05000281/LER-1995-002-02, :on 950210,lift Settings for Two MSSVs & Two Psvs Found to Be Outside as Found Range Allowed by TSs 3.6.A & 3.1.A.3.b.Caused by Setpoint Drift.Safety Valves Repaired & Readjusted

:on 950210,lift Settings for Two MSSVs & Two Psvs Found to Be Outside as Found Range Allowed by TSs 3.6.A & 3.1.A.3.b.Caused by Setpoint Drift.Safety Valves Repaired & Readjusted

ML18153B249
Person / Time
Site:	Surry
Issue date:	03/09/1995
From:	Christian D VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-95-002-02, LER-95-2-2, NUDOCS 9503160192
Download: ML18153B249 (8)

LER-1995-002, on 950210,lift Settings for Two MSSVs & Two Psvs Found to Be Outside as Found Range Allowed by TSs 3.6.A & 3.1.A.3.b.Caused by Setpoint Drift.Safety Valves Repaired & Readjusted

Event date:
Report date:
2811995002R02 - NRC Website

text

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PRIORITY 1 (ACCELERATED RIDS PROCESSING)

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9503160192 DOC.DATE: 95/03/09 NOTARIZED: NO DOCKET#

FACIL:50-281 Surry Power Station, Unit 2, Virginia Electric & Powe 05000281 AUTH.NAME AUTHOR AFFILIATION CHRISTIAN,D.A.

Virginia Power (Virginia Electric & Power Co.)

p RECIP.NAME RECIPIENT AFFILIATION SUBJECT: LER 95-002-00:on 950210,lift settings for two MSSVs & two PSVs found to be outside "as found range" allowed by TSs 3.6.A & 3.1.A.3.b.Caused by setpoint drift.Safety valves repaired & readjusted.W/950309 ltr.

DISTRIBUTION CODE: ;E22T COPIES RECEIVED:LTR _l E~CL _l SIZE:--~'----~~-

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

NOTES:

RECIPIENT COPIES RECIPIENT ID CODE/NAME LTTR ENCL ID CODE/NAME PD2-2 PD 1

1 BUCKLEY,B INTERNAL: ACRS 1

1

~~B AEOD/SPD/RRAB 1

1

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CEN [B) 02 NRR/DE/ECGB 1

1 7DE7EELB NRR/DE/EMEB 1

1 NRR/DISP/PIPB NRR/DOPS/OECB 1

1 NRR/DRCH/HHFB NRR/DRCH/HICB 1

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. NRR/DRCH/HOLB NRR/DRSS/PRPB 2

2 NRR/DSSA/SPLB NRR/DSSA/SRXB 1

1 RES/DSIR/EIB RGN2 FILE 01 1

1 EXTERNAL: L ST LOBBY WARD 1

1

• LITCO. BRYCE, J H NOAC MURPHY,G.A 1

1 NOAC POORE,W.

NRC PDR 1

1 NUDOCS FULL TXT NOTES:

1 1

NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 504-2083 )TO ELII\\U:'.\\.TATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 28 ENCL 28

• 05000281 COPIES LTTR ENCL 1

1 1

1 1

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March 9, 1995 U. S. Nuclear Regulatory Commission

• Document Control Desk Washington, D.C. 20555

Dear Sirs:

Virginia Electric and Power Company Surry Power Station P.O. Box315 Surry, Virginia 23883 10CFRS0.73 Serial No.: 95-137 SPS:JDK Docket No.: 50-281 License No.:DPR-37 Pursuant to Surry Power Station Technical Specifications, Virginia Electric and Power Company hereby submits the following Licensee Event Report applicable to Surry Power Station Unit 2.

REPORT NUMBER 50-281 /95-002-00 This report has been reviewed by the Station Nuclear Safety and Operating Committee and will be forwarded to the Management Safety Review Committee for its review.

Very truly yours, D. A. Christian Station Manager Enclosure cc: Regional Administrator 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 M. W. Branch NRC Senior Resident Inspector Surry Power Station

/(.{;}5 I y-

1.

NRC FORM366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY 0MB NO. 31SCM)104 (5-92)

EXPIRES 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COMPLY wm1 THIS INFORMATION COLLECTION REQUEST: 50.0 HRS. FORWARD LICENSING EVENT REPORT (LER)

COMMENTS REGARDING BURDEN ESTIMATE TO THE INFORMATION AND RECORDS MANAGEMENT BRANCH (MNBB n14), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555-0001, AND TO (See reverse for required number of digits/characters for each block)

THE PAPERWORK REDUCTION PROJECT (3150-0104), OFFICE OF M.ANAGEMENT AND BUDGET, WASHINGTON, DC 20503.

FACILITY NAME (1)

NUMBER (2)

II PAGE(3)

SURRY POWER STATION, Unit 2 05000 - 281

1. OF 6 TITLE (4)

Main Steam & Pressurizer Safetv Valve As Found Lift Settino Out of Tolerance EVENT DATE 5)

LER NUMBER l6 REPORT DATE m OTHER FACILITIES INVOLVED l8l MONTH DAY YEAR YEAR SEQUENTIAL REVISION MONTH DAY YEAR FACILITY NAME DOCKET NUMBER NUMBER NUMBER 05000-02 10 95 95

-- 002 --

00 03 09 95 FACILITY NAME DOCKET NUMBER 05000

• OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR:(Check one or more) (11)

MODE(9)

N 20.402(b) 20.405(c)

50. 73(a)(2)(iv) 73.71 (c)

POWER 20.405(a)(1 )(i) 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)(viii)(A)

(Specify In Abstract below and 20.405(a)(1 )(iv)

50. 73(a)(2)(ii)

50. 73(a)(2)(viii)(B)

In Text, NRC Form 366A) 20.405(a)(1 )(v)

50. 73(a)(2)(iii)

50. 73(a)(2)(x)

LICENSEE CONTACT FOR THIS LEA (12l NAME I TELEPHONE NUMBER (Including Area Code)

D. A. Christian, Station Manager (804) 357-3184 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)

CAUSE

SYSTEM COMPONENT MANUFACTURER REPORTABLE

CAUSE

SYSTEM COMPONENT MANUFACTURER REPORTABLE TONPRDS TONPRDS X

SB RV D243 y

... ~:t-:~

X AB RV C710 y

r~=t~; ~rn SUPPLEMENTAL REPORT EXPECTED 14)

I EXPECTED I MONTH I DAY I YEAR I YES (tt ves, comolete EXPECTED SUBMISSION DATEl XINO I

SUBMISSION DATE (15)

I I

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

On February 10, 1995, with Unit 2 in Cold Shutdown, setpoint testing of Unit 2 Main Steam Safety (MSSVs) and Pressurizer Safety Valves (PSVs) revealed that the lift settings for two MSSVs and two PSVs were outside the as found range that is allowed by Technical Specification (TS) 3.6.A. and 3.1.A.3.b. This event is reportable pursuant to 10CFR50. 73(a)(2)(i)(B) for conditions prohibited by TS 3.6.A, 3.6.8.3, 3.6.D and 3.1.A.3.b.

The safety valves were sent to Wyle Laboratories for testing to ensure conformance to TS requirements.

The as found set pressures for two MSSVs and two PSVs were found to be outside TS tolerances.

The safety valves were repaired and readjusted to be within the correct setpoint tolerances allowed by TS.

This event posed no significant safety implications because the safety valves would have performed

• their safety function in the event of an overpressure condition. The health and safety of the public were not affected at any time during this event.

. NRC FORM 366 (5-92)

NRC FORM366 (5-92)

.S. NUCLEAR REGULATORY COMMISSION LICENSING EVENT REPORT (LER)

(See reverse for required number of digits/characters for each block)

FACILITY NAME (1)

DOCKET NUMBER (2)

SURRY POWER STATION, Unit 2 05000 - 281 TEXT (II more space is required, use addltional copies of NRC Form 366A) (17)

,1.0 DESCRIPTION OF THE EVENT APPROVED BY 0MB NO. 3150-0104 EXPIRES 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE INFORMATION AND RECORDS MANAGEMENT BRANCH (MNBB n14), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555-0001, AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104), OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.

LEA NUMBER (6)

PAGE 131 YEAR SEQUENTIAL NUMBER REVISION NUMBER 95

- 002 -

00 2oF6 On February 3, 1995, Unit 2 was shut down to start a Refueling Outage. As part of the outage scope, the fifteen Main Steam Safety Valves (MSSVs) [EIIS-SB,RV] and three Pressurizer Safety Valves (PSVs) [EIIS-AB-RV] were removed and sent to Wyle Laboratories in Huntsville, Alabama for setpoint testing. The MSSVs and PSVs were functionally tested in accordance with station testing procedures developed pursuant to the Surry Power Station ASME Section XI Testing Program for Pumps and Valves.

On February 10, 1995, with Unit 2 in Cold Shutdown, setpoint testing of Unit 2 MSSVs revealed that the lift settings for two valves (02-MS-SV-202C and 205A) were above the

+/- 3% as found range that is allowed by Technical Specification (TS) 3.6.A. A list of the as found setpoints is provided in Attachment 1.

On February 15, 1995, it was determined that PSV 02-RC-SV-2551C's as found lift setting was out of tolerance. On February 16, 1995, it was determined that PSV 02-RC-SV-2551 B's as found lift setting was out of tolerance. The as found lift settings were below the minimum allowed by TS 3.1.A.3.b., i.e. 2485 psig +/- 1 %. A list of the as found setpoints is provided in Attachment 2.

This event is reportable pursuant to 1 OCFR50. 73(a)(2)(i)(B) for conditions prohibited by TS 3.6.A, 3.6.8.3, 3.6.D and 3.1.A.3.b. Unit 1 was operating at 100% power and was not affected by this event.

2.0 SIGNIFICANT SAFETY CONSEQUENCES AND IMPLICATIONS

The MSSVs provide overpressure protection for the main steam supply system piping upstream of the main steam trip valves. The PSVs provide overpressure protection for the reactor coolant system. The as found lift pressure settings for the MSSVs were bounded by the safety analyses for overpressure transients that are part of the current licensing basis. The PSV's lift pressure settings are bounded by the safety analysis for overpressure transients that is part of the Safety Evaluation prepared for a TS Change submitted to the NRC by Virginia Power Letter 95-016, dated January 24, 1995. The TS Change provides for an increase to the as found PSV Lift Setpoint Tolerance from

+/- 1% to+/- 3%. Since the acceptance criteria for overpressure events were met, the health and safety of the public were not affected.

NRC FORM 366 (5-92)

.S. NUCLEAR REGULATORY COMMISSION LICENSING EVENT REPORT (LER)

(See reverse for required number of digits/characters for each block)

FACILITY NAME 111 DOCKET NUMBER (2)

SURRY POWER STATION, Unit 2 05000 ~ 281 TEXT (If more space Is required, use additional copies of NRC Form 366A) (17)

3.0 CAUSE OF THE EVENT

APPROVED BY 0MB NO. 315CM>104 EXPIRES 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE INFORMATION AND RECORDS MANAGEMENT BRANCH (MNBB 7714), U.S. NUCLEAR REGULA TORY COMMISSION; WASHINGTON, DC 20555-0001, AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104), OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.

LER NUMBER (6)

PAGE (3)

YEAR SEQUENTIAL NUMBER REVISION NUMBER 95

- 002 -

00 3oF6 The cause of the event has been determined to be setpoint drift. The industry has experienced a history of setpoint drift for safety valves of this type and is not considered to be unusual.

Additionally, a portion of the PSV's difference in lift settings may be attributed to the differences between the lift setting measurement techniques utilized at the Wyle Laboratories and those employed by the valve's manufacturer.

The valves were installed in June 1994 and the initial testing for the valves was performed by the manufacturer at its facility. However, the valve manufacturer used analog gauges and visual cues to determine the lift setpoint of the valves. Wyle Laboratories utilizes stem movement indicators coupled to pressure recorders to determine the lift setpoint. This method provides a slightly more accurate lift indication. All three PSVs demonstrated lift pressure settings below the nominal TS value when tested in the Wyle facility.

4.0 IMMEDIATE CORRECTIVE ACTION(S)

Unit condition at time of discovery did not require any immediate corrective actions to be performed. Deviation Reports were submitted to document the out of specification setpoints for the valves.

5.0 ADDITIONAL CORRECTIVE ACTION(S)

Engineering performed a review of applicable overpressure transients to ensure the as found lift settings were within the bounds of existing analyses.

Those MSSVs with as found lift pressures outside the setpoint pressure allowed by Technical Specification 3.6.A, were inspected and overhauled by the manufacturer, Dresser Industries, at the Wyle Laboratories in Huntsville, Alabama. The MSSVs were as left tested to procedure 2-MPT-0427-02 to verify they meet the+/- 1% requirements of TS 3.6.A.

Minor maintenance was performed on PSV 02-RC-SV-2551 B and the valve's lift setting was adjusted.

PSV 02-RC-SV-2551 C was disassembled and inspected by the manufacturer, Crosby Valve and Gage Company. No internal problems were found and the valve's lift setting was adjusted. The PSVs were as left tested to procedure O-MPT-0424-01 to verify they meet the+/- 1% of the requirements of TS 3.1.A.3.b.

NRC FORM 366 (5-92)

.S. NUCLEAR REGULATORY COMMISSION LICENSING EVENT REPORT (LER)

(See reverse for required number of digits/characters for each block)

FACILITY NAME 111 DOCKET NUMBER 121 SURRY POWER STATION, Unit 2 05000 - 281 TEXT (If more space Is required, use additional copies of NRC Form 366A) (17) 6.0 ACTIONS TO PREVENT RECURRENCE APPROVED BY 0MB NO. 3150-0104 EXPIRES 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE INFORMATION AND RECORDS MANAGEMENT BRANCH (MNBB 7714), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555-0001, AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104), OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.

LEA NUMBER 161 PAGE 131 YEAR SEQUENTIAL NUMBER REVISION NUMBER 95

- 002 -

00.

4 OF 6 Safety valve setpoint drift is a known phenomenon. Periodic testing and maintenance will continue to be performed in accordance with the Virginia Power ASME Section XI

• Testing Program for Pumps and Valves to ensure that the valves are maintained as required. by TS. A TS Change to 3.1.A.3.b has been submitted to the NRG to modify the tolerance ofthe as found PSVs from 2485 psig +/- 1% to 2485 psig +/- 3%. The as found settings of the PSVs did fall within the proposed as found tolerance band of 2485 psig+/-3%.

7.0 SIMILAR EVENTS

Un.it 1 LER 88-016-00, Main Steam Safety Valves Setpoints Outside of Allowable Limits Unit 2 LER 89-013-00, Pressurizer Safety Valves Setpoints Outside Technical Specification Allowable Limits Due to Establishing Setpoints Without Loop Seal Unit 1 LER 90-011-00, Main Steam Safety Valves Out of Tolerance Due to Minor Setpoint Drift Unit 2 LER 91-002-00, Main Steam Safety Valves Out of Tolerance Due to Minor Setpoint Drift Unit 2 LER 91-003-00, Pressurizer Safety Valves Setpoints Outside Technical Specification Allowable Values Unit 1 LER 94-002-00, Main Steam Safety Valves Out of Tolerance Due to Minor Setpoint Drift NRC FORM366 (5-92)

.S. NUCLEAR REGULATORY COMMISSION APPROVED BY 0MB NO. 315CM)104

. LICENSING EVENT REPORT (LER)

(See reverse for required number of digits/characters for each block)

FACILITY NAME 111 DOCKET NUMBER 121 SURRY POWER STATION, Unit 2 05000 - 281 TEXT (II more space* ls required, use additional copies of NRC Form 3SSA) (17)

EXPIRES 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE INFORMATION AND RECORDS MANAGEMENT BRANCH (MNBB n14), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555-0001, AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104), OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.

LEA NUMBER 111\\

PAGE 131 YEAR SEQUENTIAL NUMBER REVISION NUMBER 95

- 002 -

00 5oF6 ATTACHMENT 1 Main Steam Safety Valves Valve Number Tolerance Band {psig)

As Found Set Pressure {psig)

SV-MS-201A 1052-1117 1114 SV-MS-2018 1052-1117 1079 SV-MS-201C 1052-1117 1113 SV-MS-202A 1063-1127 1107 SV-MS-2028 1063-1127 1115 SV-MS-202C 1063~1127 1148 SV-MS-203A 1077-1143 1126 SV-MS-2038 1077-1143 1110 SV-MS-203C 1077-1143 1120 SV-MS-204A 1086-1153 1146 SV-MS-2048 1086-1153 1131 SV-MS-204C 1086-1153 1130 SV-MS-205A 1101-1169 1170 SV-MS-2058 1101-1169 1146 SV-MS-205C 1101-1169 1130 I..

NRCFORM 366 (5-92)

, U.S; NUCLEAR REGULATORY COMMISSION LICENSING EVENT REPORT (LER)

(See reverse for required number of digits/characters for each block)

FACILITY NAME 111 DOCKET NUIIEEA 12\\

SURRY POWER STATION, Unit 2 05000 - 281 TEXT (If more space Is required, use additional copies of NRC Form 366A) (17)

ATTACHMENT 2 Pressurizer Safety Valves APPROVED BY 0MB NO. 31SQ.0104 EXPIRES 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE INFORMATION ANO RECORDS MANAGEMENT BRANCH (MNBB n14), U.S. NUCLEAR REGULA TORY COMMISSION, WASHINGTON, DC 20555-0001, ANO TO THE PAPERWORK REDUCTION PROJECT (3150-0104), OFFICE OF MANAGEMENT ANO BUDGET, WASHINGTON, DC 20503.

LER NUMBER l&l VEAR SEQUENTIAL NUMBER 95

- 002 -

REVISION NUMBER 00 PAGE131 6oF6 Valve Number 02-RC-SV-2551A 02-RC-SV-2551 B 02-RC-SV-2551 C Tolerance Band (psig) 2461-2509 2461-2509 2461-2509 As Found Set Pressure (psig) 2464 2432 2454