05000245/LER-1996-046-04, Forwards Suppl LER 96-046-04,documenting Event Occurring at Facility on 960627.Provides Addl Reportable Condition Identified on 970318.W/util Commitments Listed

Forwards Suppl LER 96-046-04,documenting Event Occurring at Facility on 960627.Provides Addl Reportable Condition Identified on 970318.W/util Commitments Listed

ML20137Y047
Person / Time
Site:	Millstone
Issue date:	04/17/1997
From:	Hinnenkamp P NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES SERVICE CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20137Y051	List: 05000245/LER-1996-046-04, Forwards Suppl LER 96-046-04,documenting Event Occurring at Facility on 960627.Provides Addl Reportable Condition Identified on 970318.W/util Commitments Listed
References
B16389, NUDOCS 9704220301
Download: ML20137Y047 (3)

LER-1996-046, Forwards Suppl LER 96-046-04,documenting Event Occurring at Facility on 960627.Provides Addl Reportable Condition Identified on 970318.W/util Commitments Listed

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(i)
2451996046R04 - NRC Website

text

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Waterford, CF 06385-0128 (203) 447 1791 s

April 17,1997 l

Docket No. 50-245 B16389 i

Re: 10CFR50.73(a)(2)(i) i i

U.S. Nuclear Regulatory Commission j

Attention: Document Control Desk i

j Washington, DC 20555 f.

5 1.

This letter forwards supplemental Licensee Event Repon (LER) 96-046-04, documenting an 4

event that occurred at Millstone Nuclear Power Station, Unit No.1 on June 27,1996. This LER is submitted pursuant to 10CFR50.73(a)(2)(i).

j-This supplemental report provides an additional reportable condition that was identified on March 1:

18,1997. Accordingly, one additional commitment has been added as B16389-1 below.

)

The following are Northeast Nuclear Energy Company's (NNECO's) commitments contained j

within this letter. All other statements contained within this letter are for information only.

I i

1 f

B15820-1 NNECO commits to modify the procedure for performing the local leak rate test (LLRT) on the vacuum breaker to include testing of the shaft packing and stuffing box. LLRTs will be performed before the overall containment Type A integrated leak rate testing (ILRT) prior to startup for operating Cycle 16.

- B15820-2 NNECO commits to modify the containment side bolting flange of valves 1-AC-9 &

1-AC-12 during refueling outage 15. LLRTs will be performed before the overall containment Type A ILRT prior to startup for operating Cycle 16.

B15820 3 NNECO commits that changes will be made to the procedure to perform the LLRT on the bolting flange between valves 1-HS-4 and 1-HS-5 during refueling outage 15.

LLRTs will be performed before the overall containment Type A ILRT prior to stanup for operating Cycle 16.

i B16211-1 NNECO will complete by May 31,1997 (prior to performing the next ILRT), the program administrative control document, " Containment Leak Rate Testing Program Administration," which will identify the specific roles and responsibilities of 22010 f*

implementing and maintaining the program. This document will also list the primary containment isolation barriers with associated basis for each penetration.

kh;I 9704220301 970417 1 PDR ADOCK 05000245 8

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U.S'. Nuclear Regulatory Commission B16389\\Page 2 of 3 l

B16211-2 NNECO will determine Appendix J Program stafling requirements and obtain program management approval by May 31,1997.

B16211-3 NNECO will develop an Appendix J action plan which will identify the importance of conservative decision making regarding implementation of Appendix J requirements from all perspectives including design, operation and engineering.

NNECO will incorporate this plan into an administrative procedure, " Containment Leak Rate Testing Program Administration," by May 31,1997.

B 16211-4 NNECO will determine Appendix J programmatic enhancement training requirements and include in administrative procedure, " Containment Leak Rate Testing Program Administration," by May 31, 1997. NNECO will implement this training by September 30,1997.

B16211-5 NNECO commits that the following corrective actions, identified by the Appendix J program review, will be completed prior to startup for operating Cycle 16.

• The LLRT surveillance procedures, which require revision to provide a valid LLRT, will be revised prior to performance of the as-left LLRT prior to startup for operating Cycle 16.

• Evaluate the need to modify Millstone Unit No.1 Technical Specifications to include air lock leakage acceptance criteria.

• Revise ILRT procedure to include correct containment penetration valve lineup j

for each containment penetration and include containment temperature survey in accordance with ANSI N45-4 -1972 prior to performance ofILRT for Refueling Outage 15.

• Modify containment penetrations X-30f and X-34f to allow valid Type C test of isolation valves 1-RR-111 A/B and 1-RR-25A/B.

• Modify surveillance procedures for the following penetrations to allow valid Type 1

C test:

X-21l A Post Accident Sampling 1-PAS-24,1-PAS-25 X-14 RWCU 1-CU-2 A X-16A/B Core Spray 1-CS-5A/B X-42 Standby Liquid Control 1-SL-7 X-47 Reactor Recirculation 1-RR-37 Resise ILRT procedure to provide LLRT for containment air pressure and e

verification flow connections on containment penetrations prior to performance ofILRT prior to startup for operating Cycle 16.

..__...__.____._____........__.__.m l

U.S: Nuclear. Regulatory Commission

. B16389\\Page 3 of 3 I

. Revise Main Steam Isolation Valve LLRT procedure to correct leakage to accident pressure of 43 psig.

• Modify containment penetration X-35E by installing an' additional containment

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isolation valve and associated test connections. Revise LLRT procedure to test

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l the new containment isolation valve and implement testing.

j Modify penetrations X-25 and X-202D to allow valid Type C test.

i B 16389-l' NNECO commits that the LLRT procedure will be revised to perform Type B l

testing of each flanged connection at penetrations X-35 A, B, C, D and E prior to the j

next required LLRT during the current outage.

i 4

Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY l

l-P. D.Tiinnenkamp M

Director, Unit Operations Attachment: LER 96-046-04 cc: Dr. W. D. Travers, Director, Special Projects i

H. J. Miller, Region I Administrator 1

S. Dembek, NRC Project Manager, Millstone Unit No.1 T. A. Eastick, Senior Resident Inspector, Millstone Unit No.1 1

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