ML20029E558

LER 94-005-00:on 940415,dicovered That Several Valves Were Not Being Tested Per Requirements of ASME Section Xi.Caused by Inappropriate Action.Corrective Action:Pump & Valve Team Has Been Formed to Perform in Depth reviews.W/940513 Ltr

ML20029E558
Person / Time
Site:	Waterford
Issue date:	05/13/1994
From:	Houghtaling J, Packer D ENTERGY OPERATIONS, INC.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-94-005-01, LER-94-5-1, W3F1-94-0050, W3F1-94-50, NUDOCS 9405190094
Download: ML20029E558 (6)

Text

. . . _ - . . . .

t Entegy saierar on ><iaa PO Box B iac-Operations xcioca.t^ 700cc Tel 004-464 3120 D.F. Packer i

Geowa:Mmaur nam onem j W*ertyd 3 W3F1-94-0050 i

A4.05 PR May 13, 1994 U.S. Nuclear Regulatory Commission

. Attn: Document Control Desk Washington, D.C. 20555 i

Subject:

Waterford 3 SES 1

Docket No. 50-382 License No. NPF-38 Reporting of Licensee Event Report i

Gentlemen: ,

I Attached is Licensee Event Report Number LER-94-005-00 for Waterford Steam Electric' Station Unit 3. This Licensee Event Report is submitted in accordance with 10CFR50.73(a)(2)(i). ,

l )

Very truly yours, iQ D.F. Packer General Manager Plant Operations l DFP/GCS/tjs Attachment 2 cc: L.J. Callan, NRC Region IV 4

G.L. Florreich J.T. Wheelock - INP0 Records Center R.B. McGehee N.S. Reynolds NRC Resident Inspectors Office (WADM526)

$ ry - -

Administrator - LRPD 9405190094 940513

.p 0 AvdU PDR S

ADOCK 05000382 l

PDR

NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED 3Y OMB NO. 3150-0104 (5 *2) l .

EXPIRES 5/31/95 l

l ESTlMATE D BU51 DEN PER DE SPONSE TO COMPty #TH Tre

' LICENSEE EVENT REPORT (LER) M.!?S$u'5sCnEZ TSUJiaO ,Nrst @l:"C AND RECORDS MANAGEME NT eMNcs !MNgg 7714L U S NUCiE AR HL SULATOm COMM LEN. A A.cnNLiON, DC 2 %$ 0001, AND 70 THE PAPEHWDRK REDUCh0N PROJECT (3150 0104t. OF FiCE OF '

I (See reverse for reouired number of digits / characters for each block) MANAGEMENT AND BUDGET, WASHING'ON, DC 2203 '

f ACIUTY NALAE (t) DOCF ET NUMBE R (2)

Waterford Steam Electric Station Unit 3 05000 PAGE 10F p)5 Tif LE (4) ,

Valves in the Inservice Test Plan - Pump and Valve, not Tested '

, EVENT DATE (5) LER NUMBER (6i REPORT NUMBER (7) OTHER FACILITIES INVOLVED (8)

MONT H DAY YEAR YEAR MONTH DAY YEAR f AQUIY NAME DOCFIT NUMHC H

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04 15 94 94 - 005 00 05 13 94 n/a 05000 OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR 6: (Check one or more) (11)

MODE (9) 5 l 20 402(b) 20.405(c) 50.73(a>(2)(iv) 73 71(bi l POWER ' 20 405(a)(1)(i) 50.36(c)(1) 5013(a)(2)(v) 73.71(c) ,

LEVEL (10) 0 20 405(a)U)(n) 50.36(c)(2) 50 73(a)(2)(vii) OTHER l 20.405(a)(1)(ni) A 50.73sa )(2)(il 50 73(a)(2)(vui)(A) W'W '" At*ac' 20.405ta)(1)(tv) 50.73(a)(2)(ii) 50.73(a)(2)(vui)(B) r, A[

20.405(a)(1)(v) 5013(a)(2)(ni) 50.73(a)(2)(x)

LICENSEE CONTACT FOR THIS LER (12)

h. A Mt i TELEPHONE NuYULH pr.clude A'ea Gocel John Houghtaling, Mgr. Tech. Services 504/464-3131 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)

CAUSE SYSTE M COMPONENT MANUFACTURER CAUSE SYSTEM COMOONENT MANUFACTURER y SUPPLEMENTAL REPORT EXPECTED (14) EXPECTED WJN'" uv vt Aa f es, compie?e EXPECTED SUBMtSS:ON CATE No X

ABSTRACT (Limit to 1400 spaces. i.e , approximately 15 single-spaced typewritten knes) (16)

On April 15, 1994, a Shift Technical Advisor discovered that several valves were not being tested per the requirements of ASME section XI. Specifically valves SI-6011, SI-6012, CVR-401A and CVR-401B remote position indicators were not being observed at least once every two years to verify that valve position matched remote indication. Also identified was that power operated valves SBV-ll3A, SBV-1138, SBV-114A and SBV-ll4B were not being timed in their closed stroke direction. Technical Specification 4.0.5(a) requires that inservice testing of ASME Code Class 1, 2, and 3 pumps and valves be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code.

The root cause of this event is inappropriate action resulting in a failure to properly incorporate IST Plmn requirements into the appropriate operating procedures during initial IST Plan implementation. A Pump & Valve Review Team has been established to perform an in depth review of the Plan and the associated implementing documents. This event did not compromise the health and safety of the public.

NRC F ORM 366 (5 90

REQUIRED NUMBER OF DIGITS / CHARACTERS

• FOR EACH BLOCK BLOCK NUMBER OF TIRE NUMBER DIGITS / CHARACTERS 1 UP TO 46 FACILITY NAME  !

2 DOCKET NUMBER 3 IN ADDITIO TO 05000 3 VARIES PAGE NUMBER 4 UP TO 76 TITLE 5 ^

2 PER BLOCK 7 TOTAL 6 LER NUMBER 3 FOR SEQUENTIAL NUMBER 2 FOR REVISION NUMBER 7 ^

2 PER BLOCK UP TO 18 - FACILITY NAME OTHE FACILUIES MOND 8 TOTAL - DOCKET NUMBER 3 IN ADDITION TO 05000 9 1 OPERATING MODE 10 3 POWER LEVEL I' REQUIREMENTS OF 10 CFR CHECK BOX THAT APPLIES 0 50 FOR NME 12 LICENSEE CONTACT 14 FOR TELEPHONE l CAUSE VARIES I 2 FOR SYSTEM 13 4 FOR COMPONENT EACH COMPONENT FAILURE 4 FOR MANUFACTURER NPRDS VARIES l 14 CHECK BOX THAT APPLIES

"^ j 15 2 PER BLOCK I l l

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l REQUIRED NUMBER OF DIGITS / CHARACTERS FOR EACH BLOCK I NUMBER OF BLOCK I

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l 4 UP TO 76 TITLE 5 NT DATE 2 PER BLOCK 7 TOT AL 2 M YEAR LER NUMBER 6

3 FOR SEQUENTIAL NUMBER  !

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^ REPORT DATE 7

P B UP TO 18 -- FACILITY NAME l 8 ' '

8 TOTAL - DOCKET NUMBER 3 IN ADDITION TO 05000  ;

9 1 OPERATING MODE i

10 3 POWER LEVEL

" CHECK BOX THAT APPLIES EQUIREMENTS OF 10 UR UP TO 50 FOR NAME 12 LICENSEE CONTACT 14 FOR TELEPHONE CAUSE VAR!ES 2 FOR SYSTEM 13 4 FOR COMPONENT EACH COMPONENT FAILURE 4 FOR MANUFACTURER NPRDS VARIES

'# ECE D CHECK BOX THAT APPLIES 15 EXPECTED SUBMISSION DATE 2 PER BLOCK

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NRC FORM 366A U.S. NUCLEAR REGULATORY COMMisslON APPROVED BY OMB NO. 3150-0104 l Iset ,

EXPIRES $/31/95 l fN O CT R  ; O HRS A LICENSEE EVENT REPORT (LER) COMusN1s ReaARosa sanots tsrum To THc iNrORMues TEXT CONTINUATION E"$a" 8c S7%$$'5*178d'S'A$$"$$

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Waterford Steam Electric Station Unit 3 05000 382 2 OF 5 94 - 005 -

00 l r ~ ~. ,,-. . n,.a .. . ._,.., -= F - n o r, REPORTABLE OCCURRENCE j On April 15, 1994, a Shift Technical Advisor discovered that valves were )

not being tested per the requirements of ASME section XI. Specifically valves SI-6011 (EIIS Identifier BP-FSV), SI-6012 (EIIS Identifier BP-FSV),

CVR-401A (EIIS Identifier BF-FSV) and CVR-401B (EIIS Identifier BF-FSV) remote position indicators were not being observed at least once every two years to verify that their valve operators were accurately indicated as per the requirements of ASME Section XI Article IWV-3300. Also power operated valves SBV-113A (EIIS Identifier VC-20), SBV-1138 (EIIS Identifier VC-20),

SBV-114A (EIIS Identifier VC-20) and SBV-114B (EIIS Identifier VC-20) were not being timed in their closed stroke direction as per the requirements of ASME Section XI Article IWV-3413(b). Technical Specification 4.0.5(a) requires that inservice testing of ASME Code Class 1, 2, and 3 pumps and

, valves be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code. The failure to test these valves per A3ME section XI requirements is a violation of Waterford 3 Technical Specification 4.0.5(a) which requires testing of ASME code class 1, 2, and 3 pumps and valves. Per 10CFR50.73(a)(2)(i)(B) any operation or condition prohibited by the plant's Technical Specification is reportable as an LER.

INITIAL CONDITIONS Plant Power 0%

Plant Operating Mode: Mode 5; Cold Shutdcwn Procedures Being Performed Specific to This Event: None Technical Specification LC0's in Effect Specific to this Event: None Major Equipment Out of Service Specific to this Event: None NRO FORM 366A (5 94

b 3 FORM 366A U.S. NUCLEAR REGULATORY COMMISSIOII APPROVEo BY OMB NO. 3150-0104 sn EXPIRES 5/31/95 ESTIMATED BUROEN PER RESPONSE TO COMPLY WITH TH:s LICENSEE EVENT REPORT (LER) E " E s"REf E E nif fs*'u d b E M fv" %2l TEXT CONTINUATION g u"5 $***v"v's i E *$11"r$"E**'$'A N "$$^$

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F ACILITY NAME (1) DOCH ET NUMBER (2) LER NUMBER 14) PAGE (3)

SEQvE TA REv;SiON I YUR NUVSER NUMBER Waterford Steam Electric Station Unit 3 05000 382 3 oF 5 94 - 005 -

00 1 EXT pt more space is revea, use edwtionai comes o! kRC Form 3664 (17) l EVENT SEQUENCE l

On April 15, 1994 a Shift Technical Advisor (STA) discovered during a review of the Waterford 3 Pump and Valve Inservice Test Plan (IST) that valves SI-60ll, SI-6012, CVR-401A, CVR-401B, SBV-113A, SBV-1138, SBV-ll4A and SBV-ll48 were in the IST plan as required but their testing requirements were only partially addressed in the plant's implementing procedures.

I Valves SI-6011, SI-6012, CVR-401A and CVR-401B have been in the IST Plan since revision 1 dated April 4, 1984. The ASME Section XI requirement to verify that valve position indicators are accurately indicating has never been proceduralized and consequently never verified. Valves SBV-Il3A, SBV-113B, SBV-114A and SBV-1148 have been in the IST Plan since revision 0 dated August 16, 1982. The ASME Section XI requirement to time these valves  ;

in the closed stroke direction has also never been proceduralized and consequently never verified. l l

l 1

CAUSAL FACTORS The root cause of this event is inappropriate action resulting in a failure  !

I to properly incorporate IST Plan requirements into the appropriate -

operating procedures during initial IST Plan implementation. Although past corrective actions associated with the IST problems appeared to be adequate, it is believed that due to the accumulation of unrelated concerns identified with the Plan, a full review of it and its implementing documents is warranted.

l l

NRC FORM 366A (S 921 I

X J

NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSloN APPROVED BY OMB No. 3150-0104 (s e2) EXPlRES 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THis

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SEQUENTIAL REVIS60N YEAR Waterford Steam Electric Station Unit 3 05000 382 3 oF 5 94 - 005 00 Tw vi n. ,o.c. , n,.a. . .-- ..n. a wc r.<,, xm o n EVENT SE0VENCE On April 15, 1994 a Shift Technical Advisor (STA) discovered during a review of the Waterford 3 Pump and Valve Inservice Test Plan (IST) that valves SI-60ll, SI-601'2, CVR-401 A, CVR-401B, SBV-ll?A, SBV-ll3B, SBV-ll4A and SBV-ll4B were in the IST plan as required but their testing requirements were only partially addressed in the plant's implementing procedures.

Valves SI-60ll, SI-6012, CVR-401A and CVR-4018 have been in the IST Plan since revision 1 dated April 4, 1984. The ASME Section XI requirement to verify that valve position indicators are accurately indicating has never

, been proceduralized and consequently never verified. Valves SBV-113A, SBV-Il3B, SBV-Il4A and SBV-ll4B have been in the IST Plan since revision 0 l dated August 16, 1982. The ASME Section XI requirement to time these valves l in the closed stroke direction has also never been proceduralized and consequently never verified.

CAUSAL FACTORS

The root cause of this event is inappropriate action resulting in a failure to properly incorporate IST Plan requirements into the appropriate operating procedures during initial IST Plan implementation. Although past corrective actions associated with the IST problems appeared to be adequate, it is believed that due to the accumulation of unrelated concerns identified with the Plan, a full review of it and its implementing documents is warranted.

NRC FORM 366A {5 92)

1 .

J NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 (s 02 ,

EXPIRES 5/31/95

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DOCKET NUMBER (2) LER NUMBER (s) PAGE (3)

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SEQVENTaAL REVISION mR ""**'" ""**'"

Waterford Steam Electric Station Unit 3 05000 382 i op 5 94 - 005 -

00 TEXT (it inore space es reewes, use ea:nonal copies of NAC Form J66Aj (17)

IMMEDIATE CORRECTIVE MEASURES i

j lhe required IST testing of valves SI-6011, SI-6012, CVR-401A, and CVR-4018 was performed on April 17, 1994 per work authorization WA 01123100. A l

2 procedure change for OP-903-043 was initiated to t%e the closure of valves SBV-113A, SBV-113B, SBV-114A and SBV-114B per the requirement of the IST plan.

l ACTIONS TO PREVENT RECURREi4CE j

I A Pump & Valve Review Team has been established to perform an in depth review of the IST Plan to ensure all current IST requirements are procedurally implemented.

A periodic test method will be implemented for valves SI-6011, SI-6012, CVR-401A and CVR-401B to verify valve position indications.

SAFETY SIGNIFICANCE 4

The purpose of the inservice testing of the valves identified in this LER i was to determine the amount of valve degradation. Upon the discovery that

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valves SI-6011, SI-6012, CVR-401A, and CVR-401B position indicators were

not being verified they were immediately tested and proven to be operational.

Although plant procedures have no time requirement associated with stroking these valves closed, valves SBV-113A, SBV-1138, SBV-114A, and SBV-114B were stroked in both the open and close position per plant procedure OP-903-043 NRC FOAV 366A (5 92)

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Waterford Steam Electric Station Unit 3 382 5 op 5 05000  !

l 94 -

005 - 00 l Tw w -. w.c. a r.w.s . .xw.a.e.. .r uaC m ass e n

" Shield Building Ventilation System Operability Check" . As such, the

! operability of the valves was demonstrated.

i Based on the above, this event did not compromise the health and safety of the general public or plant personnel.  ;

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SIMILAR EVENTS 2

j Problems with the IST Plan were identified in LER 89-014 and LER 90-010. In LER 89-014 the Auxiliary Component Cooling Water-valves (EIIS Identifier l BI-V) ACC-116A and ACC-116B were not included in the Pump & Valve IST g

program. The root cause of this event was misinterpretation of the ASME

, Section XI definition of ' active ' valves. Because ACC-116A and ACC-1168 i

were judged to be ' passive' in relation to the ASME XI definition ,- they i were never included in the IST program. In LER 90-010 feedwater check l valves, FW-181A and FW-181B, and both Emergency Diesel Generator fuel oil transfer pumps had been excluded from the Pump & Valve IST program. The

! root cause of this event was an inadequate review of ASME Section XI IST l requirements during the development of the Pump & Valve IST Plan program.

Although these events are related to the events described in this LER, the I

significant difference is that for the events of this LER there were no ,

k discrepancies identified with the Pump and Valve IST plan but with the

! procedural implementation of the plan.

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d NRC FORM 366A $ 92)

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