ML20056G328
| ML20056G328 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 08/18/1993 |
| From: | Boyle M Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20056G329 | List: |
| References | |
| NUDOCS 9309030004 | |
| Download: ML20056G328 (6) | |
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UNITED STATES i
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NUCLEAR REGULATORY COMMISSION g
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PUBLIC SERVICE ELECTRIC & GAS COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-354
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HOPE CREEK GENERATING STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 57 License No. NPF-57 1.
The Nuclear Regulatory Commission (the Commission or the NRC) has found that:
A.
The application for amendment filed by the Public Service Electric &
Gas Company (PSE&G) dated May 6,1993, complies with the standards and requirements 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:
(1) 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 Commission's regulations 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 E.
The issuance of this amendment 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. 57, 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.
9309030004 930818" PDR ADOCK 05000354
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The license amendment is effective as of its date of issuance and shall be implemented within 60 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION s
i Michael L. Bo le, Acting Director Project Directorate I-2 Division of Reactor Projects - I/II i
Office of Nuclear Reactor Regulation l
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Attachment:
Changes to the Technical Specifications i
Date of Issuance: August 18, 1993 l
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ATTACHMENT TO LICENSE AMENDMENT NO. 57 FACILITY OPERATING LICENSE NO. NPF-57 DOCKET NO. 50-354 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The. revised pages are identified by. Amendment number and contain vertical lines indicating the area of change. Overleaf page provided
.to maintain document completeness.*
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3/4 3-16 3/4 3-16 3/4 3-16a 3/4 3-16a l
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HOPE CREEK 3/4 3-15
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I TABLE 3.3.2-1 (Continued) i l
NOTES i
When handling irradiated fuel in the secondary containment and during CORE
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ALTERATIONS and operations with a potential for draining the reactor vessel.
When any turbine stop valve is greater than 90% open and/or when the key-locked bypass switch is in the Norm position.
Refer to Specification 3.1.5 for applicability.
The hydrogen water chemistry (HWC) system shall not be placed in service I
until reactor power reaches 20% of RATED THERMAL POWER. After reaching 20%
of RATED THERMAL POWER, and prior to operating the HWC system, the normal full power background radiation level and associated trip setpoints may be increased to levels previously measured during full power operation with i
hydrogen injection.
Prior to decreasing below 20% of RATED THERMAL POWER and after the HWC system has been shutoff, the background level and associated setpoint shall be returned to the normal full power values.
If l
a power reduction event occurs so that the reactor power is below 20% of I
l RATED THERMAL POWER without the required setpoint change, control rod motion shall be' suspended (except for scram or other emergency actions) until the necessary setpoint adjustment is made.
(a) A channel may be placed in an inoperable status for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for re-quired surveillance without placing the trip system in the tripped condition provided at least one other OPERABLE channel in the same trip system is monitoring that parameter.
(b) Also trips and isolates the mechanical vacuum pumps.
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(c) Also starts the Filtration, Recirculation and Ventilation System (FRVS).
(d) Refer to Table 3.3.2-1 table notation for the listing of which valves in an actuation group are closed by a particular isolation signal. Refer to Tables 3.6.3-1 and 3.6.5.2-1 for the listing of all valves within an actuation group.
(e) Sensors arranged per valve group, not per trip system.
l (f) Closes only RWCU system isolation valve (s) HV-F001 and HV-F004.
(g) -Requires system steam supply pressure-low coincident with drywell pressure-high to close turbine exhaust vacuum breaker valves.
(h)- Manual isolation closes HV-F008 only, and only following manual or automatic initiation of the RCIC system.
(1) Manual isolation closes HV-F003 and HV-F042 only, and only following manual
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or automatic initiation of the HPCI system.
i l-I HOPE CREEK 3/4 3-16a Amendment No. 57
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