ML20214R008
| ML20214R008 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 11/26/1986 |
| From: | Fielder P GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20214Q835 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.E.4.2, TASK-2.F.1, TASK-TM NUDOCS 8612050341 | |
| Download: ML20214R008 (5) | |
Text
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GPU NUCLEAR CORPORATION OYSTER CREEK NUCLEAR GENERATING STATION PROVISIONAL OPERATING LICENSE N0. DPR-16 TECHNICAL SPECIFICATION CHANGE REQUEST NO.152 DOCKET N0. 50-219 Applicant submits, by this Technical Specification Change Request No.152 to the Oyster Creek Nuclear Generating Station Technical Specifications,-changes to specifications 3.1, 3.13, 4.1 and 4.13.
By 1 M Pet @ TTiedler Vice President and Director j
Oyster Creek l
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Sworn and subscribed to before me this 8 4 day of // h 1986.
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A Notary Public of NJ Etp 4/s/*?/
0612050341 861126 DR ADOCK 05000219 PDR
r UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION IN THE MATTER OF
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DOCKET NO. 50-219 GPU NUCLEAR CORPORATION CERTIFICATE OF-SERVICE This is to certify that a copy of Technical Specification Change Request No.
152 for the Oyster Creek Nuclear Generating Station Technical Specifications, filed with the United States Nuclear Regulatory Commission on November 26 1986, has this day of November 26
, 1986, been served on the Mayor of Lacey Township, Ocean County, New Jersey by deposit in the United States mail, addressed as follows:
The Honorable Christopher Connors Mayor of Lacey Township 818 West Lacey Road Forked River, NJ 08731 AdL AL J'"^
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By:
M Peter 'HT"Fied le r Vice President and Director Oyster Creek
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GPU Nuclear Corporation BENhgMf -
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100 Interpace Parkway Parsippany, New Jersey 07054-1149 (201)263-6500 Tl: LEX 136-482 V< titer's Direct Dial Number:
November 26, 1986 The Honorable Christopher Connors Mayor of Lacey Township 818 West Lacey Road Forked River, NJ 08731
Dear Mayor Connors:
Enclosed herewith is one copy of the Technical Specification Change Request No.152 for the Oyster Creek Nucler Generating Station Operating License.
This document was filled with the United States Nuclear Regulatory Commission on November 26
, 1986.
Very truly yours, 3
_y P
edTer Vice President and Director Oyster Creek PBF:ndg:4020f Enclocure l
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l GPU Nuclear Corporation is a subsidiary of General Pubhc Utiht:es Corporation
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OYSTEP CREEK NUCLEAR GENERATING STATION PROVISIONAL OPERATING LICENSE NO. DPR-16 DOCKET N0. 50-219 TECHNICAL SPECIFICATION CHANGE REQUEST NO.152 Applicant hereby requests the Commission to change Appendix A of the license.
Also, pursuant to 10CFR50.91, an analysis concerning significant hazards considerations is presented:
1.
Sections to be Changed:
3.1, 3.13, 4.1 and 4.13 2.
Extent of Change:
The subject change request incorporates the containment high range radiation monitoring capabilities into the accident monitoring instrumentation requirements of Section 3.13 and 4.13.
In addition, the request incorporates the containment vent and purge isolation function into the protective instrumentation requirements of Section 3.1 and 4.1.
3.
Changes Requested:
The requested changes are as indicated in the attached revised Technical Specification pages 3.1-7, 3.5-13, 3.13-3, 3.13-4, 4.1-8, 4.1-9, 4.13-1, 4.13-2 and new proposed pages 3.1-15a and 3.13-3a.
4.
Discussion NUREG 0737 Items II.F.1.3 and II.E.4.2.7 require the Qyster Creek Nuclear Generating Station to develop the capability to monitor high radiation levels in containment and to isolate the containment vent and purge valves upon drywell high' radiation levels. TSCR #152 is provided in response to Generic Letter 83-36 which identified technical specification requirements.
The containment high range radiation monitoring system will provide the operator with the capability to monitor radiation levels while the isolation of containment vent and purge valves upon drywell high radiation levels will prevent releases from exceeding ten percent of the dose guideline values allowed by 10CFR100.
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Determination:
GPU Nuclear has determined that operation of the Oyster Creek Nuclear Generating Station in accordance with the proposed technical specifications does not involve a significant hazard. The change does not:
1.
Involve an increase in the probability or consequences of an accident previously evaluated. The containment high range radiation monitoring system provides a monitoring function only, existing plant response is unal tered. With respect to the isolation of the containment vent and purge valves upon drywell high radiation, the safety function of these valves and their isolation setpoints of high drywell pressure and low-low reactor water level are unchanged.
Isolation of these valves upon drywell high radiation provides greater assurance that releases are within acceptable limits and does not affect any plant safety systems other than containment vent and purge valves.
2.
Create the possibility of a new or different kind of accident from any accident previously evaluated. The containment high range radiation monitoring system provides a monitoring function only, existing plant response is unaltered.
Isolation of the containment vent and purge valves upon drywell high radiation will be in addition and subsequent to the existing isolation signals.
It will not alter the initial plant response to a LOCA, but rather provide greater assurance that releases are within acceptable limits.
3.
Involve a significant reduction in the margin of safety. The containment high range monitoring system provides a monitoring function only, existing plant response is unaltered.
Isolation of the drywell vent and purge valves upon drywell high radiation will enhance the margin of safety by providing greater assurance that releases are within acceptable limits.
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