ML19282A778
| ML19282A778 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 02/08/1979 |
| From: | Ziemann D Office of Nuclear Reactor Regulation |
| To: | Finfrock I JERSEY CENTRAL POWER & LIGHT CO. |
| References | |
| TASK-04-01.A, TASK-4-1.A, TASK-RR NUDOCS 7903060477 | |
| Download: ML19282A778 (4) | |
Text
.. l
)
d'pm afog S
UNITED STATES
[*
NUCLEAR REGULATORY COMMISSION 5'-e
.I o.
WASHINGTON. D. C. 20555
"$ [ s [./ - g February 8,1979 A
,8 Docket No. 50-219 Mr. I. R. Finfrock, Jr.
Vice President - Generation Jersey Central Power & Light Company Madison Avenue at Punch Bowl Road Morristown, New Jersey 07960
Dear Mr. Finfrock:
' Comments received on the draft evaluation of Systematic Evaluation Program Topic IV-1.A have been reviewed and the evaluation has been revised. The revised draft evaluation, copy enclosed, supersedes the ' evaluation issued by our letter dated August 17, 1978.
You are requested to examine the facts upon which the staff has based its evaluation and respond either by confirming that the facts are correct, or by identifying any errors.
If in error, please supply corrected information for the docket. We encourage you to supply for the docket any other material related to this topic that might affect the staff's evaluation.
Your response within 30 days of the date you receive this letter is requested.
If no response is received within that time, we will assume that you have no comments or corrections.
S ncerely, en Dennis L. Zieman, Chief Operating Reactors Branch #2 Division of Operating Reactors
Enclosure:
Topic IV-1.A cc w/ enclosure:
See next page 7 9 0 3 0 6 0 4 7 ~l
~
Mr. I. R. Finfrock, Jr. February 8,1979 cc w/ enclosure-G. F. Trowbridge, Esquire Shaw, Pittman, Potts and Trowbridge 1800 M Street, N. W.
Washington, D. C.
20036 GPU Service Corporation ATTH:
Mr. E. G. Wallace Licensing Manager 260 Cherry Hill Road Parsippany, New Jersey 07054 Anthony Z. Doisman Natural Resources Defense Council 917 15th Street, N. W.
Washington, D. C.
20005 Steven P. Russo, Esquire 248 Washington Street P. O. Box 1060 Toms River, New Jersey 08753 Joseph W. Ferraro, Jr., Esquire Deputy Attorney General State of New Jersey Department of Law and Public Safety 1100 Raymond Boulevard Newark, New Jersey 07012 Ocean County Library Brick Township Branch 401 Chambers Bridge Road Brick Town, New Jersey 08723 K M C, Inc.
~
ATTN:
Jack McEwen 1747 Pennsylvania Avenue, N. W.
Suite 1050 Washington, D. C.
20006
SYSTEMATIC EVALUATION PROGRAM Topic IV-I-A: Operation with less than all loops in service PLANT: Oyster Creek Nuclear Power Plant Unit No.1 Discussion The majority of the presently operating BWR's and PWR's are designed to permit operation with less than full reactor coolant flow. If a PWR reactor coolant pump or a BWR recirculation pump becomes inoperative,
' the flow provided by the remaining ' loop or loops is sufficient for
. steady state operation at some definable power level, usually less than full power.
Plants authorized for long term operation with one reactor coolant pump out of service have submitted, and the staff has approved, the necessary ECCS, steady state, and transient analyses. The remaining PWR and BWR licensees have Technical Specifications which require reactor shut-down within 24 h'ours if one of the operating loops becomes inoperable and cannot be returned to operation within the time period.
Evaluation The docketed material for Oyster Creek has been reviewed with respect to operation with less than all loops in service.
Oyster Creek is a five loop General Electric design Boiling Water Reactor (BWR).
In a submittal dated February 5,1976, Jersey Central Power & Light Company (JCP&L) presented an analysis for operation with a single recirculation pump inoperable. The analysis supported n-1 loop operation and concluded that ECCS analyses would not be affected provided that the inoperable pump was not isolated from the system.
The NRC staff reviewed and approved the February partial loop submitted in a safety evaluation (dated February 24, 1976).
In addition the staff issued Technical Specification 3.3.F.1, 3.3.F.2, and 3.3.F.3 which state that operation is permitted with one inoperable recirculation loop provided that the inoperable loop is no.t isolated from the reactor system.
Based on the information reviewed we conclude that Topic IV-I-A:
- Operation with less than all loops 'in service at Oyster Creek is acceptable and complete requiring no facility or Technical Specification changes.
s