ML18102A958

LER 97-006-00:on 970312,determined Relays That Are Part of Logic for Opening PORVs Were Not Tested.Caused by Lack of Adequate Control for Maint of TS Surveillance Procedures. Initiated New Procedures & Revised procedures.W/970408 Ltr

ML18102A958
Person / Time
Site:	Salem
Issue date:	04/08/1997
From:	Garchow D, Bernard Thomas Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-97-006, LER-97-6, LR-N97213, NUDOCS 9704150046
Download: ML18102A958 (4)

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Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit APR 0 81997 LR-N97213

.U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 LER 272/97-006-00 SALEM GENERATING STATION UNIT 1 FACILITY OPERATING LICENSE NO. DPR-70 DOCKET NO. 50-272 Gentlemen:

This Licensee Event Report (LER) entitled "Inadequate Te;!chnical Specification Required Surveillance .

Test for . Pressur.iz~r Overpressure Protection System" is being submitted pursuant to the requirements of the Code of Federal Regulations 10CFR50. 73 (a) (2) (i).

(kf'd David F. ~how General Manager Salem Operations Attachment DVH c Distribution LER File 3.7 970415004~ 6~8ri8~72 PDR ADOC PDR s

11111uum ,1111m 1110111~~111u111.nm11111111 The power is in your hands.

95-2168 REV. 6/94

NRC FORM 366 U.S. NUCL: REGULATORY COMMISSION A VED BY OMB NO. 3150-0104 (4-95) 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 AND RECORDS MANAGEMENT BRANCH (T-8 F33), U.S. NUCLEAR (See reverse for required number of REGULATORY COMMISSION, WASHINGTON, DC 20555-0001, AND TO THE PAPERWORK REDUCT~ON PROJECT (3150-0104), OFFICE OF digits/characters for each block) MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.

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

SALEM GENERATING STATION UNIT 1 05000272 1 of 3 TITLE (4)

Inadequate Technical Specif;i.cation Required surveillance Test for.

Pressurizer Overpressure I;'rotection System EVENT DATE (5) LER NUMBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED (8)

FACILITY NAME DOCKET NUMBER MONTH 03 DAY 12 YEAR 97 YEAR 97 I- SEQUENTIAL NUMBER 006 -

'REVISION NUMBER 06 MONTH 04 DAY YEAR 97 Salem, Unit 2 FACILITY NAME 05000311 DOCKET NUMBER 08 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) )( 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) Spec~ln 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 CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE

• TO NPRDS TONPRDS IYES SUPPLEMENTAL REPORT EXPECTED (14)

(If yes~ complete EXPECTED SUBMISSION DATE).

Ix'NO EXPECTED SUBMISSION

• DATE(15)

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

On March 12, 1997, a review of the Salem Unit 2 Pressurizer Overpressure Protection System (POPS) logic determined that relays that are part of the logic for opening the Power Operated Relief Valves (PORV) were not tested and calibrated as required by Technical Specifications (TS) 4.4.10.3.1.a and 4.4.10.3.1.b. The POPS Channel Functional Test and Channel Calibration have been inadequate since at least 1°985. A new procedure has been written and successfully completed to verify that *the omitted relays actuate the PORV for Salem Unit 2. Testing is not required on Salem Unit 1 in the prese~t de fueled condition. Salem Unit 1 POPS will be adequately tested prior to being required.

The cause of this occurrence .is attributed to a lack of adequate controls fo;r:

the development and maintenance of Technical Specification surveillance procedures. Corrective actions include revision of proc~~ures, initiation of new procedures and continuation o*f the TSSIP project.

This event is reportable in accordance.with 10 CFR 50.73(a) (2) ( i) ( i3) , any condition prohibited by the plant's Technical Specifications.

NRC FORM 366 (4-95)

NRC FORM 366A u. UCLEAR REGULATORY COMMISSION (4-95)

LICENSEE EVENT REPORT (LER)

ll===============~::"=:~~=o==:=::=:=========T=E=XT===C~O~N~T~l~N~U~A~T~IO=N==~"9'F======'~~====-==o==:=:=:====T===='~==='=:7==9I FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (6) PAGE (3)

.SALEM GENERATING STATION UNIT 1 05 00027 2 YEAR I SErfillriiW~AL I~'ii~~~~ 2 0F 3 97 - 006 - 00 TEXT (If more space is required, use additional copies of NRC Form 366A) (17)

PLANT AND SYSTEM IDENTIFICATION Westinghouse - Pressurized Water Reactor Pressurizer Overpressure Protection System {--/RV}

• 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 and POPS was required to be operable (Reactor Coolant system less than or equal to 312 degree ~ and reactor vessel head in place and tensioned). Salem Unit 1 was defueled and POPS was not required to be operable. '

DESCRIPTION OF OCCURRENCE On March 12, 1997, a review of the Salem Unit 2 Pressurizer Overpressure Protection system (POPS) logic determined that the surveillance procedures did not include relays that are part of the logic for opening the Power Operated Relief V~lves (PORV)" Technical Specification (TS) 4.4.10.3.1.a requires the performance of a channel functional test on each POPS (Channel I and Channel II) 31 days prior to entering a *condition in which POPS is required to be 9perable and at least once per 31 days thereafter when POPS is required to be operable.

Technical Specification 4.4.10.3.1.b requires the performance of a channel calibration on each POPS (Channel I and Channel II) at least once per 18 months.

The POPS logic is designed to actuate the PORV when the reactor pressure exceeds 375 psig when the reactor. coolant temperature is below 312 degrees F..

The channel functional and calibration procedures do not check the complete' POPS logic. Two relays, which are the last relays in the logic train to actuate the PORV, were omitted from the Channel Calibration procedure and one relay was omitted from the Channel Functional Test procedure. After the omission. was identified, both channels of POPS were declared inoperable. A'new proc~dure was written to test these relays and the test was successfully performed. The testing was performed within the 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> allowed by TS Section 4.0.3 for a missed surveillance test.

CAUSE OF OCCURRENCE The cause of this occurrence is attributed to a lack of adequate controls for the development and maintenance of Technical Specification surveillance procedures. This resulted in the failure to identify and correct the procedures for testing of the POPS functions.

NRC FORM 366A (4-95))

NRC FORM 366A mCLEAR REGULATORY COMMISSION (4-95)

LICENSEE EVENT REPORT (LER)

,, . TEXT CONTINUATION ll======='='========~~~~====================;;=================;;====================n=====~=====ll FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (6) PAGE (3)

SALEM GENERATING STATION UNIT 1 05000272 YEAR I SE,fill,i~J~AL I~~~~~~ 3 OF 3 97 - 006 - 00 TEXT (If more space is required, use additional copies of NRC Form 366A) (17)

PRIOR SIMILAR OCCURRENCES A review of LERs for Salem Units 1 and 2 over the last two years identified twenty-six LERs (272/95-004, 272/95-013, 272/95-015, 272/95-019, 272/95-024, 272/95-028, 272/96-003, 272/96-004, 2~~/96-005, 272/96-008, 272/96-016, 272/96-023, 272/96-024, 272/96-026, 311/94-012, 311/95-006, 311/95-008, 311/96-003, 311/96-007, 311/96-010, 311/96-011, 311/96-013, 311/96-016, 311/96-039, 311/96-40 and 311/97-002) that. were due to. inadequate implementation of Tecqnical.

Specification requirements. The corrective actions were specific to the missed surveillance issues addressed in each LER.

The identification of programmatic issues related to the Technical Specification requi*rement ir:nplementation resulted .in the initiation of the *Technical Specifications Surveillance Improvement Program (TSSIP) des<;:ribed in LER 311/95-008. The TSSIP should ensure that Technical Specification* surveillance requirements are adequately proceduralized and will also identify potentially deficient Technical Specification Limiting Condition~ for Operation.

SAFETY CONSEQUENCES AND IMPLICATIONS There were no safety consequences associated with this occurrence. Although the pot~ntial existed for a POPS channel to be in-operable without being identifiedf the tests verified that the relays were operable and there is no evidence that the relays had been inoperable in the past. The he~lth and safety of the public was not affected.

CORRECTIVE ACTIONS

1. A new procedure was written and successfully completed to verify that the omitted relays in the POPS circuitry actuate the PORV for Salem Unit 2.

2. A new procedure will be written for the Salem Unit 1 POPS to verify operation of the omitted relays prior to entry into Mode 6. POPS.is not required to be operable for Salem Unit 1 in the present defueled condition.

3. A Technical Specification Surveillance Improvement Program (TSSIP) has been initiated for Salem Units 1 and 2. The scope and content of the TSSIP.

program was described previously in LER 311/96-008-00. The TSSIP review is expected to be completed December 31, 1997.

NRC FORM 366A (4-95))