ML20211D160
| ML20211D160 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 09/26/1986 |
| From: | Rubenstein L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20211D163 | List: |
| References | |
| NUDOCS 8610220124 | |
| Download: ML20211D160 (5) | |
Text
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c-g6 UNITED STATES NUCLEAR REGULATORY COMMISSION h
.{e WASHINGTON, D. C. 20656
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VIRGINIA ELECTRIC AND POWER COMPANY OLD DOMINION ELECTRIC COOPEPATIVE DOCKET NO. 50-338 NORTH ANNA POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 86 License No. NPF-4 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment by Virginia Electric and Power Company et al., (the licensee) dated July 11, 1986, complies with the standards and requirements of the Atemic Energy Act of 1954, as amended (the Act), 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 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 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 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.
8610220124 860926 PDR ADOCK 05000338 P
2.
Accordingly, the license is amended by changes to the Technical Speci-fications as indicated in the attachment to this license amendment, and paragraph 2.D.(2) of Facility Operating License No. NPF-4 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 86', 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 e.
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Leste'r S. Rubenstein, Director PWR Proiect Directorate #2 Division of PWR Licensing-A
Attachment:
Changes to the Technical Specifications Date of Issuance: September 26, 1986
ATTACHMENT TO LICENSE AMENDMENT NO. 86 TO FACILITY OPERATING LICENSE NO. NPF-4 DOCKET NO. 50-338 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages as indicated.
The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
The corresponding overleaf pages are also provided to maintain document completeness.
Remove pages Insert pages 3/4 4-26 3/4 4-26 1
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20 30 40 so ao 70 so so 100 PERCENT OF RATED THERMAL POWER l
FIGURE 3.41 DOSE EQUIVALENT l-131 Primary Coolant Specific Activity Limit Versus Percent of RATED THERMAL POWER with the Primary Coolant Specific ActMty >1.DuC1/ yam Dose Equivalent 1-131 1
4IDRTH ANNA - UNIT 1 3/4 4-25
l REACTOR COOLANT SYSTEM 3/4.4.9 PRESSURE / TEMPERATURE LIMITS REACTOR COOLANT SYSTEM LIMITING CONDITION FOR OPERATION The Reactor Coolant System (except the pressurizer) temperature and 3.4.9.1 pressure shall be limited in accordance with the limit lines shown in Figures 2 4-2 and 3.4-3 during heatup, cooldown, criticality, and inservice leak and hydrostatic testing with:
A maximum heatup of 60*F in any one hour period.
a.
b.
A maximum cooldown of 100*F in any one hour period, A maximum temperature change of less than or equal to 10'F in c.
any one hour period during inservice hydrostatic and leak testing operations above the heatup and cooldown limit curves.
APPLICABILITY: At all times.
ACTION:
With any of the above limits exceeded, restcre the temperature and/or pressure to within the limit within 30 minutes; perform an engineerfng evaluation to determine the effects of the out-of-limit condition on the structural integrity of the Reactor Coolant System; determine that the Reactor Coolant System remains acceptable for continued operations or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and reduce the RCS T and pressure to less than 200*F and 500 psig,
_respectively,withinthefo11owinf30 hours.
SURVEILLANCE REQUIREMENTS 4.4.9.1.1 The Reactor Coolant System temperature and pressure shall be determined to be within the limits at least once per 30 minutes during system heatup, cooldown and inservice leak and hydrostatic testing operations.
4.4.9.1.2 The reactor vessel material irradiation surveillance specimens ii shall be removed and examined, to determine changes in material properties, at the intervals required by 10 CFR 50, Appendix H.
The results of these examinations shall be used to update Figures 3.4-2 and 3.4-3.
NORTH ANNA - UNIT 1 3/4 4-26 Amendment No. M, M, 86 s
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