ML20128J184
| ML20128J184 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 07/01/1985 |
| From: | Daltroff S PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0313, RTR-NUREG-313 IEB-74-10B, NUDOCS 8507100441 | |
| Download: ML20128J184 (2) | |
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PHILADELPHIA ELECTRIC COMPANY 23O1 M ARKET STREET P.O. BOX 8699 PHILADELPHIA. PA.19101 SHIELDS L D ALTMOFF atec a1c en E ion July 1, 1985 Docket Nos. 50-277 50-278 Mr. John F. Stolz, Chief Operating Reactors Branch #4 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C.
20555
SUBJECT:
Peach Bottom Atomic Power Station Units 2 and 3 Reactor Coolant Leakage Criteria
Dear Mr. Stolz:
This letter clarifies the status of a previous commitment made to implement the reactor coolant leakage criteria of IE Bulletin 74-10B, dated January 24, 1975, in light of subsequent developments.
Surveillance Test ST-9.17, " Reactor Coolant Leakage Test", had previously incorporated a " doubled since the previous reading" limit on the rate of change of leakage within a 4-hour period based on the guidance of IE Bulletin 74-10B.
Additionally, ST-9.17 was revised to conform to the action statement in the Bulletin for an immediate shutdown if the leakage limits are exceeded.
Subsequently, the NRC issued new criteria in NUREG-0313, Revision 1, that requested a rate of change limit of 2 gpm increase within a 24-hour period, in addition to the 5 gpm maximum limit.
By letter dated December 3, 1982 (S. L. Daltroff, PECo, to J. F. Stolz, NRC), we committed to meet the requirements of NUREG-0313, and revised ST-9.17 accordingly.
This limit was incorporated into the Peach Bottom Technical Specifications by Amendments Nos. 105 and 109 to Facility Operating Licenses Nos.
DPR-44 and DPR-56 for Units 2 and 3, respectively.
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Mr. John F. Stolz July 1, 1985.
Page 2 As a result of the redundancy of coolant leakage limits in ST-9.17 and the fact that the leakage limit now imposed by the Technical Specifications is a more stringent leakage criteria based on the latest NRC criteria, we are deleting-the " doubled since the previous reading" limit on reactor coolant leakage from ST-9.17.
Further, the action statement in ST-9.17 will be revised to conform to the Peach Bottom Technical Specification, as revised by Amendments Nos. 105 and 109, requiring hot shutdown within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and cold shutdown within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
If you have any questions, please do not hesitate to contact us.
Very truly yours,
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cc:
T.
P. Johnson, Site Inspector
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