ML18153B986

LER 89-013-00:on 891017,tests Determined That Required Lift Setpoints of 2485 +/- 1% Exceeded on All Tested Valves. Caused by Incorrect Setting of Valve Setpoints.Settings Adjusted to Proper Setpoint & tolerance.W/891114 Ltr

ML18153B986
Person / Time
Site:	Surry
Issue date:	11/14/1989
From:	Kansler M VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
89-050, 89-50, LER-89-013-02, LER-89-13-2, NUDOCS 8911280260
Download: ML18153B986 (7)

Text

I A~CELEJRATEJeDISTRIBUTION DEMCWSTRATION SYSTEM 1--~: REGULATORY.INFORMATION DISTRIBUTION SYSTEM (RIOS)

ACCESSION NBR: 85H128*0260 DOC. DATE: 89/11/14 NOTARIZED: NO DOCKET #

FACIL:50-28:L Surry Power station, Unit 2, Virginia Electric & Powe 05000281 AUTH.NAME AUTHOR AFFILIATION KANSLER,M.R.. Virginia Power (Virginia Electric & Power Co.)

RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

LER 89-013-00:on 891017,pressurizer safety valve setpoints outside of Tech Spec allowable limits.

W/8 ltr.

DISTRIBUTION CODE: IE22T COPIES RECEIVED: LTR j_ E~~L _( SIZE: _ _ _

TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.

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NOTEp:lcy NMSS/FCAF/PM. 05000281 I RECIPIENT COPIES RECIPIENT COPIES* i ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2**2 LA 1 1 PD2-2 PD 1 1. I BUCICLEY,B 1 1 I

INTERNAL: ACRS MICHELSON 1 1 ACRS MOELLER 2 2 ACRS WYLIE 1 1 AEOD/DOA 1 1 ._(

AEOI:)/DSP/TPAB 1* 1 AEOD/ROAB/DSP 2 2 DEDRO 1 1 NRR/DEST/ESB 8D 1 1 NRR/DEST/ICSB 7 1 1 NRR/DEST/MEB 9H 1 1 NRR/DEST/MTB 9H 1 1 NRR/DEST/PSB 8D 1 1 NRR/DEST/RSB 8E *l 1 NRR/DEST/SGB 80 1 1 NRR/DLPQ/HFB 10 1 1 NRR/DLPQ/PEB 10 1 1 NRR/DOEA/EAB 11 1 1 NRR/DREPfPB 10 2 2 NUDOCS-ABSTRACT RES/DSIR/EIB 1

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EXTERNAL: EG&G WILLIAMS,S 4 4 L ST LOBBY WARD 1 1 LPDR 1 1 NRC PDR 1 1 NSIC MAYS,G 1 1 NSIC MURPHY,G.A 1 1 R NUDOCS FULL TXT 1 1 I

NOTES: 1 1 D

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D NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, s

ROOM Pl-37 (EXT. 20079) TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

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• 39

e VIRGINIA ELECTRIC AND POWER COMPANY Surry Power Station P.O. Box 315 Surry, Virginia 23883_

November 14, 1989 U.S *. Nuc:lear Regulatory.Commission Serial No.: 89-050 Document Control Desk Docket No.: 50-281 Washington, D.C. 20555 License No.: DPR-37 Gentlemen:

Pursuant to Surry Power Station Technical Specifications, Virginia Electric and PQWer- Company hereby submits the following Licensee Event Report for Unit 2.

REPORT NUMBER 89-013-00 This report has been reviewed by the Station Nuclear Safety and Operating Committee and will be reviewed by Safety Evaluation and Control.

Very truly yours, Enclosure cc: Regional Administrator SuitE! 2900 101 ~[arietta Street, NW AtlaDLta, Georgia 30323 oq11~oo~~O 891114

~bR ~~b~(~ 05~)0281 S PDC

POW 28-06-01 NAC Form 3N U.S. NUCLEAR REGULATORY COMMISSION 19-831 APPROVED 0MB NO. 3160-0104 LICENSEE EVENT REPORT (LER) EXPIRES: 11/31/1111 FACILITY NAME 111 DOCKET NUMBER 121 I PAGE 131 Surry Power Station, Unit 2 o Is Io Io Io 1 218 11 I 1 loFI o Is 141 TITLE Pressurizer Safety Valve Set points Outside of Technical Specification Allowable Limits Due to Establishing Setpoints Without Loop ' Seal EVENT DATE 161 LER NUMBER (61 REPORT DATE 171 OTHER FACILITl':S :NVOLVED (Bl MONTH DAY YEAR EAR SE~~~~~~AL )) ~~~~~ MONTH DAY YEAR FACI LITV NAMES DOCKET NUMBERISI OPERATING Tl<IIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: /Chock on, or moro of th* fo110.,,,in11) 1111 MODE 1111 N IO I OIO -- 20.C02(b)

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                                                                      ----                                                                                                                             IHlow *nd in T*1'r. NRC Form i11ttlli~=

20.-(1)(1)1ili) li0.73(1112111) l50.73(1112llviill(AI 366A) 20.40511111111*1 ----X l50.7311112lliil 150.73(1112llvlli11BI . 20.40lll1l111M ---- l50.731oll2)(111) . li0.73(111211*1 LICENSEE CONTACT FOR THIS LER (121 NAME TELEPHONE NUMBER AREA CODE H. R. Kansler, Station :Manager COMPLETE ONE LINE FOR EACI-\ COMPONENT FAILURE DESCRIBED IN THIS REPORT 1131 MANUFAC* REPORTABLEitt:::r::::)}f{fff:t MANUFAC* CAUSE SYSTEM COMPONENT TO NPRDS 1*:*:*::>:*:*:*:*:-:-:*:*:*:-:-:*:*:*:*:':':*:*:*:;: CAUSE SYSTEM COMPONENT TURER TURER 1:,:=:=:,:;:=:,:;:=:,:::::,:,:=:,:::::::::,:=:::'::,::: I I I I I I I I I I I I I I I I I 1 I I I I I I I I I I t-L-..,------*-----* __s_u_PP_L_E_M_E_NT_A_L_R_E_PO_R_T_E_x_PE-,CT_ED_11_*_1- - - - - - - - - - - * - - - - ~ rii I EXPECTED SUBMISSiOI,

                                                                                                                                                                                      ~,..~::: *::1 YES ,'., ,.n, n,mpi,ro EXl'ECTEV SUBMISSION DATE)                                                     NO On October 12, 1989, following a shutdown of Unit 2 due to a leaking safety valve, notification was received from Westinghouse that a potential problem exists with the method used to test and set the pressurizer safety valves. As found tests of the safety valve lift setpoints were performed by Westinghouse on October 17, 1989.

Results of these tests, using a water loop seal, determined that required lift sefpoints of 2485 + 1 percent had been exceeded on all three! valves. This condition is-contrary to Technical Specification

3. 1. A*. 3 ( 4) . It was determined that the pr*essurizer code safety valve setpoints were not within the allowable tolerance because the valve setpoints had been established with steam rather than the lower temperature water loop seal condition. This method of testing and establishing lift setpoints had previously been considered industry practice. All three safety valve lift settings were tested with water loop seal configurations and adjusted to the proper setpoint and tolerance. The methodology for setting and testing safety valve lift setpoints will be reviewed in coordination with ongoing industry efforts.

NRC FORM 366A U.S. NUCLEAR REGULATORY COMMI (6-89) APPROVEO 0MB NO. 3150-0104 EXPIRES: 4/30/92 ESTIMATEO BURDEN PER RESPONSE TO COMPLY WTH THIS LICENSEE EVENT REPORT (LER) INFORMATION COLLECTION REQUEST: 50.0 HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS TEXT CONTINUATION AND REPORTS MANAGEMENT BRANCH (P-530). U.S. NUCLEAR REGULATORY COMMISSION. WASHINGTON. DC 20555, AND TO THE PAPERWORK REDUCTION PROJECT (3160-0104), OFFICE OF MANAGEMENT AND BUDGET. WASHINGTON, DC 20503. FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER. (Bl PAGE 13) Surry Power Station, Unit 2 TEXT (H mom -ctJ ill ,equ/19'1, u&1 *ddltionel NRC Fonn RA 'aJ 117) 1.0 Description of the Event On October 12, 1989, Unit 2*was shut down to repair a leaking pressurizer safety valve (EIIS-RV). Prior to the shutdown, operators observed parameters indicating that the "B" pressurizer safety valve was le*aking into the Pressurizer Relief Tank (PRT) (EIIS-TK). In addition, Reactor Coolant System (RCS) (EIIS-AB) leak rates were observed to increase, although they remained within the allowable specifications. Concurrent with this event, the Westinghouse site representative notified Virginia Power of a generic issue regarding safety valve testing methodology and allowable setpoint tolerances. Westinghouse had identified that the lift setpoint for the safety valves may change by more than one percent from the original setpoint when they are subjected to temperature conditions different from those used to establi~h the setpoint. ~he Surry pressurizer code safeties had previously been tested with steam on their seats, but are installed with a water loop seal at a temperature lower than test conditions.* Therefore, it was decided to test all three valves to establish the lift setpoint under the loop seal conditions. As found tests performed on October 17, 1989, using a water loop seal, determined that the required safety valve lift setpoint of 2485 psig + 1 percent had been exceeded. The following is a list-of the "as found"

                                                ~etpriints and percentage above 2485 psig.

2-RC-SV-2551A 2566 psig +3.3 percent 2559 psig +3.0 percent 2-RC-SV-2551B 2564 psig +3.2 percent 2564 psig +3.2 percent 2-RC-SV-2551C 2580 psig +3.8 percent 2581 psig +3.9 percent This condition* is contrary to the requirements of Technical Specification 3.1.A.3(4). NRC Form 366A (6-89)

NRC FORM 366A U.S. NUCLEAR REGULATORY COMMI (6-89) APPROVED 0MB NO. 3150-0104 EXPIRES: 4/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS LICENSEE EVENT REPORT (LER) INFORMATION COLLECTION REQUEST: 50.0 HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS TEXT CONTINUATION AND REPORTS MANAGEMENT BRANCH (P-530), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104), OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503. FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (6) PA ( I

SEQUENTIAL ,

,;,;.;,;, REVISION YEAR

                                                                                                                   ,..,.,,.,. NUMBER   :,*,*,;,*, NUMBER Burry Power Station, Unit 2 o Is Io I o I o 12 I 8 I 1   81 9 -             o11 I   3 -           8  I 9 o I3   OF     oI 5 TEXT '" mom apace i* fWIUimd, O'SII *ddhio,,., NRC Form 366A'a) (17) 2.0         Safety Consequences and Implications The pressurizer safety valves are provided to prevent an overpressure condition in the Reactor Coolant System (RCS).              The accident scenarios that cause significant pressure transients (i.e. Locked Reactor Coolant Pump Rotor, Loss of Feedwater, Feedwater Line Break, Rod Ejection, and Loss of Load) were evaluated.

This evaluation showed that peak RCS pressure remains below the 110 percent design overpressure limit, for safety valve lift setpoints as high as 5.4 percent above the nominal setpoint of 2485 psig. Testing revealed that the setpoint change resulting from a water loop seal was within 5.4 percent of the nominal setpoint for all three valves tested. Therefore, the health and safety of the public were not affected. 3.0 Cause It was determined that the pressurizer code safety valves setpoints were not within the allowable tolerance because the valve setpoints had been established with steam rather than the lower temperature water loop seal condition. This method of testing and establishing lift setpoints had pieviously been considered industry practice. 4.0 Immediate Corrective Action(s) None required. 5.0 Additional Corrective Action(s) All three safety valves lift settings were tested with a water loop seal configuration and adjusted to the proper setpoint and tolerance under the same configuration. Since the Unit 1 safety valves' setpoints were established under the same test conditions as the Unit 2 safety valves, the potential *exists for Unit 1 safety valves to exceed the+ 1 percent Technical NRC Form 366A (6-89)

NRC FORM 366A U.S. NUCLEAR REGULATORY COMMI

• 16-891 APPROVED 0MB NO. 3150-0104 EXPIRES: 4/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS LICENSEE EVENT REPORT ILER) INFORMATION COLLECTION REQUEST: 50.0 HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS TEXT CONTINUATION AND REPORTS MANAGEMENT BRANCH (P-530), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104), OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.

FACILITY NAME Ill DOCKET NUMBER (21 LER NUMBER 161 PAGf (3) Surry Power Station, Unit 2 o 1s Io I O I O 12 I 811 8 I 9 _ '01113 _ o I o o 14 OF o 15 TEXT (ff m<N9 apace i8 ,squired, u.* *ddltioMI NRC Form BA'a) 1171 Specifications tolerance. Discretionary enforcement was requested and received from the Nuclear Regulatory Cdmmission (NRC) to allow time to resolve the issue and continue Unit 1 operation. As an interim ,measure, the NRC was provided with a Justification for Continued Operation of Unit 1, which included compensatory measures to be taken to avoid conditions which could be impacted by relaxed safety valve lift setpoint tolerances. These compensatory actions require that the reactor trip by turbine trip circuitry must remain operable and that one pressurizer pressure operated relief valve (PORV) must remairi operable. 6.0 Action(s) Taken to Prevent Recurrence The methodology for setting and testing safety valve lift setpoints will be reviewed in coordination with ongoing industry efforts. 7.0 Similar Events Subsequent to this event, one of the primary relief valves lifted prematurely during primary plant pressure testing. The premature lifting of the relief valve is being addressed in a separate LER. U2 LER 86-015: Unit 2 pressurizer safety valves were determined to be outside the allowable Technical Specification limits. It was determined that this was due to minor valve damage/wear 'found during the surveillance test and the failure to compen.sate for operating temperature during the previous surveillance tests. Following this event, testing condftions were modified to more accurately simulate actual operating conditions. However, as described above, this modification has since* been determined to yield inaccurate results. Ul LER 88-016: Unit 1 pressurizer safety valves were determined to be outside the allowable T.S. limits. Results of an engineering evaluation performed to determine the cause of this event was inconclusive. A Technical Specification change has been submitted to NRC Form 366A 16-891

NRC F.ORM 366A U.S. NUCLEAR REGULATORY COMM!

• 16-89) APPROVED 0MB NO. 3150-0104 EXPIRES: 4/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS

                                       *LICENSEE EVENT REPORT (LERI                                        INFORMATION COLLECTION REQUEST: 50.0 HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS TEXT CONTINUATION                                           AND REPORTS MANAGEMENT BRANCH (P-530), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO l'HE PAPERWORK REDUCTION PROJECT (3150-0104). OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.

FACILITY NAME (1) DOCKET NUMBER 12) LER NUMBER IBI PAGE 13)

                                                                                                                 *:::::::::: SEQUENTIAL ::::::::::* REVISION YEAR   :;:::::::::   NUMBER   :::::::::: NUMBER Surry Power Station, Unit 2 O I5 I O I O I O I 218 I 1 8 19     -          0 I 11 3 -             0 IO    OI .5 OF O    I5 TEXT (ff mo,e fJ/>>ctJ ia ,wquired, ua1 *dditkJMI NRC Form .RA 'a) 117) the        Nuclear Regulatory Commission to revise the allowable "as found" pressurizer safety lift setpoints to + 3 percent.                This was requested due to the inherent difficulty throughout the nuclear industry in maintaining the lift setpoints -Within+ 1 percent.

a.a Manufacturer/Model Number(s) Crosby/HB-8&-BP-E. NRC Form 366A 16-891}}