ML16251A414
| ML16251A414 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 07/16/1992 |
| From: | Ross T Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9207220351 | |
| Download: ML16251A414 (16) | |
Text
pk REGjl, UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2065 July 16, 1992 Docket Nos. 50-259, 50-260, and 50-296 LICENSEE: Tennessee Valley Authority FACILITY: Browns Ferry Nuclear Plant, Units 1, 2, and 3
SUBJECT:
SUMMARY
OF A MEETING WITH THE LICENSEE REGARDING EXPANDED INDIVIDUAL PLANT EXAMINATIONS On May 28, 1992, representatives of the NRC and the Tennessee Valley Authority (TVA) met at NRC headquarters in Rockville, Maryland, to discuss TVA's plans for conducting an expanded Individual Plant Examination (IPE) for all three units of the Browns Ferry Nuclear Plant (BFN).
The principal purpose of this meeting was to brief the NRC staff on the rationale and details of TVA's approach, as described in their submittal of February 7, 1992. During this meeting, the staff expressed reservations about certain assumptions inherent in TVA's proposed expanded IPE approach, such as: 1) operation of three units represents a bounding plant configuration, 2) ten selected shared systems are sufficient to scope all significant vulnerabilities, and 3) severe accident analysis is limited to two selected initiating events. As a consequence of this meeting, and review of TVA's submittal, the staff intends to issue a formal response to TVA regarding the acceptability of their approach.
Meeting attendees are listed in Enclosure 1. A copy of TVA's presentation handouts are provided as Enclosure 2.
Thierry M. Ross, Senior Project Manager Project Directorate 11-4 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
Enclosures:
- 1. Attendees
- 2. Agenda cc w/enclosures:
See next Page NBC HLE C T
C 9207220351 920716 PDR ADOCK 05000259 P
Docket Nos. 50-259, 50-260, and 50-296 LICENSEE: Tennessee Valley Authority FACILITY:
Browns Ferry Nuclear Plant, Units 1, 2, and 3
SUBJECT:
SUMMARY
OF A MEETING WITH THE LICENSEE REGARDING EXPANDING INDIVIDUAL PLANT EXAMINATIONS On May 28, 1992, representatives of the NRC and the Tennessee Valley Authority (TVA) met at NRC headquarters in Rockville, Maryland, to discuss TVA's plans for conducting an expanded Individual Plant Examination (IPE) for all three units of the Browns Ferry Nuclear Plant (BFN). The principal purpose of this meeting was to brief the NRC staff on the rationale and details of TVA's approach, as described in their submittal of February 7, 1992. During this meeting, the staff expressed reservations about certain assumptions inherent in TVA's proposed expanded IPE approach, such as:
- 1) operation of three units represents a bounding plant configuration, 2) ten selected shared systems are sufficient to scope all significant vulnerabilities, and 3) severe accident analysis is limited to two selected initiating events. As a consequence of this meeting, and review of TVA's submittal, the staff intends to issue a formal response to TVA regarding the acceptability of their approach.
Meeting attendees are listed in Enclosure 1. A copy of TVA's presentation handouts are provided as Enclosure 2.
Thierry M. Ross, Senior Project Manager Project Directorate 11-4 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
Enclosures:
- 1. Attendees
- 2. Agenda cc w/enclosures:
See next Page OFC PDII-4/LA PDII-4/PM PDII-4/PM PDII-4 NAME MSanders JWilliam
. TRoss FHebdo__
DATE 7//92 7/
/92 7//; /92 7/ 1/92
Browns Ferry Nuclear Plant cc:
Mr. John B. Waters, Director Claude Earl Fox, M.D.
Tennessee Valley Authority State Health Officer ET 12A State Dept. of Public Health 400 West Summit Hill Drive State Office Building Knoxville, Tennessee 37902 Montgomery, Alabama 36130 Mr. J. R. Bynum, Vice President Regional Administrator Nuclear Operations U.S.N.R.C. Region II 38 Lookout Place 101 Marietta Street, N.W.
1101 Market Street Suite 2900 Chattanooga, Tennessee 37402-2801 Atlanta, Georgia 30323 Mr. Charles Patterson Mr. R. R. Baron, Site Licensing Manager Senior Resident Inspector Browns Ferry Nuclear Plant Browns Ferry Nuclear Plant Tennessee Valley Authority U.S.N.R.C.
P.O. Box 2000 Route 12, Box 637 Decatur, Alabama 35602 Athens, Alabama 35611 Mr. 0. J. Zeringue, Vice President Dr. Mark 0. Medford, Vice President Browns Ferry Nuclear Plant Nuclear Assurance, Licensing and Fuels Tennessee Valley Authority 3B Lookout Place P.O. Box 2000 1101 Market Street Decatur, Alabama 35602 Chattanooga, Tennessee 37402-2801 Mr. M. J. Burzynski, Manager Nuclear Licensing and Regulatory Affairs 5B Lookout Place Chattanooga, Tennessee 37402-2801 TVA Representative Tennessee Valley Authority 11921 Rockville Pike Suite 402 Rockville, Maryland 20852 General Counsel Tennessee Valley Authority ET 11H 400 West Summit Hill Drive Knoxville, Tennessee 37902 Chairman, Limestone County Commission P.O. Box 188 Athens, Alabama 35611 ATTENDEES BROWNS FERRY EXPANDED INDIVIDUAL PLANT EXAMINATION MEETING MAY 28, 1992 Name Organization Frederick Hebdon NRR/PDII-4 Thierry Ross NRR/PDII-4 Joe Williams NRR/PDII-4 William Beckner NRR/PRAB Kaz Campe NRR/PRAB John Schiffgens NRR/PRAB Duke Wheeler RES/SAIB John Flack RES/SAIB Ann Drummer RES/SAIB Joe McCarthy TVA/BFN Restart Mike Hellums TVA/Corporate Licensing Henry Jones TVA/BFN Engineering Richard McMahon TVA/Corporate PRA
ENCLOSURE 2 AGENDA FOR TVA/NRC MEETING ON MAY 28, 199)Y'L EXPANDED INDIVIDUAL PLANT EXAMINATIONS FOR BROWNS FERRY TOPIC SPOKESMAN BACKGROUND J. E. McCARTHY COMPLIANCE WITH GENERIC LETTER 88-20 J. E. McCARTHY PROGRAM TO ADDRESS NRC CONCERNS H. L. JONES /
R. J. McMAHON CONCLUSION J. E. McCARTHY
TVA/NRC MEETING ON MAY 28, 199X7 EXPANDED INDIVIDUAL PLANT EXAMINATIONS FOR BROWNS FERRY TOPIC SPOKESMAN BACKGROUND J. E. McCARTHY 2
TVA/NRC MEETING ON MAY 28, 199X.
EXPANDED INDIVIDUAL PLANT EXAMINATIONS FOR BROWNS FERRY TOPIC SPOKESMAN RESPONSE TO GENERIC LETTER 88-20 J. E. McCARTHY
- TVA WILL COMPLETE AN IPE WHICH CONSIDERS UNIT 2 IN OPERATION AND UNITS 1 AND 3 IN COLD SHUTDOWN BY SEPTEMBER 1, 1992
- TVA WILL INCLUDE A
SUMMARY
REPORT WHICH ADDRESSES THE DIFFERENCES BETWEEN UNITS 1 AND 3 AND UNIT 2 IN ACCORDANCE WITH THE GUIDELINES IN NUREG-1335
- NRC'S JUNE 28, 1991 LETTER CONCLUDES THAT THIS INFORMATION APPEARS TO BE IN COMPLIANCE WITH GENERIC LETTER 88-20 AND ITS SUPPLEMENTS
- IN ADDITION, TVA HAS COMMITTED TO SUBMIT DEPENDENCY MATRICES FOR UNITS 1 AND 3 PRIOR TO THE RESTART OF EACH RESPECTIVE UNIT 3
TVA/NRC MEETING ON MAY 28, 199YP EXPANDED INDIVIDUAL PLANT EXAMINATIONS FOR BROWNS FERRY TOPIC SPOKESMAN PROGRAM TO ADDRESS ADDITIONAL NRC CONCERNS H. L. JONES
- APPENDIX F OF THE BFN FSAR PROVIDES CRITERIA FOR THE DESIGN OF SHARED SYSTEMS CONTAINS LIST AND DESCRIPTION OF SHARED SYSTEMS
- DESIGN BASELINE PROGRAM FOR UNITS 1 AND 3 WILL VERIFY CRITERIA FOR SHARED SYSTEMS ARE ADEQUATE AND PROPERLY IMPLEMENTED PRIOR TO THE RESTART OF EACH UNIT 4
TVA/NRC MEETING ON MAY 28, 1997P EXPANDED INDIVIDUAL PLANT EXAMINATIONS FOR BROWNS FERRY TOPIC SPOKESMAN PROGRAM TO ADDRESS NRC CONCERNS H. L. JONES
- SUBMITTED BY TVA LETTER, DATED FEBRUARY 7, 1992
- EXPANDED IPE TO ADDRESS THREE UNITS OPERATION LIST OF SHARED SYSTEMS REVIEWED TO IDENTIFY THOSE SHARED SYSTEMS WHICH COULD POTENTIALLY AFFECT SEVERE ACCIDENT VULNERABILITIES COMPARED LIST OF SHARED SYSTEMS WITH THE LIST OF SYSTEMS BEING CONSIDERED IN THE BFN IPE HIGHEST DEMAND/LOADS FOR THESE SYSTEMS OCCUR WHEN ALL UNITS OPERATING 5
TVA/NRC MEETING ON MAY 28, 199Y.,2 EXPANDED INDIVIDUAL PLANT EXAMINATIONS FOR BROWNS FERRY Shared System Unit 2 Units 2 & 3 Units 1, 2 & 3 Units I & 2 Units I & 3 Unit I Unit 3 Operating Operating Operating Operating Operating Operating Operating AC Power System Baseline
(-)
(-)
(-)
No Change No Change 250 / 150-V DC Baseline
(-)
(-)
(-)
No Change No Change Power System
- _____._,_..X Diesel Generators Baseline
(-)
(-)
(-)
No Change No Change
[After Unit I or 3 Restart (+)].............
Plant Air Baseline
(-)
(4(-)
(-)
No Change No Change RHR Service Baseline(-
(-)
(-)
(-)
No Change No Change Water EECW System BaselineNoCag()
No Change No Change No Change No Change CRDH System Baseline No Change()()
No Change No Change No Change Raw Cooling Baseline No Change(-()
(-)
(-)
No Change Water
[After Unit I Restart (-)]
Standby Coolant Baseline
()
-()
(-)
No Change No Change Supply RBCCW Baseline())
(-)
(-)
(-)
(-)
[After Unit 1 Restart (-)I LEGEND:
(-)
This symbolizes a configuration which results in an increased challenge to the performance of the systems' safety function due to the impact of system sharing when compared to the baseline case.
(+)
This symbolizes a configuration which results in an decreased challenge to the performance of the systems' safety function due to the impact of system sharing when compared to the baseline case.
No Change No change from the baseline case in the challenge to the performance of the required safety function.
Shading indicates limiting configuration.
NOTE:
This table reflect design basis requirements (including postulated single failure). Technical Specifications may require additional equipment be operational.
6
TVA/NRC MEETING ON MAY 28, 199,1J EXPANDED INDIVIDUAL PLANT EXAMINATIONS FOR BROWNS FERRY TOPIC SPOKESMAN PROGRAM TO ADDRESS NRC CONCERNS (CONTINUED)
H. L. JONES EXPANDED IPE TO ADDRESS THREE UNITS OPERATION (CONTINUED)
DIFFERENCES IN SYSTEM REQUIREMENTS BETWEEN ONE UNIT AND MULTI-UNIT OPERATION ARE MINOR TVA DOES NOT CONSIDER BROWNS FERRY TO BE MORE SUSCEPTIBLE TO SYSTEM INTERACTION THAN OTHER MULTI-UNIT SITES 7
TVA/NRC MEETING ON MAY 28, 1991d-.
EXPANDED INDIVIDUAL PLANT EXAMINATIONS FOR BROWNS FERRY TOPIC SPOKESMAN PROGRAM TO ADDRESS NRC CONCERNS (CONTINUED)
R. J. McMAHON METHODOLOGY FOR PROPOSED EXPANDED IPE:
DATA ANALYSIS o UNIT 2 DATA BASE AND GENERIC INDUSTRY DATA o WILL APPLY "COMMON" DATA UNIT 2 DEPENDENCY MATRICES WILL BE EXPANDED TO ADDRESS UNITS 1 AND 3 SYSTEM NOTEBOOKS o MAXIMUM UTILIZATION OF UNIT 2 INFORMATION (E.G., UNIT 2 MECHANICAL SYSTEM CONFIGURATION AND SUCCESS CRITERIA ASSUMED VALID FOR UNITS 1 AND 3) o COMMON CAUSE FAILURE ANALYSIS WILL BE ADDRESSED ON A UNIT BASIS FOR MAINTENANCE, SURVEILLANCE, TESTING, OR FAILURE 8
TVA/NRC MEETING ON MAY 28, 199][
EXPANDED INDIVIDUAL PLANT EXAMINATIONS FOR BROWNS FERRY TOPIC SPOKESMAN PROGRAM TO ADDRESS NRC CONCERNS (CONTINUED)
R. J. McMAHON METHODOLOGY FOR PROPOSED EXPANDED IPE (CONTINUED):
LEVEL 1 PLANT MODEL o ONE EVENT TREE FOR ELECTRICAL SYSTEMS o MULTIPLE EVENT TREES FOR MECHANICAL SYSTEMS FRONTLINE EVENT TREES o UNIT 2 FRONTLINE EVENT TREES WILL BE VERIFIED FOR UNITS 1 AND 3 o UNIT 2 HUMAN FACTORS WILL BE DIRECTLY APPLIED TO UNITS 1 AND 3 o COMMON FACTORS WILL BE EVALUATED FOR ALL THREE UNITS o BINNING RULES WILL BE MODIFIED TO CONSIDER THREE UNIT OPERATION o RISKMAN CODE WILL BE REVISED TO INCREASE CAPACITY 9
TVA/NRC MEETING ON MAY 28, 199,9, EXPANDED INDIVIDUAL PLANT EXAMINATIONS FOR BROWNS FERRY TOPIC SPOKESMAN PROGRAM TO ADDRESS NRC CONCERNS (CONTINUED)
R. J. McMAHON METHODOLOGY FOR PROPOSED EXPANDED IPE (CONTINUED):
QUANTIFICATION o EVENT INITIATORS WILL BE SELECTED TO HIGHLIGHT INTER-PLANT INTERACTIONS RECOVERY EVENT TREES o UNIT 2 RECOVERY EVENT TREE WILL BE APPLIED TO UNITS 1 AND 3 FOR SINGLE UNIT RECOVERY ACTIONS o SPECIAL UNIT 3 RECOVERY EVENT TREE WILL BE USED FOR ANY RECOVERY ACTIONS THAT AFFECT MULTIPLE UNITS PLANT MODEL o MULTI-UNIT IPE WILL DETERMINE CORE DAMAGE FREQUENCIES 10
TVA/NRC MEETING ON MAY 28, 199%1Z EXPANDED INDIVIDUAL PLANT EXAMINATIONS FOR BROWNS FERRY TOPIC SPOKESMAN CONCLUSION J. E. McCARTHY
- DESIGN BASELINE PROGRAM FOR UNITS 1 AND 3, IPE, DEPENDENCY MATRICES, AND EXPANDED IPE WILL EVALUATE EFFECT OF SHARED SYSTEMS
- CONCERNS WITH IMPACT OF SHARED SYSTEMS WILL BE ADDRESSED
DISTRIBUTION Docket File NRC PDR Local PDR BFN Rdg. File F. Miraglia 12-G-18 J. Partlow 12-G-18 S. Varga 14-E-4 G. Lainas 14-H-3 F. Hebdon T. Ross J. Williams M. Sanders W. Beckner K. Campe J. Schiffgens B. Wilson RH J. Weschelberger 17-G-21 P. Kellogg RH C. Patterson RH OGC 15-B-18 E. Jordan MNBB-3701 ACRS(10) 1700 1' ~