ML20057A146
| ML20057A146 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 08/30/1993 |
| From: | Boyle M Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20057A147 | List: |
| References | |
| NUDOCS 9309130114 | |
| Download: ML20057A146 (5) | |
Text
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j NUCLEAR REGULATORY COMMISSION 2
WASMNGTON, D.C. N0001 g
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PUBLIC SERVICE ELECTRIC & GAS COMPANY j
ATLANTIC CITY ELECTRIC COMPANY I
DOCKET NO. 50-354 l
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HOPE CREEK GENERATING STATION f
AMENDMENT TO FACILITY OPERATING LICENSE j
l Amendment No. 58 License No. NPF-57 l
1 1.
The Nuclear Regulatory Comission (the Commission or the NRC) has found i
j that:
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A.
The application for amend. ment filed by the Public Service Electric &
Gas Company (PSE&G) dated April 23, 1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as j
amended (the Act), and the Commission's rules and regulations set 1
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 j
Commission; i
C.
There is reasonable assurance:
(1) that the activities authorized l
by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be i
conducted in compliance with the Commission's regehtions set forth in 10 CFR Chapter I; 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 i
E.
The issuance of this an.endment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
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 Facility Operating License No. NPF-57 is hereby amended to read as follows:
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 58
, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into the license.
PSE&G shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
9309130114 930830 PDR ADOCK 05000354c p
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' 3.
The license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION P
Michael L. Bo e, Acting Directar Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: August 30, 1993 1
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1 ATTACHMENT TO LICENSE AMENDMENT NO. SR FACILITY OPERATING LICENSE NO. NPF-57 DOCKET NO. 50-354 Replace the following page of the Appendix "A" Technical Specifications with the attached page.
The revised page is identified by Amendment number and contain vertical lines indicating the area of change. Overleaf page provided to maintain document completeness.*
Remove Insert 3/4 11-17 3/4 11-17*
3/4 11-18 3/4 11-18 l
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RADI0 ACTIVE EFFLUENTS MAIN CONDFNSER LIMITING CONDITION FOR OPERATION 3.11.2.7 The radioactivity rate of noble gases measured at the escombiner after-condenser discharge shall be liaf ted to less than or equal to 330 milli-curies /sec after 30 minute decay.
APPLICA8ILITY: OPERATIONAL CONDITIONS 1, 2* and 3*.
ACTION:
With the radioactivity rate of noble gases at the recombiner after-condenser discharge exceeding 330 millicuries /sec after 30 minute decay, restore the radioactivity ate to within its limit within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STAND 8Y within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.11.2.7.1 The radioactivity rate of noble gases at the recombiner after-condenser discharge shall be continuously monitored in accordance with Speciff-cation 3.3.7.1.
4.11.2.7.2 The radioactivity rate of noble gases from the recombiner after-condenser discharge shall be determined to be within the Ifaits of Specifica-tion 3.11.2.7 at the following frequencies by performing an isotopic analysis of a representative sample of gases taken near the discharge of the main con-denser air ejector:
a.
At least once per 31 days, b.
Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> following an increase, as indicated by the Offgas Radioactivity Monitor, of greater than 505, after factoring out increases due to changes in THERpmL POWER 1evel, in the nominal staaey-state fission gas release from the primary coolant.
The provisions of Specification 4.0.4 are not applicable.
c.
"When the main condenser air ejector is in operation..
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HOPE CREEK 3/4 11-17 I
RADI0 ACTIVE EFFLUENTS VENTING OR PURGING LIMITING CONDITION FOR OPERATION 3.11.2.8 VENTING or PURGING of the Mark I containment drywell shall be through either the reactor building ventilation system or the filtration, recirculation and ventilation system.*
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APPLICABILITY: Whenever the containment is vented or purged.
ACTION:
a.
With the requirements of the above specification not satisfied, suspend all VENTING and PURGING of the drywell.
b.
The provisions of Specification 3.0.3 are not applicable.
l SURVEILLANCE REQUIREMENTS l
4.11.2.8 The containment shall be determined to be aligned for VENTING or l
PURGING through the reactor building ventilation system, the filtration, recirculation and ventilation system, or the hardened torus vent within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> prior to start of and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during V" TING or PURGING of the drywell.
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i Following Type A Integrated Leakage Rate Testing, the Mark I containment drywell may be vented through the hardened torus vent.
l HOPE CREEK 3/4 11-18 Amendment No. 58
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