ML20092D448

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Amend 78 to License NPF-57,revising TS Table 4.3.6-1, Control Rod Block Instrumentation Surveillance Requirements
ML20092D448
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 09/12/1995
From: Stolz J
Office of Nuclear Reactor Regulation
To:
Public Service Electric & Gas Co, Atlantic City Electric Co
Shared Package
ML20092D453 List:
References
NPF-57-A-078 NUDOCS 9509140205
Download: ML20092D448 (4)


Text

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t UNITED STATES 3

,j NUCLEAR REGULATORY COMMISSION 2

WASHINGTON, D.C. 20665-0001

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PUBLIC SERVICE ELECTRIC & GAS COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-354 HOPE CREEK' GENERATING STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 78 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 September 29, 1994, 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 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 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 Comission's regulations and all applicable requirements

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have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical i

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:

1 9509140205 950912 PDR ADOCK 05000354 P.

PDR

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(2) Technical Soecifications and Environmental Protection Pian The Technical Specifications contained in Appendix A, as revised through Amendment No. 78, 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 and shall be implemented within 60 days.

FOR THE NUCLEAR REGULATORY COMMISSION r

J n D Stolz, Director Po et Directorate I-2 D vision of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical 4

Specifications 4

Date of Issuance:

September 12, 1995

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ATTACHMENT TO LICENSE AMENDMENT NO. 78 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 3-60 3/4 3-60 4

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TABLE 4.3.6-1 CONTROL ROD BLOCK INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL OPERATIONAL CHANNEL FUNCTIONAL CHANNEL CONDITIONS FOR WHICH TRIP FUNCTION CHECK TEST CALIBRATION

SURVEILIANCE REOUIRED 1.

ROD BLOCK MONITOR

a. Upscale NA Z"", Q"'

SA 1*

b.

Inoperative NA Z"", Q"'

NA 1*

c. Downscale NA Z"", Q"'

SA 1*

2. APRM a.

Flow Biased Neutron Flux -

Upscale NA S/U",Q SA I

b.

Inoperative NA S/U*,Q NA 1,

2, 5

c. Downscale NA S/U",Q SA 1
d. Neutron Flux - Upscale, Startup NA S/U",Q SA 2,

5 3.

SOURCE RANGE MONITORS

a. Detector not full in NA S/U",W NA 2,

5

b. Upscale NA S/U",W R

2, 5

l c.

Inoperative NA S/U*,W NA 2,

5

d. Downscale NA S/U",W R

2, 5

l 4.

INTERMEDIATE RANGE MONITORS

a. Detector not full in NA S/U",W NA 2,

5

b. Upscale NA S/U",W R

2, 5

l c.

Inoperative NA S/U",W NA 2,

5

d. Downscale NA S/U",W R

2, 5

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5. SCRAM DISCHARGE VOLUME
a. Water Level-High (Float Switch)

NA Q

R 1,

2, 5"

6. REACTOR COOLANT SYSTEM RECIRCULATION FLOW
a. Upscale NA S/U",Q SA 1
b. Inoperative NA S/U",Q NA 1
c. Comparator NA S/U",Q SA 1

7.

REACTOR MODE SWITCH SHUTDOWN POSITION NA R

NA 3,

4 HOPE CREEK 3/4 3-60 Amendment No. N N l

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