ML18102A857

LER 97-001-00:on 970115,inadequate Surveillance for PORV Accumulator Discharge Check Valves Was Noted.Caused by Reviewers Not Identifying That Test Method Did Not Meet Requirements of ASME Code.Revised procedure.W/970213 Ltr

ML18102A857
Person / Time
Site:	Salem
Issue date:	02/13/1997
From:	Garchow D, Hassler D Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-97-001-01, LER-97-1-1, LR-N97094, NUDOCS 9702200174
Download: ML18102A857 (4)

Text

CPS~G * *

' Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit FEB 131997

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LR-N97094 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 LER 311/97-001-00 SALEM GENERATING STATION - UNIT 2 FACILITY OPERATING LICENSE NO. DPR-75 DOCKET NO. 50-311 Gentlemen:

This Licensee Event Report entitled "Inadequate Surveillance for PORV Accumulator Discharge Check Valves" is being submitted pursuant to the requirements of the Code of Federal Regulations 10CFR50. 73 (a) (2) (i) (B).

S/'Jrely~- ();/ ,j}

(~_/./..or:* ~yµ/-(~/XJ David F. Garchow .

General Manager Salem Operations Attachment DVH c Distribution LER File 3.7 9702200174 970213 PDR ADOCK 05000311 5 PDR

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190125 The power is in your hands.

95-2168 REV. 6/94

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NRCFORM366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 (4-95) EXPIRES 04/30198 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS MANDATORY INFORMATION COLLECTION REQUEST: 50.0 HRS.

REPORTED LESSONS LEARNED ARE INCORPORATED INTO THE LICENSEE EVENT REPORT (LER) LICENSING PROCESS AND FED BACK TO INDUSTRY. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE INFORMATION AND RECORDS MANAGEMENT BRANCH (T-0 ~NUCLEAR (See reverse for required number of REGULATORY COMMISSION, WASHINGTON, DC , AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104), OFACE OF digits/characters for each block) MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.

FACILITY NAllE (1) DOCKET NUMBER (2) PAGE(3)

SALEM GENERATING STATION UNIT 2 05000311 1 OF 3 TITLE (4)

INADEQUATE SURVEILLANCE FOR PORV ACCUMULATOR DISCHARGE CHECK VALVES EVENT DATE (5) LER NUMBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED (8)

FACILITY NAME DOCKET NUMBER MONTH 01 DAY 15 YEAR 97 YEAR 97 I- SEQUENTIAL NUMBl!R 001 -

'REVISION NUMBER 00 MONTH 02 DAY 13 YEAR 97 FACILITY NAME 05000 DOCKET NUMBER OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check one or more) (11) 5 MODE(9) 20.2201(b) 20.2203(a)(2)(v) x 50. 73(a)(2)(i) 50. 73(a)(2)(viii)

POWER 20.2203(a)(1) 20.2203(a)(3)(i) 50. 73(a)(2)(ii) 50. 73(a)(2)(x) 000 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) S~~ln Abatract 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)

Dennis v. Hassler, LER Coordinator 609-339-1989 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)

CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE TONPRDS j~ ~ ~i~i~t~i~ ~li~j~ ~ii~ CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE TONPRDS

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SUPPLEMENTAL REPORT EXPECTED (14)

(If yes, complete EXPECTED SUBMISSION DATE).

. I XINO EXPECTED SUBMISSION DATE(15)

MONTH DAY YEAR ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines) (16)

On January 15, 1997 a review determined that the surveillance of the Salem Unit 2 check valves for the pressurizer over-pressure system had not been performed correctly in December 1994 and in January 1997. The testing was being performed with a reduced differential pressure rather than the maximum differential pressure as required by the ASME code. In accordance with the provisions of Technical Specification 4.0.3, a correct surveillance was completed on January 16, 1997. The Salem Unit 1 surveillance for the check valves was performed correctly in the past and was not affected by this occurrence.

The cause of this occurrence was the failure of the procedure writers and reviewers to identify that the procedure testing. method did not meet the requirements of the ASME code. Corrective actions include a satisfactory retest of the valves and a procedure revision.

I This event is reportable in accordance with 10 CFR .50. 73 (a) ( 2) ( i) ( B) ' any I

I condition prohibited by the plant's Technical Specifications.

1.

NRC FORM 366 (4-95)

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' NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION (4-95)

LICENSEE EVENT REPORT (LER)

TEXT CONTINUATION FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (6) PAGE (3) 2 OF 3 SALEM GENERATING STATION UNIT 1 97 - 001 - 00 TEXT (If more space is required, use additional copies of NRC Form 366A) (17)

PLANT AND SYSTEM IDENTIFICATION Westinghouse ~ Pressurized Water Reactor Control Air System {LE/-}*

Reactor Coolant System {AB/-}

• Energy Industry Identification System (EIIS) codes and component function identifier codes appear as {SS/CC}

CONDITIONS PRIOR TO OCCURRENCE At the time of occurrence, Salem Unit 2 was in Mode 5.

DESCRIPTION OF OCCURRENCE On January 15, 1997 a review determined that the surveillance of the Salem Unit 2 check valves {AB/PDVC} for the pressurizer over-pressure system had not been performed. correctly in December, 1994 and in January, 1997. In accordance with the provisions of Technical Specification 4.0.3, the surveillance was performed correctly on January 16, 1997. The Salem Unit 1 surveillance for the check vaives was performed correctly in the past and was not affected by this occurrence.

ASME Section XI, subsection IWV requirements fo:r: leak testing Category A valves requires a maximum differential pressure to be applied across the tested valve.

The pressure test values for these valves *was changed from performing a functional differential pressure test to a reduced differential pressure test in response to industry concerns about a gradual loss of control air versus a catastrophic loss of control air. In December, 1994 responsibility for the testing of these valves was changed from the Operations Department to the Inservice Inspection Test Group. A new test procedure was developed based on a gradual loss of system air pressure. This was at the time considered to be a conservative testing method.

CAUSE OF.OCCURRENCE The cause of this occurrence was personnel error in that the procedure writers and reviewers failed to identify that the testing method did not meet the requirements of the ASME code.

PRIOR SIMILAR OCCURRENCES In the past two years there have been two LERs, 272/95-018-01 and 272/96-005-09, that addressed an Inservice Testing (IST) issue. The corrective actions in LER 272/95-018-01 did not identify the discrepancies for the check valves for the pressurizer over-pressure system. The IST issue in LER 272/96-005-09 was recently identified and the corrective actions are specific to the issue in that LER.

NRC FORM 366A (4-95)

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} NRC FORM 366A U.S. NUCLEAR REGULATORY.COMMISSION (4-95)

LICENSEE EVENT REPORT (LER)

TEXT CONTINUATION FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (6) PAGE (3)

SALEM GENERATING STATION UNIT 1

.. 05000311 YEAR I SE~riiWhAL I~= 3 OF 3 97 - 001 - 00 TEXT (If more space is required, use additional copies of NRC Form.366A) (17)

SAFETY CONSEQUENCES AND IMPLICATIONS There were no safety consequences associated with this occurrence. , Satisfactory testing of the valves upon identification of the incorrect test was completed on January 16, 1997. The Power Operated Relief Valve (PORV) accumulators are designed to provide volume adequate to cycle the PORVs. Failure of the PORV accumulator check valves may result in a lower volume than required to adequately.cycle the PORVs. The PORVs are designed to limit pressurizer pressure below the high reactor trip setpoint, however they fail closed on a loss of air supply. The PORVs have adequate stroking capability using accumulator air to perform their function following a loss of control air.

However, minor leakage of air through the check valves has been evaluated as inconsequential (as contained in LCR S97-03).

The health and safety of the public was not affected.

CORRECTIVE ACTIONS

1. The PORV accumulator check valves were satisfactorily tested on January 16, 1997.

2. A review determined that other ASME Section XI, Category A valves in the IST Program that were being tested in the same manner meet Code requirements.

3. The test procedure will be revised to include a test method that includes testing at low and high differential pressure in accordance with Code

,requirements by May 2, 1997.

4. Personnel involved with the occurrence were held accountable for their actions in accordance with PSE&G's disciplinary policy.

NRC FORM 366A (4-95)