ML19350B843
| ML19350B843 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 02/23/1981 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Kay J YANKEE ATOMIC ELECTRIC CO. |
| References | |
| NUDOCS 8103230840 | |
| Download: ML19350B843 (4) | |
Text
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February 23, 1981 e....
Docket No. 50-29 LS05-81-02-048
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Mr James A. Kay Senior Engineer-Licensing d
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Framingham, Massachusetts 01 701
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Dear Mr. Kay:
D'y During our review of your request for exemption from certain requirements of 10 CFR 50, Appendix J, for Yankee-Rowe, we have determined that additional information is needed.
Please respond to the attached request for information within 30 days of your receipt of this letter so that we may complete oar review in a timely manner.
Sincerely, Dennis M. Crutchfield, ief Operating Reactors Branch #5 Division of Licensing cc w/ enclosure:
See next page 8103230W O g
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Mr. James A. Kay February 23, 1981 cc Mr. James E. Tribble, President Yankee Atomic Electric Company 25 Research Drive Westborough, Massachusetts 01581 Greenfield Coanunity College 1 College Drive Greenfield, Massachusetts 01301 Chairman Board of Selectmen Town of Rowe Rowe, Massachusetts 01367 Energy Facilities Siting Council 14th Floor One Ashburton Place Boston, Massachusetts 02108 Director, Criteria and Standards Division Office of Radiati'on Programs (ANR-460)
U. S. Environmental Protection Age ncy -
Washington, D. C.
20460 U. S. Environmental Protection Agency Region I Office.
ATTN: EIS C0ORDINATOR JFK Federal Building Boston, Massachusetts 02203 Resident Inspector Yankee Rowe Nuclear Power Station c/o U.S. NRC Post Office Box ~ 28 Monroe Bridge, Massachusetts 01350 m
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1.
BACKGROUND By a letter dated February 7, 1977, Yankee Atomic Electric Company (YAEC) requested certain exemptions from the requirements of 10CFR50, Appendix J, for Yankee Rowe.
2.
INFORMATION REQUIRED 2.1 INCOMING LINES CONTAINING CHECK VALVES In paragraph 3.0 of the February 7,1977 letter, exemptions from the testing requirements of Appendix J were requested for check valves listed in Section B of Table 3.6-1 to the Technical Specifications (Amendment 27).
YAEC stated that these valves (except for HC-V-1199) are in lines which are liquid filled at a pressure in excess of peak calculated accident pressure (Pa) and have a 30-day supply of water available. To provide an acceptable basis for exemption, these lines must be designed to remain intact post-accident (i.e., no reliance on nonsafety-related boundaries), and no single active failure can cause a loss of the 30-day water supply.
With regard to valve HC-V-1199, YAEC stated that it is in a 15-psig steam line forming a closed loop both inside and outside the containment. To justify an exemption in this case, the closed loop inside containment must be designed to remain intact post-accident.
Provide justification required to support'the above exe=ption requests.
2.2 MANUAL VALVES IN LINES PENETRATING CONTADMENT In paragraph 3.0 of the same letter, exemptions from the testing require-ments of Appendix J were requested for certain manual valves in lines pene-trating the containment that are not subjected to Type C tests.
Provide additional justification for exemption of the following valves:
a.
SC-MOV-551, 552, 553, and 554 (Shutdown Cooling) and CH-MOV-522 (MC Feed to Loop Fill Header). Describe the method (e.g., hydrostatic test, etc.) used to verify that the closed systems outside containment will remain water filled for the 30-day post-accident period such that these penetrations can not become potential atmos-pheric leakage paths. -
b.
CA-V-746 (Containment Air Charge). Describe the ability of the service air system to remain pressurized to 100 psig post-accident, including the consideration of a possible single active failure.
.