NRC-89-0246, LER 89-028-00:on 891020,eight safety-related Valves Failed Set Pressure Test.Cause Under Review.All Valves Removed for Testing Being Refurbished,Cleaned,Retested & Recertified to Be within Plant Accepted tolerances.W/891120 Ltr

LER 89-028-00:on 891020,eight safety-related Valves Failed Set Pressure Test.Cause Under Review.All Valves Removed for Testing Being Refurbished,Cleaned,Retested & Recertified to Be within Plant Accepted tolerances.W/891120 Ltr

ML19332B975
Person / Time
Site:	Fermi
Issue date:	11/20/1989
From:	Anthony P, Orser W DETROIT EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
CON-NRC-89-0246, CON-NRC-89-246 LER-89-028, LER-89-28, NUDOCS 8911220138
Download: ML19332B975 (5)

Text

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10CFR50.73

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NRC-89-0246 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 1 i

Subject Licensee Event Report (LER) No. 89-028-00 j Please find enclosed LER No. 89-028-00 dated November 20 1989, for a reportable event that occurred on October 20 1989. A copy of this LER is also being sent to the Regional Administrator. USNRC Region III.

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If you have any questions, plesse contact Patricia l Anthony at (313) 586-1617. '

Sincerely.

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1 Enclosures NRC Forms 366 366A cc: A. B. Davis >l J. R. Eckert R. W. Defayette/W. L. Axelson 3 W. G. Rogers '

J. F. Stang Wayne County Emergency j Management Division '

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$ BMtt$10N T sit m,M. . .. enterro suswwo= ce rts ] No os, 011 31 1 9 10 Aus, Act iv m um ua t. . .,cm u, .,. c ~r . s 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 conths by performing a set pressure test. Fifteen SRVs were removed and sent to Wyle Laboratories to meet the surveillance requirement.

Wyle Laboratories has verbally notified Detroit Edison that 8 of the SRVs failed their set pressure test.

The cause of this event is currently under review by Detroit Edison (Deco) and generically by the Boiling Water Reactor Owners 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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Initial Conditions:

Operational Condition: 5 (Refueling)

Reactor Power 0%

Reactor Pressure: O psig Reactor Temperaturet 89 degrees Fahrenheit Description of Event.:

The Main Steam (SB) system is equipped with fifteen Target Rock ]

.two-stage pilot-operated Safety Relief Valves (SRVs) (RV). which j are designed to prevent over-pressurization of the Nuclear Steam Supply System (NSSS). Technical Specification surveillance j requirement 4.4.2.1.2 states that half of the SRVs must be proven 1 operable at least once very eighteen months by performing a set l 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 Laboratories to meet the surveillance requirement for the first {

refueling outage, which began on September 3 1989. l Due to four SRVs exceeding their setpoint tolerance of 1 1% and in f accordance with the requirements contained in ASME Section XI.  ;

Subsection IWV-3513 1980 Edition. Winter '81 Addendum, the i remaining seven SRV valve / pilot assemblies were removed.and also ,

sent to Wyle Laboratories for testing and refurbishment. On l November 6 1989. Wyle Laboratories verbally notified the site  ;

that 4 more SRVs exceeded their set pressure test for a total of 8 r l

SRVs exceeding their Technical Specification acceptance tolerance  !

of i 1% 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 i the third group consists of five valves set to open when RPV j pressure exceeds 1130 psig. Below is a table summarising the i results of the SRVs tested.  ;

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MEASURED  !

VALVE NUMBER SET PRESSURE (psig) ACTUAL SETPOINT'(psia) + i i

oB2104-F013A 1110 1156 i oB2104-F013B** 1110 1063  !

B2104-F013C 1110 1121 i oB2104-F013D** 1120 1102 i oB2104-F013E 1130 1216 l B2104-F013F 1120 till oB2104-F0130 1110 1073 f 32104-7013H 1130 1132 i B2104-F013J** 1130 1141 oB2104-F013K 1110 1184  ;

B2104-F013L 1120 1118 i oB2104-7013M 1120 1133 {

B2104-7013N** 1120

• i oB2104-F013P** 1130 1166 j B2104-F013R 1130 1125  !

o denotes those SRVs which exceeded the T.S. 4.4.2.1.2 +1% [

t ol e r r.n c e .

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• 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.

• 8' Pilot Disk material ARMCO Alloy FH13-8MO Steel.

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+ Formal test report data has not yet been received from Wyle Laboratories. ,

i Cause of the Events i l

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

this time insufficient information has been provided by Wyle  !

Laboratories to determine the specific cause of this event.

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Analysis of the Event:

An analysis of SRV setpoint drift was performed by Fermi 2 (

engineering staff during the 1988 LLRT Outage when 9 SRVS exceeded i their set pressure. The analysis showed that even with 9 SRVS l

~ exceeding their setpoint by approximately 50 psi each. the RPV  !

pressure would have raised only 20 psid 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 l psig. This 1988 analysis bounds the 1989 first refueling SRV i setpoint test results. Therefore, the SRVs would have adequately protected the reactor coolant pressure boundary safety limit and  ;

assured NSSS integrity. j Specific analysis of these SRV failures or a bounding event will ,

be included in a revision to this LER.  !

Corrective Action: [

To minimize future high set pressure drift on SRVs, Detroit Edison has installed 15 newly refurbished spares and has modified 7 of j the currently installed pilot assemblies with the improved pilot i seat material. ARHC0 Alloy PH13-BHO Steel. This was done as recommended by the BWROG. Additional corrective actions are still ,

under investigation by Fermi 2 engineering and will be addressed in a revision to this report. This Licensee Event Report will be revised within thirty days of the receipt of the formal test results from Wyle Laboratories.

Previous Similar Events:

Two events have occurred which are similar to this. The first occurred in May 1986 and was documented in Licencee Event Report 86-013. The second occurred in March 1988 and was documented in Licensee Event Report 88-009-01.

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