ML20154E616

Summary of 880815 Meeting W/Util Re Plans for Third Refueling Outage.Major Activities During Outage Include: Chemical Cleaning of Standby Svc Water Sys,Low Pressure Turbine Insp & Inservice Insp of RCS

ML20154E616
Person / Time
Site:	Grand Gulf
Issue date:	09/14/1988
From:	Kintner L Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 8809190075
Download: ML20154E616 (19)

Text

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Docket No. 50-416 September 14, 1988 DISTRIBUTION 5ee next page LICENSEE: System Energy Resources, Inc.

FACILITY: Grand Gulf Nuclear Station, Unit 1

SUMMARY

OF AUGUST 15, 1988 HEETING REGARDING THE THIRD REFUELING OUTAGE The purpose of the meeting was to present plans for tne third refueling outage to management of the NRC, Division of Reactor Projects I/II. Attendees are listed in Enclosure 1. Enclosure 2 is a handout prepared by the licensee. The licensee stated that morale of the enerating organization is good. There is very low turnover and no union problems. System Energy Resources, Inc., has initiated random testing of plant personnel for drugs.

The licensee said its goal for the third refueling outage (RF03) was to complete the outage in 45 days while minimizing radiation exposure of personnel and reportable events, such as actuation of engineered safety features. An outage director has been put in charge of preoutage planning and coordination of outage activities. Administrative controls will be used to conduct the outage in a prudent manner. (See Sheets 3 and 4 of Enclosure 2).

A schedule of preoutage activities is shown on Sheet 5 of Enclosure 2 and a schedule of outage activities is shown on sheet 8A of Enclosure 2. A feature of the outage planning is the designation of the availability of emergency core coolaing system components and shutdown cooling systems. (Top of Sheet 8A). Components designated as "functional" are available within a short time interval while others not designated are either operating or operable.

"Functional" means they can perform their function after simple operations, like closing a breaker or opening a valve.

Major activities during the outage will include chemical cleaning of the standby service water system, a low pressure turbine inspection, inservice inspection of the reactor coolant system, removal of the remainder of the sensors used in the startup test of reactor core internals vibration, and inspsction of the Division I T0! diesel generator. During the first part of the outage, a new system for reroval of decay heat heat during outages will be installed. This alternative decay heat removal (ADHR) system will use two pumps and two heat exchangers purchased for the Grand Gulf Nuclear Station.

Unit 2 spent fuel pool cooling system. The ADHR will be installed in the residual heat removal (RHR) "C" pump room and will take suction from the RHR comon suction line and discharge to the low pressure coolant injection system line.

Technical Specification changes are grouped ur. der two headings on Sheet 9 of Enclosure 2. Those listed under "Outage Assumption" were assumed to be approv-ed in planning the outage schedule; and, therefore, the licensee considers them to have high priority. As of the date of this summary preparation, Items A, 8. E. F and G have been submitted.

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i The reload amendment was discussed with the staff on July 28, 1988; and a  !

December 9, 1988 submittal date was agreed to by the staff. Technical  !

j Specification changes listed under "Outage Centingencies/ Improvements" are  !

given a lower priority by the licensee. Items A, B and C have been submitted.

In response to a staff question, the licensee said that the noise detected in  !

the "B" recirculation loop will be investigated during the outage. If the [

noise is found to come from the recirculation flow control valve, as expected, l

. there will be no impact on the outage schedule. However, if the noise comes from the discharge valve, repairs may impact restart. >

/s Lester L. Kintner, Senior Project Manager [

l Project Directorate II-1 Division of Reactor Projects I/II ,

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Enclosures:

l As stated cc w/ enc 1s: ,

See attached list l l

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DATE:943/88 :9/i3/08  :  :  : ___

OFFICIAL RE:dRD COPY

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• DISTRIBUTION FOR MEETING

SUMMARY

DATED: September 14, 1988 Fa ci lity: GRAND GULF UNIT 1 C.M$2 NRC POR Local POR POII-l Reading S. Yarga (14E4)

G. Lainas E. Adensam P. Anderson ProjectManager OGC E. Jordan (HNBB 3302)

8. Grimes (9A2)

NRC Participants ACRS (10)

8. Troskoski (17019) cc: Licensee / Applicant Service List t

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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. McGenee, Esquire The Honorable William J. Guste, Jr.

Wise, Carter, Child, Steen and Caraway Attorney General P.O. Box 651 Department of Justice Jackson, Mississippi 39205 State of Louisiana Baton Rouge, Louisiana 70804 Nichclas S. Reynolds, Esquire Bishop. Liberman, Cook, Purcell Office of the Governor and Reynolds State of Mississippi 1400 L Street, N.W. Jackson, Mississippi 39201 Wasnington, D. C. 20005-3502 Attorney General Mr. Ralph T. Lally Gartin Building Managur of Quality Assurance Jackson, Mississippi 39205 Middle South Utilities System Services, Inc.

639 Loyola Avenue, 3rd Floor Mr. Jack McMillan, Director New Orleans, Louisiana 70113 Division of Solid Waste Management Mississippi Department of Natural Mr. John G. Cesare Resources Director, Nuclear Licensing Post Office Box 10385 System Energy Resources, Inc. Jackson, Mississippi 39209 P.O. Box 23054 Jackson, Mississippi 39205 Alton 8. Cobb, M.D.

State Health Officer Mr. C. 8. Hogg, Project Manager State Board of Health Bechtel Power Corporation P.O. Box 1700 P. O. Box 2166 Jackson, Mississippi 39205 Houston, Texas 77252-2166 President Mr. Ross C. Butcher Claiborne County Board of Supervisors Senior Rasident Inspector Port Gibson, Mississippi 39150 U. S. Nuclear Regulatory Commission Route 2, Box 399 Regional Administrator, Region !!

Port Gibson, Mississippi 39150 U. S. Nuclear Regulatory Commission 101 Marietta Street Mr. William T. Cottle Suite 2900 GGNS Site Director Atlanta, Georgia 30323 System Energy Resources, Inc.

P.O. Box 756 Port Gibson, Mississippi 39150

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. ENCLOSUPE 1 ATTENDEES AUGUST 15, 1988 MEETING NRC--SERI NAME AFFILIATION L. L. Kintner NRC, Project Manager for GGNS E. Adensam NRC, Director, Project Directorate !!-1 G. Lainas NRC, Assistant Director, for Region !! Reactors S. Varga NRC, Director, Division of Reactor Projects 1/I!

0. O. Kingsley SERI, Vice President, Nuclear Operations W. T. Cottle SERI. Site Director, GGNS-1 C. R. Hutchison SERI, General Manager, GGNS-1 F. W. Titus 3ERI, Director Nuclear Engineering Dept.

J. G. Cesare SERI, Director Licensing J. D. Fowler SERI, Licensing Department J. K. Fortenberry SERI, Licensing Department

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Enclosure 2 SERI/NRC BRIEFING ON GRAND GULF NUCLEAR STATION REFUELING OUTAGE 03 AUGUST 15, 1988 ROCKVILLE, MARYLAND l

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AGENDA I. INTRODUCTION 0. D. KINGSLEY, JR.

!!. RF03 GOALS & OBJECTIVES W. T. COTTLE

!!!. SERI OUTAGE PHILOSOPHY W. T. COTILE IV. PRE-0UTAGE MILESTONE DATES C. R. HUTcHINSON V. OVERVIEW OF RF03 ScHEUDLE & C. R. HUTcHINSON WORK EFFORT VI. LICENSING SUPPORT ACTIVITIES J. G. CESARE VII. ALTERNATE DECAY HEAT REMOVAL F. W. TITUS SYSTEM OVERVIEW VIII.

SUMMARY

0. D. KINGSLEY, JR.

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, ..e, RF03 G0ALS & OBJECTIVES OBJECTIVE: SAFE EXECUTION OF OUTAGE ,

G0ALS: 0 MINIMlZE COLLECTIVE EXPOSURE O MINIMlZE INCIDENTS 0 MINIMlZE PERSONNEL ERRORS OBJECTIVE: BETTER CONTROL OF WORK G0ALS: 0 OUTAGE DURATION OF 45 DAYS OR LESS 0 OUTAGE COMPLETED WITHIN THE ESTABLISHED BUDGET OBJECTIVE: PREPARE UNIT FOR CYCLE 4 OPERATION G0ALS: O COMPLETE ALL MAJOR MAINTENANCE ITEMS 0 COMPLETE LICENSING IMPROVEMENTS l

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SERI OUTAGE PHILOSOPHY 0 CRITICAL PATH CONTROLLED BY:

REFUELING SURVEILLANCE MAJOR MAINTENANCE l!CENS!NG IMPROVEMENTS RECOVERY PERIOD 0 CONDUCT a MANAGE REFUELING OUTAGES IN A SAFE AND PRUDENT MANNER ONE ECCS & ONE FUEL POOL COOLING SUBSYSTEM FUNCTIONAL AT ALL TIMES ONE SHUTDOWN COOLING SUBSYSTEM OF RHR FUNCTIONAL AT ALL TIMES (EXCEPT FOR PERIODS OF REQUIRED MAINTENANCE OR TESTING)

THE DIESEL / GENERATOR ASSOCIATED WITH THE REQUIRED ECCS, FUEL POOL COOLING, AND SHUTDOWN COOLING SUBSYSTEMS P"*T BE FUNCTIONAL ALTERNATE COOLING METHODS ARE DEMONSTRATED AS CAPABLE OF REMOV!NG DECAY HEAT PRIOR TO BEING DECLARED AS AN ALTERNATE MODE STATUS BOARD IS PROVIDED IN THE CONTROL ROOM l

WHICH CLEARLY INDICATES THE OPERABLE ECCS SYSTEMS, THE SHUTDOWN COOLING MODE BEING UTILIZED J

AND THE STATUS OFF ALL SYSTEMS WHICH COULD CAUSE INADVERTENT VESSEL DRAINING SPECIAL CONTROLS ESTABLISHED TO REQUIRE THE REFUELING FLOOR COORDINATOR AND THE SH!FT SUPERINTENDENT TO APPROVE MAN!PULATION OF ALL VALVES WHICH COULD DRAIN THE VESSEL WHILE THE VESSEL HEAD IS DETENSIONED 3

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SERI OUTAGE PHILOSOPHY (CONT'D)  ;

TRAINING PROVIDED TO ALL OPERATIONS SHIFT 5 AND REFUELING FLOOR COORDINATOR DISCUSSING THE TIME TO DRAIN THE VESSEL, POTENTIAL CONSEQUENCES, RESPONSIBILITIES FOR APPROVAL OF VALVE MAN!PULATIONS WHICH COULD CAUSE INADVERTENT DRAINING, AND CONTINGENCY PLANNING.

ALL TAG-0VTS ARE SCREENED AND CONTROLLED BY THE TAG-0VT COORDINATOR.

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, .. a PRE-0UTAGE MILESTONE DATES ESTABLISH PRE-0UTAGE PLANS AND FEBRUARY 29, 1988 ORGANIZATION ,

COMPLETED RF02 CRIT!QUE MARCH 9, 1988 MARCH 31, 1988 IDENTIFY TECH SPEC CHANGES ISSUED PRELIMINARY MILESTONE SCHEDULE APRIL 1, 1988 APRIL 15, 1988 IDENTIFY MAJOR RF03 DCPS .

JUNE 20, 1988 FREEZE DESIGN SCOPE ALL DISCIPLINES PROVIDE OUTAGE SCOPE ONGOING AND IMPACT OCTOBER 1, 1988

FREEZE RF03 MAINTENANCE SCOPE 1

' DECEMBER 2, 1988  :

ESTABLISH OUTAGE ORGANIZATION JANUARY 3, 1989 CYCLE 4 FUEL RECEIPT MAF.CH 1, 1989 RF03 PROJECTED START DATE

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RF03 OUTAGE SCHEDULE OVERVIEW o PROJECTED START DATE: 3/1/89 3

o PROJECTED OUTAGE DURATION: 42-45 DAYS L

o NUMBER OF MODIFICATIONS (DCPs) 81 ,

(CURRENTLY) ,

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o LICENSING MAJOR TASKS 25 j l o MAJOR PLANT / AVAILABILITY / RELIABILITY / 22 ALARA MODIFICATIONS i

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RF03 MAJOR OUTAGE ACTIVITIES l

o REFUELING FUEL SHUFFLE VIBRATION MONITORING REMOVAL HORIZONTAL FUEL TRANSFER SYSTEM UPGRADE O SURVEILLANCE INTEGRATED LEAK RATE TESTS DRYWELL BYPASS TEST EMERGENCY CORE COOLING SYSTEM TESTING LOCAL LEAK RATE TESTS PREVENTATIVE MAINTENANCE O MAJOR MAINTENANCE STANDBY SERVICE WATER 'B' CHEMICAL CLEANING STANDBY SERVICE WATER VENT AND DRAIN P! PING

• REPLACEMENT O PLANT MODIFICATIONS ALTERNATE DECAY HEAT REMOVAL SYSTEM PARALLEL POWER SUPPLY FOR SCRAM SOLENOIDS TURBINE CONTROL MODIFICATIONS 0 LICENSING RELATED ISSUES LOW PRESSURE TURBINE INSPECTION FEEDWATER N0ZZLE INSPECTION 7

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TYPICAL REFUELING OUTAGE WORK I. MAINTENANCE WORK ORDERS 0 MECHANICAL 1430 0 ELECTRICAL 343 0 INSTRUMENTAT!ON & CONTROLS 551

!!. PREVENTATIVE MAINTENANCE ,

O MECHANICAL 750 0 ELECTRICAL 888 0 INSTRUMENTATION & CONTROLS 2150

!!!. SURVEILLANCE O MECHANICAL 37 0 ELECTRICAL 60 O INSTRUMENTATION & CONTROLS 473 0 OPERATIONS 72 0 LOCAL LEAK RATE TESTS 445 i

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5 GRAND GULF NUCLEAR STATION .

RF03 SCHEDULE MARCH 1989 APRL 1989 1 2 3 4 5 6 7 8 9 10 11 12 13 1 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 1-ECCS/SDC AVALABLITY ECCS AvaLABLITY O O. G G LPCI T LPCS LPO A & LPCS FUNC , ,

LPQ T FUNCTIONAL PJTDOWN COOLNG

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G C pm B SDC RUNNING N FPC & 6--RHR A@ RHR A & Rm B Rm A FUNCTM *

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Rm 8 TO CAVITY RHR A & ADMS "RHR A ft B FUNC 2-MLESTOMS A A A A A A RX PWR 5% T/G FLOOD CAvf1Y CAVITY DRAIN ROOO CAVITY WODE 4 WODE 2 W WE A A A MODE 4 A CAVITY DRAIN SYNCMONIZATION MODE 5 3-OUTACE CRITICAL PATH SCEDLLE N . . . . . .

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VES$8. INSASSEMBLYT I ED/VIBRADON REMOVAL [ VESSEL REASSEMBLY CeS moRO _y I

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FUEL SHUFRE TEM LRT/DW BW i LINEUPS / PREP Dc/RHR k-, g FOR S/U a a ^ 1 l I GPt 1 T I DN II ECCS+ - - - {^ DNl BUS I ECCS TESg A _ JEST t OUTAGE  :

I DN 1 D/G MANT/ RETEST " ' T(HR 8 MA!NT/LLRT" I

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& d TURBME MANTENANCE 0-OUTAGE WORK PATH ______

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DtSASSEnELY REPAIR RECOVERY

BF03 TECHNICAL SPECIFICATION CHANGES COMMITTED ISSUE NRC NEED DATE SUBMITTAL DATE I. OUTAGE ASSUMPTiqNJ A. GENERIC LETTER 87-09 CHANGES 2/1/89 8/19/88 B. SEPARATE 24 HOUR DIESEL RUN FROM 2/1/89 '7/26/88 LOAD SEQUENCING TEST C. ALTERNATE DECAY HEAT REMOVAL 2/1/89 9/2/88 SYSTEM TECHNICAL SPECIFICATION CHANGES D. RELOAD LICENSE AMENDMENT 3/1/89 12/9/88 E. WIDE RANGE MON!TORING SYSTEM 3/1/89 '7/1/88 DEFERRAL J

, F. LOWER DOWNTRAVEL CUTOFF ON MAIN 3/1/89 8/19/88 HOIST G. DELETE LOCAL LEAK RATE TESTING 1/1/89 8/31/88 0F TEST CONNECT!ONS t

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II. OUTAGE CONTINGENCIES / IMPROVEMENTS A. REACTOR PROTECTION SYSTEM 1/1/89 '6/30/88

! SURVE!LLANCE INTERVAL AND ALLOWED OUTAGE TIME EXTENSION i B. DELETE TRANSFER CANAL GATE 3/1/89 8/31/88 FROM FOOTNOTE l

C. DELETE SNUBBER REJECT REGION 3/1/89 '7/25/88 l

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ALTERNATE DECAY HEAT REMOVAL SYSTEM o OBJECTIVE P ALTERNATE DECAY HEAT REMOVAL CAPABILITY BY DAY 13 0F RF03 ALTERNATE DECAY HEAT REMOVAL CAPABILITY AVAILABLE DAY l 0F FUTURE OUTAGES INDEPENDENT SUCTION PATH IN ADDITION TO RHR COMMON

SUCTION LINE O APPRCACH DEDICATED DESIGN TEAM

- POTENTIAL ALTERNATIVES EVALUATED DETAILED REVIEW OF CONCEPTUAL DESIGN FINALIZE DESIGN CONCEPT 0 DESIGN CONCEPT l -

INSTALL NEW PUMPS AND HEAT ExCHANGERS IN RHR "C" PUMP r

ROOM s

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UTILIZE ExtSTING FPCCU P! PING TO RHR COMMON SUCTION

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DISCHARGE VIA LPCI "C" INJECTION LINE f I O SCOPE OF DESIGN  :

1000 FT LARGE PIPE i

300 FT SMALL PIPE 20 LARGE VALVES 3

2 - 1800 GPM PUMPS (UNIT 2 FPCCU) t -

2 HEAT ExCHANGERS (UNIT 2 FPCCU) ,

2500 FT ELECTRICAL CONDU!T i

350 FT LEAD WRAP SHIELDING 50 LARGE P!PE SUPPORTS 10 TON ROOM COOLER i -

PROCESS RADIATION MONITOR i 10 '

ALTERNATE DECAY HEAT REMOVAL SYSTEM (CONT'D) o SYSTEM DESIGN FEATURES / CAPABILITY

- PRIMARY SYSTEM COMPONENTS ARE ASME SECTION lil, SE!SMIC CATEGORY l ADHRS HEAT REMOVE CAPABILITY IS APPROXIMATELY 3 TIMES CURRENT ALTERNATE CAPACITY 0 SYSTEM BENEFITS RF03: 13 DAYS DUE TO EARLIER START DATE FOR V!BRATION INSTRUMENTATION REMOVAL AND RHR I COMMON SUCTION WORK FUTURE OUTAGES: 10 DAYS DUE TO EARLIER START DATE FOR RHR COMMON SUCTION WORK ADDITIONAL ALTERNATE DECAY HEAT REMOVAL CAPABILITY l

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