ML20092M046
| ML20092M046 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 09/25/1995 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Public Service Electric & Gas Co, Atlantic City Electric Co |
| Shared Package | |
| ML20092M048 | List: |
| References | |
| NPF-57-A-082 NUDOCS 9509280307 | |
| Download: ML20092M046 (9) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION f
WASHINGTON, D.C. 20666-0001
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- p PUBLIC SERVICE ELECTRIC & GAS COMPANY ATLANTIC CITY ELECTRIC COMPANY
@CKET NO. 50-354 HOPE CREEK GENERATING STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 82 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 September 29, 1994, 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:
(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 Commission's regulations set forth in 10 CFR Chapter I; 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.
4 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. 82, 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.
9509280307 950925 PDR ADOCK 05000354 p
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. 3.
The license amendment is effective as of its date of issuance, to be implemented within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION
(
Jo n. Stolz, Direct oject Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: September 25, 1995
ATTACHMENT TO LICENSE AMENDMENT NO. 82 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.
Remove Insert viii viii xviii xviii 3/4 3-68 3/4 3-68 3/4 3-69 thru 3/4 3-73 3/4 3-69 thru 3/4 3-73 B 3/4 3-4 B 3/4 3-4 B 3/4 3-5 B 3/4 3-5 4
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a INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION R&faR Table 3.3.5-1 Reactor Core Isolation Cooling System.,
Actuation Instrumentation.
3/4 3-52 Table 3.3.5-2 Reactor Core Isolation Cooling System Actuation Instrumentation Setpoints....
3/4 3-54 Table 4.3.5.1-1 Reactor Core Isolation Cooling System Actuation Instrumentation Surveillance Requirements 3/4 3-55 3/4.3.6 CONTROL ROD BLOCK INSTRUMENTATION 3/4 3-56 Table 3.3.6-1 Control Rod Block Instrumentation.
3/4 3-57 Table 3.3.6-2 Control Rod Block Instrumentation Setpoints.
3/4 3-59 Table 4.3.6-1 Control Rod Block' Instrumentation Surveillance Requirements.
3/4 3-60 3/4.3.7 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation.
3/4 3-62 Table 3.3.7.1-1 Radiation Monitoring Instrumentation 3/4 3-63 Table 4.3.7.1-1 Radiation Monitoring Instrumentation Surveillance Requirements 3/4 3-66 i
Remote Shutdown Monitoring Instrumentation and Controls 3/4 3-74 s
HOPE CREEK viii Amendment No.82 l
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INDEX BASES a
SECTION P,8EE INSTRUMENTATION (Continued)
I Remote Shutdown Monitoring Instrumentation and controls.
B 3/4 3-5 Accident Monitoring Instrumentation B 3/4 3-5' Source Range Monitors B 3/4 3-5
. Traversing In-Core-Probe System B 3/4 3..
Radioactive Liquid Effluent Monitoring Instrumentation B 3/4 3-6 Radioactive Gaseous Effluent Monitoring Instrumentation B 3/4 3-6 E3/4.3.8 DELETED.
B 3/4 3-7 3/4.3.9 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION B 3/4 3-7 Figure B3/4 3-1 Reactor Vessel Water Level.
B 3/4 3-8 e
- 3/4.4 REACTOR COOLANT SYSTEM 1
'l 3/4.4.1 RECIRCULATION SYSTEM.
B 3/4 4-1 f
3/4.4.2 SAFETY / RELIEF VALVES B 3/4 4-la f
3/4.4.3 -REACTOR COOLANT SYSTEM LEAKAGE i
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Leakage Detection Systems B 3/4 4-3 l
Operational Leakage B 3/4 4-3 l
3/4.4.4 CHEMISTRY B 3/4 4-3 s
B 3/4 4-4
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3/4.4.5 SPECIFIC ACTIVITY 3/4.4.6 PRESSURE / TEMPERATURE LIMITS B 3/4 4-5 i
-Table B3/4.4.6-1 Reactor vessel Toughness B 3/4'4-7 Fi ure B3/4.4.6-1 Fast Neutron Fluence (E>1Mev) at (1/4)T as a l
Function of Service life.
B 3/4 4-8 l
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. Amendment. No.82 l
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INSTRtJMENTATION i
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NOPE CREEK 3/4 3 68 Amendment No.82 4
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i PAGES 3/4 3-69 THRU 3/4 3-73 ARE DELETED
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1 HOPE CREEK 3/4 3-69 thru 3/4 3-73 Amendment No. 82 l
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INSTRUMENTATION BASES l
3/4.3.5 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION 1
The reactor core isolation cooling system actuation instrumentation is provided tb initiate actions to assure adequate core cooling in the event of reactor isolation from.its primary heat sink and the loss of feedwater flow to
- the reactor vessel.
Specified surveillance intervals and surveillance and maintenance outage times have been determined in accordance with NEDC-30936P-A, "BWR Owners' Group Techni, cal Specification Improvement Methodology (With Demonstration for BWR ECCS Actuation Instrumentation)," Parts 1 and 2 and GENE-770-06-2-A.
" Addendum to Bases for Changes to Surveillance Test Intervals and Allowed Out-of-Service Times for Selected Instrumentation Technical Specifications." The safety evaluation reports documenting NRC approval of NEDC-30936P-A and GENE-770-06-2-A are contained in letters to D.
N. Grace from A. C. Thadani dated December 9, 1988 (Part 1), D. N. Grace to C.
E. Rossi dated December 9,'1988 (Part 2), and G. J. Beck from C. E. Rossi dated September 13, 1991.
Operation with a trip set less conservative than its Trip setpoint but within its specified Allowable Value is acceptable on the basis that the difference between each Trip Setpoint and'the Allowable Value is an allowance for instrument drift specifically allocated for each trip in the safety analyses.
3 /4. 3. 6 CONTROL ROD BLOCK INSTRUMENTATION e
The control rod block functions are provided consistent with the requirements of the specifications in Section 3/4.1.4, Control Rod Program Controls and Section 3/4.2 Power Distribution Limits and Section 3/4.3 Instrumentation. The trip logic is arranged so that a trip in any one of the inputs will result in a control rod block.
Operation with a trip set less conservative than its Trip setpoint but within its specified Allowable value is acceptable on the basis that the difference between each Trip setpoint and the Allowable Value is an allowance for instrument drift specifically allocated for each trip in the safety analyses.
3/4.3.7 MONITORING INSTRUMENTATION 3/4.3.7.1 RADIATION MONITORING INSTRUMENTATION The OPERABILITY of the radiation monitoring instrumentation ensures that; (1) the radfation levels are continually measured in the areas served by the individual channels, and (2) the alarm or automatic action is initiated when the radiation level trip setpoint is exceeded; and (3) sufficient information is available on selected plant parameters to monitor and assess these variables following an accident. This capability is consistent with 10 CFR Part 50, Appendix A, General Design Criteria 19, 41, 60, 61, 63 and 64.
3/4.3.7.2 DELETED 3/4.3.7.3 DELETED HOPE CREEK B 3/4 3-4 Amendment No.82 l
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INSTRUMENTATION i
BASES a
MONITORING INSTRUMENTATION (Continued) 3/4.3.7.4 REMOTE SHtfrDOWN MONITORING INSTRUMENTATION AND CONTROLS B
i The. OPERABILITY of the remote shutdown monitoring instrumentation and con-Ltrols ensures that sufficient capability is available to permit shutdown and maintenance of HOT SNUTDOWN of the unit from locations outside of the control room.
This capability is required in the event control room habitability is lost and'is consistent with General Design Criteria 19 of 10 CFR 50.
3 3/4.3.7.5 ACCIDENT MONITOPING IN:sikiiriiGiTATION l
The OPERABILITY of the accident monitoring instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess important variables following an accident. This capability is consistent with the recommendations of. Regulatory Guide 1.97, " Instrumentation l-for Light Water Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an Accident," December 1980 and NUREG-0737, " Clarification of TMI: Action Plan Requirements," November 1980.
t 3/4.3.7.6 SOURCE RANGE MONITORS The source range monitors provide the operator with information of the j
status of the neutron level in the core at very low power levels during startup and shutdown. At these power levels, reactivity additions shall not be made without this flux level information available to the operator.
For a discussion of SPIRAL RELOAD and SPIRAL UNLOAD and the associated flux monitoring requirements, see Technical Specification Bases Section 3/4.9.2.
When the intermediate range monitors are on scale, adequate information is available without the SRMs and they can be retracted.
3/4.3.7.7 TRAVERSING IN-CORE PROBE SYSTEM The OPERABILITY of the traversing in-core probe system with the specified
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minimum complement of equipment ensures that the measurements obtained from use of this equipment accurately represent the spatial neutron flux distribution of the reactor core.
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HOPE CREEK-B 3/4 3-5 Amendment No. 82 l
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