ML20134P783

Amends 176 & 163 to Licenses DPR-39 & DPR-48,respectively, Adding Mode of Applicability to TS 3.2.3.D

ML20134P783
Person / Time
Site:	Zion  File:ZionSolutions icon.png
Issue date:	11/25/1996
From:	Shiraki C NRC (Affiliation Not Assigned)
To:
Shared Package
ML20134P776	List: ML20134P773 ML20134P783 ML20134P794
References
NUDOCS 9611290283
Download: ML20134P783 (6)

Text

.- . . .

_7

, pau4 yw & UNITED STATES

l. * }

2 NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20065-0001

~s..... /

COMMONWEALT U DIS 0N COMPANY DOCKET NO. 50-295 ZION NUCLEAR POWER STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.176 License No. DPR-39 1

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

A. The application for amendment by Commonwealth Edison Company (the licensee) dated October 4, 1996, and supplemented on November 6, 1996, 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 thir 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 c.hanges to the Technical {

Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-39 is hereby amended to read as follows:

9611290283 961125 PDR ADOCK 05000295 P PDR

r ,.__. .. .__ . . . - . _ . - _ _ _ .. . ._ .. . _ _.

l

- \

~

(2) Technical Snecifications i The Technical Specifications contained in Appendices A and B, as

revised through Amendment No.176 , are hereby incorporated in

the license. The licensee shall operate the facility in j 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 i

~

C1 e Y. Shiraki, Senior Project Manager ,

Project Directorate III-2 Division of Reactor Projects - III/IV .

Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: November 25, 1996 ,

t UNITED STATES

• ; NUCLEAR REGULATORY COMMISSION 2 WASHINGTON, D.C. 20615 0001

\...../

1 i

COPeiONWEALTH EDISON COMPANY I DOCKET NO. 50-304 ZION NUCLEAR POWER STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 163 License No. DPR-48

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

A. The application for amendment by Commonwealth Edison Company (the licens,se) dated October 4, 1996, and supplemented on November 6, 1996, 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 (1) 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-48 is hereby amended to read as follows:

. \

l (2) Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 163 , 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 its issuance and shall be implemented within 30 days.

FOR THE NUCLEAR RE ULATORY COMMISSION ]

~ l C1 e Y. Shi aki, Senior Project Manager Project Directorate III-2 i Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation 4

Attachment:

Changes to the Technical Specifications l Date of Issuance: November 25, 1996

I I

ATTACHMENT TO LICENSE AMENDMENT NOS.176 AND 163 FACILITY OPERATING LICENSE NOS. DPR-39 AND DPR-48 DOCKET NOS. 50-295 AND 50-3Q1 l

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 marginal lines indicating the area of i

change.

Remove Paae Insert Paae 55 55

. 1 1

l J

l 4

f 4

l

i l -

LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT I

1 i

3.2.3.D.1 Apolicability: Modes 1 and 2 4.2.3.D.1.a shall be checked indirectly by I

excore detectors and/or Reouired Action: If the conditions of therr ;ouples and/or moveable incore Section 3.2.3.D.1 cannot be met the dete s tors every shift; or after any reactor shall be brought to at least the rod motion of the non-indicating rod, exceeding 12 steps, whichever Hot Shutdown condition within four hours.

i occurs first.

4. DN8 Parameters

b. During operation below 50% of rated A. The following DNB related parameters power, no special monitoring is shall be maintained within the required.

limits shown during operation.

i 4.A.I. Each of the parameters listed in

1. Reactor Coolant System Tavg Specification 3.2.4.A shall be verified FOUR LOOP: s 567.7'F to be within its limit at least once per L 2. Pressurizer Pressure 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

FOUR LOOP

2 2210 psia (2195 psig)* 2. The Reactor Coolant System total flow

3. Reactor Coolant System Total rate shall be determined to be within i Flow Rate its limit by measurement at least once FOUR LOOP: 2 362,300 GPM# per 18 months.

8. With any of the above parameters exceeding its limit, restore the

' parameter to within its limit within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or reduce thermal power to less than 5% of rated thermal power within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

i J

• Limit not applicable during either a thermal power ramp increase in excess of 5% rated thermal power per

. minute or a thermal power step increase in excess of 10% rated thermal power.

1 Includes a 3.5% flow measurement uncertainty.

i

. e w ~y n-....,,nu-%%.wr,, ,y ~m_~, n , ,- ,,.,, ,w. ,w m ,i,,,,, ,,,,py.,,, ,y , y,.