ML17285A152

LER 88-036-00:on 881118,potential Inconsistency Between Tech Spec & Channel Functional Test Surveillance Procedure Noted for Voltage Circuitry.Cause Undeveloped.Emergency Tech Spec Amend Being Submitted & Procedures revised.W/881219 Ltr

ML17285A152
Person / Time
Site:	Columbia
Issue date:	12/19/1988
From:	Davison W, Powers C WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
LER-88-036, LER-88-36, NUDOCS 8812300298
Download: ML17285A152 (7)

Text

gc CELEBRATED DISIKBU'EON DEMONSTRATE ON SYSTEM INFORMATION DISTRIBUTIQ SYSTEM (RIDE)

REGULARLY ACCESSION NBR:8812300298 DOC.DATE: 88/12/19 NOTARIZED: NO DOCKET SCIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 AUTH. NAME AUTHOR AFFILIATION DAVISON,W.S. Washington Public Power Supply System RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

LER 88-036-00:on 881118,potential inconsistency between Tech Spec,& channel functional test surveillance procedure noted.

W/8 ltr.

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

L SIZE:

NOTES:

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PDS LA 1 1 PD5 PD 1 1 SAMWORTH,R 1 1 D

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/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

'RR/DREP/RAB 10 1 1 NRR/DREP/RPB 10 2 2 NRR/DRIS/SIB,9A 1 1 NUDOCS-ABSTRACT 1 1 EG FTL 02 1 1 RES/DSIR/EIB 1 1 ES DSR/PRAB 1 1 RGN5 FILE 01 1 1 EXTERNAL: EG&G WILLIAMS,S 4 4 FORD BLDG HOY,A 1 1 H ST LOBBY WARD 1 1 LPDR 1 1 NRC PDR 1 1 NSIC HARRISFJ 1 1 NSIC MAYS,G 1 1 NOZE 10 ALL 'KIDS" PIZASE HELP US 1O RECCE %RBBEt (XRCACT 'IHE DOCUKKZ CXÃISOL DESKF RXN P1-37 (EXT. 20079) TO ZXZKQQZB YOUR HAME PRCH DISTRIBUTION LISTS MR DOCUKMS YOU DON'T MADE TOTAL NUMBER OF COPIES REQUIRED: LTTR 44 ENCL 43

NRC Form 385 U.S. NUCLEAR REGULATORY COMMISSION (8.83 I APPROVED OMS NO. 31500104 EXPIRES: 8/31/88 LICENSEE EVENT REPORT (LER)

DOCKET NUMBER (2I PAOE (3)

FACILITY NAME (1)

Mashin ton Nuclear Plant - Unit 2 050003971oF05

""""Failure'To Perform Division One 4.16 KV Emergency Bus Undervoltage Degraded Volta e Protection Technical S ecification Surveillance EVENT DATE (5I LER NUMBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED (8)

MONTH DAY YEAR YEAR SEQUENTIAL sri@ REEKS MONTH OAY YEAR FACILITYNAMES DOCKET NUMBER(SI err. NUMBER :ynrrr NUMBER 0 5 0 0 0 1 8 888 8 0 3 6 00 12 1 9 8 8 0 5 0 0 0 THIS AEPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR gs /Cheek one or more Ol the following/ (11)

OPERATINO MODE (8) 20.402(b I 20A05(cl 50,73(e I (2((lvl 73.71(EI 1

POWER 20A05(el(1)(l) 50.38(cl(1) 50.73(e I (2)(v) 73.71(cl LEYEL 1 0 0 20.405 ( ~ ) (1)(ill 50.38(c) (2) 50.73( ~ ) (2)(viil OTHER /Specifyin Ahstrect tsefow end In Text, NIIC Form k4@ 'V--.

20AOd( ~ ) (1) (ill) d0.73(e l(2) (I) 60.73(el(2) (viiiHA) 366AI 20A05(e l(1) (lv) d0.73( ~ ) (2) (ii) 50.73(el(2)(viil) (Bl 20.405 ( ~ ) (1) Iv) 50.73(e I (2) (liI ) 50.73( ~ l(2)(xl LICENSEE CONTACT FOR THIS LER (12I NAME TELEPHONE NUMBER AREA CODE D C liance En ineer 509 377 -2 501 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE OESCRIBEO IN THIS REPORT (13) EXT, 2726 COMPONENT'ANVFAC. EPOATASLE MANUFAC. EPDATASLE " 'E~ r fn orktysse'ryo 8 CAUSE SYSTEM TO NPADS SYSTEM COMPONENT TVREA yss)$

TVAER TO NPRDS kn SUPPLEMENTAL REPORT EXPECTED (14) MONTH DAY YEAR EXPECTED SUBMISSION DATE (I 5)

YES II/ yN, complete EXPECTED St/Efrt ISSIO/I DATE/ NO ABSTRACT ILimiI to f400 soccer. I e., epproximetely li fteen sinple.specs typewriven linN/ (16)

On November 18, 1988, a self initiated Safety System Functional Inspection (SSFI) being performed by the Supply System Engineering Assurance Organization revealed an potential inconsistency between the Channel Functional Test Surveillance Procedure and the Technical Specification requirement for the Division One 4.16 KV Emergency Bus Undervoltage Degraded Voltage (Second Level Undervoltage) protection circuitry. A Nonconformance Report was written to document this condition and initiate further evaluation. On November 21, 1988, further evaluation of this condition resulted in the determination that the Channel Calibration for the Division One Second Level Undervoltage 3 second time delay relay (E-RLY-27/Sj/UV) had not been performed within the 18 month frequency required by Plant Technical Specification Table 4.3.3.1-1 Section D.2.

After evaluation and direction by Plant Management, the circuitry was .declard inoperable, calibrated and then returned to service. The root causes have not been completely developed at this time. This event posed no threat to the safety of Plant personnel or the public. f e V~

88g219 aggp300298 p>0003))7 o

pDR ADOCV PNU 8

NRC Form 388

NRC Form 388A U.S. NUCLEAR REGULATORY COMMISSION (Ba3)PA

-'ICENSEE QNT REPORT:ILES)'TEXT:CONTINUON APPROVE'0 OMB NO. 3)50-0104 EXPIRES: 8/31/BB FACII Y NAME Ill DOCKET NUMBER (3) LER NUMBER (8) PACE (3)

YEAR SEQUENTIAL REVISION NUMBER NUMSER 3

Washin ton Nuclear Plant - Unit 2 0 5 0 0 0 3 9 7 8 8 0 3 6 0 00 2o" 05 TEXT f)fmare space fs rerfvfred. vse sddr'0'orMf HRC Form JSSA'sl (17)

Plant Conditions a) Power Level - 100K b) Plant Mode - 1 (Power Operation)

Event Descri tion On November 18, 1988, a self initiated Safety System Functional Inspection (SSFI) being performed by the Supply System Engineering Assurance Organization revealed a potential inconsistency between the Channel Functional Test Surveillance Procedure and the Technical Specification requirement for the Division One 4.16 KV Emergency Bus Undervoltage Degraded Voltage (Second Level Undervoltage) protection ci rcuitry.

A Nonconformance Report was written to document this condition and initiate further evaluation. On November 21, 1988, further evaluation of this condition resulted in the determination that the Channel Calibration for the Division One Second Level Undervoltage 3 second time delay relay (E-RLY-27/S7/UV) had not been performed within the 18 month frequency required by Plant Technical Specification Table 4.3.3.1-1 Section D.2.

Immediate Corrective Action Significant discussions concerning a discretionary enforcement request occurred between the Supply System staff, NRC Region Five staff and NRR during the morning and early afternoon of November 21, 1988. For the purposes of this LER, however, the reportable event occurred at 1400 hours0.0162 days <br />0.389 hours <br />0.00231 weeks <br />5.327e-4 months <br /> when Technical Specification Section 3.0.3 was entered.

On November 21, 1988, after evaluation and direction by Plant Management, the following actions were taken by WNP-2 Plant Staff:

1400 hours0.0162 days <br />0.389 hours <br />0.00231 weeks <br />5.327e-4 months <br /> - Division One Second Level Undervoltage System was declared inoperable 1 h 1 1 dp 111 1 L.t.d. 1 3 3.3.3 d. 3 Emergency Classification of Unusual Event was declared.

1459 hours0.0169 days <br />0.405 hours <br />0.00241 weeks <br />5.551495e-4 months <br /> - With initial plant power level at 100 percent, plant operators began

~p 1 1 p requirements of the WNP-2 Technical Specifications.

3 1 ht d h 31 1" d 1 h th 1510 hours0.0175 days <br />0.419 hours <br />0.0025 weeks <br />5.74555e-4 months <br /> - The channel calibration for the Division One Second Level Undervoltage d13 1 t d.

1755 hours0.0203 days <br />0.488 hours <br />0.0029 weeks <br />6.677775e-4 months <br /> - The Division One channel calibration was completed satisfactorily.

1800 hours0.0208 days <br />0.5 hours <br />0.00298 weeks <br />6.849e-4 months <br /> - The Division One 4.16 KV Second Level Undervoltage circuit was declared pPP fh tt

~tf

. p1 p d h1 d 333.

1925 hours - Technical Specification Action Statement 3.0.3 was exited and the

• pl'1 1 f 3 1 3 NRC FORM SOSA ~ U.S ~ GPOr 'L988-f20 S89/00010 (843)

NRC Form 388A U rL NUCLEAR REOULATORY COMMISSION (943) g.

LICENSEE NT REPORT (LER) TEXT CONTIN ON' APPROVE'0 OMB NO. 3150-0(04 EXPIRES: 8/31/88 FACI IY NAME (1) OOCKET NUMBER (2) LER NUMBER (8) PAOE (3)

YEAR ~

~%%

SEQUENTIAL NUMBER R6VISION NUMBER Washington Nuclear Plant - Unit 2 p s p () p 3 9 7 8 8 0 3 0 0 OF TEXT /// more 8/Mos /s rer/Ir/red, Iree edditione//VRC Form 3//I/4's/ (17)

Further Evaluation and Corrective Action Further Evaluation

1. This event is being reported as a "condition prohibited by the plants Technical Specification" per the requirements of 10CFR50.73(a)(2)(i)(B).

2. The root causes for this event have not been completely developed at this point. The following preliminary cause information is presented as status on the root cause determination effort. Additional information will be provided in a supplemental 'report:

o Procedure Failure - Prior to initial fuel load and plant licensing in ecem er o , discussions were held between WNP-2 and the Nuclear Reactor Regulations branch of the NRC,concerning the time delay design for Division One, Two and Three Second Level Undervoltage protection schemes.

The WNP-2 staff interpretation was that the extent to which the channels were testable was previously approved and defined by the channel design.

The 3 second time delay 'elays and the Division Three Second Level Undervoltage circuitry were subsequently not included in any Technical Specification Surveillance procedures for channel calibration or functional testing. They were both included in the Logic System Functional Tests which are performed on an annual basis.

o Mana ement System Error - The discussions with NRR were not documented nor was t ere any de one .method to accomplish this. 'As a result of this less than adequate management system process, the Technical Specification Surveillances procedures may not have been adequately written to accompl.ish these particular requirements of the WNP-2 Technical Specifications. The Supply System has since developed a Technical Specification interpretation procedure which requires Plant Operations Committee approval to implement an interpretation.

3. Both the Division One and Division Two Second Level Undervoltage 3 Second Time Delay Relay Calibrations have been previously controlled via the plants non-Technical Specification Surveillance Testing Program at two year required intervals. The Division Two Second Level Undervoltage 3 Second Time Delay Relays did not require calibration because they had been calibrated during the 1987 annual refueling outage via the non-Technical Specification Testing Program. The Division One Surveillance was scheduled for the 1988 annual outage but was deferred for performance during the 1989 outage. Prior to the performance on November 21, 1988, the Division One Second Level Undervoltage 3 second time delay relay had not been calibrated since initial plant startup.

NRC FORM 088A II~ 8 ~ CPOr (988-520-589r00070 (943)

NRC Form 3BBA (943) r LICENSEE NT.:REPORT (LER) TEXT CONTIN ON'.S. NUCLEAR REOULATORY COMMISSION

~ APPRQVEO OMB NO. 3)SOM104 EXPIRES: 8/31/88 FACEIITY NAME (1) OOCKET NUMBER (3) LER NUMBER (8) PACE (3)

SEQUENTIAL REVISION NUM ER NUMBER Washington Nuclear Plant TEXT /i/ moro EPoco /r roOII/rod, Irro oddidons/NRC %%drm

- Unit 35843/ ()7) 2 o s << o 3 9 7 8 8 036 00 04 OF 0 4~ The Division One (and Division Two) Second Level Undervoltage protection consists, of three ITE static type definite time undervoltage relays and three secondary time delay (3 second) relays. The undervoltage relays monitor the three phases of the 4160 volt emergency busses. These three relays each provide two contacts which contribute to a two out of three logic array. The relays are set to actuate at approximately 87.3% of nominal bus voltage and will change the state of their contacts following a 5 second time delay.

Actuation (contact closure) of two of these relays will energize two of three secondary time delay (3 second) relays. These three second time delay relays contribute to the total eight second time delay referenced in the WNP-2 FSAR and the Technical Specification. They are the end-point relays which actuate circuit breaker movement, alarms and other functions.

On December 2, 1988, during subsequent evaluation of the Division One 4.16 KV Emergency Bus Second Level Undervoltage event, a possible inconsistency was discovered concerning the Technical Specification surveillance requirements for the Division Three 4.16 KV Emergency Bus Second Level Undervoltage circuitry.

The Division Three circuitry is not specifically called out in Technical Specification Table 3.3.3-1, ECCS Minimum Channels Required, nor listed in Table 4.3..3-1, ECCS Surveillance Requirements. Its setpoint is, however, listed in Table 3.3.3-2, ECCS Actuation Setpoints.

On December 2, 1988, during a plant outage, the Division 3 Second Level Undervoltage Channel Calibration Test was successfully performed per the requirements of the WNP-2 Technical Specifications.

Further Corrective Action WNP-2 is currently involved in discussion with NRR and NRC Region Five Staff concerning this issue. An emergency Technical Specification amendment with a Safety Analysis is being submitted to clarify the testing requirements.

Included in this discussion is the exclusion of the Division Three circuitry from the Channel Functional Test requirement due to the inability to test this circuit during power operation without loss of the circuit protective function and without the use of jumpers to place the logic in a tripped condition. The emergency Technical Specification change will address the Division One, Two and Three Technical Specification surveillance requirements.

2. Channel Calibration Technical Specification Surveillance procedures have been revised to include the Division One and Division Two 3 second time delay relays.

NRC FORM SEBA AU.S. OPOI (988 520 589/OOOTO (84)3)

NRC Fyrm 388A U.S. NUCLEAR REOULATORY COMMISSION (943), '

LICENSEEhNT REPORT (LERI TEXT CONTINUATION 'APPROOEDoMh'N0.31NMI04 EXPIRES: 8/31/88 FACI. TY NAME (1) OOCKET NUMBER (3) PACE (3)

LER NUMBER (8)

~I SEQUENTIAL j'r'SI REVISION NUMBER o%$ NUMBER P - U 0 5 0 0 0 3 OF TEXT ///more epeoe /8 rer/0/rerL ore er/I/r&nal//RC Form 3SEA'8/ (IT)

Safety Si nificance Upon notification by NRC Region Five staff that a plant shutdown must be initiated absent of formal receipt of discretionary enforcement, the Division One Second Level Undervoltage circuitry was declared inoperable and, appropriate action was taken to

,place the plant in the condition specified by the Technical Specifications. The Division Two Second Level Undervol tage circuitry was operable during this entire period of time, therefore the redundant Division Two 4.16 KV Emergency Bus was capable of performing all of the functions required to establish safe shutdown during accident conditions. Normal Onsite and Offsite electrical power distribution systems were operable during this event. This event posed no threat to the *safety of Plant personnel or the public.

Similar Events None EIIS Information Text Reference EIIS Reference System Component Division One/Two/Three 4.16 KV Emergency Bus Undervoltage EA 27 Degraded Voltage Protection Circuitry E- RL Y-27/S7/U V EA 27 3 Second Time Delay Relay NRC FORM 088A rU.S ~ CPOr IBSB-530-588r00070 IB %3 I

WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O. Box 968 ~ 3000 George Washington Way ~ Richland, Washington 99352 Docket No. 50-397 December 19, 1988 Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Subject:

NUCLEAR PLANT NO. 2 LICENSEE EVENT REPORT NO.88-036

Dear Sir:

Transmitted herewith is Licensee Event Report No.88-036 for the WNP-2 Plant.

This report is submitted in response to the report requirements of 10CFR50.73 and discusses the items of reportability, corrective action taken, and action taken to preclude recurrence.

Very truly yours,

.M. Powers (M/D 927M)

WNP-2 Plant Manager CMP:lg

Enclosure:

Licensee Event Report No.88-036 cc: Mr. John B. Martin, NRC - Region V Mr. C.J. Bosted, NRC Site (M/D 901A)

INPO Records Center - Atlanta, GA Ms. Dottie Sherman, ANI Mr. D.L. Williams, BPA (M/D 399)

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