05000354/LER-2006-005, Drywell Hoist Breaker Not Open Prior to Operational Condition 2 Entry

Drywell Hoist Breaker Not Open Prior to Operational Condition 2 Entry

ML070580113
Person / Time
Site:	Hope Creek
Issue date:	02/16/2007
From:	Massaro M Public Service Enterprise Group
To:	Document Control Desk, NRC/NRR/ADRO
References
LR-N07-0031 LER 06-005-00
Download: ML070580113 (5)

LER-2006-005, Drywell Hoist Breaker Not Open Prior to Operational Condition 2 Entry

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 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)(viii)(A) 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(ix)(A) 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(x) 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 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(v), Loss of Safety Function
3542006005R00 - NRC Website

text

.PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 0 PSEG Nuclear LLC 10CFR50.73 LR-N07-0031 United States Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-001 HOPE CREEK GENERATING STATION UNIT 1 FACILITY OPERATING LICENSE NO. DPR-57 DOCKET NO. 50-354

'~~1 Subject: LER 354/06-005-00 This Licensee Event Report entitled, "Drywell Hoist Breaker Not Open Prior to Mode 2 Entry" is being submitted pursuant to the requirement of 10CFR50.73(a)(2)(i)(B).

Sincerely, Michael J. Massaro Plant Manager - Hope Creek Attachment 95-2168 REV. 7/99

NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSIOI APPROVED BY OMB: NO. 3150-0104 EXPIRES: 06/30/2007 (6-2004)

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

13. PAGE Hope Creek Generating Station 05000 354 1 OF 4

4. TITLE Drywell Hoist Breaker Not Open Prior to Operational Condition 2 Entry

5. EVENT DATE

6. LER NUMBER

7. REPORT DATE

8. OTHER FACILITIES INVOLVED FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR SEQUENTIAL REV NUMBER NO.

MONTH DAY YEAR N/A FACILITY NAME DOCKET NUMBER 05 02 2006 2006 005 -

00 02 16 2007 N/A

9. OPERATING MODE

11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check all that apply)

El 20.2201(b)

El 20.2203(a)(3)(i)

El 50.73(a)(2)(i)(C)

El 50.73(a)(2)(vii) 2 El 20.2201(d)

El 20.2203(a)(3)(ii)

El 50.73(a)(2)(ii)(A)

El 50.73(a)(2)(viii)(A)

El 20.2203(a)(1)

[I 20.2203(a)(4)

El 50.73(a)(2)(ii)(B)

El 50.73(a)(2)(viii)(B)

El 20.2203(a)(2)(i)

[I 50.36(c)(1)(i)(A)

El 50.73(a)(2)(iii)

E-50.73(a)(2)(ix)(A)

10. POWER LEVEL El 20.2203(a)(2)(ii)

[3 50.36(c)(1)(ii)(A)

El 50.73(a)(2)(iv)(A)

[I 50.73(a)(2)(x)

[3 20.2203(a)(2)(iii)

[1 50.36(c)(2)

El 50.73(a)(2)(v)(A)

El 73.71(a)(4)

[I 20.2203(a)(2)(iv)

El 50.46(a)(3)(ii)

[E 50.73(a)(2)(v)(B)

El 73.71(a)(5) 000 El 20.2203(a)(2)(v)

[1 50.73(a)(2)(i)(A)

El 50.73(a)(2)(v)(C)

El OTHER El 20.2203(a)(2)(vi) 0 50.73(a)(2)(i)(B)

El 50.73(a)(2)(v)(D)

Specify in Abstract below nr in NRr. Fo*rm.SARA

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

Francis D. Possessky, Compliance Engineer 856-339-1160CAUSE MANU-REPORTABLE

CAUSE

SYSTEM COMPONENT MANU-REPORTABLE SYSTEM COMPONENT FACTURER TO EPIX N/A

14. SUPPLEMENTAL REPORT EXPECTED

15. EXPECTED MONTH DAY YEAR SUBMISSION [E YES (If yes, complete 15. EXPECTED SUBMISSION DATE)

Z NO DATE ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines)

On December 18, 2006, the breaker 52-263042 for the drywell Safety Relief Valve (SRV) hoist 10H202 was discovered in the closed position. Technical Specification 3.8.4.1 requires that all primary containment penetration conductor over-current protective devices shown in Table 3.8.4.1-1 shall be operable in Operational Condition 1, 2, and 3, with the exception of three breakers identified with an asterisk. The breakers identified with an asterisk are to be administratively maintained open in Operational Condition 1, 2, 3, and are not required to be sur'eilled. Breaker 52-263042 is identified with an asterisk. Operation in Operational Condition 1, 2, and 3 with breaker 52-263042 closed is not in accordance with Technical Specifications. This condition was determined to be reportable under 1 OCFR50.73(a)(2)(i)(B), as any operation or condition prohibited by the plant Technical Specifications.

A latent status control database (SAP) error and a procedure revision error to HC.OP-IO.ZZ-0002 (Q)

"Preparation for Plant Startup" were identified as the root causes.

The Database error was corrected, the procedure revised to ensure this step is not missed, and lessons learned training is being developed for Licensed Operator Training.

NRC FORM 366 (6-2004)

AU.S. NUCLEAR REGULATORY COMMISSION (1-2001)

LICENSEE EVENT REPORT (LER)

FACILITY NAME (1)

DOCKET (2)

LER NUMBER (6)

PAGE (3)

SEQUENTIAL REVISION YEAR NUMBER NUMBER Hope Creek Generating Station 05000354 2 OF 4 1 2006 005 00 TEXT (If more space is required, use additional copies of NRC Form 366A) (17)

PLANT AND SYSTEM IDENTIFICATION

General Electric-Boiling Water Reactor (BWR/4)

AC Breaker - EIIS Identifier {--/52}*

• Energy Industry Identification System {EIIS} codes and component function identifier codes appear as

{Ss/CCC}

IDENTIFICATION OF OCCURRENCE Event Date: May 02, 2006 Discovery Date: December 18, 2006 CONDITIONS PRIOR TO OCCURRENCE Hope Creek was in cold shutdown for the thirteenth refueling outage (RF13). No structures, systems, or components were inoperable that contributed to the event. Breaker 52-263042 was not open and administratively controlled prior to entry into Operating Condition 2 on May 02, 2006.

DESCRIPTION OF OCCURRENCE On December 18, 2006, while training a Senior Reactor Operator (SRO) candidate on the performance of the weekly Work Control Document (WCD) tagging audit, the work control supervisor discovered Temporary Release documentation indicating breaker 52-263042 for the drywell SRV hoist 1 0H202 was closed.

The SRO recognized that the correct breaker position for Operational Condition 1 was open and under administrative control to comply with Technical Specification 3.8.4.1. A field walk down of the component was performed, and the breaker was determined to be closed. The Work Control SRO directed an operator to open the breaker, and re-apply the tag for administrative control of the breaker.

Technical Specification 3.8.4.1 requires that all primary containment penetration conductor over-current protective devices shown in Table 3.8.4.1-1 shall be operable in Operational Conditions 1, 2, and 3, with the exception of three breakers identified with an asterisk. Breaker 52-263042 for the drywell SRV hoist 1 0H202 is one of the asterisked breakers.

The breakers identified with an asterisk are to be administratively maintained open in Operational Condition 1, 2, 3, and are not required to be surveilled. Operation in Operational Conditions 1, 2, and 3 with breaker 52-263042 closed is not in accordance with Technical Specifications.U.S. NUCLEAR REGULATORY COMMISSION (1-2001)

LICENSEE EVENT REPORT (LER)

FACILITY NAME (1)

DOCKET (2)

LER NUMBER (6)

PAGE (3)

SEQUENTIAL I REVISION YEAR NUMBER NUMBER Hope Creek Generating Station 05000354 3 OF 4 1_11 1_2006 005 00 CAUSE OF OCCURRENCE The root cause has been determined to be a latent status control database (SAP) error and a procedure revision error to "Preparation for Plant Startup". In addition, shortfalls in the performance of the revision reviews to "Preparation for Plant Startup" contributed to the removal of a procedural barrier to this event.

The status control database incorrectly listed this breaker being required to be closed in Operational Condition 1,2 and 3.

The "Preparation for Plant Startup" procedure was revised in June of 2005 and the revision error resulted in the requirement for the breaker position verification and administrative control being located in the attachment for entrance to Operational Condition 3. In this instance, the outage schedule reflected direct entry into Operational Condition 2 from Operational Condition 4. The steps for preparation for entering Operational Condition 3 are not performed when transitioning directly from Operational Condition 4 to Operational Condition 2.

PREVIOUS OCCURRENCES

A review of previous reportable events at Hope Creek was performed to determine if a similar event had occurred. No similar events were identified.

SAFETY CONSEQUENCES AND IMPLICATIONS

Primary containment electrical penetrations and penetration conductors (the cables that share the penetration with the subject breaker load) are protected by demonstrating the operability of primary and backup over-current protection circuit breakers.

The risk presented by this condition is minimal. The set points of the two redundant in-series breakers were designed, and set per calculation E-7.13 (Q), to prevent damage to the penetration. Although the trip function is not tested in accordance with the specified Technical Specification Surveillance Requirement frequency, the non-adjustable, thermal-magnetic breaker trip mechanism would have actuated in the event of an over current condition.

Per Technical Specifications, the breaker is maintained open during the modes of applicability in lieu of periodically demonstrating over current protection device operability in accordance with the surveillance requirements.

A review of this event determined that a Safety System Functional Failure (SSFF) has not occurred as defined in Nuclear Energy Institute (NEI) 99-02.U.S. NUCLEAR REGULATORY COMMISSION (1-2001)

LICENSEE EVENT REPORT (LER)

FACILITY NAME (1)

DOCKET (2)

LER NUMBER (6)

PAGE (3)

SEQUENTIAL

) REVISION YEAR NUMBER NUMBER Hope Creek Generating Station 05000354 4 OF 4 2006 005 00

CORRECTIVE ACTION

SAP/WCM database corrected:

The procedure has been modified to place the step in an attachment that ensures completion of the activity prior to entering Operational Condition 2.

Lessons learned training will be provided for licensed individuals and procedure reviewers.

COMMITMENTS

This LER contains.no commitments.