ML20058K069
| ML20058K069 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 05/26/1989 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | Durr J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| NUDOCS 8906130312 | |
| Download: ML20058K069 (2) | |
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NUCLEAR REGULATORY COMMISSION n.
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May 26, 1989 f
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MEMORANDUM FOR: $55iiTNiFECNAf3 Project Branch No. 1.
Division of Reactor Projects, Region I FROM:
Walter'R. Butler, Director Project Directorate I-2~
,1 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
SUBJECT:
INSPECTION VERIFICATION TO.CLOSE00T FOUR MPA ITEMS IN ACCORDANCE WITH CHANGE NOTICE 88-04 0F THE NRC' INSPECTION MANUAL In accordance with Region I's request that the Licensing Project Man 6g'ers verify the closecut of four MPA' items described in Change Notice 88-04 of the-NRC Inspection Manual, S. Brown, Licensing Project Manager of Shoreham has.
determined that TI2515/93 and TI2515/95 are applicable to Shoreham Nuclear Power Station, Unit 1.
The status for each of the' items discussed in the Temporary Instructions is as follows:
1.
TI2515/93 - Inspection For Verification of Quality. Assurance Request Regarding Diesel Generator Fuel Oil Multi-Plant Action Item A-15.
The purpose of this TI is to verify that the diesel generator oil is included in the plant's quality assurance program under 10 CFR Part' 50 Appendix B requirements. LILCO-is currently required-to perform analysis for diesel fuel oil used in its electric power system and fire suppression system diesels by SNPS Technical Specifications:4.7.7.I.2 and 4.8.1.1.2d.
The methods for sampling and analyzing the diesel fuel oil for these systems are specified in Station Procedure 74.017.01, which was reviewed and approved by the plant's Quality Control organization.
Based on the above, we consider HPA Iten A-15 to be closed.
2.
TI2515/95 - Inspection for Verification of BWR Recirculation Pump Trip Multi-Plant Action Item C-02. The purpose of this.TI is verify that licensees have installed a reactor recirculation' pump trip under conditions indicative of an ATWS event in response to Multi-Plant Action Item C-02.
l LILC0 has installed both required recirculation pump trips (reactor vessel water level-low low and reactor vessel pressure-high) and both are included in the SNPS Technical Specifications, in specification-3/4.3.4, "ATWS Recirculation Pump Trip System Instrumentation." Based on the above, we consider MPA Item C-20 to be closed.
I r
u Walter R. Butler, Director
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Project Directorate'I-2 3
Division of Reactor Projects I/II Office of Nuclear Reactor Regulation S c'l 0 b ) 2 0 # I E
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