ML20054L466
| ML20054L466 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 06/18/1982 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20054L462 | List: |
| References | |
| NUDOCS 8207080147 | |
| Download: ML20054L466 (6) | |
Text
I
'o UNITED STATES E4 s N
NUCLEAR REGULATORY COMMISSION
{.. --M/-t WASHINGTON, D. C. 20555 g%,,,,.*/
A COMMONWEALTH EDIS0N COMPANY DOCKET N0. 50-295 ZION STATION UNIT 1 AMEllDMENT TO FACILITY OPERATING LICENSE Amendment No. 74 License No. DPR-39 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The applications for amendment by Commonwealth Edison Company (the licensee) dated May 21, 1982 as supplemented by letter dated June 2, 1982 and by letter dated June 18, 1982, 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.
8207080147 820618 PDR ADOCK 05000295 P
PDR kk
. 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:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 74, 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 EGULATORY COMMISSION l
l Y.
Operating Reacto ranch No. 1 Division of Lice g
Attachment:
Changes to the Technical Specifications Date of Issuance: June 18,1982 m
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 74 TO FACILITY OPERATING LICENSE NO. DPR-39 DOCKET NO. 50-295 Revise Appendix A as follows:
Pemove Pages Insert Pages 45 45 63a 63a 97 97 e
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D (h..D s
i8 4.IMITIliG CONDITI0fl FOR OPERATION SURVEILLA.NCE REOUIREf4ENT i
' 3.3.3 D.
If the total leakage, other than 4.3.3 D.
Not Applicable Icakage from controlled sources, exceeda 10 gpm the reactor shall be placed in the hot shutdown condition within 4' hours.
The reactor shall be placed in cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
E.
Primary-to-Secondary leakage through the stenra generator tubes shall be limited to 1 GPM total for all steam generators not isolated from the Reactor Coolant System and 500 gallons
- per day through any one steam generator not isolated from t.he Reactor Coolant System.
If in excess of specificat. ion, reduce leakago to
. within levels within 4' hours o,r be in cold shutdown within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />'.
- During Unit 1 cycle 7 operation, the baseline
- ^5-primary to secondary leak rate for each steam generator shall be determined after re Nhing equilibrium operating conditions.
After reaching primary to secondary leak rate for any steam generator of 100 gallons per day,'
an increase of 50 gallons per day over a 7 day ;
period or 100 gallons per day over a 30 day period shall be reported to the assigned NRC l
project flanager verbally within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> with j
a written follow up report within 14 days.
The follow up report shall include a CEC 0 analysis of the increased leakage and an 6
)
evaluation to assure an acceptable level of l
tube integrity will be maintained.
In the.
event of a mid cycle shutdown to repair tube
. leakage, CEC 0 will inform the fiRC of actions t
to be taken and inspections to be performed.
These requirements will no longer be in effect once the unit cycle 7-8 refueling begins and l
this footnote will be void as.~of that date.
i Amendment flo. 74
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LIMITIrlG C0tDITION FOR OPERATIOrj SLEVEILLAt1CE REQUIREttill i
3.2.2 Power Distribution Limits 4.2.2 Power Distribullon
~
A.
Ibt Channel Factor Limits
- A.
Ilot Channel Factor Limits 1.1 At all times, except during physics tests 1.1 Following initial core loading and at 1 75% rated power".*, the hot channel at a minimum of regular effective factors defined in the bases must meet full power monthly intervals 4
the following limits:
thereafter, power distribution maps, using the Movable Detector I
Unit 1, only)] =
System, shall be made to confirm F (Z)1 [F (Z 2.13/P x Kj(Z) for P>0.5 that lie hot channel factor limits g
g L
4.26 x K (Z), for P 0.5 2.13- = Fg constant (LOCA limiting value);,
of this specir! cation are g
1 satisfied.
K (Z) = factor from Figure 3.2-9 selected'at the gcore elevation, Z, of the measured F ;.
Following initial loading and each q
subsequent reloading. a' power l
N and F 1 1.55 [1
- 0.2 (1-P)]
distribution map using the. Movable an Detector System,- shall be made to confirm t hat power distribullon P
= fraction of rated power r)t which the core i
limits are met, in the full power operated during Fq and F measurement';
au configuration before a unit 1s-
[F (Z)] = F (Z) limit; operated above 75% of rating.
g n
The hot channel factors above are defined for a period not to exceed the predicted minimum time to collapse' exposure levels for each fuel region as referenced in the bases.
Ouring Physics iests which may exceed these hot channel factor 11mits, the reactor may be in this condition for a period of time not to exceed eight hours contlnuously.
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l 45 Amendment No. 74 9
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Figure 3.2-9 Hot Channel ' Factor Normalized
. Operating Envelope for Unit 1, only 6
8 Q
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F C6i.; tant (LOCA Limiting Value) = 2.13 3'
q 1
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Core Height (Feet)
Ahiendment No. 74
-63a-
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