ML20037C363
| ML20037C363 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 01/22/1981 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | Bauer E PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| References | |
| NUDOCS 8102040743 | |
| Download: ML20037C363 (5) | |
Text
s Q/lpCM
[g/
UNITED STATES 1
NUCLEAR REGULATORY COMMISSION 1,^ Q' [)/
j t.
g WASMNG TON, D. C. 20555 l
gv January 22, 1981 Dockets Nos. 50-277 and 50-278 i
Mr. Edward G. Bauer, Jr.
Vice President and General Counsel Philadelphia Electric Company 2301 Market Street Philadelphia, Pennsylvania 19101
Dear Mr. Bauer:
Your letter dated August 12, 1976 requested certain exemptions from the requirements of 10 CFR 50, Appendix J, Containment Leakage Testing for Peach Bottom Units Nos. 2 and 3.
In the course of our review we have determined that the additional infor-mation, set forth in the enclosure is required. We raquest you provide this information within 30 days of your receipt of this letter.
Sincerely,
^
A i
l 3,(.. n/ }ji.,. - >. n)
Robert W. Reid, Chief Operating Reactors Branch #4 Division of Licensing
Enclosure:
Request for Additional i
l Infomation cc w/ enclosure:
m e \\ c0 i
See next page g
9 a
M g b ~-
,,s. g G,a # j72 3
1 l l f l
4
/
l i
La> '
N l
ie Olb k D u ',
i l
Philadelphia Electric Company cc w/ enclosure (s):
Eugene J. Bradley U. S. Environmental Protection Agency Philadelphia Electric Company Region III Office Assistant General Counsel ATTN: EIS C0ORDINATOR 2301 Market Street Curtis Building (Sixth Floor)
Philadelphia, Pennsylvania 19101 6th and Walnut Streets Philadelphia, Pennsylvania 19106 Troy B. Conner, Jr.
1747 Pennsylvania Avenue, N.W.
M. J. Cooney, Superintendent Washington, D. C.
20006 Generation Division - Nuclear Philadelphia Electric Company Raymond L. Hovis, Esq.
2301 Market Street 35 South Duke Street Philadelphia, Pennsylvania 19101 York, Pennsylvania 17401 Government Publications Section Warren K. Rich, Esq.
State Library of Pennsylvania Assistant Attorney General Education Building Department of Natural Resources Commonwealth and Walnut Streets Annapolis, Maryland 21401 Harrisburg, Pennsylvania 171X Philadelphia Electric Company ATTN: Mr. W. T. Ullrich Peach Bottom Atomic Power S ation Mr. R. A. Heiss, Coordinator Delta, Pennsylvania 17314 Pennsylvania State Clearinghouse Governor's Office of State Planning Albert R. Steel, Chairman and Development Board of Supervisors P. O. Box 1323 Peach Bottom Township Harrisburg, Pennsylvania 17120 R. D. #1 Delta, Pennsylvania 17314 Curt Cowgill U.S. Nuclear Regulatory Corraission Office of Inspection and Enforcement Peach Bottom Atomic Power Station P. O. Box 399 Delta, Pennsylvania 17314 Director, Criteria and Standards Division Office of Radiation Programs (ANR-460)
U. S. Environmental Protection Agency Washington, D. C.
20460
Enclosure lD " " 3
" 3
~ 3
' V M r e o M o N LtinL REQUEST FOR ADDITIONAL INFORMATION CONTAINMENT LEAKAGE RATE TESTING PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM UNITS 2 AND 3 m,aw -
__---:=-
,.---==-a.----m--
N AC DOCKET NO.
50-277, 50-278 NRC TAC NC.
08503, 05504 1
l i
- -- ~~~
i l
9 i
l
,y 1.
BACKGROUND In a letter dated August 12, 1976, Philadelphia Electric Co:pany (PE,CO) requested certain exe=ptions from the requirements of 10CFR50, Appendix J, Contain:en t Leakage Testing.
2.
INFORMATION REQUIRED 2.1 REVERSE DIREC* ION TESTING PECO requested exemption from the require =ents of Appendix J-1973,Section III.C.1, to per=it continued testing of 11 containment isolation valves (each with a noninal diameter of less than 12 in) in the direction oppcsite that inwhich the valves perfor= their safety function (reverse direction testing).
PECO's basis for this request was that' Appendix J-1971 allowed reverse direction testing for valves with a no:inal diameter of less than 12 in and that Peach Sotto: Units 2 and 3 were essentially constructed prior to the issuance of Appendix J-1973.
Where reverse direction testing of isolation valves will not provide results equivalent to, or more conservative than, results obtained from testing in the direction of post-accident containment pressure, a nominal valve diameter of less than 12 in does not provide a basis for exe=ption from Section III.C.1.
Nevertheless, the leak testing of some of these valves may be excluded for other.easons.
For exa=ple, if valve MO-13-al remains water covered through-the post-accident period due to suppression pool level, or if valve MO-10-32 out is effectively water sealed by the discharge pressure-head of the residual heat removal (RHR) pu=ps throughout the post-accident period (in spite of a single active failure in the RHR system), testing in accordance with Appendix J cay not be required. In general, isolation valves which are not relied upon to prevent the escape of containment air to the outside atmosphere during the post-accident period do not require Type C testing in accordance with Appendix J.
For those valves for which reverse direction testing vill not provide -
equivalent or more conservative results, provide a basis 1for exclusion' from Type C testing. Valves for which justification-for exclusion does not exist will require Type C testing in the direction of post-accident pressure.
Zh... Fran;&. Research Center s w n. c,w m e
mW m
OwwUB-vJuuJuAInl.a 2.2 REACTOR BUILDING CLOSED COOLING WATER SYSTEM (PSCCVS) AND CHILLED WATER SYSTEM (CWC) VALVES PECO requested an exe=ption from the Type C testing requirements of
. Appendix J for the containment isolation valves of the F3CCWS and CWS.
Generally, these valves will not require Type.C testing if the respec-tive syste s are closed inside containment and are designed to remain intact fello -ing a postulated LOCA (i.e., designed to engineered-safety-feature system criteria).
Provide an appropriate basis for exclusion of these valves from the Repe C testing require:ents of Appendix J.
t
/h
-2
.... Frankl;n Research Center
- :ww em *,.w-masw.
...