ML20090L715
| ML20090L715 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 10/08/1976 |
| From: | Mayer L NORTHERN STATES POWER CO. |
| To: | Ziemann D US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 9102120556 | |
| Download: ML20090L715 (3) | |
Text
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NSF NOMTHEMN STATES POWEM COMPANY MIN N E A POLI S, MIN N E SOTA 89401 FCO?Y
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October 8, 1976 G)
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Mr D L Ziemann, Chief 6
'3 Operating Reactors Branch No. 2 3 OCT 1
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Dear Mr Ziemann:
8 MONTICELLO NUCLEAR CENERATING FIANT Docket No. 50-263 License Fo. DPR-22 Monticello Confomance to 10CFR50. Appendix J Our submittals dated September 19, 1975, January 30, 1976, May 4, 1976, and May 5,1976, outlined our program for implementing the provisions of 10CFR50, Appendix J at the Monticello Nucicar Generating Plant. Our submittals included a detailed description of the existing provisions for conducting containment icakage testing, a brief description of proposed modificetions to permit testing in several areas to conform to Appendix J, and a request for exemption from Appendix J requirements in other areas.
1 We have been informed by your Staff that a number of items in our submit-l tais require further discussion and resolution.
These items include:
Additional justification must be provided *o a.
exempt Core Spray and Low Pressure Coolant Injection testable check valves f rom Type C Tests.
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Additional justification must be provided to exempt Drywell Spray, Torus Spray, and RILR Recirculation motor operated valves from Type C
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An acceptance criterion for 10 psig airlock c.
tests must be provided which relates the leakage rate at 10 psig to the expected Icakage rate at Paa d.
The manner in which the Appendix J criteria were used for determining which isolation valves require Type C Tests must be explained.
We have been asked by the Staf f to meet with them to discuss and resolve 10256 9102120556 761000 PDR ADOCK 05000263 P
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.ERN OTATEC POWER COf ANY NOR7 j
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Mr D L Ziemann Page 2 October 8,1976 j
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these issues for Monticello.
It is our understanding that there is wide-4 l
spread divergence of opinion on what is required under the current Appen-It may be premature to expect resolution and coamitments to dix J.
possible backfits on a case-by-case basis until guidance has been issued j
A meeting and there has been sufficient opportunity for licensee input.
j with your Staff to discuss our experience with containment leakage testing and the difficulties we have in satisfying certain Appendix J requirements
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would be very useful, however, if it is understood that we do not believe we can make any additional coamitments at this time. We will make arrange-
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ments for such a meeting through our NRC Project Manager for a mutually convenient time later this month.
Because of the number of potentially generic issues that will be discussed, we have asked representatives of the Monticello Architect-Engineer and the Monticello Nuclear Steam Supply Syscem vendor to attend also. Other in-terested utility representatives would also be welcome to attend.
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Yours very truly, i
Y a, a l
L 0 Mayer, PE Manager of Nuclear Support Services 1
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WM Attn:
J W Ferman l
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uissioN ooc"fTNUMD M-1 WI NRC DISTRIBUTION roR PART 50 DOCKET MATERI AL FROM:
Northern States Pwr Co oAlt or oocuutNT TO:
Mr Ziemann 10-8-76 Minneapolis, Mn L 0 Mayer oAtt Rectivr o 10-12-76 CLE TTE R ONoTORitto P R OP INPUT F oRM NUMBER OF COPitS RtCliVt o M oR'G6N AL
@ UNC L AS$1F a t o ice OcoPv ot SC RIP Tio N E NCLoSU RE Ltr te their 9-19-76, 1-30-76, 5-4-76 6..
5-5-76 submitt als..... furnishing info with regard to clarification of Appendix J Requirements.....
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