05000272/LER-2004-006, Operation in a Condition Prohibited by Technical Specification - Containment Isolation Valves

Operation in a Condition Prohibited by Technical Specification - Containment Isolation Valves

ML043280520
Person / Time
Site:	Salem  (DPR-070)
Issue date:	11/15/2004
From:	Fricker C Public Service Enterprise Group
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
LR-N04-0498 LER 04-006-00
Download: ML043280520 (6)

LER-2004-006, Operation in a Condition Prohibited by Technical Specification - Containment Isolation Valves

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(ix)(A) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(v), Loss of Safety Function
2722004006R00 - NRC Website

text

PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 NOV 1 i 2004 0 PSEG A'uclear LLC LR-N04-0498 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 LER 272/04-006-00 SALEM - UNIT 1 FACILITY OPERATING LICENSE NO. DPR-70 DOCKET NO. 50-272 This Licensee Event Report, "Operation in a Condition Prohibited by Technical Specification - Containment Isolation Valves," is being submitted pursuant to the requirements of the Code of Federal Regulations 10CFR50.73(a)(2)(i)(B).

The attached LER contains no commitments.

Sin Iy Sal m Plant Manager Attachment

/EHV C

Distribution LER File 3.7 95-2168 REV. 7199

NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 06/3012007

6-20041)

, the NRC may digits/characters for each block) or sponsor, and a person Is not required to respond to, the

3. PAGE Salem Generating Station Unit 1 05000272 1 OF 5 4.-TITLE Operation in a Condition Prohibited by Technical Specification - Containment Isolation Valves

5. EVENT DATE

6. LER NUMBER

7. REPORT DATE

8. OTHER FACILMES INVOLVED SEQUENTIAL REV FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR NUMBER RN~O. MONTH DAY YEAR FACILITY NAME DOCKET NUMBER 09 15 2004 2004 - 006 -

00 11 15 2004

9. OPERATING MODE

11. THIS REPORT IS SUBMITTED PURSUANTTO THE REQUIREMENTS OFI 1CFR§: (Checkalithat apply) 0 20.2201(b) 0 20.2203(a)(3)(i) 0 50.73(aX2)(I)(C) 50.73(a)(2)(vii) 1 0 20.2201(d) 0 20.2203(aX3Xii) 0 50.73(aX2)(ii)(A) 0 50.73(a)(2XviiiXA) 0 20.2203(a)(1) 0 20.2203(a)(4) 0 50.73(a)(2Xii)(B) 0 50.73(a)(2XviiiXB) 0 20-2203(a)(2)(i) 0 50.36(c)(1)(iXA) 0 50.73(a)(2Xiii) 0 50.73(a)(2)(ix)(A)

10. POWER LEVEL 0 20.2203(aX2)(ii) 0 50.36(c)(1)(ii)(A) 0 50.73(a)(2Xiv)(A) 0 50.73(a)(2)(x) 0 20.2203(a)(2)(iii) 0 50.36(cX2) 0 50.73(a)(2)(vXA) 0 73.71 (aX4) 0 20.2203(aX2)(iv) 0 50.46(a)(3Xii) 0 50.73(a)(2)(vXB) 0 73.71(aX5) 99.6%

0 20.2203(aX2)(v) 0 50.73(a)(2)(iXA) 0 50.73(a)(2)(v)(C) 0 OTHER o 20.2203(a)(2)(vi) 0 50.73(aX2)(i)(B) 0 50.73(aX2)(v)(D)

Specify In Abstract below nr in NJr(* Fnrm O.ARA

12. LICENSEE CONTACT FOR THIS LER FACILITY NAME TELEPHONE NUMBER (Indude Area Code)

E. H. Villar, Licensing Engineer 856-339-5456CAUSE SYSTEM COMPONENT MANU-REPORTABLE

CAUSE

SYSTEM COMPONENT MANU-REPORTABLE TMCM NET FACTURER TO EPIX FACTURER TO EPIX A

BI V

No 1CMPN

14. SUPPLEMENTAL REPORT EXPECTED

15. EXPECTED MONTH DAY YEAR SUBMISSION 0 YES (If yes, complete 15. EXPECTED SUBMISSION DATE) 0 NO DATE ABSTRACT (Limit to 1400 spaces, I.e., approximately 15 single-spaced typewritten lines)

On September 17, 2004, a review of actions associated with the performance an In Service Test (IST) determined that the actions taken on September 15 were inappropriate and the Plant was not in compliance with Technical Specifications. On September 15, 2004, during performance of the quarterly In Service Test in accordance with approved plant surveillance test procedures, the Service Water inlet valve to the 11 Containment Fan Coil Unit (11 SW58) failed to indicate closed on the control console upon stroking the valve, thus exceeding its Required Action stroke time. Technical Specification 3.6.3.1 was entered at 21:17 on September 15, 2004.

Following non-intrusive troubleshooting, additional strokes, and consultation with IST personnel, the Technical Specification was exited at 22:41 on September 15. A review of the actions taken on September 15 by the IST Program Manager concluded that Technical Specification 3.6.3.1 should not have been exited. According to the requirements of the IST program, the first stroke is the IST stroke time. The IST program does not include provisions for multiple strokes to determine operability of a valve that has exceeded its Required Action stroke time without the performance of maintenance or a rigorous engineering evaluation. The cause of this event was determined to be personnel error. An immediate corrective action taken was to repair and retest the 1 1 SW58 valve.

This report is being made in accordance with 10CFR50.73(a)(2)(i)(B), "Any operation or condition which was prohibited by the plant's Technical Specifications..."

NRC FORM 366 (6-2004)

PRINTED ON RECYCLED PAPER

(If more space Is required, use additional copies of (If more space Is required, use additional copies of (If more space is-required, use additional copies of (if more space Is required, use additional copies of NRC Form 366A)

SAFETY CONSEQUENCES AND IMPLICATIONS (cont'd)

A review of this event determined that a Safety System Functional Failure (SSFF) as defined in NEI 99-02 did not occur.

CORRECTIVE ACTIONS

1. The 11SW58 valve was repaired and retested satisfactorily.

2. Procedure SH.RA-AP.ZZ-01 05 (Q) will be reviewed and revised as necessary to ensure that proper guidance is included for helping in assessing operability determinations to preclude recurrence of this type of event.

3. This event will be included in the IST Training module being developed for licensed operator requalification training.

COMMITMENTS

This LER contains no commitments.