ML20064N146
| ML20064N146 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 02/28/1994 |
| From: | Chris Miller Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20064N149 | List: |
| References | |
| NUDOCS 9403290187 | |
| Download: ML20064N146 (3) | |
Text
- p %,,b5, UNITED STATES f s.{ %[ gj NUCLEAR REGULATORY COMMISSION gg WASHINGTON, D.C. 20666-0001 gv...../
PUBLIC SERVICE ELECTRIC & GAS COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-354 HOPE CREEK GENERATING STATION AMENDMENT TO FACILITY OPERATIM UCENSE Amendment No. 66 License No. NPF-57 1.
The Nuclear Regulatory Comission (the Comission or the NRC) has found that:
A.
The application for amendment filed by the Public Service Electric &
Gas Company (PSE&G) dated August 30, 1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), 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 provisions of the Act, and the rules and regulations of the Comission; 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 set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the comon 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 Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 66, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into the licenso.
PSE&G shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
9403290107 940228 PDR ADOCK 05000354 P
1.
3.
The license amendment is effective as of its date of issuance 'and shall be implemented within 60 day days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Y
k Charles L. Miller, Director Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: February 28, 1994 l
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ATTACHMENT TO LICENSE AMENDMENT NO. 66 FACILITY OPERATING LICENSE N0. NPF-57 DOCKET N0. 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 pages provided to maintain document completeness.*
Remove Insert 3/4 8-29 3/4 8-29 3/4 8-30*
3/4 11-17 3/4 11-17 3/4 11-18*
1
a TABLE 3.8.4.1-1 (Continued) d PRIHARY CONTAINMENT PENE ION CONDUCTOR OVERCURRENT PROTECT 1,u DEVICES
- 2. 480-VOLT MOLDED CASE CIRCUIT BREAKERS (Continued)
CIRCUIT SYSTEMS OR BREAKER No. LOCATION TYPES EQUIPMENT POWERED 52-253064 10B253 IM HFB150 Reactor Vessel Head Vent to TM HFB150 Steam Line 1BB-HV-F005 52-263011 10B263 IM HFB150 Reactor Vessel Head Vent TM HFB150 Outboard Isolation 1BB-HV-F002 52-263012*
10B263 IM HFB150 Recirc Pump Motor Holst 1BH201 TM HFB150 Disconnect Switch 1BS204 j
52-263042*
10B263 IM HFB150 Mai7 Steam Relief Valve Holst TM HFB150 10H;02 Diaconnect Switch 10S207 52-263054 10B263 IM HFB150 RWCU Suction from Recirc TM HFB150 Loop A 1BG-HV-F100 52-263081 10B263 IM HFBISO RWCU Suction from RPV Drain TM HFB150 Valve 1BG-HV-FlOl 52-263082 10B263 IM HFB150 RWCU Suction Valve 1BG-HV-F102 TM HFB150 52-263083 10B263 IM HFB150 RWCU Suction from Recirc Loop TM HFB150 B Valve 1BG-HV-F106 52-264053 10B264 IM HFB150 Recirc Pump A Discharge Valve TM HFB150 1BB-HV-F031A 52-264062 10B264 IM HFB150 Feedwater Inlet B Shutoff TM HFB150 Valve IAE-HV-F011B 52-264071 10B264 IM HFB150 Reactor Recirc Pump 1AP201 TM HFB150 Space Heater 1AS220 52-264072 10B264 IM HFB150 Reactor Recirc Pump 1BP201 TH HFB150 Space Heater 1BS220 52-264083 10B264 IM HFB150 Recirc Pump.A Suction Valve TM HFB150 1BB-HV-F023A These breakers shall be administratively maintained open in OPERATIONAL CONDITIONS 1, 2 and 3 and are not required to be tested.
HOPE CREEK 3/4 8-29 Amendment No. 66 l+
ELECTRICAL POWER SYSTEMS MOTOR OPERATED VALVES - THERMAL OVERLOAD PROTECTION (8YPASSED)
LIMITING CONDITION FOR OPERATION 3.8.4.2 The theru.al overload protection bypass circuit of each motor operated valve (MOV) shown in Table 3.8.4.2-1 shall be OPERABLE.
APPLICABILITY:
Whenever the MOV is required to be OPERABLE.
ACTION:
With the tirermal overload protection bypass circuit for one or more of the above required MOVs inoperable, restore the inoperable thermal overload pro-tection bypass circuit (s) to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or declare the affected MOV(s) inoperable and apply the appropriate ACTION statement (s) for the affected system (s).
SURVEILLANCE REQUIREMENTS 4.8.4.2.1 The thermal overload protection bypass circuit for each of the above required MOVs shall be demonstrated OPERABLE:
a.
At least once per 18 months by the performance of a CHANNEL FUNCTIONAL TEST for:
1.
Those thermal overload protection devices which are normally in force during plant operation and bypassed only under accident conditions.
2.
A representative sample of at least 25% of those thermal overload protection devices which are bypassed continuously and temporarily placed in force only when the MOVs are undergoing periodic or maintenance testing, such that the bypass circuitry for each thermal overload protection device of this type is tested at least once per 6 years.
3.
A representative sample of at least 25% of those thermal over-load protection devices which are in force during normal manual (momentary push button contact) MOV operation and bypassed dur-ing remote manual (push button held depressed) MOV operation, such that the bypass circuitry for each thermal overload pro-tection device of this type is tested at least once per 6 years.
b.
Following maintenance on the motor starter.
4.8.4.2.2 The thermal overload protection for the above required MOVs which are continuously bypassed and temporarily placed in force only when the MOV is under-going periodic or maintenance testing shall be verified to bs continuously bypassed following such testing.
HOPE CREEK 3/4 8-30
a RADIOACTIVE EFFLUENTS J
MAIN CONDENSER LIMITING CONDITION FOR OPERATION
......................n.......................................................
3.11.2.7 The radioactivity rate of noble gases measured at the recombiner after-condenser discharge shall be limited to less than or equal to 3.30 E+5 microcuries/see after 30 minute decay.
APPLICABILITY: OPERATIONAL CONDITIONS 1, 2* and 3*.
ACTION:
With the radioactivity rate of noble gases at the recombinar after-condenser discharge exceeding 3.30 E+5 microcuties/see after 30 minute decay, restore l
the radioactivity rate 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 SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
l SURVEILLANCE REQUIREMENTS 4.11.2.7.1 The radicactivity rate of noble gases at the recombiner after-condenser discharge shall be continuously monitored in accordance with Specification 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 limits of Specification 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 condenser 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 Pretreatment Radiation Monitor, of greater than 50%, after factoring l out increases due to changes in THERMAL POWER level, in the nominal steady-state fission gas release from the primary coolant.
c.
The provisions of Specification 4.0.4 are not applicable.
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- When the main condenser air ejector is in operation.
l HOPE CREEK 3/4 11-17 Amendment No. 66 l
]
RADI0 ACTIVE EFFLUENTS VENTIM OR PUMIM LIMITIM COMITION FOR OPERATION 3.11.2.8 VDITIM or PURGIM of the Mark I containment drm11 shall be through either the reactor building ventilation system or the filtration, recirculation and ventilation systee.*
1 APPLICABILITY: Whenever the containment is vented or purged.
ACTION:
a.
With the requirements of the above sv.it;ation not satisfied, suspend all VENTIM and PURGIM of tb drywell.
b.
The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.8 The containment shall be deterairmi to be aligned for VENTIM or PURGIM 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 VENTIM or-PURSIM of the drywell.
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l l
Following Type A Integrated Leakage Rate Testing, the Mark I containmant drywell may be vented through the hardened torus vent.
HOPE CREEK 3/4 11-18 Amendment No. 58 me n,m
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