05000245/LER-1996-046, Forwards LER 96-046-03,documenting an Event That Occurred at Millstone Nuclear Power Station,Unit 1 on 960627 Per 10CFR50.73(a)(2)(i).Util Commitments Made within Ltr, Listed

Forwards LER 96-046-03,documenting an Event That Occurred at Millstone Nuclear Power Station,Unit 1 on 960627 Per 10CFR50.73(a)(2)(i).Util Commitments Made within Ltr, Listed

ML20138Q202
Person / Time
Site:	Millstone
Issue date:	03/03/1997
From:	Hinnenkamp P NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES SERVICE CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20138Q205	List: 05000245/LER-1996-046, Forwards LER 96-046-03,documenting an Event That Occurred at Millstone Nuclear Power Station,Unit 1 on 960627 Per 10CFR50.73(a)(2)(i).Util Commitments Made within Ltr, Listed
References
B16211, NUDOCS 9703060205
Download: ML20138Q202 (3)

LER-2096-046, Forwards LER 96-046-03,documenting an Event That Occurred at Millstone Nuclear Power Station,Unit 1 on 960627 Per 10CFR50.73(a)(2)(i).Util Commitments Made within Ltr, Listed

Event date:
Report date:
2452096046R00 - NRC Website

text

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. Northeast m.ne r-o noi,e rerry na.. woierrera, cr

Utilities System i>.o. 3,,, na Waterford, Ur 0638rs-0128 (860) 447-1791 March 3,1997 Docket No. 50-245 i B16211 f

Re: 10CFR50.73(a)(2)(i) 2 U.S. Nuclear Regulatory Commission i Document Control Desk Washington, DC 20555 This letter forwards supplemental Licensee Event Report (LER) 96-046-03, documenting an

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 supplement provides an update to the cause of.he event and the required corrective actions

! as a result of the completion of a root cause investigation and Appendix J program self-4 assessment.

Commitment No. B15820-3 has been revised 1o indicate that a procedural change will be made rather than a modification to the bolting flange.  ;

3  !

Commitment No. B15820-4, which stated that, "NNECO commits that the self-assessment of the l Appendix J program will be completed and the final results reported to the NRC via a supplement to this LER by March 1,1997," is complete.

Commitment No. B16106-1, which stated that, "NNECO commits that the issues identified for 3

the Appendix J program are being investigated through a root cause evaluation which is expected l to be completed by March 1,1997," is complete.

. The following are Northeast Nuclear Energy Company's (NNECO's) commitments contained within this letter. All other statements contained within this letter are for information only.

B15820-1 NNECO commits to modify the procedure for performing the local leak rate test i (LLRT) on the vacuum breaker to include testing of the shaft packing and stufling i box. L.LRTs 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.  ;

9703060205 970303 PDR ADOCK 05000245 I g Q '/1 S PDR mo422 9 nev. i2 9s g

U.S. Nuclear Regulatory Commission B1621l\Page 2 of 3 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

, startup for operating Cycle 16.

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 re!cs and responsibilities of implementing and maintaining the program. This document will also list the primary containment isolation barriers with associated basis for each penetration. +

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.

B16211-4 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.

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

e Revise ILRT procedure to include correct containment penetration valve lineup for each containment penetration and include containment temperature survey in accordance with ANSI N45-4 '97 ) 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.

I i

U.S. Nuclear Regulatory Commission

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B1621l\Page 3 of 3

• Modify surveillance procedures for the following penetrations to allow valid Type C test:  ;

X-211 A Post Accident Sampling 1-PAS-24,1 -PAS-25 X-14 RWCU 1-CU-2 A X-16A/B t e Spray 1-CS-5 A/B X-42 Standby Liquid Control 1-SL-7 X-47 Reactor Recirculation 1-RR-37 e Revise ILRT procedure to provide LLRT for containment air pressure and {

verification flow connections on containment penetrations prior to performance oflLRT prior to startup for operating Cycle 16. i e 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 isolation valve and associated test connections. Revise LLRT procedure to test the new centainment isolation valve and implement testing.

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

Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY 0 YD

.__ d ,V j X P. D. Hinnenkamp V Director, Unit Operations

Attachment:

LER 96-046-03 cc: Dr. W. D. Travers, Director, Special Projects H. J. Miller, Region I Administrator S. Dembek, NRC Project Manager, Millstone Unit No.1 T. A. Easlick, Senior Resident Inspector, Millstone Unit No. I