ML20127B965
| ML20127B965 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley, 05000000 |
| Issue date: | 08/07/1984 |
| From: | Parr O Office of Nuclear Reactor Regulation |
| To: | Knighton G Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20126J910 | List: |
| References | |
| FOIA-84-926 NUDOCS 8408220120 | |
| Download: ML20127B965 (2) | |
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'o UNITED STATES
[
g NUCLEAR REGULATORY COMMISSION g
't WASHINGTON, D. C. 20555
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ggg 7 1934 MEMORANDUM FOR:
G. Knighton, Chief Licensing Branch #3, DL FROM:
- 0. D. Parr, Chief Auxiliary Systems Branch, DSI
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION FOR BEAVER VALLEY POWER STATION, UNIT 2 - AUXILIARY SYSTEMS BRANCH In the process of re-reviewing and updating the Auxiliary Systems Branch draft safety evaluation report (DSER) for Beaver Valley Power Station, Unit 2, to reflect the applicant's responses to the previously identified open items, we have identified two additional items that need to be addressed by the applicant. These concerns are identified in the enclosure.
Please expedite the applicant's response in order to permit their resolution prior to submittal of our final SER input.
b
. D.
arr,' Chief Auxiliary Systems Branch Division of Systems Integration
Enclosure:
As stated cc:
R. Bernero l
L. Rubenstein T. Novak J. Wenniel J. N. Wilson M. Licitra M. Ley R. Anand
Contact:
R. Anand, D
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c0 REQUEST FOR ADDITIONAL INFORMATION BEAVER VALLEY POWER STATION, UNIT 2 AUXILIARY SYSTEMS BRANCH l
i l
1.
In regard to internally generated missile protection inside and outside of containment (i.e., SRP Section 3.5.1.1 and 3.5.1.2), we are unable l
to confirm that you have properly assumed a single active failure concurrent with postulated internally generated missiles. Verify that redundant safety-related trains are protected from damage which may result from the impact of missiles generated fron nonsafety-related sources consistent with the guidelines of Position C.2 of Regulatory Guide 1.29, 2.
Verify that the instrumentation provided for indication of los.; of component cooling water to the reactor coolant pumps is safety grade (in accordance with IEEE 279) as identified in Part 4d. of the Review Frocedures of SRP Section 9.2.2.
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