ML17286B125

From kanterella
Jump to navigation Jump to search
LER 91-028-00:on on 910930,containment Airlock Door Seal Leakage Test Not Performed within Allowable Surveillance Interval.Caused by Inadequate Personnel Work Practices. Master Startup Checklist amended.W/911030 Ltr
ML17286B125
Person / Time
Site: Columbia Energy Northwest icon.png
Issue date: 10/30/1991
From: John Baker, Swank D
WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GO2-91-199, LER-91-028, LER-91-28, NUDOCS 9111060116
Download: ML17286B125 (6)
v • d • e


Text

ACCELERATED DISTRIBUTION DEMONSTRATION SYSTEM

~ ~

REGULATORY INFORMATXON DXSTRIBUTXON SYSTEM (RIDS)

ACCESSION NBR:9111060116 DOC.DATE: 91/10/30 NOTARIZED: NO DOCKET I FACXL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 AUTH. NAME AUTHOR AFFILIATION SWANK',D.A. Washington Public Power Supply System

'BAKER,J.W. Washington Public Power Supply System RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

LER 91-028-00:on on 910930,containment airlock door seal leakage test not performed within allowable surveillance interval. Caused by inadequate personnel work practices.

Master startup checklist amended.W/911030 ltr.

DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR TXTLE: 50.73/50.9 Licensee Event Report (LER),

gIncident ENCL g SIZE:

Rpt, etc.

NOTES:

RECIPXENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD5 LA 1 1 PD5 PD 1 1 ENG,P.L. 1 1 INTERNAL: ACNW 2 2 ACRS 2 2 AEOD/DOA 1 1 AEOD/DSP/TPAB 1 1 AEOD/ROAB/DSP 2 2 NRR/DET/ECMB 9H 1 1 NRR/DET/EMEB 7E 1 1 NRR/DLPQ/LHFB10 1 1 NRR/DLPQ/LPEB10 1 1 NRR/DOEA/OEAB 1 1 NRR/DREP/PRPB11 2 2 NRR/DST/SELB 8D 1 1 NRR/DST/SICB8H3 1 1 RR+D - LBSD1 1 1 NRR/DST/SRXB 8E 1 .1 EG FILE 02 1 1 RES/DSIR/EIB 1 1 RGN LE 01 1 1 EXTERNAL: EG&G BRYCE,J.H 3 3 L ST LOBBY WARD 1 1 NRC PDR 1 1 NSIC MURPHY,G.A 1 1 NSIC POOREIW 1 1 NUDOCS FULL TXT 1 1 NOTE TO ALL "RIDS" RECIPIENTS PLEASE HELP US TO REDUCE 9 ASTE! CONTACT THE DOCUMENT CONTROL DESK, ROO>I Pl-37 {EXT. "-N79) TO 1LIMINATEYOUR NAivIE FROM DISTRIBUTION LISTS FOR DOCUiilENTS YOU DON'T NEED!

FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 33 ENCL 33

~,

4a WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O. Box 988 ~ 3000 George )Vashington Way ~ RichIand, Washington 99352 October 30, 1991 Ci02-91-199 Docket No. 50-397 Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Subject:

NUCLEAR PLANT NO. 2 LICENSEE EVENT REPORT NO: 91-028

Dear Sir:

Transmitted herewith is Licensee Event Report No.91-028 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,

~ W. Baker WNP-2 Plant Manager

Enclosure:

Licensee Event Report- No.91-028 cc: Mr. John B. Martin, NRC Region V Mr. C. Sorensen, NRC Resident Inspector (M/D 901A)

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

NRC Resident Inspector walk over copy pL

NRC FORM 3$ 6 (64(9) 'PPROVED US. NUCLEAR REGULATORY COMMISSION OMB NO. 31604)104 EXPIRES: 4I30I92 ESTIMATED BURDEN PER RE$ PONSE TO COMPLY WTH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS. FORWARD LICENSEE EVENT REPORT (LER) COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH (F430), U.S. NUCLEAR REGULATORY COMMISSION. WA$HINGTON, OC 20565, AND TO THE PAPERWORK REDUCTION PROJECT (31600104), OFFICE OF MANAGEMENTAND BUDGET, WASHINGTON. DC PA 20603'ACILITY DOCKET NUMBER l1) E 3 NAME (1) 0 5 0 0 0 1 OF TITLE ( ~ )

Seal Test No't Performed in Allowable Time Period EVENT DATE (6) LER NUMBER (6) REPORT DATE (7) OTHER FACILI'TIES INVOLVED (Bl

~~X". SEQUENTIAL IIEVISION MONTH DAY YEAR FACILITYNAMES DOCKET NUMBER($)

MONTH OAY YEAR YEAR NUMBER NUMBER 0 5 0 0 0 028 0 1 0 3 0 THIS REPORT IS SUBMITTED PURSUANT 7 0 THE RtoUIREMENTs oF 10 cFR (II Icnrcs onr of morr of tnr forrovnnp) (11 0 5 0 0 0 OPERATINQ (i(i)

MODE (9) 20.402(s) 20.40S(c) 60.73(v)(2) (ivl 73.71(6)

POWER 20.406(sl(1)(il 50.36 (c) (I ) 60.73(s) l2)(v) 73.71(c)

LEVEL OTHER ISprclfy ln Apttrrct (10) 20.40$ (s'll1)(il) 50.36(cl(1) 50.73(sl(2) lvii) tNrow md ln Trst, ffRC Form 20.406(s) (1) 50,73(s) (1HI) $ 0,73(s)(2) ( villi(A) 3664) i@/(;. (TBI(~gp~gvp 20.405 (~ )(I ) (lv) 50.73( ~ ) l2) lii) 60.73( ~ l(2)(villi(8)

(Q$

",. I".I'P~igp@j:

20.406( ~ l(1) lvl 50.73(sl(1) liiil 60.73( ~ )(2)(s)

LICENSEE CONTACT FOR THIS LER ((2)

NAME TELEPHONE NUMBER AREA CODE COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)

MANUFAC. EPORTABLE MANUFAC. EPORTABLE CAUSE SYSTEM COMPONENT TURER TO NPRDS .; '.,':E~~~~~:.

CAUSE SYSTEM COMPONENT TUBER TO NPRDS 5<Wix'='.;"

SUPPLEMENTAL REPORT EXPECTED (14) MONTH OAY YEAR EXPECTED SUBMISSION DATE (15I YFS (if yrt. complrtr EXPECTED SUBMISSION DATE) NO ABSTRACT (Limit ro trp0 tprcrt. I r.. rpprosimrrrty fi ltrrn tinprrrprcr ryprwritrrn linrrl l16)

On September 30, 1991 at 1036 hours0.012 days <br />0.288 hours <br />0.00171 weeks <br />3.94198e-4 months <br /> the containment airlock door seal leakage test required by Technical Specification 3/4.6.1.3 was not performed within the allowable survei 1,lance interval. This is a deviation from the plant's Technical Specifications and is reportable in accordance with the requirements of 10 CFR 50..73(a)(2)(i)(B).

WNP-2 entered Node 2 from,Node 4 at 1636 hours0.0189 days <br />0.454 hours <br />0.00271 weeks <br />6.22498e-4 months <br /> on September 26, 1991. From that time the plant had 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> (plus 255 or 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br />) to complete the required airlock seal test. The test was completed approximately four hours after expiration of the Technical Specification allowed surveillance interval, but within the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period provided in Action Statement 3.6.1.3.c.

The. root cause of this event is personnel work practices less than adequate in that an intended or requi red veri fication was not performed . A procedurally required verification that the airlock seal test be performed in the allotted time period was not satisfied'orrective actions include: 1) Immediate performance of the required testing within tile Action Statement time requirements; 2) Deviations to plant startup procedures to include specific guidance and requirements to ensure the test is performed prior to entry into the applicable Operational Condition; and 3) 7'his LLR wi.ll be required reading for Operations personnel.

NRC Form 366 (649)

NRC FORM 388A U S NUCLEAR REGULATORY COMMISSION APPROVEO OMB NO. 31504)104 I689)

EXPIRES: 4/30/92 TIMATED BURDEN PEA RESPONSE TO COMPLY WTH THIS LICENSEE EV NT REPORT {LER) INFORMATION COLLECTION REOUEST: 503) HAS. FORWARD COMMENTS REGARDING BUADEN ESTIMATE TO THE RECORDS TEXT CONTINUATION AND REPORTS MANAGEMENT BRANCH IP4)30), U.S. NUCLEAR REGULATORY COMMISSION. WASHINGTON, DC 20555, AND TO 1HE PAPERWORK REDUCTION PROJECT 13)504)104), OFFICE OF MANAGEMENTAND BUDGET, WASHINGTON, DC 20503.

FACILITY NAME II) DOCKET NUMBER lll LER NUMBER )6) PAGE 13)

SPY/FSEOVENTIAL +QQ REVISION YEAR <s'.I'JI NVMBEA ~> NVMSE A 0 4 Washington Nuclear Plant Unit 2 p 6 p p p OF TEXT /// moro 4Pooo ir n//I/ror/ Iroo oddioooo/HRC %%drm 36643/ (17)

Plant Conditions Plant Node 1 (RUN)

Power Level -12K Event Descri tion At approximately 1030 hours0.0119 days <br />0.286 hours <br />0.0017 weeks <br />3.91915e-4 months <br /> on September 30, 1991 plant personnel discovered that the primary containment airlock door seal leak rate test had not been performed within the allowable surveillance interval. WNP-2 was starting up from Cold Shutdown (Node 4) conditions after an extended outage. The actual startup began on September 26, 1991 at 1636 hours0.0189 days <br />0.454 hours <br />0.00271 weeks <br />6.22498e-4 months <br /> when the Node Switch was placed in the Startup/Hot Standby position and control rods were withdrawn.

Technical Specification 4.6,1.3.b requires that the a'irlock door seals be tested "within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> following each closing, except when the airlock is being used for multiple entries, then at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />..." and is applicable in Nodes 1, 2 and 3. Since the plant was taken from Node 4 directly to Node 2 during this startup as normal for a startup from refueling, the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> interval commenced when Node 2 was entered. The allowable 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> expi red at 1636 hours0.0189 days <br />0.454 hours <br />0.00271 weeks <br />6.22498e-4 months <br /> on September 29, 1991. However, Technical Specification 4.0.2 provides flexibility for surveillance scheduling by permitting Ra maximum allowable extension not to exceed 25$ of the specified surveillance interval." In this case, the 255 provided an additional 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> for performance of the test. The additional 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> expired at 1036 on September 30, 1991. Although the test was begun at 0817 hours0.00946 days <br />0.227 hours <br />0.00135 weeks <br />3.108685e-4 months <br /> on September 30, 1991, it was not completed unti 1 1455 hours0.0168 days <br />0.404 hours <br />0.00241 weeks <br />5.536275e-4 months <br />, a deviation from the Technical Specification requirements.

Immediate Corrective Action The airlock door seal surveillance was successfully completed at 1455 hours0.0168 days <br />0.404 hours <br />0.00241 weeks <br />5.536275e-4 months <br /> on September 30, 1991, restoring the airlock to fully operable status, Further Evaluation and Corrective Action A. Further Evaluation The bases For the WNP-2 Technical Specifications states Afailure to perform a surveillance within the provisions of Specification 4.0.2 is a violation of a Technical'pecification requirement and is, therefore, a reportable event under the requirements of 10 CFR 50.-73(a)(2)(i)(B) because it is a condition prohibited by the plant's Te'chnical Specifications.R 1'his LER is submitted pursuant thereto.

2 ~ There were no structures, systems or components inoperable prior to 'the event which conl:ributed to the event.

NAC F orro 386A 164)9)

NRC FORM 368A US. NUCLEAR REGULATORY COMMISSION (649) APPROVED OMB NO.3150010S EXPIRES: S/30/92 TIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS LICENSEE E NT REPORT ILER) INFORMATION COLLECTION REOUEST: 60.0 HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS TEXT CONTINUATION AND REPORTS MANAGEMENT BRANCH (PJ)30), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO 1HE PAPERWORK REDUCTION PROJECT (31500)04). OFFICE OF MANAGEMENTAND BUDGET, WASHINGTON. DC 20503.

FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (6) PAGE (3)

YEAR gyR SSOUSNTIAL GN REVISION NUMSSR >>> NUMBER Washington Nuclear Plant Unit 2 p s p p p3 97 1 028 0 0 0 3oF TEXT /// moro sPooo /s rer/Ir/ror/ Iroo or/I//r/ooo/HRC Forrrr 36643/ ()7)

3. On expiration of the allowed surveillance time interval (plus 25K) the airlock was technically inoperable. Upon determining that the airlock door seal leak test had not been performed, the Shift Manager logged entry into the Action Statement for the airlock Technical Specification (3/4.6.1.3) at 1045 hours0.0121 days <br />0.29 hours <br />0.00173 weeks <br />3.976225e-4 months <br /> on September 30, 1991. Airlock operability was restored within the action statement 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> time limit and no further immediate action was necessary.

4, The apparent cause, of this event is personnel work practices were less than adequate in that an intended or required verification was not'erformed. The Master Startup Checklist procedure (PPN 3.1.1) specifies that the procedure performer verify that the airlock door seals be tested "within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> following closing [of the airlock door] for establishing primary containment."

This procedure step was signed off with the understanding that the seals would be tested following the completion of required containment entries for inspections, and prior to the expi ration of the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> allowable time period.

Normal administrative methods of tracking required actions for Technical Specification Limiting Condition For Operation or inoperable equipment were not utilized. This resulted in the seal test not being completed within the allowable time period.

B. Further Corrective Action The Master Startup Checklist, PPM 3. 1.1, has been amended to require performance of the airlock door seal tests prior to entry into Node 2.

Previously, the procedure required only a verification that the "Door seals tested within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> following closing...R This change forces performance of the surveillance prior"to entry into Node 2, or logging the equipment as inoperable.

2. Precautions and signoff steps have been added to PPNs 3.1.1, 3.1.2 (Reactor Plant Cold Startup), and 3.1.4 (Minimum Startup Checklist) to reflect the surveillance requirements following closure of the airlock.
3. This LER will be required reading for Operations personnel.

Safet Si nificance This event had no safety significance. Performance of the required airlock door seal leakage test verified that the seals were intact and met the required leakage acceptance criteria. In addition, the test of the entire airlock for leakage, as required by Technical Specification 4.6.1.3.c, was up-to-date. This test provides additional assurance that the airlock was capable of performing it's intended safety function.

NRC Form 366A (6$ 9)

NRC FORM 366A U.S NUCLEAR REGULATORY COMMISSION (649) APPROVED OMB NO. 31500104 EXPIRES: 6/30/92 TIMATED BUADEN PER RESPONSE TO COMPLY WTH THIS LICENSEE E ENT REPORT (LER) INFORMATION COLLECTION REOUESTI 60.0 HAS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS TEXT CONTINUATION AND REPORTS MANAGEMENT BRANCH IP430). U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO 1HE PAPERWORK REDUCTION PROJECT (3150010m), OFF/CE OF MANAGEMENTAND BUDGET, WASHINGTON. DC 20503.

FACILITY NAME (11 DOCKET NUMBER (2) LEA NUMBER (6) PAGE (3)

YEAR SEGUE NTIAL REVISION NUMSSII NUMSSII Washington Nuclear Plant Unit 2 o s o o.o 3 979 l 028 0 0 0 4 OF 0 4 TEXT /// moro S>>oe /n nor/rr/rmd, Iree odd/dor>>/HRC Form 366AB/ (17)

Similar Events LER 87-031 documented one instance of a Technical Specification deviation due to personnel failure to follow established procedural requi rements. In that instance, plant personnel failed to recognize that a surveillance requirement was not met during the performance of a surveillance test and failed to notify the Operations Shift IIIanager'f this condition as required by the procedure.

EIIS Information Text Reference EIIS Reference System ~tom onent Containment Airlock AL NRC Form 366A (649)

Retrieved from "https://kanterella.com/w/index.php?title=ML17286B125&oldid=2430844"