ML20094D389
| ML20094D389 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 10/31/1995 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Public Service Electric & Gas Co, Atlantic City Electric Co |
| Shared Package | |
| ML20094D391 | List: |
| References | |
| NPF-57-A-086 NUDOCS 9511030348 | |
| Download: ML20094D389 (4) | |
Text
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UNITED STATES s
j NUCLEAR REGULATORY COMMISSION f
WASHINGTON, D.C. 20086 4001 i
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PUBLIC SERVICE ELECTRIC & GAS COMPANY ATLANTIC CITY ELECTRIC COMPANY l
DOCKET NO. 50-354 HOPE CREEK GENERATING STATION AMENDMENT TO FACILITY OPERATING LICENSE j
Amendment No. 86 i
License No. NPF-57 l
1.
The Nuclear Regulatory Commission (the Comission or the NRC) has found i
that:
A.
The application for amendment filed by the Public Service Electric &
f Gas Company (PSE&G) dated November 28, 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 J
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 i
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 comon defense and security or to the health and safety of the public; and d
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:
9511030348 951031 PDR ADOCK 05000354 P
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, (2) Technical Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 86, 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.
3.
The license amendment is effective as of its date of issuance, to be implemented within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION
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John F. Stolz, D rec r
Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
October 31, 1995 A
k ATTACHMENT TO LICENSE AMENDMENT N0.86 l
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 contains vertical lines indicating the area of change.
Remove Insert 3/4 3-59 3/4 3-59
____.m
TABLE 3.3.6-2 CONTROL ROD BLOCK INSTRUMENTATION SETPOINTS 5
TRIP FUNCTION TRIP SETPOINT ALLOWABLE VALUE
- 1. ROD BLOCK MONITOR
- a. Upscale i.
Flow Biased s 0.66 (w-Aw) + 40%"
s 0.66 (w-Aw) + 43%*
ii. High Flow Clamped s 106%
s 109%
b.
Inoperative NA NA
- c. Downscale a 5% of RATED THERMAL POWER a 3% of RATED THERMAL POWER
- 2. APRM a.
Flow Biased Neutron Flux - Upscale s 0.66(w-Aw) + 42%*
s 0.66 (w-Aw) + 45t' b.
Inoperative NA NA
- c. Downscale a 4% of RATED THERMAL POWER a 3% of RATED THERMAL POWER
- d. Neutron Flux - Upscale, Startup s 12% of RATED THERMAL POWER s 14% of RATED THERMAL POWER 3.
SOURCE RANGE MONITORS
- a. Detector not full in NA NA 5
5
- b. Upscale s 1.0 x 10 cps s 1.6 x 10 cps c.
Inoperative NA NA
- d. Downscale a 3 cps a 1.8 cps 4.
INTERMEDIATE RANGE MONITORS a.
Detector not full in NA NA
- b. Upscale s 108/125 divisions of s 110/125 divisions of full scale full scale c.
Inoperative NA NA
- d. Downscale a 5/125 divisions of 3/125 divisions of a
full scale full scale 5.
- a. Water Level-High (Float Switch) 109'1" (North Volume) 109'3" (North Volume) 108'11.5" (South Volume) 109'1.5" (South Volume) 6.
REACTOR COOLANT SYSTEM RECIRCULATION FLOW
- a. Upscale s 111% of rated flow s 114% of rated flow l-b.
Inoperative NA NA
- c. Comparator s 10% flow deviation s lit flow deviation 7.
REACTOR MODE SWITCH SHUTDOWN POSITION NA NA t-The rod block function is varied as a function of recirculation loop flow (w) and Aw which is defined as the difference in indicated drive flow (in percent of drive flow which produces rated core flow) between two loop and single loop operation at the same core flow.
The trip setting of the Average Power Range Monitor Rod Block function must be maintained in accordance with Specification 3.2.2.
HOPE CREEK 3/4 3-59 Amendment No.86 li
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