ML20005G135

Forwards Summary of Surveillance Tests Completed After Fuel Load for Facility,Per TMI Item III.D.1.1, Primary Coolant Outside Containment

ML20005G135
Person / Time
Site:	Limerick
Issue date:	01/09/1990
From:	Hunger G PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
TASK-3.D.1.1, TASK-TM NUDOCS 9001180180
Download: ML20005G135 (3)

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PHILADELPHIA ELECTRIC COMPANY NUCLEAR GROUP HEADQUARTERS I

955 65 CHESTERBROOK BLVD.

WAYNE, PA 19087-5691

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!.aisi u o-sooo January 9, 1990 Docket No. 50-353 License No. NPF-85 i

i U.S. Nuclear Regulatory Cownission Attn:. Document Control Desk Washington, DC 20555

SUBJECT:

Limerick Generating Station Unit 2 l

,A PrimaryCoolantOutsideContainment(TNIItem 111.0.1.1)

REFERENCE:

_(1) Letter,J.S.Kemper(PEco)toA.Schwencer(NRC),

7 dated September 12, 1984 (2) Letter,G.A. Hunger,Jr.(PECo)toDocumentControlDesk(NRC),

dated July 14, 1989 Gentlemen:

l The Reference (1) letter committed to perform sixteen leakage reduction surveillance-tests to sat'isfy the program described in the Limerick Generating Station (LGS) Final Safety Analysis Report (FSAR) Section 6.2.8.

Leakage limits for Unit 2 were established for each of these systems based on LGS Unit 1 data prior to these tests. Eight of these tests were completed prior to fuel load and the results j-were provided in Reference (2). The remaining surveillance tests were completed t

after fuel load and the test results for all the tests are susunarized in the

~ Attachment.

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If you have any questions regarding this matter, please contact us.

Very truly yours, h

a G. A. Hunger, Jr.

Director Licensing Section 9

p$11001809001opADOCK 05000353 l

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Nuclear Services Department PDC Attachment 0k cc:

W. T. Russell, Administrator, Region I, USNRC 9

T. J. Kenny, USNRC Senior Resident Inspector LGS

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ATTACHMENT s

Leakage Reduction Program Initial' Surveillance Tests

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Established Tsst No.-

Test ID Number-Title Status Goal Results

.I-ST-1-030-700-2 Post Accident Sampling System Liquid Sample Complete:

I gpm Acceptable loops Contaminated Piping Inspection 2

ST-1-030-701-2 Post Accident Sampling System (PASS) and Complete 100 scc / min / loop Note 1 Containment Atmospheric Control (CAC) Sample Loops Contaminated Piping Inspection 3

ST-1-047-700-2 Scram Discharge Volume Complete I gpm Acceptable Contaminated Piping Inspection 4

ST-1-049-701-2 Reactor Core Isolation Cooling Pump Complete 1 gpm Acceptable Contaminated Piping Inspection 5

ST-1-049-702-2 Reactor Core Isolation Cooling Turbine Complete 1 gpm Acceptable Contaminated Piping Inspection 6

ST-1-051-701-2 A Residual Heat Removal Loop Contaminated Complete 1 gpm Acceptable Piping Inspection.

7 ST-1-051-702-2 B Residual Heat Removal loop Contaminated Complete 1 gpm Acceptable Piping Inspection 8

ST-1-051-703-2 C Residual Heat Removal Loop Contaminated Complete 1 gpm Acceptable Piping Inspection 9

ST-1-051-704-2 D Residual Heat Removal Loop Contaminated Complete 1 gpm Acceptable Piping Inspection 10 ST-1-052-701-2 A Core Spray Loop Contaminated Piping Complete 1 gpm Acceptable Inspection il ST-1-052-702-2 B Core Spray Loop Contaminated Piping Complete I gpm Acceptable

' Inspection 12

- ST-1-052-705-2 Safeguard Piping Fill System Contaminated Complete 1 gpm Acceptable Piping Inspection e

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Page 2 ATTACHMENT (Cont'd) teakage Reduction Program Initial Surveillance Tests Established Test No.

Test ID Number Title Status Goal Results i

13 ST-1-055-701-2 High Pressure Coolant Injection Pump Complete I gpm '

Acceptable-Contaminated Piping Inspection 14 ST-1-055-702-2 High Pressure Coolant Injection Turbine Complete I gpm Acceptable Contaminated Piping Inspection-15 ST-1-058-701-2 A Post LOCA Recombiner Complete 150 scc / min Acceptable Contaminated Piping Inspection-16 ST-1-058-702-2 B Post LOCA Recombiner Complete 150 scc / min Acceptable Contaminated Piping Inspection OTES:

s1) System leakage for the PASS and CAC Sample Loops is determined for six individual boundaries.. Boundaries 2, 4, 5, and 6 were acceptable. Maintenance Request Forms (MRFs) were initiated to correct leakage in excess of the goals for Boundaries 1 and 3.

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