ML20197C594
| ML20197C594 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 09/03/1998 |
| From: | Roche M GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 1940-98-20411, 50-219-98-07, 50-219-98-7, NUDOCS 9809140117 | |
| Download: ML20197C594 (3) | |
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GPU Nuclear, Inc.
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U.S. Route #9 South i
NUCLEAR Post Ofhce Box 388 Forked River, NJ 087310388 Tel 609-971-4000 l
September 3, 1998 1940-98-20411 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Gentlemen:
Subject:
Oyster Creek Nuclear Generating Station (OCNGS)
Docket No. 50-219 Facility Operating License No. DPR-16 Response to NRC Motor Operated Valve Inspection l
Report No. 50-219/98-07 GPU Nuclear's review of NRC Inspection Report (IR) No. 50-219/98-07, Motor Operated Valve Program Review, identified the following areas requiring clarification or update:
1.
IR 98-07, Section El.l.b, page 3, states that GPU Nuclear plans to increase the design capability of valve V-14-30 by replacing the motor power cable during the 17R refueling outage. This statement is correct based on previously docketed GPU Nuclear commitments and securately reflected the 17R outage plan at the l
time of the inspection. However, recent assessment indicates that the valve design margin based on a preliminary Electric Power Research Institute (EPRI) l Performance Prediction Methodo;ogy (PPM) thrust determination accounting for Limitorque Bulletin 98-01 Guidance is considered sufficient for Cycle 17 operation. Therefore, GPU Nuclear is deferring this modification to V-14-30 to the 18R refueling outage. Replacement of the power cable to valve V-14-36 is still planned for the 17R refueling outage.
2.
IR 98-07, Section El.l.b, page 4, sta.es that GPU Nuclear plans to dynamically test both shutdown cooling system valves, V-17-19 and V-17-54, in the 17R refueling outage.
GPU Nuclear is planning to dynamically test only the shutdown cooling system pump discharge valve (V-17-54) during the 17R I
outage. A dynamic test of the pump suction valve 'V-17-19) is not practical.
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Page 2 3.
IR 98-07, Section El. l.b, page 4, last paragraph, states GPU Nuclear committed to dynamically test four valves in the drywell spray and shutdown cooling systems. Based on the clarification described in Item 2 above, it should be noted that this dynamic testing includes the shutdown cooling system valve V-17-54 (Group 4), the containment spray system valves V-21-15 and V-21-18 (Group 6), and the containment spray valve V-21-13 (Group 5).
As discussed during the subject inspection, provided in the attachment to this letter is a summary of the remaining OCNGS Generic Letter 89-10 Program docketed commitments. It is noted that EPRI PPM calculations, previously committed to be completed by 18R (Fall 2000), have been recently completed as shown on the attachment.
If any additional information is needed, please contact Mr. David J. Distel, GPU Nuclear Licensing and Regulatory Affairs at (973) 316-7955.
Sincerely, t
%g Michael. Roche Vice PrW.ent and Director Oyster Creek
/DJD
Attachment:
OCNGS Generic Letter 89-10 Program Commitments cc:
Administrator, Region I - H. J. Miller NRC Region 1 - D. Dempsey OCNGS Senior Project Manager - R. Eaton OCNGS Senior Resident inspector - J. Schoppy
ATTACHM ENT OCNGS Generic Letter 89-10 Program Commitments 1
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A.
Valve Modifications l
1.
Contamment Spray Valves V-21-5 and V-21-11 to be modified (torque switch adjustment) in 17R (Fall 1998)
I to provide improved thrust margins to acconunodate the EPRI PPM maximum predicted thrust.
2.
Isolation Condenser Valves V-14-36 to be modified in 17R (Fall 1998) and V-14-30 to be modified in 18R to improve available voltage and design margin. Modification consists ofinstalling larger power cables to the valve motors.
3.
Isolation Condenser Valves V-14-36 and V-14-37 to be modified in 18R (Fall 2000) to install new guides or discs, or to install new replacement valves.
4.
Reactor Water Cleanup Valves V-16-1, V-16-2, V-16-14, and V-16-61 to be modified in 17R (Fall 1998) to install replacement valve discs with hard-faced disc guide areas.
l B.
Complete EPRI PPM calculation for Isolation Condenser Valves V-14-36 and V-14-37 in 18R (Fall 2000).
This calculation was completed on July 24,1998, 2.
Complete EPRI PPM calculation for Reactor Water Cleanup Valves V-16-1, V-! %2 V-16-14, and V-16-61 in 17R (Fall 1998). This calculation was completed on July 24,1998.
3.
Complete EPRI PPM calculation for Core Spray Valves V-20-15, V-20-21, V-20-40, and V-20-41 in 18R (Fall 2000). This calculation was completed on July 24,1998.
C.
Valve Testing 1.
Containment Spray Valves V-21-15 and V-21-18 will be dynamically tested in 17R (Fall 1998) to confirm the established valve factor.
2.
Containment Spray Vahu V-21-13 and Shutdosm Cooling System Valve V-17-54 to be dynamically tested in 17R (Fah !998) in accordance with Generic Letter 96-005 Joint Owners Group Program Periodic Verification 1 cing commitment.
D.
Procram Documentation Updates 1.
Convert rate-of-loading methodology to the EPRI method for valve stroke time calculation in 17R (Fall 1998).
2.
Upgrade weak link calculation and complete design verification in 17R (Fall 1998).
3.
Evaluate EPRI/NMAC testing of stem lubricant Synco Super Lube EP-2 to determine impact on rate-of-loading assumptions by If>R (Fall 2000).
l 4.
Revise hand calculations for Anchor-Darling double-disc valves to reference NRC SER limitations and conditions on the EPRI PPM and include Revision 2 of EPRI TR-103237 by December 31,1998.
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