ML18102A247

LER 96-008-00:on 960613,failed to Meet Tech Spec Requirement While in Mode 5 for Natural Circulation.Caused by Insufficient Technical Input for Development of Controls. Revised Operating Logs for Mode 5.W/960711 Ltr

ML18102A247
Person / Time
Site:	Salem
Issue date:	07/15/1996
From:	Garchow D, Hassler D Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-96-008-01, LER-96-8-1, LR-N96193, NUDOCS 9607160242
Download: ML18102A247 (5)

Text

OPS~G e

• Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit JUL 111996 LR-N96193

u. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:

LER 272/96-008-00 SALEM GENERATING STATION - UNIT 1 FACILITY OPERATING LICENSE NO. DPR-70 DOCKET NO. 50-272 This Licensee Event Report entitled "Failure to Meet Technical Specifications Requirement While in Mode 5 for Natural Circulation" is being submitted pursuant to the requirements of the Code of Federal Regulations 10CFR50.73(a) (2) (i) (B).

Sincerely, C2£/Z David F. Garcho~

General Manager -

Salem Operations Attachment SORC Mtg.96-094 DVH/tcp C Distribution LER File 3.7 9607160242 960715 PDR ADOCK 05000272 S PDR The pov.:er is in wur hands.

95-2168 REV. 6/94

Document Control Desk LR-~96193 Attachment A The following item represents the commitment that Public Service Electric & Gas (PSE&G) made to the Nuclear Regulatory Commission (NRC) relative to this LER (272/96-008-00). The commitment is as follows:

Plant operating logs for Mode 5 have been revised to include specific criteria to ensure that the Reactor Coolant System loops are full and natural circulation conditions can be established if steam generators are being relied on for a backup to an inoperable RHR system.

NRCFORM366 (4-95)

U.S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER)

APPROVED BY OMB NO. 3150-0104 EXPIRES 04/30/98 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS MANDATORY INFORMATION COLLECTION REQUEST: 50.0 HRS.

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.e F3~ NUCLEAR (See reverse for required number of REGULATORY COMMISSION, WASHINGTON, DC 20 , AND TO THE PAPERWORK REDUCTION PROJECT (31504!04), OFACE OF digits/characters for each block) MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.

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

SALEM GENERATING STATION, UNIT 1 05000272 1 OF3 TITLE (4)

Failure to Meet Technical Specifications Requirement While in Mode 5 for Natural Circulation EVENT DATE (5) LER NUMBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED (8)

FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR I SEQUENTIAL I REVISION MONTH DAY YEAR NUMBER NUMBER SALEM UNIT2 05000311 06 13 96 96 - 008 - 00 07 15 96 FACILITY NAME DOCKET NUMBER 05000 OPERATING N 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 0 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~in 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)

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 CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE TONPRDS TONPR.DS IYES 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 June 13, 1996, a review identified that Salem Units 1 and 2 had operated in the past in Mode 5 in a condition not in compliance with Technical Specification 3.4.1.4. Specifically, the units were operated with a Residual Heat Removal loop inoperable when the Reactor Coolant System loops may not have been adequately filled to support natural circulation. This issue was identified during reviews as a result of NRC Information Notice 95-35.

The cause of this occurrence is attributed to insufficient technical input for the development of controls for relying on steam generators as a backup method for decay heat removal. Additional controls were subsequently put in place to ensure the availability of natural circulation in Mode 5 with one RHR loop inoperable.

Th{s event is reportable in accordance with 10 CFR 73(a) (2) (i) (B) I any condition prohibited by the plant's Technical Specifications.

NRC FORM 366 (4-95)

NRC FORM 366A (4-95) *

• LICENSEE EVENT REPORT (LER)

• U.S. NUCLEAR REGULATORY COMMISSION TEXT CONTINUATION FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (6) PAGE(3) 05000272 YEAR I SEtfillriCJAAL I~~~~~ 2 OF 3 SALEM GENERATING STATION, UNIT 1 96 - 008 - 00 TEXT (If more space is required, use additional copies of NRC Form 366A) (17)

PLANT AND SYSTEM IDENTIFICATION Westinghouse - Pressurized Water Reactor Residual Heat Removal System (RHR) {BP/-}*

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

CONDITIONS PRIOR TO OCCURRENCE The plant was in Mode 5 prior to each event.

DESCRIPTION OF OCCURRENCE On June 13, 1996, a review identified that Salem Units 1 and 2 had operated in the past in Mode 5 in a condition not in compliance with Technical Specification 3.4.1.4. Specifically, the units were operated with a Residual Heat Removal (RHR) loop inoperable when the Reactor Coolant System (RCS) {AB/-} loops may not have been adequately filled to support natural circulation. Salem Technical Specifications 3.4.1.4, Reactor Coolant System (RCS), states that when in Mode 5, "Two residual heat removal loops shall be OPERABLE and at least one RHR loop shall be in operation." A note to this section states that, "One RHR loop may be inoperable for up to two hours for surveillance testing, provided the other RHR loop is OPERABLE and in operation. Additionally, four filled reactor coolant loops, with at least two steam generators with their secondary side water levels greater than or equal to 5 percent (narrow range), may be substituted for one residual heat removal loop."

NRC Information Notice 95-35 addressed the potential to degrade the ability of steam generators to remove decay heat by natural *circulation. The Information Notice indicated that if the RCS was vented, decay heat removal by natural circulation may not occur. This condition had previously been identified at Vogtle Unit 1 and Turkey Point Units 3 and 4. As a result of the NRC Information Notice, a condition report was initiated in the Corrective Action Program to review this issue for Salem Units 1 and 2. A subsequent engineering evaluation for this issue stated that a minimum RCS pressure of 100 psig must be maintained to take credit for natural circulation. The review completed on June 13, 1996 found occasions where in the past, one RHR loop was inoperable and the RCS pressure was below 100 psig. Additional controls were subsequently put in place to ensure the availability of natural circulation in Mode 5 with one RHR loop inoperable.

NRC FORM 366A (4-95)

NRC FORM 366A (4-95) . ~ *

• LICENSEE EVENT REPORT (LER)

• U.S. NUCLEAR REGULATORY COMMISSION TEXT CONTINUATION FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (6) PAGE (3) 05000272 YEAR I SEQUENTIAL NUMBER IREVISION NUMBER 3 OF 3 SALEM GENERATING STATION, UNIT 1 96 - 008 - OD TEXT (If more space is required, use additional copies of NRC Form 366A) (17)

CAUSE OF OCCURRENCE The cause of this occurrence is attributed to insufficient technical input for the development of controls for relying on steam generators as a backup method for decay heat removal.

PRIOR SIMILAR OCCURRENCES A review of LERs for Salem Units 1 and 2 over the last two years identified one LER that was a result of an industry problem identified in a NRC Information Notice or Generic Letter. LER 272/96-002-01 addressed a concern for motor operated gate valves that were susceptible to pressure locking and thermal binding. This issue was identified in NRC Generic Letter 95-07. Corrective actions were specific to the susceptible valves.

SAFETY SIGNIFICANCE During the period that the steam generators were credited as a decay heat removal source, one train of RHR was available for removal of decay heat. On the loss of the operating RHR loop, the operators would enter the abnormal procedure for loss of RHR and take the appropriate actions. A review of the evaluated occasions determined that there were no challenges to the operating RHR loop and, therefore, no actual safety consequences. The health and safety of the public was not affected.

CORRECTIVE ACTIONS Plant operating logs for Mode 5 have been revised to include specific criteria to ensure that the Reactor Coolant System loops are full and natural circulation conditions can be established if steam generators are being relied on for a backup to an inoperable RHR system.

NRC FORM 366A (4-95)

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