ML19247B298
| ML19247B298 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 07/20/1979 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | Bauer E PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| References | |
| NUDOCS 7908080334 | |
| Download: ML19247B298 (4) | |
Text
l.
Y MG
. _t Qg f
UNITED STATES y % v (/[ h NUCLEAR REGULATORY COMMISSION g/
v AsmNGTON, D. C. 20555 7
JULY 2 0 1979 Ncket Nes. 50-277 and 50-287 Mr. Eaward G. Bauer, Jr., Esquire vica cresident and General Counsel Philadelphia Electric Company 4J01 Market Street Philadelphia, Pennsylvania 19101 naar '4r. Bauer:
PEACH BOTTOM ATCMIC STATION, UNITS 2 AND 3 We are reviewing your subnittal dated April 25, 1979 in response to IE Bulletin 79-08.
We have detemined that the additional infomation reouested in the enclosure is necessary in order to ccnplete our safety evaluation.
We request that responses to the items in the enclosure be forwarded to this office within two weeks of your receipt of the enclosure, which was previously transmitted to you by telecopy.
Please contact William F. Kane at (301) 492-7745 if you require additional discussions or clarification regarding the infomation requested.
Sincerely Thomas A. Ippolito, Chi-Operating Reactors Branch #3 Division of Onerating Reactors E ncl osure:
Request for' Additional Infomation cc w/erclosure:
See next page l} ') G)
ONU 7908080 moeero 4
Mr. Edward G. Bauer, Jr.
2 JULY Philadelphia Electric Company 2 0 srg cc:
Eugene J. Bradley Philadelpr.ia Electric Company Assistant General Counsel 2301 Market Street Philadelphia, Pennsylvania 19101 Troy b. Conner, Jr.
17a7 Dennsylvania Avenue, N. W.
Washington, D. C.
20006 Rcyrc.d L. Hovis, Esquire
'; C.ut-Duke Street v <, P.1nsylvania 17401 o
Warren K. P.ich, Esquire
":cistant Attorney General lepartment of Natural Resources Ar.napolis, Maryland 21401 Government Publications Section State Library of Pennsylvania Education Building Commonocalth and Walnut Streets Harrisburg, Pennsylvania 17126 M.' J. Cooney. Supe 'ntendent Generation Division - Nuclear Philadelphia Electric Company 2301 Market Street Philadelphia, Pennsylvania 19101 Edward Greenman U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement PBAPS Site Office General Delivery Conowingo, Maryland 21918 Philadelphia Electric Company ATTN:
Mr. 'W. T. Ull rich Peach Bottom Atomic Power Station Ocita, Pennsylvania 17314 i} () 5' O'JU
ENCLOSURE PEACH BOTTOM 2 & 3 REQUESTS FOR ADDITIONAL INFORMATION IEB 79-08 Item No. 2 1.
Item 2 of IES 79-03 requires that containment isolation initiation design and procedures be reviewed to assure that manual or automatic isolation is initiated for all lines whose isolation does not degrade needed safety features or cooling capability upon all automatic initiations of safety injection. This includes those lines designed to transfer potentially radioactive gases and liquids out of containment. Clarify your response to indicate whether your design and procedures contorm to these ^rquirements.
2.
The isolation procedure for the four conductivity sample lines discussed in your response should be revised to include manual or automatic isolation on all automatic initiations of safety injection.
Provide the results of your engineering design review to determine whether automatic isolation of these lines is required.
3.
Discuss how you intend to provide permanent positive cortrol of the three 3/4-inch lines used for the integrated leak rate test to assure compliance with the requirements of IES 74-08.
4.
Confirm that containment isolation of the Residual Heat Removal Sample Lines is initiated either manually or automatically on all automatic initiations of safety injection.
In addition, provide the results of your engineering design review to determine whether automatic isolation of these lines is required.
5.
Provide a schedule for any actions on item 2 that have not yet been completed.
Item No. 7 1.
Provide the results of your review of the design of systems capable of transferring radioactive gases and liquids out of containment.
2.
Verify that inadvertent transfer of radioactive gases or liquids from containment will not occur on resetting engineered safety features inst:;-
mentation.
3.
Discuss the basis upon which continued operability is assured of the features designed to prevent inadvertent transfer of radioactive gases and liquids out of containment.
7e e-
'~
PEACH BOTTOM 2 & 3 Item No. 3 1.
We understand from your response that operability tests are performed on redundant safety-related systems prior to removal of any safety-related system from service. Since you may be relying on prior operability verifi-cation within the current Technical Specification surveillance interval, operability should be further verified by at least a visual check of the system to the extent practicable, prior to removing the redundant equipment from service. Please supplement your response to provide a commitment that you will revise your maintenance and test procedures to adopt this position.
2.
It is not clear from your response that all involved reactor operational personnel in the oncoming shift are explicitly notified about the status of systems removed from or returned to service. Please indicate how this information is transferred at shift turnover.
Item No. 10 1.
The existing procedures are stated to be under revisien. Please provide your schedule for completion.
d
%