ML20073A112

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Amend 92 to License DPR-22,revising Requirements of TS 4.6.E.1.a to Require Valves to Be Tested in Accordance W/Section XI Inservice Testing Requirements of ASME Code
ML20073A112
Person / Time
Site: Monticello Xcel Energy icon.png
Issue date: 09/15/1994
From: Marsh L
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20073A116 List:
References
NUDOCS 9409200133
Download: ML20073A112 (4)


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T UNITED STATES

NUCLEAR REGULATORY COMMISSION e

WASHINGTON, D.C. 2055M)001 NORTHERN STATES POWER COMPANY DOCKET NO. 50-263 MONTICELLO NUCLEAR GENERATING PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 92

-License No. DPR-22 1.

The Nuclear Regulatory Commission-(the Commission) has found that:

A.

The application for amendment by Northern States Power Company (the-licensee) dated January 3, 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; 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 Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-22 is hereby amended to' read as follows:

4

-9409200133 940915 PDR-ADOCK 05000263 p

PDR a

_2 Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 92, 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 the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Ledyard B. Marsh, Director Project Directorate III-I Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

September 15, 1994

ATTACHMENT TO LICENSE AMENDMENT NO. 92 FACILITY OPERATING llCENSE NO. DPR-22 DOCKET NO. 50-263 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.

REMOVE INSERT 127 127 t

3.0 LIMITING CONDITIONS mR' OPERATION 4.0 SURVEILLANCE REQUIREMENTS E.. Safety / Relief Valves E.

Safety / Relief Valves 1.

During power operating conditions and 1.

a.

Safety / relief valves shall be tested whenever reactor coolant pressure is or replaced each refueling outage greater than 110 psig.and temperature is pursuant to Specification 4.15.8.

greater than. 345'F:

The nominal self-actuation setpoints a.

The safety valve function (self-actuation) _of seven safety / relief b.

At least two of the safety / relief valves shall be operable.

valves shall be disassembled and inspected each refueling outage.

b.

The solenoid activated relief function (Automatic Pressure Relief) c.

The integrity of the safety / relief-shall be operable'as required by valve bellows shall be continuously Specification 3.5.E.

monitored.

c.

The low-Low Set Function for three d.

The operability of the bellows.

non-Automatic Pressure Relief Valves monitoring system shall be shall be operable.as required by demonstrated at-least once every

~

Specification 3.2.H.

three-months.

2.

If Specification 3.6.E.1.a is'not met, 2.

Low-Low Set Logic surveillance shall be initiate an orderly shutdown and have performed in accordance with Table 4.2.1.

reactor coolant pressure 'and temperature reduced to 110 psig or less and '345'F or less within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

4 3.4/4.6 127-Amendment No. 36, (E, 76, 92

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