ML20154F887
| ML20154F887 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 10/05/1998 |
| From: | Eugene Kelly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Roche M GENERAL PUBLIC UTILITIES CORP. |
| References | |
| 50-219-98-07, 50-219-98-7, NUDOCS 9810090412 | |
| Download: ML20154F887 (2) | |
See also: IR 05000219/1998007
Text
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October 5, 1998
Mr. Michael B. Roche
Vice President and Director
GPU Nuclear, Inc.
Oyster Creek Nuclear Generating Station
P.O. Box 388
- Forked River, New Jersey 08731
SUBJECT:
NRC INSPECTION REPORT NO. 50-219/98-07- REPLY
Dear Mr. Roche:
' This letter refers to your September 3,1998 correspondence, in response to our
July 2,1998 letter.
Thank you for informing us of the clarifications and commitments documented in your
letter. These actions pertain to your program implemented in response to Generic Letter 89-10, " Safety-related Motor Operated Valve Testing and Surveillance." Your
commitments will be examined during a future inspection of your licensed program.
Your cooperation with us is appreciated.
Sincerely,
Eugene M. Kelly, Chief
Systems Engineering Branch
Division of Reactor Safety
Docket No. 50 219
cc:
M. Laggart, Manager, Licensing and Vendor Audits
G. Busch, Manager, Nuclear Safety and Licensing
State of New Jersey
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9810090412 981005
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Distribution:
Region l Docket Room (with concurrences)
Nuclear Safety information Center (NSIC)
PUBLIC
J. Wiggins, DRS
L. Nicholson, DRS
E. Kelly, DRS
D. Dempsey, DRS
NRC Resident inspector
P. Eselgroth, DRP
N. Perry, DRP
D. Haverkamp, DRP
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C, O Daniell, DRP
B. McCabe, OEDO
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C. Thomas, PD1-3, NRR
R. Eaton, PD1-3, NRR
T. Colburn, PDl-3, NRR
R. Correia, NRR
F. Talbot, NRR
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DOCDESK
Inspection Program Branch, NRR (IPAS)
DRS File
DOCUMENT NAME: OC9807. REP
TA receive a copy of this document. Indicate in ttm box:
"C" = Copy without attachment / enclosure
"E" = Copy with attachment / enclosure
- N" = No
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GPU Nuclear,inc'.
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U.S. Route d South
NUCLEAR
Post Office Box 388
Forked Ruer. NJ 087310388
Tel 609 97I 4000
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
deport 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 accurately reflected the 17R outage plan at the
time of the inspection. However, recent assessment indicates that the valve
design margin based on a preliminary Electric Power Research Institute (EPRI)
Performance Prediction Methodology (PPM) thmst determination accounting for
Limitorque Bulletin 98-01 Guidance is considered sufficient for Cycle 17
operation. Therefore, GPU Nucler.r 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, states 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
outage. A dynamic test of the pump suction valve (V-17-19) is not practical.
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1940-98-20411
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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
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(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.
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If any additional information is needed, please contact N&. David J. Distel, GPU Nuclear Licensing and
Regulatory Affairs at (973) 316-7955.
Sincerely,
.
%g Michael .Roche
Vice President and Director
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Oyster Creek
/DJD
Attachment: OCNGS Genenc Letter 89-10 Program Commitments
1
cc:
Administrator, Region I - H. J. Miller
NRC Region I- D. Dempsey
OCNGS Senior Project Manager - R. Eaton
OCNGS Senior Resident Inspector - J. Schoppy
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ATFACHMENT
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OCNGS Generic Letter 89-10 Program Commitments
A.
Valve Modifications
1.
Containment Spray Valves V-21-5 and V-21-11 to be modified (torque switch adjustment) in 17R (Fall 1998)
to provide improved thrust margins to accommodate 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
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discs, or to install new replacement valves.
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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.
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B.
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1.
Complete EPRI PPM calculation for Isolation Condenser Valves V-14-36 and V-14-37 in 18R (Fall 2000).
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his calculation was completed on July 24,1998.
2.
Complete EPRI PPM calculation for Reactor Water Cleanup Valves V-16-1, V-16-2, V-16-14, and V-16-61 in
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17R (Fall 1998). His calculation wr 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 Testimg
1.
Containment Spray Valves V-21-15 and V-21-18 will be dynamically tested in 17R (Fall 1998) to confmn
the established valve factor.
2.
Containment Spray Valve V-21-13 and Shutdown Cooling System Valve V-17-54 to be dynamically tested in
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17R (Fall 1998) in accordance with Generic Letter 96-005 Joint Owner, Group Program Periodic
Verification Testing commitment.
D.
Prostram Documentation Uodates
1.
Com crt rate-of-loading methodology to the EPRI method for valve stroke time calculation in 17R (Fall 1998).
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2.
Upgrade wrak link calculation and compleo design verification in 17R (Fall 1998).
3.
Evaluate EPRl/NMAC testing of stem lubricant Synco Super Lube EP-2 to determine impact on rate-of-
loading assumptions by 18R (Fall 2000).
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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