ML18153A469

LER 94-002-00:on 940204,main Steam Safety Valves Found Out of Tolerance.Caused by Minor Setpoint Drift.Valves Inspected & overhauled.W/960228 Ltr

ML18153A469
Person / Time
Site:	Surry
Issue date:	02/28/1994
From:	Kansler M VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
94-127, LER-94-002-03, LER-94-2-3, NUDOCS 9606190156
Download: ML18153A469 (5)

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• 10CFR50.73 Vll'lfima Elecuic and Power Company Surry Pow Staffon P. O.Bos815 .

SU1TY, Vlrpda 23883 Febro.ary,28, 1994 U.S. Nuclear Regulatory Commission ENTERED Serial No.: 9'-127 Document Control Desk SPS:VAS Washington, D. C. 20555 RECEfVEO SY Docket No.: 50-280*

License No.: DPR-32 MAR 04 1994

Dear Si:

rs:

Pursuant to Surry Power Station Technic~ Spe~ltions, Virginia Electric and Power Company hereby s*ubmits the following Licensee Event Report applicable to Surry Power Station Unit 1. * * . ** .

This report has been reviewed by the Station Nuclear Safety and Operating Coinm.ittee and will be for~*ardsd to the Management Safety Review Committee for its review.

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. Kansler tation Manager Enclosure cc: Regional Administrator

• 10.1 Marietta Street, "NW1 Suite 2900 Atlanta; Georgia 30323

-M. W. Branch NRC Senior Resident Inspector Surry Power Station 9606190156 940228 ~£1.L PDR ADOCK 05000280 S PDH 'I,

\ I NRC FORM 366 U.$. NUCLEAR FIEGULATORV COMMISSION e

• APPROVED BY DMB NO. 3150-G104 *

(9*921*

- .EXPIRES 5/31/95 :.

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• FC~AAr, Ij LICENSEE EVENT REPORT {LEA) COMMiN'l'S lli&GARC4NO SUAOl!:N E~"'A~ T:) THE *NFORMATf,::lN I ANO RECORDS MANAGEMENT Bl'IANCH ~aa '714l, LJ.S .. ,;ucLEAA .

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• ABSTRACT' (Limit to 1400 sp-.C.e5, ,.e., approx!mately 15 sirigle-si,il!.eed typewritten lines)* (16) II I

II,. On February 4, S, and 7, 1994*. with Unit, at cold.shutdown and Unit 2 at 100°-' power.

I setpolnt testing on fifteen Unit 1 Main Steam Code Safety ValYes revealed that the lift settings of three valves*(1*MS-SV*105B, 102B and 104A) were outside the+/- 3% *As Foundu range that is allowed by the Technical Specifications (TS). The three valves exhibited ntt settings ranging from 3.3% to 4. 7% above their nominal value. The affected valves were inspected and overhauled by the manufacturer. They were adjusted to Within

,. :t , ~/o ol the required "As Lett* setpoints. The valves were tested to verify that three consecutive lifts were within tolerance Witnout setpoint adjustment. *An engineering evaluation ot the accident analysis was pertonned which verified that the safeties would I have performed t'1elr safety function. Therefore, the health and safety of the public were not affected. This event ls reportable pursuant to ioCFRS0.73(a)(2)(1)(B) tor conditions prohibited by -TS 3.6.A, 3.6.B.3 and 3.6.D. ..

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{5*821 LICENSEE EVENT REPORT (LER)

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II Surry Power StatioD:. Uni~ 1 05000 - 280 94* _ 002 _ 00 2 OF 3 i

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1 .0 DESCRIPTION OF THE EVl!NJ I

On February 4, 5, ar.d 7, 1994. with Unit 1 at cold shutdown and !Jnlt 2 at 1009/a power.

I setpoint testing on fifteen Unit 1 Main*Steam Code Safety Valves (MSSV) (EllS..SB, RV}

revealed that t!'1e lift settings of three valves (1-MS-SV-105B, 102B and 104A) were outside the .,: 3% "As Found" range that Is allowed by ihe Technical Specifications (TS)

Table 3.6*1 A. The three valves el(hibited lift settings ranging from 3.3% to 4.7°/o above their nominal setpoint value. This event is reportable pursuant to 10CFR50. 73(a)(2)(i}(B) for conditions prohibited by TS 3.6,A, 3.6.. B.3 and 3.6.D.. *

2. o s1GHIEICANT SAFETY CQNSEOYENC!$ ANQ *MPLICAJIQti&

I Under plant accldent conditions, the MSSVs remove plant sensible heat and core decay heat and provide overpressure protection. for the secondary side of the Steam Generators [EliS-AB, SG} and main steam system COff1X)nents. An engineering I evaluation was performed to determine the effects of high safety valve lift setpoints on the accident analysis. The evaluation concluded that for the Umiting overpressure event (complete loss of load without reactor trip) peak reactor coolant system temperature and i,ii-pressure would not be sii;:nificantly affected, and the peak secondary side pressure would remain,well within the design limits .of the secondary piping. Therefore. the as i found condition would not r.esult in any safety* limits being exceeded. Because the . Ii1' safeties would have performed their safety function, the health and safety of the public

,I II" were not affected. ,

• i 3.0 CAUSE Of THE EVENT II

• 1 The MSSVs experienced minor setpoint drift which can be expected under normal operating condit!ons. Although the specific cause of this setpoint dritt is not known. its occurrence is well documented in the industry and is not considered to be abnormal. 1!

4, O IMMEDIATE CORRECTIVE AC:TION(I) l ij The affected valves were inspected and overhauled by the vendor, Dresser Industries, at

.the Wyle Testing Lab site in Huntsville, Alabama. They were adjusted to within .::. 1% of I',I the required "As Left setpoints.

• s. o_ AQQIIIQNAL CQRRECTIYE ACTION($)

I!

After the setpoint adjustment, the valves were tested to verify three consecutive lifts were within the +/- 1% *As Left" tolerance as specified by TS 3.6. Based upon evaluations of Ii' the test data, no additional testing or maintenance will be recommended. r*I j:

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(5,821

-U.S. NUCLEAR REGULATORY COMMISSION e

AP.PROVED EIY OMS NO. 3150-0104 EXPIRES 5/31/95 ES'71.:...'!'!0 IIURO!N l'li:~ ll!fSPOHS! ~ COMl'LY.

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LICENSEE EVENT REPORT (LEA) llll'ORMJ\'l'ION =-~ON l'll!CUEST: !11.Q Hl'IS.

COMM!il'lfS ~G,t,II01Ml lilUROl!N liST1MATE T:I T1'1E fORYJAI;:;

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TEXT CONTINUATION ANO Pl;COR:JS W.NAGEMe~.rr &MNc,,, <!IINBS n1J1, u.s. r.~c:.;;:.q

-1':EGU..A'l"ORV CCYMl$S*ON. WASHilliuTON, DC :i!lmiS-0('!~,. ANC TO

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r;,,e PAPECIWOl'll< ,'!EOi./CTIOI\/ PROJECT. (~1110-C1C4); OFF"iCE Oi' I!

M,UIIAG!:MENT ANO 8'.IOGET, WAS"'INGTO!'., o,; 205,03. . I I

FACJl,fTY NAME (I! OOCl<iT NUMBER (21 Li:R NlJM~ER (II D*ClE (lJ Ji

.Surr, Power Stati~n, Unit 1 05000. _ 280 II 94 - 002 00 3 OF 3 II

6. o ACTIONS IP PREVENT RECURRENCE None.

7. o SIMILAR EVENIS Unit 1 LER 90-011-00, Main Steam Safety Valves OUt of Tolerance Due to Minor Setpoint Drift Unit 2 LEA 91 *002-00, Main Steam Safety Valves OUt of Tolerance Due to Minor Setpoint Drift 8.0 ADPIIJP~AL INEQBMATION The MSSV testing is govemed by a program that utilizes in situ testing as well as removal and shipment of the valves to the vendor tor inspection and overhaul. The MSSVs are tested in situ for two refueling outages and sent to the vendors every third refueling outage. This testing verifies that the lift settings mi9t TS as stated in Table 3.6-1A for the MSSVs. Previous in situ. "As Found" settings show smaller variations due to setpoint drift I and the MAS Founct* values were within TS allowable rimits. This method of testing I 11 eliminates potential vanations attributable to <:i1fferences in the test enV1rcnment.

. !I Eguipmem lntocmauon~ 1*,I Dresser 6" inlet, 1O" outlet safety relief valve, Type 3707RA*RT21 (1-MS-SV*105B) jl Dresser 6" iniet, 10k outlet safety relief valve, Type 3707RA-RT21 (1-MS-SV-1028) . iI Dresser 6" inlet, 10~ outlet smaty relief valve, Type 3707RA-RT21 (1-MS-SV-104A) .

• I I

11 11 11 I

I

e LE R S1.94~002-00 VERIFICATION OF ACCURAQI

1. DR S-94-0305, S-94-0306, S-94-0318

2. Technical Speeification 3.6 .

3. Memo from J. O. Erb to J. I. Kelly dated February 11,. 1994

4. UFSAR 10.3.1.2

5. NAPS LEA S1-93*002-00

6. LER S2*91-002-00

7. LER S1*90-011-00

8. 1-MPT-0427-02 .

9. 1-MPT-0421.01 and completed Attachment 2

10. Memo from L.A. Hilbert-Semmes to Viki Shifflett dated February 22, 1994

11. Main Steam System Design Basis Document (i4.2.3)

COMMITMENTS <CTS)

• I ACTION PLAN *tLARS}

None.