05000272/LER-1993-014, :on 930722,determine 4 Kv Vital Bus Second Level Undervoltage Protection Dropout Setpoint Would Not Protect Motors.Detailed Study Showed Motors Would Have Performed Intended Safety Functions

:on 930722,determine 4 Kv Vital Bus Second Level Undervoltage Protection Dropout Setpoint Would Not Protect Motors.Detailed Study Showed Motors Would Have Performed Intended Safety Functions

ML18101A285
Person / Time
Site:	Salem
Issue date:	10/05/1994
From:	Hagan J, Pastva M Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-93-014, LER-93-14, NUDOCS 9410200158
Download: ML18101A285 (6)

LER-1993-014, on 930722,determine 4 Kv Vital Bus Second Level Undervoltage Protection Dropout Setpoint Would Not Protect Motors.Detailed Study Showed Motors Would Have Performed Intended Safety Functions

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(ii) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v), Loss of Safety Function
2721993014R00 - NRC Website

text

e OPS~G 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-70 DOCKET NO. 50-272 UNIT NO. 1 October 5, 1994 SUPPLEMENTAL LICENSEE EVENT REPORT 93-014-02 This submittal is made to reclassify an occurrence as a Voluntary Report for informational purposes.

This occurrence had been previously identified as reportable pursuant to Code of Federal Regulations 10CFR 50.73.

MJPJ:pc Distribution

...,nnr.---~

~

- 4 i i I. '.. J..-:

........ v vu-(; v l11e power is in your hands.

9410200158 941005 PDR ADOCK 05000272 s

Sincerely yours, 95-2189 REV 7-92

N~C FORM 366

.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 (5-92)

EXPIRES 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COME'LY 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 (31S0-0104), 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)

II PAGE (3)

Salem Generating Station - Unit 1 05000 272 1 OF 04 TITLE (4)

Voluntary Reporting of 4 Kilo-Volt Vital Bus Second Level Undervoltage (UV)

I Protection DroJout Setvoint.

EVENT DATE (5)

LER NUMBER f6 REPORT NUMBER f7)

OTHER FACILITl!':S INVOLVED (8)

SEQUENTIAL REVISION FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR NUMBER NUMBER MONTH DAY' YEAR 05000 311 Salem Unit 2 FACILITY NAME DOCKET. NUMBER 05000 07 22 93 93 014 02

.10 05 94 OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check one or more (11)

• MODE (9) 1 20.402(b) 20.405(c) 50.73(a)(2)(iv) 73:71(b)

I L:~E~~~O) I 80 I 20.405(a)(1) 0)

• 50.36(c)(1)

50. 73 (a)(2)(v) 73.71 (c) 20.405 (a)(1 )(ii) 50.36(c)(2) 50.73(a)(2)(vii) x OTHER I

20A05(a)(1)(iii)

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)

Voluntarv J LICENSEE:CONTACT FOR THIS LER (12).

NAME TELEPHONE NUMBER (Include 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

SYSTEM COMPONENT MANUFACTURER REPORTABLE TONPRDS TO NPRDS SUPPLEMENTAL REPORT EXPECTED 14 EXPECTED MONTH DAY YEAR I

YES NO SUBMISSION (If yes, complete EXPECTED SUBMISSION DATE) x DATE (15)

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

On 7/22/93, it was determined that the 91. 6% dropout set point for second level undervoltage protection of both Salem Units' 4* kilovolt (KV) vital buses would not fully protect the 230 and 460 volt (V) motors should the 4KV bus voltage degrade to less than 93.2%, but greater than 91. 6%.

At that time it was concluded the intent of the Updated Final Safety Analysis Report and guidance provided in "Safety Evaluation And Statement Of Staff Positions Relative To The Emergency Power Systems For Operating Reactors" NRC letter, dated 6/2/77, were not fully met.

Continued operation of both Sa_lem Uni ts was based upon self-imposed administrative controls on 4KV bus p.lignment until implementation of design changes to change the dropout setpoint.

A subsequent detailed study shows the motors would have performed their intended safety functions with the 91. 6% setpoint.

As such, this report is made voluntarily for informational purposes.

NRG FORM 366 (5-92)

BLOCK NUMBER 1

2 3

4 5

6 7

8 9

10 11 12 13 14 15 REQUIRED NUMBER OF DIGITS/CHARACTERS FOR EACH13LOCK NUMBER OF DIGITS/CHARACTERS TITLE UP TO 46 FACILITY NAME 8 TOTAL 3 IN ADDITION TO 05000 DOCKET NUMBER VARIES

'PAGE NUMBER UP T076 TITLE 6TOTAL 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

VOLUNTARY LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station Unit 1 DOCKET NUMBER 5000272

PLANT AND SYSTEM IDENTIFICATION

Westinghouse

- Pressurized Water Reactor LER NUMBER 93-014-02 PAGE 2 of 4 Energy Industry Identification System (EIIS) codes are identified in the text as {xx}

REPORT IDENTIFICATION:

Voluntary Reporting Of 4 Kilo-Volt Vital Bus Second Level Undervoltage (UV) Protection Dropout Setpoint Date of Discovery:

7/22/93 Report Date:

10/5/94 This report was initiated by Incident Report No.93-320.

INITIAL"CONDITIONS:

Unit 1:

Mode 1 Reactor Power 80% - Unit Load 815 MWe Unit 2:

Mode 1 Reactor Power 100%

Unit Load 1140 MWe DISCUSSION:

On July 22, 1993, an initial determination was made that the 91.6%

dropout setpoint for second level undervoltage protection of both Salem Units' 4 kilovolt (KVJ vital buses* {VJ}, would not fully protect the 230 and 460 volt (V) motors should the 4KV bus voltage degrade to less than 93.2%, but greater than 91.6%.

At that time it was concluded the intent of the Updated Final Safety Analysis Report

{UFSAR) and guidance provided in "Safety Evaluation And Statement Of Staff Positions Relative To The Emergency Power Systems For Operating Reactors" NRC letter, dated June 2, 1977, were not fully met.

This was identified during a self-initiated adequacy review to ensure the intent of the 1977 NRC letter was being met.

Continued operation of both sa.lem Units was based upon ensuring that the 4KV bus voltage would be maintained at or above 93.2% by imposition of additional administrative controls on 4KV bus alignment until implementation of design changes to change the dropout setpoint.

The NRC was notified of this determination pursuant to 10CFR50.72(b) {l) (ii) (B).

In addition, on August 20, 1993, this issue was reported pursuant to the requirements of 10CFR50.73(a) (2) (ii) (B) and 10CFR50.73(a) (2) (v) (D)

A subsequent detailed study shows the motors would have performed their intended safety functions with the 91.6% setpoint.

Therefore, a reportable occurrence with the setpoint, as described, does not 1

..\\

VOLUNTARY LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station Unit 1 DOCKET NUMBER 5000272 LER NUMBER 93-014-02 PAGE 3 of 4 DISCUSSION: (cont'd) exist pursuant to 10CFR50.72 or 10CFR50.73.

ANALYSIS:

In July 1993, a self-initiated adequacy review concluded the 91.6%.

dropout setpoint for second level undervoltage protection of both Salem Units' 4 KV vital buses, would not fully protect 230 and 460V motors.

Continued operation of both Salem Units was based upon the following self-imposed administrative controls regarding 4KV bus alignment:

1.

Hourly logging of 4KV vital bus voltages, maintained between 4.3KV and 4.5KV.

2.

Maintaining only two vital buses energized from their operating transformer, if both the corresponding group buses are on their respective Auxiliary Power Transformer (APT).

3a.

Maintaining three vital buses energized from the operating transformer, if one of the corresponding group buses is transferred to the operating Station Power Transformer (SPT) or 3b.

Maintaining three vital buses energized from the operating transformer, if the load which can be transferred from the APTs is reduced by 5 mega volt amps.

However, revision 01 to calculation ES-15.00S(Q), "Salem Units 1 and 2 Degraded Grid Study", shows worst case recovery vital bus voltage is 93.2% of 4KV following transfer of the APTs to the SPTs.

A subsequent detailed study shows that the 230 and 460V motors will perform their safety functions with the 91.6% setpoint.

As such, the self-imposed administrative controls serve to add greater enhancement to the performance of these motors, from a reliability standpoint.

The initial determination that the 91.6% dropout setpoint did not meet the intent of the UFSAR and the BTP resulted from overly restrictive conservatism in reviewing/assessing the ES-15.00S(Q), revision 01 calculations, without benefit of the results of the subsequent detailed study.

Dropout setpoint selection at 91.6%*was based on the lowest voltage the 4.16KV motors could be allowed to operate (i.e.

90%) due to voltage drops in the motors' cables and relay inaccuracy considerations.

I~---

VOLUNTARY LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station Unit l DOCKET NUMBER 5000272 LER NUMBER 93-014-02 PAGE 4 of 4 SIGNIFICANCE:

This report is made for informational purposes, since the dropout setpoint provides adequate protection for the worst case design basis event.

As such, this issue is not reportable pursuant the requirements of 10CFR50.73.

ACTIONS TAKEN/PLANNED:

Related design changes, including changing the dropout setpoint, were implemented on Unit 1 during its last refueling outage and are scheduled for Unit 2 during its next refueling outage.

The self-imposed administrative controls will be maintained for Unit 2 until implementation of the aforementioned design changes.

License Change Requests have been submitted to revise Technical Specifications regarding the second level undervoltage relay setpoint.

The importance of adequately considering lower voltage levels whenever evaluating 4KV setpoints for changes has been discussed with the Electrical Engineering Group.

Appropriate changes to the UFSAR will be implemented.

Appropriate documents will be revised to incorporate the results of the subsequent study involving the 91.6% dropout setpoint.

MJPJ:pc SORC Mtg.94-077 ager -

tions