NRC-90-0019, LER 89-028-01:on 891028,eight Safety Relief Valves Failed Set Pressure Tolerance Test.Cause Under Review by Util & Generically by BWR Owners Group Safety Relief Valve Set Point Drift Committee.Valves Removed & cleaned.W/900131 Ltr

LER 89-028-01:on 891028,eight Safety Relief Valves Failed Set Pressure Tolerance Test.Cause Under Review by Util & Generically by BWR Owners Group Safety Relief Valve Set Point Drift Committee.Valves Removed & cleaned.W/900131 Ltr

ML20011E164
Person / Time
Site:	Fermi
Issue date:	01/31/1990
From:	Orser W, Pendergast J DETROIT EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
CON-NRC-90-0019 LER-89-028, NUDOCS 9002080297
Download: ML20011E164 (5)

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NRC-90-0019-DA'- U. S. Nuclear Regulatory Commission-Attention: Document Control Desk.

Washington,-D.C. 20555

Reference:

Fermi 2 NRC Docket No. 50-341

, Facility Operating License No. NPF-43

Subject:

Licensee Event Report (LER) No. 89-028-01 s

Please find enclosed LER No. 89-028-01, January 31, 1990,-

. for a reportable event that occurred on October 28,

1989 A copy of this LER is also being sent to the Regional Administrator, USNRC Region III.

If you have any questions,-please contact Joseph' Pendergast at (313) 586-1682.

Sincerely

Enclosure:

NRC Forms 365, 366A cc: A. B. Davis:

J. R. Eckert R. W. Defayette/W. L. Axelson W. G. Rogers J. F. Stang Wayne County Emergency Nanagement Division 9002080297 900131 PDR ADOCK 05000341 S PDC

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NAME TittPMONE NUM$tR f Amta C004 Joseph Pendergast, CCEpliance Engineer 3l1 13 586iil i i i 6i 8l2 co-stn oNG uNt som E Acu cowoNENT e AnuRTBE CRino iN TMis RteonT Hai I ca.un symu cowoNENT "^*Wl^* "!Ml^!!' s cAun sv Ttv cowoNtNT *^*Wl^c 0

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1 The Main Steam System is equipped with fifteen Safety Relief Valves (SRVs). Technical Specifications require that half of the  ;

SRVs be proven operable at least once every eighteen months by performing a set pressure test. Fifteen SRVs were removed and l sent to Wyle Laboratories to meet the surveillance requirement.

lE Wyle Laboratorles has notified Detroit Edison that 8 of the 3RVs l failed their set pressure test. This report is being revised to l reflect the test results received from Wyle Laboratories. I l

The cause of this event is currently under review by Detroit Edison (DECO) and generically by the Boiling Water Reactor Ouners Group (BWROG) SRV Set Point Drift Committee.

All valves removed from the plant for testing are being refurbished, cleaned, retested and recertified to be within accepted tolerances prior to return to Fermi 2 from Wyle Laboratories.

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TEXT Initial Conditions: <

~ Operational Condition

5 (Refueling)

L Reactor Power: 05 l' Reactor Pressure: O psig Reactor Temperature: 89 degrees Fahrenheit Description of Event:

The Main Steam (SB) system is equipped with fifteen Target Rocki two-stage pilot-operated Safety Relief Valves (SRVs) (RV), which

,L, are designed to prevent over-pressurization of the Nuclear Steam Supply System (NSSS). Technical Specification surveillance requirement 4.4.2.1.2 states that half of the SRVs must be proven l- operable at least once very eighteen months by performing a set pressure test. All fifteen SRVs must be set pressure tested during a forty month period.

Eight SRV valve / pilot assemblies were removed and sent to Wyle I Laboratories to meet the surveillance requirement for the first i refueling outage, which began on September 3, 1989 o

Due to four SRVs exceeding their setpoint tolerance of 1 15 and in l accordance with the requirements contained in ASME Section XI, l

Subsection IWV-3513, 1980 Edition, Winter '81 Addendum, the remaining seven SRV valve / pilot assemblies were removed and also sent to Wyle Laboratories for testing and refurbishment. On November 6, 1989, Wyle Laboratories verbally notified the site that 4 more SRVs exceeded their set pressure test for a total of 8 SRVs exceeding their Technical' Specification acceptance tolerance of i 15 of their pressure setpoint.

SRVs are divided into three pressure setpoint groups. The first group consists of five valves set to open when Reactor Pressure Vessel (RPV) pressure exceeds- 1110 psig, the second group consists ,

of five valves set to open when RPV pressure exceeds 1120 psig and the third group consists of five valves set to open when RPV pressure exceeds 1130 psig. Below is a table summarizing the results of the SRVs tested. ,

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MEASURED VALVE NUMBER SET PRESSURE (psig) ACTUAL SETPOINT (psig) oB2104-F013A 1110 1156 oB2104-F013B'8 1110 1063 .

B2104-F013C 1110 1121 l oB2104-F013D'# 1120 1102. l oB2104-F013E 1130 1216 B2104-F013F 1120 1111 oB2104-F013G 1110 1073 ,

B2104-F013H 1130 1132 B2104-F013J'8 1130 1141 oB2104-F013K 1110 1188 I B2104-F013L 1120 1118 )

oB2104-F013M 1120 1133 -I '

B2104-F013N## 1120 oB2104-F013P 1130 1166 B2104-F013R 1130 1125 o Denotes those SRVs which exceeded the T.S. 4.4.2.1.2 15 1

tolerance.

• SRV as-found set pressure test was voided due to the inadvertent loosening of pilot assembly bonnet to body I assembly bolts which decompressed the pilots' set pressure spring.

• • Pilot Disk material ARMCO Alloy PH13-8MO Steel.

Cause of the Event:

SRV set pressure drift is an industry problem and is being addressed by DECO in conjunction with Boiling Water Reactor Owners Group (BWR00) SRV Setpoint Drift Committee as a generic issue. _

l Analysis of the Event: l

-l An analysis of SRV setpoint drift was performed by Fermi 2 . l engineering staff during the 1988 LLRT Outage when 9 SRVS exceeded j Ltheir set pressure. The analysis showed that even with 9 SRVS 1

exceeding their setpoint by an average of approximately 50 pai, l.

the RPV pressure would have raised only 20 paid over the existing USFAR analyzed peak pressure of 1278 psig. The resulting peak pressure of 1298 psig is a value well below Technical Specification Safety Limit 2.1 3 for reactor coolant system pressure which is 1325 psig. This 1988 analysis was reviewed by l the engineering staff. It was determined that the analysis l beunds the 1989 first refueling SRV setpoint test results. l Timrefore, the SRVs would have adequately protected the reactor coolant pressure boundary safety limit and assured NSSS integrity.

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-Detroit Edison is continuing to pursue resolution through the l BWROG and the Fermi 2 corrective actions process. Detroit Edison l has installed 15 newly refurbished spares and has modified 7 of I the. currently-installed pilot assemblies with pilot seat I materikl of ARMCO Alloy PH13-8MO steel as was recommended by the l' BWROG at the time of installation. l l'  ;

E -Previous Similar Events:

Two events have occurred which are similar to this. The first  ;;

occurred in May 1986 and was documented in Licensee Event Report 86-013. The second occurred in March 1988 and was documented in '

l Licensee Event Report 88-009-01.

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