ML20045D860

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LER 93-006-00:on 930525,two HPSI Discharge Check Valves Declared Inoperable Due to Inadequate Surveillance Testing. Caused by Personnel Error.Test Written & Performed to Demonstrate Valve operability.W/930621 Ltr
ML20045D860
Person / Time
Site: Millstone Dominion icon.png
Issue date: 06/21/1993
From: Scace S, Young J
NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-93-006-02, LER-93-6-2, MP-93-493, NUDOCS 9306300144
Download: ML20045D860 (3)


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  • I NORTHEAST UTILITIES o=ere o*a saen s"eet Beran connecticut 5, NifaNaYsNnu*stII.$r$cc [aA>Y P.O. BOX 270 EfoE*'aIt O'E'I***EErEEE%oany

' HARTFORD. CONNECTICUT 06141.0270

_L ' T2 Nortreast ru.iear Ene gy comr.a,y (203)S65-5000 June 21, 1993 MP-93-493 Re: 10CFR50.73(a)(2)(i) .

U.S. Nuclear Regulatory Commission Document Control Desk Washington. D.C. 20555 _

Reference:

Facility Operating License No. NPF-49 Docket No. 50-423 Licensee E' cent Repo,t 93-006-00 Gentlemen:

This letter forwards Licensee Evem Report 93-006-00 required to be submitted within thirty (30) days pursuant to 10CFR50.73(a)(2)(i).

Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY

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Ste' er) 'Scace Vice President - Millstone Station SES/JSY:bjo

Attachment:

LER 93-006-00 cc: T. T. Martin, Region I Administrator P. D. Swetland. Senior Resident inspector, Millstone Unit Nos.1, 2 and 3

. V. L. Rooney, NRC Project Manager, Millstone Unit No. 3 290029 lN'$$$Ansjaa / pI m t v

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NRC Form 366 U.S NUCLEAR REGULATOR Y' COMMISSION APPROVED OMB NO. 3150-0104 I (6-@k EXP;RES: 4/30/92 Estimated burden per response to comply with tNs .j

+ - mtormabon cohection roguest: 50 0 hrs - Forward 4 comments regarding buroen estimate to tne Recordt - i

, LICENSEE EVENT REPORT (LER) and Reports Manageme,t Branch tP-53cL U.S Nuclear - i Regulatory Commiss+on WasNngton, DC 20555, and to tre Paperwork Recuction Prenect (3950-0104). Office of '

Management and Buoget Washmgton. ()C 20503 r

F ACIUTY NAME (1) DOMT NUWR 21 WV '3' Millstone Nuclear Power Station Unit 3 01 sl 0l 010141213 1lOFl 0l 2 TITLE l4; Inadequate Surveillance Testing of High Pressure Safety Injection Check Vahes EVENT DATE (Si LFR NUMBFR 16t REPOAT DATE (71 l OTHER F ACluTES INVOLVED (81

" F ACLITY NAMES MONTr DAY VEAR YEAA MONTH CAY YE/R

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0 5 25 9 3 9 3 0l0l6 00 0 6 2l1 9l 3 0l 5l 0l 0l 0l l l OPE A ATING THIS REPORT l$ BEING SUBMITTED PURSUANT TO THE REQUiAEMENTS OF 10 CFR O (Check one or more of the foltowing)(11)  : l 20 402:0) 20 402(c) 50.73(a )(2) Uv) 73.71 (c) powgR 20 405ta)(1)fi) 50.36(cI lt ) 50.73(a)(2)(v) 73 71(c) t? 1l0l0 ao 405(a)(1)o'l So.36<ct(2) 50.73. Ia)(2t ty4)

OTHER (Scecify m Atistrac* twow and m

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Sv.73(a)(2)(viid ( A) Text, NRC Form 366A) ,

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UCENSEE CONTACT FOR TMS LER (121 g NAME TELEPHONE NU ABER 5 AREA CODE '

Jeffrey S. Young, Engineer, Ext. 6442 2f0l3 -1 l 4 l 7 l -l 1 [ 7 l 9 l 1 COMPLETE ONE LINF FOR EACH COMPONENT F AILURE DESCR!BFD IN THIS REPORT (13)

CAUSE SYSTEM COMDONENT k CAUSE SYSTEU COMPONEN' '

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SUPPL EMENTAL REPORT EXPECTED tidi MONTH DAY YEAR SUBMISSiCN . r YES Uf yes comrsete EXPECTED SUBMISSION DATE) NO DA E D51 g l l ABSTRACT (Umit to '400 spaces, s e., soproomate<y foteen singie-space typewrmen hnest D6)

On May 25.1493 at 1730 with the plant in Mode I at 100rc, two High Pressure Safety injection (SlH) I discharge check valves were declared inoperable due to inadequate testing. The in Service Test (IST) Manual specified a quarterly panial stroke test of the two valves. The discovery was rnade during a review of the SIH

. system by the Reliability Centered Maintenance group.

The apparent root cause of the event was personnel error. A planned relief request to delete the requirement to test tnese valves was never submined but the surveillance procedure was changed based on a verbal commitment.

The immediate corrective action was to declare the two valves inoperable. A test was written and performed to demonstrate operability of the valves within the time allowed by surveillance requirement 4.0.3. This test will be performed on a quarterl3 basis as required.

As action to present recurrence, the need to verify that surveillance procedure changes reflect actual chances to the IST manual is being reinforced with the Operations and Engineenng Departments. Additionally, an audit of the IST rnanual will be performed to ensure that all testing requirements are incorporated in surseillance i procedures.

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i NRC Form 366 I (6-Mi l

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l NP9 Form 3t 6 A u$ NUCLEAR REGULATORY CoMM:SSON APPRDVED oMB No. 31$0-0104 1989; E XPiRE S : 4/30/92 Estimata f buroen per reroonse to compiy wan tnis .) '

' " ' m** c "scw est SM ms. Fors 3rd LICENSEE EVENT REPORT (LER) Com"ments regarding b# con estimate to the Records TEXT CONTINUATION and Reports Manage nent eranen m-s30; u s Nuciear Regwater/ Cornmission. Wasnington. DC 20555 and to 1 the Pa:wwork Recuao's Pro;oct (3150-0104). Office of ,

Management and Buaget, Washmaton. DC 20503 l LF:4 NuvmF A m PAGE (3)  ;

F AcOT v NAME (1) DoOKET UuMBER t2) ~

vEn smuoa. mvm l NLNBER NU W Nhlistone Nuclear Power Stauon CDU 3 0l 5l 0l 0l 0l4 l2 j a 9l3 0 l 0l 6 0l0 0l 2 OF 0l2 TE XT pf more spata. Is eeowrec use acamona' NRO Form 366 A 3) (17)

L Descrmtion of Event On Niay 25.1993 at 1730 with the plant in 51od: 1 at 1005 power (2250 psia and 587 degrees Fahrenheit), two SlH discharge check valves on the "B" train (3SlH*V110 and 3SlH'V112) were declared inoperable due to inadequate surveillance testmg. The IST manual directed a quarterly partial stroke test of these valves but the surve illance procedure had been modified in 1986 to delete this test.

TL dncovery was made dunng a review of the SlH system by the Reliabihty Centered 51amtenance group.

A review of the surveillance procedure in 1989 did not detect the omission due to an inadvertent typographical error m a revision to the IST manual This error had left the quarterly partial stroke test requuement for the two valves off a table summanzing testing requirements. Therefore, it appeared that the survet!!ance procedure was correct when the review was performed.

11. Qtuse of Esent The root cause of ths es ent was personnel error m that a verbal commitment to submit a rehef request was used as a basis to change the surveillance procedure in 1956.

Ill. Analvsn of Event This event is bemg reported m accordance with 10CFR50.73(a)(2)(i) as a condition prohibited by Technical Spectheations. The IST $1anual required a quarterly partial stroke test of these two valves, but this testmg was not performed.

This event has m!mmal safety sienificance. In the past, the valves have operated properly during 18 month full stroke testt The valves operated properly when partially stroked. In addnion, the opposite train check valves do not require quarterly testing.

IV, Conecure Action The immediate corrective action was to dec!are the two valves inoperable and enter the appropriate Limning Condition for Operations (LCO) Action Statement. A test was wntien and performed to demonstrate operabihty of the two valves within the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> time hmit of surveillance requirement 4.0.3.

This test will be performed on a quarterly basis as required.

As action to prevent recurrence, the need to ensure that surveillance procedures are changed only after the IST N1anual test requirements have been changed is bemg remforced to the Operations and Engmeeting Departments. Additionally, an audit of the IST 51anual will be performed to ensure that all testmg requirements are incorporated in sur eillance procedures.

V. Additional In form:nion 1

No other Licensee Esent Repons (LERs) have been submitted where IST hianual test requirements were not incorporated in suneillance procedures.

f.IIS codes Entem Cernnonent liigh Pressure Safety Valve - V Iniection System

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