05000423/LER-1997-027, Provides Revised Completion Date for Commitment Submitted within LER 97-027-00 Re Corrective Action Not Met for Trending Valve Leakage.Revised Completion Date Is 970501

Provides Revised Completion Date for Commitment Submitted within LER 97-027-00 Re Corrective Action Not Met for Trending Valve Leakage.Revised Completion Date Is 970501

ML20203D467
Person / Time
Site:
Issue date:	12/05/1997
From:	Hicks G NORTHEAST NUCLEAR ENERGY CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
B16889, NUDOCS 9712160201
Download: ML20203D467 (4)

LER-1997-027, Provides Revised Completion Date for Commitment Submitted within LER 97-027-00 Re Corrective Action Not Met for Trending Valve Leakage.Revised Completion Date Is 970501

Event date:
Report date:
4231997027R00 - NRC Website

text

.-.

4gg Rope Ferry Rd. (Route 156), Tcterford, CT 06385 Nuclear Energy m,tooe Naa, em, stam,o Northeast Nudear Energy compacy P.O. Bas 128 Waterford, CT 06385-0128 i

(860) 447 1791 Faz (860) 444-4277 T1,e Northeast Utihties System Qocket No. 50-421 B16889 December 5,1997 RE: LER 97-027-00 IST and Appendix J Programs U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Millstone Nuclear Power Station Unit No. 3 Revision Of Commitment Date For Completion Of Accendix J Proaram Administrative Procedure The purpose of this letter is to provide a revised completion date for a commitment submitted within Licensee Event Report (LER) 97-027-00, "Cerrective Actions Not Met for Trending Valve Leakage." Within the LER we indicated that by December 2,1997, an administrative procedure would be developed to coordinate the containment isolation valve leak testing requirements of 10 CFR 50 Appendix J with the Section XI Inservice Test Program requirements of the American Society of Mechanical Engineers (ASME)

Code.

ASME Section XI subsection IWV, titled " Inservice Testing of Valves in Nuclear Power Plants," paragraphs IWV-3426 and IWV-3427 require that CIVs be repaired or replaced when the leakage exceeds the maximum leakage limits established by the owner for the valve, or exceeds the value determined from the leakage rate equations given in paragraph IVN-3426. Operations surveillance testing procedures ensure that corrective actions will be implemented if allowable leakage limits are exceeded. This meets the technical basis for the commitmer' made within the LER.

I po n 9712160201 971205 PDR ADOCK 05000423 8

PDR#c.

ll 1.Elll1.5.1 I.IH. R.

_,.t...,

U.S. Nucle:r Regul tory Commission B16889\\Page 2 4

i The addition of an administrative procedure to link the Appendix J and Section XI programs is an enhancement to the controlling site document currently used to perform the Appendix J Program at each unit. Additional time is necessary to ensure that the administrative procedure will encompass the needs of each of the Millstone units and define how the programs are implemented and maintained at the site.

Our revised commitment date for developing the administrative procedure is provided in Attachment 1.

Should you have any questions regarding this matter please contact Mr. David A.

Smith at (860) 437-5840.

a j

Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY

^

.DD cu.

- w Director - Millstone Unit 3 4

RAL:ral cc:

H. J.

Miller, Region 1 Administrator W.D. Travers, PhD, Director, Special Projects Office J. W. Andersen, NRC Project Manager, Millstone Unit No. 3 A. C. Cerne, Jenior Resident inspector, Millstone Unit No. 3 P

--,g.,

.-,,nm

-,v.,.

v-

,e,,

w,..-..,

w

+

9 Docket No. 50-423 p16889 Millstone Nuclear Power Station Unit No. 3 Revised Schedule For Completion Of Accendix J Proaram Administrative Procedure December 1997

, U.S. Nuclerr Regul tory Commission B16889 \\ Attachment 1\\Page 1 Enclosure List of Regulatory CommMments The following table identifies those actions committed. to by NNECO in this document.

Please notify. the Manager - Nuclear Licensing at the Millstone l

Nuclear Power Station Unit No. 3 of any questions regarding this document or any associated regulatory commitments.

Committed Date or Number

Commitment

Outage

- B16889-01 An administrative procedure will be May 1,1998 developed to coordinate the containment isolation valve leakage testing requirements from the 10 CFR 50 Appendix J and the Section XI i

inservice Testing Programs.

1 I

2 i

L v-ern-+y wr w w ir

-~.

- yo-,,-y--

+, -.

--y-,

- g-&----y-g-y vwy-y.nwwg -

---rw-7,m 4

p-gy-p

--.myw e.,,,

44