ML19294B249
| ML19294B249 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 02/04/1980 |
| From: | Ziemann D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19294B245 | List: |
| References | |
| NUDOCS 8002280047 | |
| Download: ML19294B249 (6) | |
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UNITED STATES o
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DAIRYLAND POWER _ COOPERATIVE DOCKET NO. 50-409 LA CROSSE BOILING WATER REACTOR AMENDMEF :0 PROVISIONAL OPERATING LICENSE Amendment No. 19 License No. DPR-45 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Dairyland Power Cooperative (the licensee) dated January 17, 1980, as supplemented by letter dated January 22, 1980, complies with the standards and requirenents 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 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 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.
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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 Provisional Operating License No. CPR-45 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A issued October 21, 1969, with Authorization No. DPRA-6, as revised through Amendment No.19, 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.
F R THE NUCLEAR REGULATORY COMMISSION
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/3 pfnw' Dennis L. Ziemann, Diief Operating Reactors Branch #2 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance:
February 4, 1980
ATTACHMENT TO LICENSE AMENDMENT NO.19 PROVISIONAL OPERATING LICENSE NO. DPR-45 DOCKET NO. 50-409 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages.
The revised pages are identified by the captioned amendment number and contain vertical lines indicating the area of change.
PAGES 32a 32a(1)*
32aa
- This new page does not involve a change in the prov sions; it merely involves repositioning of the provisions.
- 32a -
REACTOR COOLANT SYSTEM 4.2.2.22 ACTIVITY LIMITING CONDITION FOR OPERATION 4.2.2.22 The activity
- of the:
7 a.
Reactor coolant shall be limited to:
1.
1 0.2 pCi/ gram DOSE EQUIVALENT I-131, 2.
1 100/E pCi/ gram, and
-6 3.
1 5.0 x 10 Ci/ gram gross alpha activity.
b.
Off-gas emission, measured at the 150 cu. f t. off-gas holdup tank effluent monitor, shall be limited to 2 750 Ci/d (P/P )
F
+AT (1-0.018t) (P/P ), where:
F 1.
(P/P ) = fraction of RATED THERMAL POWER between 33 MWt e
and 1 : MWt, 2.
A = tramp activity, Ci/d, not to exceed 1500, at THERMAL PbWER (P ) as detemined upon initial power escalation af ter eabh refueling.
3.
t = days af ter the determination of A with the limitation T
that t 1 50.
4.
Activity values shall ce normalized for correlation with previous cycles due to changes in monitoring, sampling and/or analysis methods.
- Limits for Cycle 6 core configuration with reactor operation extended beyond 15000 MWD /MTU lead assembly average exposure in the remaining AC " core II" fuel assemblies.
1 Dose Equivalent 0.082 uCi/ gram 131
-0 Gross Alpha Activity 0.9 x 10 pCi/ gram Off-gas 571. Ci/ day APPLICABILITY:
OPERATIONAL CONDITIONS 1, 2, 3 and 4.
ACTION:
a.
In OPERATIONAL CONDITION 1, 2 or 3, with the activity of the reactor coolant; 1
>0.2 uti/ gram DOSE EQUIVALENT l-131 but 1 4.0 vCi/ gram, entry to OPERATIONAL CONDITION 1, 2, 3 or 4 is pemitted and operation may continue for up to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> provided that operation under these conditions shall not exceed 800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> in any consecutive 12-month period.
Should Amendment No.1/, /,19
32a(1)_
the total operatina time at a primary coolant specific activity >0.2 uCi/ oram DOSE EQUIVALErlT I-131 exceed 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> in any consecutive six-r.onth period, the licensee shall report the number of hours of operation above this limit to the NRC within 30 days.
2.
> 0.2 uti/ gram DOSE EQUIVALENT I-131 for more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> during one continuous time interval or > 4.0 uCi/arar be in at least HOT SHUTDOWN with the main steam line isolation valve closed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
Amendment No. )(, K, 19
- 32aa -
POWER DISTRIBUTION LIMITS MAXIMUM AVEP. AGE FUEL ASSEMBLY EXPOSURE LIMITING CONDITION FOR OPERATION 4.2.4.2.5 The maximum average exposure of any fuel assembly shall be limited to 15,600 MWD /MTU.
l APPLICABILITY: OPERATIONAL CONDITION 1.
ACTION:
With the maximum average fuel assembly exposure greater than 15,600 l
MWD /MTU, be in at least HDT SHUTDOWN with the main steam line isolation valve closed 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 />.
SURVEILLANCE REQUIREMENT 5.2.17.5 The maximum average exposure of each fuel assembly shall be determined to 09 less than 15,600 MWD /MTU by calculation at least once
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per Si EFPD, Amendment No. J4',19