ML20246N430
| ML20246N430 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 03/21/1989 |
| From: | Kemper J PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 8903270373 | |
| Download: ML20246N430 (3) | |
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,:s' PHILADELPHIA ELECTRIC COMPANY 2301 MARKET STREET P.O. BOX 8699 PHILADELPHIA. PA,19101 i
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MAR 211989
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23NIOR VICE PRESIDENT. NUCLE AR U. S.' Nuclear Regulatory Ccmnission Docket No. 50-353 Attn: Document Control Desk-
. Washington, D.C. 20555-
Subject:
Limerick Generating Station, Unit 2 Changes to Final Safety Analysis Report Since Unit 1 Licensing
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Reference:
Letter, J. S. Kemper (PECo) to NRC Docunent Control Desk dated February 24, 1989.
Gentlemen:
In the. referenced letter, Philadelphia Electric Company (PECo) provided the results of its assessment of each change identified in the Limerick Generating Station Final Safety Analysis Report (FSAR).
Appendix B to identify those with the potential to impact the NRC's Safety Evaluation Report. The attachment to this letter repeats the information from the February 24, 1989 letter and supplements it to in-clude.FSAR Revision 57.
For each Revision 57 change identified in Appendlx B, PECo reviewed the corresponding SER sections to determine whether the information con-tained therein was accurate in light of the FSAR change. For the FSAR changes listed in the attachment t9 this letter, PECo found that the FSAR information differed frtxn that contained in the corresponding section of the SER, suggesting th;t NRC review of that change and subsequent updating of the SER might be appropriate. For the remainder of the FSAR changes assessed, PECo identified no impact on either the content or conclusions 1
presented in the SER.
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8903270373 890321 f
PDR ADDCK 05000353.
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- U. S. Nucle:r R:gulctory Conmission l'
Dock t'No. 50-353 Page 2 Similar infonnation associated with any future FSAR revisions will be provided shortly after their submittal.
If PECo can provide any additional assistance or you have questions l-
' regarding any of the items in the IIsting, please contact H. D.
I' Honan of the PECo LGS-2 Licensing Branch.
l S i nce rely,
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1 ERG /ds/02218902 Attachment Copy to:
R. A. Granm, Unit 2 Senior Resident Inspector W. T. Russel l,. Region I Achinistrator R. d. Clark, LGS Project Manager l
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ATTACFf4E9 T
' LIMERICK GENERATING STATION, UNIT 2 FINAL SAFETY ANALYSIS REPORT. APPENDIX B:
j REVISION SUH4ARY DESCRIPTIONS (5)
ITEMS WITH POTENTIAL IMPACT ON THE l
L NRC SAFETY EVALUATION REPORT (1)
From Revisions 44 through'52:
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.B.4.5
' B.6.2(2X33 B.9.6 B.1.2 B.2.3 B.4.8 '
B.6.3 B.9.7
- B. 2. 4 '
B.4.11 B.7.1(2)
B.9.8
'B.2.6 B.4.12 B.8.1
.B.9.17 B.2.11 B.4.16 B.8.4(2)(3)
B.9.25(2(3)-
.B.3.6 B.5.3.
B.8.6 B.9.27 B.4.2~
B.5.6 B.8.12(2)
B.9.28 B.4.4 B.5.11(2).
B.9.3 B.9.50(2X4)
From Revision 53:
B.10.1 From Revision 55:
B.12.I' From Revisions 54 and 56:
B.1h1(2)
B.11,8 B.11.31 B.13.2.
B.11.2 B.11.12(2)
B.11.35 B.13.3(2)
B.11.4 B.11,24 B.11.36'.
B.13.5(2)
B.11.5-B.11.2C(2)
B.11.58 B.13.8 B.11.7 From Revision 57: B.14.1(2) and B.14.17 Notes:
(1) Unit 1/2 differences with no SER impact are not IIsted.
(2) Unit 1/2 differences.
(3) Unit 1/2 differences previously approved by NRC via letter SER.
(4) NRC approval requested via letter from J. S. Kemper to R.J. Clark, dated dune 21, 1988.
(5) Revision Samary Descriptions for Revisions 53 througn 56 were re-ntsrbered in RcIslon 57 with no change in content.
4 ERG /ds/02218902.
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