ML20140B879
| ML20140B879 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 03/21/1997 |
| From: | Hunger G PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GL-96-01, GL-96-1, NUDOCS 9704010409 | |
| Download: ML20140B879 (3) | |
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Station Eupport DeprrtmInt A
GL 96-01 iECO NUCLEAR reco % c -
A Unit of PECO Energy N ynI PIi N N t March 21,1997 Docket Nos. 50-352 50-353 License Nos. NPF-39 NPF-85 i
l U. S. Nuclear Regulatory Commission l
Attn: Document Control Desk l
Washington, DC 20555 i
l
Subject:
Limerick Generating Station, Units 1 and 2 Response to Generic Letter 96-01, " Testing of Safety-Related l
Logic Circuits"
Dear Sirs:
Generic Letter (GL) 96-01, dated January 10,1996, " Testing of Safety-Related Logic Circuits," requested Licensees to provide a written response within 60 days of the date of the GL indicating whether or not the licensee will implement the requested actions. Our response to this request was provided in a letter l
dated April 18,1996. Additionally, the GL requested that within 30 days of completion of the requestod actions, a response confirming completion of these actions be submitted to the U. S. Nuclear Regulatory Commission (USNRC).
The following is our response confirmin0 completion of these actions for Limerick Generating Station (LGS), Units 1 and 2.
i As stated in our letter dated April 18,1996, PECO Energy Company (PECO Energy) has defined the scope of GL 96-01 as Technical Specifications required surveillance procedures for systems that are required for either accident mitigation or whoso failura - 11 affect accident mitigation. Having defined the scope, PECO Energy cornmitted to ensuring that these surveillance procedures adequately test safety-related automatic actuation logic circuitry so that a failure of an essential tactric component (e.g., relay, contact) will not be undetected for an extended period of time. Generally, these surveillance requirements are i
l completed by a Logic System Functional Test (LSFT); however, PECO Energy will include other tests, such as channel functional tests, that are intended to
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verify operability of equipment within the scope of GL 96-01.
k As discussed in the action plan contained in the April 18,1996 letter, a thorough review of the licensing basis of LGS would be completed to identify those 4
. systems, structures, and components that satisfy the scope of GL 96-01. For g
LGS, during Surveillance Test (ST) initial development, a thorough methodology I
was employed to ensure all components were tested. To verify that the original i
methodology was maintained through procedure revisions, a review of one logic l
channel of each of the systems within the scope of GL 96-01 would be i
completed. Where there are differences between the logic channels in a j
syMem, a rcview would be completed to ensure that these differences are adequately iested.
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a March 21,1997 i
Page 2 f
l Our review determined that the following systems are within the scope of GL 96-01:
i 1.
Automatic Depressurization System (ADS) i 2.
Core Spray (CS) System t
3.
Reactor Protection System (RPS)/ Scram Discharge Volume (SDV) 4.
High Pressure Coolant injection (HPCI) System 5.
Reactor Core isolation Cooling (RCIC) System 6.
Nuclear Steam Safety Shutoff (NSSS) System 7.
Residual Heat Removal (RHR) System
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8.
Emergency Service Water (ESW) System / Emergency Heat Sink i
9.
Control Room Emergency Fresh Air System (CREFAS)
- 11. Emergency Diesel Generator (EDG)/4 kV 4
)
A review of the LGS, Unit i systems has been completed to satisfy the requested actions of this GL. The LGS, Unit 1 and LGS, Unit 2 systems are i
tested and designed in a similar manner. For LGS, Unit 1, all divisions of the ADS, HPCl, RCIC, ESW/ Emergency Heat Sink, and NSSS were reviewed. One division of the CS, R. S/SDV, RHR, CREFAS, RERS/SGTS, and EDG/4 kV were i
reviewed. The only deficiencies identified were associated with the EDG/4 kV.
1 Three deficiencies (untested contacts) common to all divisions of the EDG/4 kV were identified. The untested contact circuits involve the EDG output breaker trip while in test logic, the off site power voltage monitoring log!c, and the 4 kV load breaker connected position trip logic. Corrective actions were immediately i
taken to compensate for the untested logic. All of the untested contacts were tested, and all but one of the contacts operated correctly. All of the contacts i
have been restored to an operable status. The appropriate ST procedures have i
been permanently revised to incorporate the required testing identified during the review. The untested contacts were the subject of Licensee Event Report 1-97-001 for LGS, Units 1 and 2.
1 if you have any questions, please contact us.
i V ry truly yours, N h.
4 G. A. Hunge, Jr.,
l Director-Licensing j
Attachment, Affidavit I
cc:
H. J. Miller, Administrator, Region I, USNRC N. S. Perry, USNRC Senior Resident inspector, LGS j
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l COMMONWEALTH OF PENNSYLVANIA-l l
ss.
COUNTY OF CHESTER D. B. Fetters, being first duly swom, deposes and says:
That he is Vice President of PECO Energy Company; that he has read the enclosed response to Generic Letter 96-01 dated January 10,1996, for Limerick l
Generating Station Operating Licenses NPF-39 and NPF-85, and knows the 1
contents thereof; and that the statements and matters set forth therein are true l
and correct to the best of his knowledge, information and belief.
l l
{A R
c - - -
l
~ ~ Vice President i
l Subscribed and swom to before me this2/ day of Ovf4b-1997.
YAM 4111 N ary Public
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