ML18101A739

LER 95-004-00:on 790515,used Ten Containment Air Temp Points to Determine Primary Containment Average Air Temp.Caused by Mgt/Qa Defeciency.Implemented Procedure Revs to Satisfy TS SR

ML18101A739
Person / Time
Site:	Salem
Issue date:	05/18/1995
From:	PASTVA M J Public Service Enterprise Group
To:
Shared Package
ML18101A738	List: ML18101A737 ML18101A739
References
LER-95-004-01, LER-95-4-1, NUDOCS 9505310243
Download: ML18101A739 (5)

Text

NRC FORM 366 . U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 (5*92) EXPIRES 5/31/95 c ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS LICENSEE EVENT REPORT (LER) INFORMATION COLLECTION REQUEST: 50.0 HRS. FORWARD 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 Generating Station -Unit 1 05000272 1 OF4 TITLE(41Use ot ten (!U) contairunent air temperature

• points to determine primary contairunent average air temperature (both.units)

EVENT DATE (5) LER NUMBER (6 REPORT NUMBER (7) OTHER FACILITIES INVOLVED f8l SEQUENTIAL REVISION FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR NUMBER NUMBER MONTH DAY YEAR Salem .,... Uri.it 2 05000311 -d5 15 79 95 004 00 05 18 95 FACILITY NAME DOCKET NUMBER ----05000 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) 73.7.1 (b) POWER 94% 20.405(a)(1)(i) 50.36(c) (1) 50.73(a)(2)(v) 73.71(c) LEVEL (10) 20.405 (a) (1) (ii) 50.36 (c) (2) 50.73(a)(2) (vii) OTHER -20.405(a)(1)(iii) x 50.73(a)(2)(i) 50.73(a)(2) (viii) (A) (Specify in Abstract below and in Text, NRG 20.405(a}

(1) (iv) 50. 73 (a) (2) (ii) 50. 73 (a) (2) (viii) (B) Form 366A) 20.405(a)(1)(v) 50.73(a}(2)(iii) 50.73(a)(2)(x}

LICENSEE CONTACT FOR THIS LEA 12) NAME LER Coordinator TELEPHONE NUMBER l"clude Area Code) Michael J. Pastva, Jr. 609 339-5 65 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13) REPORTABLE SYSTEM COMPONENT MANUFACTURER REPORTABLE CAUSE SYSTEM COMPONENT MANUFACTURER TO NPRDS CAUSE TO NPRDS SUPPLEMENTAL REPORT EXPECTED 14) EXPECTED MONTH DAY YEAR I YES x SUBMISSION yes, complete EXPECTED SUBMISSION DATE) NO DATE (15) ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines) (16) Since 5/15/79, PSE&G has used 10 primary containment perimeter locations to determine the primary containment average air temperature to comply with Technical Specification (TS) SURVEILLANCE REQUIREMENT 4.6.1.5, on both Units. In 1992, an internal evaluation determined this practice was an acceptable approach to the surveillance requirement, which specifies use of any 5 of the 10 specified locations.

On 3/21/95, PSE&G determined this practice was not in verbatim compliance with the surveillance requirement.

This event resulted from interpretative oversight of the verbatim requirement to use any 5 of the specified locations.

Procedure revisions have been implemented to satisfy the requirement.

The average air temperature value will be obtained from use c:if 5 primary designated locations.

These designated location::;

have been determined to be representative of containment average air temperature.

The long term solution is to revise the existing TS Surveillance 4.6.1.5 to ref le ct these designated locations.

The importance of procedure adequacy to ensure TS compliance will be stressed with appropriate plant groups. The late submittal of this report has been discussed with NRC Region I Management.

9505310243 950518 PDR A DOCK 05000272 --s PDR --... NRC FORM 366 (5-92)

BLOCK NUMBER 1 2 3 4 5 6 7 8 g 10 11 12 13 14 15 REQUIRED NUMBER OF DIGITS/CHARACTERS FOR EACH BLOCK NUMBER OF DIGITS/CHARACTERS TITLE UP TO 46 FACILITY NAME 8 TOTAL DOCKET NUMBER 3 IN ADDfflON.

TO OSOOO VARIES PAGE NUMBER UP T0-76 -TITLE 6 TOTAL 2 PER BLOCK EVENT DATE 7 TOTAL 2 FOR YEAR 3 FOR SEQUENTIAL NUMBER LER NUMBER 2 FOR REVISION NUMBER 6 TOTAL 2 PER BLOCK REPORT DATE UP TO 18 FACILITY NAME 8 TOTAL -DOCKET NUMBER OTHER FACILITIES INVOLVED 3 IN ADDITION TO 05000 1 OPERATING MODE 3 POWER LEVEL 1 CHECK BOX THAT APPLIES REQUIREMENTS OF .10 CFR UP TO 50 FOR NAME 14 FOR TELEPHONE LICENSEE CONTACT CAUSE VARIES 2 FOR SYSTEM 4 FOR COMPONENT EACH COMPONENT FAILURE 4 FOR MANUFACTURER NPRDS VARIES ... . ..... ****** 1 CHECK BOX THAT APPLIES SUPPLEMENTAL REPORT EXPECTED 6 TOTAL 2 PER BLOCK EXPECTED SUBMISSION DATE ..

' ' I* I * .. LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station Docket Number LER Number Page 2 of 4 Unit # I 50-272 95-004-00 Plant and System Identification:

Westinghouse

-Pressurized Water Reactor Energy Industry Identification System (EIIS) codes appear in the text as {xx} Identification of Occurrence:

Use of Ten (10) Containment Air Temperature Points To Determine Primary Containment Average Air Temperature (Both Units) Event Date: May 15, 1979. Event Discovery Date: March 21, 1995 Report Date: May 18, 1995 This report was initiated by Incident Report No.95-273. Conditions Prior to Occurrence:

Unit 1 Mode** 1 Unit 2 Mode 1 Reactor Power 94% Reactor Power 96% Description of Occurrence:

Unit Load 1090 MWe Unit Load 1060 MWe Since May 15, 1979, ten (10) primary containment perimeter locations have been used, on both Units, for the arithmetical average to determine the primary containment average air temperature.

This practice does not constitute verbatim compliance with Technical Specifications (TS) SURVEILLANCE REQUIREMENT 4.6.1.5, which specifies use of any five (5) of the ten (10) specified locations.

On March 21, 1995, this occurrence was confirmed by PSE&G as a TS compliance issue. The late submittal of this report has been discussed with NRC Region I Management.

LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station Docket Number LER Number Page 3 of 4 Unit # 1 50-272 95-004-00 Analysis of Occurrence:

Limitations on containment average air temperature ensure the overall containment average air temperature does not exceed the initial temperature condition assumed in the accident analysis for a loss of coolant accident or steam line break inside containment.

Since May 1979, ten (10) primary containment perimeter locations have been used in accordance with procedure by the P-250 and Doric process computers to determine primary containment average air temperature.

This practice conflicts with the method to meet the TS surveillance requirement.

On October 20, 1992, Nuclear Licensing

& Regulation had determined this practice complied with the intent of the TS surveillance requirement.

Following the subsequent identification of this occurrence on March 21, 1995, immediate action was taken to satisfy the TS surveillance requirement.

Apparent Cause of Occurrence:

The use of ten (10) locations to determine primary containment ave.rage air temperature is attributed to Quality Assurance Deficiency", as classified in NUREG-1022, Appendix B. This occurred as a result of interpretative oversight of the verbatim requirement to use five (5) locations (averaging ten locations yields a truer average than averaging five locations).

Prior Similar Occurrence:

Review of documentation did not reveal a prior similar occurrence.

Safety Significance:

This occurrence is reportable pursuant to 10CFR50. 73 (a) (2) (i) (B), due to failure to comply with the requirements of TS SURVEILLANCE REQUIREMENT 4.6.1.5. This occurrence had minimal safety significance as use of ten (10) primary containment perimeter locations results in LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station Docket Number LER Number Page 4 of 4 Unit # 1 50-272 95-004-00 Safety Significance: (cont'd) a more accurate value of primary containment average air temperature, than use of the TS prescribed number of locations.

Corrective Action: Following discovery, procedure revisions were implemented to satisfy the TS surveillance requirement by requiring use of designated five (5) primary of the ten (10) primary containment perimeter locations to determine primary containment average air temperature.

These designated locations were determined by Nuclear Engineering to be representative of containment average air temperature.

The long-term solution, in progress, is to revise the existing TS Surveillance 4.6.1.5 to reflect these designated temperature detector locations.

The importance of procedure adequacy to ensure TS compliance will be stressed with appropriate plant groups. MJPJ:vs REF: SORC Mtg.95-049 J. C. Summers General Manager -Salem Operations