ML18102A938

LER 97-004-00:on 970221,inadequate Surveillance Testing of Molded Case Circuit Breakers Were Identified.Caused by Instantaneous Function Not Accurately Specified in Procedure.Tssip Has Been initiated.W/970321 Ltr

ML18102A938
Person / Time
Site:	Salem
Issue date:	03/21/1997
From:	Garchow D, Bernard Thomas Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-97-004-01, LER-97-4-1, LR-N97184, NUDOCS 9703280229
Download: ML18102A938 (4)

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• Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit MAR 211991 LR-N97184 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 LER 272/97-004-00 SALEM GENERATING STATION -UNIT 1 FACILITY OPERATING LICENSE NO. DPR-70 DOCKET NO. 50-272 Gentlemen:

This Licensee Event Report (LER) entitled "Inadequate Surveillance Testing of Molded Case Circuit Breakers" is being submitted pursuant to the requirements of the Code of Federal Regulations 10CFR50.73(a)

(2) (i) (B). Attachment DVH C Distribution LER File _3. 7 9703280229 970321 PDR ADOCK 05000272 S PDR Sincerely, David F.-

General Manager Salem Operations I If llll /11/11111111111111111111111111111111111111111111 St 1

• ii & 3 I St

• 95-2168 REV. 6/94

--NRC fORM 366 U.S. NUCL AR REGULATORY COMMISSION AP OVED BY OMB NO. 3150-0104 . ("'r95) EXPIRES 04/30/98 . ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS MANDATORY INFORMATION COLLECTION REQUEST: 50.0 HRS. LICENSEE EVENT REPORT (LER) REPORTED LESSONS LEARNED ARE INCORPORATED INTO THE LICENSING PROCESS AND FED BACK TO INDUSTRY.

FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE INFORMATION (See reverse for required number of AND RECORDS MANAGEMENT BRANCH (T-6 F33), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC. 20555-0001, AND TO digits/characters for each block) THE PAPERWORK REDUCTION PROJECT (3150-0104), OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503. FACILITY NAllE (1) DOCKET NUMBER (2) PAGE (3) SALEM GENERATING STATION UNIT 1 05000272 1 of 3 TITLE (4)' Inadequate Surveillance Testing of Molded Case Circuit Breakers.

EVENT DATE (5) LER NUMBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED (8) YEAR I FACILITY NAME DOCKET NUMBER MONTH DAY YEAR SEQUENTIAL I REVISION MONTH DAY YEAR NUMBER NUMBER Salem, Unit 2 05000311 02 21 97 97 004 00 03 97 FACILITY NAME DOCKET NUMBER --OPERATING NA THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check one or more) (11) MODE (9) 20.2201(b) 20.2203(a)(2)(v) x 50. 73(a)(2)(i)

50. 73(a)(2)(viii)

POWER 000 20.2203(a)(1) 20.2203(a)(3)(i)

50. 73(a)(2)(ii) 50.73(a)(2)(x)

LEVEL (10) 20.2203(a)(2)(i) 20.2203(a)(3)(ii)

50. 73(a)(2)(iii) 73.71 20.2203(a)(2)(ii) 20.2203(a)(4)

50. 73(a)(2)(iv)

OTHER 20.2203(a)(2)(iii) 50.36(c)(1)

50. 73(a)(2)(v)

Abstract below or in C Form 366A 20.2203(a)(2)(iv) 50.36(c)(2)

50. 73(a)(2)(vii)

LICENSEE CONTACT FOR THIS LER (12) NAME TELEPHONE NUMBER (Include Area Code) Brian J. Thomas, Licensing Engineer 609-339-2022 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13) CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE I CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE TO NPRDS TONPRDS SUPPLEMENTAL REPORT EXPECTED (14) EXPECTED MONTH DAY YEAR 'YES xlNO SUBMISSION (If yes, complete EXPECTED SUBMISSION DATE). DATE (15) ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spac;:ed typewritten lines) (16) During NRC inspection activities, an inadequate performance of a surveillance requirement was identified.

Technical Specification (TS) Surveillance Requirement

4. 8. 3. 1. a .*2 requires that ten percent of each type of all required containment penetration conductor overcurrent protection devices (e.g., circuit breakers) required to provide thermal protection of a penetration be verified operable every 18 months. In addition, TS 4.8.3.1.b requires.each required overcurrent protection device be inspected and have the manufacturer's preventative maintenance performed once per 60 months. Contrary to these requirements an adequate verification of the required overcurrent protection devices was not performed.

Certain elements of the. protective devices were not verified, because an acceptance criterion was not specified in the procedure.

The protection devices were adequately tested, and the test procedures were clarified to better define the TS requirements.

This event is being submitted pursuant to 10 CFR 50. 73 (2),(i) (B)' any operation or condition prohibited by TS. NRC FORM 366 (4-95)

,, NRC FORM 366A (4-95) U. . NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER) TEXT CONTINUATION FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (6) PAGE (3) SALEM GENERATING STATION UNIT 1 05000272 YEAR I SEQUENTIAL I REVISION NUMBER NUMBER 2 97 -004 -00 TEXT (If more space is required, use additional copies of NRC Form 366A) (17) PLANT AND SYSTEM ID.ENTIFICATION Westinghouse

-

Water Reactor 460V/230V/120V Breakers {-/BKR}

• Energy Industry Identification System (EIIS) codes and component function identifier codes appear as {SS/CC} CONDITIONS PRIOR TO OCCURRENCE OF 3 At the time of identification, Salem Unit 1 was defueled and Salem Unit 2 was in Mode 5. DESCRIPTION OF OCCURRENCE During NRC inspection activities, an inadequate performance of a surveillance requirement was identified.

Specifically, Technical Specification (TS) Surveillance Requirement 4.8.3.1.a.2 requires that ten* percent of each type of all required containment penetration conductor overcurrent protection devices (e.g., circuit breakers {-/BKR}) required to provide thermal protection of containment penetrations

• be verified operable every 18 months. In addition, TS 4.8.3.1.b states each required overcurrent protection device be inspected and have the manufacturer's preventative maintenance performed once per 60 months. Contrary to these requirements verification of the required overcurrent protection devices was not performed.

Three distinct types of molded case circuit breakers are used at Salem Generating Station to provide thermal protection for The first type of molded case circuit breaker has a thermal element and an adjustable instantaneous trip function.

The second type of molded case circuit. breakers has a thermal element and a fixed instantaneous trip funcition.

The third type of molded case circuit breaker has only an adjustable .instantaneous trip function (i.e., no thermal element in the circuit breaker.)

The instantaneous trip function in the third type of molded case circuit breaker was tested during surveillance testing. The thermal element of the first and second type of molded case circuit breaker was tested during surveillance testing; however, the fixed instantaneous and adjustable instantaneous trip functions for the first and second type of *molded case circuit breakers was not by the. surveillance test. CAUSE OF OCCURRENCE The station procedures accurately identified that the thermal element and the instantaneous element required testing; however, the instantaneous element was not tested, because an acceptance criterion for the instantaneous function was not accurately specified in the NRC FORM 366A (4-95))

NRC FORM 366A (4-95) U. . NUCLEAR REGULATORY COMMISSION FACILITY NAME (1) LICENSEE EVENT REPORT (LER) TEXT CONTINUATION DOCKET NUMBER (2) LER NUMBER (6) SALEM GENERATING STATION UNIT 1 0 5 0 0 0 2 7 2 YEAR I SEQUENTIAL I REVISION NUMBER NUMBER 97 -004 -00 TEXT (If more space is required, use additional copies of NRC Form 366A) (17) PRIOR SIMILAR OCCURRENCES PAGE (3) 3 OF 3 A review of LERs for Salem Units 1 and 2 issued in the last two years identified ten LERs (272/95-019, 272/96-004, 272/96-006, 272/96-008, 272/96-016, 008, 311/96-003, 311/96-007, 311/96-010 and 311/96-011) where surveillance requirements were not performed because of procedure problems.

The identification of this programmatic issue, along with other related issues, resulted in the initiation of the Technical Specification Surveillance Improvement Program (TSSIP) described in LER Jll/95-008.

The TSSIP should ensure that Technical Specification surveillance requirements are adequately implemented.

SAFETY CONSEQUENCES AND IMPLICATIONS There were no safety consequences as a result of this event because the containment penetrations remained operable.

Redundant protection devices (e.g. fuses, circuit breakers) are installed on these circuits.

These redundant protection devices are reliable, therefore, a fault would likely have caused a one of the piotection devices to tiip. This is supported by the testing that was performed on the devices after this event was discovered.

The testing demonstrated that the tested circuit breaker instantaneous elements would have cleared the fault prior to exceeding the thermal capability of the penetration.

Further, the thermal element for both the fixed instantaneous trip and adjustable instantaneous trip circuit breakers were verified to be operable in accordance with the TS. The thermal element provides a measure of fault protection such that it is unlikely that a fault would have caused thermal damage to the penetration.

The health and safety of the public was not affected.

CORRECTIVE ACTIONS 1. For Salem Unit 2, the protection devices were adequately tested. 2. For Salem Unit 1, the protection devices will be tested prior to entry into Mode 4. 3. The common test procedure was revised to better clarify the TS requirements.

4. The Technical Specification Surveillance Improvement Program (TSSIP) has been initiated for Salem Units 1 and 2. The scope and content of the TSSIP program was previously described in LER The TSSIP review is expected to be completed by December 31, 1997. NRC FORM 366A (4-95))