ML20215K203
| ML20215K203 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 06/18/1987 |
| From: | Gallagher J PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Butler W Office of Nuclear Reactor Regulation |
| References | |
| GL-87-06, GL-87-6, NUDOCS 8706250255 | |
| Download: ML20215K203 (3) | |
Text
{{#Wiki_filter:_ j d; + PHILADELPHIA ELECTRIC COMPANY 2301 MARKET STREET P.O. BOX' 8699 - PHILADELPHI A. PA.19101 'I .t21e 841 soot JOSEPH W. G ALLAGHER .u.5*/d"ll.'.*I"7... June 18, 1987 Docket No. 50-352 Mr. Walter. Butler,. Director Project. Directorate I-2 Division of Reactor' Projects I/II l U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 i 1
SUBJECT:
-Generic Letter 87-06 Periodic Verification of Leak Tight l
Integrity of Pressure Isolation.: Valves i
Dear Mr. Butler:
( l The subject Generic Letter required licensees " to submit a list of all pressure isolation valves (PIV) in your plant. For each valve, describe the periodic tests or other i measures performed to assure the integrity of the valve as an ( independent barrier at the Reactor Coolant Pressure Boundary (RCPB) along with the acceptance criteria for' leakage, if any, 1 operational. limits, if any, and frequency of test' performances... If current plant Technical Specifications require leak rate j testing for all PIVs in the plant, your reply to that effect will be sufficient." i i Pressure Isolation Valves (PIVs) are defined for each interface as any two valves in series within the reactor coolant pressure boundary which separate the high pressure reactor coolant system from an attached low pressure system. These valves are normally. closed during operation. 1 QR 8706250255 870618 s0 PDR ADOCK 05000352 p PDR . 3 .g t ( i i
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- Mr. Walter R. Butler June 18, 1987 J
Page 2 Y l h1 ' Response L The attached _ table lists Pressure' Isolation Valves (PIV). These valves are included in Table 3.6.3-1 of the Limerick Technical Specifications as containment isolation valves and are therefore leak. tested in accordance with 10CFR50 Appendix J. In addition, j these' valves are also subject to ASME Section XI leak testing ) once per 18 monthsLwith an acceptance criteria of.1 gpm and a test' pressure'of 950 + 10 psig. a.- r., 1 Very truly yours, l 1 b ?!< i,
- l 1
' Attachment -l I cc: ' Addressee E. M. Kelly,' Senior Resident Site Inspector l W. T. Russell, Idministrator, NRC, Region I ' l P I t I r 3. f L t J t l L
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