ML20147C369

Amend 37 to Oper Lic DPR-48.Changes Tech Specs to Allow Boron Concentration in Pressurizer to Be 200 Ppm Less than Reactor Coolant Loop Boron Concentration.Corrections Are Made to Tech Specs.Changes to Tech Specs Encl

ML20147C369
Person / Time
Site:	Zion  File:ZionSolutions icon.png
Issue date:	11/30/1978
From:	Schwencer A Office of Nuclear Reactor Regulation
To:
Shared Package
ML20147C354	List: ML20147C348 ML20147C363 ML20147C369 ML20147C376 ML20147C380
References
NUDOCS 7812180240
Download: ML20147C369 (6)

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UNITED STATES NUCLEAR REGULATORY COMMISSION W ASHINGTON. D. C. 20$$5 COMMONWEALTH EDISON COMPANY DOCKET NO. 50-304 ZION STATION UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 37 License No. DPR-48

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

A, The application for amendment by Comonwealth Edison Comp. ny l (the licensee) dated May 24, 1977 as supplemented Septembs.r 27, 1978, complies with the standards and requirements of the ,

Atomic Energy Act of 1954, as amended (the Act), and the i Commission's rules and regulations set forth in 10 CFR  !

Chapter I; l B. The facility will operate in conformity with the applicat:an, the provisions of the Act, and the rules and regulations 'f )

the Commission; 1 C. There is reasonable assurance (i) that the activities authorized by this amendment car, be conducted without endangering th health and safety of '.ne public, and (ii) that such activ. ties will be conducted in compliance with the Commission's regtlations; D. The issuance of this amendment will 'it be inimical to the connon defense and security or to the health and safety o.

the public; and E. The issuance of this amendment is in accordance with 10 C'R Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

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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 License No. OPR 48 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 37 , 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.

FOR THE NUCLEAR REGULATORY COMMISSION LLd'd 8 V A. Schwencer, Chief Operating Reactors Branch #1 Division of Operating Reactors

Attachment:

Changes to the Technical Specifications Date of Issuance: November 30, 1978 l

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t ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 40 TO FACILITY OPERATING LICENSE NO. OPR-39

- AMENDMENT NO. 37 TO FACILITY OPERATING LICENSE NO. DPR-48 DOCKET NOS. 50-295 AND 50-304 Revise Appendix A as follows:

Remove Pages Insert Revised Pages 40 40 197 197 198 198

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LIMITING CONDITION FOR OPERATION SURVEILLAffCE REQUIREMENT

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4.2.1.B once a shift while. remaining in this condition. During heatup, the boron d

concentration in the reactor coolant-loops and pressurizer shall be sampled every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. The reactor coolant loop boron concentration must not decrease by'  ;

more than 50 ppm between successive 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> samples. The pressteizer boron C. Unit Startup concentration must not be more than 200 ,

ppm less than the reactor coolant loop '

l. Immediately prior to startup, the boron concentration.

reactor coolant temperature shall be shown to be greater than the tempera- C. Startup ture above which the noderator temp-erature coefficient is always negative 1. The Tavg of each reactor coolant and greater than 500*F, except during loop shall be logged before low power physics tests. attempting to bring a reactor critical.

2. When a reactor is approaching critica-lity, the shutdown banks shall be fully 2. Not Applicable.  ;

withdrawn in sequence (shutdown bank ,

A,B,C,0) before any other rods are withdrawn. The control group rods shall be no further inserted than the limits shown by Figure 3.2.2 for Unit ,

1 and Figure 3.2-4 for Unit 2 for

. 4-loop operation and Figure 3.2-3 for Unit I and Figure 3.2-5 for Unit 2

, for 3-loop operation when criticality j is attained.

D. Power Operation D. Power Operation j l. When a reactor is critical, except 1. Rod operation shall be' verified by for physics tests and control rod partial movement of all rods- every exerrises, the shutdown rcos MialI two weets. hoos i.icn siave 'een o be fully with- exercised within tt"hmendment No. 40, Unit 1 7 40 Amendment No. 37, Unit 2 i

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PROPOSED TECHNICAL SPECIFICATION SECTION 3.9.1.B l

f LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT f

i l 3.9 CONTAINMENT ISOLATION SYSTEMS (per unit) 4.9 CONTAINMENT ISOLATION SYSTEM (per unit)

Applicability: Appl-icabil ity: _

Applies to containment isolation systems. Applies to containment isolation systems.

Objective: Objective:

To insure containment isolation within To establish the surveillance require-acceptable limits and define the opera *.ing ment for containment isolation.

status of the reactor containment for plant operation.

Specification: Specification:

1. Isolation valve seal water system 1. Isolation valve seal water system (Table 4.9-1)

A. The isolation valve seal water system .

shall be operable unless the reactor A. The isolation valve seal water is in the cold shutdown condition system shall be tested every except as specified in 3.9.1C. refueling outage. Perfomance will be acceptable if the five seal water headers are maintained at a minimum pressure of 47 psig for two hours following manual actuation. The seal water header isolation valves are closed throughout the test.

B. The isolation valve seal water tank B. The level and pressure of the shall be maintained at a minimum isolation valve seal water tank pressure of 68 psig and a minimum shall be checked monthly.

valo...e of 70 gal'er.a.

C. Any one header of the isolation valve C. Not Applicable.

seal water system may be inoperable I for a period not to exceed four consecutive days during reactor 197 Amend, ment, nnoratinn to normit maintonanco amon, mon nn No.ty 40, Unit

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PROPOSED TECliNICAL SPECIFICATION SECTION 3.9.2.E .

'* LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT 3.9.2. Penetration pressurization systems 4.9 2. Penetration pressurization systems Table 4.9-2)

A. The penetrations (electrital and A. The pressure of the four nitrogen mechanical) and liner weld channels and penetration pressurization ,

shall be continuously pressurized headers shall be checked monthly, above 47 psig unless the reactor is in the cold shutdown condition except as specified in 3.9.2B.

B. Any one header of the nitrogen or B. Immediately following maintenance '

air pressurization system may be on a pressurization header, the inoperable for a period not to header pressure must be checked, exceed four consecutive days during reactor operation to permit main-tenance.

C. The penetration air com- C. The penetration air compressor shall' pressor system and either the in- be load tested (+ 10% of design strument air system or the nitrogen pressure and capacity) during each I

system shall be operable except as refueling outage. '

specified in 3.9.2.0.

D. One penetration air compressor may D. Immediately following maintenance be inoperable for a period not to .on a penetration compressor, that exceed 15 days to permit compressor shall be load tested.

maintenance.

E. The upper limit for long term E. The air flow to the penetration l

uncorrected air consumption for the pressurization headers shall penetration pressurization systems be checked monthly.

j stall be less than 0.2% of the containment volume per day at 47 l

psig (960 SCFil).

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l 198 Amendnent No. 40, Unit 1

' Anendment No. 37, Unit 2 l

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