or high energy line breaks. Initially reported on TASK: d Bj0604. Westinghouse program developed to address issue. CLEMENTS.B.R. Texas Utilities Electric Co. (forme 840830 1p. w TRDEFR EUTTUCC DEFR-840921 NE R4 W C410100663 Final Deficiency Rept SDAR-144 re mat! defect of delivery FILE /P: 84101C0663 . volve, holder in diesel generator fuel injection pump. FICHE: 26897 277 26897 277 l Initially reported on 840720. Investigation concluded matter TASK: 8- ! pot reportable per 10CFR50.55(e). ! CLEMENTS.B.R. Tesas Utilities Electric Co. (forme 840921 1p. ( W. l 57 . i s
o 1's ' Ci
} 1/ 6/05 PACE 15
, U. S. NUCLEAR RECULATORY CONNISSION
, PRELIMINARY TITLE LIST REPORT '
s. 50-445 Comanche Peak Steam Electric Station, Unit 1 DTC AA1: DIN: RA1: SN TRDEFR EUTTUCC DEFR-840921 NE R4 01 E410100663 Final Deficiency Rept SDAR-144 re matt defect of delivery FILE /P: 8410100663 volve holder in diesel generator fuel injection pump. FICHE: 26097 277 26897 277 Initially reported on 840720. Investigation concluded matter TASK: not reportable per 10CFR50.55(e). CLEMENTS,B.R. Texas Utilities Electric Co. (forme 840921 1p. f TRDEFR EUTTUCC DEFR-840%21-01 NE R4 E410100729 Final Deficiency Rept SDAR-142 re ungualified Limitorque FILE /P: 8410100729 electric motors. Initially reported on 840720. Investigation FICHE: 26897 319 26897 319 concluded matter not reportable per 10CFR50.55(e). TASK: CLEMENTS.B.R. Tesas Utilities Electric Co. (forme 840921 1p. TRDEFR EUTTUCC DEFR-84C921-01 NE R4 01 I s G410100729 Final Deficiency Rept SDAR-142 re unqualified Limitorgue FILE /P: 8410100729 electric motors. Initially reported on 840720. Investigation FICHE: 26897 319 26897 319
,ts'ncluded matter not reportable per 10CFR50.55(el. TASK:
CLEMENTS.B.R. Temas Utilities Electric Co. (forme 840921 1p. TRDEFR EUTTUCC DEFR-840924-01 NE R4 8410100490 Interim Deficiency Rept SDAR-146 re concerns in design of FILE /P: 8410100490
' primary coolant & component water sys. Initially reported FICHE: 26895 220 26895 220 en 840824. Evaluation in progress & will be completed by TASK:
E41012. CLEMENTS,B.R. Texas Utilities Electric Co. (forme 840924 1p. -
, TRDEFR EUTTUCC DEFR-840924-01 NE R4 01 p110100490 Interim Deficiency Rept SDAR-146 re concerns in design of FILE /P: 8410100490 primary coolant & component water sys. Initially reported FICHE: 26f*- , 220 26895 220 en 840824. Evaluation in progress & will be completed by TASK:
841012.
,. CLEMENTS.B.R. Texas Utilities Electric Co. ( forme 840924 1p.
I SW i
4 dE ., 1/ 6/95 PACE 16 i U. S. NUCLEAR REOULATDRY COMMISSION 1 m,
- PRELIMINARY TITLE LIST REPDRT 6
50-445 Comanche Peak Steam Electric Station. Unit 1
%>..,___________.____________ ______. .._____.._ _ _____._______ _ i I. DIC AA1: DIN: R A1: SN n
TRDEFR EUTTUCC DEFR-840927 NE R4 E410150177 Final Deficiency Rept SDAR-150 re NSSS ausiliary relag FILE /P: 8410150177 trccks'not qualified per IEEE-323-1974 Initially reported on FICHE: 26970 349 26970 349 E40031. Matter not reportable per 10CFR50.55(el. TASK: h CLEMENTS.B.R. Texas Utilities Electric Co. (forme 840927 1p.
*T TRDEFR EUTTUCC DEFR-840927 NE R 4 01 3 -3 E410150177 Final Deficiency Rept SDAR-150 re NSSS ausiliary relay FILE /P: 8410150177 tracks not qualified per IEEE-323-1974. Initially reported on FICHE: 26970 349 26970 349 C40831. Matter not reportable per 10CFR50.55(el. TASK:
CLEMENTS.B.R. Texas Utilities Electric Co. (forme 840927 1p.
-)
TRDEFR EUTTUCC DEFR-840927-O! NE R4 es 84101pO333 Interim Deficiency Rept SDAR-149 re air operated diaphragm FILE /P: 8410150333 volves having natural frequency less than required. Initially FICHE: 26972 253 26972 253 repsrted on 840831. Item not reportable per 10CFR50.55(el. TASK: " CLEMENTS.B.R. Tomas Utilities Electric Co. (forme 840927 1p.
,' =>
TRDEFR EUTTUCC DEFR-840927-01 NE R4 01 so C410150333 Interim Deficiency Rept SDAR-149 re air operated diaphragm FILE /P: 8410150333 valves having natural frequency less than required. Initially FICHE: 26972 253 26972 253 reported on 840831. Item not reportable per 10CFR50. 55(e). TASK:
- C[EMENTS.B.R. Texas Utilities Electric Co. (forme 840927 1p.
w TRDEFR EUTTUCC DEFR-841000 NE R4 0 8310260202 Interim Deficiency Rept SDAR-140 re main steam relief valves FILE /P: 8410260202 not qualified for actual loading conditions. Initially FICHE: 27161 001 2716i 001 repsrted on 840710. Item not reportable per 10CFR50.55(el. TASK:
- bLENENTS.B.R. Tesas Utilities Electric Co. (forme 041000 1p. '
9 W
, s.
3 k dI is
. 9 1/ 6/85 PACE 17
, / U. S. NUCLEAR RECULATORY COMNISSION
- #* PRELIMINARY TITLE LIGT REPDRT 50-4I5'Comenche Peat hteam Electric Station, Unit 1
=
DTC AA1: DIN: RA1: SN i TRDEFR EUTTUCC DEFR-841000 NE R4 01 l 8110260202 Interim Deficiency Rept EDAR-140 re main steam relief valves FILE /P: 8410260202 no( qualified for actual loading conditions. Initially FICHE: 27161 001 27161 001 reported on 840710. Item not reportable per 10CFR50.55(el. TASK: CLEMENTS.S.R. Texas Utilities Electric Co. (forme 841000 1p. 6 1 TRDEFR EUTTUCC DEFR-841012 NE R4 8310260267 Interim Ceficiency Rept SDAR-154 re safe shutdown analysis FILE /P: 8410260267 ovaluations not considering potential fire in HVAC. Initially FICHE: 27160 226 27160 226 reported on 840913. Evaluation continuing.Next rept espected TASK: by 841106. CLEMENT 8,B.R. Texas Utilities Electric Co. (forme 841012 1p. i TRDEFR EUTTUCC DEFRm941017 NE R4 01
\
E410260267 Interim Deficiency Rept SDAR-154 re safe Shutdown analysis FILE /P: 8410260267 ovaluations not considering potential fire in HVAC.2nitially FICHE: 27160 226 27160 226 reported on 840913. Evaluation continuing. Nest rept espected TASK: by 041196. CLENFNTS,H.R. Terms Utilities Electric Co. (forme 841012 1p. TRDEFR EUTTUCC DEFR-841012-01 NE R4 8410290042 Interim Deficiency Rept SDAR-156 re safety class of FILE /P: 8410290042 f instrument lines w/pipini downstregn of root valve. Initially FICHE: 27172 357 27172 357 rsported on 840918. Evaluation continuing. completion espected TASK: by 841127. CLENENTS,8.R. Texas Utilities Electric Co. (forme 841012 1p.
#. TRDEFR EUTTUCC DEFR-841012-01 NE R4 01
' E410290042 Interim Deficiency Rept 8DAR-156 re safety class of FILE /P: 0410290042 T instrument lines w/ piping downstream of root valve.Initistly FICHE: 271*l 357 27172 357 reported on 840918. Evalua tion continuing. completion e sp ected TASM: by R41127. CLCMENTS.B.R. Teres Utilities Electric Co. (forme e41012 1p. e (oO t _ _ , , _ . , _ , , , -m . ~ =~'+ w
j A 9-1/ 6/85 PAGE 18
, . U. S. NUCLEAR RECULA1D4Y COMMISSIDN
.' PRELIMINARY TITLE LIST REPORT 3
50-445 Co,anche Peak Steam Electric Statien, Unit 1 '
.._u,-.___________....__._____..____.._______________.._ __ _ _ . _ . _ _ r f, DTC AA1: DIN: RA1: SN TRDEFR EUTTUCC DEFR-041012-02 NE R4 C410290048 Interim De f eclency Hep t SDAR-146 re d esign of prima?g FILE /P: 8410290048 coslant component uatar mys. Initially reported on 840924. FICHE: 27172 350 27172 358 Evaluation continuir.g.Ceepletion espected by 841106. TASK: '
?. ..
CLFMENTS.B.R. Tesas Utilities Electric Cs (forme 848012 1p. TRDEFR EDTTUCC DEFR-841012-02 NE R4 01 C410290048 Interim Defeciency Rept SDAR-146 re design of primary FILE /P: 0410290048 coolant coeponent water sys. Initially reported on 840924 FICHE: 27372 358 27172 358 Evolu,ation continuing. Completion espected by 841106. TASK:
- CLEMENTS,0.R. Tesas Utilities Electric Co. (forme 841012 1p.
TRDEFR EUTTUCC DER-841012 NE R4 8410270306 Interim Deficiency Rept SDAR-153 re transmitters w/ potential PILE /P: 8410290306 leonage path between sensor module & housing for moisture. FICHE: 27173 018 27173 018 Initially reported on 840913. Evaluation continuing. Nes t rep t TASK: *' espected by 841120. CLEMENTS,B.R. Tesas Utilities Electric Co. (forme 841012 Sp. i TRDEFR EUTTU0C DER-841012 NE R4 01 8410290306 Interim Deficiency Rept SDAR-153 re transmitters w/ potential FILE /P: 8410290306 Icotage path between sensor module & housing for moisture. FICHE: 27173 018 27173 018 Initially reported on 840913. Evalua tion continuing. Ne s t rep t TASK: ' otpected by 841120. CL'ENENTS, B. R. Tesas Utilities Electric Co. (forme 041012 1p. J
, TRDEFR EUTTU0C DEFR-841012-03 NE R4 4
C410300039 Interim Deficiency Rept SDAR-152 re ventilation eshaust FILE /P: 8410300339 dtmpers possibig failing to close. Initially reported on FICHE: 27185 029 27188 029 C40913/ Evaluation continuing. Completion espected by 841120. TASK: ** dLEMENTB,B.R. Texas Utilities Electric Co. (forme 841012 1p. w e l .
.s:. == (
2 U. S. NUCLEAR RECULATORY CONNISSION
- .' ' . PRELIMINARY TITLE LIST REPDRT ,
50-445' Comanche Peak Steam Electric Station, Unit 1 DTC AA1: DIN: R A1: SN'
- TRDEFR EUTTUCC DEFR-841012-03 NE R4 01 8310300039 Interim Deficiency Rept SDAR-152 re ventilation exhaust FILE /P: 8410300039 dadpers possibly failing to close. Initially reported on FICHE: 27185 029 27185 029 C40913. Evaluation continuing. Completion espected by 841120. TASK:
CLEMENTS.B.R. Tesas Utilities Electric Co. (forme 841012 1p.
. TRDEFR EUTTU0C 5EFR-841018 NE R4 8411d50470 Am' ended response to Significant Deficiency Rept SDAR-142 FILE /P: 8411050470 cubmitted on 840928 re ungualified Limitorque electric FICHE: 27327 362 27327 362 motors. Correct ref for block is CP-84-18. TASK:
CLEMENTS B.R. Texas Utilities Electric Co. (forme 841010 1p. TRDEFR EUTTUCC DEFR-841018 NE R4 01 8 C411d50470 Amended response to Significant Deficiency Rept SDAR-142 FILE /P: 8411050470 submitted on 840928 re ungualified Limitorque electric FICHE: 27327 362 27327 362 cators. Correct ref for block in CP-84-18 TASK:
, CLEMENTS.B.R. Temas Utilities Electric Co. (forme 841010 1p.
e TRDEFR EUTTUCC DEFR-841031 NE R 4 8411130642 Interim Deficiency Rept SDAR-136 re temp envelope FILE /P: 8411130642 I reguirements on environ qualification of equipment outside FICHE: 27462 044 27462 044 containment for high energy line breaks. Initially reported TASK: an 840604. Nest rept will be submitted by 850401. CLEMENTS.B.R. Temas Utilities Electric Co. (forme 841031 1p. TRDEFR EUTTUCC DEFR-841031 NE R4 01 r. E411130642 Interim Deficiency Rept SDAR-136 re temp envelope FILE /P: 8411130642
# requirements on environ goalification of equipment outside FICHE:
containment for high energy line breat s. Initially reported TASK: ' on 840604 Nest rept will be submitted by 850401.
._ CLEMENTS,B.R. Tesas Utilities Electric Co. (forme 841031 1p.
1 .
w ' 8[ > U. S. 1/ 6/85 PACE 20 NUCLEAR RECULATORY COMNISSION p ;3
.I PRELIMINARY TITLE LIST REPORT 1
5'0,445 Comanche Peak Steam Electric Station. Unit 1 /
;, DTC AA1: DIN: R A1: En e'
TRDEFR EUTTUCC DEFR-841105 NF. R4 8411160609 Interim Deficiency Rept SDAR-157 re defective architectural FILE /P: 8411160609 mall located above control room. Wall being removed. Seismic FICHE: 27545 017 27545 018 design const & insp activities for new separation wall TASK: scheduled for completion by 841215. CLENENTS.S.R. Texas Utilities Electric Co. (forme 841105 2pp.
- TRDEFR EUTTUCC DEFR-841105 NE R4 01 E411160609 Interim Deficiency Rept SDAR-157 re defective architectural FILE /P: 8411160609 wall located above control room. Wall being removed. Seismic FICHE: 27545 017 27545 018 design const & insp activities for new separation wall TASK:
schsduled for completion by 841215. CLEMENTS.B.R. Texas Utilities Electric Co. (forme 841105 2pp. TRDEFR EUTTUCC DEFR-841105-01 NE R4 0411{60617 Final Deficiency Rept SDAR-146 re design of primary coolant FILE /P: 8411160617
& camponent cooling water sys. Initially reported on 840824. FICHE: 27545 013 27545 013
- Iteo?not reportable under 10CFR50.55(el. TASK:
- CLEMENTS.B.R. Texas Utilities Electric Co. (forme 841105 1p.
TRDEFR EUTTUCC DEFR-841105-01 NE R4 01 , 8411160617 Final Deficiency Rept SDAR-146 re design of primary coolant FILE /P: 8411160617
& component cooling water sys. Initially reported on 840824. FICHE: 27545 013 27545 013 Itec not reportable under 10CFR50.55(e). TASK: '-
CbENENTS.B.R. Texas Utilities Electric Co. (forme 841105 1p. w TRDEFR EUTTUCC DEFG-841105-02 NE R4 me , 8411160619 Interim Deficiency Rept SDAR-154 re safe shutdown analysis FILE /P: 0411160619 , evaluations which did not consider effects of potential fire FICHE: 27544 361 27544 362 en co'ntrol room HVAC.All essential cables & components TASK: "8 Af f arded protec tion, per 10CFR50, App R.Section III.C.2.c.
- 'CLENENTS.D.R. Tesas Utilities Electric Co. (forme 841105 2pp.
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i _
f) e6 i Af, 7 1/ 6/05 PACE 21 l
, U. S. NUCLEAR RECULATDRY CONNISSION PRELIMINARY TITLE LIST REPORT <
50-445 Comanche Peak Steam Electric Station. Unit i DTC AA1: DIN: RA1: SN TRDEFR EUTTUCC DEFR-841155-02 NE R4 01 C411160619 Interim Deficiency Rept SDAR-154 re safe shutdown analysis FILE /P: 8411160519 ova'luations which did not consider effects of potential fire FICHE: 27544 361 27544 362 en control room HVAC.All essential cables & components TASK: afforded protection,per 10CFR50, App R Section III.O.2.c. CLEMENTS.D.R. Texas Utilities Electric Co. (forme 841105 2pp. r' TRDEFR EUTTUCC DEFR-841108 NE R4 8411$10222 Deficiency Rept SDAR-147 re Conas penetration connectors. FILE /P: 8411210222 Initially reported on 840824. Evaluation continuing. Ne x t rep t FICHE: 27606 075 27606 075 will be submitted by 041207. TASK: CLEMENTS.B.R. Texas Utilities Electric Co. (forme 041100 1p. 9 TRDEFR EUTTUCC DEFR-841100 NE R4 01 s 8411210222 Deficiency Rept SDAR-147 re Conas penetration connectors. FILE /F: 8411210222 Initially reported on 840824. Evaluation continuing Next rept FICHE: 27606 075 27606 075 pill be submitted by 841207. TASK: CLEMENTU,B.R. Texas Utilities Electric Co. (forme 841108 1p.
, TRDEFR EUTTUCC DEFR-841119 NE R4 8,412050162 Deficiency & Part 21 Rept SDAR-156 re Rosemount transmitters FILE /P: 0412050162 w/petential leakage path between sensor module & housing. FICHE: 27778 000 27778 009 Instruments removed & will be installed prior to plant TASK:
eperation. CLENENTS,B.R. Tomas Utilities Electric Co. (forme 841119 2pp.
,, TRDEFR EUTTUCC DEFR-841119 NE R4 01 C412050162 Deficiency & Part 21 Rept SDAR-156 re Rosemount transmitters FILE /P: 8412050162 w/ potential leakage path between sensor module & housing. FICHE: 277 ]' 000 27778 009 l Instruments removed & will be installed prior to plant TASK:
speration.
- ., CLENENTS B.R. Tomas Utilities Electric Co. (forme 841119 2pp.
l 1 _____ _ ~
a, osua rave sa C 8
- U. S. NUCLEAR REQULATORY COMMISSIDN
.}
PRELIMINARY TITt E LIST REPORT
.- t .
59-44,5 Comanche Pean Steam Electric Station. Unit I
- 4. DTC AA1: DIN: RA1: SN TRDEFR EUTTUCC DEFR-841119-01 NE R4 D412050235 De f i c i enc y R e p t SD AR-158 r e ITT Barton dif f erential pressure FILE /P: 8412050235 switches esperiencing setpoint shifts in excess of specs FICHE: 27778 361 27778 361 when operated at temps above 225 F. Condition not reportable TASK:
por 10CFR50.55(e1. CLEMENTS.B.R. Texas Utilities Electric Co. (forme 041119 1p. TRDEFR EUTTUCC DEFR-841119-01 NE R4 01 8412050235 Deficiency Rept SDAR-150 to ITT Barton differential pressure FILE /P: 8412050235 ewitches esperiencing setpoint shifts in excess of specs FICHE: 27778 361 27778 3o1 when, operated at temps above 225 F. Condition not reportable TASK: per*10CFR50.55(el. CLEMENTS.B.R. Tomas Utilities Electric Co. (forme 041119 1p. TRDEFR EUTTUCC DEFR-841119-02 NE R4 C412030321 Deficiency Rept SDAR-156 re safety glass of instrument lines FILE /P: 8412050321 u/ piping downstream of root valve. Initially reported on F1CHE: 27778 362 27778 362 i C40918. Condition not reportable per 10CFR50.55(e1. TASK: CLEMENTS.B.R. Texas Utilities Electric Co. (forme 841119 1p.
- TRDEFR EUTTUCC DEFR-841119-02 NE R4 01 8312050321 Deficiency Rept SDAR-156 re safety glass of instrument lines FILE /P: 8412050321 w/ piping downstream of root valve. Initially reported on FICHE: 27778 362 27778 362 840918. Condition not reportable per 10CFR50.55(el. TASK:
i CLEMENTS.B.R. Texas Ut!!! ties Electric Co. (forme 041119 1p. TRDEFR EUTTUCC DEFR-841120 NE H4 C412050207 Deficiency Rept SDAR-152 re ventilation exhaust dampers FILE /P: 8412050287 designed / installed to fait closed & divert rad ioac tive FICHE: 27778 353 27778 353 w releases to operator rooms. Initially reported on 840913. TASK:
;Cempletion espected by 841221.
CLEMENTS.B.R. Texas Utilities Electric Co. (forme 841120 1p. w w e
1/ 6/05 PACE 24 U. S. NUCLEAR RECULATORY CONNISSIDN , PRELIMINARY TITLE LIST REPORT i . , I 50-445 l *- Comanche Peak Steam Electric Station. Unit I i I. DTC AA1: DIN: RA1: SN , TRDEFR EUTTUCC DEFR-841210 NE R4 C412200015 Deficiency Rept SDAR-159 re voltage balance relays outside FILE /P: 8412200015 cpoco'for operating time. Initially reported on 841115. FICHE: 20031 305 28031 305 Candition determined not reportable per 10CFR50.55(el. TASK:
?.
CLEMENTS.B.R. Tesas Utilities Electric Co. (forme 841210 1p. TRDEFR EUTTUCC DEFR-841210 NE R4 01 8412200015 Deficiency Rept SDAR-159 re voltage balance relags outside FILE /P: 8412200015 epoco for operating time Initially reported on 841115. FICHE: 20031 305 20031 305 Ccnd) tion determined not reportable per 10CFR50.55(el. TASK: CLEMENTS.B.R. Tesas Utilities Electric Co. (forme 841210 1p. TRDEFR EUTTUCC DEFR-841217 NE R4 0501040068 Interim Significant Deficiency Rept SDAR-152 re ventilation FILE /P: 8501040368 oshev.at dampers designed / installed to fait closed. Initially FICHE: repcrted on 841213. Completion anticipated by 850206. TASK: CL,ENENTS.B.R. Tesas Utilities Electric Co. (forme 041217 1p. e TRDEFR EUTTUCC DEFR-841217 iJF R4 01 C50tO;0060 Interim Significant Deficiency Rept SDAR-152 re ventilation FILE /P: 8501040068 otheust dampers designed / installed to fait closed.Initia!!v FICHE: rcperted on 841213. Completten anticipated by 850206. TASK: T CLEMENTS.B.R. Tesas Utilities Electric Co. (forme 041217 1p. 4 e e
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l f. ' - In Reply Refer To: JUL 111983
. Dockets: 50-445/83-15 50-446/83-09 Texas Utilities Generating Company ATTN: R. J. Gary, Executive Vice President & General Manager 2001 Bryan Tower Dallas, Texas 75201 Gentlemen:
This refers to the independent measurements inspection conducted by Mr. H. W. ' Ketch, R. H. Harris, and R. M. Campbell from the NRC Region I office, during
.the period April 18.- May 6, 1983, of activities authorized by NRC Construction Permit CPPR-126 and CPPR-127 for the Comanche Peak facility, Units 1 and 2, and to the discussion of our findings with you and other members of your staff at the conclusion of the inspection.
Areas examined during the inspection and our findings are discussed in the enclosed inspection report. Within these areas, the inspection consisted of , selective examination of procedures and representative records, interviews with personnel, and observations by the inspectors. These findings are documented in the en-losed inspection report. During this inspection, it,was found that certain of your activities were in violation of NRC .equirements. Consequently, you are required to respond to these violations, in writing, in accordance with the provisions of Section 2.201 of the NRC's " Rules af Practice," Part 2, Title 10, Code of Federal Regulations. Your response should be based on the specifics contained in the Notice of Violation enclosed with this letter. In accordance with 10 CFR 2.790(a), a copy of this letter and the enclosures l will be placed in the NRC Public Document Room unless you notify this office, I by telephone, within 10 days of the date of this letter, and submit written application to withhold information contained therein within 30 days of the date of this letter. Such application must be consistent with the requirements of 2.790(b)(1). RPS-A h 0Hunnicutt/cb RPBl# DDRRP RIV JGagli r o a>
~
pGMadsen 07////83 07/s)/83 07/u/ p AlY Ottioxnt pm ' ! - , - ) (p ' 3 0 _PotL hph-4vCy
Texas Utilities Generat'n- JKR' l1 83 . Company Should you have any questions concerning this inspection, we will be pleased to discuss them with you. Sincerely, 80Msinei sisned byr W6 A, CROSsMAM9 G. L. Madsen, Chief Reactor Project Branch 1
Enclosures:
- l. Appendix A - Notice of Violation
- 2. Appendix B - NRC Inspection Report 50-445/83-15 50-446/83-09 cc w/ enclosures:
Texas Utilities Generating Company , ATTH: H. C. Schmidt, Project Manager 2001 Bryan Tower Dallas, Texas 75201 bec to DMB (IE01) bec distrib. by RIV: RPB1 Resident Inspector RPB2 Enforcement Assistant TPB Section Chief (RPS-A) J. Collins, RA T. T. Martin, DDE&TP, RI C. Wisner, PA0 D. Hunnicutt M. Rothschild, ELD TEXAS STATE DEPT. OF HEALTH MIS SYSTEM RIV File Juanita Ellis David Preister
4 l l i NOTICE OF VIOLATION Texas Utilities Docket No. 0500446 Commanche Peak 2 License No. CPPR-127 As a result of the inspection conducted on April 25-May 5,1983 and in accord-ance with the NRC Enforcement Policy (10 CFR 2, Appendix C) published in the Federal Register Notice (47 CFR 9987) dated March 9,1982, the following violations were identified. A. 10 CFR 50 Appendix B Criterion V requires that activities affecting quality shall be prescribed by documented instructions and procedures of a type appropriate to the circumstances and shall be accomplished in accord-ance with these instructions and procedures. l Site Procedure Q1-QAP-16.1-2, Rev 4, dated May 20, 1982, paragraph 3.1.1, i requires a Noncomformance Report to be written for documentation of base i metal repairs. I Contrary to the above, on or before July 15, 1982 a base metal repair was
- made adjacent to weld No. FW2RB-025-SW2RI (W8) as described on Ultrasonic -
- Test Report No. 3146 and was not documented on a Noncomformance Report.
B. 10 CFR 50.55a requires that the reactor coolant pressure boundary be constructed in accordance with the ASME III Code for class I systems. I
- The Americian Society of Mechanical Engineers (ASME) Boiler and pressure
!, Vessel Code, Section III, paragraph NB5111, references ASME Section V, ] Article 2, paragraph T-263.2 which requires the density of the radiograph to be essentially uniform. If the density of the radiograph varies by more l than minus 15% or plus 30% through the body of the penetrameter the radi-ograph is unacceptable and shall be retaken. Contrary to the above, an NRC review of radiographs during April 25-May 5, . 1983 disclosed that the inspected and accepted class I weld, RC-2RB73
+
FW 17, film area 6-8, had densitys of 2.31, 2.43, and 2.05. The density through the body of the penetrameter was 2.87, thus exceeding the minus
- 15% and plus 30% requirements.
These are Severity Level V Violations (Supplement II). Pursuant to the provisions of 10 CFR 2.201, Texas Utilities is hereby required to submit to this office within 30 days of the date of this Notice, a written statement or explanation in reply including (1) the corrective steps which ! have been taken and the results achieved, (2) corrective steps which will i be taken to avoid further violations and (3) the date when full compliance i will be achieved. When good cause is shown consideration will be given to ! extending this response time. l W i
.~ _ y ._._--._..m, , , - _ - - . - . _ _ _ . _ _ , _ _ . ._ _.- __
_ _ _ . . _ . . ,___..____m._. ~ ._ _ _ ,__ - _.,._._._._ ,__ ___._ _ - ____. _ _-. _-,- - -_, -
l U. S. NUCLEAR REGULATORY COMMISSION REGION I 50-445/83-15 Report No. 50-446/83-09 50-446 Docket No. 50-445 CPPR-126 License No. CPPR-127 Priority -- Category C Licensee: Texas Utilities Generatino 2001 Bryan Tower Dallas Texas 75201 Facility Name: Commanche Peak Units 1 and 2 Inspection At: Glen Rose, Texas Inspection Conducted: April 18 - May 6, 1983 Inspectors: \ A h / Harry W. (eYc'h, Reactor Engineer i date A / b l
' Kfcharc H.' Harris, NDE Technician / ;Hite 4 hC/
/
~
afate h Ran . Campbe/1,NDETecnnician Approved by: r au 4 ///[27 gJ.P.Ourr, Chief,Materialsanc Processes Section
/ ddte Inspection Summary: Insoection on Aoril 18-May 6, 1983 (Recort No. 50-445/83-15, 50-446/83-09)
Areas Insoected: A routine, announced NRC independent measurements inspection of construction. The purpose of this inspection was to verify the adequacy of 2he licensee's OA/QC and NDE program. NRC Mobile NDE Van and three regional h .
2 based personnel assisted by two subcontracted NDE personnel were utilized during this inspection. The inspection involved 600 onsite hours and 120 offsite hours. > Results: Two violations were identified, failure to issue proper weld repair documentation (50-446/83-09-03), and failure- to meet code required radiographic density (50-446/83-09-02). The following unresolved items were identified. Docket No. 50-445 1 83-15-01 Preservice ultrasonic recor'ds 83-15-02 PSI procedures 83-15-03 NDE Level III certification 83-14-04 Vendor radiographic film problems Docket No. 50-446 83-09-01 NDE Level III Certification '
. 83-09-04 Vendor radiographic film problems 42y a 2
ka-
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$ m 0
4 m-F f
i, Details 1.0 persons Contacted Texas Utilities Generating Comoany
*J. T. Merritt, S/V Mgr.
*R. G. Tolson, QA. Supv.
Brown and Root "E. P. Opilski, NDE Level III
*G. R. Purdy, QA. Mgr.
J. McCurtain, RSO U.S. NRC
*W. Kerch, NDE Engr.
*R. H. Harris, NDE Technician
*R. M. Camobell, NDE Technician
*R. G. Taylor, Resident NRC
- Denotes attendance at Exit Meeting 5/5/83 .
2.0 Independent Measurements - NRC Nondestructive Examination and Quality Records Review of Safety Related Systems During the period of April 18 through April 22, 1983 quality records received from Commanche Peak Nuclear Power Plant #2 were reviewed in the
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regional office for completeness and compliance to the licensee's FSAR commitment to applicable codes, standards and specifications. Subsequently, an on-site independent verification inspection was conducted l during the weeks of April 25 through May 5, 1983 using the NRC Mobile Nondestructive Examination (NDE) laboratory. This inspection was conducted by regional based personnel in conjunction with NRC sub-contract personnel. The purpose of this examination was to verify the adequacy of the licensee's welding quality control program. This was accomplished by duplicating those examinations required of the licensee's by the regulations and l evaluating the results. In addition to the required examinations, several I additional confirmatory examinations designed to verify conformance with material specifications were performed and compared to quality assurance reco rds . An NRC inspector made a random selection of welds. These were intended to provide a representative sample of piping systems, components, pipe size, materials, shop and field welds to AWS and ASME Class 1, 2, and 3 Codes. i The items selected were previously accepted by the licensee based on l vendor shop or onsite NDE records. I l
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t 2 2.1 Material Traceability Twenty-two document packages were reviewed for the following: Material Certification, including weld wire NDE results Fabrication record - shop and field Drawings (Isometric) Physical properties Quality Procedures Results: All areas examined were acceptable per applicable criteria. 2.2 Nondestructive Examination Examinations were performed using NRC procedures with addenda written specifically for compliance to the Licensee's PSAR commitment to ASME B&PV Code, for onsite fabrication. The intent was to duplicate to the extent practicable the techniques and methods of the original examinations. The following examinations were performed: . Radiograohic Examination - Twenty-five welds were examined by radiography using an Iridium 192 source per NRC Independent Measurements Procedure NDE-5, Rev. O, addenda CMP-1.5-1. Welds examined were ASME Class 1, 2, and 3 carbon and stainless steel.
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Results: All areas examined were found acceptable per applicable pro-cedure and acceptance crtieria. Magnetic particle Examination - Sixtee'n safety related pipe weldments and structural supports were examined per NRC procedure NDE-6, Rev. O and addendum CMP-1-6-1. Samples included ASME welds and AWS Code welds. Results: - All areas examined were found acceptable per applicable , procedures and acceptance criteria. Liouid penetrant Examination Twenty-three safety related pipe weldments were examined per NRC procedure NDE-9, Rev. O, and addendum CMP-1-9-1. Samples examined included ASME Class 1, 2, and 3 welds. Results: All areas inspected were acceptable. Visual Examination - Forty-six weldments and adjacent base material were visually inspected for weld reinforcement, overall workmanship and surface condition per NRC procedure NDE 14, Rev. O. Results: All areas inspected were acceptable. Ultrasonic Examination - Forty-four Hilti anchor bolts were inspected ultrasonically, for length only per NRC procedure NDE 9, Rev. O.
^ 3 Results: All bolts examined were found acceptable per applicable criteria. l Thickness Measurement - Fourteen weldments, and adjacent pipe material were examined per NRC procedure NDE-11, Rev. O using a NORTEC NOT thickness gauge. Minimum wall thickness was determined by using ASTM standard pipe sizes and nominal thickness chart. Results: All areas examined were within tolerance requirements. Ferrite Measurements - Six pipe welds were checked for delta ferrite content using a Type II Ferrite Indicator (Severn Gauge). Results: All Measurements were within acceptable limits. Hardness Measurements - Three welds were checked for hardness (base material adjacent to welds) using the Equo-tip hardness tester per NRC procedure NDE-12, Rev. O. Hardness numbers were converted to Brinnell values and the approximate tensile strengths were determined by use of conversation tables. Results: All areas examined were within acceptable limits. , r Alloy Analyzer - Six pipe welds and adjacent base metals were examined using a-Texas Nuclear Alloy Analyzer. A qualitative chemical analysis was made on four stainless steel 304 type and two stainless steel 316 type material.
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Results: Areas examined were within 2% of chemical analysis indicated on corresponding certified mill test reports. Attachment - Attachment #1 is a tabulation of the specific areas examined and results of tests.
- 3.0 Verification of Nondestructive Examination Film Intercerters l The inspector reviewed six film interpreter's qualification and certifica-tion records. The records met SNT-TC-1A and the American Society of mechanical Engineers (ASME) code requirements. However, the licensee had committed to the site NDE Level III certification by examination. One of the site NDE level III personnel had not been certified by examination.
The individual's record indicated he had once successfully completed the required examination. This item is unresolved pending recertification or removal of the existing certification. 446/83-09-01. 4.0 Review of Licensee Radiographs The inspector reinterpreted: licensee radiographs to verify the adequacy of the radiographic program at this facility. I i L -
l l 4 I Thirty-nine welds from Unit Number 2 and nine welds from Unit Number 1 were radiographically reinterpreted. These welds were accepted by the : licensee. The welds selected for reinterpretuion were field welds and ! shop welds. Unit 2 . Weld RC-2RB73 FW17, Film area 6-8, had a density problem in that the penetrameter density was 2.87 and the weld had densities of 2.31, 2.43 and 2.05. The ASME Code requires film densities to range between -15% and
+30% of the density of the penetrameter, in this case 2.44 to 3.73. The failure to mai.'tain radiographic densities in accordance with ASME code requirements is a violation (446/83-09-02).
Unit 2 Ultrasonic test report A3146 describes an under wall condition for weld FW 2R8-025 SW2RI (W8) in the base metal 2 1/2" x 2 3/8" area. Weld 8 had been cut out from the system and replaced with a new weld W8A. The weld data card was voided out on 7-15-82. The back side of this weld data card contained a documented base metal repair which was also voided out. No Nonconformance Report (NCR) was issued for this base metal repair. Site . procedure Q1-QAP-16.1-2 Rev. 4, dated May 20, 1982 paragraph 3.1.1, requires a NCR to be issued for base metal repairs. The failure to properly document repair welds is a violation of 10 CFR 50 Appendix B, Criterion V (446/83-09-03). The quality of workmanship of the weld is not in question. 5.0 Review of Preservice Ultrasonic Examination The inspector reviewed the ultrasonic preservice inspection (PSI) records for compliance with 10 CFR 50.55a and'ASME XI Code requirements. During the review of PSI data for the reactor coolant piping welds, the notation,
. " volume not examinable was 60% -2, 5, 7, and 8," was found on data reports.
The licensee's staff was unable to explain the meaning of the notation and subsequently contacted the PSI subcontractor for clarification. The notation means that 60% of the bottom 1/3 of the weld volume, 360 around the pipe weld, in the four ultrasonic directions (2, 5, 7, and 8), were not inspectable. The inability of the licensee's staff to understand the ultrasonic test reports and the failure to adequately report the extent of examination implies an inherent weakness in the PSI program. Further, the inspector noted that the PSI-NDE procedures did not have provisions for quality assurance review and acceptance. Lastly, the licensee could not provide evidence that the PSI subcontractor's Level III examiner is qualified and certified. The foregoing items are considered unresolved pending completion of licensee actions and review by the NRC (445/83-15-01).
5 O 6.0 Vendor Radiograoh Review ' Based on previous industry problems related to valve radiographs, the inspector selected 25 vendor radiographs for review. The review was performed to verify compliance with ASME III and V Code requirements. The following Borg Warner valve radiographs were reviewed. Valve Serial No. Finding
#14116 Film area 2-3, 4-5 has density problem.
Penetrameter 3.19, center of weld density 3.85.
#25-425(weld 13) . Radiograph report indicates some film areas were accepted on 4/7/81; however, those film areas had a R2 marked thru and were dated 4/19/81 indicating they were not the film for the reports of 4/7/81.
Film area 3 does not have a lead identifying number 4, it has a scribed 4 on the radiograph.
#27934 Penetrameter in weld area of interest for film reviews 1-2, 3-4, 5. .
#44107 Density problem in film area 4-5. Penetrameter density 2.93, area in weld 2.14 density.
#73009 Penetrameter in area of interest for film view 7-8, 9-10
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The valve radiograph problems were previously identified by the NRC at another facility and are currently under investigation by the Vendor Inspection Branch.
- The above items are unresolved pending completion of the licensee's corrective actions and the NRC review (445/83-15-02 and 446/83-09-04).
7.0 Exit Interview An exit interview was held on May 5, 1983 with members of the licensee's staff. The inspector summarized the purpose, scope of the inspection, and the findings, i
INDEPENDENT MEASUREMENT PROG W Page 1 of 3 Atttchment 1 COMANCllE PEAK UNIT 2 (TEXAS) , WELD MlMBER CLASS SIZE DATA THICK H.T. R.T. U.T. P.T. IIARDNESS VISUAL REMARKS Line/ ISO j RC-2-520-001 FW-3 1 31" Accept N/A N/A Accept N/A Accept N/A Accept FW-4 1 31" Accept N/A N/A Accept N/A Accept N/A Accept l fn Range 3.5 to 7.5 FW-5 1 31" Accept N/A N/A Accept N/A Accept Accept Accept RC-2-RB-021-1 Fn Range 3.5 to 5.0 W-F 1 12" Accept Accept N/A Accept N/A Accept Accept Accept Alloy Test - Accept
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Fn Range 3.5 to 7.5 FW-4 1 12" Accept Accept N/A N/A N/A Accept Accept Accept AlloyAnalized-Acceptf I-2 1 12" Accept N/A N/A Accept N/A Accept N/A Accept b RC-2-RB-072 l W-15 1 6" N/A N/A N/A N/A N/A Accept N/A Accept W-16 1 6" N/A N/A N/A N/A N/A Accept N/A Accept ! k W-17 1 6" Accept Accept N/A Accept N/A Accept N/A Accept j W-18 1 6" Accept Accept N/A Accept N/A Accept N/A Accept i W-19A 1 6" Accept N/A N/A Accept N/A Accept N/A Accept Ril-2-RB-003 FN Check 3.5 to 7.5 FW-1 1 12" Accept N/A N/A N/A N/A N/A N/A Accept Alloy Analized-Accept
- Ril-2-SB-026 l
W2-1 2 12" Accept N/A N/A Accept N/A Accept N/A Accept ; FW-2 2 12" Accept N/A N/A Accept N/A Accept N/A Accept I
P:ge 2 of 3 Attcchment 1 INDEPENDENT MEASUREMENT PROGRAM Comanche peak Unit 2 WELD NUMBER CLASS SIZE DATA TillCK M.T. R.T. U.T. P.T. IIARDNESS VISUAL REMARKS - Line/ ISO S1-2-58-045 W-12A 2 4" Accept Accept N/A Accept N/A Accept N/A Accept FW-17 2 4" Accept N/A N/A Accept N/A Accept N/A Accept SI-2-RB-060 _ Fn-Check 3.5 to 7.5
- W-22 1 6" Accept N/A N/A Accept N/A Accept N/A Accept i
j 6" fn-Check 3.5 to 7.5 1 FW-21 1 Accept Accept N/A Accept N/A Accept N/A Accept j SI-2-RB-070 Alloy Analized - Accept : j W-B 1 10" Accept Accept N/A Accept N/A Accept N/A Accept 7 l CC-2-AB-001 5
, FW-12 3 24" Accept Accept Accept N/A N/A N/A N/A Accept i W-A 3 24" Accept N/A Accept N/A N/A N/A N/A Accept ,1 B
CS-2-AB-080A ' Alloy Analized-Acc pt FW-2-1 2 3" Accept N/A N/A N/A N/A N/A N/A Accept W-2 2 3" Accept Accept N/A Accept N/A Accept N/A Accept W-3 2 3" Accept Accept N/A Accept N/A Accept N/A Accept Sphere weld Alloy F-3 2 10" Accept Accept N/A Accept N/A Accept N/A Accept Analized - Accepted CS-2-RB-027 fn Check - Accept FW-3 2 3" Accept Accept N/A N/A N/A Accept N/A Accept CT-2-RB-081 W-8 2 3" Accept N/A N/A N/A N/A Accept N/A Accept i CT-2-RB-082 FW-1 2 3" Accept N/A N/A Accept N/A N/A N/A Accept ;
. - - a
k , P:ge 3 of 3 Attcchme t 1 INDEPENDENT MEASUREMENT PROGRAM Comanche Peak Unit 2 (Texss) . WELD NUMBER CLASS SIZE DATA TillCK M.T. R.T. U.T. P.T. IIARDNESS VISUAL REMARKS Line/ ISO FW-2-RB-003 W-2 R 6" Accept N/A N/A Accept N/A N/A N/A Accept FW-1 2 6" Accept N/A N/A Accept N/A N/A N/A Accept FW-2-RB-025 8A 2 6" Accept N/A N/A Accept N/A N/A~ N/A Accept 10A 2 6" Accept N/A N/A Accept N/A N/A N/A Accept MS-2-RB-021 i FW-1 2 32" Accept Accept Accept Accept N/A N/A N/A Accept MS-2-RB-024 l W-A 2 32" Accept Accept Accept Accept N/A N/A N/A Accept g l Qty (11) UT examloation of liliti Various Suppo t -- Various N/A N/A N/A N/A Accept N/A N/A Accept bolts for length Aux Plates R1dn/linit ?- I 44 Enchor Bolts . Qty (12) Unit 2/ Aux. Bldg , Support Plate -- Various N/A N/A Accept N/A N/A N/A N/A Accept Elev 813 Room 204 Welds Room 195 i I l l l
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MEMORANDUM FOR: James E. Gagliardo, Director Division of Resident, Reactor Project and Engineering Programs, RIV FROM: Thomas T. Martin, Director Division of Engineering and Technical Programs, RI
SUBJECT:
MOBILE NDE VAN INSPECTION REPORT Transmitted herewith is the inspection report resulting from our inspection activities with the NRC Mobile Nondestructive Examination Van at Comanche Peak Unit I and 2. We hope that this independent measurement inspection activity and documentation fulfills your needs and offer our services to you in the future. We solicit your comments and recommendations regarding improvement in the NDE Van Program to better serve NRC needs. f.homasT. Martin, Director (j Division of Engineering and Technical Programs
Enclosure:
as stated cc: (w/o encis) R. Lewis, R-II J. Olshinski, R-II R. Spesserd, R-III C. Norelius, R-III J. Crews, R-V
.....u.. espe M.J NRC:1 Fonn 6 R::v. Oct 80 (SI'de 1) },
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. PF INSPECTION COVER SHEET gRegion I Work Form)
From: e s-/ 5" ymmv w i<r,te + (Reporting Inspector) Report No. 83-o 9 To: JPOMR (Reporting Inspector's Supervisor) ! Subj: INSPECTION OF tentk6nwea e v,=_m 'Jdud%z ONhence*t .c3 rArv 6 ntaves (Facili ty) (Da'tes )
/ / List of outstanding items up to date, reviewed and proper items selected.
A </ Inspection plan completed (attached or suninarized below). Inspection Items: Jin,A..h -_s..,.~/~/a~ f'sitsi-) ens l, n A% Eu . trf'/M k vi> bA iwAb > > > 11 ,, 3 ,i A/nn*}ti 4 l Jt N u k A L ]A b / nrA $l u L ,. css,/#A meJ> tux /Yi> > /JYn Ari _n n n $4 / V Aw w/>l5. kl0k Aee d s , hk.v/n Nh cw/ b
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NAMES OF ACCOMPANYING PERSONNEL: RESIDENT INSPECTOR NOTIFIED: Project Section Chief ACKNOWLEDGED: Rie n n e n u. un e, ,k Pmject Inspector ACKNOWLEDGED:
,t n w n v rn en me no m Accompanying Inspector's Supervisor (if applicable)
SUBMITTED: Hanov w e n.w APPROVED: 2,24/ Reporting Inspector eporting Inspector's gSupervisor File: lirain'ch Files (Inspector's Branch and Project Branch) ! l Hotel: GRAMMRRy stre INM Phone: (47)S75 .u 9/ FTS: ' Site Contact (Name) R.C. Tnvut Phone: (so)f97-ne / FTS: Region I Form 1 * (Nov1979)
Region I Form 2
, '(Revised February 1977) . POST-INSPECTION COVER SHEET DATE SUBMITTED: 19 FROM: /h/'f $WW RE: 3-69 on $hAPE Mnt 4Mr/195 (Reporting Inspector) (Inspection No.) ()ates of Inspection)
TO: 7. B o EC Comanche. %w. Unit D (Reportln; Inspector's Supervisor) (Facil ty Identification) b<f The facility project inspector has been informed of the inspection results. b<f Inspection Report is completed and ATTACHED.
// Feeder Reports have been completed, reviewd by author's supervisor, and are attached - List:
1. 2. I 3. 4>( Documentation letter completed and attached (a
- standard form with new or modified paragraphs desired).
/P7 List of updated outstanding items completed. For Materials, license folder
! attached (list will be with it).
/Af Statistical Data Sheet completed a'nd ATTACHED.
i . /v7 Inspection Plan as corrected, ATTACHED for Branch Files. A4k Input for Gray Book / Yellow Book submitted to Project Inspector. l l Additional Comments: i
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j f- (Rtporting Inspector) i File: Reporting Inspector's Branch i NOTE: Cross out .and initial sections not applicable. i i
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llLE CD)Y APR 11 1933
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In Reply Refer To: Dockets: 50-445/83-15 / 50-446/83-09 Texas Utilities Generating Company ATTN: R. J. Gary, Executive Vice President & General Manager 2001 Bryan Tower Dallas, Texas 75201 Gentlemen: , This letter is to confirm the NRC Region IV plan to perform an independent verification inspection at the Comanche Peak facility, Units 1 and 2, using the NRC NDE van and contractor technicians under NRC direction. This plan was discussed by Mr. L. D. Gilbert of the NRC Region IV staff, with Mr. R. G. Tolson and others of your staff. We consider this inspection to be an independent verification of construction and the Comanche Peak facility, Units 1 and 2. Construction activities and materials will be sampled through nondestructive examinations as a supplement to our existing ongoing inspection efforts. Similar future nondestructive examinations by NRC are planned on a routine basis at other licensee construction sites. This inspection at the Comanche Peak facility Units 1 and 2, is expected to begin on April 25, and will be completed on May 6, 1983. We have requested documentation packages for each of the 47 welds selected for independent verification to be prepared by your staff. Additional information on the documentation selected for inspection is provided in Attachment A and Attachment B. It is requested that all data packages be in the NRC Region I office by April 11, 1983. If the entire group of packages can not be shipped in time to arrive in the NRC Region I office by April 11, 1983, then it is requested that a partial shipment of data packages be made so that approximately one-half of the data packages will be in the NRC Region I office by April 11 and the remainder by April 14, 1983. NRC will review your documentation packages and update NRC procedures to be consistent with your procedures. All documentation supplied by your staff will be returned at the completion of the inspection. Licensee representatives wil'1 be kept informed of NRC inspection progress and significant findings and at the conclusion of the onsite activities, an exit meeting with you or members of your staff will be conducted May 6, 1983, in accordance with our normal p'rocedures. *f ES/h LDui' bert: ES 8 DMHunnicutt RPB2 RPS-Ah yC5eidle JW terman RPB1 DDRRP&E 3LMadsen JEGagliardo IV
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Texas Utilities Generating 2 Company The evaluation of examination results and preparation of an inspection report will be completed and the results of the inspection will be transmitted to you through NRC Inspection Report 50-445/83-15 and 50-446/83-09. If you should have any further questions regarding this planned inspection, please contact the assigned Senior Resident Inspector, or Mr. L. D. Gilbert (817/860-8156) of the NRC Region IV office, or Mr. Harry Kerch (215/337-1264) of the NRC Region I office. Sincerely,
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J. E. Gagliardo, Director Division of Resident, Reactor Project and Engineering Programs
Enclosures:
Attachments A and 2 bec to DMS (IE01) bec distrib. by RIV: RPB2 Resident Inspector TPB Section Chief RIV File T. Westerman Br. Reading File L. Gilbert RA RPB1 C. Wisner
- TEXAS STATE DEPT. OF HEALTH
O ATTACHMENT A On or about April 20, 1983, the NRC NDE van will arrive at the Comanche Peak Site for NRC NDE use during the period of April 25 through May 6, 1983. We request that the NRC NDE van be positioned as near as practical to the containment vessel exit of Unit I while performing NRC NDE independent inspections. Tht NRC HDE van should be positioned as near as practical to the Unit 2 containment vessel exit while performing NRC NDE independent inspections of the Second unit. The NRC NDE var. requires the following while sited at Comanche Peak:
- 1. Site water with a garden hose connection - this water is for film rinse wpter.
- 2. No sanitary or chemical disposal shall occur from the NRC NDE van without prior concurrence f rom appropriate licensee personnel. At the end of the independent inspection period (May 5 or 6) the NRC needs to dispose of the film developing chemicals prior to moving the NRC NDE van from the Comanche Peak site.
- 3. Two 30 amp 110 volt circuits are required for operation of the NRC NDE van during film developing and related activities.
The van and materials are insured by NRC/ government and you have no liability. The radiation source will be a nominal 100 curie IR-192 source. This source is licensed by NRC, but owned by Wisconsin Test Company. Wisconsin Test Company personnel will perform authorized RT using this source. The names of the four NDE personnel will be supplied to you by April 20, 1983. Clearance on shif ts for these personnel is necessary. Most of their NDE will be performed on yo,ur midnight shift (12-8 or 11-7). The N3E personnel will attempt to modify their procedures to meet your ASME Code and Addenda requirements. We need your cooperation to schedule four to five welds for NDE per shif t f rom April 25 straight through May 6,1983. We will shutdown the radiation source and cease RT of welds on the May 5 shift. We request that you hold a mini-radiation safety training course (session) for the four NDE personnel. This course should familiarize these four personnel with your facility and procedures. The van will contain PT and MT approved materials. They will need two rolls of your chemically approved tape and two approved markers for identifying welds and marking weld areas. We are tentatively scheduling the exit interview for 9:00 a.m. on May 6, 1983.
'O The four NDE personnel will maintain contact with the Senior Resident Inspector and the Region IV office, while they are at your site. , It will be necessary for you to remove the paint or other material that could mask PT or MT NDE on the selected welds. Af ter we have selected the welds for our NDE inspection, we request that you prepare a package containing the following on each weld: Inspection Report Weld history (QC history) Materi.il Certs Weld wire certs Weld drawings, isos, etc. NDE Report on all NDE performed NDE procedures Weld procedures A list of NDE procedures for RT, PT, MT (licensee and contractor) A list of weld procedures from licensee and, if available, from welds facilities . The assembled packages should be forwarded by UPS to: USNRC Region I
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August 5, 1983 TXX-4020 Mr. G. L. Madsen, Chief Reactor Project Branch 1 U.S. Nuclear Regulatory Commission Office of Inspection and Enforcement' 611 Ryan Plaza Drive, Suite 1000 Docket Nos.: 50-445 Arlington, TX 76012 50-446 COMANCHE PEAK STEAM ELECTRIC STATION RESPONSE TO NRC NOTICES OF VIOLATION INSPECTION REPORT NO. 83-15/09 FILE NO.: 10130
Dear Mr. Madsen:
We have reviewed your letter dated July 11, 1983 on the inspection conducted by H.W. Ketch, R.H. Harris and R.M. Campbell from the NRC Region I office of actlytties authorized by NRC Construction Permits CPPR-126 and CPPR-127 for Cemanche Peak. Units 1 and 2. We have re-
. sponded to the findings listed in Appendix A of th.at letter.
To aid in the untierstanding of our response, we have repeated the requirefrent and your firiding followed by our corrective action. We feel the enclosed information to be responsive to the Inspector's findtogs. If you have any questions, please advise. Very truly yours, yaA f r~ m# (@4r) RJ3/rt.pd Enclosures cc: NRC Region !Y - (0 + 1 copy) Director, inspection & Enforcement (15 copies) U.S. Nuclear Regulatory Comission T<CO\ Washington, D.C. 20$55 * -
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TXX-4020 August 5, 1983 Page 2 APPENDIX A NOTICE OF VIOLATION Texas Utilities Docket No. 0500446 Co canche Peak 2 License No. CPPR-127 As a result of the inspection conducted on April 25-May 5,1983 and in accord-ance with the NRC Enforcement Policy (10 CFR 2 Appendix C) published in the Federal Register Notice (47 CFR 9987) dated March 9, 1982, the following violations were identified. A. 10 CFR 50 Appendix B Criterion V requires that activities affecting quality shall be prescribed by documented instructions and procedures of a type appropriate to the circumstances and shall be accomplished in accordance with these instructions and procedures. Site Procedure Ql-QAP-16.1-2, Rev 4. dated May 20, 1982, paragraph 3.1.1, requires a Nonconformance Report to be written for documentation of base metal repairs. Contrary to the above, on or before July 15, 1982 a base metal repair was made adjacent to weld No. FW2RB-025-SW2RI (W8) as described on Ultrasonic Test Report ho. 3146 and was not documented on a Nonconformance Report. ~ COPRECTIVE STEPS WHICH HAVE BEEN TAKEN AND THE RESULTS ACHIEVED NOTE: The aforementioned base metal repair was documented on the back side of the weld data card and subsequently voided. Nonconformance Report (NCR.) No. M-6611 was generated on May 7,1983, docu-menting the base metal repair. All applicable documents have the NCR referenced. CPSES is in full compliance with Site Procedure Ql-QAP-16.1-2, Rev. 4. C0RRECTIVE STEPS, THAT HAVE BEEN OR Will 8E TAKEN TO PRECLUDE RE_ PETITION Only individuals authorized by the Project Welding Engineer may void documentation. No further action is considered necessary in that this appears to be an isolated incident. DATEWHENFU_LLCOMPLIANCEWILLBEACHIEVEQ Corrective and preventive . action was completed on May 26, 1983.
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l TxX-4020 August 5, 1983 Page 3 B. 10 CFR 50.55a requires that the reactor coolant pressure boundary be constructed in accordance with the ASME !!! Code for Class I systems. The American Society of Mechanical Engineers (ASME) Boiler and Pressur'e vessel Code, Section !!!, paragraph hB5111, references ASME Section V, Article 2, paragraph T-263.2 which requires the density of the radiograph to be essentially uniform. If the density of the radiograph varies by more than minus 15% or plus 30% through the body of the penetrameter the radi-l ograph is unacceptable and shall be re.taken. Contrary to the above, an NRC review of radiographs during April 25-May 5, 1983 disclosed that the inspected and accepted class I weld, RC-2RB73 FW 17, film area 6-8, had densities of 2.31, 2.43, and 2.05. The density through the body of the penetrameter was 2.87, thus exceeding the minus 15% and plus 30% requirements. l CORRECTIVE STEPS WHICH HAVE BEEN TAKEN AND THE RESULTS ACHIEVED Nonconformance Report (NCR) No. M-6942 was written on fiay 12, 1983 to re-radiograph weld No. FW-17, with the toe of the weld indicated by lead markers. Results of the re-radiograph were acceptable. NCR No. M-6942 was closed on May 26, 1983. CORRECTIVE STEPS THAT HAVE BEEN TAKEN OR WILL BE TAKEN TO PRECLUDE REPETITION Transition welds and welds which have been ground flush are now being marked at the toe of the weld with lead markers, when necessary, in order to clearly
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define the area of interest. A training class was conducted to indoctrinate QC RT personnel in these requirements. DATE WHEN FULL COMPLIANCE WILL BE ACHIEVED Corrective and preventive action was complete May 26, 1983. _ _ _ - _ _ _ _ _ _ - - - ~ - -}}