05000336/LER-1984-005, Confirms That Rev to LER 84-005 Will Be Submitted within 2 Months,Clarifying Performance of Type A,B & C Testing During 1983 Refueling Outage as Discussed in 860604 Meeting

Confirms That Rev to LER 84-005 Will Be Submitted within 2 Months,Clarifying Performance of Type A,B & C Testing During 1983 Refueling Outage as Discussed in 860604 Meeting

ML20206J592
Person / Time
Site:	Millstone
Issue date:	06/18/1986
From:	Opeka J NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
To:	Thadani A Office of Nuclear Reactor Regulation
References
B12129, TAC-60646, NUDOCS 8606270208
Download: ML20206J592 (3)

LER-2084-005, Confirms That Rev to LER 84-005 Will Be Submitted within 2 Months,Clarifying Performance of Type A,B & C Testing During 1983 Refueling Outage as Discussed in 860604 Meeting

Event date:
Report date:
3362084005R00 - NRC Website

text

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, , (203) 665-5000 June 18,1986 Docket No. 50-336 B12129 Office of Nuclear Reactor Regulation Attn: Mr. Ashok Thadani, Director PWR Project Directorate #8 Division of PWR Licensing - B U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Gentlemen:

Millstone Nuclear Power Station, Unit No. 2 10CFR50 Appendix 3 Testing On June 4, 1986, Northeast Nuclear Energy Company (NNECO) met with personnel at Region I headquarters to discuss 10CFR50, Appendix 3, testing at Millstone Nuclear Power Station, Unit N

3. Butcher dated November 6,1985,(1)o. 2. In a had NNECO letter from 3. aF.schedule proposed Opeka to forE.

future Type A testing at Millstone Unit No. 2. Based on past experience with Type A, B and C testing at Millstone Unit No. 2, NRC Staff requested that NNECO provide a presentation of our justification that the proposed schedule would ensure the leak tightness of the Millstone Unit No. 2 containment.

During the meeting, NNECO informed the NRC Staff that certain steps were planned to address those particular penetrations which in the past were the major contributors to failure to meet the technical specification requirements for Type B and C testing. In addition, the NRC Staff requested that NNECO provide an updated version of an LER submitted in February,1984, clarifying the sequence of events for the Appendix 3 testing performed during the 1983 refueling outage and the results of that testing. The purpose of this letter is to document those commitments.

As stated during the Sune 4,1986 meeting, all of the valves in Group 1 of the attached list will have their valve seats replaced during the upcoming refueling outage, planned for Fall,1986. One half of these valves will have their seats changed out during each subsequent refueling outage so that no valve seat would be in service longer that two cycles. In addition, as far as practically possible, NNECO will change the seats in such a way that for those penetrations with two valves in series, one of two valves will have its seat changed out each outage so (1) J. F. Opeka to E. 3. Butcher, dated November 6,1985.

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o' 8606270208 860618 PDR ADOCK 05000336 S PDR

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that each penetration will have at least one valve .with a new seat at the beginning of each cycle. For the two valves in Group 2 of the attached list, NNECO informed the NRC Staff that an evaluation would be ' performed to

define the best way to resolve the problems with these valves. As stated, these i valves provide containment isolation for the normal containment sump. Foreign i material that finds its way to the sump tends to get caught in the valve seat and j degrade their ability to seat tightly. NNECO is examining the different options available and the potential impact of each one before selecting the optimum i solution. NNECO's evaluation will be complete prior to the upcoming refueling 1 outage currently scheduled to begin approximately September 20, 1986. If -

possible, the corrective action will be taken during that outage.

As committed during the meeting, NNECO will be submitting a revision to LER 34-005 within the next two months. The revised LER will provide a clarification 4

of how and when Type A, B and C testing was performed during the 1983 refueling outage for Millstone Unit 2.

We trust that you will find this information satisfactory.

, Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY f

4 3.F. Dpeka

-b M U

Senior Vice President Attachments cc: Division of Reactor Safety

'l At:n: Mr. S. D. Ebneter, Director U. S. Nuclear Regulatory Commission Region 1 631 Park Avenue King of Prussia, PA 19406 1

1 1

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Attachment Group 1 Penetration Valve SYSTEM TYPE 25/30 2-RB-28.1 D RBCCW 10" Fisher Butterfly 25/30 2-RB-28.2 D 6" 25/30 2-RB-28.3D 10" 26/31 2-RB-28.l B 10" 26/31 2-RB-28.2B 6" 2-RB-28.3B " " "

26/31 10" 27/32 2-RB-28.l A 10" " "

27/32 2-RB-28.2A 6" " "

1 27/32 2-RB-28.3A 10" "

2-RB-28.1 C " " "

, 28/33 10" 28/33 2-RB-28.2C "

4" " "

l 28/33 2-RB-28.3C "

10" " "

39 2-AC-4 CMT. Purge 48" " "

. 39 2-AC-5 "

48" " "

40 2-AC-6 "

48" " "

40 2-AC-7 48" " "

^

82 2-EB-91 Hyd. Purge 6" " "

82 2-EB-92 6" " "

83 2-EB-99 6" " "

83 2-EB-100 " " "

6" Group 2 14 2-SS P-16.1 CMT. Sump 3" Masonellan Globe 14 2-SS P-16.2 CMT. Sump 3" Masoneilan GIobe

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