IR 05000324/1986003

Insp Rept 50-324/86-03 on 860108-10.No Violations or Deviations Noted.Major Areas Inspected:Safety Relief Valve Testing

ML20137T054
Person / Time
Site:	Brunswick
Issue date:	02/06/1986
From:	Jape F, Larry Nicholson NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20137T044	List: IR 05000324/1986003 ML20137T040
References
50-324-86-03, 50-324-86-3, NUDOCS 8602180171
Download: ML20137T054 (4)

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NUCLEAR REGULATORY COMMISSION REGION 11 g j 101 MARIETTA STREET, * 2 ATLANTA, GEORGIA 30323

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' Report.No.: _50-324/86-03 Licensee: Carolina Power and Light Company P..O. Box 1551 l Raleigh, NC 27602 I Docket No.: 50-324 License No.: DPR-62 Facility Name: Brunswick Inspection Conducted: January 8-10, 1986 Inspector: M t/c 4

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L. Nic661 son 'Date Signed Approved by:

F. Jape, SeYtion Chief 7 /

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0~ ate Signed Test Programs Engineer.ing Branch

- Division of Reactor Safety l

SUMMARY l Scope: This:special announced inspection entailed 10 inspector-hours at the Wyle l p,-

Laboratories in Huntsville, Alabama in the' area of safety relief valve (SRV) ,

testin l l

Results: No violations or deviations were identifie L B602180171 B60210 DR ADOCK O y4

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s REPORT DETAILS

' Persons Contacted-Licensee Employees l

• D.;Hickman,' Project Engineer

• J. Lane, Project Engineer Other Organizations

• J. Boseman, General Electric

• A. Szeglin, Target Pock C ~

• J. Napp,'Wyle Laboratories

• M. Wegner, NRC/IE

Attended exit interview Exit Interview The inspection scope and findings were summarized on January 9,1986, with those persons indicated in paragraph I above. The inspector described the

' areas inspected and discussed in detail the inspection finding No .

dissenting comments were received from the licensee. The licensee did not identify aas proprietary any of the materials provided to or reviewed by the inspector during this inspectio . Licensee Action on Previous Enforcement Matters This subject was not addressed in the inspectio . Unresolved Items

' Unresolved items were not identified during the inspectio . Surveillance Testing of Safety Relief Valves (61701)

The inspector reviewed Wyle Test Procedure No. 1025, Test Procedure for "As Received" Testing of Target Rock Two-Stage Pilot-Operated Safety Relief Valves _ Model Number 7567F. This procedure was developed as a diagnostic

. method to determine the actual pressure required to separate the pilot disc from its sea This is done by first heating the valve with steam to achieve thermal stabilization at a body temperature greater than 530 F. The

steam is then removed and the manifold pressurized with gaseous nitrogen to 5 psig 1. p s i g .' The air operator is then pressurized with nitrogen to lift the pilot rod off the pilot disc, leaving the disc unrestrained. At this point the manifold is pressurized with nitrogen at a rate of less than psi per second until the disc lifts, or a nitrogen pressure of 200 psig is reached.

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The '.results of this diagnostic test revealed six' out of 11 valves were pressurized to 200 psig nitrogen without lifting.(see Table I). Four of the

< ' stuck valves were successfully lifted ~ using the solenoid actuator, demonstrating operability-in the ADS and manual modes. A'fifth valve (S/N 1109)- was steam popped, . lifting at 1219 psig steam. The sixth valve was mistakenly disassembled before it could be subjected to further testin The. inspector witnessed the disassembly . of valve #1109 and examined the removed parts. The disc appeared normal with a solid, bright seating band

.and no obvious .cause for problems. The labyrinth seal area showed- very light wear. This valve is scheduled to receive a new disc manufactured fro . PH 13-8 Mo as a part of refurbishmen Within the areas -examined, no violations or deviations were identifie ,

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-1986 WYLE LAB TEST,RESULTSi ' BRUNSWICK 2

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.. VALVE # - SET PRESS N2 PRESS- STEAM PRESS-t 1091' '1105 11 1131

"1099 '1105 200+. (Solenoid) + 1107 1101 1115- 11 1134-1102* 1115 82- 1134-1103 1125 48 1134-

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1104*- .1125- 200+- (Solenoid) + 1153 1105~ 1115- -200+ (Disassembled)

1106*- .

1105 5 1116 1107* 1115 200+ (Instrument Failure).

1108* 1125 200+ (Solenoid) + 1176 1109*~ 1105- 200+ 1219

' * Scheduled to receive new PH 13-8-Mo dis _

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