ML20046C547

LER 93-018-00:on 930707,discovered Remote Position Indication Verification Test for SI Sys Accumulator Vent & Header Valves Had Not Been Performed in 2 Yrs Due to Change to IST plan.W/930806 Ltr

ML20046C547
Person / Time
Site:	South Texas
Issue date:	08/06/1993
From:	Cloninger T, Pinzon J HOUSTON LIGHTING & POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-93-018, LER-93-18, ST-HL-AE-4531, NUDOCS 9308110126
Download: ML20046C547 (6)

Text

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The Light c o mp a n yS uth Texas Project Electric Generating Station P. O. Box 289 Wadsworth, Texas 77483 Houston Lighting & Power August 6, 1993 ST-HL-AE-4531 File No.: G26 10CFR50.73 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 '

South Texas Project Unit 1

-Docket No. STN 50-498 Licensee Event Report 93-018 Remote Position Indication Verification Tests on Safety Injection System Accumulator Valves not Performed in Accordance with Technical Soecification 4.0.5 Pursuant ' to 10CFR50.73, Houston Lighting & Power (HL&P) submits the attached Unit 1 Licensee Event Report 93-018 for not performing ASME Boiler and Pressure Vessel Code Section XI remote  !

position indication verification tests on Safety Injection System Accumulator Valves as required by Technical Specification 4.0.5.

This event did not have an adverse effect on the health and safety of the public.

If you should have any questions on this matt please  !

contact Mr. J. M. Pinzon at (512) 972-8027 or me at ( 72-8787.

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. H. C n Vice P eside ,

Nucl- r neering DNB/pa. -l

Attachment:

LER 93-018 (South Texas,'Un )

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100050

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LER-93\L93018RO.U1 Project Manager on Behalf of the Participants in the South Texas Project /,! '

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9308110126 930806 ro t/ i PDR ADOCK 05000498 Ik S PDR .

~ Houston Lighting & Power Company File No.: G26 South Texas Project Electric Generating Station Page 2 c:

Regional Administrator, Region IV Rufus S. Scott Nuclear Regulatory Commission Associate General Counsel 611 Ryan Plaza Drive, Suite 400 Houston Lighting & Power Company Arlington, TX 76011 P. O. Box 61867 Houston, TX 77208 Lawrence E. Kokajko Project Manager Institute of Nuclear Power U.S. Nuclear Regulatory. Commission Operations - Records Center Washington, DC 20555 13H15 700 Galleria Parkway Atlanta, GA 30339-5957 David Loveless Senior Resident Inspector c/o U. S. Nuclear Regulatory Dr. Joseph M. Hendrie

• Commission 50 Bellport Lane P. O. Box 910 Bellport, NY 11713 Bay City, TX 77414 D. K. Lacker J. R. Newman, Esquire Bureau of Radiation Control Newman & Holtzinger, P.C., STE 1000 Texas Department of Health 1615 L Street, N.W. 1100 West 49th Street Washington, DC 20036 Austin, TX 78756-3189 D. E. Ward /T. M. Puckett U.S. Nuclear Regulatory Comm.

Central Power and Light Company Attn: Document Control Desk P. O. Box 2121 ' Washington, D.C. 20555 Corpus Christi, TX 78403 J. C. Lanier/M. B. Lee City of Austin Electric Utility Department '

721 Barton Springs Road Austin, TX- 78704 K. J. Fiedler/M. T. Hardt City Public Service P. O. Box 1771 San Antonio, TX 78296 LER-93\L93018RO.01

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U.S. NUCLEAR REGAATORT COWilSSION APPROWED BY Dee No. 3150-0104 lNRC F(cM 366 LXPIRES 5/31/95 j (5-02)

ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH

" 8 "8 LICENBEE EVENT REPORT (LER) $4,3"'"a"AIIU" p ggu SRbRDIN BURDEN ES I TE b 1 THE INFORMATION AND RECORDS MANAGEMENT BRANCH (MMBS 7714), U.S. NUCLEAR REGULATORY COMMIS$10N, (See reverse for required tuber of digits / characters for each block) WASHINGTON, DC 20555-0001, AND TO THE PAPERWORK REDUCTION PROJECT (3150 0104), OFFICE OF MANAGEMENT AND BUDGET, WASHlWGTON, DC 20503.

FACILITY MAME (1) DOCKET NLseER (2) PAGE (3)

South Texas Unit 1 05000 498 1 OF 4 TITLE (4) Remote Position Indication Verification Tests on Safety Injection System Accumulator Valves not Performed in Accordance with Technical Specification 4.0.5 l EVENT DATE (5) LER IEmeER (6) RFPORT DATE (7) OTHER FACILITIES INVOLVED (8) l SE N AL RE FACILITY NAME DOCKET NUMBER  ;

MONTH DAY YEAR YEAR MONTH DAY YEAR STP Unit 2 05000 499 l FAC HY NAME CKET 07 07 93 93 --

018 -- 00 08 06 93 OS OPERATING g TH 3 WORT IS MANIMM MSUANT TO M RNIRNNM OF 10 CFR i: W ck one or more) U M C DE (9) 20.402(b) 20.405(c) 50.73(a)(2)(iv) 73.71(b)

POWER * ' ' '

0 20.405(a)(1)(ii) 50.36(c)(2) 50.73(a)(2)(vil)

LEVEL (10) OTHER  !

20.405(a)(1)(iii) X 50.73(a)(2)(1) 50.73(a)(2)(vill)(A) (SPecify in Abstract ow 20.405(a)(1)(iv) 50.73(a)(2)(ii) 50.73(a)(2)(vill)(B) 20.405(a)(1)(v) 50.73(a)(2)( f i l) 50.73(a)(2)(x) NRC Form 366A)

LICFNSEE CONTACT FOR THIS LER (12)

NAME TELEPHONE NUMBER (Include Area Code)

Jairo Pinzon - Senior Engineer (512) 972-8027 COMPLFTE ONE LINF FOR EACH COMPONENT FAILURF DESCRIBFD IN THIS RFPORT (13)

" COMPONENT MANUFACTURER CAUSE SYSTEM COMPONENT MANUFACTURER CAUSE SYSTEM p g To DS SUPPLEMENTAL REPORT EXPECTED (14) EXPECTED MONTH DAY YEAR YES SUBMISSION 11 0 (If yes, conplete EXPECTED SUBMISSION DATE). X DATE (15)

ASSTRACT (Limit to 1400 spaces, i.e., approximately 15 single spaced typewritten lines) (16)

On July 7, 1993, Unit 1 was in Mode 5 at 105'F and 85 psig and Unit 2 was

, defueled in a refueling outage. It was discovered that Technical Specification 4.0.5 had not been met because the Remote Position Indication (RPI) verification test for the Safety Injection (SI) System accumulator vent valves PV-3928, PV-3929, and PV-3930, and accumulator header vent valves HV-899 and HCV-900 had not been performed within the two year period required by Section XI of the ASME Boiler and Pressure Vessel Code. The valves had been added to the Inservice Test (IST) Plans, but permanent test procedures had not been issued for RPI verification. The cause of this event was that changes to the IST Plan were not being reflected in associated documents such as test procedures. Corrective actions for this event include performing RPI verification tests on the affected valves, reviewing the IST Plan and test procedures that implement the IST Plan to ensure that Section XI requirements are satisfied, and conveying standards and expectations to appropriate personnel concerning the implementation of requirements in plant documents.

CRC FORM 366 (5-92)

LER-93\L93018RD.U1

NRC FDP.M 366A U.S. NUCLEAR REGULATORY COIMIS$10N APPROWED BY oms No. 3150-0104 (5 93) EXPIRES 5/31/95 ESTIMAVED BURDEN PER RESPONSE TO COMPLY tjlTN VHIS

- INFORMATION COLLECTION REQUEST: 50.0 NRS.

~ "*" '

LICENSEE EVENT REPORT (LER) N"STEAND M RE D "kA c M NT BRINCH M TEXT CONTINUATION 7714), U.S. WUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555-0001 AND TO THE PAPERWORK REDUCTION PROJECT (31S0-0104), OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.

FACIL ITY NAME (1) DOCKET ORMRfR (2) LER plMBER (69 PAT (3)

YEAR SEQUENTIAL REVISION South Texas, Unit 1 05000 498 2 OF 4 93 -- 018 -- 00 TEXT (If more sosee is reaufred, use additional copies of NRC Form 366A) (17)

DESCRIPTION OF EVENT On July 7, 1993, Unit 1 was in Mode 5 at 105'F and 85 psig and Unit 2 was defueled in a refueling outage. It was discovered that Technical Specification 4.0.5 had not been met because the Remote Position Indication (RPI) verification test for the Safety Injection (SI) System accumulator vent valves PV-3928, PV-3929, and PV-3930, and accumulator header vent valves HV-899 and HCV-900 had not been performed within the ,

required two year period. The valves had been added to the Inservice Test (IST) Plans, but test procedures had not been issued.

In April 1989, the Nuclear Regulatory Commission (NRC) issued Generic Letter (GNL) 89-04, " Guidance on Developing Acceptable Inservice Testing Programs". The objective of GNL 89-04 was to provide guidance to utilities in the creation and implementation of IST programs. Attachment 1 of GNL 89-04 described program scopes and listed examples of valves that were frequently erroneously omitted from IST programs. This list included accumulator motor operated isolation valves and accumulator vent valves.

The contents of GNL 89-04 conflicted with an earlier HL&P decision that the accumulator vent valves PV-3928, PV-3929, and PV-3930 and the accumulator header vent valves HV-899 and HCV-900 were not required to be tested in accordance with Section XI of ASME Boiler and Pressure Vessel Code. Following telephone conferences concerning this issue with the NRC, HL&P took actions to test and include the valves in the IST program.

Unit i valves were stroke time tested and the RPI verified on June 11, 1990, under a temporary surveillance procedure. The Unit 2 valves were stroke time tested on November 19, 1990, but the RPI were not verified due to the accumulators being depressurized while in Mode 5. The temporary procedure was replaced with permanent procedures, but the permanent procedures did not include biennial verification of the RPI.

In June, 1993, during the semi-annual audit performed by the Authorized Nuclear Inservice Inspector Supervisor, biennial tests could not be'found for the RPI on the accumulator vent valves PV-3928, PV-3929, and PV-3930, and the accumulator header vent valves HV-899 and HCV-900. Lack of tests for the RPI was investigated by HL&P and on July 6, 1993, HL&P determined that Technical Specification 4.0.5 was not being met.

,CAUSE OF EVENT J

The cause of this event was that changes to the IST Plans were not being tracked to ensure that all required changes to associated documents, such j as test procedures, were completed.

LER-93\L93018RO.U1

MRC FORM 366A U.S. IUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104

,(5-92) EXPIRES 5/31/95  ;

ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THl$

INFORMATION COLLECTION REQUEST: 50.0 HRS.

LICENBEE EVENT REPORT (LER) NT[AND RE MAIAcEMENTBR NCH M TEXT CONTINUATION 7714), u.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555 0001 AND TO THE PAPERWORC ,

REDUCTION PROJECT (31$0-0104), OFFICE OF )

MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.

FACIllTY WApf (1) DOCKET NLMBER (2) LER WlMBER (65 PAT (3)

YEAR SEQUENTIAL REVISION South Texas, Unit 1 05000 498 3 OF 4 93 -- 018 -- 00 TEXT (If more space is reautred, use additional cooles of NRC Form 366A_1 (17) l ANALYSIS OF EVENT Accumulator vent valves PV-3928, PV-3929, PV-3930, and accumulator header vent valves HV-899 and HCV-900 were added to the Unit 1 and Unit 2 Inservice Testing Plans on August 23, 1990 and December 20, 1990, respectively. Based on these additions, the valves were to be tested in accordance with Technical Specification 4.0.5, which includes RPI verification tests as required by ASME Section XI Article IWV-3000, at 3 least once every 2 years to verify that valve operation is accurately indicated. Technical Specification 3.5.1 requires that the SI accumulators be operable in Modes 1, 2, and 3. Because the RPI on valves PV-3928, PV-3929, PV-3930, HV-899, and HCV-900 were not tested within the required interval, the accumulators were technically inoperable and the associated action statement for Technical Specification 3.5.1 was not met.

This condition is reportable pursuant to 10CFR50.73 (a) (2) (1) (B) .

The accumulators are pressure vessels partially filled with borated water and pressurized with nitrogen gas. Each accumulator is isolated during normal operation from the Reactor Coolant System (RCS) by check valves.

Should the RCS pressure fall below the accumulator pressure, the check valves open and borated water is forced into the RCS by the high pressure nitrogen gas.

During refueling operations, the accumulators are isolated from the RCS by isolation valves. Redundant isolation valve position indication is provided at the Main control Panel and the Auxiliary Shutdown Panel.

Accumulator vent and accumulator header vent valve (PV-3928, PV-3929, PV-3930, HV-899, and HCV-900) position indication is provided at the Main Control Panel.

Plant operators manipulate valves PV-3928, PV-3929, PV-3930, HV-899, and HCV-900 periodically. The accumulators are vented and recharged during refueling outages using the SI Accumulators procedure. This procedure is also used during power operation to repressurize the accumulators after nitrogen leakage. The SI System Initial Lineup procedure is performed after each refueling to ensure SI valves are in the proper position. The periodic operation of these valves provides confidence that Control Room indication corresponded to actual valve position, hence, this event did not affect the health and safety of the public.

The NRC Operations Center was notified on July 7, 1993 at 1246 hours0.0144 days <br />0.346 hours <br />0.00206 weeks <br />4.74103e-4 months <br />.

This event was reported as required by the provisions of Plant Operating Licenses NPF-76 and NPF-80, (2G), Section 2.c(2).

LER-93\L93018RO.U1

unc Foo 366A U.s. mucttAa mE(RJLATORY COMMISSION APP 90WED BY DIS NO. 3150-0106 (5-92) EXPIRES 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH TCIS

- INFORMATION- COLLECTION REQUEST: 50.0 HRS.

FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE LICENSEE EVENT REPORT (LER) INFORMAil0N AND RECORDS MANAGEMENT BRANCH (MNBB 7714), U.S. NUCLEAR REGULATORY COMMISSION, TEXT CONTINUATION WASHINGTON, DC 20555-0001 AND TO THE PAPERWORK REDUCTION PROJECT (31$0-0104), OFFICE OF MANAGEMENT AND BUDGET. WASHINGTON. DC 20503.

FACILITY NAE (1) DOCKET IsAmER (2) LER NLDIBER (69 PAGF (3)

SEQUENTIAL REVISION ,

YEAR M BER M BER South Texas, Unit 1 05000 498 4 OF 4 93 -- 018 -- 00 TEXT (If more spa.ge is reouired, use additional cooles of NRC Form 366A) (17)

CORRECTIVE ACTIONS

1. HL&P will verify proper operation of the RPI for valves PV-3928, PV-3929, PV-3930, HV-899, and HCV-900 in accordance with ASME Section XI prior to startup from the current outages in Units 1 and 2.

2. HL&P reviewed the tests specified in the IST Plans for valves (full >

stroke, RPI, partial stroke, local leak rate test, check valve full flow) to verify that there are corresponding procedures designated to  ;

perform the required testing. No other tests were determined not to ,

have test procedures.

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3. HL&P will convey standards and expectations to appropriate personnel by September 27, 1993, regarding the implementation of requirements in ,

plant documents.

L ADDITIONAL INFORMATION There have been 2 previous LERs submitted to the NRC regarding missed ASME Section XI surveillances. These LERs are as follows:

Unit 1 LER 89-022 " Technical Specification Violation due to the Failure to Perform a Required Post Maintenance Test."

Unit 2 LER 93-004 " Technical Specification Violation due to the Failure to Perform a Surveillance Required by ASME Section XI 3 Codes."

The causes of LERs89-022 and 93-004 were sufficiently different from the '

cause of this event such that the corrective actions described in LERs89-022 and 93-004 would not have been expected to preclude this event.

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