ML20235F416

Summary of 870602 Mgt Site Visit W/Licensee Re Licensing Actions,Including Second Refueling Outage.List of Attendees, Agenda & Licensee Handout Encl

ML20235F416
Person / Time
Site:	Grand Gulf
Issue date:	06/29/1987
From:	Kintner L Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 8707130373
Download: ML20235F416 (34)

Text

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June 29,1987 Docket No. 50-416 DISTRIBUTION

'6 J. Partlow NRC PDR" ACRS (10)

LICENSEE: System Energy Resources, Inc. Local PDR B. Troskoski PD22 Rdg. R. Butcher FACILITY: Grand Gulf Nuclear Station, Unit 1 L. Rubenstein L. Kintner

SUMMARY

OF JUNE 2, 1987 NRC PROJECT OGC-Bethesda DIRECTORATE-II-2 MANAGEMENT SITE VISIT E. Jordan The NRC Director of Project Directorate-II-2, L.S. Rubenstein, and the NRC Pro-ject Manager, L.L. Kintner met with the licensee's Vice President, Nuclear j Operations, 0.D. Kingsley, Jr. the Vice President, Nuclear Engineering and Support T. H. Cloninger, and the Director of Nuclear Licensing, J. G. Cesare, to discuss licensing actions, including the second refueling outage and to tour the facility. The NRC Senior Resident Inspector, Ross Butcher, participated in the meeting and tour. Enclosure 1 is a list of meeting participants, and Enclosure 2 is the agenda and handout prepared by the licensee.

l The licensee summarized the plant status (sheet 3 of Enclosure 2). The plant is operating at full power and has been in continuous operation since fuel cycle 2 started on January 6, 1987. In anticipation of continued good operation in the last half of fuel cycle 2, the start of refueling outage two (RF02) has i been changed from January 8,1988 to November 6,1987. Turnover of SERI person-nel has been low (6 0 .

The plant operation safety record is excellent - there have been 1.6 x 106man- <

hours worked without a lost time accident. In response to staff questions, I the licensee described specific goals in plant operation, using performance in-dicators recommended by INPO. Goals and performance are posted in the plant for employee's information. A monthly performance report is prepared to inform licensee management, including the President and CEO, of performance relative '

to goals. The table of contents and highlights from the April 1987 Report are reproduced in Enclosure 3.

The licensee briefed the staff on its plans for the second refueling outage (Enclosure 2, Sheets 4-21). The licensee's goal is to have the critical path for the outage controlled by refueling activities, normal surveillance and normal maintenance. Preliminary milestones for the outage were provided (Enclosure 4). The target outage time is 8 weeks. Sheet 11 is a list of re-quired licensing actions, which include: modifications resulting from the detailed control room design review (DCRDR); modifications required by the ATWS regulation-alternate rod insertion and standby liquid control system (SLCS);'

addition of containment isolation valves in six instrument lines; completion of the design review and quality revalidation (DR/QR) inspection of Division II hh Doh $ 6 P

(, -

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emergency diesel generator; inspection of one of the three low pressure main ,

steam turbines; about 770 surveillance tests; about 300 local leak rate tests (LLTRs); inservice inspection and inservice testing; and snubber inspection.

Refueling will include replacement of 1/3 of the fuel assemblies in the reactor core with new Exxon fuel assemblies. Other major activities will include: re-packing of about 340 valves and testing of 75 relief valves; preventative main-tenance; and maintenance work scheduled for the outage. 4 The licensee identified several areer which have a potential adverse impact on the outage schedule or manpower requirements including: installation of neutron flux monitors to meet Regulatory Guide 1.97 requirements; installation of Jon-tainment isolation valves for six instrument lines; and completion of DR/y. in-spections for the Division II emergency diesel generator. The impact on the RF02 outage schedule and justification for retief from the relevant regulatory requirements are provided in Sheets 17 through 21 of Enclosure 2.

The licensee also identified several propo' sod changes to Technical Specifict-tions based on experience gained in RF01. These proposed changes will be sub-mitted for NRC action prior to RF02 to facilitate the outage work (Sheet 15 of Enclosure 2). Two of the proposed changes were requested by the licensee's letter dated June 3,1987 and are undergoing review by the staff. Additional or potential changes to the Technical Specifications are indicated on Sheet 16 Enclosure 2. The licensee will perform a 10 CFR 50.59 safety analysis of the core reload to determine whether there is a need to submit it to the staff for approval. If necessary, it would be submitted in August 1987.

During routine reactor coolant sampling in May 1987, the licensee detected in-creased radioactivity in the reactor coolant (Sheet 22 of Enclosure 2). Reactor coolant dose equivalent iodine values are well below limits in the Technical Specifications. Radiation levels in the offgas charcoal vault increased from 80 mr/hr to 1500 mr/hr. Analysis of the data indicates that there is leakage from fuel having about 15,000 megawatt days per metric ton of uranium (MWD /MTU),

which is fuel that was initially loaded into the reactor. In addition to rou-tine monitoring of reactor coolant, offgas retreatment samples are taken daily and reactor coolant iodine samples are taken following substantial rates of power changes.

The tour of the plant included the control room, the containment upper level above the reactor, the spent fuel pool, portions of the auxiliary building and the turbine building. The areas toured were clean and freshly painted with few contaminated areas roped off. The plant was operating at 100% power. When en-tering containment, the inboard airlock door was stuck closed for several minutes. The licensee immediately informed plant management of the problem and appropriate maintenance personnel initiated corrective action.

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i Following the tour of the plant, the staff met briefly with the licensee. The staff expressed satisfaction with the meeting presentation and tour.

l L. L. Kintner, Project Manager ,

Project Directorate 11-2  !

Division of Reactor Projects-I/II j

Enclosures:

1. Attendance List

2. Agenda

3. Perfomance Monitoring  ;

Management Information l Program I

4. Preliminary Milestone  !

cc w/ enclosures:

See next page 2 II-2 'P : kN-2 er LKintner:bg LRubJnstein 6/ /87 6/tj/87 6/g/87 I

1 '. j 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. i System Energy Resources, Inc. Post Office Box 756 J 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 Jackson, Mississippi 39205 State of Louisiana Baton Rouge, Louisiana 70804 ,

Nicholas S. Reynolds, Esquire  !

Bishop, Liberman, Cook, Purcell Office of the Governor i and Reynolds State of Mississippi 1200 17th Street, N.W. Jackson, Mississippi 39201 l l

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 Licensing and Safety Bureau of Pollution Control System Energy Resources. Inc. Post Office Box 103B5 P.O. Box 23054 Jackson, Mississippi 39209 l Jackson, Mississippi 39205 -

Alton B. Cobb, M.D.

Mr. R. W. Jackson, Project Engineer State Health Officer Bechtel Power Corporation State Board of Health 15740 Shady Grove Road . P.O. Box 1700 Gaithersburg, Maryland 20B77-1454 Jackson, Mississippi 39205 Mr. Ross C. Butcher President Senior Resident Inspector Claiborne County Board of Supervisors U.S. Nuclear Regulatory Commission Port Gibson, Mississippi 39150 Route 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

Enclosure I '

NRC - SERI MEETING JUNE 2,.1987 AFFILIATION NAME NRC Ross Butcher NRC Senior Resident Inspector L. S. Rubenstein NRC Director, PDII-2 L. L. Kintner NRC Project Manager, PDII-2  :

SERI J. G. Cesare SERI Director, Nuclear Licensing O. D. Kingsley, Jr. SERI VP, Nuclear Operations  ;

M. L. Crawford SERI Supervisor, Licensing M. A. Krupa SERI Schedule Superintendent J. C. Roberts SERI Manager, Plant Modifications and Construction A. McCurdy SERI Manager, Operations W. R. Patterson SERI Reactor Engineering Supervisor - -

C. Tyrone Manager, Nuclear Services & Fuels -

J. E. Cross SERI Site Director -

J. L. Robertson SERI, Plant Licensing Superintendent J. Walker SERI, Nuclear Fuels Group B. Angle SERI, Manager Operational Analysis-NPE J. B. Lee SERI, Supervisor Nuclear Fuels Group R. S. Reynolds SERI, Nuclear Fuels Group T. H. Cloninger SERI, V. P. Nuclear Engineering & Support J. V. Parrish SERI, Chemistry / Radiation Control Superintendent

ENCL 3SURE 2 GRAND GULF NUCLEAR STATiDN SYSTEM ENERGY RESOURCES, INC.

MIDDLE SOUTH UTILITIES, INC.

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NRC MANAGEMENT SITE VISIT JUNE 2, 1987 i A .G E N D A

[NERGY SERVICES CENTER, CONFERENCE Room #1

1. INTRODUCTION / PURPOSE OF MEETING 0. D. KINGSLEY.

0900

11. GGNS PLANT STATUS A. S. McCURDY 0905 0915 III. BRIEFING ON SECOND REFUELING OUTAGE (RF02) l A. OUTAGE MANAGEMENT' APPROACH 0. D. KINGSLEY B. CRITIQUE OF RF01 J. E. CROSS

- C. CONDUCT OF RF02 J. E. CROSS D. LICENSING SUPPORT ACTIONS J. G. CESARE E. DISCUSSION /00ESTIONS SERl/NRC F. CONCLUSIONS / ACTION ITEMS 0. D. KINGSLEY 1145 IV. SPECIAE INTEREST ITEM - G. O. SMITH POTENTIAL FUEL PIN LEAKAGE J. V. PARRISH 1200 BREAK FOR LUNCH 1300 PLANT TOUR 0. D. KINGSLEY J. E. CROSS GGNS ADMINISTRATION BLDG., GENERAL MGR. CONFERENCE Room WRAP-UP/ ACTION ITEMS, IF ANY SERI/NRC 1500

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J16 MISC 87060102 - 1 , .

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1 ' INTRODUCTION O PURPOSE OF MEETING PLANT STATUS OVERVIEW OF SERI MANAGEMENT APPROACH TO OUTAGE j MANAGEMENT 4

ORGANIZATIONAL ASPECTS-PERTINENT TO OUTAGE  !

PLANNING a EXECUTION i

- CURRENT OUTAGE SCHEDULE, SCOPE, AND KEY WORK ITEMS LICENSING SUPPORT ACTIVITIES SERI ACTIONS AND NRC SUPPORT REQUESTED TO EXECUTE SUCCESSFUL OUTAGE FAMILIARIZATION OF NRC MANAGEMENT OFLCERTAIN ITEMS HAVING SIGNIFICANT IMPACT ON OUTAGE SCHEDULE / PERFORMANCE O OPPORTUNITY TO DISCUSS ITEMS OF INTEREST TO NRC POTENTIAL FUEL PIN LEAKAGE O PLANT TOUR 0 WRAP UP N

J16 MISC 87060102 - 2

11. PLANT STATUS

o CYCLE 2 COMMENCED JANUARY 6, 1987-0 PLANT PERFORMANCE, OVERALL.VERY Good CONTINUOUS OPERATIONS SINCE CYCLE 2 STARTUP

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o CLoSE MONITORING OF PLANT THERMAL EFFICIENCY, CORRECTIVE ACTIONS TAKEN AS PRACTICAL o PLANT PERFORMANCE REQUIRED RE-REVIEW OF OUTAGE SCHEDULE o REVISED OUTAGE SCHEDULE, ACCELERATED START DATE OF NOVEMBER'6 O

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III. BRIEFING ON SECOND REFUELING OUTAGE (RF02) _

A. OUTAGE MANAGEMENT APPROACH 0 ORGANIZATION 1

MANAGEMENT REVIEW BOARD (MRB)

MRB ADVISORY COUNCIL NUCLEAR PLANT ENGINEERING NUCLEAR LICENSING PROCUREMENT PLANT STAFF PLANT MODIFICATION AND CONSTRUCTION O CRITICAL PATH CONTROLLED BY: I REFUELING SURVEILLANCE MAINTENANCE EXCEPT FOR SUBSTANTIAL SAFETY ISSUES O OUTAGE GOAL OF 8 WEEKS 1

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I MANAGEMENT REVIEW BOARD O MEMBERS l l

V. P., NUCLEAR OPERATIONS l k

V. P., NUCLEAR ENGINEERING AND SUPPORT SITE DIRECTOR  !

GENERAL MANAGER l

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- DIRECTOR, NUCLEAR PLANT ENGINEERING '

- DIRECTOR, NUCLEAR LICENSING

- PANAGER, UNIT 1 PROJECTS 0 DEFINE, REVIEW, AND APPROVE SIGNIFICANT WORK ACTIVITIES 1

NRC REQUIREMENTS )

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PLANT BETTERMENTS MAJOR INSPECTION AND MAINTENANCE ITEMS l

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J16 MISC 87050102 - 5 h

i NUCLEAR PLANT ENGINEERING RESPONSIBILITIES 0 COMPLETE DESIGN O PREPARE OR SUPPORT TECH SPEC REV1SiONS 0 PURCHASE MAJOR EQUIPMENT AND MATERIAL u

NUCLEAR LICENSING RESPONSIBILITIES O PROCESS TECH SPEC REVISIONS  !

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0 SUPPORT NRC REVIEW OF SERI REQUEST TO DEFER / REVISE POSITION ON SELECTED NRC REQUIREMENTS AND SERI-COMMITMENTS PROCUREMENT RESPONSIBILITIES 0 PROCESS PURCHASE ORDERS 0 EXPEDITE EQUIPMENT AND MATERIALS j j

PLANT STAFF RESPONSIBILITIES 0 MANAGE OUTAGE SENIOR MANAGER ASSIGNED TO BACKSHIFT

.- SERI SUPERVISORY STAFF ASSIGNED To ALL MAJOR l AND/OR' SAFETY RELATED JOBS 0 DEVELOP DETAILED INTEGRATED SCHEDULE O DETERMINE / IMPLEMENT REFUELING, SURVEILLANCE, INSPECTION, AND MAINTENANCE ACTIVITIES  ;

O PROVIDE KEY SUPPORT ACTIVITIES J16 MISC 87060102 - 6 7

PLANT MODIFICATION AND CONSTRUCTION RESPONSIBILITIES 0 PERFORM DESIGN WALKDOWNS CONCEPTUAL WALKDOWN AT DESIGN INITIATION REVIEW AND COMMENT ON ISSUED DESIGN O IDENTIFY FIELD MATERIALS l

0 PREPARE WORK PACKAGES 0 DIRECT CONTRACTORS l

0 STAGE MATERIALS l 0 MONITOR AND CLOSE OUT DOCUMENTATION

-. . O_~ CRAFT TRAINING i 0 DEVELOP DETAILED DESIGN CHANGE COST / SCHEDULES

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B, CRITIQUE OF FIRST REFUELING OUTAGE (RF01) o CRITICAL LOOK AT OUTCOME AND PROCESS ]

o CRITIQUE INVOLVED ALL DEPARTMENTS o DEVELOPED FORMAL OUTAGE CRITIQUE DOCUMENT l

o. DEVELOPED 77 ACTION ITEMS / RECOMMENDATIONS AS PART OF THE CRITIQUE - APPROXIMATELY 30%

IMPLEMENTED / COMPLETED o KEY LESSONS LEARNED:

REDUCE SCOPE FREEZE OUTAGE SCOPE EARLY AND MANAGE SCOPE CREEP- I l

DEVELOP A MORE DETAILED SCHEDULE .....

TO INCLUDE MAJOR SURVEILLANCE, PM'S, AND MWO'S DEVELOP A BETTER PLAN AND STAFF FOR CONTRACTOR MANAGEMENT SUBMIT TECH SPEC RELIEF REQUEST AS EARLY AS POSSIBLE

- AVOID, IF AT ALL POSSIBLE, MAJOR SCHEDULE LOGIC CHANGES DURING THE OUTAGE CONTINGENCY PLANS ON MAJOR ITEMS '

J16 MISC 87060102 - 8 f

C, CONDUCT OF SECOND REFUELING OUTAGE (RF02) i GRAND GULF NUCLEAR STATION - UNIT I

SUMMARY

o PROJECTED START DATE: ACCELERATED FROM JANUARY 8, 1988 TO NOVEMBER 6, 1987 i o PRELIMINARY OUTAGE DURATION PROJECTED: 58 DAYS 1

o NUMBER OF MODIFICATIONS (DCPS) l WITH POTENTIAL DECREASE 107 l

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o REGULATORY REQUIRED MAJOR TASKS 17 (INCLUDES APPROXIMATELY 36 DCPS) l l

o COMMITTED MNCR WORK 0FF 37 o MAJOR PLAN AVAILABILITY /

RELIABILITY /ALARA MODIFICATIONS 44 i l

0 SIGNIFICANT FINANCIAL COMMITMENT $20 MILLloN i l

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REGULATORY REQUIRED MAJ0P TASKS o DCRDR (18 DCPS)  ;

1 o ALTERNATE ROD INSERTION (2 DCPS) o INSTRUMENT LINE ISOLATION VALVES (2 DCPS) o REACTOR WATER LEVEL TRANSMITTERS i o 0FFGAS H SENSORS 2

SRV LO-LO SET MODIFICATION (2 DCPS) o o UPGRADE ROSEMOUNT TRANSMITTERS o ATWS - SLCS 0 AUTO CLOSURE OF HI-RAD DOORS l

o VISUAL ALARMS IN HI-NOISE AREAS

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o SECURITY MODIFICATIONS (4 DCPS) f l

0 TIME DELAY IN TOPAZ INVERTER LOGIC o CONTAINMENT E D/W H ALARMS 2

o DIVISION 11 D/G DR/0R o LOW PRESSURE TURBINE INSPECTION o SSW FLOW BALANCE & INSPECTION o IEB 85-03 INSPECTIONS / TEST o SURVEILLANCE (APPRoXIMATELY 770) o LLRTS (APPRoXIMATELY 300)  !

o DRYWELL BYPASS TEST l 0 ISI/IST o SNUBBER INSPECTION / REFURBISHMENT j J16 MISC 87060102 - 10 11

MAJOR SCOPE ITEMS FOR RF02 OTHER MAJOR OUTAGE ACTIVITIES o REFUEL FLOOR ACTIVITIES 1/3 CORE REPLACEMENT o DISASSEMBLY 8 INSPECTION OF RFPT AND RFP "A" & "B" o CONDENSER CLEANING o INSTALLATION OF ON-LINE CONDENSER CLEANING SYSTEM o MAJOR VALVE INSPECTION / SDC HI/ LOW INTERFACE VALVES 8 ,

REWORK SDC RETURN TO REACTOR CAVITY '

o REWORK FEEDWATER CHECK SOFT SEAT SERVICE LIFE VALVES "A" 8 "B" o VALVE REPACKING & RELIEF BASED ON RF01 EXPERIENCE VALVE TESTING APPROXIMATELY 340 VALVES REWORKED 8 75 RELIEFS TESTED o PREVENTIVE MAINTENANCE BASED ON RF01 EXPERIENCE ITEMS APPR0XIMATELY 2100 18C, 500 ELECTRICAL, 2450 MECHANICAL o MAINTENANCE WORK ORDERS- BASED ON RF01 EXPERIENCE APPROXIMATELY 1040 18C, 650 ELECTRICAL, 1600 MECHANICAL o BUS CLEANING OUTAGE DC BUSSES FOR GROUNDING PROBLEMS

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RF02 CONTINGENCY' PLANNING o AREAS OF POTENTIAL SCHEDULE IMPACT.

DIVISION 11 D/G DR/QR.- SCOPE OF 50% PISTONS INSTRUMENT LINE ISOLATION VALVES l

FEEDWATER CHECK VALVE WORK SNUBBER TESTING / REFURBISHMENT j LOW PRESSURE TURBINE INSPECTION STANDBY SERVICE WATER INSPECTION AND CLEANING PLANT SERVICE WATER INSPECTION AND CLEANING J16 MISC 87060102 - 12 /1

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D. LICENSING SUPPORT ACTIONS 0 PROPOSED' CHANGES TO-TECHNICAL SPECIFICATIONS LESSONS LEARNED FROM RF01 REQUIRED TO SUPPORT INTENDED RF02 DESIGN CHANGES 0 SELECTED ITEMS IN WHICH REGULATORY RELIEF WILL;BE SOUGHT i INSTALLATION OF UPGRADED NEUTRON FLUX MONITORING INSTRUMENTATION (REG. GUIDE. 1.97, Riv, 2)  ;

INSTALLATION OF IMPROVED ISOLATION PROVISIONS-FOR CERTAIN INSTRUMENT LINES PENETRATING CONTAINMENT REMAINING 1D1 DROR INSPECTIONS ON DIVISION. ll l EDG J16 MISC 87060102 - 13 / tr

PROPOSED TECH SPEC CHANGES l RF01 LESSONS LEARNED SCHEDULED DESCRIPTION SUBMITTAL DATE

1. REMOVE IRM/SRM/LPRM/TIP & SPECIAL 6/03/87 MOVABLE DETECTORS FROM DEFINITION OF CORE ALTERATION

2. CHANGE SNUBBER ADDITIONAL TEST SAMPLE 6/03/87 SIZE FROM 10% TO 5%

3. CLARIFY TS OPERABILITY REQUIREMENTS 6/10/87 WHEN CHANGING RPV WATER LEVEL - 3.0,4 EXCEPTIONS FOR RHR SHUTDOWN COOLING AND ECCS

4. CLARIFY OPERABILITY REQUIREMENTS FOR 6/15/87 ISOLATION INSTRUMENTATION WHEN CONTAINMENT INTEGRITY NOT REQUIRED J16 MISC 87060102 - 14 /5~

PROPOSED TECH SPEC CHANGES RF02 CHANGES l

SCHEDULED DESCRIPTION SUBMITTAL DATE i

1. ATWS CHANGES 6/30/8/  :

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2. DELETE OR CHANGE TS FOR NEW ISOLATION VALVES T.B.D.

3. RELOAD LICENSING (POTENTIAL) 8/27/87 i l

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. 1 INSTRUMENTATION FOR R.G. 3.97 l

1. REQUIREMENT {

0 RF02 LICENSE REQUIREMENT INSTALL OR UPGRADE NEUTRON FLUX MONITORING 0 REGULATORY GUIDE 1.97 REPORT - FLUX MONITORING POSITION PURSUE CAT. 1 INSTRUMENTATION FOLLOW INDUSTRY DEVELOPMENT IMPLEMENT CAT. 1 INSTRUMENTAL 10f1 OR UPGRADE BASED ON DESIGt! REQUIREMENTS

11. VEHICLE FOR REllEF 1

0 SUEMIT PROPOSED LICENSE CONDITION CHANGE TO DEFER FLUX  !

MONITORING CHANGES UlJTIL RF03 111. TECHNICAL JUSTIFICATION FOR RELIEF l

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0 WHILE PROGRESS RECOGNIZED IN APPLICATION TO BWRS IN RECENT YEARS, OVERALL, SERI CONSIDERS SYSTEMS TO BE IN DEVELOPMENT PHASE O TWO PRINCIPAL ALTERNATIVE APPROACHES FOR NEW SYSTEM:

INCORE OR EXCORE MORE BWR EXPERIENCE WITH EXCORE

- H0h*E'vER, INCORE SATISFIES NUMEROUS PLANT BETTERMEf4T ASPECTS l 0 SCRAM REDUCTION (WIDE RANGE AVotDS SCRAMS DUE TO OVER-RANGING) 0 REDUCTION OF PHYSICAL INTERFERENCE TO UNDER RPV MAINTENANCE O ALARA CONSIDERATIONS JI6 MISC 87060102 - 16 I7

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9 0 FLUX MONITORING INSTRUMENTATION RELIABILITY -

SIMPLER. SYSTEM, NO DRIVES l EXCORE SYSTEM HAS HAD QUALIFICATION PROBLEMS AT WPPS j EXCORE SYSTEM SEEN AS LIKELY TO SATISFY

! R.G. 1.97 REQUIREMENT BUT-MAY NOT j REPRESENT OPTIMUM SOLUTION.

- OVERALL, ADDITIONAL TIME REQUIRED FOR ,1 SERI TO ASSESS ALTERNATIVES O CHARACTERISTICS OF BWR DESIGN, OTHER !NFORMATION AVAILABLE-TO OPERATOR TO SUPPORT EMERGENCY PROCEDURE DECISION MAKING 0 SERI WILL INSTALL IN RF02 UPGRADED SHUTDOWN AND FUEL ZONE RANGE WATER LEVEL INSTRUMENTATION (R.G. 1.97) CONSISTENT WITH BWR EPGS AND CURRENT GGNS EMERGENCY PROCEDURES-0 - SERI PARTICIPATING IN BWROG COMMITTEE ASSESSING SAFETY FUNCTION OF FLUX MONITORING INSTRUMENT AND PROPER QUALIFICATION LEVEL OF SYSTEM

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IV. IMPACT ON OUTAGE O COMPLEX MODIFICATION (INCORE) j I

O ADDITIONAL DETAILED ENGINEERING REQUIREMENTS O LONG LEAD TIME TO PROCURE INCORE SYSTEM (APPROX. 54 )

WEEKS) -

j V. SERI LICENSING SCHEDULE  !

O SUBMIT PROPOSED AM'ENDMENT BY JUNE 15, 1987 f

J16 MISC 87060102 - 17 /I

INSTRUMENT LINE ISOLATION VALVES

1. REQUIREMENT 0 GDC 55 AND 56, REGULATORY GUIDE 1.11 REQUIRES SPECIFIC ISOLATION PROVISIONS FOR LINES PENETRATING CONTAINMENT AND AN ACCEPTABLE BASIS FOR INSTRUMENT LINES.

O SERI COMMITED TO INSTALL MOV IN SIX (6) INSTRUMENT LINES TO COMPLY 4 IN MSIV LEAKAGE CONTROL SYSTEM 1 IN RHR 1 IN LPCS 0 DEFERRED VALVE INSTALLATION UNTIL RF02.

11. VEHICLE FOR RELIEF' O SERI LETTER REQUESTING PERMANENT RELIEF FROM COMMITMENT 111. TECHNICAL JUSTIFICATION FOR RELIEF O NEW APPROACH - CONTAINMENT INTEGRITY ASSURED.

O SRP 6.2.4 SPECIFIES ACCEPTABLE ALTERNATE CONTAINMENT ISOLATION PROVISIONS FOR INSTRUMENT LINES CLOSED INSIDE AND OUTSIDE CONTAINMENT AND GESIGNED FOR POST-LOCA CONDITIONS AND DYNAMIC EFFECTS, ARE ACCEPTABLE WITHOUT ISOLATION VALVES.

O AFFECTED LINES CAN BE CLASSIFIED AS CLOSED LINES OUTSIDE CONTAINMENT, THUS AS ISOLATION' BARRIERS.

O INBOARD CONTAINMENT ISOLATION VALVE FOR EACH PROCESS LINE IS OTHER ISOLATION BARRIER.

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SUMMARY

- EACH INSTRUMENT LINE HAS TWO ISOLATION  !

BARRIERS AND CAN MAINTAIN LEAK TIGHT CONTAINMENT INTEGRITY.

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r a IV, IMPACT ON OUTAGE (ESTIMATES)

{

0 2,500 MANHOURS REQUIRED FOR DESIGN O APPROXIMATELY 11,000 MANHOURS REQUIRED FOR INSTALLATION O REQUIRE APPROXIMATELY FOUR WEEKS CRITICAL PATH TIME O . COMPLEX MODIFICATION VALVE INSTALLATION RUN CABLE CONDUIT INSTALLATION PIPE WHIP RESTRAINT INSTALLATION HYDROTESTING V. SERI LICENSING SCHEDULE-0 SUBMIT PERMANENT COMMITMENT RELIEF' REQUEST BY  !

JUNE 10, 1987  :

0 NEED NRC DECISION AS SOON AS PRACTICAL TO AVOID /

UNNECESSARY DILUTION OF ENGINEERING RESOURCES  !

1 i

i J16 MISC 87060102 - 19 70

EDG DIVISION 11 PARTIAL TEARDOWN

1. REQUIREMENT 0 NRC APPROVED LIMITED DEFERRAL OF DR/QR INSPECTION ON THE GRAND GULF DIVISION 11 EDG UNTIL RF02 l

l

11. VEHICLE FOR RELTEF 1 i

0 SERI LETTER REQUESTING NRC APPROVAL OF REQUEST TO-DEFER REMAINING INSPECTIONS UNTIL REQUIRED 5-YEAR.

MINl-0VERHAUL 111. TECHNICAL JUSTIFICATION FOR RELIEF 0 FAVORABLE INSPECTION OF APPROXIMATELY TWO-THIRDS )

0F CRITICAL AREA / COMPONENTS DURING RF01 0 FAVORABLE INSPECTION OF REMAINING COMPONENTS AT f OTHER UTILITIES O EXCELLENT DIVIS10N 11 EDG STARTING PERFORMANCE AT GGNS 0 GGNS EDG OPERATED AT REDUCED LOAD 0 . TECHNICAL' JUSTIFICATION FOR DEFERMENT CONCURRED WITH BY EDG CONSULTANT (FAAA)

IV. IMPACT ON OUTAGE O KEY GGNS MAINTENANCE PERSONNEL DIVERTED FROM OTHER CRITICAL WORK 0 CRITICAL PATH SAVINGS V. SERI LICENSING SCHEDULE O SUBMIT DEFERRAL REQUEST BY JUNE 12, 1987 O NEED NRC RESPONSE BY AUGUST 1,11987 l J16 MISC 87060102 - 20 <2. )

l I

i

~

IV. SPECIAL INTEREST ITEM -

Potential Fuel Pin Leakage ,

Problem Identification 5/20/87 - Routine reactor coolant isotopic analysis indicated an elevated Iodine - 131 concentration over previous levels. An increase from the average of IE-5 u Ci/ml to 4.1E-5 uCi/mi prompted sampling for Coolant .

Dose Equivalent Iodine - 131 (DE I-131) and retreatment offgas. l 1

Dose Eouivalent Iodine l 5/21/87 - Reactor coolant dose equivalent Iodine - 131 was 1.36E-4 u Ci/gn. Previous levels averaged 5.9E-5 u Ci/gm. The DE I-131 l reached 1.6E-4 p Ci/gm on 5/23/87 and was 5.37E-5 # Ci/gm on 5/28/87.

Retreatment Offaas 1 5/22/87 - Retreatment Offgas release rate was 7.5E .u ci/sec. Previous I levels averaged 5.0E2 u Ci/sec. Retreatment offgas release reached 1.4E4 u Ci/see on 5/23/87 and was 3.5E3.u ci/ set on 5/3./87.

Cesium Ratio 5/26/87 - A cesium separation on reactor coolant yielded a ratio of 1.1 l

~

for Cs 137/134. This ratio corresponds to a MWD /MTU value of 9 approximately 15000. l Offaas Distribution  !

A/Y A vs. A plots for offgas activity indicate a slope of near 1 after recoil activity is subtracted out. A slope of 1 is indicated of an i equilibrium release. l l

Plant Radiation Le"el l Rad levels have increased in the Offgas Charcoal Vault area from 80 mr/hr to 1.5 R/hr. Currently this is the only change in plant radiation levels. 1 Action Plan Currently, Offgas Retreatment samples are being taken daily and Reactor Coolant Iodine samples are taken following substantial power changes

(+15% / 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />). Routine monitoring of reactor coolant continues through isotopic analysis (weekly) and gross beta / gamma measurements (daily).

This monitoring program alerted us to the problem initially and these  ;

results will be evaluated in a like manner in the future. .

l 1

( J16 MISC 87060103 - 1 2. 1 i

- 1

ENCLOSURE 3 i

GRAND GULF NUCLEAR STATION UNIT ONE PERFORMANCE MONITORING MANAGEMENT INFORMATION PROGR/L*f ,

, i l

• • MANAGEMENT REPORT **

for APRIL 1987 Prepared by: C . e 4 ,^ ^ '

. Reviewed-C. L. Tyrode Manager h Nuclear Fuels & Services 9

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J02PMIB70416 - 2 i

m . .

TABLE OF CONTENTS I. REPORT HIGHLIGHTS II. PERFORMA.CEN INDICATORS Indicator Indicator No. Description 1 ........................... Forced Outage Rate 2 ........................... Number of Unplanned Reactor Trips While Critical 3 ........................... Number of Unplanned Safety System Challenges 4 ........................... Safety System Unavailability 5 ........................... Gross Heat Rate 6 ..................... ..... Net Heat Rate l

7 ........................... Reactor Coolant Dose Equivalent  !

I-131 l

i 8 ........................... Equivalent Availability 9 ........................... Unit Capacity Factor 10 ........................... License Event Reports

?

11

...................}....... a Collective Radiation Exposure 12 ....................%...... Total Volume of Solid Radioactive Waste 13 ..........r................ Lost Time Injuries per 200,000 Hours 14 ........................... Gaseous Radioactive Effluent - Organ Dose 15 ........................... Gaseous Radioactive Effluent - Air

> Dose 16 ........................... Liquid Radioactive Effluent 17 ........................... Airborne Radioactivity Areas 18 ........................... Personnel Contaminations "49 ........................... Surface Contamination Area i

l 1

J02PMIB70416 - 3

) et

TABLE OF CONTENTS (Cont'd)

Indicator Indicator No. Description 20 ........................... Feedwater Chemistry Status 21 ........................... Reactor Water Chemistry Status 22 ........................... Violations 23 ........................... Status of Licensing Commitments 24 ........................... Core Burnup vs Time 25 ........................... Maintenance Work Order Status 26 ........................... Temporary Modification Status 27 ........................... Spare Parts Availability 28 ........................... Design Change Status 29 ........................... Material Non-Conformance Report Status

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30 ........................... QA Non-Conformance Performance Indicators 3' ........................... Design Document As-Built Status 32 ........................... Examination Performance i

33 ........................... Attrition from' Training Courses 34 ........................... Personnel Error Incident Reports 35 ........................... Number of Contract Employees l

! 36 ........................... Turnover Rate 37 ........................... Plant Staff Overtime 38 ........................... Status of INPO Recommendations 39 ........................... Employee Safety Performance Index 40 ........................... Nuclear Operations & Nuclear l

Engineering & Support Staffing l Status I

I I

J02PMIS70416 - 4

l I

II. HIGRLIGHTS i

• Indicator #4 - Safety System Unavailability i

Overall Safety System Unavailability for April was 1.5%. HPCS/DIV3 and DIV2 were 0% unavailable for the month. RCIC was unavailable 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> in April when it was tagged out for repair of a leaking union and other maintenance activities. DIV1 was inoperable 22.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> due to repair of the overspeed trip device and investigations into voltage regulatur trouble alarm problems. With the exception of DIV2, year-to-date unavailability for each system is above the yearly goal.

• Indicator #9 - Unit Capacity Factor Capacity Factor for April was 106.2%. This brings the year-to-date Capacity Factor to 90.8%.

• Indicator #20 - Feedwater Chemistry Status Feedwater Chemistry hours out of goals has exceeded the goal for 1987 and presently stands at 552.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. Following is a brief explanation of the suspected problem and the proposed solution:

The Condensate system receives makeup water from the Condensate Storage Tank which is vented to the atmosphere. This results in air Saturated water being introduced directly to the Condensate system and in turn causes high feedwater crygen concentrations. This

- problem is especially prevalent during changes in power when large volumes of water are being returned and made up from the Condensate Storage Tank. A DCR has been written which will inert the atmosphere in the Condensate Storage Tank and Demineralized Storage Tank with nitrogen and thus prevent air saturated water from being introduced into the Condensate system.

• Indicator #22 - Violations Three violatichs were issued in April. A brief description of each is as follows:

Level 5 - Failure to document an identified deficiency.

Level 4 - Failure to implement the SSW basin acid addition system per the temporary alteration.

Failure to install hydraulic control units per the design drawing.

f l

1 J02PMIB70416 - 6 3 Y

r

• Indicator (125 - Maintenance Work Order Status The number of open MW0s increased from 1119 in March to 1388 in April. This increase can be attributed to a revised method of l reporting open MW0s which more accurately reflects INPO guidelines.

14

• Indicator (135 - Number of Contract Employees Contract employees increased slightly in April to 36. The increase is due to the hTE takeover of the Bechtel Resident Design Group.

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