PLA-4162, Forwards Vols 1 & 2 of Rept NE-94-001, SSES Individual Plant Exam for External Events (Ipeee), in Response to GL 88-20.IPEEE Addresses Generic Regulatory Issues USI A-45 & GI 57
| ML20070C068 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 06/27/1994 |
| From: | Byram R PENNSYLVANIA POWER & LIGHT CO. |
| To: | Chris Miller Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17158A378 | List: |
| References | |
| REF-GTECI-057, REF-GTECI-A-45, REF-GTECI-DC, REF-GTECI-NI, TASK-057, TASK-57, TASK-A-45, TASK-OR GL-88-20, PLA-4162, NUDOCS 9407010283 | |
| Download: ML20070C068 (2) | |
Text
((@ Pennsylvania Power & Light Company Two North Ninth Street + Allentown, PA 18101 1179
- 610/774 5151 JUN 2 71994 Robert G. Byram Senior Vice President-Nuclear 610/774 7502 x: 610/774 5019 Director of Nuclear Reactor Regulation Attention: Mr. C.L. Miller, Project Director Project Directorate 1-2 Division of Reactor Projects U.S. Nuclear Regulatory Commission Washington, D.C. 20555 SUSQUEll ANNA STEASI ELECTRIC STATION SUllN11TTAL OF Tile IPEEE REPORT Docket Nos. 50-387 PL A-4162 FILES _R41-2/R41-1 D and 50-388
Dear Mr. Miller:
References:
L Letter, PLA-3280, H. IV. Keiser to IV.R. Butler, " Proposed Response to Generic Letter 88-20, Individual Plant Examinations, " dated October 26, I989.
2.
Letter, PLA-3073. H. IV. Keiser to C.L. Miller " Proposed Programfor Completion of IPEEE, " dated Decembc 20.I991.
Enclosed with this letter is PP&l 's response to NRC's Generic Letter 88-20, Supplement 4 requesting an Individual Plant Examination for External Events (IPEEE). Our response is documented in a two volume report entitled "Susquehanna Steam Electric Station Individual Plant Examination For External Events",
NE-94-001, dated June,1994. Overall, the IPEEE effort confirms that Susquehanna SES is well designed and capable of withstanding severe external challenges. The physical condition and cleanliness of the plant were found to be good.
The major result of the fire PRA is that defense-in-depth exists for all fires without credit for Thermo-Lag or other type of fire wrap. That is, multiple equipment remains operable for successful core and containment defense from any realistic fire in Susquehanna SES even if all fire wrap is removed.
Adequate separation and barriers between different divisions of safety equipment is verified.
The screening approach used in analysis of high winds, external floods, and nearby facilities / transportation accidents shows adequate defense against these threns. No weaknesses or plant modifications were identified by this analysis.
Only one seismic observation was found to be significant enough to require immediate action and it has been corrected.
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. FILES R41-2/R41-1D PLA-4162 N1r. C. L. N1 iller The IPEEE report content and format reflects the guidance of NUREG-1407. The risk assessment process utilized to generate the report considered the objectives delineated in Supplement 4 to Generic Letter 88-20: appreciation of severe accident behavior, understanding of the likely event sequences, qualitative understanding of the likelihood of core damage and radioactivity release, and search for cost beneficial risk reduction modifications.
The IPEEE report represents a part of a continuing process of risk evaluation and reduction for Susquehanna Steam Electric Station. PP&L has been actise in addressing severe accident issues since the early 1980s. Our first IPE of the Susquehanna Station was completed in 1986. Later a set of defense-in-depth criteria was developed forjudging our protection against severe accidents. PP&L's IPE for internal events submitted in response to Generic Letter 88-20 (PLA-3696, dated December 13, 1991) utilized these criteria, and they are also utilized with the IPEEE.
The IPEEE addresses two generic regulatory issues: USl A-45, "Shutdow n Decay Heat Removal Requirements" and GI 57," Effects of Fire Protection System Actuation on Safety-Related Equipment" Defense-in-depth of decay heat remosal is demonstrated by the IPEEE and USI A-45 is considered to be satisfactorily resolved. Final resolution of GI-57 for SSES is dependent on the outcome of ongoing analysis of four identified potential equipment impacts from fire protection system water spray. Details regarding this issue are provided in Section 8 of the report.
PP&L believes our IPE and IPEEE work satisfies, and in certain areas, exceeds the requests contained in Generic Letter 88-20. The performance of the IPEEE completes our initial comprehensive assessment of severe accident sequences during power operation and their effect on nuclear safety at Susquehanna SES.
We plan to continue our assessments, particularly with respect to application recommendations and modifications. We anticipate applying the process used to conduct these evaluations to our overall program of risk management at Susquehanna SES.
We look forward to the NRC staffs review.
Should you have any questions, please contact N!r. W.W. Williams at 610 774-5610.
Very truly yours, f,w
/
R. G. I fr n n
Attachment ec:
NRC Document Control Desk (original)
NRC Region 1 N1r. G. S.
Barber, Sr. Resident inspector - SSES Alr. C.
Poslusny, Jr., Sr. Project Nianager - Rockville