ML20213D009
| ML20213D009 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 07/09/1979 |
| From: | Denise R Office of Nuclear Reactor Regulation |
| To: | Varga S Office of Nuclear Reactor Regulation |
| References | |
| CON-WNP-0281, CON-WNP-281 NUDOCS 7908030409 | |
| Download: ML20213D009 (3) | |
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Central Files FIN R/F CPB R/F JUL 9 1979 RP0enise MEMORANDUit FOR: Steven A. Varga, Acting Assistant Director for Light Water Reactors, DPM FROM:
Richard.P. Denise, Acting Assistant Director for Reactor Safety, DSS
SUBJECT:
STAFF POSITIONS FOR WNP, UNIT 2 Plant Name:
Washington.Public Power Supply System, Unit 2 Docket No:
50-397 Milestone flumber:
12-24 Licensing Stage:
OL Responsible Branch LWR f4 and Project Manager:
M. D. Lynch Systems Safety Branch Involved:
Core Perfomance Branch Description of Review:
Staff Positions Requested Completion Date:
M y 9, 1979 The Reactor Fuels Section of the Core Performance Branch has prepared the enclosed staff positions for WMP-?.. The Reactor Physics Section j
has no further questions.
/
Richard P. Denise, Acting Assistant i
Director for Reactor Safety Division of Systems Safety
Enclosure:
As stated cc:
R. Denise R. Mattson/F. Schree' der L. Rubenstein M. Lynch R. Meyer D. Fieno D. Houston W. Brooks
Contact:
D. Houston, x 27603 7 9080y0 40'i W. Brooks, x27577 I
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JUL S 1379 MEMORAflDUt1 FOR: Steven A. Varga, Acting Assistant Director for Light Water Reactors, DPt1 FROM:
Richard P. Denise, Acting Assistant Director for Reactor Safety, DSS
SUBJECT:
STAFF POSITI0f4S FOR Wi1P, UilIT 2 Plant f!ame:
Washington Public Pcder Supply System, Unit 2 Docket flo:
50-397 Milestone fiumber:
12-24 Licensing Stage:
OL Responsible Branch LWR #4 and Project Manager:
li. D. Lynch Systems Safety Branch Involved:
Core Perfontance Branch Description of Review:
Staff Positions Requested Completion Date:
May 9, 1979 The Reactor Fuels Section of th'e Core Performance Branch has prepared the enclosed staff positions for UtlP-2. The Reactor Physics Section has no further questions.
2 kkd T Richard P. Denise h g Assistant Director for Reactor Safety Division of Systems Safety
Enclosure:
As stated cc:
R. Denise R. Mattson/F. Schroeder L. Rubenstein M. Lynch R. Meyer D. Fieno D. Houston W. Brooks
Contact:
D. Houston, x 27603 W. Brooks, x27577 e
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Staff Positions WNP-2 Reactor Fuels 231.3 Your response to our previous question concerning fuel surveillance and fuel rod failure detection is inadequate. You state that the FSAR was prepared in accordance with Revision 2 of Regulatory Guide 1.70, yet paragraph 7 of Section 4.2.1 of the noted guide requests a discussion of your surveillance program. Such a provision should not alter the design of your plant in any way. Therefore, provide a discussion of the WNP-2 fuel surveillance program.
Also, we would believe that instrumentation exists to monitor radio-activity in the steam and coolant systems. The instrumentation should provide some indication of fuel rod failures. Our request is for WNP-2 to provide a description of these systems (can be done by referencing other FSAR sections) and discuss their application in regard to detecting fuel red failures.
231.4 The BWR/4 and BWR/S topical report fails to discuss the intended lifetime for the 8 C control blades. General Electric has recently 4
informed NRC that the prior design limit of 40% burnup of the B-10 content will lead to failure of some control rods. A new design limit of 32% burnup of the B-10 content has been recommended.
Confirm that UNP-2 is aware of this change in control rod design l i fe.
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