ML19283B800
| ML19283B800 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 03/06/1979 |
| From: | Boyd R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19283B801 | List: |
| References | |
| NUDOCS 7903260340 | |
| Download: ML19283B800 (6) | |
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UNITED STATES o
yi NUCLEAR REGULATORY COMMisslON WASHINGTON, D. C. 20555 j
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- % **....P' VIRGINI A ELECTRIC AND POWER COMPANY DOCKET NO. 50-338 NORTH ANNA POLER STATION, UNIT NO.1 FACILITY OPERATING LICENSE License No. NPF-4 Amendment No. 8 1.
The Nuclear Regulatory Comm1ssion (the Commission) has found that:
A.
The issuance of this license amendment to Virginia Electric and Power Company complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comnission's rules and regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the license, as amended, the provisions of the Act, and the rules and regula-tions of the Commission; C.
There is reasonable assurance (i) that the activities author-ized 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.
2.
Accordingly, Paragraph 2.0.(3)f is amended to read as specified below:
- 2. D. (3 )f. Prior to startup following the first regularly scheduled refueling outage,. Virginia Electric and Power Company shal' implement the " Administrative Procedures, Controls, and Fire Brigade Program" and the Quality Assurance Program" associated with the fire protection program for North Anna Unit 1.
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. Prior to startup following the second regularly scheduled refueling outage, Virginia Electric and Power Company shall implement the fire protection program modifications as described in the NRC Safety Evaluation Report, " Fire Protection Program for North Anna Power Station, Units 1 and 2," dated February, 1979.
The License is further amended by a change to Appendix A Technical Specification 3.9.7 as indicated in the attachment to this license amer.dment of Facility Operat-ing License No. NPF-4 and is hereby amended to read as follows:
(2) Techrical Scecifice'.icns The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 8, are hereby incorporated into the license. The licensee shall operate the facility in accordance with the Technical Specifications.
H.
This amended license is effective as of the date of issuance.
FOR THE NUCLEAR-REGULATORY COMMISSION
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Roger S. Boyd, Director i
Division of Project Management Office of Nuclear Reactor Regulation Date of Issuance: MRC
Enclosure:
Pages 3/4 9-7 and 3/4 9-8 to Appendix A Technical Specifications
we
. Mr. W. L. Proffitt cc:
Mr. Michael S. Kidd U. S. Nuclear Regulatory Commission P. O. Box 128 Spotsivania, Virginia 22553 Dr. Paul W. Purdom Departaent of Civil Engineering Drexel University Philadelphia, Pennsylvania 19104 Dr. Lawrence R. Quarles Apartment No. 51 Kendal-at-Longwood Kennett Square, Pennsylvania 19348 Mr. A. D. Johnson, Chairman Board of Supervisors of Louisa County Trevillians, Virginia 23170 Ms. Susan T. Wilburn Commonwealth of Virginia Council on the Environment 903 9th Street Office Building Richmond, Virginia 23219 U. S. Envrionmental Protection Agency Region III Office ATTN:
EIS Coordinator Curtis Building
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6th and Walnut Streets Philadelphia, Pa.
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ATTACHMENT.T0 LICENSE AMENDMENT NO. 8 FACILITY OPERATING LICENSE NO. NPF-4 DOCKET NO. 50-338 Replace page 3/4 9-7 of the Appendix "A" Technical Specificaions with the attached page.
Page 3/4 9-8, the corresponding overleaf page, is also provided to maintain document completeness.
5 REFUELING OPERATIONS CRANE TRAVEL - SPENT FUEL PIT _
LIMITING CONDITION FOR OPERATION 3.9.7 Loads in excess of 2500 pounds shall be prohibited from travel over irradiated fuel assemblies in the spent fuel pit.
APPLICABILITY: With irradiated fuel assemblies in the spent fuel pit.
ACTION:
With the requirements of the above specification not satisfied, place the crane load in a safe condition. The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.9.7 Loads shall verified to be less than 2500 pounds prior to movement over irradiated fuel assemblies in the spent fuel pit.
NORTH ANNA - UNIT 2 3/4 9-7 Amendment No. 8
REFUELING OPERATIONS COOLANT CIRCULATION LIMITING CONDITION FOR OPERATION 3.9.8 At least one residual heat removal loop shall be in operation.
APPLICABILITY: MODE 6.
ACTION:
a.
With less than one residual heat removal loop in operation, except as provided in b. below, suspend all operations in-volving an increase in the reactor decay heat load or a re-duction in boron concentration of the Reactor Coolant System.
Close all containment penetrations providing direct access from the containment atmosphere to the outside atmosphere within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
b.
Thd residual heat removal loop may be removed from operation for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period during the performance of CORE ALTERATIONS in the vicinity of the reactor pressure vessel hot legs.
c.
The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.9.8 A residual heat removal loop shall be determined to be in opera-tion and circulating reactor coolant at a flow rate of > 3000 gpm at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
NORTH ANNA - UNIT 1 3/4 9-8
MAR 6 197')
SAFETY EVALPATION IN SUPPORT OF APPENDIX A TECHNICAL SPECIFICATION CHANGE 3.9.7 FOR NORTH ANNA POWER STATION UNIT NO.1 A.
Evaluation of change of Appendix A - Technical Specification 3.9.7 Technical Specification 3.9.7 states that loads in excess of 3250 pounds shall be prohibited from travel over irradiated fuel assemblies in the spent fuel. We have determined that the 3250 pounds load was an error and should be changed to 2500 pounds which is the upper limit for the weight of the fuel and control rod assemblies and associated handling tool as indicated in the basis for this technical specification (pg. B 3/4 9-2 of the Technical Specification).
B.
Environmental Consideration We have determined that the amendment does not authorize a change in effluent types or total amounts nor an increase in power level and will not result in any significant environmental impact. Having made this determination, we have further concluded that the amendment involves an action which is insignificant from the standpoint of environmental impact and, pursuant to 10 CFR Section 51.5(d) (4), that an environmental impact statement or negative declaration and environ-mental impact appraisal need not be prepared in connection with the issuance of this amendment.
C.
Conclusion We have concluded, based on the considerations discussed above, that:
(1) because the amendment does not involve a significant increase in the probability or consequences of accidents previously considered or a significant decrease in any safety margin, it does not involve a significant hazards consideration, (2) there is reasonable assurar:e that the health and safety of the public will not be endangered by operation in the proposed manner, and (3) such activities will be conducted in compliance with the Conmission's regulations and the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.
Also, we reaffirm our conclusions as otherwise stated in our Safety Evaluation and its Supplements.
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