ML20071E144
| ML20071E144 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 03/04/1983 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20071E154 | List: |
| References | |
| NUDOCS 8303150079 | |
| Download: ML20071E144 (8) | |
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NUCLEAR REGULATORY COMMISSION
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VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-280 SURRY POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 84 License No. DPR-32 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The apolication for amendment by-Virginia Electric and Power Comp..y (tW 11censee) cald September.23,1982, as supplesnented January T7,1983, 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 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 pubite, 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.
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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 3.8 of Facility Operating License No. DPR-37 is herehy amended to read as follcws:
B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 84, are herehy 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 1.
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Attachment:
Changes to the Technical Specifications Date of Issuance: March 4,1983 i
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VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-281 SURRY POWER STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 85 License No. DPR-37 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Virginia Electric and Power Company (the licensee) dated September 23, 1982, as supplemented January 17, 1983, 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 (11) 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.
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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 3.B of Facility Operating License No. DPR-32 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications co'ntained in Appendix A, as revised through Amendment No. 85, are hereby incorporated in the license. The licensee shall 4
operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
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Attachment:
Changes to the Tech ~nical Specifications Date of Issuance: tiarch 4, 1983 1
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ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 84 TO FACILITY OPERATING LICENSE NO. DPR-32 AMENDNENT NO. 85 TO FACILITY OPERATING LICENSE NO. OPR-37 DOCKET NOS. 50-280 AND 50-281 Revise Appendix A as follows:
Remove Pages Insert Pages 3.10-4 3.10-4 5.4-2 5.4-2 Figure 5.4-1 e
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A spent fuel cask or heavy loads exceeding 110 percent of the weight of a fuel assembly (not including fuel handling tool) shall not be moved over spent fuel, and only one spent fuel assembly will be handled at one time over the reactor or the spent fuel pit.
- 13. A spent fuel cask shall not be moved into the Fuel Building unless the Cask Impact Pads are in place on the bottom of the spent fuel pool.
B.
If any one of the specified limiting conditions for refueling is not met, refueling of the reactor shall cease, work shall be initiated to correct the conditions so that the specified itait is met, and no operations which increase the reactivity of the core shall be made.
C.
After initial sual loading and after each core refueling operation and prior to reactor operation at greater than 75% of rated power, the movable incore detector system shall be utilized to verify proper power distribution.
Basis l
Detailed instructions, the above specified precautions and the design of the l
fuel handling equipment, which incorporates built-in interlocks and safety l
features, provide assurance that an accident, which would result in a hazard to public health and safety, will not occur during refueling operations.
When no change is being made in core geometry, one neutron detector is Amendments 84 & 85.'
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assemblies to assure eff 0.95, even if unborated water were used to fill the spent fuel storage pit. The spent fuel pool is divided into a two-region storage pool. Region I comprises the first three rows of fuel racks (324 storage locations) adjacent to the Fuel Building Trolley Load Block. Region 2 comprises the remainder of the fuel racks in the fuel pool. During spent fuel cask handling, Region 1 is limited to storage of spent fuel assemblies which have decayed at least 150 days after discharge and shall be restricted to those assemblies in the " acceptable" domain of Figure 5.4-1.
Administrative controls with written procedures will be employed in the selection and placement of these assemblies. The enrichment of the fuel stored in the spent fuel racks shall not exceed 4.1% weight percent of U-235.
C.
Whenever there is spent fuel in the spent fuel pit, the pit shall be filled with borated water at a boron concentration not less than 2,000 ppm to match that,used in the reactor cavity and refueling canal during refueling operations.
D.
The only drain which can be connected to the spent fuel storage area is that in the reactor. cavity. The strict step-by-step procedures used during refueling ensure that the gate valve on the fuel transfer tube which connects the spent fuel storage area with the reactor cavity is closed before draining of the cavity commences. In addition, the i
procedures require placing the bolted blank flange on the fuel transfer i
tube as soon as the reactor cavity is drained.
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References FSAR Section 9.5 Fuel Pit Cooling System FSAR Section 9.12 Fuel Handling System Amendments 84 & 85 I
TS Figure 5.4--I 2000 ppm Boron in Pool Water 30,000 ~ -
Funi Exposure K ( 0.95
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region (ACCEPTABLE) 20,000 -
(UNACCEPTABLE) l 10,000 -
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.L 2.0 3.0 4.0 Initial Fuel Enrichment (w/o U235)
FIGURg 5.4-1 MINIMUM RTEL EXPOSURE VERSUS INITIAL Eh7ICHMENT TO PREVENT CRITICALITY IN DAMAGED RACKS Amendments 84 & 85
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