ML17164A602
| ML17164A602 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 02/21/1995 |
| From: | Poslusny C Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9503020277 | |
| Download: ML17164A602 (20) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055&4001 February 21, 1995 LICENSEE:
Pennsylvania Power
& Light Company FACILITY: Susquehanna Steam Electric Station, Units 1 and 2
SUBJECT:
MEETING
SUMMARY
OF JANUARY 24, 1995 On January 24, 1995, staff from the Office of Nuclear Reactor Regulation (NRR) met with representatives from the Pennsylvania Power
& Light Company (PP&L) in Rockville, Maryland.
The purpose of the meeting was to discuss the contents of the November 21, 1994 PP8L amendment request to delete the main steam isolation valve leakage control system (MSIVLCS) from the Susquehanna Steam Electric Station Units 1
& 2.
Enclosure 1 is a list of those who attended the meeting.
The PP&L staff provided a general discussion of the planned plant modifications, benefits to be realized, the analyses that were conducted in accordance with the BWR Owners Group (BWROG) guidance, and the schedule which is being followed (Enclosure 2).
The licensee indicated that it would like to receive the license amendments by early summer to support outage planning for Unit 2.
PP&L would be removing the Unit 2 LCS in the fall of 1995 and the Unit 1
LCS a year later.
The staff indicated that it has concerns about what earthquake/facility pairs PP&L had chosed to use from the BWROG data base.
In addition, there was a
question about what specific equipment was related to the chosen earthquake data.
The staff also stated that it had some general problems with the BWROG data base but these concerns related to the basis for selected information would be pursued generically with the BWROG.
Other discussion items included the scope and depth of the PP&L bounding seismic analysis, the turbine building analysis, the floor response
- spectra, the methodology used for the "chi over q" analyses 'in the Final Safety Analysis Report, and validation of in-leakage into containment..
It was agreed that the staff would complete its preliminary review of PP&L's submittal in the near term and would send to PP&L two rounds of questions to support the completion of the staff's safety evaluation.
The first, to be sent within a week, will address information concerning the radiological analysis associated with the removal of the LCS.
These questions had been discussed with the staff prior to and during the meeting.
The second set of questions will be sent within 3 weeks of the meeting and will deal with seismic issues and the dynamic analysis completed by PP&L.
0"OGOB 9503020277 95022i'DR ADQCK 05000387 P
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In addition, PP8L indicated that it would be providing a supplemental submittal to address how the proposed modification complies with Appendix A to 10 CFR Part 100 and will also include a request for exemption from Appendix J to 10 CFR Part 50 by February 21st.
It was also agreed that a follow-up working level meeting would be needed to discuss the details of PP8Ls supporting analyses after the RAI responses were received by the staff.
Docket Nos. 50-387/50-388
/s/
Chester
- Poslusny, Project Hanager Project Directorate I-2 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
Enclosures:
1.
List of Attendees 2.
Licensee's Handout cc w/encls:
See next page DISTRIBUTION w encl s 182:
Docket File PUBLIC PDI-2 Rdg.
CAnderson CPoslusny DISTRIBUTION w encl 1:
WRussel 1 /FMiragl i a RZimmerman RLSpessard SVarga Jzwolinski JStolz MO'Brien OGC EJordan ETrottier
OFC NAME DATE PDI-2 LA MO'Brien PDI-2 P
CPoslusny:tlc DI-2/D Stolz OFFICIAL RECORD COPY
'/ /
l' ii In addition, PPLL indicated that it would be providing a supplemental submittal to address how the proposed modification complies with Appendix A to 10 CFR Part 100 and will also include a request for exemption from Appendix J to 10 CFR Part 50 by February 21st.
It was also agreed that a follow-up working level meeting would be needed to discuss the details of PPKLs supporting analyses after the RAI responses were received'y the staff.
Docket Nos. 50-387/50-388
Enclosures:
1.
List of Attendees 2.
Licensee's Handout cc w/encls:
See next page Chester
- Poslusny, Project Nanager Project Directorate I-2 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
i
Pennsylvania Power
& Light Company t
Susquehanna Steam Electric Station, Units 1
& 2 CC:
Jay Silberg, Esq.
- Shaw, Pittman, Potts
& Trowbridge 2300 N Street N.W.
Washington, D.C.
20037 Bryan A. Snapp, Esq.
Assistant Corporate Counsel Pennsylvania Power
& Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Nr. J.
H. Kenny Licensing Group Supervisor Pennsylvania Power
& Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Mrs. Maitri Banerjee Senior Resident Inspector U. S. Nuclear Regulatory Commission P.O.
Box 35 Berwick, Pennsylvania 18603-0035 Nr. William P. Dornsife, Director Bureau of Radiation Protection Pennsylvania Department of Environmental Resources P. 0.
Box 8469 Harrisburg, Pennsylvania 17105-8469 Hr. Jesse C. Tilton, III.
Allegheny Elec. Cooperative, Inc.
212 Locust Street P.O.
Box 1266 Harrisburg, Pennsylvania 17108-1266 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, Pennsylvania 19406 Mr. Harold G. Stanley Superintendent of Plant Susquehanna Steam Electric Station Pennsylvania Power and Light Company Box 467 Berwick, Pennsylvania 18603 Hr. Herbert D. Woodeshick Special Office of the President Pennsylvania Power and Light Company Rural Route 1,
Box 1797 Berwick, Pennsylvania 18603 George T. Jones Manager-Engineering Pennsylvania Power and Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Hr. Robert G.
Byram Senior Vice President-Nuclear Pennsylvania Power
& Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Dr. Judith Johnsrud National Energy Committee Sierra Club 433 Orlando Avenue State College, PA 16803
PPRL MEETING January 24, 1995 NAME Jim Kenny John Schleicher Chet Poslusny Gonzalo Arauz Danny Reinsmith Robert Rothman Arnold Lee Gus Geise-Koch
'ohn Ma Paul O'onnor Dick Wessman Kamal Hanoly Hichael Crowthers David A. Natchick David E.
Shuey Larry Gifford Samir Serhan Scott Boynton Jay Lee ORGANIZATION PP&L PP&L NRC/NRR Gilbert PP&L NRC NRC NRC NRC NRC NRC NRC PP&L PP&L PP&L GE (BWROG)
Gilbert NRC NRC ENCLOSURE 1
SUSQUE A
STEAM ELECTRIC STATION LICENSE NDMENT TO INCREASE MSIV LE GE RATE AND DELETE THE MSIV LE GE CONTROL SYSTEM
> OVERVIEW
> BENEFITS i EVALUATIONS:
~ LEAKRATE
~ SEISMIC i MODIFICATIONS
> SCHEDULE
OVERVIEW INCREASE ALLOWABLEMSIV LEAIMGE FROM 46 SCFH FOR ALLAVIONSTEAMLINES TO 100 SCFH FOR ANY ONE MSIV WITH A TOTAL MAXIMUM LEAIMGEOF 300 SCFH FOR ALLFOUR 5VQN STEAM LINES.
ADD NEW REQUIREMENT TO REPAIR AND RETEST TO 11.5 SCFH FOR ANYVALVENOT MEETING THE 100 SCFH CRITERIA.
REMOVE MSIV-LCS AND UTILIZE MAIN STEAM DR AJN LINEAND CONDENSER ACCOMPLISH QKCHANGES INACCORDANCEWITH BWROG REPORT NEDC-31858P WHICHDETAILSHOW TO EVALUATETHE &BIOLOGICALAND SEISMIC IMPLICATIONS.
BENEFITS REDUCE
&AVIATION EXP OS&&
TO PLANT WORIMRS.
EXTEND EFFECTIVE SERVICE LIFE OF MSIV'S.
MORE EFFECTIVE TREATMENTMETHOD.
EXPANDED OPERATING &&fGE.
NO LOGIC CONTROLS OR INTERLOCKS REQUIRED.
MAJI.'4TAjKSPHILOSOPHY OF MULTIPLEBABMERS.
REDUCE OUTAGE DURATION.
EVALUATIONS:
~ LEAKRATE WK)IOLOGICALEVALUATION:
PERFOKVKD PER NEDC-31858P METHOD BY GE.
SAbdE ASSUIVPTIONS AM)METHODS AS SSES FSAR.
INCLUDES POWER UPRATE.
&V3IOLOGICALCONCLUSIONS:
INSIGNIFICANT INCREASE TO PREVIOUS.
CALCULATEDDOSES.
SIGNIFICANT I'vbWGIN TO DOSE LIMITS hVENTAjQVED.
EVALUATIONS:
> LEAKRATK APPENDIX J CONFORIvb'&ICE CURPXNT EXEMPTIONBASED ON MSIV-LCS.
WILL PROVIDE BASIS FOR TRANSFER3JNG THE EXEMPTION TO THE NEW TREATMENT METHOD AND LEAIMGE RATES BY 2/20/95 TO MEET NRC SCHEDULE NEEDS.
EVALUATIONS:
~ SEISMIC BWROG SEISMIC EXPERIENCE DATABASE.
SEISMIC BOUNDARYDETERMINATIONBY PP8cL.
CONSTRUCTION CODE COMPAjRISON OF SSES TO SEISMIC EXPERIENCE DATABASE.
SEISMIC WALKDOWNS, OUTLIERS EVALUATED8c MODIFIEDAS NECESSARY.
MARGIN ANALYSIS OF PIPING SYSTEM "WEAK LINK"- EXPANSION ANCHOR SELECTED BASED ON H.JDGMENT TO BE WORSE CASE.
CONSERVATIVE, BIASED STAPLE.
ANALYSISRESULTS CONFIRMTHE WALKDOWN RESULTS.
TURBINEBUILDINGDESIGN.
CONDENSER COMPAjRISON TO DATABASE.
CONDENSER ANCHORS ANALYZED.
EVALUATIONS:
~ SEISMIC SEISMIC CONCLUSIONS:
MEET APPENDIXA EXPANSION ANCHOR SAMPLE.
OUTLIEREVALUATIONS.
EXPERIENCE DATABASE.
CONDENSER TURBINEBUILDING
~ MODIFICATIONS ADDRESS OUTLIERS.
PROVIDE DIESEL BACKED POWER TO ISOLATION VALVESANDDRAJN VALVE.
REMOVE MSIV-LCS.
~ SCHEDULE Ab/lEND SUBMITTALBY 2/20/95 APPENDIX A APPENDIX J IMPLEMENTCW&fGES DURjNGU27RIO IN 9/95.
IMPLEMENTCHt'QPGES DUIuNGU19RIO IN 9/96.
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