ML20044G430

LER 93-009-00:on 930426,Tech Spec Violation Occurred Due to Use of Inappropriate Ref Value Data for RHR Pump Inservice Test.Surveillance Procedures Revised to Include Appropriate Ref values.W/930525 Ltr

ML20044G430
Person / Time
Site:	South Texas
Issue date:	05/25/1993
From:	Pinzon J, Rosen S HOUSTON LIGHTING & POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-93-009-01, LER-93-9-1, ST-HL-AE-4464, NUDOCS 9306030078
Download: ML20044G430 (6)

Text

v The Light company "'

Houston Lighting & Power

• • • • 5 'I' O*" *'** "Ib'** " * *****'7 May 25, 1993 ST-HL-AE-4464 File No.: G26 10CFR50.73 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 South Texas Project Unit 2 Docket No. STN 50-499 Licensee Event Report 93-009 Technical Specification Violation Due to the Use of Inaooropriate Reference Value Data for a RHR Puno Inservice Test Pursuant to 10CFR50.73, Houston Lighting & Power (HL&P) submits the attached Unit 2 Licensee Event Report 93-009 regarding a Technical Specification violation due to the use of inappropriate reference value data .for a Residual Heat Removal (RHR) pump Inservice Test. This event'did not have an adverse effect on the health and safety of the public.

If you should have any questions on this matter, please contact Mr. J. M. Pinzon at (512) 972-8027 or me at (512) 972-7138.

S. JL. Rosen Vice President, Nuclear Engineering JMP/sr

Attachment:

LER 93-009 (South Texas, Unit 2) 020031 ,

Proiers Manarer on Behalf of the Participants in the South Texas Project /t 9306030079 930525 PDR ADOCK 05000499

/

./

(7 l S PDR

( .

Houston l'ighting & Power Company ST-HL-AE-4464 South Texas Project Electric Generating Station File No.: G26 Page 2 .

c: I Regional Administrator, Region IV Rufus S. Scott Nuclear Regulatory Commission Associate General Codnsel 611 Ryan Plaza Drive, Suite 400 Houston Lighting & Power Company Arlington, TX 76011 P. O. Box 61867 i Houston, TX 77208  :

L. E. Kokajko '

Project Manager U.S. Nuclear Regulatory Commission Institute of Nuclear Power Washington, DC 20555 Operations - Records Center ,

1100 Circle 75 Parkway  ;

J. I. Tapia Atlanta, GA 30339-3064 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. i 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 i

I l

J l

LER\L93-0 W.U2 ]

i i

NRC FORQ 366 U.S. CELEAR REOJLAT(ClY C0pmISSION APPROVED B7 OMB CD. 3150-0204 (5-92) ,

EXPIRES 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH

' LL " 8 "8 LICENSEE EVENT REPORT (LER) Eag3I"'Uj"EN S fEGA DI(G R EN ST TE b THE INFORMATION AND RECORDS MANAGEMENT BRANCH (MNBB 7714), U.S. NUCLEAR REGULATORY COMMISSION, (See reverse for recpired ruber of digits / characters for each block) WASHINGTON, DC 20555-0001, AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104), OFFICE OF MANAGEMENT AND BUDCET, WASHINGTON. DC 20503.

FACitlTr uME (1) South Texas, Unit 2 DOCKET N!MBER (2) PAGE (3) 05000 499 1 OF 4 TITLE (4) Technical Specification Violation due to the Use of Inappropriate Reference Value i

Data for a RHR Pump Inservice Test EVENT DATE (5) LER N!MRER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED (8)

DAY YEAR MONTH DAY YEAR MONTH YEAR NUMBER NUMBER 05000 04 26 93 93 009 00 05 25 93 O O OPE RATING THIS REPORT IS SUBMITTED PLRSLIANT TO THE REQUIREMENTS OF 10 CTR 6: (Check one or more) (11)

MODE (9) y/A 20.402(b) 20.405(c) 50.73(a)(2)(iv) 73.71(b)

POWER 20.405(a)(1)(1) 50.36(c)(1) 50.73(a)(2)(v) 73.71(c)

LEVEL (10) 0 20.405(a)(1)(ii) 50.36(c)(2) 50.73(a)(2)(vii) OTHER 20.405(a)(1)(iii) X 50.73(a)(2)(i) 50.73(a)(2)(vi i i )( A) (Specify in ac w 20.405(a)(1)(iv) 50.73(a)(2)(ii) 50. 73(a)(2)(vi i i )(B) 20.405(a)(1)(v) 50.73(a)(2)( t i i ) 50.73(a)(2)(x) NRC Form 366A)

LICTNSEE CONTACT FOR THIS LER (17)

NAME TELEPHONE WUMBER (include Area Code)

( Jairo Pinzon -

Senior Engineer (512) 972 - 8027 COMPLETE ONE LINE FOR EACH COMPONENT F AltlRE DESCRIBED IN THIS REPORT (13)

E CAUSE SYSTEM COMPONENT MANUFACTURER ,

CAUSE SYSTEM COMPONENT MANUFACTURER 0

SUPPLEMENTAL REPORT EXPECTED (14) EXPECTED MONTH DAY YEAR YES(If yes, conplete EXPECTED SUBMISSION DATE). X NO E (15 ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced Typewritten lines) (16)

On April 26, 1993, Unit 2 was in a refueling outage in No Mode. Plant personnel completed a reportability review which determined that Technical l

Specification 3.5.6 and 4.0.5 were violated due to the use of inappropriate

! reference values for differential pressure during surveillance testing of the Residual Heat Removal (RHR) pump 2A. The cause of this event was less than adequate attention to detail by the preparer and the subsequent reviewers during preparation, review and approval of a field change to a procedure. A revision to the surveillance procedure incorporated the inappropriate reference values for differential pressure. Corrective actions include revising the surveillance procedure to incorporate the appropriate reference values and providing lessons learned from this event to appropriate personnel. Additionally, a review of a sample of other completed field changes will be performed to ensure this is an isolated incident.

h4C fDkM To6 (542)

IrtC FORM 366A U.S. O CLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 i (5-92) EXPIRES 5/31/95 ESTIMSTED BU2 DEN PE3 RESPONSE TO COMPLV WITH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS.

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

FACILITY NAME (1) DOCKET NLMBER (2) LFR NUMBER (61 PAGE (3)

YEAR SEQUENTIAL REVISION South Texas, Unit 2 "* " "**"

05000 499 2 OF 4 93 009 00 TEXT fif more space is reavired, use atJitional copies of NRC Form 366A_J (17)

DESCRIPTION OF EVENT:

On April 26, 1993, Unit 2 was in a refueling outage in No Mode. Plant personnel completed a reportability review which determined that Technical Specification 3.5.6 and 4.0.5 were violated due to the use of inappropriate reference values for differential pressure during surveillance testing of the Residual Heat Removal (RHR) pump 2A.

On January 29, 1993, Plant Engineering Department personnel generated a Field Change (FC) to the RHR Pump 2A Inservice Test, to add a means to control RHR pressure during inservice testing to prevent a challenge to the relief valves. This FC included a RHR pump 2A data sheet which contained pump Differential Pressure (D/P) values from a February 11, 1989 reference value test. This inappropriately changed the RHR pump 2A D/P reference value test data. The appropriate reference value data should have been from a September 3, 1992 test.

A surveillance test was conducted on February 18, 1993, that obtained as-found pump D/P which was unacceptable per the inappropriate reference value data but was acceptable per the September 3, 1992 reference value data. The test performers were unaware that the data on the RHR pump data sheet was inappropriate and determined that the test was unacceptable. The RHR pump 2A was subsequently declared inoperable.

A second surveillance was performed on February 20, 1993, at 1448 hours0.0168 days <br />0.402 hours <br />0.00239 weeks <br />5.50964e-4 months <br />.

The as-found pump D/P was unacceptable per both the inappropriate reference value data and the September 3, 1992 reference value data. The surveillance was run again following a calibration of the suction side pressure indicator. The as-found pump D/P was determined acceptable per the inappropriate reference value data but was actually unacceptable based on the September 3, 1992 reference value data. RHR pump 2A was returned to service.

A surveillance test on March 21, 1993, obtained results similar to the February 20, 1993 test.

Unit 2 was in Mode 4 on February 20, 1993, and remained in Mode 4 until February 23, 1993 when Mode 3 was entered. Unit 2 was in Mode 3 until March 2, 1993 when the plant started cooling down for a refueling outage.

bc FotM 366A U.S. MUCLEAR C2GutATORY tomISSION APPROVD BY CMB NO. 3150-0104 (5-92) EXPIRES S/31/95

, ]

EST! MATED BURDEN PER RESPCUSE TO COMPLY WITH THis

-

• INFORMATION COLLECTION REQUEST: 50.0 HRS.

FORWARD COMMENTS REGARDING BURDEN ESilMATE TO THE LICENSEE EVENT REPORT (LER) INFORMATION AND RECORDS MANAGEMENT BRANCH (MNBB TEXT CONTINUATION TM4), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555-0001 AND TO THE FAPERWORK REDUCTION PROJECT (31$0-0104), OFFICE OF MANAGENENT AND BUDGET, WASHINGTON, DC 20503.

FACILITY MAME (1) DOCKET NLMBER (2) LFR WlMBER (61 PAGE (3)

YEAR SEQUENTIAL REVISION South Texas, Unit 2 05000 499 3 OF 4 93 009 00 TEXT (if more space is reauired, use aMitional copies of GC Foem 366A) (17)

CAUSE OF EVENT:

The cause of this event was less than adequate attention to detail by the preparer and the subsequent reviewers during preparation, review and approval of the FC. The preparer and reviewers did not verify that a previous FC was incorporated in the subsequent FC. As a result, the reference values from September 3, 1992 were omitted and inappropriately replaced with the February 11, 1989 reference value data. It is the responsibility of the preparer to verify that the FC portion of the page is changed and ensure that all previous FCs are still incorporated including revision bars and FC numbers. This barrier did not prevent this event from occurring. It can not be ascertained how the inappropriate reference values were substituted during the preparation of the FC.

This event was discovered during a review of the RHR 2A pump surveillance data by the System Engineer. The System Engineer wa; trending the as-found pump surveillance data and noticed the adverse trend. Any similar occurrences would also be noticed by the applicable system engineer since trending is performed in accordance with the inservice testing program for pumps. The generic implications of this event are already programmatically monitored by the inservice testing program.

ANALYSIS OF EVENT:

Failure to meet the requirements of the Technical Specifications is reportable pursuant to 10CFR50.73 (a) (2) (i) (B) . Technical Specification 3.5.6 requires three independent RHR loops to be operable in Modes 1, 2, and

3. The surveillance requirements specified in Technical Specification 4.5.6.1 requires each RHR loop to be demonstrated operable per the requirements of Technical Specification 4.0.5. Technical Specification 4.0.5 refers to ASME Section XI subsection IWP-3230(b) which states "if deviations fall within the Required Action Range of Table IWP-3100-2, the pump shall be declared inoperative and not returned to service until the cause of the deviation has been determined and the conditions corrected".

RHR pump 2A was returned to service on February 20, 1993, based on the as-found D/P values which was in the required action range per the September 3, 1992 reference value data. This resulted in a violation of Technical Specification 4.0.5 and 3.5.6.

The inappropriate inservice testing did not impact the function of the RHR 2A pump. There was no significant impact on pump flow. If challenged, the RHR pump 2A would have performed its safety function. No adverse radiological or safety consequences resulted from this event.

BBC FCRM'3f 6A U.S. NUCLEAR REQJLATORY COMISSION APPROVED BY OMB NO. 3150-0104 )

(5-92) EXPIRES $/31/95  ;

ESTIMATED BURDEN PER RESFC; SE TO COMPLY tt!TH THIS l INFORMATION COLLECTION REOUEST: 50.0 HRS.  !

FORWARD COMMENTS REGARDING BURDEN ESilMATE TO THE <

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

FACILITV NAME (1) DOCKET NLMrsER (2) LER NUMBER (61 PACF (3)

YEAR SEQUENTIAL REVlslON South Texas, Unit 2 "" """

05000 499 4 OF 4 93 009 00 TEXT (if more space is reovired. use ed:fitional copies of NRC Form 366A) (17)

CORRECTIVE ACTIONS:

1. A Field Change was issued to correct the current RHR pump 2A Inservice Test procedure and includes changes previously made on all FCs.

2. The lessons learned from this and similar events involving preparation of procedure changes will be provided to appropriate personnel.

Techniques for precluding recurrence will also be provided. This action will be completed by July 9, 1993.

3. A review of a sample of other completed field changes will be performed to ensure that this is an isolated incident. This review will be completed by June 9, 1993.

ADDITIONAL INFORMATION:

During the past two years the following LERs, which were the result of less than adequate procedure reviews, have been submitted to the NhC:

+

Unit 1 LER 92-011 regarding the Reactor Coolant pump undervoltage and underfrequency surveillance not performed completely per Technical Specifications.

Unit 1 LER 92-013 regarding the Containment Spray Channels not being completely verified as required per Technical Specifications.

Unit 1 LER 92-017 regarding Feedwater isolation response time not being correctly tested par Technical Specifications.