ML20247M309
| ML20247M309 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 07/24/1989 |
| From: | Fitzpatrick E GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| RTR-NUREG-0737, RTR-NUREG-1342, RTR-NUREG-737 GL-89-06, GL-89-6, NUDOCS 8908020053 | |
| Download: ML20247M309 (3) | |
Text
.-
.. - -: E GPU Nuclear CorporaHon L
Nucle-ar
- ait; 88 I
I-Forked River, New Jersey 08731-0388 l
609 971-4000
[
Wnter's Direct Dial Number:
July 24,1989 U.S. Nuclear Regulatory Commission Attn: Document Contrra Desk
-Washington, DC 20555
Dear Sir:
Subject:
Oyster Creek Nuclear Generating Station Docket No. 50-219 Response to Generic Letter 89-06
" Safety Parameter Display System" As requested by the subject Generic Letter 89-06 dated April 12, 1989, this correspondence provides our response.
GPU Nuclear hereby certifies that the Oyster Creek Safety Parameter Display System (SPDS) fully meets the requirements of NUREG 0737, Supplement 1 taking into account the information provided in NUREG 1342, with the clarifications outlined in the attachment. Supporting documentation, including the Generic Letter checklist and SPDS photographs used to establish SPDS implementation status will be made available to inspection personnel.
Correspondence dated March 5,1986, NRR to GPU Nuclear, stated that the documentation of SPDS was acceptable with comments.
The safety evaluation stated that a post-implementation audit would be performed. The Oyster Creek l
SPDS was made operational in December 1987.
As discussed and agreed to by year staff on Friday, July 14,1989, due to the delay in receiving the subject Generic Letter, the response period for Oyster Creek was extended two weeks until July 28, 1989.
i 8908020053 890724 003 I
PDR ADOCK 05000219 P
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l GPU Nuclear Corporation is a subsidiary of General Public Utilities Corporation i
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U.S. Nuclear R:gulatory Commission Document Control Desk
~Page 2 Should you require further information please contact Brenda DeMerchant, OC Licensing Engineer at (609)971-4642.
Very truly yours, E. E. Fitzp rick Vice President and Director Oyster Creek EEF/BDe/dmd:(0794A)
Attachment cc: Mr. William T. Russell, Administrator Region.I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. Alexander W. Dromerick, Project Manager U.S. Nuclear Regulatory Commission Washington, DC 20555 NRC Rcsident Inspector Oyster Creek Nuclear Generating Station l
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ATTACHMENT Clarification of Compliance to NUREG 0737, Supplement 1 The Oyster Creek Safety Parameter. Display System (SPDS) meets the requirements' of NUREG-0737, Supplement 1. - Additionally, the Oyster Creek SPDS meets the intent of NUREG-1342 with the following clarifications:
~ The Oyster Creek SPDS does not use Source Range Monitoring (SRM) o-instrumentation (reference 1). The SRMs were not considered to be beneficial for' post-shutdown reactivity monitoring. Power levels below 2% APRM downscale trip are within the decay heat removal capability of Oyster Creek. Therefore, from an energy balance point of view, it is not critical to monitor these power levels. From a criticality point of view, the E0Ps require the operator to confirm reactor shutdown with control rod position rather than continuously monitoring.SRM readings. Finally, reference I states that SPDS will not be used for reactor startups but rather' for power operation, emergency and post trip conditions.
The Oyster Creek-SPDS does not provide indication of containment o
isolation valve status. The SPDS provides an indication of containment isolation demand. The intent of SPDS is to provide the user with an overview of the critical safety. function. The user does not depend upon SPDS to operate the plant.
The Oyster Creek Plant Computer uses a maximJm-minimum range check o
for validation purposes.
Where available, redundant sensors are considered in the alarm calculations.
Therefore, bad sensors are not used in establishing alarms. GPUN comnitted to evaluate the use of advanced data validation schemes. Algorithms have been developed I
to provide data validation. However, they have not been fully l
tested or implemented.
The Oyster Creek SPDS is not operational in all modes of operation above cold shutdown. GPU Nuclear's original submittal to the NRC (Reference 1) noted that SPDS would be utilized during power range operation and reactor trips. The startup mode was not considered, however, SPDS is operable and all valid information is made i
available to the operator.
Reference 1:
Letter dated April 2,1984, P. B. Fiedler, GPUN to D. G.
Eisenhut, USNRC f
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