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(203) 665-5000 December 11, 1991 Docket No. 50-336 A09945 Re:
Employee Concerns Mr. Charles W. Hehl, Director Division of Reactor Projects U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406
Dear Mr. Hehl:
Millstone Nuclear Power Station, Unit No. 2 RI-91-A-0238 We have completed our review of identified issues concerning activities at Millstone Station. As requested in your transmittal letter of October 16,
- 1991, our responses do not contain any personal privacy, proprietary, or safeguards information. The material contained in these responses may be released to the public and placed in the NRC Public Document Room at your discretion.
The NRC transmittal letter and our responses have received controlled and limited distribution on a "need-to-know" basis during the preparation of these responses. An additional two weeks in which to respond to these issues was granted in a telephone conversation with the Region I Staff on November 25, 1991.
j 1
ISSUE 04:
"On or about August 29, 1991, surveillance SP 2404AW for the RBCCW liquid radiation monitor RM-6038 could not be performed as written due to procedure / data sheet conflicts.
More important, the calculated detector sensitivity and its linearity value were out of tolerance, as were seven other i
monitor channels."
REQUEST:
"Please discuss the validity of the above assertion, and actions taken to correct any deficiencies.
If deficiencies are found to be of a generic
- nature, please notify us of the corrective actions you have taken to prevent recurrence.
Please provide us with an assessment of the safety significance i
of any identified deficiencies."
RESPONSE
This assertion is correct. We were made aware of the concern at the time the calibration was attempted when an Instrumentation and Controls (I&C) techni-9503010233 940009 Y
HusBARD92-162 PDR i
Mr. Charles W. Hehl i
A09945/Page 2 December 11, 1991 cian identified problems in performing the surveillance as it was written.
The procedure was revised to address the concerns of the individual
- and, following consultation with our Radiological Assessment Branch (RAB),a detector response linearity specification was removed from the data sheet.
The calibration was successfully completed using the revised procedure and data sheet.
The calibration at issue uses three sources (designated
'A', 'B' and 'C') in the couyte of a calibration. Additional review following successful comple-tion of the surveillance concluded that the 'B' source used in the calibration was weak enough to have resulted in the abnormal responses noted during the calibration.
The Chemistry Department has since manufactured a new Cesium 137 source at the request of the I&C Department.
A second issue involved sensitivity and linearity abnormalities found during the calibration.
As specified in Revision 2 of SP 2404AW, the I&C Supervisor and an RAB scientist were contacted for review of these calibration abnormal-I ities.
The supervisor and scientist concurred that the sensitivity calcula-tion (on the 'B' test source) was not of concern, and the linearity value, while out of the desired range, did not invalidate the calibration and was acceptable as is.
There are no significant safety or generic concerns associated with these issues in that the techniques and procedures employed resulted in valid calibrations and fully functional equipment.
ISSUE 05:
"There appeared to be no acceptance criteria for Procedure 2404AW, Revision 2, although Revisions 0 and I had acceptance criteria.
The review process did not identify this omission."
REQUEST:
"Please discuss the validity of the above assertion, and actions taken to correct any deficiencies.
If deficiencies are found to be of a generic
- nature, please notify us of the corrective actions you have taken to prevent recurrence.
Please provide us with an assessment of the safety significance of any identified deficiencies."
RESPONSE
Acceptance criteria were present on the data sheet, but the words " Acceptance Criteria" were omitted. The surveillance procedure at issue (SP 2404AW) was revised as part of the procedure upgrade process in the Millstone Unit No. 2 1&C Department.
During the upgrade, the data sheets were retyped and the
' Acceptance Criteria' notation and asterisk contained in Revision I were inadvertently omitted from Revision 2.
The designation of required values and tolerances was present on the revised data sheet, but the acceptance designa-tion indicators were not.
The person responsible for the procedure and an l
independent reviewer did not find the error during the review process.
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I Mr. Charles W. Hehl A09945/Page 3 1
December 11, 1991 i
When we were informed of this concern during performance of the surveillance in August 1991, the work was stopped and the procedure and data sheets were revised.
The surveillance was successfully completed using the revised documents.
q We find no safety sign'ificance to this omission since all of the required
- data, tolerances, and procedural steps were intact, and the data sheet would not have been accepted by the Operations Department had the procedure been I
completed with out-of-specification readings.
There is a potential for generic concern in that the independent and owner reviews of a procedure missed an important characteristic. A review within the I&C Department of all existing radiation monitor Technical Specification-required procedures has found that Acceptance Criteria are present on all associated data sheets.
This review indicates that this specific problem is isolated. As a local action to prevent recurrence, the department manager and supervisors will be conducting training of all department personnel to stress the importance of thorough reviews at every step of the procedura revision process.
As an offshoot of our continuing procedure upgrade process, staffing is under way for a broad-based action to address the generic issue of procedure ade-quacy.
Initiated by the Station Director, the Procedure Upgrade Project will ensure that procedures undergo a thorough review as well as a validation and verification process prior to being submitted for approval by the appropriate operating review committee.
After our review and evaluation of these issues, we find that these issues did not present any indication of a compromise of nuclear safety.
We appreciate the opportunity to respond and explain the basis of our actions.
Please contact my staff if there are further questions on any of these matters.
Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY
- FAJ-J. F.Jp4ka O
Executive Vice President cc:
W. J. Raymond, Senior Resident Inspector, Millstone Unit Nos.1, 2, and 3 E. C. Wenzinger,
- Chief, Project Branch No. 4, Division of Reactor Projects E. M. Kelly, Chief, Reactor Projects Section 4A J. T. Shedlosky, U.S. Nuclear Regulatory Commission, Millstone l
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.e' ifNIl' OSURE ENCLOSURE Issue 238-04 On or about August.29,1991, surveillance SP 2404AW for the RBCCW liquid radiation monitor RM-6038 could not be performed as written due to procedure / data sheet conDicts. More important, the calculated detector sensitivity and its linearity value were out of tolerance, as were seven other monitor channels.
Issue 238-05 There appeared to be no acceptance criteria for Procedure 2404 AW, Revision 2, altho Revisions 0 and I had acceptance criteria. The review process did not identify this omissior,.
Request Please discuss the validity of the above assertions, and actions taken to correct any deficiencies. If deficiencies are found to be of a generic nature, please notify us of the corrective actions you have taken to prevent recurrence. Please provide us with an assessment of the safety significance of any identified deficiencies.
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'D DIS BUTIO '
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~ APR 07 '92 07:53 USNRC HADDAM NECK CT PO4 2
3 ALLEGATION RECEIPT REPORT
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Allegation No.
RI 4-0238 04/ 3*
ee ffpp' (leave blank)
Name:
Address:
Phone:
City / State / Zip:_
Confidentiality:
Was it requested?
Yes No I
Was it initially granted?
Yes No Was it finally granted by the allegation panel Yes No Does a confidentiality agreement need to be sent to alleger?
Yes No
'Has a confidentiality agreement been signed?
Yes No f
Memo documenting why it was granted is attached?
Yes No 1
Alleger's l
Employer: M n7WSW/-
Position /
Title:
, 674w/Sn /N C l
L/77 4/7?dLS fpff awro m Fai. n t ty: /h/ t frons up,7 A Docket No.: Q - ff.6 (Allegation Summary (brief description of concern (s): # 8 8 8 / M v v 5 2.5"
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Employee Receiving Allegation:
(sfirst two initials and last name)
Type of Regulated Activity (a)gReactor (d
Safeguards (b) _ Vendor (e _ Other:
(c) _ Materials (5pecify)
Materials License No. (if applicable):
FunctionalArea(s): 2(a) Operations
_ (e) Emergency Preparedness
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f Oncite Health and Safety
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_ (h) Other:
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(NRC Region I Form 207
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PICORD OF ALLEGATION PANEL DECISIONS SITE:
N s' 3 SM -f PANEL ATTENDEES:
ALLEGATION NO.: 8I-SI M% b Ch a i rrna n -
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DATE: b@N (Panel No.12 3 4h Branch Chief -
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H.gh Hedium Section Chief fAOC) -
1 Sr. Alleantion Coord (SAC) k ratT(5 h
Unkn SAFETY SIGNIFICANCE:
Yes CONCURRENCE TO CLOSEOUT:
CONFIDENTIALITY GRANTED:
Yes (Other) 32 ids $ f M!M (T)
(See Allegation Receipt Report) j IS THEP" A HARASSMENT /DISCRIHINATION ISSUE:
Yes No IF YES, 1) has the individual teen infermed of the DOL process and the need to fi'e a complaint within 30 days Yes No 2) has the individual filed a complaint with DOL Yes No 3) has a letter been sent to the complainant seeking Yes No any safety concerns IS A CHILLING EFFECT LETTER WARRANTED:
Yes No IF YES, HAS IT BEEN SENT Yes No HAS THE LICENSEE RESPONDED TO THE CHILLING EFFECT LE p Yes No
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V 26, 1983 TO:
E. J. Mroczka Station Superintendent. Millstone V, h m FROM:
M. V. Bonaca Systems Manager, eactor Engineerinf ~
SUBJECT:
Emergency Core Cooling System Operability Requirements
REFERENCE:
M. S. Kai meno NE-83-SAB-145 (Rev. 2) to S. E. Scace dated 9/19/83 The NUSCO Safety Analysis Branch Transient Analysis and LOCA Sections have reviewed existing requirements for Emergency Core CoolinC System (ECCS) operability during all modes of plant operation. This review was conducted for the three Millstone units and Connecticut Yankee.
Based on this evaluation, current technical specification requirements for the Millstone units are considered adequate with a few exceptions.
These items are summarized below for each plant and are addressed in detail in the referenced memo (attached). The purpose of this memo is to forward recorsnended changes to NNECO that will resolve the concerns that have been raised. The recocuended changes should have no signifi-cant impact on plant operation. It is requested that NNECO provide a response by December 31, 1983, addressing disposition of these concerns.
For clarification or amplification of the concerns and recommendations, please contact S. E. Scace (X5544).
Millstone 1 The existing technical specifications allow operation with both core spray systems inoperable for up to 7 days. This time period is not consistent with current standard technical wecification action state-ments and should be reduced. Although there is another low pressure ECCS system (LPCI), no time period of at length is currently justifiable with no core spray systems operable. Further, use of the core spray system has been assumed in the post-accident hydrogen control evaluation that was used to justify not installing hydrogen recombiners in Millstone 1.
Therefore. it is recomended that specification 3.5.A.3 be eliminated.
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Millstone 2 Technical Specifications governing ECCS equipment avail-ability are modeled after the Combustion Engineering standard techni-cal specifications (CE STS). As such, there are no requirements to maintain Low Pressure, Safety Injection (LPSI) or Safety Injection i
Tank (SIT) operability below 1750 PSIA in Modes 3-4.
There is a l
requirement to maintain operability of one High Pressure Safety Injec-tion (HPSI) pump during the above plant conditions.
The reference memo points out that ECCS equipment requirements to mitigate a LOCA is dependent upon decay heat, system pressure and break flow rate. For certain LOCA break sizes. HPSI alone will not be sufficient to provide core protection, even at pressures below 1750 PSIA. Consequently, it is prudent to assure availability of low pressure safety injection (both LPSI and SIT) during operating condi-tions below 1750 PSIA.
Since the Millstone 2 LPSI system is utilized for shutdown cooling. it is necessary to make the LPSI system inoperable below 1750 PSIA to align it to the shutdown cooling mode, equalize boron in the piping, and heat the system prior to initiation. Therefore, the LPSI system cannot be maintained fully " operable" in terms of the strict technical specification definition. However, availability of a LPSI Pump and shutdown cooling heat exchanger for post-accident iong ters cooling is considered essential. In addition. SIT's should not be isolated until well below 1750 PSIA. 600 PSIA is reenmended to provide protection but still give margin for isolation to preclude inadvertent discharge into the reactor coolant system. This will provide the necessary ECCS equipment availability in Modes 3 (<1750 PSIA) and 4.
Specifically, additions recomended for ECCS equipment availability are as follows:
1.
Mode 3 (<1750 PSIA). Mode 4 One LPSI pump. one shutdown cooling heat exchanger, and a flow path from the RWST available with the capability of manual I
injection to the RCS.
2.
Mode 3.4 (600 < P < 1750 PSIA)
All SIT's avalTable y,
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E. J. Ikoczka '
- @ %.k Page 3 It is recommended that these changes be taplemented administrative 1y (incorporate into operating procedures) rather than ty a change to the technical specifications at this ties. Since the changes recommended above provide additional equipment availability requirements beyond the CE STS. the NUSCO Safety Aralysis Branch will discuss ECCS equipment availability in Modes 3 and 4 with CE. A recommendation (if any) on possible technical specification changes will follow resolution of this item with CE.
Millstone 3 The Millstone 3 technical specifications will be based on the Westinghouse standard technical specifications. Since the Westinghouse STS have requirements for availability of a RHR Pump and heat exchanger in Modes 3 and 4 (RHR is equivalent to shutdown cooling), and requires operability of SIT's for RCS pressure >1000 PSIA, the concerns discussed above for Millstone 2 are adequately soaressed for Millstone 3.
No changes are therefore reconnended.
SES/MYB/kkv attachment cc:
R. T. Harris w/o S. E. Scace w/o J. A. Blaisdell w/o
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b SAMPLE RECORD OF ALLEGATION PANEL DECISIONS SITE:
5 d-PANEL ATTENDE ALLEGATION NO.: 01 M-A-019d Chairman -
84<.
i DATE:.115MI- (Panel No@2 3 4 5)
Branch Chief-PRIORITY: High bfedijgip IAw Section Chief (AOC) - fell 1.
! SAFETY SIGNIFICANCE: Yes No @
Sr. Allegation Coord (SAC) f5kmehk&-
1 CONCURRENCE OI Reoresenta:ive -
l TO CLOSEOUT: DD @ SC (Other) Sked%k M Sdm CONFIDENTIALITY GRANTED: Yes h b evan (c4
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! IS THERE A HARASSMENT / DISCRIMINATION I
Yes h l
ISSUE:
! IF YES,
- 1) has the individual been informed of the DOL process and the need to file a complaint within 30 days Yes No
- 2) has the individual filed a complaint with DOL Yes No
- 3) has a letter been sent to the complainant seeking Yes No any safety concerns
~
l IS A CHILLING EFFECT LETTER WARRANTED:
Yes No l IF YES, HAS IT BEEN SENT Yes No l HAS THE LICENSEE RESPONDED TO THE CHILLING EFFECT LETTER:
Yes No ACTION:
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B N - NOT BLIC DIS du 4
)i ENCLOSURE
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File No. RI-91-A-0241:
f It was alleged that there were several problems associated with the Safety Injection Tank pressr a switches, PS-313, PS-323, PS-333, PS-343, presently installed at Millstone Unit 2.
i (1)
The pressure switches are the wrong range.
(2)
Millstone Unit 2 does not have the correct vendor technical manual for the pressure switches presently installed.
(3)
A customer assistant for the manufacturer of the pressure switches
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stated that the pressure switches were not desigp for nuclear application.
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i (4)
The tempe e
e ted n the sti endor technical manual is,-30' to +160', which does not appear to be a proper range for equip side containment on the Safety Injection Tank.
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]{(5)
A customer assistant for the manufacturer of the pressure switches stated that the pressure switches would not operate correctly 601 side their proper operating range, which was stated to bE.60 to 225 PSI i
The pressure switches installed in Millstone Unit 2 have a t set i
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[L of 245 PSIG, which is outside this o rating range.
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Please provide your review of the above issues. If the above information id,
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notify us of the corrective acti taken to prevent reoccurrence. Al
/j provide us with an assessment of the safet ificance of any identified deficiencies, /
s including ge'neric considerations.
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' //G ALLEGATI0N M A N A G E.M E N T SY STEM ALLEGATION NUMBER - RI-91=A-0241 RUN DATE: 10/17/91 DOCKET / FACILITY / UNIT: 05000336 / MILLSTONE 2
/2 DOCKET / FACILITY / UNIT:
/
/
DOCKET /FA CILITY / UNIT:
/
/
DOCK ET / FA CIL IT Y / UNIT :
/
/
ACTIVITY TYDES - REACTOR MATERIAL LICENSES -
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9UNCTIONAL ARE A S OPERATIONS DESCRIPTION -
NUMEROUS PROBLEMS EXIST WITH SIT PRESSURE SWI TCH E S: RANGE IS WRONGr INCORRECT TECH MANUALr MANUFACTURER SAYS NOT FOR NUCLEAR APPLICATIONSa WRONG TEMPER ATURE R ATING, VENDOR S AYS CONCERNS
- WON'T CORRECTLY AT SET PRESSURE I
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t SOURCE - LICENSEE EMPLOYEE CONFIDENT = NO r
RECEIVED - 910906 BY - DA DEMPSEY
/ RI I
ACTION OFFICE CONTACT - EM KELLY (FTS)346-5183 SAFETY SIGNIFIC ANCE - NO 80ARD NOTIFICATION - NO STATUS - OPE N SCHED COMPLETION
. 920430 DATE CLOSED -
ALLEGATION SUBSTANTIATED =
ALLEGER NOTIFIED -
OI ACTION
- 01 REPORT NUMBER -
REMARKS - RECEIVED IN RESIDENT OFFICE VI A MEMORANDA.
PANELED 11SEP91.
l i
l SUPPORT OFFICE:
RPS-4A ACTION PENDING:
REFER TO LICENSEE (DR P)
DOCUMENTATION:
ALLEGEP LAST CONTACTED:
11SEP91
REFERENCE:
i KE YWORD:
SIT, PRESSURE SWITCH j
ENTERED SYSTEM - 910919 CLOSED SYSTEM -
RECORD CHANGED - 910919 i
/'
i
s Atom the dash ob' j ar/9L OENE KELLY
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i Docket Number:
50-336 File Number:
RI-91-A-0241 j
Northeut Nuclear ergy Company ATTN: Mr. John F.
ka Executive Vi President - Nuclear P.O. Box 270 Hartford, Connecticut 141-0270
Dear _ Mr. Opeka:
The U.S. Nuclear Regulatory ommission recently received information concerning activities at the Millstone Unit 2. The de ils are enclosed for your review and followup.
We request that the results of your eview and disposition of these matters be submitted to Region I within 30 days of the date receipt of this letter. We request that your response contain no personal privacy, proprie or safeguards information so it can be released to the public and placed in the NRC Public ument Room. If necessary, such information shall be contained in a separate attachmen which will be withheld from public disclosure.
The affidavit required by 10 CFR 2.790(b) ust accompany your respor,se if proprietary information is included. Please refer to file mber RI-91-A-0241 when providing your response.
The enclosure to this letter should be controlled an distribution limited to personnel with a "need to know" until your investigation of the conce has been completed and reviewed by NRC Region I. The enclosuie to this letter is conside Exempt from Public Disclosure in accordance with Title 10, Code of Federal Regulations, art 2.790(a). However, a copy of this letter excluding the enclosure will be placed in the N Public Document room.
]
The response requested by this letter and the accompanying e losure are not subject to the clearance procedures of the Office of Management and Budget required by the Paperwork Reduction Act of 1980, PL 96-511.
Your cooperation in this matter is appreciated. We will gladly discu any questions you l
have concerning this information.
Sincerely,
/
g/
$+bk Charles W. Hehl, Director d
Division of Reactor Projects b
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Northeast Nuclear Energy QNqnkgast Nuclear Energy Company 2
Enclosure:
10 CFR 2.790(a) Information Issues and Requests cc w/o encl:
Public Document Room (PDR)
Local Public Document Room (LPDR)
State of Connecticut bec /w encl:
Allegation File: RI-91-A-0241 E. Conner's files W. Raymond/T. Shediosky Contractor's office files (Meeker)
I concurrences:
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11:28 Secured A D/G No abnormalities observed during run or on instrumented test points.
Auaust 6,_.1121
~
04:18 Start and run B D/G for normal surveillance.
06:48 Secure"B"D/G No abnormalities noted j
17:08 Start and run 'A" D/G 19:46 Secure D/G
. l't No abnormalities noted t
'"# pt. August.14,. 1991 l
3 09:00 started *'Y D/G and run in accordance with troubleshooting plan.
Reference AWO M2 !
07648.
11:21 Secured"A'D/G
~
r No abnormalities observed during nm or en nts I m s z ^ ^ d m '* * " *****
Aucust,*t, instrumented test gano,,.
sFAntas ~A **M, ryean Am **seog. ' '
- WW.
AW August 20. 199Y.' r da b E [ M E r5 YIo f
09:34 Started"A"D/G and run in accordance with troubleshooting plan.
Reference AWO M2 07648.
11:58 Secured'A"D/G No abnormalities observed during run or on instrumented test points.
Anaust 21. 1991 7/p- 09:10 Started "A" D/G. Synchronized, and loaded to 1300KW. Ran diesel through load changes inc. to 2100KW, dec. to 1400). No erratic operatJ(.ons.
I s/h-11,: 28 Secured "A" D/G after a successful run.
Started "A" D/G. Synchronized,d change (inc. to ed and loaded to 9y y/,tf 17:02 1350KW. Ran riiesel through loa 2100KW). After 45 minutes of operating at 2100KW g,Y' the load drifted to 3200KW.
Jtid ers mar. gaea 4rcer.
a imr.gigm caew w _ _- w sset.ea ee-y 18:04
" Ar D/G 10-4 (KW) pegged high at 3500KW. Operator opened output breaker. Engine continued to run.
C i
Y 18:06 Tried to synchronize "A" D/G, and reload. But, speed was erratic which made it difficult.
After Ay (N synch, load jumped to 1500KW, and when the operator V
tried to reduce it the load fell to 600KW./A wide]
goad swing cause the breaker to trip on reverse
].
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Cr f' o
"A", D/G breaker trippsr.mur vara yewar. +J W **** ** J 18:07 a reverse l
rm rany a.v mer ::.
c 18:24 Started' "B" D/G. Synchronized, and loaded to f
1350KW. Ran diesel through load change (inc. to 2100KW).
No erratic operations.
20:44 "B" D/G secured.
22:58 Started "A" D/G. Synchronized and loaded to
,1350KW. Varied load for engine,ering evaluations.
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b M.'Ea'ifo[It HR. 5wice Ering the run
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Increased]illations, load to 1350KW. Held steady load (no 23:00 evers osc only normal oscillations of 25 to 50 KW).
\\
23:08 load to 2100KW. Load drifted up to 2200KW, and the oonrator lowered it to 2100KW.
l 1puras sunw-w m soue vA row #*~s7 23:39 Loadfinc. to 2200EW Oper[ator reduced load back to M+4Mk swin se**r
- As*ce< W 4y,'z %g Load drifted 23:40 y C
back up (by 01:08 it was back to 2200KW).
Aucrust 22. 1991 i
01:09 Reduced load to 1400KW.
01:15 Secured "A" D/G. After breaker open frequency oscillations.were 60.1 to 60.2 HZ.
Adjusted the local speed controls t g ampen_,)h y oge g agig g y,,c deE-g p,
casonM nrae~ ce~
03:15 Started "B" D/G. Synchronized, and loaded to 1400KW. Ran diesel through load change (inc. to 2100KW).
No erratic operations.
03: 45 Secured "B" D/G.
10:02 Started "B" D/G. Synchronized, and loaded to 1300KW. Ran diesel through load change (inc. to 2100KW).
No erratic operations.
11:26 "B" D/G shutdown.
13:45 Started "A" D/G. Synchronized, and loaded to
\\
\\
1
D i
SAMPLE RECORD OF ALLEGATION PANEL DECISIONS SITE:
N/ I E
PANEL ATTENDEES:
(l'l-91-A-02 42 Chairman -
u)/nm 5 ALLEGATIONpO.:
DATE: 6SEF -
Branch Chief-PRIORITY: @(Panel No.@2 3 4 5)
~'
l Medium Low Section Chief (AOC) - J/elv
! SAFETY SIGNIFICANCE: @ No Unkn Sr. Allegation Coord (SAC) CAmet h l CONCURRENCE 01 Reoresentative -
TO CLOSEOUT: DD BC h (Other) &ms bilu.left f-CONFIDENTIALITY GRANTED: Yes h s h % tD Moq (See Allegation Receipt Report) v i IS THERE A HARASSMENT / DISCRIMINATION k
i ISSUE:
Yes i IF YES, i 1) has the individual been informed of the DOL 1
process and the need to file a complaint within 30 days Yes No 1 2) has the individual filed a complaint with DOL Yes No
- 3) has a letter been sent to the complainant seeking Yes No l
any safety concerns
- IS A CHILLING EFFECT LETTER WARRANTED:
Yes k
- IF YES, HAS IT BEEN SENT Yes No l HAS THE LICENSEE RESPONDED TO THE CHILLING EFFECT LETTER
Yes No ACTION:
- 1) 35'bF b CB i! fem 25 rif 4oh t WW f
796 i
v s
v
- 2) _ ME D.
f[M L _OfS A d L ' h.
6M r t dul*f h h h
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- 3) h u F '2 '.
r moerr b2.bmki wk-d 4 o#4 4 oro teche4 4kieuuk & wa.a natus F
4) 5)
NOTES:
A4-1
i ALLEGATION MA0AGEMENT SYSTEM J
RUN DATE: 10/17/91 ALLEGATION NUMBER - RI A-0242 DOCKET / FACILITY / UNIT: 05000336 / mis.LSTOKE 2
/2
/
DOCKET / FACILITY / UNIT:
/
/
DOCKET / FACILITY / UNIT:
/
/
DOC K ET / FA CIL ITY / UNIT :
/
ACTIVITY TVPfc5 - RE ACTOR M AT ERI AL LICENS ES -
OPERATIONS FUNCTIONAL AREAS DESCRIPTION - 1) TEST EQUIPMENT IS BEING USED WHICH ADVERSELY AFFECTS THE OPER ATION OF THE DIESEL GENERATOR, AND COULD D AMAGE EQUIPT.
- 2) TESTS AND MAINTENANCE ARE BEING PERFORME0 BY STATION PER-CONCERNS -
SONNEL WHO LACK SPECTTIC KNOWLEDGE REQUIRED 3
- 3) ON-SITE S AFETY COMMITTEE REVIEW OF A PROCEDURE FOR THE DIESEL WAS SUPERFICIAL SOURCE - CONTRACTOR EMPLOYEE CONFIDENT - NO RECEIVED - 910905 8Y - JT SHEOLOSKY
/ RI (FTS)346-5183 ACTION OFFICE CONT ACT - EM KELLY 3 &F ET Y SI G NI F IC A NC E
- UNKNOWN 80ARD NOTIFICATION - NO STATUS - OPEN SCHED COMPLETION - 920430 DATE CLOSEC "
ALLEGATION SUBSTANTIATED -
ALLEGER NOTIFIED -
OI ACTION -
OI REPORT NUMBER -
REMARKS - RECEIVED IN RESIDENT OFFICE FROM VENDOR REP.
PANEL MET 6SEP91.
SUPPORT OFFICE:
RPS*4A ACTION PENDING:
INSPECT PROCEDURE REVIEW (DRP) f D3COMENTATION:
ALLEGER LAST CONT ACTED:
SSEP91
REFERENCE:
AEYWORD:
EDGr DIESEL, PROCECURE ENTERE0 SYSTEM - 910919 CLOSED SYSYEM -
RECORD CHANGED = 910919
SAMPLE RECORD OF ALLEGATION PANEL DECISIONS SITE:
A/5 4
PANEL A'ITENDEES:
ALLEGATION pO.: EI-9f-#-o243 Chairman -
Lw.s IM (Panel No. 92 3 4 5)
Bmnch Chief-l DATE:
PRIORITY: High M
I.ow Section Chief (AOC) - feAv.
I SAFETY SIGNIFICANCE: Yes No @
Sr. Allegation Coord (SAC) fdmedb 1 CONCURRENCE OI Reoresentative -
I TO CLOSEOUT: DD @ SC (Other) Eh Cnue U f
CONFQENTIALITY GRANTED: Yes (See Allegation Receipt Report) l IS THERE A HARASSMENT / DISCRIMINATION ISSUE:
Yes @
! IF YES, I I) has the individual been informed of the DOL l
process and the need to file a complaint within 30 days Yes No 1 2) has the individual filed a complaint I
with DOL Yes No 1 3) has a letter been sent to the complainant seeking Yes No any safety concerns i IS A CHILLING EFFECT LETTER WARRANTED.
Yes Qo l IF YES, HAS IT BEEN SENT Yes No I HAS THE LICENSEE RESPONDED TO THE CHILLING EFFECT LETTER:
Yes No ACTION:
bm ou e.v--
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4) 5)
NOTES:
i f
A4-I t
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ENCLOSURE Issue 91-243:
During the performance of SP-2404AV, it was noted that copies of form OP 2383C-1, " Alarm Setpoint Control," were not forwarded to the Engineerir.g Department for review on two occasions as required by procedure OP 2383C, " Radiation Monitor Setpoint Control". Specifically, the alarm setpoint changes for RM 6038, the Reactor Building Closed Cooling Water Monitor, which occurred on May 11,1991 and July 8,1991 were not forwarded to Engineering Department as required. In fact, the last change made to the setpoint for RM 6038 which was reviewed occurred on February 2, 1991.
Request:
r Please provide your review of the above assertion. If the above conditions are valid, notify us of the corrective actions you have taken to prevent recurrence. Also, provide us with an assessment of the safety significance of any identified deficiencies, including any potentially generic considerations.
pDISTRIBUT40N - NOT "9RtimLICfHQURE f~
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l A NOTE ON EINEMETRICS PART NUMBERS l
FOR PRIllTED WIRING BOARDS 1.
A complete printed wiring (circAit)' board is defined by an assembly drawing. The part number is the same as the essembly drawing number. Normally, the part number and the assembly drawing number and with the digit 0 or the digit 5, 2;2 Tha,pqyL Aumber end. drawing, number;of..the*.etchef, machined,coard,dsitKou%Eompc~pYrtL4.17,irWhore411yatup Algite greater than the assembly.part_and,dra @
symbgrs.
Not~eY."The"part number etched *on' the. board;isiof4 thy pachined board.(not.cf the. assembled Acagdy.
3.
The drawings below show a typical' example of a complete assembly (part no. 100920) and a machined board (part no. 300922).
tv pe. mm m.,_ __!rs-....
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- HILLSTONE UNIT TWO - REWORK REPORTIIEC1 LIST OF LOCAL 1DS & EQUIPMENT DESCRIPTION UNS=U WOS=F TOTAL OF CH AND Of IS =i4 FROM 05-01-1989 TO 09-15-1990 AS OF 09/19/90 TYPE GRAND 10TAL LOCALID CH OT EQUIPNENT DESCRIPTION H2 ANALYZER "A" CONTROL NODULE E SENSOR 4
2 SPENT FUEL POOL AREA R/N AREAS BISTABLES H2BA303 0
4 BORON RECOVERY HEAT TRACING RECORDER N2BRR-6 4
0 CORE PROTECTION CALCULATOR 2, RPS-B N2CPC-B-2 1
3 CORE PROTECTION CALCULATOR 1, RPS-C M2CPC-C 1 4
0 SERVICC WATER TO HX 169A FLOW TMDICATOR M2FI-4668 3
1 FIRE PROTECTION OELUGE/ WET SPRINKLER SYSTEM - MISC CONPONENTS N2 FIR 4
0 RADWASTE VENTILATION RADIATION MONITOR SAMPLE FLOW IND SWITCH N2FIS-8997 4
0 CHARGING HEADER TO REGEN llEAT EXCH X21 FLOW TRANSMITTER M2FT-Z12 3
1 AERATED WASTE TO CIRC WATER DISCHARGE FLOW H2FT-9118 1
3 CONUENSER PIT "B" SUHP PUNP 39A LEVEL CONTROL SWITCH (EAST)
0 N2LI-226 3
1 VOL CONT TANK T5 LEVEL INDICATOR TERRY TURBINE STEAN SUPPLY WATER DETECTOR M2LS-4590 4
0 2ND STAGE REHEATER DRAIN TANK 1A DUNP TO COND LEVEL VALVE N2LV-4126 3
1 SEISHIC HONITOR FOR CIHF UPPER WALL +75' ELEVATION M2HE-9448 3'
1 SEISMIC MONITOR FOR INTAKE STRUCTURE & 34*6" ELEV M2NE-9450 2
2 SEISHIC HONITOR FOR FREE FIELD 1 14*6" M2NE-9451 3
1 FIRE PRO 1ECTION PUNP P82 DISCHARGE PRESSURE INDICATOR M2PI-7302 3
1 LINEAR POWER RANGE DRAWER RPS-C M2PR-SAF-C 1
3 RHCCW PUNP P11A SUC1 ION PRESSURE LO SWITCH N2PS-6119A 1
3 SIEAM GEN #2 DUMP TO AIMOS VALVE POSITIONER H2PV-4224 4
0 PZR PRESS V TO I CONVERTER M2PY-102D3 3
1 PRESSURIZER SPRAY VALVES POSITIONER H2RC-100F 3
1 SIACK GAS EFFLUENT RAD MONITOR CONTROL ROOH PANEL H2RIC-8168 4
0 STEAM CENERATOR BLOWDOWN COUNT RATE MODULE M2RIT-4262 0
4 CTHT ATHOS PARTICULATE RADIATION INDICATING XHTR CRM HERIT-8125A 1
3 CTNT AIR GASEOUS RADIATION CRH M2RIT-8262B 1
3 CONTROL ROOM VENTILATION CADIATION NONITOR PI N2RIT-9799A 2
2 NAIN STEAM LINE RAD NONITOR LOOP H2hM-4299C 4
0 CTNT ATHOS GASEOUS RAD ttONITOR LOOP
%~~-
3 RADWASTE VENTILATION EXHAUST RAD MON LOOP
"' ~~
0 RADWASTE VENTILATION RADIATION HONITOR LOOP N2RN-8997 4
0 RADWASTE VENTILATION RADIATION MONITOR LOOP H2RM-8998 3
1 WASTE GAS TO STACK RAD NONITOR LOOP H2RN-9095 3
1 s
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l PAGE2 u NILLSTONE UNIT TWO - REWORK REPORT (IEC)
LIST OF LOCAL _ IDS & EQUIPMENT DESCRIPTION f
UNS=U WOS=F TOTAL OF CH AND OT IS =>4
[
FRON 05-01-1989 TO 09-15-1990
(
AS OF 09/19/90 l
TYPE l ; RAND LOCALID CN OT EQUIPMENT DESCRIPTION roTAL N2RPS-A 3
1 RPS PANEL A LOOP (RCOSA) l CALIBRATION AND INDICATION PANEL,RPS-A j
N2dPSCIP-A 4
0 REACTOR NEGULA1ING SYSTEM CilANNEL Y POWER INDICATON l
4 ANNONIUM llYDROXIDE PUNP STROKE POSITIONER PUNP P-69A l
1
(
NOT-111Y 3
1 REACTOR COOLANT LOOP 1A COLD LEG TEMP LOOP REACTOR COOLANT LOOP ID COLD LEC TEMP RTD l
3 l
3 SG 1 SECONDARY SIDE TEMPERATURE (HANUWAY RTDI REACTOR COOLANT LOOP 2 NOT LEG TEMP INDICATOR l
2 LETDOWN llEAT EXCif X22 TEMP INDICATING CONTROLLER l
N2 TIC-223 4
0 CONDENSATE IIDR. CONDUCTIVITY & NYDRAZINE HDR. CONCEN RECORDER l
0 CINT PRESSURE E TEMP RECORDER HOUR-9862 4
0 ACOUSTIC VALVE MONITOR ALANN HODULE FOR 2-RC-201 l
N2VN-201 1
3 ACOUSTIC VALVE MONITOR ACCELEROMETER 42-RC-201) l N2ZS-201 0
4 COND UfMIN 2J OUILET CONDUCTIVITY ALARM SWITCil N22CNDCIS159 3
1 l ".
l M2AE-8154 2
3 112 ANALYZLR "B" CONTROL NODULE AND SENSOR
(
H2AR-203 3
2 BORONONFTER RECORDER NAIN TURHINE ELECTROllVDRAULIC CONTROL SYSTEN i
N2ElfC 3
2
(
3 STACK GAS SAMPLE FLOW SWITCH FEEDWATER llEATER 6A NORNAL LEVEL CONTKOL l
0 l
0 BORIC ACID TANK T8B LEVEL INDICATOR -- - fu U S T l
5 NE T TOWER INSTRUNENTATION (NAINTAINED BY NUSCO) l N2PR-SAF-A 0
5 LINEAR POWER RANGE DRAWER RPS-A-l H2 REED-P/S-A 2
3 REED SWI1Cil POWER SUPPLY STACK GAS PARTICULATE E GASEOUS RAD RECORDER l
3 l
NOTU-D-1 3
2 CllANNEL-B TRIP DISTABLE: IIIGil POWER H2WQM-D 4
1 WATER QUALITY NON[ TOR (DISCHARGEILOOP (T6691 2 A66931 N2WW*l-Q 5
0 WATER QUALITY NONITOR (QUARRY CUTI LOOP (T6695 & A6694)
N22CLSPNLO7RR S
0 CPF RADIATION HONITOR RECORDER LINE DILUTION WATER FLOW RECORDER H22CNDFR247 5
0 AUTOHATIC TEST INSERTER (ATI NODULE) i en N2ATI 6
0 AUXILIARY LOGIC DRAWER RPS-A RAllWASTE VENTILATION RADIATIDH NONITOR FLOW IND. SWITCH - p N2AUXLOGIC-A 0
6 N2F15-8998 6
0 AERATED WASTE TO CIRC WATER DISCHARGE FLOW H2FR-9118 1
5 CTNT ATHOS GASEOUS RADIATION INDICATING XHTR CRM i
I M2RIT-8123D 0
6
L
/
4 PAGE3
- MILLSTONE UNIT TWO - REWORK REPORT (IEC)
LIST OF LOCALIDS 1 EQUIPMENT DESCRIPTION UNS=U WOS:F TOTAL OF CH AND OT IS =>4 FROM 05-01-1989 TO 09-15-1990 AS OF 09/19/90 TYPE FQUIPMENT DESCRIPTION G2AND TOTAL LOCALID CM OT SPENT FUEL POOL RADIATION MONITOR CRM (EAST)
6 CTNT-HI_ RANGE RADIATION CRM IEAST)
3 AERATED LIQUID RADWASTE PROCESS RADIATION MONITOR LOOP 4
2 REACTOR REGULATING SYSTEM CHANNEL X POWER INDICATON
/ M2RM-9116 f M2RRS-IND-X 1
5 WIDE RANGE DRAWER RPS-A CARBOM MONOMIDE MONITOR ALARM'(PORTABLE IN-LINE MONITOR)
8 7
M2 COMA-5
- 5 2
SJAE DISCHARGE TO STACK NAD MON FLOW ING SWITCH M2FIS-SO99 4
3 AERATED WASTE FLOW TO CIRC WATER DISCHARGE M2FQI-9118 2
5 FEEDWATER HEATER DRAINS 1 VENTS STACK GAS EFFLUENI RAD MONITOR LOCAL CONTROL PANEL M2HOS 2
5 SERVICE WATER PUMP PSC FILIER PRESSURE DIFF SWITCH 7
1 M2 PDC-6488 6
1 S.G BLOWDOWN PROCESS RAD MONITOR LOOP ( A M M2RM-4262 1
6 RECORDER FOR RM-202 & RM-2e2A f MEb WATER QUALITY MONITOR (INTAKEl LOOP (T6698 8 A6692)
M2NR-292 7
0 M2WQM-I 5
2 WIDE RANGE DRAWER RPS-B M2WR-LOG-B 6
1 WIDE RANGE DRAWER RPS-C'
- ACM M2WR-LOG-C 6
1 COND DEMINS A-G EFFLUENT FLOW RECORDER RADWASTE VENTILATION EXHAUST RAD MON FLOW ING SW fq M22CNDFR310 7
0 l
8 M2FIS-8434 7
1 SPENT FUEL POOL RADIATION MONITOR LOOP (EAST) l M2RM-8156 4
4 WASTE MEUT SUMP RAD MONITOR LOOP M22CNDRM245 5
3 CIMT AIR PARTICULATE RADIATION CRM SPENT FUEL POOL RADIATION MONITOR LOOP (WEST) -
8 9
l 9
M2RIT-8262A-CTNT A1MOS PARTICULATE 1 GASEOUS RAD RECORDER M2RM-8157 5
4 CLEAN WASTE DIStil LIQUID RAD MONITOR LOOP M2RR-8123-1 8
l CTMI AIR SAMPLE FOR RAD MONITOR FLOW IMO SWITCH l
10 M2RM-9049 7
3 11 M2FIS-8123-7 4
INST AIR DRYERS E FILTERS INSTRUMENIATION M21MS-AIR-C 8
3 STACK GAS GASEOUS RAD MON LOOP CTMT AIR PARTICULATE RADIATION MONITOR LOOP M2RM-8132B 2
Y M2RM-8262A-8 3'
CTMT AIR RAD MONITOR FLOW INDICATING SWITCH 48'gp ALRW 2 CLRW RADWASTE PROCESS RADIATION MONITOR SYSTEM 12 M2FIS-8262-7 5
/.
11 1
CTMT ATMOS PARTICULATE RAD MONITOR LOOP M2RM-8123A 8
4 U2 STACK EFFLUENT RAD MONITOR LOOP NI RANGE) KM;4H O ch 2PIOPS EC44
/.
6 PROCESS RADIAIION RECORDER (15 M2RJR-9129 12 3
REACTOR PROTECTION SYSTEM CABINETS D LOOP 6
le 16-M2RPS 1
L-T rn'we y
,g PAGE4 w MILLSTONE UNIT TWO - REWORK REPORTtIRC)
LIST OF LOCAL 1DS a EQUIPMEhT DESCRIPTION UNS=U WOS=F TOTAL OF CM AND OT IS =>4 FROM 05-01-1989 TO 09-15-1990
.AS OF 09/19/90 GRAND TYPE LOCALID CM OT EQUIPMENT DESCRIPTION T@TAL A7 M2CMM 16 1
COMMUNICATIONS SYSTEM d1O M2METRASCOPE 17 2
METRASCOPE ROD POSITION INDICATION ON C04F E 'R O"k s20 M2RJR-9373 7
13
' PROCESS RADIATION MULTI POINT RECORDER
[
12 RBCCW LIQUID RAD LOOP g4 M2 ANN 46 3
ANNUNCIATOR SYSTEM dM d 445 M2RM-5099 33 12 SJAE DISCHARGE TO STACK RAD MON LOOP 0
M20THER-WORK 12 38 WORK NOT RELATED TO PLANT EQUIPMENT (NO PMMS ID)
U
/[5 s
12/7/90 To: Terry Arnett
, h
+
From: Don Grindle
Subject:
Top ICR Generating Instruments The following is a list of t ie top 17 instruments that generated the most ICR's in the last 5 years.
Instrument (s).
A v 0 'y ".9 ft of ICR's Of 85
/
1.
Linear Range NI drawers 33 59 M
nok
- 2. / CTMT Rad Monitors 9
4e p
- 3. / SFP Area Rad Monitors f
35
/4
M N**j 0 b
34
- 5. / Rad Monitor Flow Switches dI"*
28 6.
S/G LP Eleck Bistable 27 Recorders f 7. y CTMT Radmonitor 26 b m
8.
AVMS p
f 9.
RC-14 Radiation Recorders 9129 L 9373 IT 25 10.
Aerated and Clean Liquid Discharge 9( g 16 recorders and integrators 15 h
C' 11.
Water Quality Monitoring eM.q mluw Xt-13 12.
RCS Flow Instruments 13 f 13.
P2R Level transmitters 12 14.
RM-8168 g
g 11 15.
AE-8154
\\
9 Ji.
: t Tr::r-
[
9 17.
Seismic
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Unit 2'I&C Memo e
December 26, 1990 MP2-I-1714 To:
Terry Arnett f
Y,
- s From: Bob Salen Subjr?AWO/ICR Overview and Summary
.i The following information represents an overview of recent AWO and ICR history
- as we discussed at our meeting'last week.
The listed items were ranked by directly adding the numberHof AWOs and ICRs and listing from highest to lowest (assuming that each AWO/ICR represents wasted man-hours and faulty equipment performance).
This list may be further refined and ranked based on the equipment's function and importance.
Component AWOs ICRs Sum Remarks.
RM-8123/
33 59 92 on list to upgrade.
RM-8262 RPS Linear 1
86 87 ICRs.very high, but' cms Range Dwrs okay.
Unstable?
RJR-9129/
19 41' 60 On list to upgrade i
RJR-9373 SFP Area 9
48 57 R/Ms Mige Recorders 7
2CNDFR310-7 5
2CNDFR247 5
5 2CESPNLO7RR 5
I 7
RR-202 7
3 AR-203 3
RR-8123 l_
2_7_.
2.0, i
28 27 55 Upgrade recommended i
h
-RM-5099 33 12 50 Upgrade approved 46 Typically card problems Annunciator 46 System RPS CPCs 5
35 40 i
RM-8168 16 12 28
(
F
.,m+.,w, w.,p-,
T
'n' 22 CRT Problems?
PICPs 22 11
-AE-8154 2
Miscellaneous 6
Flow control problems FIS-8998 6
startino in 9/89.
Worked fine prior to that.
i 3
Hi Rads - why not an MOV?
RC-100F 3
Does it really need a positioner?
AWO Data from PMMS rework report (5/1/89 to 9/15/90); ICR data from analysis by Don Grindle.
l
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cc: John Becker Pete Smith Ray.Schleicher Rework File I&C File i
i i
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g-PAGE1
- MILLSTONE UNIT TWO - REWORK REPORTEISCI LIST OF LOCALIDS E EQUIPMENT DESCRIPTION UNS*U WOSrF TOTAL OF CM AND Of IS n4 FROM e5-01-1989 TO 89-15-1998 AS OF 89/19/98 TYPE GRAND TSTAL LOCALID CM OT EQUIPMENT DESCRIPTION H2 ANALYIFR "A" CONTWOL MODULE 8 SENSOR 4
2 M28A383 9
4 SPENT FUEL POOL AREA R/M AREAS BISTABLES BORON R*COVERY HE AT TRACING RECORDER M2BRR-6 4
8 CORE PRolECTION CALCULATOR 2, RPS-B M2CPC-B-2 1
3 CORF PROTECTION CALCULATOR 1. RPS-C M2CPC-C-1 4
8 SERVICE WATER TO HX 169A FLOW INDICATOR M2F1-4668 3
1 FIRE PROTECTION DELUGE / WET SPRINKLER SYSTEM - MISC COMPONENTS RADWASTE VENTILATION RADIATION MONITOR SAMPLE FLOW IND SWITCH M2 FIR 4
8 M2FIS-8997 4
0 CllARGING HEADER TO REGEN HE AT EXCH X21 FLOW TRANSMITTER M2FT-212 3
1 AERATED WASTE TO CIRC WATER DISCHARGE FLOW M2FT-9118 1
3 CONDENSER FIT "B" SUMP PUMP 39A LEVEL CONIROL SWITCH (EAST)
0 VOL CONT TANK 15 LEVEL INDICATOR M2LI-226 3
I TERRY TURSIME STEAM SUPPLY WATER DETECTOR M2LS-4 5*. 9 4
9 2ND STAGE REMEATER DRAIN TANK 1A DUMP TO COND LEVEL VALV(
1 SEISMIC MONITOR FUR CTMT UPPER WALL +75* ELEVATION M2ME-9448 S
1 SEISMIC MONITOR FOR INTAKE STRUCTURE A 14*6" ELEV M2NE-945e 2
2 SEISMIC MONITOR FOR FREE FIELD 1 14*6" M2ME-9%51 3
1 FIRE PRolECTION PUMP P82 DISCHARGE PRESSURE IDWICATOR M2PI-7392 3
1 LINE AR POWER RANGE DRAWER RPS-C M2PR-S AF -C 1
3 RBCCW PUMP P11 A SUCIION PRESSURE LO SWITCH M2PS-6119A 1
3 STEAM GEN 82 DUMP TO ATMOS VALVE POSITIONER M2PV-4224 4
4 M2PV-19203 3
1 PZR PRESS V TO I CONVERTER PRESSURIZER SPRAY VALVES POSITIONER M2RC-100F 3
1 STACK GAS EFFLUENT RAD MONITOR CONTROL ROOM PAmt.
S STFAM CFNERAIOR BLOWDOWN COUNT RATE MODULE M2RIT-4262 e
4 CTNT ATHOS PARTICULATE RADIATION INDICATING XMTh CRM M2RIT-8123A 1
5 CTNT AIR GASEOUS RADIATION CRM M2RIT-82628 1
3 CONTROL ROOM VENTILATION RADIATION MONITOR M2RIT-9799A 2
2 MAIN STEAM LINE RAD MONITOR LOOP M2RM-4299C 4
8 CTMT ATMOS GASEOUS RAD MONITOR LOOP M2RM-81238 1
3 RADWASTE VENTILATION EMHAUST RAD MON LOOP M2RM-8434A 4
0 RADWASTE VFMTILATION RADIATION MONITOR LOOP M2RM-8997 4
e RADWASTE VENTILATION RADIATION MONITCR LOOP M2RM-8998 3
1 WASTE GAS TO STACK RAD MONITOR LOOP M2RM-9995 3
2
t PAGE2 8 MILLSTONE UNIT TWO - NEWORR REPORTtISC)
LIST OF LOCALIDS & EQUIPMENT DESCRIPTION UNS=U WOSar TOTAL OF CM AND OT IS =>4 FROM es-41-1989 TO 49-15-1990 AS OF 09/19/99 TYPE GRAND T&TAL LOCALID CM OT EQUIPMENT DESCRIPTION M2RPS*A 3
CALIBRATION AND IMUICATION PANEL.RPS-A M2RPSCIP-A 4
0 REACTOR REGULATING SYSTEM CHA994EL Y POWER INDICATON M2RRS-IMO-Y S
4 APMONItM HYOROMIDE PLRIP STROKE POSIT 10p*ER PUMP P-69A M2SC-7021 3
1 REACTOR COOLANT LOOP 3A COLD LEG TEMP LOOP MOT-111Y 3
1 REACTOR COOLANT LOOP IB COLD LEG TEMP RTD MOTE-112CD 1
3 SG I SECONDARY SIDE TEMPERATURE (HANDWAY RTDs M2TE-5457 1
3 REACTOR COOLANT LOOP 2 HOT LEG TEMP INDICATOR M2TI-122HO 2
2 LETOOWN HEAT EMCM N22 TEMP INDICATING CONTROLLER M2 TIC-223 4
4 COMOENSATE HDR. CopWUCTIVITY 8 HYDRAZINE MOR. CONCEN RECORDER M2UR-7269 4
8 CTMT PRESSURE a TEMP RECORDER MOUR-9862 4
e ACCUSTIC VALVE MONITOR ALARM MODULE FOR 2-RC-281 M2VM-201 1
3 ACOUSTIC VALVE MONITOR ACCELEROMETER E2-RC-2913 M2ZS-201 0
4 COMO DEMIN 2J OUTLET CONOUCTIVITY ALARM SWITCH M22CMDCIS159 3
1 H2 ANALVZER "S" CONTROL MODULE AND SE9tSOR 5
3 M2AR-203 3
2 BOROMONETER RECORDER MAIN TURBINE ELECTRCHYDRAULIC CONTROL SYSTEM M2E MC 3
2 STACK GAS SAMPLE FLOW SWITCE M2FIS-8132 2
3 FEEDWATER HEATER 6A NORMAL LEVEL CONTROL M2LC-5043A 5
8 SORIC ACID TANK T88 LEVEL INDICATOR M2LI-208A 5
4 MET TOWER INSTRUMENTATION (MAINTAINED BY MUSCol M2 MET-TOWER 4
5 LINEAR POWER RANGE DRAWER RPS-A M2FR-$AF-A 0
5 REED SWITCH POWER SUPPLY M2 REED-P/5-A 2
3 STACK GAS PARTICULATE E GASEOUS RAD RECORDER M2RR-8132 2
3 M2TU-8-1 3
2 CHANNEL-B TRIP BISTABLEt HIGH POWER M2WOH-D 4
1 WATER QUALITY MONITOR EDISCHARGEBLOOP (T6691 8 A6693B M2WGM-9 5
9 WATER OUALITY fl0NITOR (OUARRY CUT) LOOP tT6695 4 A66941 CPF RADIATION MONITOR RECORDER M22CESPML97RR 5
0 LINE DI1UTION WATER FLOW RECORDER M22CNDFR247 5
e AUTOMATIC TEST INSCRTER (ATI MODULEI 6
M2ATI 6
9 AUNTLIARY LOGIC DRAWER RPS-A M2AUMLOGIC-A e
6 NADWASTE VENTILATION RADIATION MONITOR FLOW IND. SWITCH M2FIS-8998 6
8 AERATED WASTE TO CIRC WATER DISCHARGE FLOW M2FR-9118 1
5 CTMT AIMOS GASEOUS RADIATION IMOICATING MMTR CRM M2RIT-81238 2
6 i
l
(
(
L
P PAGES e MILLSTONE UNIT TWO - REWORK REPORTEISC)
LIST OF LOCALIDS t EQUIPMENT DESCRIPTION UNSsU WOSsF TOTAL OF CM AND OT IS =>g FROM 95-01-1989 70 89-15-1999 AS OF 99/19/94 YYPE GRAND YtTAL LOCALID CM OT EQUIPMENT DESCRIPTION SPENT FUEL POOL RADIATION MONITOR CRM IEAST)
6 CTMT MI RANGE RADIATION CRM (Et.ST)
5 AENATED LIOUID RADWASTE PROCESS RADIATION PRIB8ITOR LOOP M2RM-9116 4
2 REACTOR REGULATING SYSTEM CMAte0EL M POWER IMUICATON M2RRS-IMD-X 1
5 WIDE RANGE DRAWER RPS-A M2tMt-LOG-A 6
8 CARBON MONOMIDE MONITOR ALARM (PORTABLE IN-LINE MONITORD 7
M2 COMA-5 5
2 SJAE DISCHARGE TO STACK RAD MON FLOW IND SWITCM M2FIS-5899 4
3 AERATED WAS1E FLOW TO CIRC WATER DISCHARGE M2FOI-9118 2
5 FEEDWATER ME ATER DRAINS R VENTS M2MDS 2
5 STACK GAS EFtLUENT RAD MONITOR LOCAL CONTROL PANEL M2LIC-8168 6
1 SERVICE WATER PUMP PSC FILTER PRESSURE DIFF SWITCH M2 PDC-6488 6
1 S.G BLOWOOWN PROCESS RAD MONITOR LOOP M2RM-4262 1
6 RECORDER FOR WM-292 8 RM-202A M2RR-202 7
0 WATER OUALITY lt0NITOR IINTAKCB LOOP (T6690 4 A6692)
M2WQM-I 5
2 M2WR-LOG-B 6
1 WIDE RANCE DRAWER RPS-B M2WR-LOG-C 6
1 WIDE RANGE DRAWER RPS-C COMO DEMINS A-G EFFLUENT FLOW RECORDER M22CNOFR319 7
8 RADWASTE VENTILATION EMMAUST RAD MON FLOW IIW SWITCM C
M2FI::-8454 7
1 SPENT FUEL POOL RADIATION MONITOR LOOP (EAST S M2RM-8156 4
4 WASTE MEUT SUMP RAD MONITot" LOOP M22CMDRM245 5
3 CfMT AIR PARTICULATE RADIA. ION CRM 9
9 SPENT FUEL POOL RADIATION MONITOR LOOP (WEST)
4 CTNT ATHOS PARTICULATE E CASEOUS RAD RECORDER M2RR-8123 1
8 CLEAN WASTE DISCH LIQUID RAD MONITOR LOOP le M2RM-9e49 7
3 CTMT AIR SAMPLE FOR RAD MONITOR FLOW IND SWITCM 11 M2FIS-8123 7
4 INST AIR DRVERS E FILTERS INSTRUMENTATION M2 INS-AIR-C 8
3 STACK GAS GASEOUS RAD MON LOOP MORM-81528 2
9 CTMT AIR PARTICULATE RADIATION MONITOR LOOP M2RM-8262A 8
3 CTMT AIR RAD MONITOR FLOW INDICATING SWITCM 12 M2F13-8262 7
5 ALRW 8 CLRW RADWASTE PROCESS RADIATION MONITOR SYSTEM M2PIOPS 11 1
CTMT ATMOS PARTICULATE RAD MONITOR LOOP M2RM-8123A 8
4 M2Rtt-4168 6
6 U2 STACK EFFLUENT RAD MONITOR LOOP (HI RANGEl 15 M2RJR-9129 12 3
PROCESS RADIATION RECORDER REACTOR PROTECTION SYSTEM CASIIIETS A-D LOOP 16 M2RPS 6
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a MILLS 10ME UNIT TWO - REWORK REPORTEIRC)
PAGE4-LIST OF LOCALIDS S EOUIPME;;T DESC74IPTION UNSzU WOS*F TOTAL OF CM Ale OT IS =>4 FROM 85-01-1989 70 99-15-1994 AS OF 99/19/99 GRAND TYPE TETAt LOCALID CM OT EQUIPMENT DESCRIPTION 17 M2Cret 16 1
COMMUNICATIONS SYSTEM 19 M2METRASCOPE 17 2
METRASCOPE ROO POSIf!ON 18MIICATION ON C04F 20 M2R A-9375 7
15 PROCESS RADIATION MULTI POINT RECORDER M2RM-6458 8
12 RSCCW LIQUID RAD LOOP 45 M2RM-5499 33 12 SJAE DISCHARGE TO STACK RAD NON LOOP 49 M2 ANN 46 3
A884UNCIATOR SYSTEM 5e M20THER-WORE
- 12 38 WORK NOT RELATED TO PLANT Egu1PMENT INO PERES IDI 4
1
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SAMPLE RECORD OF ALLEGATION PANEL DECISIONS SITE: b5 mit PANEL ATTENDEES:
f 7-9 i-4 -0241 Chairman -
b+s.M S ALLEGATION pO.:
DATE: dBW (Panel No@ 3 4 5)
Branch Chief -
l PRIORITY: High lu Low Section Chief (AOC) - Kelk SAFETY SIGNIFICAN@CE:h Sr. Alleration Coord (SAC) C kn4/er Yes No i
i CONCURRENCE OI Reoresentative -
l TO CLOSEOUT:
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IS THERE A HARASSMENT / DISCRIMINATION l
ISSUE:
Yes h
! IF YES, l 1) has the individual been informed of the DOL l
process and the need to file a complaint within 30 days Yes No i 2) has the individual filed a complaint I
with DOL Yes No i 3) has a letter been sent to the complainant seeking Yes No i
any safety concerns h
l IS A CHILLING EFFECT LETTER WARRANTED:
Yes
! IF YES, HAS IT BEEN SENT Yes No
! HAS THE LICENSEE RESPONDED TO THE CHILLING EFFECT LETTER:
Yes No ACTION:
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PROJECTED REPLACEMEN15 YEAR 1991 1992 1993 1994 1995 WIDERANGEORAERREPLACEMENT 300 LINEAR RANGE DRAER REPLACEMENT 400 RPSCIP DRAWER REFUR8/ REPLACE 201 391 CORE PRoitti10N CALC. REPLAC(
RPS POER SUPPLY REPLACEMENT 50 ANNUNCIATOR POE R SUPPLY REPLACE
,Idp SPEC 200 POKR $UPP REFUR8/ REPLACE 30 SEISMit MONiiOR REPLACEMENT F
ESAS Olli/ MODULE REPLACEMENT 252 304 LOOSE PARI $ MONITOR REPLACEMENT 503 709 CONTAINMENT GAS /PART RADMON REPLACE 600 600 500 SJAE PADM0N REPLACEMENT 495 AVMS $ENSOR REPLACEMENT 50 GEMAC INDICATOR REPLACEMENT 50 dp GEMAC CONTROLLER REPLACEMENT METRASCOPE REPLACEMENT 150 HJfC ENHANCEMENTS (TEST BOX) 25 HJTC CABLE REPLACEMENT 5 300 RCP SPEED SENSOR REPLACEMENT 50 140 RP5 N015E PR08 TEM 5 25 ANNUNCIATOR OPi! CAL !$0LATORS 10 DATA COLLECTION SYSTEM RCS RID's 75 MSR L0 LOAD CONTROLLER UP6RADE 25 RCS CORE AND PUMP PDT UP6RADE 10 R8CCW SW TEMP IND UPGRADE 10 RBCCW SW FT UPGRADE / RELOCATE 25 STATOR COOLING PS UP6RADE 10 )
$PF AREA MAINT. JACK 10 '
8.A. EVAP TU8ING/LT UP6RADE 10
- CED5 P0E R SUPPLY REPLACEMENT 80 -.2 >
FEED WIR HEATER LT UPGRADE 25 "?
DRAIN TANK LT UPGRADE 10 - *
- Meansplannedbutnotauthorized.
TOTAL Kl 1,710 1,633 1,721 981 500 C RT.b (;
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O M t.
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ALLEGATION NO.: fl-il-ko14f Chairman -
(4)cu M 1 DATE: 185N' (Panel No.$2 3 4 5)
Braneb Chief -
Section Chief (AOC) - llelly.
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any safety concems l IS A CHILLING EFFECT LETTER WARRANTED:
Yes @
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