ML20079P274
| ML20079P274 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 01/26/1984 |
| From: | Daltroff S PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20079P277 | List: |
| References | |
| NUDOCS 8401310153 | |
| Download: ML20079P274 (2) | |
Text
e-8 PHILADELPHIA ELECTRIC COMPANY 23O1 M ARKET STREET P.O. BOX 8699 1881 -1981 PHILADELPHIA. PA.19101 SHIELDS L. DALTROFF n:E?U"/U'*do-January 26, 1984 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 License Amendment Application on Shock Suppressors (Snubbers)
Dear Mr. Stolz:
In response to requests per telephone conversations from the Peach Bottom Project Manager to our Licensing Section, attached is the proposed Technical Specification Table 3.11.L.1,
" Safety-Related Shock Suppressors (Snubbers)", for Peach Bottom Atomic Power Station, which is a compilation of the changes to the existing Technical Specification Table resulting from numerous modifications and as submitted in our March 24, 1981, August 6, 1981, December 13, 1982, and June 22, 1983, Amendment Applications.
Changes relative to the addition of snubbers, deletion of snubbers, or changes in snubber designation number, from our existing Technical Specification Table 3.11.D.1 are indicated by a vertical bar in the margin.
The attached Table replaces the Table 3.11.D.1 as submitted in our [[letter::05000277/LER-1983-014-03, /03L-0:on 830812,control Room Fire Barrier Discovered W/O Fire Damper in One Ventilation Duct Penetration.Caused by Damper Not Incorporated Into Original Ventilation Sys Installation.New Damper on Order|September 14, 1983, letter]] (J. S. Kemper, PECo, to G. E. Gears, NRC) and is provided in total, since the format in our existing license has also been changed to comply with the Standard Technical Specifications as required by Mr. D. G. Eisenhut's [[letter::05000277/LER-1980-025-03, /03L-0:on 801103,setpoints on DPIS 2-13-83 & DPIS 2-13-84 (Redundant Reactor Core Isolation Cooling Turbine Steam Line High Flow DPIS Instrumentation) Exceeded Tech Specs.Caused by Setpoint Drift.Instruments Recalibr|letter dated November 20, 1980]].
8401310153 840126 PDR ADOCK 05000277 P
PDR N
dO i
i x
i
a e
Mr. John F. Stolz Page 2 If you have any questions or require additional information, please do not hesitate to contact us.
Very truly yours, l
l
^
/, /
lLL Lv Attachments cc:
A. R. Elough, Site Inspector D. R. Haverkamp, Region I, NRC l
l
(
l I
l I
l l
h