ML18102A207

LER 96-007-00:on 960524,determined P-12 Setpoint Above Tech Spec Table 3.3-3 Value.Caused by Incorrect Conversion from Standard Tech Spec for Westinghouse Pressurized Water Reactors. Revised procedures.W/960621 Ltr

ML18102A207
Person / Time
Site:	Salem
Issue date:	06/24/1996
From:	Garchow D, Hassler D Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-96-007-01, LER-96-7-1, LR-N96176, NUDOCS 9606280109
Download: ML18102A207 (5)

Text

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0.PS~G Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit JUN 21 1996 LR-N96176 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:

LER 272/96-007-00 SALEM GENERATING STATION - UNIT 1 FACILITY OPERATING LICENSE NO. DPR-70 DOCKET NO. 50-272 This Licensee Event Report entitled "ESFAS Permissive (P-12) Above TS Table 3.3-3 Value" is being submitted pursuant to the requirements of the Code of Federal Regulations 10CFRSO. 73 (a) (2) (i) (B).

O:Der.~

David F. Garchow General Manager -

Salem Operations Attachment SORC Mtg.96-086 DVH/tcp C Distribution LER File 3.7 9606280109 960624

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PDR ADOCK 05000272 S PDR The power is in your hands.

95-2168 REV. 6/94

) Document Control Desk LR~N96176 Attachment A The following item represents the commitments that Public Service Electric & Gas (PSE&G) made to the Nuclear Regulatory Commission (NRC) relative to this LER (272/96-007-00). The commitments are as follows:

1. A Technical Specification Surveillance Improvement Project (TSSIP) has been initiated for Salem Units 1 and 2. The scope and content of the TSSIP program was described previously in LER 311/95-008-00. The TSSIP review is expected to be completed by December 31, 1997.

2. Resolve the difference between the Tavg setpoint in TS Table 3.3-4 (543 F) and the manual block permissive in TS Table 3.3-3 (541 F). This will be completed prior to either unit entering Mode 3.

3. Based on the results of Corrective Action 2, develop a License Change Request (LCR) to correct the Technical Specifications, if necessary.

This LCR must be implemented prior to either unit entering Mode 3.

4. Revise procedures to ensure compliance with the channel calibration requirements as it relates to the block/permissive functions of the protection circuits. This will be completed prior to either unit entering Mode 3.

NRCFORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 (4-95) EXPIRES 04130198

- . ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS MANDATORY INFORMATION COLLECTION REQUEST: 60.0 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 (HI ~NUCLEAR (See reverse for required number of REGULATORY COMMISSION, WASHINGTON, DC , AND TO THE PAPERWORK REDUCTION PROJECT ~150-0104), OFFICE OF digits/characters for each block) MANAGEMENT AND BUDGET, WASHINGTON, 20503.

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

SALEM GENERATING STATION, UNIT 1 05000272 1 OF 3 TITLE (4)

ES FAS Permissive (P-12) Above TS Table 3.3-3 Value 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, Unit 2 05000311 05 24 96 96 - 007 - 00 06 24 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) S~~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)

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 TONPRDS

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mtmnnn SUPPLEMENTAL REPORT EXPECTED (14) EXPECTED MONTH DAY YEAR IYES SUBMISSION (If yes, complete EXPECTED SUBMISSION DATE). XINO DATE (15)

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

During a review of pending Design Change Package 2EC-3264 a compliance problem with Technical Specification (TS) 3.3.2.1 was identified. This TS provides that with two out of four Tavg channels less than 541 degrees F the P-12 interlock will allow a manual block of the Safety Injection actuation on high steam line flow and low steam line pressure. On May 24, 1996 it was determined that the P-12 setpoint for allowing manual block of the SI function was 543 degrees F instead of 541 degrees F.

The cause of the non-compliance is that the conversion from the "Standard Technical Specifications for Westinghouse Pressurized Water Reactors", NU REG 0452 was not correctly implemented. This led to the presence of two values in the TS applicable to Low Tavg ( 541 degrees F and 543 degrees F) . Since the design cannot accommodate both setpoints, and since there is no specific requirement to calibrate the 541 degree setpoint, the 543 degree setpoint was used in applicable procedures. Corrective action includes revision to applicable procedures and a review of the TS for necessary change(s) .

This event is reportable in accordance with 10 CFR. 73 (a) (2) (i) (B) ' any condition prohibited by the plant's TS.

NRC FORM 368 (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 96 - 007 - 00 TEXT (If more space is required, use additional copies of NRC Form 366A) (17)

PLANT AND SYSTEM IDENTIFICATION Westinghouse- Pressurized Water Reactor Engineered Safety Features Actuation System Instrumentation {BP/RLY}*

• Energy Industry Identification System (EIIS) system and component codes appear in the text as {SS/CC}

CONDITIONS PRIOR TO OCCURRENCE At the time of identification, Salem Units 1 & 2 were shutdown and defueled.

The TS Mode applicability is Modes 1, 2 and 3##. (##: Trip function may be bypassed in this Mode below P-12). P-12 is defined as the reactor coolant average temperature signal which allows manual block of safety injection actuation on high steam flow and blocks steam dump to prevent undesired cooldown.

DESCRIPTION OF OCCURRENCE TS 3.3.2.1 requires that the Engineered Safety Feature Actuation System (ESFAS) instrumentation channels and interlocks shown in Table 3.3-3 shall be operable with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table.3.3-4 and with response times as shown in Table 3.3-5.

The TS Mode applicability is Modes 1, 2 and 3##. (##: Trip function may be bypassed in this Mode below P-12). Table 3.3-3 defines P-12 as the reactor coolant average temperature signal which allows manual block of safety injection actuation on high steam flow and blocks steam dump to prevent undesired cooldown. The value for P-12 in TS Table 3.3-3 is less than 541 degrees F. The manual block is used to enable normal plant shutdown below 541 degrees F without incurring an inadvertent Engineered Safety Features (ESF) actuation.

TS Table 3.3-4 provides for a Safety Injection signal on a decreasing Tavg coincident with high steam flow. The Tavg setpoint is equal to or greater than 543 degrees F.

During a review of pending Design Change Package 2EC-3264 a potential compliance problem with Technical Specification (TS) 3.3.2.1 was identified. On May 24, 1996 it was determined that the P-12 setpoint for allowing block of the SI function was 543 degrees F instead of 541 degrees F.

It was also determined that the existing system design, with a single bistable for Low-Low Tavg in each channel cannot satisfy both setpoints.

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) 05000272 YEAR I SEQUENTIAL NUMBER IREVISION NUMBER 3 OF 3 SALEM GENERATING STATION, UNIT 1 96 - 007 00 TEXT (If more space is required, use additional copies of NRC Form 366A) (17)

CAUSE OF OCCURRENCE The cause of the non-compliance is that the conversion from the "Standard Technical Specifications for Westinghouse Pressurized Water Reactors", NUREG 0452 was not correctly implemented. This resulted in the presence of two different values in the TS that are applicable to Low Tavg. The value for P-12 is described in TS Table 3.3-3 as 541 degrees F. The Low-Low Tavg setpoint of 543 degrees F is in TS Table 3.3-4. Since the design cannot accommodate both setpoints, and since there is no specific requirement to calibrate the 541 degree setpoint, the 543 degree setpoint was used in the I&C Surveillance Procedures to set P-12.

PRIOR SIMILAR OCCURRENCES This event is similar to LER 311/96-003 in that the design of the ESFAS does not support requirements in the TS. It is also similar to LER 311/95-008 in that Surveillance Procedures did not satisfy TS requirements.

SAFETY CONSEQUENCES AND IMPLICATIONS There was no safety consequence to the block function being enabled at 543 degrees F vice 541 degrees F for the following reasons: 1) the SI trip function was operable with its setpoint according to TS Table 3.3-4, 2) TS Table 3.3-3 allows the manual block to be in effect in Mode 3 until 545 degrees F is achieved, 3) the system design provides for automatically removing the block on increasing temperature above 545 degrees F, and 4) the TS prohibits use of the manual block in Modes 1 and 2 and the reactor is subcritical in Mode 3.

Therefore the health and safety of the public was not affected by this occurrence.

CORRECTIVE ACTIONS

1. A Technical Specification Surveillance Improvement Project (TSSIP) has been initiated for Salem Units 1 and 2. The scope and content of the TSSIP program was described previously in LER 311/95-008-00. The TSSIP review is expected to be completed by December 31, 1997.

2. Resolve the difference between the Tavg setpoint in TS Table 3.3-4 (543 F) and the manual block permissive in TS Table 3.3-3 (541 F). This will be completed prior to either unit entering Mode 3.

3. Based on the results of Corrective Action 2, develop a License Change Request (LCR) to correct the Technical Specifications, if necessary. This LCR must be implemented prior to either unit entering Mode 3.

4. Revise procedures to ensure compliance with the channel calibration requirements as it relates to the block/permissive functions of the protection circuits. This will be completed prior to either unit entering Mode 3.

NRC FORM 366A (4-95)