ML20212J862

Summary of 870211 Meeting W/Util Re Program for Obtaining Data on Containment Purging.Meeting Agenda,List of Mark III Access Requirements & Other Related Info Encl

ML20212J862
Person / Time
Site:	Grand Gulf
Issue date:	03/03/1987
From:	Kintner L Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 8703090157
Download: ML20212J862 (12)

Text

.

34 UNITED STATES

, [ iw g NUCLEAR REGULATORY COMMISSION 3 p WASHINGTON, D. C. 20555 c

%, '..... / March 3, 1987 Docket No. 50-416 LICENSEE: System Energy Resources, Inc. (SERI)

FACILITY: Grand Gulf Nuclear Station, Unit 1~

SUBJECT:

SUMMAPY OF FEBRUARY 11, 1987 MEETING REGARDING CONTAINMENT PURGING The purpose of the meeting was to discuss a program for obtaining operational data regarding containment purging. SERI participants were J. G. Cesare,

'J. Fowler and L. Robertson. NRC participants were J. Kudrick, P. Hearn, J. Unda and L. Kintner. Enclosure 1 is a handout prepared by SERI.

The present limits in the Technical Specifications on purging during plant operation (continuous puroe through the 6-inch line and 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br /> per year through the 20-inch line) were based on General Electric Company analyses of reactor coolant activity and leakage. In accord with License Condition 2.C.16, SERI provided a report dated October 3, 1986, based on data gathered during the first fuel cycle. SERI recommended in the report that the present limits on purging be continued.

Based on its review of the report, the staff expressed two concerns: (1) that the purge system should not be used for temperature and humidity control; and (2) that the data provided in the report was not adequate to justify the present purge limits. The information presented in this meeting was in response to these concerns.

The licensee described the need for routine, periodic access to the Mark III containment because many reactor support systems are located inside containment and maintenance and surveillance requires entries every day.

Sheet 2 of the Enclosure shows typical systems and access requirements.

Sheets 4 through 6 show the design of the Mark III containment and the purge system and present criteria for its operation. The system is not relied on for temparature or humidity control. The system includes recirculation of 3000 CFM through a charcoal filter train. Containment purge isolation valves are required by Technical Specifications to close in four seconds and are designed to close against LOCA pressures.

The staff questioned whether surveillance and maintenance activities were coordinated to achieve minimum access time in containment. The licensee stated that some surveillances are required once a day (e.g. reactor water samples and standby liquid control system concentration). Because of the large containment volume, the large purge system requires two days to make one air change.

Therefore, if cleanup were needed for access, continuous purge may be needed.

The air recirculation filter system is run continuously. During the first fuel cycle, radioactivity in the containment air was small (about 1% of the 10 CFP 8703090157 870303 PDR P ADOCK 05000416 pop ,

. Part 70 maxirum permissible concentration (MPC) at the end of the first fuel cycle). Presently, the containr.,ert air is about 8% MPC. The need for a continuous purae for access has not been demonstrated in the first fuel cycle.

From ALARA considerations, 25% MPC is selected as a reasonable limit for access.

The licensee proposed a program to obtain additional data regarding the need to purge during the second fuel cycle (See Sheets 7 and 8 of Enclosure 1). Tc resolve the concern that purging not be used to control temperature and humidity, the licensee proposed a 30 dry test in which the puroa sytem would be isolated.

Parameters to be meesured would include temperature, relative huridity, pressure and air radioactivity. If radioactivity reaches 25% MPC, purging for access would be initiated. The test is planned to be run in February and March. To resolve the concern for adequate data regarding need for access, containment access will be monitored (individual's name, discipline, and time spent in containment) during the second fuel cycle. The security computer monitoring program has been modified tc obtain needed data. The purge systems will be isolated unless containment air radioactivity reaches 25% MPC.

SERI will send NRC a letter within a few weeks summarizing the test monitoring program described in this meeting and provide a commitment to document the methodology used to determine the annual purcing time limits for Grand Gulf after the second fuel cycle.

hDs Lester L. Kintner, Project Manager BWR Project Directorate No. 4 Division of BWR Licensing Enclosure (s):

As stated ccw/ enclosure (s):

See next page 1

o .

D Mr. Oliver D. Kingsley, Jr.

System Energy Resources, Inc. Grand Gulf MLclear Station (GGNS)

CC.

Mr. Ted H. Cloninger Mr. C. R. Hutchinson Vice President, Nuclear Engineering GGNS General Manager and Support . System Energy Resources, Ir.c.

Syster Energy Resources. Inc. Post Office Box 756 Post Office Box 23054 Port Gibson, Mississippi 39150 Jackson, Mississippi 39205 Robert B. McGehee, Esquire The Hnnorable 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 and Reynolds State of Mississippi 1200 17th Street, N.W. Jackson, Mississippi 39101 Washington, D. C. 20036 Attorney General Mr. Ralph T. Lally Gartin Building Manaoer 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 10385 P.O. Box 23054 Jackson, Mississippi 39209 Jackson, Mississippi 39205 Alton B. Cobb, M.D.

Mr. R. W. Jackson, Project Engineer State Fealth Officer Bechtel Power Corporation State Board of Health 15740 Shady Grove Road P.O. Box 1700 Gaithersburg, Maryland 20877-1454 Jackson, Mississippi 39205 Mr. Ross C. Cutcher 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 Pegional 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 Systen. Energy Resources, Inc.

P.O. Box 756 Port Gibson, Mississippi 39150

. Er. closure l' NRC - SERI MEETING: CONTAINMENT PURGE BETHESDA, MARYLAND FEBRUARY ll, 1987 MEETING AGENDA I. INTRODUCTION J. G. CESARE II, 0VERVIEW 0F THE-MARK III-CONTAINMENT J. L. ROBERTSON ACCESS REQUIREMENTS III, DESIGN OF THE CONTAINMENT PURGE J. L, ROBERTSON/

J. O. F0WLER IV. NRC CONCERNS REGARDING THE ADEQUACY OF J. 0, F0WLER THE CONTAINMENT COOLING SYSTEM V. CYCLE 2 MONITORING PROGRAM /USE OF PURGE J. G,-CESARE VI

SUMMARY

/ CONCLUSION REMARKS J. G. CESAPE 4

J16 AGENDA 87020301 - 2

MARK Ill CONTAINMENT ACCESS REOUIREMENTS 0 COMPARISON OF THE MARK 11 AND MARK 111 CONTAINMENT DESIGNS MARK 11 CONTAINMENT ROUGHLY EQUIVALENT IN SIZE TO THE MARK 111 DRYWELL MARK 111 CONTAINMENT DESIGN ALLOWS MORE REACTOP SUPPORT ,

SYSTEMS TO BE LOCATED INSIDE CONTAINMENT THEREFORE REQUIRING ACCESS DURING POWER OPERATION O TYPICAL EQUIPMENT / SYSTEMS LOCATED INSIDE THE MARK lli CONTAINMENT REACTOR WATER CLEANUP SYSTEM REACTOR WATER SAMPLE PANEL

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STANDBY LIQUID CONTROL CRD HYDRAULIC CONTROL UNITS RECIRC FLOW CONTROL VALVE HYDRAULIC POWER UNITS REACTOR VESSEL & DRYWELL INSTRUMENTATION RACKS UPPER CONTAINMENT POOLS TRANSVERSING INCORE PROBE SYSTEM i

ISOLATION VALVES CONSIDERED ACCESSIBLE O TYPICAL ACCESS REQUIREMENTS BASED ON EARLY CYCLE 2 DATA (1/6/87 - 1/31/87)

OPERATIONS - 41 MAN HOURS / WEEK MAINTENANCE - 73 MAN HOURS / WEEK HEALTH PHYSICS - 47 MAN HOURS / WEEK CHEMISTRY - 12 MAN HOURS / WEEK THE ABOVE ACTIVITIES REPRESENT THE MAJORITY (94%) 0F IN-CONTAINMENT WORK WHILE AT POWER, J16 AGENDA 87020301 - 3 2-

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NUREG-1037 6 APPENDIX B f

DESIGN OF THE CONTAINMENT PURGE O DESCRIPTION OF THE LOW VOLUME AND HIGH VOLUME PURGE O COMPLIANCE WITH THE POSITIONS OF BTP 6-4 ISOLATION VALVES HAVE BEEN SHOWN TO FUNCTION PROPERLY AGAINST LOCA PRESSUPES. CLOSURE TIMES ARE REQUIRED BY TECH SPECS TO BE LESS THAN 4 SECONDS. TESTING OF THE ISOLATION VALVES IS COVERED UNDER THE ISI PROGRAM.

THE NUMBER OF SUPPLY AND EXHAUST LINES TRE LIMITED TO ONE SUPPLY LINE AND ONE EXHAUST LINE FOR EACH PURGE SUBSYSTEM. TECH SPECS PROHIBIT USE OF BOTH THE HVP AND THE LVP AT THE SAME TIME.

THE LVP NOMINAL LINE SIZE IS 6 INCHES. THE HVP NOMINAL LINE SIZE IS 20 INCHES, HOWEVER, USE OF THE HVP IS LIMITED TO 1000 HOURS PER YEAR WHILE IN OPERATIONAL CONDITIONS 1, 2 AND 3.

THE PURGE PENETRATIONS MEET GDC 54 AND 56 FOR LINES PENETRATING CONTAINMENT.

PURGE LINES HAVE REDUNDANT ISOLATION VALVES WHICH ISOLATE ON LOCA SIGNALS. OUTBOARD AND INBOARD VALVES ARE POWERED BY SEPARATE DIVISIONS.

ISOLATION VALVES ARE TESTED PERIODICALLY IN ACCORDANCE WITH TECH SPECS.

SEISMIC CATEGORY I SCREENS ARE PROVIDED FOR BOTH THE INLET AND EXHAUST VALVES TO PREVENT DEBRIS FROM EFFECTING VALVE CLOSURE UNDER POSTULATED ACCIDENT CONDITIONS.

NOT RELIED ON TO CONTROL TEMPERATURE AND HUMIDITY.

PROVISIONS FOR ATMOSPHERE CLEANUP ARE PROVIDED BY THE CONTAINMENT FILTRATION SUBSYSTEM.

ISOLATION FUNCTION IS DEMONSTRATED ONCE PER 18 MONTHS AND LEAK RATE TESTED ONCE PER 92 DAYS.

ANALYSIS HAS BEEN PERFORMED ON THE CONSEQUENCES OF A LOCA WHILE PURGING THE CONTAINMENT ATMOSPHERE. THE RADIOLOGICAL CONSEQUENCES ARE WITHIN THE 10CFR100 GUIDELINES.

J16 AGENDA 87020301 - 4 5

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UFC CONCERNS REGARDING THE ADE0l!ACY OF THE-CONTAINMENT COOLING SYSTEM 0 STATEMENT OF THE CONCERN 0 SPECIAL' TEST WILL CONFIRM THE ADEQUACY OF THE CONTAINMENT COOLING SYSTEM 0 DESCRIPTION OF THE SPECIAL TEST WITH PURGE ISOLATED PARAMETERS TO BE MONITORED TEMPERATURE RELATIVE HUMIDITY CONTAINMENT PRESSURE OXYGEN LEVEL EXPLOSIVE GASES PARTICULATE ISOTOPES GASEOUS ISOTOPES TEST DURATION OF AT LEAST 30 DAYS ACCESS WILL BE MONITORED IN ACCORDANCE WITH THE CYCLE 2 CONTAINMENT PURGE MONITORING PROGRAM 0 DURING THE TEST, KEY AIR QUALITY PARAf1ETERS WILL BE EVALUATED TO ASSURE NO HAZARDS TO PERSONNEL ENTERING THE CONTAINMENT.

THE PURGE MAY BE INITIATED AT ANY TIME THAT AIR QUALITY APPROACHES FRE-SPECIFIED' LIMITS, O A REPORT OF THE TEST RESULTS WILL BE SUBMITTED WITHIN 60 DAYS OF COMPLETION OF THE TEST. THE TEST REPORT WILL ADDRESS:

TEMPERATURE AND RELATIVE HUMIDITY TRENDS DURING THE TEST PERIOD USE OF THE LVP DURING THE TEST PERIOD (IF REQUIRED)

ADJUSTMENTS TO THE CYCLE 2 CONTAINMENT PURGE MONITORING PROGRAM (IF REQUIRED)

O SCHEDULE FOR TEST J16 AGENDA 87020301 - 5 7

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9 CYCLE'2 CONTAINMENT PURGE MONITORING PROGRAM /USE OF PURGE O PURPOSE OF THE PROGRAM GATHEP DATA TO EVALUATE THE LONG TERM NEED FOR CONTAINMENT PURGE DURING OPERATION O MONITORED AIR QUALITY PARAMETERS OXYGEN EXPLOSIVE LIMITS PARTICULATE ISOTOPES GASEOUS ISOTOPES 0 CRITERIA FOR THE USE OF THE PURGE DURING OPERATION LVP WILL EE USED ONLY TO MAINTAIN AIR QUALITY WITHIN ESTABLISHED GUIDELINES.

O USE BASED ON THRESHOLDS 0 SPECIAL CONDITIONS (EXPECTED TO BE RARE)

HVP WILL BE CONTROLLED IN ACCORDANCE WITH TECH SPECS.

O IMPROVED CONTAINMENT ACCESS MONITORING PROGRAM SECURITY SOFTWARE MODIFICATIONS ARE NOW COMPLETE ACCESS TO CONTAINMENT IS MONITOPED CONTINUOUSLY - RECORDS ARE MAINTAINED AS TO INDIVIDUALS NAME, DISCIPLINE AND TIME

. SPENT IN CONTAINMENT.

SAMPLE PRINTOUT OF CONTAINMENT ACCESS REPOPT 0 REPORT WILL BE SUBMITTED PRIOR TO RESTART FROM RF02.

,- DETAIL OF CYCLE 2 DATA RECOMMENDATIONS FOR USE OF LVP FOR CYCLE 3 J16 AGENDA 87020301 - 6 2f

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Part 20 maximum pemissible concentration (MPC) at the end of the first fuel cycle). Presently, the containment air is about 8% MPC. The need for a continuous purge for access has not been demonstrated in the first fuel cycle.

From ALARA considerations, 25% MPC is selected as a reasonable limit for

-access.

The licensee proposed a program to obtain additional data regarding the need to purge during the second fuel cycle (See Sheets 7 and 8 of Enclosure 1). To resolve the concern that purging not be used to control temperature and humidity, the licensee proposed a 30_ day test in which the purge sytem would be isolated.

Parameters to be measured would include temperature, relative humidity, pressure and air radioactivity. If radioactivity reaches 25% MPC, purging for access would be initiated. The test is planned to be run in February and March. To resolve the concern for adequate data regarding need for access, containment access will be monitored (individual's name, discipline, and time spent in containment) during the second fuel cycle. - The security computer monitoring program has been modified to obtain needed data. The purge systems will be isolated unless containment air radioactivity reaches 25% MPC.

SERI will send NRC a letter within a few weeks summarizing the test monitoring program described in this meeting and provide a commitment to document the methodology used to determine the annual purging time limits for Grand Gulf' after the second fuel cycle.

N Lester L. Kintner, Project Manager BWR Project Directorate No. 4 Division of BWR Licensing Enclosure (s):

As stated ccw/ enclosure (s):

See next page-D STRIBUTION I

R M NRC PDR LPDR PDf4 Reading

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