ML20234B220
| ML20234B220 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 09/03/1987 |
| From: | Kintner L Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| GL-84-15, GL-86-10, NUDOCS 8709180320 | |
| Download: ML20234B220 (30) | |
Text
-
September 3,1987_
4 Docket No. 50-416 DISTRIBUTION
BTroskoski j
LICENSEE: System Energy Resources, Inc.
Local PDR.
NTrehan l
PD22 Rdg.
JKudrick FACILITY: Grand gulf Nuclear Station, Unit 1 HBerkow ANotafrancesco LKintner J. Craig
SUBJECT:
SUMMARY
OF AUGUST 7, 1987 MEETING OGC-Bethesda J. Unda j
REGARDING LICENSING ACTION STATUS EJordan L. Rubenstein i
JPartlow I
The purpose of the meeting was to discuss the status of licensing actions. is the list of attendees. is the agenda and licensing i
action status and projections prepared by the licensee. Enclosure 3 is an outline of actions to address a deficiency in the design of a containment iso-
)
lation valve in the reactor water cleanup system. contains sket-ches illustrating plans for removing a two-hour fire wall _ to expand the Tech-4 1
nical Support Center.
The licensee said GGNS Unit I has operated at full power during the second fuel cycle except for two scrams due to equipment failure. A world record continous run for BWRs in the second fuel cycle was_ established prior to the scrans. The first scram on June 30, 1987 was due to failure of a relay in the control of a valve in the steam supply line~ for the stean jet air ejector. The valve closed causing a loss of condenser vacuum and reactor trip. The plant was restarted l
the next day. The second scram occurred on August 6, 1987, when two output breakers in the switchyard opened due to condensation within the breaker cabinets, causing a load reject and reactor trip. :The plant remained shut down for a few days to replace the HVAC ducts that penetrate the reactor building walls. A design review indicated the ducts would collapse under accident conditions be-i cause the duct walls were too thin. A scram reduction program was implemented at the start of the second fuel cycle. The licensee is preparing for an INP0 ap-i praisal in the second and third week of September.
The second refueling outage (RF02) is currently scheduled to begin November 6, 1987 and to last 64 days.
The licensee described a design deficiency regarding a containment isolation valve in the reactor water cleanup systen. An inboard isolation valve (F252) has the same division of power supply as the outboard isolation valve (F004) 1 (see page 4, Enclosure 3). Corrective options are to:
(1) use another valve (F253) having the redundant divisional power supply as the inboard isolation valve; or (2) change the power supply to valve F252 (see pages 1-3, Enclesure 3).
An LER is in preparation to describe the deficiency and corrective action.
New fuel is being received onsite from Advanced Nuclear Fuels Corporation (formerly Exxon). During the unloading of a cart used to transport assemblies, the cart was ripped by a crane sling causing two fuel assemblies to slide off the cart, Although there was no apparent damage, the two assemblies were shipped l
8709180320 870903 PDR ADOCK 05000416 P
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1 2-back.to the fuel vendor for examination and repair, if necessary. The trans-fer of new fuel from the transport vehicle to the new fuel storage racks in the auxiliary building is cumbersome because the railroad bay door was not designed to criteria for use as a secondary containment boundary. The licensee plans to modify this design after the next refueling outage.
The licensed End staff discussed licensing actions identified in the agenda (Pages 2-6 Enclosure 2). Coments on specific items are sumarized below.
Target dates for licensee submittals and NRC license amendment or safety evalua-i tion issuances are shown in the' agenda.
l III.A.3 and Attachment 1, I.B.3 The NRC staff said that Generic Letter 86-10. " Implementation of Fire Protec-tion Requirements" is being implemented with Wolf Creek as the lead plant. The i
staff is reviewing the licensee's request for an amended license condition and f
transfer of limiting conditions for operation and surveillance requirements from the Technical Specifications to the Final Safety Analysis Report. The staff plans to issue another generic letter in early 1988 to provide guidance for the review of other plant licente amendment requests pursuant to Generic Letter 86-10. Therefore, review of the GGNS Unit l' request to amend the fire protection license condition will be deferred until 1988. The staff's review of the GGNS Unit I revisions to the Fire Hazards Analysis (Rev. 0) and Appendix R exceptions is continuing at a low priority and is estimated to be completed by October 15, 1987.
The licensee said that a request for changes to the Technical Specifications regarding fire protection instruments was submitted on August 6,1987, in the event the fire protection license co'ndition was not changed by the second re-fueling outage. The licensee requested expeditious review so that changes could be made prior to the refueling outage.
IV.B.7 and Attachment 1. III.C
, The licensee described plans to remove a two-hour fire-rated wall of the Tech-nical Support Center (TSC) in the control building to make more room for the occupants of the TSC. Emergency preparedness drills and exercises have shown the need for expansion of the TSC. The wall is a designated fire-rated wall, but it has not been used in fire hazards analyses. As shown in Enclosure 4, the wall to be removed is within the control room controlled boundary for habitability considerations and its removal will not change that boundary.
1 A fire protection analysis and 10 CFR 50.59 analysis will be perfonned for the modifications. The staff said that habitability and other safety-related con-siderations should be included in the 10 CFR 50.59 analysis.
If the licensee concludes from its analysis that there is no adverse impact on fire protection and there is no unreviewed safety question, the planned wall removal will not be submitted for NRC approval.
l
' III.A.1 and Attachment 1, II.B l
l The staff said the July 2,1987 submittal proposing the use of manual valves in pressure instrument lines for the MSIV-CCS and ECCS systems in lieu of auto-matic containment isolation valves appeared to be acceptable. The staff's safety
. evaluation is~ scheduled to be issued August 21, 1987.
III.A.1 and Attachment 1, II.C The staff said some questions have arisen during its review of the licensee's June 30, 1987, request to defer completion of the DR/QR baseline inspection of the GGNS Unit 1, Division II, TDI emergency diesel generator. The licensee has-requested deferral until the 5-year required maintenance inspection because of the recent good performance record of similar TDI diesel generators. Since appropriate licensee technical personnel were not available in the meeting, the licensee suggested a conference call. On August 10, 1987, a conference call was held between the NRC sta'f and the licensee to discuss certain staff cuestions.. The licensee will submit additional infonnation regarding the TDI ciesel generators which respond to these questions by August 17, 1987.
III.A.2 The staff has issued Technical Specifications for GGNS emergency diesel gene-rators based or Generic Letter 84-15, " Proposed Staff Actions to Improve and Maintain Diesel. Generator Reliability." However, the diesel generator test schedule is based on 100 valid tests, instead of 20 valid tests as recommended i
in Generic Letter 84-15. The licensee will request a change in Technical Specifications to allow use of the less restrictive test schedule.
III.A.4 The licensee will submit its proposed reload licensing package for Cycle 3 for NRC staff review. The package will include proposed Technical Specification changes for two new fuel types (MAPLHGR curves) and analyses of loss of feedwater heating.
III.A.5 The staff said that the coment period on NUREG-1150 would be extended to October 1, 1987 in response to System Energy Resources, Inc. and other requests.
The present target date for issuance of the final NUREG-1150 is July 30, 1988.
III.A.6 The licensee said that the improved GE Standard Technica1 Specifications are scheduled to be submitted in June 1988.
III.B.1 The licensee said it had requested Region II to consider rescheduling its PRA-I based inspection from the end of August to the end of 1987.
i j
.a.
III.B.3 The licensee said it had requested further interpretation of the requirement to report actuations of ESF by means of a letter dated July 30, 1987, transmitting LER 87-010-00.
In this event, containment isolation valves were closed when a power supply breaker was. manually opened for maintenance purposes. Because the isolation valves were not closed by actuation of ESF protection logic, the licensee questioned the need to report the event and requested a determination by the NRC as to the need to report similar events in the future. The staff is considering the matter.
l III.B.4 The staff asked.the licensee what 'urther actions are planned regarding the 1
information provided by General Electric in its letters to Mississippi Power &
I Light Company dated February 3, 1986 and February 14, 1986. These letters pro-I vided infomation regarding the number of safety relief valves (SRVs) that could safely be out-of-service during power operation. The letters indicated that FSAR Chapter 15 accident analyses and ATWS analyses were based on only 1 of the 20 SRVs being out-of-service due to a single failure. Technical Specifications for Grand Gulf require only 13 of 20 SRVs to be operable based on the ASME over-pressure transient. The licensee has restricted GGNS Unit 1 operation by an administrative position statement which requires 19 of the 70 SRVS to be operable during plant operation.
The licensee said it planned to ask the BWR Owners Group Technical Specification Improvement Work Force to consider whether Technical Specifications should be. developed., I.A.4 The request to delete the requirement that certain containment isolation instru-mentation be operable during Operational Condition 4. " Cold Shutdown" and 5
" Refueling" was discussed briefly. The staff said that the automatic actuation of valves that isolate the reactor upon receipt of a reactor low water level should be retained because of their safety function to prevent inadvertent draining of the reactor water during shutdown. The licensee will review its request to detemine that such valves are not included in the application., I.A.5 The licensee is preparing additional infomation regarding its request to raise the setpoint o# the relief valve in the standby liquid control system (SLCS). The staff had expressed concern because the application stated that the reason for raising the setpoint was that the relief valve lifts occasion-ally during the running of a surveillance test to demonstrate capability to inject into the reactor. The additional infomation will address the staff's concern that the margin between the present and proposed relief valve setting and the pressure expected for the SLCS when injecting into the reactor is adequate to assure that the SLCS will be able to deliver rated flowrate to the reactor without the possibility of some flow being diverted through the relief valve.
i
! 1.
l The staff made the following observations regarding licensee performance.
The staff noted that licensee performance in the area of updating and following plant procedures had improved significantly over the past year, based on reports from the inspection staff. However, a few areas still need improvement.
It was noted in NRC Inspection Report 87-17 dated July 28, 1987 that a system operating instruction for the drywell purge compressor had not been updated to include a check of valve position indicators in the control room when determining system operability. These control room valve position indicators had been installed in the last refueling in the fall of 1986.
The time lag for updating the procedures appears excessive. Also, in Inspection Report 87-17, it was noted that due to analysis errors, a high steam flow setpoint for the RHR/RCIC steam line in the Technical Specifications was found to be nonconservatively high (less than or equal to 145 inches of H O instead of less than or equal to 37 inches of H 0).
2 A position statement was placed in the Technical Specifications requiring $he correct setpoint; however a Technical Specification change was not initiated immediately. The staff said that administrative procedures are appropriate when a nonconservative Technical Specification is found to assure the plant is oper-ated in a safe manner; however, the time lag to initiate a Technical Specifica-tion change should be reduced. The staff also noted that a similar analysis error had resulted in a Technical Specification change for the setpoint in the RCIC steam line and questioned whether similar analysis errors existed for other instruments used to mitigate high energy line breaks. The licensee indicated it would look for similar analysis errors.
The staff provided the licensee with two examples of good analyses about the issue of no significant hazards considerations required by 10 CFR 50.92 for license amendments.
The June 3, 1987 submittal on core alterations and the July 1, 1987 submittal on the relief from the requirement in Regulatory Guide 1.97 for flow measurement in the SLCS were exceptionally good.
The licensee expressed an interest in hearing the staff's concerns regarding its perfomance in order to better direct improvement efforts.
The licensee said it would be interested in a SALP-type evaluation of the licensing functional area at the next licensing action meeting.
Lester L. Kintner, Project Manager Project Directorate II-2 Division of Reactor Projects-I/II Enclosures :
1.
Attendance List 2.
Agenda i
3.
Corrective Action Plan 4.
Sketches cc w/ enclosures:
See next page LA 2
II-2 Pb II-2 DM r
LKintner:bg HBe ow 9/'
7 9/f_/87 9/ S/87
Mr. Oliver D. Kingsley, Jr.
System Energy Resources, Inc.
Grand Gulf Nuclear Station (GGNS)
.CC:
Mr. Ted H. Cloninger Mr. C. R. Hutchinson Vice President, Nuclear Engineering GGNS General Manager and Support System Energy Resources, Inc.
System Energy Resources, Inc.
Post Office Box 756 Post Office Box 23054 Port Gibson, Mississippi 39150 Jackson, Mississippi 39205 Robert B. McGehee, Esquire The Honorable William J. Guste, Jr.
Wise, Carter, Child, Steen and Caraway Attorney General P.O. Box 651 Department of Justice Jo ason, Mississippi 39205 State of Louisiana i
Baton Rouge, Louisiana 70804
'ficholas S. Reynolds, Esquire Bishop, Liberman, Cook, Purcell Office of the Governor l
and Reynolds
. State of Mississippi l
1200 17th Street, N.W.
Jackson, Mississippi 39201 Washington, D. C.
20036 Attorney General Mr. Ralph T. Lally Gartin Building Manager of Quality Assurance Jackson, Mississippi 39205 Middle South Utilities System Services, Inc.
P.O. Box 61000 Mr. Jack McMillan, Director New Orleans, Louisiana 70161 Division of Solid Waste Management Mississippi Department of Natural Mr. John G. Cesare Resources Director, Nuclear Licensina and Safety Bureau of Pollution Control System Energy Resources, Inc.
Post Office Box 10385
-P.O. Box 23054 Jackson, Mississippi 39209 Jackson, Mississippi 39205 1
Alton B. Cobb, M.D.
{
Mr. R. W. Jackson, Project Engineer State Health Officer j
Bechtel Power Corporation State Board of Health
)
15740 Shady Grove Road P.O. Box 1700 l
Gaithersburg, Maryland 20877-1454 Jackson, Mississippi 39205 i
Mr. Ross C. Butcher President Su.icr Resident Inspector Claiborne County Board of Supervisors U.S. Nuclear Regulatory Comission Port Gibson, Mississippi 39150 "oute 2, Box 399 Port Gibson, Mississippi 39150 Regional Administrator, Region II U.S. Nuclear Regulatory Commission 101 Marietta Street, N.W., Suite 2900 Atlanta, Georgia 30323 Mr. James E. Cross GGNS Site Director System Energy Resources, Inc.
P.O. Box 756 Port Gibson, Mississippi 39150 lO_-_--______
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ENCLOSURE 1 ATTENDEES NRC - System Energy Resources, Inc.'(SERI) Meeting, August 7, 1987 SERI O. D. Kingsley, Jr.
J. G. Cesare M. Crawford NRC L. S. Rubenstein L. L. Kintner J. Unda-i N. Trehan J. Craig J. Kudrick A. Notafrancesco R. Butcher (part-time via telephone)
I
'l ENCLOSURE 2 l
2 NRC - SYSTEM ENERGY RESOURCES, INC.
LICENSING ACTION STATUS MEETING Bethesda, August 7, 1987 I.
INTRODUCTIONS II.
PLANT ACTIVITIES III.
SPECIAL TOPICS OF INTEREST A.
NRR Interface Issues B.
NRC Region II Interface Issues IV.
KEY LICENSING ACTIONS A.
NRC ACTION B.
SERI ACTION V.
OBSERVATIONS REGARDING LICENSEE PERFORMANCE i
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NRC-SERI LICENSING ACTION STATUS MEETING August 7, 1987 AGENDA
^
I. INTRODUCTIONS i
II. PLANT ACTIVITIES A.
Plant Status and Upcoming Events OD Kingsley, Jr.
B.
RF02 Scope Update ODK C.
Recent Plant Issue / Events j
J 1.
Reactor Water Clean-up System - Containment Isolation Issue JG Cesare 2.
Mishandled Fuel Bundles JGC III. SPECIAL TOPICS OF INTEREST A.
NRP Interface Issues 1.
RF02 Support (Attachment 1)
ML Crawford 2.
EDG Testing Frequency (Generic Letter 84-15)
MLC 3.
Fire Protection (TS deletion /0LC Revision)
MLC o
TS Deletion /0LC Revision o
FHA Rev. O and Appendix R Exceptions 4.
Reload Licensing - Cycle 3 JGC o
Reload Package o
18 month fuel cycle TS 5.
NUREG-1150 Activity MLC 6.
Tech Spec Improvement Program MLC j
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B.
Region II Interface Issues 1.
PRA Based Inspection Plan NRC 2.
Potential Appendix R Audit - 1988 NRC 3.
Deportability Determination Regarding ESF
- tomponents/ Systems, Request for Guidance NRC 4.
Potential TS LC0 Regarding SRV Operability JGC IV. KEY LICENSING ACTIONS A.
NRC Action
(
1.
RF02 Tech Specs (Attachment 1) 2.
RF02 Deferrals (Attachment 1) 3.
RF02 Miscellaneous (Attachment 1) 4.
FHA Rev. O and Appendix R Exceptions 8/31 5.
SERI Organization Changes 10/15 6.
10CFR20.103 Exemption Request 9/15 7.
SRV Fatigue Evaluation 9/30 TBD 8.
IST Program 9.
Various HCOG Submittals B.
SERI Action 1.
TS Change - RHR/RCIC Hi Steam Flow Setpoint 8/6 2.
Deletion of Commitment to inspect RHR Heat Exchanger During RF02 8/11 3.
10CRF20.103 Exemption Request - RAI 8/21 4.
Comments on Draft NUREG-1150 8/21 5.
Semi-Annual Effluent Release Report 8/30 6.
Revised PGP pages 8/31 7.
Remove Two Hour Fire Wall in TSC 8/12 8.
Summary Level Long Term Plant Schedule 9/1
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ATWS RAI - Testing of Backup Scram Valves 9/7 10.
Response to IEB-87 Thinning of Pipe Walls 9/13
/.-
11.
Salem ATWS - Reactor Protection System 10/13 12.
TS Changes _- 18 Month Fuel Cycle 11/6 13.
Unit 2 Preservation & QA Program TBD l
V. OBSERVATIONS REGARDING LICENSEE PERFORMANCE NRC Attachments
'1.
RF02 Action Status 2.
Recent SERI Submittals 3.-
Forecast (Next 90 days) h /
4 I
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SERI/NRC RF02 LICENSING SUPPORT ACTIONS I. TECH SPECS ~
A.
RF01, Lessons Learned 1.
Core Alteration Defir,ition Noticed July 15 Issue 9/15 2.
Snubber Test Sample Noticed July 29 Issue G/15-l 3.
Spec. 3.0.4 Exception To be Noticed August 12 Issue 9/30 i
4.
Cont. Isolation Instrumentation To be Noticed August 12 i
Issue 9/30 l
5.
SLCS Relief Valve Setpoint To be Noticed j
August 12 Issue 9/30 B.
RF02 Suoport
\\
- 1..
ATWS Submit by 8/6 2.
Reload Licensing Package - Cycle 3 11/6 l
1 Include MAPLHGR Curves and LFWH Analyses 3.
Fire Protection Submitted TS changes related to 8/6 smoke and fire detector installation l
II. DEFERRALS i
A.
RG 1.97, Flux Monitoring PCOL submitted to NRC 7/1 I
SERI submitted revised PCOL SHC based 8/4 based on NRC comments Notice in Federal Register 8/26 Issue to SERI 9/30 4
[
J16 MISC 87080601 - 5
I B.
MSIV/ECCS Inst. Lines L
Formal deferral request submitted with 7/2 l
proposed commitment to install additional MANUAL VALVE NRC response to SERI 8/7 C.
EDG II J
Deferral request submitted 6/30 NRC response to SERI 8/30 III. OTHER A.
ISI Relief Request (RPV Nozzles)
Submitted relief request for areas not 6/12 accessible or practical from geometry standpoint, RPV nozzles, RPV lower head, various ECCS piping
' Response to SERI 9/15 B.
ISI Relief Request (Later Addition of ASME Code)
Submit relief request to adopt later 8/10 edition of ASME code for Class 3 Integral Attachments Submit relief request to adopt later 8/10 edition of ASME code to allow use of pressure test boundary definition l
Response to SERI 9/30 1
C.
Fire Protection (FP)
Submit a request to remove 2-hour 8/12 fire rated wall in the Control Building (TSC Area) b J16 MISC 87080601 - 6
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SYSTEM ENERGY RESOURCES, INC.
I LICENSING PRIORITY ITEMS 1
SHORT TERM 1.
RF02 Support Items a.
TS 3.0.4 Exception b.
Containment Isolation Instrumentation c.
ATWS TS changes d.
Reload TS changes e.
Fire Protection, TS changes f.
Fire Protection, Derated Fire Barrier in Control Building (TSC) i g.
Reg. Guide 1.97 Flux Monitoring deferral h.
MSIV/ECCS Instrument Line Isolation 1.
EDG Division II, DRQR Limited Deferral l
j.
ISI Relief Requests 2.
RWCU Containment Isolation Issue LONG TERM l
1.
NUREG 1150/GGNS PRA Related Activfties 2.
Resolution of Reg. Guide 1.97 Flux Monitoring Issue l
3.
Technical Specification Improvement Program (Commissioner Policy l
StatementFollow-up)
Fire Protection,'ompletion of NRC GL86-10 Related Work C
4.
5.
Resolution of Hydrogen Control Issue 6.
Resolution of Spent Fuel Pool Cooling Issue 7.
Assessment / Improvements to 10CFR50.59 Evaluation Process l
8.
Improvements in Plant & Design Deficiency Tracking & Evaluation Process l
9.
Overall Improvements in SALP Area of Licensing Function Resolution 1
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1 RECENT SERI SUBMITTALS
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MFit HUCLEAS LICENSING & SAr[it.
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MF8L CO U IS. HUM l 10FIC 0F SUBMITIAL MF6L CORRIS NUM RESFONSE MP&L ID N3M NEEDEi IA0 NUMiEF
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05/19/87 YES 02/16/87 G.L. 86 10 SUEM:
TECH SPECS AND THE STANDARD LICENSE CO AECM-87/0046 FMI-67/0130 10 70117 SUBMll RESULTS OF THE CONTAINMENT ISO 05/22/87 01/20/87 CONIAINMENTFURGE FMI-6?/006!
AECM-87/00%
10 70040 SUPMlf CORRECTED CER11FICATE OF NU 05/22/S7 04/01/37 INSURANCE AECMS?/00?o-A!CM07/0CJ1 IE 702/!
FA) THIRD QUAtTER 1966 INSFEti!0N FEES.
05/22/07 04/2e/07 FE!!
AECM-87/00M MAEC-87/010:
]D 70300 k
05/22/$'-
NM EAA" OVESil M SUFMll 09ESil0N! 0h NH OFERATOR EIA.!
0!/26/D IPN': TELECOL AECPS/010:
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AECM87/0101 MAEC-67/Cl!G 10 7034?
StP !i MSF?NS! REGARDING GGNS FRES
'05/28/C?
C3/13/07 Gt (9-Oc (FluL MAEC-07/0'J!
DELETE!
ID70283 SUBMli SERI SFECIFIC COMMENTS ON 05/20/S7
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RULE CHANGE 50.47(e).
100FR50.47(e)
10 70351 SUIM11 SPECIAL REVISED FSAR UFDA 06/03/87 03/20/87 FSAR UF0 ATE CURRENT ]NCORNATION ON MINEFdt R PMI-87/13e!
AECM87/0100 DCLUSION AREA.
t ID 70255 INTERIM LETTER 10 NRC DUE TO ORG i
06/05/87
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MFt'. RTLEAR LICEh!ING & SAFElf DATE: 08/06/S' AC' ION IFACKINS MANAGEMENT SYSI!"
RECEN' Mit'. LICENSIW3 ACTIVITIE!
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SU!Ml1TAL DATE NRC REQUEST DATE MP&L CORRES. N'.?
RES%N!E MFL; C0RFFF. NU" 10FIC 0: SUiM!1TAL DESCRIFIION MF4L ID NVM NEE 0!E TAC NUMi::
06/05/f7
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FELI!I REQUEST SUFMIT AN ASME SECTION !!! RELIEF RICUE!! F0F N0ZlLE TO RFV AECM67/0172 WELOS WHERE FULL CODE COVERAGE !$ NOT ATTAINAELE.
10 70140
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$UiMIT REY. 6 OF THE 00AM 10 THE NRC.
06/11/87 AECM67/0131 X
10 70:84 06/11/07 05/12/07 GL 67-Oc SUBMIT AECM PROVIDING RESPONSE 10 GL B7-06.
AECM-87/Oll7 FMI-6iil522 ID 70326 Ot/12/07 05/ll/f7 LEE SUBM!i UFDATE LER TO NEC CONCERNING RHR*A' SURV!ILLANCE AECP87/0!!6 IF 8'-! '
LATE.
IL 70391 06/15/07
/ /
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AECM67/0!?C N'.S A : C.4 1061342 06/22/07 Oi/10/E' S/::!f: ME!!!M SU!M!iAECM00CVMENTIN35/27/87 MEETING iETWEEN SERI AND NR:
AECM67/Cll; IEi TELE 00Fi
!!GION Il REGARt!NG 0FERATOR REQUA'.IFICATION.
10 7040^
06/22/f' Ce/II/E7 Ct A!c t. f 0!' P:EL SUfMIT R' FORT TO NRC OESCFIEI E FECfh!Li IDENTIrIEL AECH87/Cl2; ML f',
DEFICIEN:IES IN CLASS A DOSE M XEL 10 7040:
06/23/U 04/C:/c?
ATL!
SU6MITAECMDELETINGW?RL'0ECAPORATE'FROMAECM-67/0055 AECM87/0!Ci AECM-87/0^"
RESPON!!T0NCCFEQVESI9FEFC5/22/67SERi/NR:CONTERENCE 10703d CALL.
Ot/?d/E'
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ASME REL!!r SUiMIT ASME SECTION 11 FELIEF REQUESTS FOR CODE VOLUME!
l AECM-07/Cll:
1 OM]TTE: FROM RFV INSPECTIONS Ki 10 IMFROFET FLACEMEW10F j
10 703 "
AUTOMAi!D ELD EXAMINATION EQUIPMENL Oo/25/S7 YEe
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DR/0RDEFERRAL SUBMIT A FR0F0 SED DEFERRAL OF CR/0R INSPECTIONS FOR DIV. !!
AECM87/0065 N/A UNTIL THE 5 YEAR CONFIRMATORY INSFECTION.
10 70367 06/29/07 YES 05/13/07 10CFR20.103 EXEMF1 SUBMIT 100FR20.103EXEMFTIONREQUEST.
AECM-87/0043 FMI-87/152e i
ID70334 l
06/30/07 05/29/07 LER6e029-08 SUBMIT UPLATE LER 10 NRC CONCEFWIN; FIFE F0VLI 4 IN LOW AECM67/012e AECM-87/0!07 FLOWS T0 ESr ROOM COOLERS AND RELATED SSW DESIGk CONCEFNS 10 70.i10 l
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A0i!0N TRACXING RANAGEMENI SYSTEP RECENT M?&L LICEN!!NG ACitylf!!!
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-SV6MillAL DATE NRC REQUESTDATE MFil CORR!?, NUM' RESFON!E N LL 00RRE E NUM 10'!C 0F SUfMif1AL DE!CRiffiON MF4LIDNUM NEE 0E0 TA0NUMiER
- ::: : :::::::: ::::r :: : : : :. ::::..:: ::::::
07/01/07 02/28/f!
HEVfRON N0Hi UFGR FREFARE LICENSE CHANGE REQUESI 10 NRC TO IMPLEMihi N!VIRON l
' A!CM47/00lf -
AECM45/00M MON!!0 RING VFGRADE IN RF03 INSTEAD OF FF02.
'10 60871 04/09/P?
CNTHNT!$0 VALVES
. SUBMIT AECM REQUESilNG ELIMINATION Of COMMIIMEW1 TO INSTALL 07/02/87 l
'AECM-87/0103 A!CM62/102 6 M0W INTO VARIOUS INSTRUMENT LINES.
1070336 l
07/06/87
/ /
SLCS SU8M!i FCOL RE0 VESTING i$ CHANGES TO INCREASE SLCS FVMF AECM-87/012S IS 4.1.5.d.2 RELIEF VALVE SETF0 INT ID 70420 I
07/13/87 04/23/87 SFilED SAMFLES 5UBM!i ANALYSIS /RESULI! 0F SFIIED SAMFLES TO NRC FOR NRC AECM87/0130
. MAEC47/0111 00HrlRMATORT MEASUREMENT FROGRAM.
ID61004 07/15/67' 07/15/f,7 MOR SUBMli JULY MONTH;Y OPERATING FIFORT TO NRC.
A!CM-87/0!::
1.5. 6.9.1.10 If 70407 07/16/87
/ '/
FW hS:lLE SVFMli A REFORT ADDRE!$1NG NVsEG-0619 FW NallLE INSFECil0NS AECM47/0!M NUREG-Oc!:
WlIHIN 6 MONTHS Of FW N0llLE INSCECil0N C0MFLEi10N.
10 70266 07/17/87
/ /
FINAT:n SU!M!iCecc0CATEFINACIALREF0FTSF0FMF&L/SERIAE A!CM8'/01D N' Sat 2.4 SMirA F0F l y:
IF61341 07/17/07 0!!04/f?
H1D8 N!h CONIFOL FREFARE ANE !V!MIT LEliER 10 THE NFC FF0VIDING NEW SCHEDULE AECM87/0!!?
LICEL!! CONE.
AND DATE FOR COMFLET10N OF THE GRAND GULT HYDR 0 GEN CONTROL ID 7037tc FROGFAL 07/17/67 06/10/F SFV F A116'.'!
SV!Ml? 10 NRC THE NVIECH REFORi! REFEREN^ED IN THE OLC AECM47/0127 NRC H 0 VEST 2.C(10)(a)SRVFAi!GUEEVAIVATIONS.
If 70400 07/17/67 07/15/07 00AM REY. 6 SVBMil LETTER DOCUMENTING 7/15 CONFERENCE CALL W ik NRC All.
AECM87/0136 M10-87/0665 DVE DATE F0F REVISION 610 00AM DELAYED 10 7/13.
ID70481 07/23/07
/ /
ISI RELIEF RE0.
SUBMIT FESPONSE TO INr0RMAL RAI re: SOURCE OF MAIEVF FLOW
.AECM87/006S NRCREQ(INFOR) 10 D VESSEL FOLLOWING BREAf IN CRD HOUSING.
ID61239 07/24[87 07/14/07 LICENSE RENEWAL SVEMll 0FERA10R LICENSE RENEWAL APPLICAi!0k.
AECM-87/0137 FMI87/4504
~10 70507 l
I II
\\
1
MF4L NUCLEAR LICENSING & SAFE 11 DATE: 08/06/87 ACT!6 TRACilha MANAGEMENT SYSTEM RECEN! W 4L LICENSING ACTIVII!ES PAGE:
4
$USMlilALDATE HFC REQUEstDATE QF4; CORRES. NUM.RE$FONSE MFil C0FRE!. NUM 10FIC 0F SUSMITTAt DESCRIFi!0N MFIL (( N'JM NEEDED TACNUM!!F
- .::::.:2::::.::- : ::::::::::::::: ::: :: ::- ::::::.:
07/29/$?
06/24/87 LEF SUf Mit MJ 10 NR0 CONCERNING REACTOR SCRA". Oh LOSS OF AECM-87/0146 1R 67-6 3 CCN EN!D VACVUM.
1970475 0(/30/07 LER SUBMIT LER TO NRC CONCERNING SEVERAL DIV. 2 AUX BUILDING 07/30/07
-~
l AECM87/0142 1R87-64.
ISOLAi!0N VALVES STROIING SHVI.
10 70476 07/30/87
//
ROVilHE REPORI SUBMIT SEMI-ANNUAL REPORT 10 NRC COMFILING MONTHL) INTERNAL l'
AECM-87/2-000t NLSAF 2.4 ENVIRONMENTAL FROTECTION PROGRAM REPORIS.
10 61069 l.
l 07/30/87 07/15/07 LICENSE EXFIRAi!0N S','IMIT NOTICE Of 100FR55.55(a) OPERATOR LICEN!! EXFIRAi!0NS.
AECP47/0136 FMI-67/4517
-10 7050s
)
'07/31/67-05/15/!
LEE SU! Mil UFDATE LER 10 NRC CONCERNING M3ts EXCEEDING IRIP l
AECM 67/0:44 AECP87/00n LIMIT.
.!D 70200 07/31/8'
//
Sui".11 H 0! 00A".
SUBMIT REVI!!0N ( OF THE 0;AM TO THE HRC. THE SV!M!ilAL WA?
AECM-8?/0!?!
Nff. FEQUE!i dei.AYED FENDING ORGANIZATIONAL CHANi!! IN THE QA DEFARTMENT.
ID 70471 07/31/F7 07/15/67 0.A. REORGe.
SV!MIT TECH. SFEC. CHANGES FOR 0A REfRGANIZAl!0N.
AECM.4'/C:M -
00N"EF.W/NE ID 7C4D 0?/31/87 1E!
Oc./2t /CI 15 0FFSliE CHAF1 SUBMli AECM Oh 15 CHANG! 10 ORG612ATION CHAF1 TO NRO.
AECM-!?/C:!!
M.CfIFECTIVE 10 7044!
07/31/67 07/0!!07 V10LA1108 SV8MIT A RESPONSE 10 NSV C'-14 FAILUP.E 10 PROVID! AND AECM4?/014E MAE(47/Cle0
!MFLEMENT AN ADEQUATE FF0CENE! F0; SURVEILLANCE TESTING OF ID 704fC SLC.
08/06/67
//
FCOL-SM0!! DETECT SV6MIT i.S. CHANGE TO ADD / RELOCATE SM01E DETECT 0F3 TO COMFu AECM87/0139 NFE87/04 W!iN NFPA72E IB70436 0S/0(/07 05/04/67 TECH SPEC SUIMITPCOL10CHANGEISTABLE3.3.2-?,RHR/R0!CSTEAMllNE AECM87/0134 FMI87/2873 FLOWSETPOINT.
ID70453 08/06/87 05/29/f7 E.F.F. REYlSION SUBMil TO THE WRC A PROPOSED CHANGE 10 THE EFF 10 RESOLVE AECM87/0!?9 FMI47/
DISCFEFANCIES IN RECORD IEEPING REQUIREMENTS.
ID703??
lL i
)
e 9
FORECAST (NEXT 90 DAYS) l b_
. _ _ _ - _ _ - _ - _ _ _ _ _ = _ _ _ _ _ _ _ _ _ - _ _ _ _ -. _ _
1 4
MSALNUCLEAFLICENSING& SAFETY
' DATE: 08/06/67 ACil0NIFACXINGi;ANAGEMENTSYSTEM FORECASTMFilLICENSINGACTIVli!ES FAGE:
1
- ::: :: ::::: ::::::i ::::::::::.: - ::: ::::::::::: ::
SCHEDULED DATE NRC REQUEST DATE i
MFil 10 NUM RESPON!E Mill CORFES. NUM T0FIC OF !UBMillAL DESCRIPTION
)
NEEDEf TACNUMi!E I
08/10/07 07/21/f7 RELIEFREQUE!i SUEMIT REQUEST FOR RELIEF FROM THE ASME SECT, XI 1977 ID70513 FMI-87/G1 EDIl!0N. SUMMER 1979 ADDENDA, IABLE IND 25001, REGARDING i
I INSPECI!ONINTERVAL.
08/10/87
/ /
RE!!!! FE0 VEST SUBMIT REQUEST FOR RELIEF FROM ASME SEC. XI RE WIREMENTS 10 ID 70414 X
IN!FECT INTEGRAL WELDED ATTACHMENTS ON CLASS III COMFONENis l
EVERYFERIOD.
1 08/10/07 04/03/87 ATW!
SUBMITFCOLREQUESTINGI$CHANGESTOINCORFORATEATWSDESIGN 1D70340 AECM-E7/0055 08/11/87
/ /
SSWINSFECTION SUBMIT DOCUMENTATION OF AGRFEMENT 10 CHANGE COMMITMENT 10 10 70 M X
INFSECTFHRHEATEXCHAN!!RDURINGRF02.
OS/12/f' 07/29/P D0F-86/0044 SU!MIT TO NRC THE FROF0 SED REMOVAL OF THE 2 HOUR FIRE WALL 1070523 Mi!-t'/00d IN C0HTML BUILDIN^
08/14/07 07/28lF7 SLC!
SU!MIT ADDlil0NAL INf0RMATION RE00ESTEC FY NRC CONCEFNING 4
10 70525 MIHe/%M THE IN:FEASE IN THE SLCS RELIEF YALVE SEiF0!NT.
08/15/87 0'/l(/S.
LER SUEMil LER 10 HEC CONCERNING HFCS D/G AU10 START ON LOSS OF 1070!?'
IF E7 ' t llSh M ER SOUKE.
OS/Pl/EJ 03/13/P NUREG ll50 PR0 VIDE SER] COMMENTS ON DRAFT NURE6-ll50 10 THE NRC.
ID 70201 FED. REG.
4 08/22/0'
//
ff SU!M!i !! 10 N R CONCERNING DIY 11 D/G TRIF ON HIGH 10 70514
!! 0?-7-l?
YllRAi!M MING MONTHLY SURVEILLAN:L s
06/22/07 07/23/t?
LER SUIM11 LER TO NRC.CONCERNING TOTAL CORE FLOW EXCEEDING ID70520 IP 87-7-11 102.51WHILEUSINGTHEFLUXCONTROLLER.
l 08/2i./f7 04/07/87 AFF R ErCEP110NS SulMITREVISIONS/
SUMMARY
OFREVISIONS10THEAPFREXCEF110N l ID70277 AECM87/0073 REQUEST.
08/27/87
//
MAFFGAS/FROPOSAL SUBMIT FOLLOWUF SPECIAL REFORT RE: REPORTAllt!TY ID70491 X
DETERMINATIONOFMAPFGAS/FROFAMESTORAGEISSUE.
IY
RFLL NUCL!AF LICENSIN3 ( SACETY DATE: 03/0e/;'
ACTION TRACRING MAWAGEMEN! SYSTEM FORECA!I MFt'. LICENSING ACTIVli!ES FAGE:
....- : :::. : :. ::- -.~.::::..::::
SCHEDULEDDATE NR RE WEST DATE MFl! 10 N?
RESF0N!!
M'tt CORFES, NUM 10FIC 0F SUBMITTAt CESCRIFi!0N NEEDEE TA0 NUM!!F 08/26/67 06/30/6' LEF 66-020-0:
SUS":t LEF TO NR0 CONCERNIN3 FIFE FOULIN3 F.!SULTIN: IN LOW ID 7047' A!CM87/012e-FLOW 1 10 E!r ROOM COOLER! A C RELATED SSW C0N:!FNS 08/30/S?
//
EFFLUENTS SU!"li SEMIANNUAL EFFLUENT RELEASE REFORT 10 NRO.
1061340 N'SAF 2.4 08/31/87
//
FCOL-SRV.F.SW!iCH SUEMIT TO NRC A TECH SFEC CHANGE INYOLVING SRV TAIL FIFE ID 704!9 NFE87/04 SWITCH OUI 0F SERVICE TIMES.
08/31/67 07/26/07 ERO FGF SUBMIT REVISED FAGES 10 EF F6F BASED ON NRC CON ERENCE CALL IE 705:'
MtH?
F0F RESOLUTION 0: N;CCOMMENi!.
1 09/01/E7 04/20/$'
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SUEMIT
SUMMARY
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ACCM-67/000 FINALI?!D.
l 1
0;/0147 04/23/07 U2 C; EXTENSION SUBMIT INFORMATION R! U2 E0VIFMENT FFESEFVATION AND QUAllIV 10 7020; AECM67/2-00.
1 0' /07/f ?
07/H/0' IEE SUIMIT RESPONSE 10 ATWS REWEST FOR ACDITIONAL INFORMATION 10 7045' FM!-E7/40S!F:
RE: TESi!N2 0F 6ACLUF SCFAM VA'.YES 04/12/07
/ /
TEC-SSEC SUf"It FCOL F0F CHAN5! 10 CL AFIF1 WHICH 0!. C00. AFFLY 10 10 7045' N.C RER E51 WHICH TEM:: F0F SF TEMF. l.IMIi!
00/13/f?
07/13/07 FIFi WALL THINNIN3 SU!M!i INF0RMA110N CONCERNING FROGRAMF F0F MONIT0!!NG THE THICINESS OF FIFE WALLS IN HI6u ENEFEY SINE! FH:!! AO 10 10 704?c MAEC-8'/0le c
FHAFE CARBON S1 EEL FIFING.
10/13/07 03/1S/85 SALEM ATWS SUBMIT FLANT-SFECIFIC COMPARISON 10 NE00-30H4(TECH SPEC ID S0004 MAEC-85/00SS SURY. INTERNALS) WITHIN 90 DAYS OF NRC ISSUAkCE Of EVALVAi!0N.
10/30!$7
/ /
FUEL SUBMIT MATERIAL STATUS REFORT ON SNM DEFLETED U L NATURAL 10 e13!9 NLSAF 2.4 U 10 00E 11/01/87 10/03/W IE6 REFONSE SUBM!i REFORT CONCERNING HFCS AG RCIC VALVE TESTING FER ID 61225 AECM-86/02;l REQUIREMENTS OF IE6 86-03.
17
MP&L NUCLEAs LICENSING & SAFETY DATE: 08/06/87 ACTIONTRACl!NGMANAGEMENTSYSTEF FOR!CAS1 MP&L LICEN!!NG ACTIVlilES PAG!:
3 4
!CHEDULED DATE NRC REQUEST DATE MFil ID NUM RESPONSE ' Mf&L CORf.is. HUM 10PIC 0F SUBMITIAL DESCRIPTION NEEDED TAC NUMBER 09/12/87
//
TECHSPEC SU6MlfPCOLFORCHANGE10CLARIFYWHICH(P. CON: APPLY 10 1070*:5 MiC REQUEST WHICHTEMFS.FORSPTEMP. LIM 115.
09/13/F7
' 07/13/87 PIPE WALL THINNING SulMil INFORMATION CONCERNING PROGRAMS FOR MONITORING 1HE ID70479 MAEC-87/0160~
THICINESS OF PIPE WALLS IN HIGH ENERGY SINGLE PHASE AND TWO PHASE CARBON SIEEL PlP[NG.
10/13/87 03/15/85 SALEM ATWS SUBMil PLANT-SPECIFIC COMPARISON 10 NEDC-30844(TECH SPEC 10$0004 MAEC85/0088 SURY. INTERNALS)W!iHIN90DAYSOFNRCISSUANCEOF l
EVALUATION.
10/30/87
//
FUEL SU6MIT MATERIA'. STATUS REPORT ON SNM DEPLETED U & NATURAL 1061334 NLSAF?.4 U TO DOE.
11/01/87 10/03/So IES REPONSE SU6MIT REPORT CON 0ERNING HPCS AND ACIC VALVE TESTING PER 106122F AECM46/0241 P.!0'JIREMENTS OF IEE B6-03, i
f i
r
ENCLOSURE 3 Revision 1 8/6/87 RWCU CONTAINMENT ISOLATION ISSUE Corrective Action Plan A.
ACTIONS TO ADDRESS SPECIFIC RWCU CONTAINMENT ISOLATION ISSUE PLS
' i'. ' Monitor RWCU component and system performance CNGOING in PREPUMP mode (G33-F252, F253 closed).
RWCU pump seals
- Coolant chemistry PLS 2.
Monitor temperatures of containment penetration ONGOING i
affected by PREPUMP mode operations at RATED l
conditions.
NPE 3.
Identify likely options to correct divisional (Overall power supply concern for RWCU valves lead G33-F252 and G33-F253. Evaluate each option responsi-to support decision on corrective action, bility)
DOR, and schedule.
a.
OPTION 1.
Redefine containment isolation boundary to provide required single failure criteria.
PLS 1.
Review past LLRT data and practices COMPLETE for valves associated with affected penetrations (Nos. 87 and 366).
Based on' data, establish LLRT performance records for the valves or expectations if they should be subjected to LLRT.
PLS 2.
Evaluate system espability, COMPLETE required steps, required plant /
system conditions, etc. (overall work scope) that would be necessary to conduct LLRT of G33-F253.
NPE 3.
Determine work scope and schedule TBD required to establish piping run G33-F252 to F253 as "no break zone" piping.
hMEUNC GUY CESARE - 2
b.
OPTION 2.
Reverse divisional power supplies to F252 and F253.
NPE 1.
Evaluate workscope and schedule TBD l
required to design and implement DCP that would reverse divisional power supplies currently provided to F252 and F253.
B.
ROOT CAUSE ASSESSMENT l
NPE 1.
Establish chronology of key events 8/5 l
NPE 2.
Identify root cause(s).
8/5 NPE 3.
Establish and implement corrective actions 8/5 based on root cause identification.
ACTION IDENTIFIED TO DATE a.
Review of automatic containment 8/10 isolation valves for proper divisional power supply alignment b.
Review of RCPB automatic isolation valves for proper divisional power supply 8/14 C.
NRC INTERFACE / REPORTS PLS/
1.
Meeting ~ with NRC Resident, briefing on 8/6 NPE, NL Corrective Action Plan.
NL/NPE 2.
File LER on issue.
Include actions taken 8/26 to identify and address root cause(s) identified.
NPE 3.
Determine deportability of issue under Constrained 10CFR21.
by LER Safety Assessment NPE 4.
Determine appropriate notification 8/10 method to alert other BVRs of RWCU isolation issue (CE RICSIL, Nuclear Notepad, etc.).
D.
MISCELLANEOUS i
NL 1.
Advise other BWR/6 plants of the RWCU CIV COMPLETE issue and make preliminary assessments of applicability to these plants.
l NPE 2.
Develop action plan to investigate the viring 8/14 scheme of containment isolation valve "Out of Service" control room alarms to determine that the annunciators receive the correct signals.
2.
NMEUNC GUY CESARE - 3
l, l
NPE/NL 3.
Determine if inboard / outboard CIV divisional 8/7 pcwer supplies were intended to follow a certain general scheme'i.e., outboard on Division 1, inboard Division 2.
1 1
NL/NPE, 4.
Review TSAR /UFSAR descriptions of RWCU
.8/14 l
..related containment isolation provisions to confirm consistency with Technical Specifications and plant design documentation. Establish action plan to address any inconsistencies identified.
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