ML20235K598

Summary of 870915 Meeting W/Util & Southern Co Svcs in Atlanta Re Status of Plants Licensing Actions.List of Participants,Outline of Topics Discussed & Outstanding Licensee Submittals Requiring NRC Action Encl

ML20235K598
Person / Time
Site:	Hatch, Vogtle, 05000000
Issue date:	09/25/1987
From:	Mark Miller Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 8710050160
Download: ML20235K598 (26)

Text

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UNITED STATES

[\ ;A'gg NUCLEAR REGULATORY COMMISSION

'* W ASHINGTON, D. C. 20555

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\...../ SEP 2 51987

~ Docket Nos.: 50-321 50-366 50-424 LICENSEE: Georgia. Power Company FACILITY: Hatch Units 1 and 2 and Vogtle Unit 1

SUMMARY

OF MEETING HELD SEPTEMBER 15, 1987, TO DISCUSS STATUS OF HATCH AND V0GTLE LICENSING ACTIONS On September 15, 1987, the staff met with Georgia Power Company representatives at the licensee's offices in Atlanta to discuss the status of licensing actions and activities for both of the Hatch units and-Vogtle Unit

1. Participants are listed in Enclosure 1. Enclosure 2 outlines the topics discussed during the meeting.

The outstanding licensing submittals requiring NRC action are listed in Enclosure 3. Progress has been n.ade since the last meeting in reducing the backlog,-but there still are a number of items that require early NRC actions. A prioritized listing of those submittals considered most important by the lic nsee-is provided in Enclosure 3.

The two Hatch units have operated well during the past few months except for a flurry of trips at the end of July and in early August. Unit 1 experienced two trips, both due to equipment failures. Unit 2 also experienced two trips due to equipment problems and had to be shut down for several days in mid-August to reoair a leak in an unisolable instrument line. At the time of the meeting, both units were on line, Unit I at 100f power and Unit 2 at 90%

power. Unit 2 is being held at 90% to control excess airborne activity due to leaking pins and also to extend core life until the next outage, now scheduled to begin on January 13, 1988.

The licensee discussed the efforts underway at Plant Hatch to improve the balance of plant systems so as to reduce unnecessary challenges to safety systems. A special group at the plant is devoted to addmssing BOP issues. A recent NRC team inspection concentrated on B0P matters and was quite pleased with the licensee's efforts at improving BOP performance. Enclosure 4 is +he briefing slide used for this portion of the meeting.

The licensee is participating with the BWR Owners Group in the Technical Specification Improvement Program. There are 15 utilities involved in this effort and Hatch 2 has been selected as the lead BWR 4 plant. The BWROG expects to complete its topical report regarding the TS improvements in June of 1988 and the Hatch 2 submittal will follow NRC review of the topical.

Upgrading of the Hatch 1 TS will follow the effort on Unit 2. Details of the presentation on the TSIP are in Enclosures 5 and 6.

l 8710050160 870925 PDR ADOCK 05000321 P PDR ,

SEP 2 51987 After the initial difficulties with plant trips during the plant startup and test program, Vogtle Unit I has done well, with a capacity factor of more than 97% since August 1, 1987. The last plant trip occurred on July 28. Efforts are underway at improving the plant security program and the analysis and resolution of events at the plant. A twelve-day maintenance outage is scheduled to begin on October 9, 1987, during which the licensee will inspect snubbers and the turbine steam strainer. The first refueling outage for the plant no is projected to start on September 2, 1988. Enclosure 7 outlines the discussion topics regarding Vogtle and lists the outstanding licensing actions and submittals currently under staff review.

At the completion of the joint meeting, the Project Managers met individually with licensee and regional representatives to discuss the status of the Safety Issues Management Systems (SIMS) report that NRR is now in the process of trying to update.

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Melanie A. Miller, Project Manager Project Directorate 11-3 Division of Reactor Projects I/II

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Lawrence P. Crocker, Project Manager Project Directorate 11-3 Division of Reactor Projects I/II

Enclosures:

As stated cc: See next page M{hfD$kII MP/ 4 t6d/ rad PDII-3/DRPI/II LCrocker PDII- /URPI/II KJabpour 09/]S7 09/)N87 09/p/87 1

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.. 1 After'the initial difficulties with plant trips during the plant startup and test program, Vogtle Unit 1 has done well, with a capacity factor of more than 97%'since August I, 1987. The-last plant trip occurred on July 28. Efforts are underway at improving the plant security program and the analysis and resolution of events at the plant. A twelve-day maintenance outage is scheduled to begin on October 9, 1987, during which the licensee will inspect snubbers and the turbine steam strainer. The first refueling outage for the plant is projected to start on September 2,1988. Enclosure 7 outlines the discussion topics regarding Vogtle and lists the outstanding licensing actions and submittals currently under staff review.

At the completion of the joint meeting, the Project Managers met individually with licensee and regional representatives to discuss the status of the Safety l Issues Management Systems (SIMS) report that NRR is now in the process of trying to update.

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• Melanie A. Miller, Project Manager '

Project Directorate II-3 Division of Reactor Projects I/II onL Lawrence P. Crocker, Project Manager Project Directorate 11-3 Division of Reactor Projects I/II

Enclosures:

As stated cc: See next page

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c  : Enclosure 1 l

l Participants NRC GPC Leigh Trocine Jim Heidt John Rogge Steve Tipps Marvin Sinkule William Burns Melanie Miller Len Gucwa Lawrence Crocker Biff Bradley Ken McElroy R. D. Baker i

John Hartka Dave Smith Southern Company Services Ken Kopecky 9

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s-t NRC/GPC QUARTERLY MEETING l'0:00 Introduction

' 1 10:15 Plant Hatch Outstanding Submittals 10:30 Plant Hatch Status l 11:15 Plant Hatch Proactive Issues f o B0P Improvements o - Suppression Pool- Temperature {

12:00 Lunch

.l 1:00 Technical Specifications Improvement Program 1:30 Plant Vogtle Operating Status 1:45 Plant Vogtle Outage 2:00 Plant Vogtic Proactive Issues 2:30 Summary I

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ENCLOSURE 1 PLANT HATCH - UNITS 1~, 2 NRC DOCKETS 50-321, 50-366 OPERATING LICENSES DPR-57, NPF-5 0UTSTANDING LICENSING SUBHITTALS REOUIRING NRC ACTION i

LETTER HATCH DAIE D311 SUBJECT Key 0- APPROVAL OF ITEM REQUIRED FOR UPCOMING OUTAGE C- NRC ACTION COMPLETE ON ITEM SINCE LAST REPORT i N- ITEM ADDED SINCE LAST REPORT 05/13/85 321,366 REQUEST FOR ADDITIONAL INFORMATION - SEISMIC SPECTRA BROADENING 01/06/86 366 PROPOSED CHANGE TO TECHNICAL SPECIFICATIONS -

DELETE REQUIREMENT FOR HYDROGEN RECOMBINERS 02/17/86 331,366 C PROPOSED CHANGE TO TECHNICAL SPECIFICATIONS -

REORGANIZATION -- RESPONSIBILITY FOR RADIOLOGICAL ENVIRONMENTAL MONITORING, MET T0HER LOCATION, QA ,

RECORDS, DELETE EPDD, ETS PROCEDURE APPROVAL, j' PRB/ SRB COMPOSITION AND QUORUM, AUDIT REQUIREMENTS 02/28/86 321,366 PROPOSED LICENSE EXTENSION TO 40 YEARS FROM  ;

OPERATING LICENSE VICE CONSTRUCTION PERMIT 03/27/86 321,366 PROPOSED CHANGE TO TECHNICAL SPECIFICATIONS -

EQUALIZING REACTOR PROTECTION SYSTEM SPECIFICATIONS BETHEEN UNITS -i 03/31/86 321,366 C PROPOSED CHANGES TO TECHNICAL SPECIFICATIONS -

EMERGENCY P0HER - DIESEL GENERATOR TESTING -

. GENERIC LETTER 84-15 04/04/86 366 C PROPOSED DELETION OF BUILDING SETTLEMENT ,

TECHNICAL SPECIFICATIONS HITH INCORPORATION OF SETTLEMENT CRITERIA FROM OUR 12/1/78 LETTER INTO l

1 PLANT PROCEDURES l 08/25/86 321,366 C CHANGE TO RHCU LEAKAGE DETECTION TECHNICAL j SPECIFICATIONS - HIGH TEMPERATURE ISOLATION 1195C El-1 9/11/87  !

SL-3225 mm

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, Georgia Power d ENCLOSURE 1(Continued)

OUTSTANDING LICENSING SUBMITTALS LETTER HATCH DATJ UNil SUBJECT 09/09/86 '321,366 CHANGE TO TE HNICAL SPECIFICATIONS - RIVER LEVEL 10/24/86 321,366 PROPOSED TECHNICAL SPECIFICATION CHANGE FOR FIRE PROTECTION COMPLIANCE -

ADD REQUIREMENT OF PERFORMING EVERY THIRD TEST OF EQUIPMENT CONTROLLED FROM REMOTE SHUTDOHN PANELS FROM SAID PANELS 10/27/86 321,366 C PROPOSED REVISION TO TECHNICAL SPECIFICATIONS -

DELETION OF ORGANIZATIONAL FIGURES, REALIGNMENT OF HNP STRUCTURE 11/14/86 321,366 RESPONSE TO VERBAL REQlJEST FOR ADDITIONAL INFORMATION - CABLE TRAY SUPPORTS 12/23/86' 321,366- DETAILED CONTROL ROOM DESIGN REVIEW 02/13/87 321,366 REQUEST TO REVISE REPORTING REQUIREMENT TECHNICAL SPECIFICATIONS TO FIT LICENSEE EVENT REPORT REQUIREMENTS 03/04/87 321,366 REQUEST FOR ADDITIONAL INFORMATION - SEISMIC SOIL ANALYSIS 03/20/87 366 CHANGES TO TECHNICAL SPECIFICATIONS -

HYDROGEN HATER CHEMISTRY 03/27/87 321,366 C PROPOSED CHANGE TO TECHNICAL SPECIFICATIONS -

CORE SPRAY DELTA P (BREAK DETECTION) j INSTRUMENTATION 05/01/87 321,366 PROPOSED CHANGE TO TECHNICAL SPECIFICATIONS - l GASEOUS EFFLUENT RELEASE POINTS l 05/08/S7 366 C PROPOSED CHANGE TO TECHNICAL SPECIFICATIONS -

TURBINE VALVE TESTING l 7/13/87 321 PROPOSED CHANGE TO TECHNICAL SPECIFICATIONS -

ELECTRICAL SURVEILLANCE INTERVAL l

1195C El-2 9/11/87 SL-3225 700??$

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!. NiigggiaPowerd ENCLOSURE 2 PLANT HATCH - UNITS 1, 2 NRC DOCKETS 50-321, 50-366 ,

OPERATING LICENSES DPR-57, NPF-5 i OUTSTANDING LICENSING SUBMITTALS PRIORITIZED LIST REASON SUBJECT FOR PRIORITY

1. Operational Hardships PROPOSED CHANGE TO TECHNICAL SPECIFICATIONS -

GASEOUS EFFLUENT RELEASE POINTS

2. Hardware Installed CHANGES TO TECHNICAL SPECIFICATIONS -

HYDROGEN HATER CHEMISTRY g39 3. Piping Replaced with REQUEST TO RESCIND CONFIRMATORY ORDER ON Nuclear Grade Material REACTOR COOLANT SYSTEM STAINLESS STEEL PIPE

4. Unnecessary Plant PROPOSED CHANGE TO TECHNICAL SPECIFICATIONS -

Shutdown ELECTRICAL SURVEILLANCE INTERVAL

+ 5. Agreements with Union PROPOSED CHANGE TO TECHNICAL SPECIFICATIONS -

Imminent SHIFT OVERTIME REQUIREMENTS

6. NRC SER has been issued PROPOSED CHANGE TO TECHNICAL SPECIFICATIONS -  ;

on Generic Topical EQUALIZING REACTOR PROTECTION SYSTEM i Report SPECIFICATIONS BETHEEN UNITS

7. Preclude Potential CHANGE TO TECHNICAL SPECIFICATIONS - )

Future Problems RIVER LEVEL I

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1195C E2-1 9/11/87 SL-3225 I mm  ;

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. Georgia Power A ENCLOSURE 3 PLANT HATCH - UNITS 1, 2 NRC DOCKETS 50-321, 50-366

'0PERATING LICENSES'DPR-57, NPF-5 0UTSTANDING LICENSING SUBMITTALS REOUIRING ADDITIONAL INFORMATION LETTER HATCH DAIL UNII SUBJECT.

01/10/85 366 REQUEST TO RESCIND CONFIRMATORY ORDER ON REACTOR COOLANT SYSTEM STAINLESS STEEL PIPE 06/25/85 321,366 PROPOSED CHANGES TO IST PROGRAM 07/17/86 '321,366 REQUEST FOR ADDITIONAL INFORMATION REGARDING TECHNICAL SPECIFICATION AMENDMENT TO GASEOUS EFFLUENT RELEASE POINTS.

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• t t B0P IMPROVEMENTS o GOAL - REDUCE UNNECESSARY CHALLENGES TO SAFETY SYSTEMS o . AREA 0F INVESTIGATION - 80P EQUIPMENT TIED TO SAFETY SYSTEMS o' METHODOLOGY - RE-EXAMINE SYSTEM SAFETY DESIGN BASES DELETE OR MODIFY REQUIREMENTS BASED ON FINDINGS o EXAMPLES - TURBINE BUILDING TEMPERATURE SENSORS; CONDENSER VACUUM O

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l o PRESENT HATCH TECHNICAL SPECIFICATIONS:

o UNIT 1 i

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- CUSTOM FORMAT

- CONDITIONAL SURVEILLANCE

- 7 DAY A0Ts o UNIT 2

- STS FORMAT

- 3 DAY A0Ts o OPERATORS LICENSED ON BOTH UNITS I

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9 o NEW TECHNICAL SPECIFICATIONS o COMMISSION INTERIM POLICY STATEMENT

- CRITERIA FOR INCLU3 ION

- HUMAN FACTORS

- BASES o FINAL POLICY EXPECTED SOON

- NO MAJOR CHANGES 9

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1 o HATCH - 2 LEAD PLANT FOR BWR 4 o TOPICAL REPORT COMPLETE 6/88 o HATCH - 2 SUBMITTAL FOLLOWING NRC REVIEW HATCH - 1 SUBMITTAL SUBSEQUENT i

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1 o MAJOR ELEMENTS

- USER DEFINITION .

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- REDUCED SCOPE

- REDUCED INTERPRETATIONS

- BETTER OPERATOR TRAINING 1

1 STATUS:

o BWROG - 15 PARTICIPANTS IN HEW TS o PHASE 1 TOPICAL - NOVEMBER 1987 o PHASE 2 TOPICAL - JUNE 1988 o NUMARAC ISSUE

- COORDINATED PRODUCTS, SCHEDULES

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~~ - - - - - - - - . - _ _ , _ . _ _ _ _ _ _ _ _ _ . . __ _ _ _ _

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h BWROG RELIABILITY BASED IMPROVEMENTS

- RPS INSTRUMENTATION

- ECCS INSTRUMENTATION

- ISOLATION INSTRUMENTATION i

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TSIP KEY ELEMENTS o AD0PT NEH REDUCED SCOPE TECHNICAL SPECIFICATIONS UTILIZING BWROG/NRC CRITERIA HUMAN FACTORS IMPROVEMENT IMPROVED / MODERN BASES

.o INCORPORATE APPLICABLE PORTIONS OF BWROG IMPROVEMENTS REACTOR PROTECTION SYSTEM (RPS)

ECCS INSTRUMENTATION o INCORPORATE NEN BWR LOCA/ECCS MODEL SAFER /GESTR o UTILI2E NEH LOCA/ECCS MARGINS TO INCORPORATE  ;

EQUIPMENT-0UT-OF-SERVICE-PERFORMANCE IMPROVEMENTS i

o. UTILI2E HATCH - SPECIFIC RELIABILITY MODELS TO OPTIMIZE A0Ts, STIs ON ECCS - RELATED MECHANICAL EQUIPMENT ENCHANCE PLANT SAFETY AND OPERATION l

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l' TSIP - SAFER /GESTR SAFER /GESTR ANALYSES SUPPORT o NEW PLANT HATCH LICENSING BASES AT UPRATED POWER o SUBSTANTIAL IMPROVEMENTS / RELAXATION IN EQUIPMENT / SYSTEM' PERFORMANCE REQUIREMENTS D/G START TIME PUMP FLOW RATES VALVE STR0KE TIMES' INSTRUMENTATION SETPOINTS o SUFFICIENT MARGIN REMAINING FOR FUTURE PLANT PERFORMANCE-IMPROVEMENTS AND SELECTED EQUIPMENT OUT-0F-SERVICE-STATUS:

- NEH PLANT LICENSING BASES HILL BE-SUBMITTED 9/30/87, INCLUDING SELECTED RELAXED PERFORMANCE REQUIREMENTS OTHER RELAXATIONS AND E00S ANALYSES TO BE SUBMITTED IN EARLY 1988 l

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GKM - 2 I

.c TSIP - RELIABILITY ANALYSES..

o HATCH - SPECIFIC EPRI PROJECT (RELIABILITY - BASED) TO JUSTIFY. CHANGES IN A0Ts AND STIs

- HPCI RCIC

- LPCI RHR (CONTAINMENT COOLING H0DE)

RHRSH AND PSH D/G o ~MODELS IN PLACE TO QUANTIFY RELIABILITY OF " HATER INJECTION" FUNCTION (LEVEL 1 PRA)

METHODOLOGY /MODELS SIMILAR TO BWROG HORK ON RPS AND ECCS INSTRUMENTATION MAY " TRADE OFF" A0Ts AND STIs ON ECCS - RELATED MECHANICAL

' EQUIPMENT STATUS:

- SENSITIVITY STUDIES BEING PERFORMED

- PROGRAM COMPLETE BY 12-87 GKM - 3

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bekwe 7 PLANT V0GTLE PERFORMANCE O CAPACITY FACTOR GREATER THAN 97% SINCE AUGUST 1

-0 LAST REACTOR TRIP OCCURRED JULY 28. 1987 J 0 PROGRAM IMPROVEMENTS IN SECURITY 0 PROGRAM IMPROVEMENTS IN EVENT ANALYSIS AND RESOLUTION W_____-_-__-______-_ - - _ - - -

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L-PLANNED PLANT OUTAGES 0 FALL MAINTENANCE / TESTING OUTAGE

- OCTOBER 9, 1987 START DATE

- PROJECTED 12 DAY DURATION

- SNUBBER INSPECTION

- TURBINE STEAM STRAINER

- INTERIM ACCESS PLAN 0 FIRST REFUELING OUTAGE

- SEPTEMBER 2, 1988. START DATE

- 6 WEEK DURATION

- REFUEL ATWS/AMSAC

- RELOAD TECHNICAL SPECIFICATION PACKAGE 0518M-

l LICENSING ACTION ITEMS 0 INORGANIC ZINC C0ATING OF DIESEL FUEL TANKS 0 ALTERNATE RADWASTE FACILITY 0 CRDR EVALUATION 0 STEAM GENERATOR TUBE RUPTURE o RFAI ISI O RFAI SETTLEMENT MONITORING PROGRAM REVISION O RFAI IMPLEMENTING STATUS REPORT 0 ATWS/AMSAC 0 IER 87-26 AND 87-50 SECURITY ENFORCEMENT ACTION 0 IER 87-31 AND 87-37 OPERATIONS ENFORCEMENT ACTION 0 IER 87-44 IMPROPER MODIFICATION OF AUXILIARY BUILDING HVAC 0 SIX POTENTIAL LICENSEE EVENT REPORTS -

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SUBMITTALS PENDING REVlEW 0 CHLORINE MONITOR SETPOINT TECHNICAL SPECIFICATION O FUEL HANDLING BUILDING VENTILATION LC0 0 SEISMIC DESIGN OF'SPES'T' FUEL RACKS J _f a t.

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g Mr. James P. O'Reilly Edwin I. Hatch Nuclear Plant, Georgia Power Company Units Nos. I and 2 cc:

' G. .F. Trowbridge, Esq.

Shaw, Pittman, Potts and Trowbridge 2300. N Street , N. W.

Washington,.D.C. 20037 Mr. L. T.'Gucwa Engineering Department Georgia Power Company P. O. Box 4545 Atlanta, Georgia 30302 Nuclear Safety and Compliance Manager <

Edwin 1. Hatch Nuclear Plant Georgia Power Company P. 0. Box 442 Baxley, Georgia 31513 Mr. Louis B. Long.

Southern Company Services,-Inc.

P. 0. Box 2625 Birmingham,. Alabama 35202 Resident Inspector .i U.S. Nuclear Regulatory Comission Route 1, Box 725 Baxley, Georgia 31513 Regional Administrator, Region 11 j U.S. Nuclear Regulatory Commission 101 Marietta Street, Suite 2900 Atlanta, Georiga 30323 Mr. Charles H. Badger Office of Planning and Budget' Room 610 270 Washington Street, S.W. 3 Atlanta, Georgia 30334 Mr. J. Leonard Ledbetter, Commissioner Department of Natural Resources 270 Washington Street, N.W.

• Atlanta, Georgia 30334 Chairman Appling County Commissioners County Courthouse Baxley, Georgia 31513

. 1 Mr. J. P. O'Reilly.

a. Georgia Power Company _ Vogtle Electric Generating Plant cc:

Mr. L. T. Gucwa Resident Inspector

-  ; Chief. Nuclear Engineer- Nuclear Regulatory Comission.

Georgia Power Company P. O. Box 572

.P.O. Box-4545 Waynesboro, Georgia 30830 Atlanta, Georgia 30302 Mr.~ Ruble A.. Thomas Deppish Kirkland, III, Counsel Vice President - Licensing Office of the Consumers' Utility

'Vogtle' Project Council Georgia Power Company / Suite 225 Southern Company Services, Inc. 32 Peachtree Street, N.W.

P.O. Box 2625 Atlantc, Georgia .30303 Birmingham, Alabama 35202 James E. Joiner Mr. Paul D. Rice Troutman, Sanders, Lockerman, Vice President & Project General Manager & Ashmore Georgia Power Company Candler Building Post Office Box 299A, Route 2 127 Peachtree Street, N.E.

Waynesboro, Georgia 30830 Atlanta, Georgia 30303 Danny Feig Mr. J. A. Bailey 1130 Alta Avenue Project Licensing Manager Atlanta, Georgia 30307 Southern Company Services, Inc.

P.O. Box 2625 Carol Stangler Birmingham, Alabama 35202 Georgians Against Nuclear Energy 425 Euclid Terrace Ernest L. Blake, Jr. Atlanta, Georgia 30307 Bruce W. Churchill, Esq.

Shaw, Pittman, Potts and Trowbridge 2300 N Street, N. W.

. Washington, D. C. 20037 Mr. G. Bockhold, Jr.

Vogtle Plant Manager Georgia Power Company Route 2, Box 299-A Waynesboro, Georgia 30830 Regional Administrator, Region II U.S. Nuclear Regulatory Comission 101 Marietta Street, N.W., Suite 2900 Atlanta, Georgia 30323 Mr. R. E. Conway Senior Vice President and Project Director Georgia Power Company Rt. 2. P. O. Bcx 299A Waynesboro, Georgia 30830

MEETING

SUMMARY

DISTRIBUTION PLD6ckeiFile. SEP 2 51987 NRC Participants NRC PDR M. Miller L PDR L. Crocker NSIC PRC System PD#11-3 Rdg M. Duncan B. Kolostyak W. Troskoski (MNBB 6113)

OGC-Bethesda .

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