ML18005A752

From kanterella
Jump to navigation Jump to search
LER 88-033-00:on 881125 & 1202,declared Charging Safety Injection Pump (Csip) Inoperable.Caused by 1C Csip Scantily Covered in ESF Response Surveillance Test Procedures.Test to Verify 1C Csip Response Time completed.W/890103 Ltr
ML18005A752
Person / Time
Site: Harris Duke Energy icon.png
Issue date: 01/03/1989
From: Jerrica Johnson, Watson R
CAROLINA POWER & LIGHT CO.
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
HO-880250-(O), LER-88-033, LER-88-33, NUDOCS 8901120436
Download: ML18005A752 (6)
v • d • e


Text

p,c Cp~ ~YED 31STR1BUTI ON DE M 04 STRAT1 ON SYSTEM REG'(+TORY INFORMATION DISTRIBU3N SYSTEM (RIDE j ACCESSION NBR:8901120436 DOC.DATE: 89/01/03 NOTARIZED: NO DOCKET FACIL:50-400 'Shearon Harris Nuclear Power Plant, Unit 1, Carolina 05000400 AUTH. NAME AUTHOR AFFILIATION JOHNSON,J.R. Carolina Power 6 Light Co.

WATSON,R.A. Carolina Power 6 Light Co.

RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

LER 88-033-00:on 881202,Tech Spec violation due to inoperable CSIP caused by failure to perform ST.

W/8 DISTRIBUTION CODE: IE22D COPIES RECEIVED:LTR / ENCL TITLE: 50.73 Licensee Event Report (LER), Incident Rpt, etc.

L SIZE:

NOTES:Application for permit renewal filed. 05000400 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-1 LA 1 1 PD2-1 PD 1 1 BUCKLEYFB 1 1 INTERNAL: ACRS MICHELSON 1 1 ACRS MOELLER 2 2 ACRS WYLIE 1 1 AEOD/DOA 1 1 AEOD/DSP/TPAB 1 1 AEOD/ROAB/DSP 2 2 ARM/DCTS/DAB 1 1 DEDRO 1 1 NRR/DEST/ADE 8H 1 1 NRR/DEST/ADS 7E 1 0 NRR/DEST/CEB 8H 1 1 NRR/DEST/ESB 8D 1 1 NRR/DEST/ICSB 7 1 1 NRR/DEST/MEB 9H 1 1 NRR/DEST/MTB 9H 1 1 NRR/DEST/PSB 8D 1 1 NRR/DEST/RSB 8E 1 1 NRR/DEST/SGB 8D 1 1 NRR/DLPQ/HFB 10 1 1 NRR/DLPQ/QAB 10 1 1 NRR/DOEA/EAB 11 1 1 NRR/DREP/RAB 10 1 1 NRR/DREP/RPB 10 2 2 DR.I IB 9A 1 1 NUDOCS-ABSTRACT 1 1 02 1 1 RES/DSIR/EIB 1 1 RES/DSR/PRAB 1 1 RGN2 FILE 01 1 1 EXTERNAL: EGSG WILLIAMSFS 4 4 FORD BLDG HOYFA 1 1 H ST LOBBY WARD 1 1 LPDR 1 1 NRC PDR 1 1 NSIC HARRISFJ 1 1 NSIC MAYSFG 1 1 NOIR 'IO ALL 'KIDS" RZCZPIENIS:

PURSE HELP US IO REDUCE HASTE> CGMIRCZ 'IHE DOCXIHEPZ CONTROL DESK, RXN P1-37 (EXT. 20079)

ZZSTS MR DOC%KEPIS ~ TO EKaIKMGS %SR ?QMB HKH DZ8TRZBUTIGN DCNFT NEEDf T N> Kl!~!Il w

~,

TOTAL NUMBER OF COPIES REQUIRED: LTTR 45 ENCL 44

NAC Form 385 U.S. NUCLEAR RECULATORY COMMISSION (983)

APPROVED OMB NO. 31604104 EXPIRES: 8/31/88 LICENSEE EVENT REPORT ILER)

FACILITY NAME (1I DOCKET NUMBER l2) PACE 3 Shearon Harris Nuclear Power Plant Unit 1 0 5 0 0 04 0 0 1 OFO 4

"'"echnical Specification Violation Due to Inoperabl'e Charging Safety Injection Pump Caused b Failure to Perform Surveillance Testin EVENT DATE (5) LER NUMBER IS) REPORT DATE (7) OTHER FACILITIES INVOLVED (Sl MONTH DAY YEAR YEAR SEOVSNTIAL "Arr. REVISE" MONTH OAY YEAR FACILITYNAMES DOCKET NUMBER(s)

NVMSSR NVMSSR 0 5 0 0 0 1 2 0 2 88 88 0 3 3 00 0 1 03 89 0 5 0 0 0 THIS AEPORT IS SUBMITTED PUASUANT TO THE REOUIREMENTS OF 10 CFR g: ICnecft one or more of the IOIIOvflnol (ill OPERATINO MODE ISI 60.73(e)l2)(N) 73.71(S) 20A05(cl POWER 20.405 ( ~ ) (1) (II 50.38(c) (11 50.73(e)(2)(v) 73.71(cl LEYEL 1

9%4'0.C02(S) 0 0 20A05(e) l1) IS) 50.38(c) (2) 60.73(eH2)(vll I DTHER Ispeclfy In Aottrect trefow end In Text, IIRC Form 20A05( ~ )11)(ill) 50.73(e) (2)(ll 60 73(e) (2)(vill)(A) 366AI 20A05 (e) (1) ( iv) 50.73(e) (2)(ll) 50.73(el(2)(vill) (BI 6Pcanf c'

'4S o'6".MNI'P'54:i 20.405(e) III(v) 50.73(e) (2)(lii) 60.73( ~ ) (2) (xl LICENSEE CONT'ACT FOR THIS LER (12)

NAME TELEPHONE NUMBER Joseph R. Johnson AREA CODE Senior Specialist Regulatory Compliance 9 19 3 6 2- 2 08 3 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)

CAUSE SYSTEM COMPONENT MANUFAC. EPORTABLE CAUSE SYSTEM COMPONENT MANUFAC EPORTABLE >,

TURER TO NPADS TURER TO NPRDS

.rr..x. c

.c A r rv.rrr .. vr!

'r'UPPLEMENTAL REPORT EXPECTED (lcl MONTH OAY YEAR EXPECTED SU 5 MlSS ION DATE (15)

YES Ilfyer, complere EXPECTED SUSMISSIOH OATEI NO ABSTRACT ILlmlt to f400 tpecee, l.e., eppmxlmetely fifteen tfnolecpece typewritten liner) (18)

ABSTRACT:

On November 25, 1988, at 0345, the 1B Charging Safety Injection Pump (CSIP) was declared inoperable to perform corrective maintenance. The 1C CSIP was placed in service at 0110 on November 26, 1988. On December 2, 1988, during a review of the plant status, the Shift Technical Advisor discovered that all the ESF response testing requirements may not have been completed on the 1C CSIP. An engineering eval.uation was immediately performed to determine operability of the 1C CSIP. It was determined that 1C CSIP should not have been considered operable because certain required surveillance testing had not been completed. As a result, the surveillance requirements of Technical Specifications were not performed at the required interval. The pump was declared inoperable at 1430 on December 2, 1988.

The event occurred because the 1C CSIP was not adequately covered in ESF response surveillance test procedures. Personnel did not realize that all the 18 month surveillance requirements had not been met. The surveillance tests will be revised to ensure that all required testing of the 1C CSIP is performed.

8'7)01120436 890103 PDR ADOCK 05000400 S PNU NRC Form 385 (943)

NRC form 3EBA U.S. NUCLEAR REGULATORY COMMISSION (94)3l LICENSEE EVENT REPORT ILERI TEXT CONTINUATION APPROVED OMB NO, 3150&)04 EXPIRES; 9/31/BB FACILITY NAME (1) DOCKET NUMBER (ll LER NUMBER (B) PAGE (3)

N SEQUENTIAL <<EVOKIN Shearon Harris Nuclear yEA4 krff NUMSE4 NOo NUMOE4 Power Plant Unit 1 0 5 0 0 0 4 0 0 88 03 3 0 0 0 2 OF 0 4 TEXT /IS moro NMoo /4 OO//rr'd, SSO ~ /RrooN/ P/RC Forrrr JSB49/ ((3)

DESCRIPTION:

On November 25, 1988, the plant was operating in Node 1, Power Operation, at

. 100X reactor power. At 0345, the 1B Charging Safety Injection Pump -(CSIP)

(EIIS:BQ:P) was declared inoperable. A 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Limiting Condition for Operation (LCO) began in accordance with Technical Specification 3.5.2, Action "A". The 1B CSIP was removed from service to repair a leak on the equalizing line on the pump casing. When it appeared that the repair could not be completed within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, the decision was made to align the 1C CSIP to replace the 1B pump. The 1C CSIP was placed in service at 0110 on November 26, 1988. The 1C CSIP is a "swing" pump which may be manuall.y connected to either the 1A-SA or 1B-SB electrical bus. The design of the plant prohibits the "swing" pump from being in service unless the pump it. is replacing is out of service. This configuration provides redundant backup for both the 1A and 1B CSIP during maintenance and provides increased operational.

flexibility. The two systems which include "swing" pumps are Safety Injection and Component Cooling Water.

On December 2, 1988, during a review of the plant status, a Shift Technical Advisor discovered that all the applicable Technical Specification surveillance testing requirements may not have been completed on the 1C CSIP. An engineering evaluation was immediately performed to investigate the operability status of the 1C CSIP. The evaluation determined that two surveillance requirements were not met: A test to ensure that the 1C CSIP breaker would trip upon a loss of off-site power (T.S. 4.8.1.1.2.f), and a test to measure the response time from the breaker cLosure signal until the pump reaches full operating pressure (T.S. 4.3.2.2).

The pump was declared inoperable at 1430 on December 2, 1988. A 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Limiting Condition for Operation (LCO) began in accordance with Technical Specification 3.5.2, Action "A". The 1B CSIP repair was subsequently completed and the 1B CSIP was returned to service at 1600 on December 3, 1988.

CAUSE:

r The preoperational testing performed in 1986 demonstrated, through a series of overlapping tests, that the "swing" pumps performed satisfactorily when aligned to either safety bus. Since the "swing" pumps are normally inoperable, they were not included in the methodology for establishing the 18 month surveillance testing of the 1A and 1B pumps. The 18 month surveillance tests do not include specific acceptance criteria for the actuation logic to the "swing" components. With no specific acceptance criteria, this discrepancy in the operability of the 1C CSIP was not flagged for tracking.

As a result, administrative controls did not identify a need to perform special testing on the actuation logic prior to declaring the pump operable.

NRC SQRM 3444 *U.S.GPO:19BB.OB24 d38/4dd 1943)

NRC Form 388A U.S. NUCLEAR REGULATORY COMMISSION (903)

LICENSEE EVENT REPORT (LER1 TEXT CONTINUATION APPROVEO OMS NO. 3)50-0)04 EXPIRES; 8/31/88 FACILITYNAME ill DOCKET NUMSER l2) LER NUMBER (8) PAGE 13)

Shearon Harris Nuclear YEAR ssQUENTIAL o)i'c REVISION NVMSSR NVMSSR Power Plant Unit 1 0 5 0 0 0 8 8 0 3 3 0003 OF 0 4 TEXT /I/ moro soooo /I sou/)or L uso ~ ///o/N/ H/IC forrr 388A's/ II 7)

CAUSE: (continued)

The pump was placed in service in accordance with operating procedures and tested for operability in accordance with Operations Surveillance Test (OST) 1007. This test demonstrated the proper response to an actuation by the control switch and pump performance in accordance with acceptance criteria of the Inservice Testing Program.

ANALYSIS OF EVENT:

This event is being reported as a violation of Technical Specifications in accordance with 10CFR73.(a)(2)(i)(B).

Although the 1C CSIP was inoperable due to failure to perform certain Technical Specifications Surveillance requirements, the pump did operate satisfactorily in its normal charging pump mode, and could reasonably have been expected to perform its safety function if an ESF actuation had occurred. A special test to verify the 1C CSIP response time was successfully completed on December 15, 1988, and a test to verify proper load shedding was completed on December 21, 1988. The 1A CSIP was operable throughout this period. For these reasons, the event had no significant safety consequences or implications.

Plant records were reviewed to identify when the "swing" pumps were previously operable in Modes 1-4, and to determine if the 18 month surveillance testing requirements were satisfied in those circumstances. The 1C CSIP was placed in service at 2138 on February 21, 1987, and remained in service until 1724 on May 20, 1987. The 1C Component Cooling Water Pump was placed in service at 1345 on February 28, 1987, and remained in service until 1344 on March 2, 1987. In these cases, the surveillance requirements were satisfactorily met by the preoperational tests, and the performance dates of the tests were such that the required surveillance test intervals were not exceeded.

There have been no previous similar events.

NRC FORM 368A RU.S.GPO:1988.0824 838/SSS

)983)

NRC Form 388A U.S. NUCLEAR REGULATORY COMM/SSION I9831 LICENSEE EVENT REPORT (LER) TEXT CONTINUATION APPROVEO OMB NO. 3ISOMIOE EXPIRESI 8/31/88 fACILITYNAME Ill OOCKET NUMBER 12l LER NUMBER (Sl PAGE 131 Shearon Harris Nuclear YEAR IIOIX EEOVENTIAL NVMEEII REVISION NVM ER Power Plant Unit 1 TEXT /// more EOeoe /e eorr/'red. See CORRECTIVE ACTION:

~ S/RC %%drm 3ESA'r/ I Ill o s o o o 40088 0 3 3 0 0 04oF04

1. A speciaL test to verify the 1C CSIP response time was successfully completed on December 15, 1988, and a test to verify proper load shedding was successfully completed on December 21, 1988. These test results, along with other applicable tests, document satisfactory completion of the applicable surveillance requirements.
2. Administrative controls are currently tracking the inoperability of the 1C CSIP until completion and approvaL of necessary surveillance tests.
3. Applicable surveillance test procedures will be revised to ensure that all required testing of the 1C CSIP will be performed.
4. Similar actions will be taken to preclude a similar event involving the 1C Component Cooling Water Pump.

NRC SO/IM 3EEA er U.S GPO:19884.828.538/855 1983 l

Carolina Power 8 Light Company HARRIS NUCLEAR PROJECT P.O. Box 165 New Hill, NC 27562 JAN 0 3 )989 File Number'SHF/10-13510C Letter Number'HO-880250 (0)

U.S. Nuclear Regulatory Commission ATTN: NRC Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 DOCKET NO. 50-400 LICENSE NO. NPF-63 LICENSEE EVENT REPORT 88-033-00 Gentlemen.'n accordance with Title 10 to the Code of Federal Regulations, the enclosed Licensee Event Report is submitted. This report fulfills the requirement for a written report within thirty (30) days of a reportable occurrence and is in accordance with the format set forth in NUREG-1022, September 1983.

Very truly yours, R. A. Watson Vice President Harris Nuclear Project JRJ:dj Enclosure cc: Mr. W. H. Bradford (NRC SHNPP)

Mr. B. Buckley (NRR)

Mr. M. L. Ernst (NRC RII)

~pP'EM

'HO-8802500/1/OS1

Retrieved from "https://kanterella.com/w/index.php?title=ML18005A752&oldid=1960726"