ML20056F782

From kanterella
Jump to navigation Jump to search
Amend 142 to License DPR-36,deleting Surveillance Requirements for Environ Monitors from TS
ML20056F782
Person / Time
Site: Maine Yankee
Issue date: 08/23/1993
From: Butler W
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20056F781 List:
References
NUDOCS 9308310063
Download: ML20056F782 (4)


Text

a marag g'o, UNITED STATES

+

I' ) y ~j NUCLEAR REGULATORY COMMISSION E

W ASHINGTON. D. C. 20555 o

MAINE YANKEE ATOMIC POWER COMPANY DOCKET NO. 50-309 MAINE YANKEE ATOMIC POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 142 License No. DPR-36 1.

The Nuclear Regulatory Commission (the Commission or the NRC) has found that:

A.

The application for amendment filed by the Maine Yankee Atomic Power Company (the licensee) dated May 12, 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:

(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; 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 Specifica-tions as indicated in the attachment to this license amendment, and paragraph 2.B(6)(b) of Facility Operating License No. DPR-36 is hereby I

amended to read as follows:

i i

l 1

i 9308310063 930823 PDR ADOCK 05000309 P

PDR

6 :

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.142, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of its date of issuance and shall be implemented within 30 days.

FOR THE NUCLEAR REGULATORY COMMISSION v5 Walter R. Butler, Director Project Directorate I-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

August 23, 1993 l

l

=._

I I

ATTACHMENT TO LICENSE AMENDMENT NO. 142 4

FACILITY OPERATING LICENSE NO. OPR-36 DOCKET NO. 50-309 4

Replace the following page of the Appendix A Technical Specifications with the attached page. The revised page is identified by Amendment number and l

contains a vertical line indicating the area of change.

Remove Insert

{

4.1-10 4.1-10 i

i I

I l

i t

i l

i i

i l

1 I

i

Table 4.1-3 Minimum Frequencies for Checks, Calibrations and Testing of Miscellaneous Instrumentation and Controls Channel Description Surveillance Frequency Surveillance Method Function

l. Reed Switch Rod Check S

Compare rod position indication from the Reed Switch Position Indication Position Indication System with that of the Pulse System Counting Position Indication System whenever the reactor is critical and the plant computer is available.

2. Pulse Counting Rod Check S

Compare rod position indication from the Pulse Counting Position Indication Position Indication System with that of the Reed Switch System Position Indication System whenever the reactor is critical and the plant computer is available.

3. Radiation Area
a. Check D"'

a.

Internal test signals used to check instrument Monitors operation.

b. Functional M")

b.

Expose the detector with either an internal or an Test external radiation source or an electronic signal to verify instrument operation.

c. Calibrate R

c.

Exposure to known radiation source.

4. Emergency Plant
a. Check D")

a.

Internal radiation source provides continuous signal Radiation verifying instrument operations.

Containment High Range

b. Calibrate R

b.

Exposure to known radiation source.

5. Deleted 6.

Pressurizer

a. Check S("

a.

Comparison of independent level readings.

Level

b. Calibrate R

b.

Known differential pressure applied to sensor.

Amendment 81,86,94, 133, 142 4.1-10

., - -. - - _,