ML19341D380
| ML19341D380 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 02/25/1981 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19341D381 | List: |
| References | |
| NUDOCS 8103050502 | |
| Download: ML19341D380 (8) | |
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VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-280 SURRY POWER STATION, UNIT-NO.1 l
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 65 License No. DPR-32 1
~ 1.
The Nuclear Regulatory Commission (the Commission) has found that:
~ A.
The application for amendment by Virginia Elect ic and Power Company (the licensee) dated May 15, 1980, as supplemar ted September 15, 1980 and December 4,1980, 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 (i) tnat 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 complian< 3 wit the Commission's regulations; D.
The issuacee of this amendment will not be inimical to the common defense and security or to the health and safety of the public; E.
The issuance of this amendment is in accordance with 10 CFR Part 51 l
of the Commission's regulations and all applicable requirements i
have been satisfied.
2.
Accordingly, the license is amended by deleting paragraph 3.F of the license and by changes to the Technical Specifications as indicated in the attachment to the license amendment, and paragraph 3.B of Facility Operating License No. DPR-32 is amended to read as follows:
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_2 B.
Technical Specificationr.
The Technical Specifications contained in Appendices A and B, as revises through Amendment No. 66
, are hereby incorporated in une license.
ine licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendr.ent is effective as of the date of its issuance.
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Operating Raactors Branch #1 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: February 25, 1981 a
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VIRGINI A' ELECTRIC' AND POWER COMPANY DOCKET NO. 50-281 SURRY POWER STATION, UNIT NO. 2 AMENDMENT TO FACILITY ' OPERATING LICENSE Amendment No.65 License No. DPR-37 i
1.
The Nuclear Re'gulatory Commission (the Commission) has found that:
A.
The application for amendment by Virginia Electric and Power Company (the licensee) dated May 15, 1980, as supplemented September 15, 1980 and December 4,1980, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's i
rules and regulations set forth in 10 CFR Chapter ~ It i
B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; l
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 wit 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; 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.
fccordingly, the license is amended by deleting paragraph 3.F of the license and by changes to the Technical Specifications as indicated e
in the attachment to the license amendment, and paragraph 3.8 of i
Facility Operating License No. DPR-37 is amended to read as follows:
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B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 65
, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
2.
This license-amendment is effective as of the date of its issuance.
FC)THENUCEARfhEGULATORYCOMMISSION
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Attachment:
Changes to the Technical Specifications Date of Issuance:
February 25, 1981 W
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l ATTACHMENT TO LICENSE AMENDMENT NOS. 66 AND G5 FACILITY OPERATING LICENSE NOS. DPR-32 AND DPR-37 DOCKET NOS. 50-280 AND 50-281 Replace the following pages of the Appendix "A" Technical Specifications with enclosed pages.
The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
Remove Pages Insert Pages 5.3-2 5.3-2 5.4-1 5.4-1 5.4-2 5.4-2 9
i
TS 5.3-2 4
3.
Reload fuel will be similar in design to the initial core. The enrich-ment of reload fuel will not exceed 3.7 weight percent of U-235.
4.
Burnable poison rods are incorporated in the initial core. There are 816 poison rods in the form of 12 rod clusters, which are located in vacant control rod assembly guide chimbles. The burnable poison rods consist of pyrex clad with stainless steel.
5.
There are 48 full-length control rod assemblies in the reactor core. The full-length control rod assemblies contain a 144-inch length of silver-Lndium-cadmium alloy clad with stainless steel.
6.
Surry Unic 1, Cycie 4, Surry Unit 2, Cycle 3, and subsequent cores will meet.the following criteria at all times during the operation lifetime.
Hot channel factor limits as specified in Section 3.12 shall be a.
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i Amendment Nos. 66 & 65 5
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TS 5.4-1 5.4 FUEL STORAGE i
Applicability Applies to the design of the new and spent fuel storage areas.
4 Obj ective To define those aspects of fuel storage relating to prevention of. criticality in fuel storage areas; to prevention of dilution of the borated water in the reactor; and to prevention of inadvertent draining of water from the spent i
fuel storage area.
1 Specification l
A.
The reinforced concrete structure and steel superstructure of the Fuel Building and spent fuel storage racks are designed to withstand Design Basis Earthquake loadings as Class 1 structures. The spent fuel pit has a stainless steel liner.to ensure against loss of water.
B.
The new and spent fuel storage racks are designed so that it is im-possible to insert assemblies in other than the prescribed locations.
New fuel is stored vertically in an array with a distance of 21 inches between assemblies to assure kaff < 0.98 with fuel of the highest anticipated enrichment in place assuming optimum moderation.* Spent fuel is stored vertically in an array with a distance of 14 inches between a
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- E.G., an aqueous foam envelopment as'the result of fire fighting.
Amendment Nos. 66 & 65
TS 5.4-2 assemblies to assure keff < 0.95, even if unborated water were used to fill the spent fuel storage pit.
The enrichment of the fuel stored in the spent fuel racks shall not exceed 3.7% weight percent of U-235.
C.
Whenever there is spent fuel in the spent fuel pit, the pit shell ie 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 i
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 procedures require placing the bolted blank flange on the fuel transfer tube as soon as the reactor cavity is drained.
References FSAR Section 9.5 Fuel Pit Cooling System FSAR Section 9.12 Fuel Handling System a
1 Amendment Nos. 66 & 65
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