ML20129F077

Amends 89 & 79 to Licenses DPR-39 & DPR-48,respectively, Revising Tech Specs Re Limits for Total Nuclear Peaking Factor.Revised Peaking Factor Is 2.32.Peak Cladding Temp Calculated to Be 2,159 F

ML20129F077
Person / Time
Site:	Zion  File:ZionSolutions icon.png
Issue date:	05/24/1985
From:	Varga S Office of Nuclear Reactor Regulation
To:
Shared Package
ML20129F037	List: ML20129F033 ML20129F077 ML20129F129
References
NUDOCS 8506060675
Download: ML20129F077 (10)

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% UNITEJ 8TATES NUCLEAR REGULATORY COMMISSION WASHl880708f, D. C. 20G66 COMMONWEALTH EDISON COMPANY DOCKET NO 50-295 ZION NUCLEAR POWER STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.89 License No. DPR-39

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

A. The application for amendment by Comonwealth Edison Company .

(thelicensee)datedOctober 19, 1984, augmented t,y letters dated December 20, 1984, February 14,1985, March 8,1985 and April 19, 1985, complies with the standards and re EnergyActof1954,asamended(theAct)quirementsoftheAtomic and the Comission'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 Comission; 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 act'vities will be conducted in compliance with the Comission'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 publict and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission'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-39 is hereby amended to read as follows:

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, 2 (2) Technical Specifications The Technical Specifications contained in Appendices A and 8 as revised through Amendment No.gg , are hereby incorporated in the license. The Ticensee 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 NUCLE $R REGULATORY COP 91!$510N a, e Operating Reactors anch #1 Division of Licensi

Attachment:

Changes to the Technical Specifications Date of Issuance: May 24, 1985 r

-[ Io,, UNITEJ STATES 8 g NUCLEAR REGULATORY COMMISSION 3 -l WASHINGTON, D. C 20655

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COMMONWEALTH EDIS0N COMPANY 00CKET NO. 50-304 ZION NUCLEAR POWER STATION, UNIT 2 AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendment No. 79 License No. DPR-48

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

A. The application for amendment by Comonwealth Edison Company f (thelicensee)datedOctober 19, 1984, augmented by letters dated December 20, 1984, February 14,1985. March 8,1985 and April 19, 1985, complies with the standards and re Energy Act of 1954, as amended (the Act)quirements of the Atomic and the Comission'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 Comission; 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 Comission's regulations; D. The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and i

E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission'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:

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(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 79 , 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. l FOR THE NUCLEAR REGULATORY COMMISSION h

ae . r'gi , .

Operating Reactors Br nch #1 Division of Licensi

Attachment:

Changes to the Technical Specifications Date of Issuance: May 24, 1985 f

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. l ATTACHMENT TO LICENSE AWiNDMENTS AMENDMENT NO. 89 FACILITY OPERATING LICENSE NO. DPR-39 AMENDMENT N0. 79 FACILITY OPERATING LICENSE NO. DPR-48 DOCKET NOS. 50-295 AND 50-304 Revise Appendix A as follows:

Remove Pages Insert Pages 45 45 63a 63a 63b 63b 69a 69a 174 174

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• 4 l.IMITING CONDITION FOR.0PERATIDN SURVEILLANCE REQUIREMENT' .

l 3.2.2 Power Distribution Limits 4.2.2 Power Distribution-A. Hot Channel Factor Limits

• A. Hot Channel Factor Limits t

1.1 At all times, except during physics tests 1.1 Following initial core loading and i at a minimum of regular effective at $ 75% rated power **, the hot channel factors defined in the bases must meet full power monthly intervals the following limits: thereafter, power distribution i

maps, using the Novable Detector Units 1 and 2 System, shall be made to confirm -

that the hot channel factor limits I

, Fg(Z) $ [Fg(Z)]t = 2.32/P x K (Z), for P>0.5 of this specification are 4.64 x K (Z), for P50.5 satisfied.

2.32 - Fg constant (LOCA limiting value);

K (Z) = factor from Figure 3.2-9 selected at the i

core elevation .Z, of the measured Fg; following initial' loading and each subsequent reloading, a power distribution map using the Movable I

[Fg(Z)]t - Fg(Z) limit; Detector. System, shall be made to Units 1 & 2 (For 4-loop operation above 2% thermal confirm that power distribution power) limits are met, in-the full power

configuration before a unit is '

operated above 75% of' rating.

and FlH $ 1.55 [1+0.3 (1-P)] for 0.02 < P 11.00 P = fraction of rated power at which the core ,

operatedduringFgandFlHmeasurement;

• The hot channel factors above are defined for a period not to exceed the predicted minimum time to g= collapse exposure levels for each fuel region as m referenced in the bases.

! E I 5 ** During Physics tests which may exceed these hot i 5 channel factor limits, the reactor may be in this 4 me condition for a period of time not to exceed eight l

f hours continuously.

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Figure 3.2-9 Hot Channel Factor Normalized Operating Envelope for Units 1 and 2 Fg Constant (LOCA Limiting Value) = 2.32 (0.0, 1.000) (6.0, 1.000) 1.0 (10.8, 0.940)

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2 4 6 8 10 12' Core Height (Feet) i Amendment Nos. 89 and 79

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' Amendment Nos. 89 and 79

1 significantly different from those resulting from operation within the target band. The

! instantaneous consequences of being outside the band, provided rod insertion-limits are observed, is not worse than a-10 percent increment.in l peaking (y + 3) percentfactor.for flux difference (t y percent to .4 percent in the range 1 indicated) increasing by 1 1 percent for each 2 i' percent decrease in rated power. Therefore, while the deviation exists the power level is limited to 90% of PT or lower _ depending on the indicated flux difference.

If, for any reason, flux difference is not controlled within the AI target band for as long i

a period as one hour, then xenon distribution may

' be significantly changed and operation at 50 percent is required to protect-against.potentially more severe consequences of.some accidents.

As discussed above, the essence of the procedure is to maintain the xenon distribution in the core i as close to the equilibrium full power condition as possible. This is accomplished by.using the boron system to position the full length control rods to produce .the required indicated flux difference.

g=

For Condition 11 events, the core is protected

(( from overpower and a minimum DNBR of the

- g r+ applicable design limit DNBR by an automatic jp protection system. Compliance with operating r procedures is assumed as a precondition for o,

Condition 11 transients; however, operator error u) and equipment malfunctions are separately assumed I

g to lead to the cause of transients considered.

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LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT i

3.8.5 Accumulator System 4.8.5 Accumulator System (Table 4.8-4)

A. The four accumulators systems shall

, satisfy the following conditions whenever A. Surveillance and testing of the accumulator.

the reactor coolant system pressure system shall be performed as follows

exceeds 1000 psig except as specified in 3.8.5.A.S. (See 3.3.2.G for low RCS 1. The pressure and level of the temperature operation.) accumulator tanks shall be checked once a shift. At each 5% increase in-level,

1. Each accumulator shall be the boron concentration will be checked.

pressurizedtoatleast600psigand shall contain minimum of 818 ft

. 2. The accumulator boron concentration and a maximum of 888 ft3 of water. shall be checked monthly.

2. Each accumulator shall contain water  ; 3. The accumulator check valve operability borated to at least 2000 ppm.  ! (SI-8948A, B, C, and D) and (SI-8956A, l B, C, and D) will be verified at each

3. Each accumulator's isolation valve refueling outage by opening the shall be open. accumulator outlet isolation valve.

(MOV-SI8808A, B, C, and D) and i verifying a decrease in accumulator level and a leakage test to determine l l[ that no gross valve leakage is experienced.

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g 4. Isolation Valves f Not applicable.

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