ML20237A111

Amend 163 to License DPR-25,revising TS 4.6.E to Allow one-time Extension of 40-month Surveillance Interval Requirement to Set Pressure Test or Replace MSSVs to Max Intenval of 60 Months

ML20237A111
Person / Time
Site:	Dresden
Issue date:	08/07/1998
From:	Rossbach L NRC (Affiliation Not Assigned)
To:
Shared Package
ML20237A113	List: ML20237A111 ML20237A134
References
NUDOCS 9808130104
Download: ML20237A111 (4)

Text

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UNITED STATES s

j NUCLEAR REGULATORY COMMISSION 2

WASHINGTON, D.C. 20086-0001

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COMMONWEALTH EQ1 SON COMPANY DOCKET NO. 50-249 DRESDEN NUCLEAR POWER STATION. UNIT 3 AMENDMEN's TO FACILITY OPERATING LICENSE Amendment No.163 1

License No. DFR-25 1.

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

i A.

The application for amendment by the Commonwealth Edison Company (the j

licensee) dated May 6,1998, 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 anurance (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 3.B. of Facility Operating License No. DPR-25 is hereby amended to read as follows:

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9808130104 980807 m

PDR ADOCK 05000249 Y

PDR

2-B.

Technical Soecifiegigag The Techn' cal Specifications contained in Appendix A, as revised through Amendment No. 163, are hereby incorporated in the license. The licensee shall operate the ft cility in accordance with the Technical Specifications.

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION

.g o.

w Lawrence W. Rossbach, Project Manager Project Directorate 111-2 Division of Reactor Projects - Ill/IV Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of issuance: August 7, 1998 l

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AWACHMENT TO LICENSE AMENDMENT NO.153 FACILITY OPERATING LICENSE i DPR-25 DOCKET NO. 50-249, Revise the Appendix A Technical Specifications by removing the page identified below and inserting the attached page. The revised page is identified by the captioned amendment number and contains marginallines indicating the area of change.

REMOVE JNNS1BT 3/4.6 7 3/4.6-7 I

PRIMARY SYSTEM BOUNDARY Safety Valves 3/4.6.E 3.6 - LIMITING CONDITIONS FOR OPERATION 4.6 - SURVEILLANCE REQUIREMENTS E.

Safety Valves E.

Safety Valves The safety valve function of the 9 reactor 1.

Deleted.

coolant system safety valves shall be OPERABLE in accordance with the specified 2.

At least once per 18 months,1/2 of the code safety valve function lift settings'd safety valves shall be removed, set established as:

pressure tested and reinstalled or replaced with spares that have been 1 safety valve'S @1135 psig 11%

previously set pressure tested and 2 safety valves @1240 psig i1%

stored in accordance with 2 s.nfety valves @1250 psig

• 1 %

manufacturer's recommendations. At 4 safety valves @1260 psig 1%

least once per 40 months'd, the safety valves shall be rotated such that all 9 safety valves are removed, set APPLICABILITY:

pressure tested and reinstalled or replaced with spares that have been 4

OPERAT ONAL MODE (s) 1,2 and 3.

previously set pressure tested and

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stored in accordance with l

manufacturer's recommendations.

I ACTION:

1.

With the safety valve function of one or more of the above required safety valves inoperable, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

2.

Deleted.

i a

The lift setting pressure shall correspond to ambient conditions of the valves at nominal operating temperatures and pressures.

b Target Rock combination safety / relief valve.

c The surveillance interval has been extended to 60 months for Unit 3, Cycle 15 only, and the provisions of t

Specification 4.0.B are not applicable to the 60-month interval.

DRESDEN - UNITS 2 & 3 3/4.6-7 Amendment No 163 l

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