ML18100A889

LER 94-002-00:on 940119,determined That Unit May Have Operated Above 3,411 MW Specified in OL Condition 2.C.(1). Administrative Controls Implemented to Power to 95% by Calorimetric

ML18100A889
Person / Time
Site:	Salem
Issue date:	02/17/1994
From:	HAGAN J J, PASTVA M J Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-94-002-01, LER-94-2-1, NUDOCS 9402240010
Download: ML18100A889 (6)

Text

e Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge; New Jersey 08038 Salem Generating Station 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 94-002-00 February 17, 1994 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.

MJPJ:pc Distribution 9402240010 940217 PDR ADOCK 05000311 S . PDR 1 he power is in your hands. Sincerely yours, gan General Manager -Salem Operations 95-2189 REV 7-92

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 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 2 05000 311 1 OF 04 TITLE (4) Reactor Power Higher Than Indicated

.. EVENT DATE (5) LEA NUMBER (6 REPORT NUMBER (7\ OTHER FACILITIES INVOLVED (8) SEQUENTIAL REVISION FACILITY NAME DOCKET NUMBER MONTH DAY YEAR' YEAR NUMBER MONTH DAY *YEAR 05000 NUMBER FACILITY NAME DOCKET NUMBER 01 19 94 94 --002 --00 02 17 05000 94 OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: CChecl< one or more (11) 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) LEVEL (10) 100 20.405(a)(1)(ii) 50.36(c)(2) 50.73(a)(2)(vii)

OTHER I-20.405(a)(1)(iii) x 50.73(a)(2)(i) 50.73(a) (2) (viii) (A) (Specify in Abstract 20.405(a)(1)(iv) 50.73(a)(2)(ii) 50.73(a) (2) (viii) (B) below and in Text, NRC Form 366A) 20.405(a)(1)(v) 50.73(a) (2) (iii) 50. 73 (a)(2)(x)

LICENSEE CONTACT FOR THIS LEA 12) NAME TELEPHONE NUMBER (lnclu.de Area Code) M. J. Pastva, Jr. -*LER Coordinator (609) 339-5165 COMPLETE ONE LINE FOR' EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13) CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE CAUSE SYSTIEM COMPONENT MANUFACTURER REPORTABLE TO NPRDS TO NPRDS ;:;: SUPPLEMENTAL REPORT EXPECTED (14) EXPECTED MONTH DAY YEAR I YES SUBMISSION X (If yes, complete EXPECTED SUBMISSION DATE) NO DATE (15) 03 31 94 ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines) (16) On 1/19/94, review of Unit 2 Fuel cycle 8 calorimetric and Reactor Coolant System flow calculations, determined the Unit may have .. operated above the.3411 megawatts (thermal)

I sp'ecified in Operating License Condition 2.C.(l). .This results from Reactor thermal power being higher than indicated by nuclear instrumentation.

Preliminary data shows a potential indication error ranging from 2.5% to as high as 4.5%, resulting from f eedwater flow being higher than indicated.

To avoid exceeding 100% reactor power, administrative controls have been implemented to limit power to 95% by calorimetric.

Nuclear instrumentation has been adjusted due to the identified error. Existing overtemperature delta temperature (OTDT) and overpower delta temperature (OPDT) setpoints provide adequate margin, as long as rod control is in manual when all rods are not fully withdrawn.

The Unit will be maintained in manual rod control when all rods are not fully withdrawn until new setpoints for OTDT and OPDT are established, to reflect revised full power operating conditions.

The cause of the f eedwater flow indication error is under investigation.

It is anticipated that on or before 3/31/94, a supplement to this report will be provided to detail results of further investigation and testing and safety significance assessment of this event. NRC FORM 366 (5-92)

BLOCK NUMBER f 2 3 4 5 6 7 8 9 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 3 IN ADDITION TO 05000 DOCKET NUMBER VARIES PAGE NUMBER UP TO 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 REQUIREMENTS OF 10 CFR CHECK BOX THAT APPLIES 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 LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station Unit 2 DOCKET NUMBER 5000311 PLANT AND SYSTEM IDENTIFICATION:

Westinghouse

-Pressurized Water Reactor LER NUMBER 94-002-00 PAGE 2 of 4 Energy Industry Identification system (EIIS) codes are identified in the text as {xx} IDENTIFICATION OF OCCURRENCE:

Reactor Power Higher Than Indicated Event Date: 1/19/94 Report Date: 2/17/94 This report was initiated by Incident Report Noo 94-027. CONDITIONS PRIOR TO OCCURRENCE:

Mode 1 Reactor Power 100% -Unit Load 1180 MWe DESCRIPTION OF OCCURRENCE:

on January 19, 1994, review of Unit 2 Fuel Cycle 8 calorimetric and Reactor Coolant System (RCS) flow calculations indicated that either RCS flow was low or that the Unit may have operated above the 3411 megawatts (thermal), specified in Operating License Condition 2.C.(1). Power was reduced by 3% to conservatively compensate for an estimated 2.5% error in indicated power. Preliminary data from a single feedwater flow tracer test on February 3, 1994 shows a potential indication error as high as 4.5%. To avoid exceeding 100% reactor power, administrative controls have been implemented to limit Reactor thermal power to 95% by calorimetric.

In addition, nuclear instrumentation has been adjusted due to the identified error. Existing overtemperature delta temperature (OTDT) and overpower delta temperature (OPDT) setpoints provide adequate margin, as long as rod control is in manual when all rods are not fully withdrawn.

The Unit will be maintained in manual rod control when all rods are not fully withdrawn until new setpoints for OTDT and OPDT are established, to reflect revised full power operating conditions

• . The NRC was notified of this-event per 10CFR50.72(b)

(1) (ii) (B). ANALYSIS OF OCCURRENCE:

Nuclear instrumentation trip setpoints ensure that safety limits for the reactor core and reactor coolant system are not exceeded during normal operation and basis operational occurrences.

Review of Fuel Cycle 8 calorimetric and Reactor Coolant System flow LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station Unit 2 DOCKET NUMBER 5000311 ANALYSIS OF OCCURRENCE: (cont'd) LER NUMBER 94-002-00 PAGE 3 of 4 calculations, shows the Unit's Operating License Condition maximum Reactor power level of 3411 megawatts may have been exceeded.

Initial assessment determined this event resulted from a potential error of 2.5% in actual Reactor thermal power higher than shown by nuclear instrumentation.

Preliminary data from a single f eedwater flow tracer test shows a potential indication error as high as 4.5%. To avoid exceeding 100% reactor power, administrative controls have been implemented to limit Reactor thermal power to 95% by calorimetric.

In addition, nuclear instrumentation has been adjusted for the indicated error. Evaluation of the OTDT and OPDT setpoints shows adequate margin for the existing installed values, provided there are no uncontrolled rod withdraw events. As such, the Unit will be maintained in manual rod control when all rods are not fully withdrawn.

This will prevent uncontrolled rod withdraw events until new setpoints for OTDT and OPDT are established, to reflect revised full power operating conditions.

APPARENT CAUSE OF OCCURRENCE:

The cause of the feedwater flow indication error is presently under investigation.

PRIOR SIMILAR OCCURRENCES:

A review of documentation did not show any prior similar occurrence of this event. SAFETY SIGNIFICANCE:

This is reported pursuant to the requirements of 10CFR50.73(a)

(2) (i) (B) due to error introduced to the nuclear instrumentation as a result of the event. Initial safety assessment by Westinghouse, of the potential effect of operating Salem Unit 2 at 104.5% power, shows no adverse consequence for events such Loss of Cooling Accidents (LOCAs) and the LOCA Containment Integrity This determination was made because depending on the analysis involved, either power level is not an initial condition in the analyses, there is sufficient margin in the analyses to mitigate the effects of the event, or because credit can be taken for items outside of the licensing basis. With regard to non-LOCA events,. power level is both an initial condition and a basis for the setpoints of both the Reactor Protection System and Engineered Safety Feature Actuation System. Following final assessment of the feedwater flow verification test results, the potential impact on safety significance for RPS settings and initial conditions for

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LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station Unit 2 SAFETY SIGNIFICANCE: (cont'd) DOCKET NUMBER 5000311 non-LOCA events will be assessed.

CORRECTIVE ACTION: LER NUMBER 94-002-00 PAGE 4 of 4 Administrative controls have been implemented to limit Reactor thermal power to 95% by calorimetric and nuclear instrumentation has been adjusted due to the identified error. The Unit will be maintained in manual rod control when all rods are not fully withdrawn.

This will prevent uncontrolled rod withdraw events until new setpoints for OTDT and OPDT are established, to reflect revised full power operating conditions.

It is anticipated that on or before March 31, 1994, a supplement to this report will be provided to detail the results of further investigation and testing and safety significance assessment of this event. MJPJ:pc SORC Mtg.94-017