ML18100B074

LER 94-006-00:on 940325,failure to Declare Pressurizer Relief Valves 2PR1 & 2PR2 Inoperable After Closure of Pressurizer Block Valves 2PR6 & 2PR7 Identified.Caused by Defective Procedures.Procedures revised.W/940511 Ltr

ML18100B074
Person / Time
Site:	Salem
Issue date:	05/11/1994
From:	Hagan J, Pastva M Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-94-006-01, LER-94-6-1, NUDOCS 9405190069
Download: ML18100B074 (6)

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~iJ,.~' PS~G P.ublic Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station May 11, 1994

u. s. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Dear Sir:

SALEM GENERATING STATION LICENSE NO. DPR-75 DOCKET NO. 50-311 UNIT NO. 2 LICENSEE EVENT REPORT 94-006-00 This Licensee Event Report is being submitted pursuant to the requirements of Code of Federal Regulation 10CFR50.73(a) (2) (i) (B).

Issuance of this report is required within thirty (30) days of event discovery.

Sincerely yours, General Manager -

Salem Operations MJPJ:pc Distribution

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.. '* ~* \.i ...... ..J 9405190069 940511 PDR ADOCK 05000311 S PDR . //'\-;f j 1 h~' ! *:. :'. : ~ :: ;: ' \ ~ l[i i- f>'J <J .")t,,O L/

95-2189 REV 7-92

NRC FORM 366 .S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 (5-92) EXPIRES 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS. FORWARD LICENSEE EVENT REPORT (LER) COMMENTS REGARDING BURDEN ESTIMATE TO THE INFORMATION AND RECORDS MANAGEMENT BRANCH (MNBB 7714), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555*0001, AND TO THE PAPERWORK REDUCTION PROJECT (3150*0104), OFFICE OF (See reverse for required number of digits/characters for each block) MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.

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

Salem Generatin~ Station - Unit 2 05000 311 1 OF 04 TITLE (4) Failure To Declare Pressurizer Relief Valves 2PR1 And 2PR2 Inoperable After Closure Of Pressurizer Block Valves 2PR6 and 2PR7.

EVENT DATE 15\ LER NUMBER 16 REPORT NUMBER (7) OTHER FACILITIES INVOLVED 18\

FACILITY NAME DOCKET NUMBER SEQUENTIAL REVISION MONTH DAY YEAR YEAR MONTH DAY YEAR NUMBER NUMBER 05000 FACILITY NAME DOCKET NUMBER

-- -- 05000 03 25 94 94 006 00 05 11 94 OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check one or more 111)

MODE (9) 1 20.402(b) 20.405(c) 50. 73(a) (2) (iv) 73.71(b)

• powER 20.405(a)(1)(i) 50.36(c) (1) 50.73(a) (2)(v) 73.71(c) _

20.405(a)(1)(ii) 50.36(c)(2) 50.73(a) (2) (vii) OTHER llill NAME M. J. Pastva. Jr. - LER Coordinator 20.405(a) (1) (iii) 20.405(a)(1) (iv) 20.405(a)(1)(v) x 50. 73(a)(2) (i) 50.73(a)(2)(ii) 50.73(a)(2)(iii)

LICENSEE CONTACT FOR THIS LER 12)

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

50. 73(a)(2)(viii)(B) 50.73(a) (2) (x)

(Specify in Abstract below and in Text, NRC Form 366A)

TELEPHONE NUMBER (Include Area Code)

(609) 339-5165 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)

REPORTABLE REPORTABLE CAUSE SYSTEM COMPONENT MANUFACTURER CAUSE SYSTEM COMPONENT MANUFACTURER TO NPRDS TO NPRDS SUPPLEMENTAL REPORT EXPECTED 14 EXPECTED MONTH DAY YEAR I YES (If yes, complete EXPECTED SUBMISSION DATE) x NO SUBMISSION DATE (15)

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

Action "a." of Technical Specification (TS) 3.4.5 should have been entered, at 0332 hours0.00384 days <br />0.0922 hours <br />5.489418e-4 weeks <br />1.26326e-4 months <br /> on March 25, 1994, when 2PR6 and 2PR7 (respective block valves for the power operated relief valves, 2PR1 and 2PR2) were closed per procedure. TS were not met until the block vaives were reopened, at 1045 hours0.0121 days <br />0.29 hours <br />0.00173 weeks <br />3.976225e-4 months <br /> on 3/25/94. While the block valves were closed, a Nuclear Control Operator was stationed to open them, if required. This event occurred because the procedure did not clarify the effect of block valve closure on PORV operability. Night Order Book entries were made on 3/25/94 and 3/31/94 to inform licensed operators of the requirement to enter TS 3.4.5 when the PORV block valve(s) are closed for leak determination. This event was reviewed with licensed Operations personnel. Procedures will be appropriately revised to require reference to TS, whenever PORV block valve(s) a:re closed. This event will be included in Licensed Operator re-qualification and initial License training. Appropriate TS interpretation(s) will be reviewed and revised, as necessary.

NRC FORM 366 (5*92)

REQUIRED NUMBER OF DIGITS/CHARACTERS FOR EACH BLOCK BLOCK NUMBER OF TITLE NUMBER DIGITS/CHARACTERS 1 UP TO 46 FACILITY NAME 8 TOTAL 2 DOCKET NUMBER 3 IN ADDITION TO 05000 3 VARIES PAGE NUMBER 4 UP TO 76 TITLE 6 TOTAL 5 EVENT DATE 2 PER BLOCK

' 7 TOTAL 2 FOR YEAR 6 LER NUMBER 3 FOR SEQUENTIAL NUMBER 2 FOR REVISION NUMBER 6 TOTAL 7 REPORT DATE 2 PER BLOCK UP TO 18 -- FACILITY NAME 8 OTHER FACILITIES INVOLVED 8 TOTAL -- DOCKET NUMBER 3 IN ADDITION TO 05000 9 1 OPERATING MODE 10 3 POWER LEVEL 1

11 REQUIREMENTS OF 10 CFR CHECK BOX THAT APPLIES UP TO 50 FOR NAME 12 LICENSEE CONTACT 14 FOR TELEPHONE CAUSE VARIES 2 FOR SYSTEM 13 4 FOR COMPONENT EACH COMPONENT FAILURE 4 FOR MANUFACTURER NPRDS VARIES 1

14 SUPPLEMENTAL REPORT EXPECTED CHECK BOX THAT APPLIES 6 TOTAL 15 EXPECTED SUBMISSION DATE 2 PER BLOCK

LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station DOCKET NUMBER LER NUMBER PAGE Unit 2 5000311 94-006-00 2 of 4 PLANT AND SYSTEM IDENTIFICATION:

Westinghouse - Pressurized Water Reactor Energy Industry Identification System (EIIS) codes are identified in

• the text as {xx}

IDENTIFICATION OF OCCURRENCE:

Failure To Declare Pressurizer Relief Valves 2PR1 and 2PR2 Inoperable After Closure Of Pressurizer Block Valves 2PR6 And 2PR7 Event Date: 3/25/94 Event Discovery Date: 4/12/94 Report Date: 5/11/94 This report was initiated by Incident Report No.94-104.

CONDITIONS PRIOR TO OCCURRENCE:

Mode 1 Reactor Power 92% - Unit Load 1010 MWe DESCRIPTION OF OCCURRENCE:

Action "a." of Technical Specification (TS) 3.4.5 should have been entered, at 0332 hours0.00384 days <br />0.0922 hours <br />5.489418e-4 weeks <br />1.26326e-4 months <br /> on March 25, 1994, when 2PR6 and 2PR7 {AB}

(respective block valves for the power operated relief valves, 2PR1 and 2PR2 {AB}) were closed in accordance with procedure. TS were not met until the block valves were reopened, at 1045 hours0.0121 days <br />0.29 hours <br />0.00173 weeks <br />3.976225e-4 months <br /> on March 25, 1994.

ANALYSIS OF OCCURRENCE:

TS Action "a. 11 requires, in part, that in MODES-1, 2, and 3, with one or more PORVs inoperable, within one hour either restore the PORVs to operable status or close the associated block valves and remove power to the block valves; otherwise, be in at least HOT STANDBY within the next six hours and in COLD SHUTDOWN with the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

The PORV block valves were closed, in accordance with Abnormal Operating Procedure (AOP) S2.0P-AB.PZR-0001(Q), Pressurizer Pressure Malfunction. This was done to support Pressurizer Relief Tank (PRT)

{AB} inleakage determination by'measurement of PRT inleakage with and without the PORVs isolated. The interpretation of this action is that the PORVs are rendered inoperable by closure of the block valves.

Therefore, power to the block valves should have been removed within

______J

LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station DOCKET NUMBER

• LER NUMBER PAGE Unit 2 5000311 94-006-00 3 of 4 ANALYSIS OF OCCURRENCE: (cont'd) one hour of closing the valves. TS 3.4.5 was reviewed along with TS Interpretation 2-Limiting Condition of Operation-3.4.5. Neither document addre-sses specifically the operability of the PORVs when manually isolated by closure of the block valves. Based upon the procedure guidance, Operations believed that the 2PR6 and 2PR7 closure did not affect PORV operability since the block valves were closed manually and were still capable of being opened by the NCO. In a pending.revision of the TS, power to the block valve will not be removed when the valve is closed i.n order to isolate a leaking PORV.

NRC Generic Letter 90-06 confirms the desirability of keeping the PORV*

block valves energized if a PORV is suspected to be the cause of excessive leakage.

The source of the subject leakage was subsequently determined to be from the one or more of the Reactor Head Vent valves, 2RC40, 41, *42, and 43 {AB}.

Event determination followed review of Technical Basis Document S2.0P-AB.PZR-001 and discussion with the NRC Senior Resident Inspector.

APPARENT CAUSE OF OCCURRENCE:

The cause of this occurrence is "Defective Procedure", as classified in Appendix B of NUREG-1022, due to failure of the procedure to clarify the effect of block valve closure on PORV operability.

PREVIOUS OCCURRENCES:

There are no previous documented occurrences of this event since closure of the Pressurizer block valves under administrative controls was not considered as rendering the PORV inoperable.

SAFETY SIGNIFICANCE:

This event is reportable pursuant to the requirements- of 10CFR50.73(a) (2) (i) (B), due to failure to comply with TS. This event did not affect the health and safety of the public as credit is not taken for PORV operation in the accident analyses of the Salem Updated Final Safety Analysis Report.

CORRECTIVE ACTION:

Night Order Book entries were made on March 25, 1994 and reemphasized on March Ji, 1994 to inform licensed operators of the requirement to enter TS 3.4.5 when the PORV block valve(s) are closed for leak

LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating station DOCKET NUMBER LER NUMBER PAGE Unit 2- 5000311 94-006-00 4 of 4 CORRECTIVE ACTION: (cont'd) determination.

This event was reviewed.with licensed Operations personnel.

Procedures for both Units will be appropriately revised to require reference to TS, whenever PORV block valve(s) are closed.

This event will be included in Licensed Operator re-qualification and initial license training.

Appropriate TS.interpretation(s) for both Units will be reviewed and revised, as necessary.

The Reactor Head Vent valve(s) will be repaired during the next outage of sufficient length.

MJPJ:pc

. SORC Mtg.94-042