ML17159A205
| ML17159A205 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 03/09/1998 |
| From: | Nerses V NRC (Affiliation Not Assigned) |
| To: | NRC (Affiliation Not Assigned) |
| References | |
| TAC-M74478, TAC-M74479, NUDOCS 9803190294 | |
| Download: ML17159A205 (35) | |
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March 9, 1998 I ICENSEE:
Pennsylvani wer and Light Company (PP8L)
FACILITY:
Susquehanna Steam Electric Station (SSES), Units 1 and 2
SUBJECT:
MEETING WITH PP&L STAFF CONCERNING THE REVISION TO THE SSES, UNITS 1 AND2, INDIVIDUALPLANT EXAMINATION(IPE) (TAC NOS.
M74478 and M74479)
On February 27, 1998, NRC staff met with representatives of PP&L. A list of attendees is contained in Enclosure 1. The purpose of the meeting was to discuss the revision to the IPE.
PP8L discussed the remaining IPE issues on human error analysis, common cause failure analysis, and the "backend" analysis and the work performed to address these issues.
The information and the proposed schedule for completion of the work is summarized in Enclosure 2 The staff noted that PP8L appeared to have adequately addressed the issues and considered a
trip to PP&L to audit the work that PP8L had done.
The staff concluded that PP&L's scheduled submittal by March 31, 1998, will not be necessary because both parties agreed that a staff trip in March 1998 to audit the PP&L work may be sufficient to complete the information the staff needs to write their IPE closure safety evaluation.
/s/
Victor Nerses, Senior Project Manager Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket Nos. 50-387 and 50-388
Enclosures:
- 1. List of Attendees
- 2. Licensee Handouts cc w/encls:
See next page
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 9, 1998 LICENSEE:
Pennsylvania Power and Light Company (PP&L)
FACILITY:
SUBJECT Susquehanna Steam Electric Station (SSES), Units 1 and 2 MEETING WITH PPB L STAFF CONCERNING THE REVISION TO THE SSES, UNITS 1 AND2, INDIVIDUALPLANT EXAMINATION(IPE) (TAC NOS.
M74478 AND M74479)
On February 27, 1998, NRC staff met with representatives of PPB L. A list of attendees is contained in Enclosure 1. The purpose of the meeting was to discuss the revision to the IPE.
PP&L discussed the remaining IPE issues o'n human error analysis, common cause failure analysis, and the "backend" analysis and the work performed to address these issues.
The information and the proposed schedule for completion of the work is summarized in Enclosure 2.
The staff noted that PP&L appeared to have adequately addressed the issues and considered a trip to PPB L to audit the work that PPB L had done.
The staff concluded that PP&L's scheduled submittal by March 31, 1998, will not be necessary because both parties agreed that a staff trip in March 1998 to audit the PPB L work may be sufficient to complete the information the staff needs to write their IPE closure safety evaluation.
Docket Nos. 50-387 and 50-388
Enclosures:
- 1. List of Attendees
- 2. Licensee Handouts cc w/encls:
See next page Victor Nerses, Senior Project Manager Project Directorate l-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
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Pennsylvania Power 8 Light Company Susquehanna Steam Electric Station, Units18 2 CC:
Jay Silberg, Esq.
Shaw, Pittman, Potts 8 Trowbridge 2300 N Street N.W.
Washington, D.C. 20037 Bryan A. Snapp, Esq.
Assistant Corporate Counsel Pennsylvania Power 8 Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Licensing Group Supervisor Pennsylvania Power 8 Light Company 2 North Ninth Street Allentown, Pennsylvania I8I01 Senior Resident Inspector U. S. Nuclear Regulatory Commission P.O. Box 35 Berwick, Pennsylvania 18603-0035 Director-Bureau of Radiation Protection Pennsylvania Department of Environmental Resources P. O. Box 8469 Harrisburg, Pennsylvania 17105-8469 Regional Administrator, Region I
U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, Pennsylvania 19406 General Manager Susquehanna Steam Electric Station Pennsylvania Power and Light Company Box 467 Berwick, Pennsylvania 18603 Mr. Herbert D. Woodeshick Special Office of the President Pennsylvania Power and Light Company Rural Route 1, Box 1797 Berwick, Pennsylvania 18603 George T. Jones Vice President-Nuclear Operations Pennsylvania Power and Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Dr. Judith Johnsrud National Energy Committee Sierra Club 433 Orlando Avenue State College, PA 16803 Mr. Jesse C. Tilton, III Allegheny Elec. Cooperative, Inc.
212 Locust Street P.O. Box 1266 Harrisburg, Pennsylvania 17108-1266 Chairman Board of Supervisors 738 East Third Street Berwick, PA 18603 Mr. Robert G. Byram Senior Vice President-Generation and Chief Nuclear Officer Pennsylvania Power and Light Company 2 North Ninth Street Allentown, PA 18101
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LIST OF ATTENDEES MEETING BETWEEN NRC AND PENNSYLVANIAPOWER AND LIGHT REGARDING REVISION TO THE INDIVIDUALPLANT EXAMINATION SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND2 FEBRUARY 27, 1998
~Agg V. Nerses W. Hodges M. Drouin E. Lois A. Rubin J. Chen G. Miller J. Kenny G. Butler M. Simpson T. Roscioli C. Kukielka E. Jebsen S. Maingi 0
G NRC/NRR NRC/RES NRC/RES NRC/RES NRC/RES NRC/RES PP8L PP&L PP8L PP8L PP8L PP8L PP8L State of Pennsylvania ENCLOSURE 1
gUgQUEHANNA IPK MEETING 2/27/9S Agenda
~ purpose ofMeeting
, ~ Key Issues
~ How PPL Addressed Key Issues
~ Results Summary
'. ~ Closure Strategy/Schedule
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PURPOSE OF THIS MEETING Review Work Performed to Address ssues
~ Identify any Remaining Issues I
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Reach Agreement on Closure Strategy an Schedule
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KEYISSUES
~ Human Error Analysis
~ Common Cause Failure Analysis
~ Uncertainty Analysis
~ Back End Analysis
HUMANERROR ANALYSIS
SUMMARY
OF ISSUE
~ Pre-initiator Errors Associated With Tests and Maintenance
~ Control Room Implementation ofEOPs
~ Plait Implementation ofEOPs
~ Recovery Actions
I I HUMANERROR ANALYSIS WORK TO ADDRESS ISSUE
~ Third Party Review ofHRAMethod
~ Reviewed Latest HRALiterature Including G 115Q and Other IPE/PRAs
~ Reviewed Plant Surveillances arid History to Determine Additional Potential Impacts
~ Performed a Detailed HRA Review ofEOPs
" ~ Formally Incorporated Additional Human Errors for the Categories Identified Above Including Uncertainties
HUMANERROR ANALYSIS CONCLUSIONS
~ Human Error Re-quantification Modifies SSES CDF Results and Increases the Range ofResults
COMMONCAUSE FAILUREANALYSIS
SUMMARY
OF ISSUE
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~ CCF Associated with Tests, Calibration, and Maintenance
~ CCF Associated withLike Active Components
~ Inter-System CCF
COMMON CAUSE FAILUREANALYSIS WORK TO ADDRESS ISSUE
~ Third Party Review ofCCF Method
~ Reviewed Latest CCF Literature Including G 1150 and Other IPE/PRAs
~ Reviewed Plant Surveillances and: History to Determine Potential Impact
~ Formally Incorporated Additional CCF for the Categories Identified Above Including Uncertainties
COMMONCAUSE FAILUREANALYSIS CONCLUSIONS
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~ CCF Re-quantification Modifies SSES CDF Results and Increases the Range ofResults
~ CDF Increases for Many Sequences Due to
'dditional CCF I
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g UNCERTAINTYANALYSIS
SUMMARY
OF ISSUE e
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~ Lack ofUncertainty Analysis
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~1 PFg-UNCERTAINTYANALYSIS WORK TO ADDRESS ISSUE S Developed Upper and Lower Bounds for Plant Data
~ Developed Upper and Lower Bounds HRA Data Derived from Plant Experience and Simulator Exercise
.. ~ Used Bounds Provided By Generic Data
~ Re-quantified Susquehanna IPE Incorporating Uncertainty r
UNCERTAINTYANALYSIS CONCLUSIONS a Results Now Include the Uncertainty Range vs. A Point Estimate
BACKKNDANALYSIS
SUMMARY
OF ISSUE
~ High Rate of Success at Terminating the Damage Progression In-vessel a Limited Treatment ofCore Debris Ex-'vessel i
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-,l High Pressure Melt Ejection
-:"- Core Concrete interaction
~ Lack ofOther Damage Progression Scenarios I
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BACKEND ANALYSIS WORK TO ADDRESS ISSUE S Evaluated Impact ofDamage Progression Modeling on ~Containment Perfonnance
~ Re-evaluated the Probability ofHigh Pressure Melt Ejection for SSES
~ Incorporated G/CR-6025 Findings on Treatment ofDebris Coolability Ex-vessel l
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. BACKEND ANALYSIS CONCLUSIONS
~ Evaluation ofAdditional Damage Progression Scenarios Produces a Wide Range of Consequences
~ Use ofMELCOR/BWRSARInstead of
-3B/4 Produces Significant Differences in Damage Progression and Consequences
SUMMARY
OF CONCLUSIONS ADDRESSING KKYISSUES
~ Human Error and CCF Re-quantification Increase the Range for the CDF Value
~ Additional Accident Evaluations Increase the Range ofConsequences
~ Revised Results for SSES Address NRC Issues and GL 88-2Q Objectives
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CLOSURE STRATEGY/SCHEDULE
~ Review Any Open Items From This Meeting to Address Closure Plan
~ Submit Report in Form Agreed to at This Meeting by March 31, 1998
~ Support Final NRC Review
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March 12, 1998 MEMORANDUMTO: John A. Zwolinski, Acting Director Division of Reactor Projects - I/II FROM:
SUBJECT:
John F. Stolz, Director Project Directorate I-2 Division of Reactor Projects - I/II DELEGATIONOF AUTHORITY During my absence from the office on March 13,'1998 (while in on sick leave),
I have designated Bartholomew C. Buckley Acting Director. Mr. Buckley can be reached on 415-1483 t
and found in Room 14F-14.
cc: PDI-2 Staff DIS U 0 Central File PDI-2 Readin OFFICE NAME DATE PDI-2/PM Stolz:rb
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98 OFFICIAL RECORD COPY DOCUMENT NAME: DELEG.MEM
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