ML20210U230
| ML20210U230 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 05/28/1986 |
| From: | Donohew J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20210U235 | List: |
| References | |
| NUDOCS 8606020253 | |
| Download: ML20210U230 (4) | |
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7 UNITED STATES f-f NUCLEAR REGULATORY COMMISSION 3,.
g W ASHINGTON, D. C. 20565 e
GPU NilCLEAR CORPORATION AND JERSEY CENTRAL POWER _ & LIGHT COMPANY DnCKET NO. 50-719 0YSTER CREEK NUCLEAR GENERATING STATION AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No.103 License No. DPR-16 1.
The Nuclear Reaulatory Commission (the Comission) has found that:
A.
The application for amendment by GPU Nuclear Corporation and Jersey Central Power and Light Company (the licensees) dated January 30, 1986, complies with the standards and recuire-ments of the Atomic Energy Act of 1954, as amended (the Act),
and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health 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 t
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Coninission's regulations and all applicable requirements have been satisfied.
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Accordingly, the 11 tense is amended by chances to the Technical Specifications ss indicated in the attachinent to this ';icense amendment and ' Paragraph 2.C.f 2) of Provisional liperating Lic'ense No. DP9-16 is bereby.3manded to read as foll6w3:
(2) T&chnical Specifications The Techn'ical Specificati.ons conthined in Apcendices A and B, as revised throbgh Amendment No.103, are hereby incorporated in the license, GPU Kuclear Corporatirn shcll operate the facility in accordance with the Technical Specifications.
I 3.
This license amendnient is effective as of the date of its issuance.
FOR THE NilCLEAR RErd'LATORY CC/WIS$f0N k
' tono ew, r.,
oject Nansper
\\ BWR Pro.iect Of rectorate 11 Division of SMR Licensing
Attachment:
Chances to the Technical Specifications i
Date of issuance:
ltay 28.'1966.
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ATTACHMENT TO LICENSE AMENDMENT NO.103 PROVISIONAL OPERATING LICENSE NO. DPR-16 DOCKET NO. 50-219 Revise Appendix A Technical Specifications by removing the pages identified below and insertino the attached pages. The revised pages are identified by the captioned amendment number and contain vertical lines indicating the area of change.
REMOVE INSERT 3.5-4 3.5-4 b
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3.5-4 3.
With one standby gas treatment system circuit inoperable:
a.
During Power Operation:
1.
Demonstrate the operability of the other standby gas treatment system circuit within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> unless significant painting, fire, or chemical release has taken place in the reactor building within the previous 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
In this event, demonstration of operability shall take place within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of the expiration of the 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> period, and 2.
Continue to demonstrate the operability of the standby gas treatment system circuit once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> until the inoperable standby gas treatment circuit is returned to operable status.
3.
Restore the inoperable standby gas treatment circuit to operable status within 7 days or be subcritical with reactor coolant temperature less than 212*F within the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
b.
During Refueling:
1.
Demonstrate the operability of the redundant standby gas freatment system within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> unless significant painting, fire, or chemical release has taken place in the reactor building within the previous 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
In this event, demonstration of operability shall take place within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of the expiration of the 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> period, and 2.
Continue to demonstrate the operability of the redundant standby gas treatment system once per 7 days until the inoperable system is returned to operable status.
3.
Restore the inoperable standby gas treatment syste:n to operable status within 30 days or cease all spent fuel handling, core alterations or operation that could reduce the shutdown margin (excluding reactor coolant temperature changes).
4.
If Specifications 3.5.B.2 and 3.5.B.3 are not met, reactor shutdown shall be initiated and the reactor shall be in the cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and the condition of Specification 3.5.B.1 shall be met.
Bases:
Specifications are placed on the operating status of the containment systems to assure their availability to control the release of any radioactive materials from irradiated fuel in the event of an accident condition. The primary containment system (1) provides a barrier against uncontrolled release of fission products to the environs in the event of a break in the reactor coolant systems.
Whdnever the reactor coolant water temperature is above 212*F, failure of the reactor coolant system would cause rapid expulsion of the coolant from the reactor with an associated pressure rise in the primary containment.
Primary containment is required, therefore, to contain the thermal energy of the expelled coolant Amendment No. 14, 74, 103
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