05000272/LER-2004-004, Regarding Non-essential Loads Not Isolated with One Chiller Inoperable as Required by Technical Specifications

Regarding Non-essential Loads Not Isolated with One Chiller Inoperable as Required by Technical Specifications

ML042720339
Person / Time
Site:	Salem
Issue date:	09/20/2004
From:	Fricker C Public Service Enterprise Group
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
LR-N04-0398 LER 04-004-00
Download: ML042720339 (5)

LER-2004-004, Regarding Non-essential Loads Not Isolated with One Chiller Inoperable as Required by Technical Specifications

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)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat
2722004004R00 - NRC Website

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. r PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 SEP 2 0 2004 LR-N04-0398 o PSEG ANuclear LLC U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 LER 272104-004- 00 Salem Generating Station Unit I Facility Operating License DPR-70 Docket No. 50-272 This Licensee Event Report entitled "Non-essential Loads Not Isolated With One Chiller Inoperable as Required by Technical Specifications" is being submitted pursuant to the requirements of 1 OCFR 50.73(a)(2)(i)(B). The attached LER contains no commitments.

Should there be any questions regarding this matter please contact Howard Berrick at 856-339-1862.

Sincere C.

ricker S lem Plant Manager Attachment HGB C

Distribution LER File 3.7 0L."

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1
b 95-2168 REV. 7/99

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V NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 06/3012007 (6-2004)

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

3. PAGE Salem Generating Station - Unit 1 050002 1 OF 4

4. TITLE Non-essential Loads Not Isolated With One Chiller Inoperable as Required by Technical Specifications

5. EVENT DATE

6. LER NUMBER

7. REPORT DATE

8. OTHER FACILMES INVOLVED FACILAIY NAME DOCKET NUMBER MONTH DAY YEAR YEAR NEQUMBL RE V MONTH DAY YEAR I FACILITY NAME DOCKET NUMBER 07 21 2004 2004 - 004 -

00 09 20 2004

9. OPERATING MODE

11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check ali that apply) 0 20.2201(b) 0 20.2203(aX3)(i) 0 50.73(a)(2XiXC) 0 50.73(a)(2)(vii) 1 0 20.2201(d) 0 20.2203(aX3)(ii) 0 50.73(a)(2)(ii)(A) 0 50.73(a)(2)(viiiXA) o 20.2203(aXl) 0 20.2203(aX4) 0 50.73(a)(2)(iIXB) 0 50.73(aX2)(viiiXB) 0o 20.2203(a)(2Xi) 0 50.36(cXl)(i)(A) 0 50.73(a)(2)(iii) 0 50.73(aX2)(ix)(A)

10. POWER LEVEL 0 20.2203(a)(2Xii) 0 50.36(cX1)(iiXA) 0 50.73(a)(2)(iVXA) 0 50.73(aX2)(x) 0 20.2203(a)(2XiiI) 0 50.36(cX2) 0 50.73(a)(2)(v)(A) 0 73.71 (aX4) 0 20.2203(a)(2Xiv) 0 50.46(aX3)(ii) 0 50.73(a)(2)(v)(B) 0 73.71(aX5) 100 0 20.2203(a)(2Xv) 0 50.73(aX2)(i)(A) 0 50.73(aX2)(v)(C) 0 OTHER o 20.2203(a)(2Xvi) 0 50.73(aX2)(i)(B) 0 50.73(aX2)(v)(D)

Specify In Abstract below nr in NRC. Fnrm.WRA

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

Howard G. Berrick, Senior Licensing Engineer 856-339-1862CAUSE SYSTEM COMPONENT MANU-REPORTABLE

CAUSE

SYSTEM COMPONENT MANU-REPORTABLE SE CMOETFACTUJRER TO EPIX FACTURER TO EPIX I

1 No~l 1CMPNE

14. SUPPLEMENTAL REPORT EXPECTED

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

On July 21, 2004 at 0414 hours0.00479 days <br />0.115 hours <br />6.845238e-4 weeks <br />1.57527e-4 months <br /> Salem Unit 1 No. 11 Chiller was removed from service for a scheduled work activity. With a single chiller inoperable, Technical Specifications (TS) require that the appropriate non-essential heat loads be isolated within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. This required closing of valves 1CH30 and 1CHI51.

These valves were closed and white caution tag stickers hung next to the panel control switches. During July 21, 2004 dayshift, operations personnel were performing surveillance testing on Train 'A' of the Solid State Protection system. The procedure directs the 1 CH30 and 1 CHI51 valves to be opened following completion of test. During restoration the Nuclear Control Operator performing the test noted the No. 11 Chiller out of service, but failed to notice the white caution stickers for the valves. At 1205, valves 1CH30 and 1CHI51 were reopened. At approximately 1858 hours0.0215 days <br />0.516 hours <br />0.00307 weeks <br />7.06969e-4 months <br />, the oncoming nightshift noted valves were open and entered TS 3.0.3. The valves were immediated reclosed, non-essential load isolation was reinstated, and TS 3.0.3 was exited. The cause of this event was human error attributed to a lack of attention to detail and the lack of QV&V prior to taking action. Corrective actions taken include incorporation of this event into current licensed operator requalification training segment emphasizing and re-enforcing the use of human error reduction techniques. Additionally, procedure(s) will be revised to require closing associated manual isolation valves when isolating non-essential loads. This event is reportable per the requirements of 10 CFR 50.73(a)(2)(i)(B), Operation or Condition Prohibited by 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 NRC Formn 366A)

CORRECTIVE ACTIONS

1. The Unit 1 CRS was immediately notified of the condition. TS 3.0.3 was entered since non-essential loads Chilled Water system loads were not isolated per TS and procedure. Actions were immediately taken to close valves 1CH30 and 1CH151. TS 3.0.3 was exited after non-essential load isolation had been re-established.

2. Salem Operations performed a stand-down to discuss this and other events. The stand-down was an interactive discussion between Operations management team and the shift operators.

3. This event has been incorporated into the current licensed operator requalification training segment, emphasizing and re-enforcing the use of human error reduction techniques.

4. All individuals on the approved tagging list will be required to be observed performing a tagging evolution by supervision.

5. Salem Unit 1 Chilled Water Operations procedure will be revised to require closing associated manual isolation valves when isolating non-essential loads.

COMMITMENTS

This LER contains no Commitments.