ML20247M008
| ML20247M008 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 05/23/1989 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | GPU Nuclear Corp, Jersey Central Power & Light Co |
| Shared Package | |
| ML20247M014 | List: |
| References | |
| GL-84-011, DPR-16-A-133 NUDOCS 8906020324 | |
| Download: ML20247M008 (4) | |
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UNITED STATES -
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NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D C.20555 y
GPU NUCLEAR' CORPORATION AND JERSEY CENTRAL ~ POWER'& LIGHT COMPANY' 4
DOCKET NO. 50-219-OYSTER' CREEK NUCLEAR GENERATING STATION AMENDMENT-T0' PROVISIONAL OPERATING LICENSE'
- Amendment No..133 License No. DPR-16
- 1..
The Nuclear Regulatory Commission (the Comission) has found that:
.A.
The. application for amendment-by GPU Nuclear Corporation, et al.,
(thelicensee),datedMarch 17, 1987 complies with the standards and' '
. requirements of the Atomic Energy Act of '1954, as -amended- (the Act),
3:
and the Comission's rules and regulations set forth in 10 CFR
' Chapter I; B.
The' facility will ' operate in conformity with the application, the provisiens of the Act, and the rules-and regulations of the
-Commission; C.
There is reasonable assurance (1) that the' activities authorized.
by this~ amendment can be conducted without endangering the health L- ;
and' safety of the public, and (ii) that.such activities will be conducted in compliance with the Comission's regulations; D.
- The-issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The' issuance of this amendment is'in accordance with 10 CFR Part 51 1
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of the Comission's regulations and all. applicable requirements have been satisfied.
8 G906020324 890523
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2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Provisional Operating License No. DPR-16 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.133, are hereby incorporated in the license. GPU Nuclear Corporation shall operate the facility in 4
accordance with the Technical Specifications.
l 3.
This license amendment is effective as of the date of issuance, to be implemented within 30 days of issuance.
l FORTHENUCLEARREGL)ATORYCOMMISSION 1
oh i' F. Stolz, 'irecto Pr ject Directorate Di ision of Reactor ojects I/II fice of Nuclear Reactor Regulation
Attachment:
l Changes to the Technical l
Specifications Date of Issuance: May 23, 1989 1
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ATTACHMENT TO LICENSE AMENDHENT fl0.133 PROVISIONAL OPERATING LICENSE N0. DPR-16 DOCKET NO. 50-219 l
Replace the following page'of the Appendix A Technical Specifications with the enclosed page as indicated. The revised page is identified by amendment number and contains vertical lines indicating the areas of change.
Remove Insert Page.3.3.2 Page 3.3.2 e
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Reactor Coolant System Leaka'ge 1.
Reactor lcoolantsystemleakageshallbelimitedto:
a.
5 gpm unidentified leakage b.- 25 gpm total (identified and unidentified) c.
2 gpm increase in unidentified leakage rate within any 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period while operating at steady state power 2.
With the reactnr coolant system leakage greater than the limits in 3.3.D.1.a or b above, reduce the leakage rate to within the acceptable-limits-within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. or place the reactor in the shutdown condition-within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and be in the cold shutdown. condition within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />..
3.
With any reactor coolant leakage greater than the limit in-3.3.D.1.c above, identify the source of leakage within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />,
~or be in the shutdown condition within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and be in the cold shutdownJcondition within'the~following 24. hours.-
4.
For determination of unidentified leakage, the primary containment sump flow monitoring system shall be operable'except as specified below; a.
With the primary containment sump flow integrator inoperable:
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1.
Restore it to operable status within 7 days.
2.
Calculate the unidentified leakage rate utilizing an 1
acceptable alternate means as specified in plant procedures.
b.
If Specification 3.3.D.4a cannot be met, place the reactor in the shutdown condition within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
eauipment-drain tank monitoring system shall' primary containment
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For determination of identified leakage, the 5.
be operable except as specified below:
4.
With the primary containment eauipment drain tank monitoring system inoperable:
1.
Restore it to operable status within 7 days.
2.
Calculate the identified leakage rate utilizing an acceptable alternate means as specified in plant l
procedures.
b.
If' Specification 3.3.0.5.a cannot be met, place the reactor in the shutdown condition within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
OYSTER CREEK 3.3-2 I
Amendment No. 133 1
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