ML20003H776
| ML20003H776 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 04/29/1981 |
| From: | Clark R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20003H777 | List: |
| References | |
| NUDOCS 8105070431 | |
| Download: ML20003H776 (14) | |
Text
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[ga nog *c UNITED STATES
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vlRoINIA ELECTRIC AND e0wER C0s9ANv DOCKET NO. 50-338 NORTH ANNA POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 27 License No NPF-4 1.
The Nuclear Regulatory Comission ithe Commission) has found that:
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A.
The application for ainendment by Virginia Electric and Power Company (the licensee) dated March 6,1981 as supplemented March 26,
,1981 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations set forth in 10 CFP. Chapter I; B.
The facility will operate in confortnity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonLble 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 Commission's regulations; l
1 0.
The issuance of this amend.aent 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.D.(2) of Facility Orerating License No. NPF-4 is hereby amended to read as follows:
(2) Technical Specifications 1
The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 27, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effecthe as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSICN Robert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
April 29, 1981
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 27 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.
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NCRTH ANNA - UNIT 1*
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DESIGN FEATURES In accordance with the code requirements specified in Section a.
5.2 of the FSAR, with allowance for normal degradation pur-suant to the applicable Surveillance Requirements, b.
For a pressure of 2485 psig, and For a temperature of 650'F, except for the pressurizer which c.
is 680*F.
VOLUME 5.4.2 The total water and steam volume of the reactor coolant system is 9957 + 10 cubic feet at a nominal T f 525'F.
avg 5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological tower shall be located as shown"on Figure 5.1-1.
5.6 PJEL STORAGE CRITICALITY 5.6.1 The spent fuel storage racks containing new and/cr spent fuel are designed and shall be maintained with a ncminal 14 inch center-to-center distance between fuel assemblies placed in the spent fuel storage racks l d with unborated watIk[ equivalent of < 0.95 with the storage pool fil e to ensure a k The k of < 0.95 includes a conservative allowance
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of 3.4% ak/k for uncertI(kties7 l
l The new -fuel pit storage racks are designed and shall be maintained with a nominal 21 inch center-to-center distance between new fuel assemblies such that, on a best estimate basis, k will not exceed.98 with fuel ofthehighestanticipatedenrichmentTkplaceassupingoptimummoderation.*
If 'resh fuel is stored dry for a core loading in the spent fuel racks, a center-to-center distance between new fuel assemblies will be admini-stratively limited to 28 inches. On a best estimate basis, k,f will not exceed.98 with fuel of the highest anticipated enrichment in place assuming optimum moderation.*
"E.G., an aqueous foam envelopment as the result of fire fighting.
.?rendment No. 14,27
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a v.< f VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-339 NORTH ANNA POWER STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPCRATING LICENSE Amendment No. 8 License No. NPF-7 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A'.
The application for, amendment by Virginia Electric and Power Company (the licensee) dated March 6,1981 and as supplemented March 26, 1981 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; 9.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; There is reasonable assurance (i) that the activities authorized C.
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 Si of the Comission's regulations and all applicable requirements have been satisfied.
0.
2.
Accordingly, the license is amended by changes to the Technical
, Specifications in paragraph 2.C.(2) of Facility Operating License No. NPF-7 and pagagraph 2.C.(2) is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices
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A and B, as revised through Amendment No. 8
, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
(a) The written procedures required by Technical Specification 6.8.h for the Technical Specifications listed below shall be implementer within 30 days after the date of this license:
4.3.2.1.3 Items 10 and 11 of Tabin 3.3-5 4.3.3,6 4.4.3.2.1
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4.4.3.2.2 4.4.6.2.2 The required surveillance shall be completed before the end of the first surveillance interval.
(b) The end of the current surveillance period for the Surveillance Requirements listed below may be extended beyond the time limit specified by Technical Specification 4.0.2.a.
In each case, the required surveillance shall be completed by the revised due date.
After May 31, 1981 the plant shall not be operated in Modes 1, 2, 3, or 4 until the Surveillance Requirements listed below have Upon accomplishment of the surveillance, the been completed.
provisions of Technical Specification 4.0.2.a shall apply.
Specification 4.8.2.3.2.d 4.8.2.4.2 This license amendment is effective as of the date of its issuance.
3.
l FOR THE NUCLEAR REGULATORY COMMISSION Robert lark, Chief
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l Operating Reactors Branch 83 Division of Licensing l
Attachmentf Chances to the Technical Soicif_ications Date of Issuance:
April 29, 1981 l
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ATTACHMENT TO LICENSE AMENOMENT AMENDMENT NO. 8 TO FACILITY OPERATING LICENSE NO. NPF-7 DOCKET NO. 50-339
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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.
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DESIGN FEATURES
- 5. 5 METEOROLOGICAL TOWER LOCATIOk 5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1.
5.6 FUEL STORAGE CRITICALITY 5.6.1.1 The spent fuel storage racks are designed and shall be maintaihed with:
A K,ff equivalent,to less than or equal to 0.95 when flooded with a.
unborated water, which includes a conservative. allowance of 3.4%
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delta k/k for uncertainties, b.
A nominal 14 inch center-to-center distance between fuel assemblies placed in the storage racks.
5.5.1.2 The new fuel pit storage racks are designed and shall be maintained with a nominal 21 inch center-to-center distance between new fuel assembifes such that, on a best estimate basis, k,ff will not exceed.98, with fuel of.the highest anticipated enrichment in place, when aqueous foam moderation is assumed.
5.6.1.3 If new fuel for the first core loading is. stored dry in the spent fuel storage.acks the center-to-center distance between the new fuel assemblies will be administrative 1y limited to 28 inches and the k,ff shall not exceed 0.98 whea aqueous foam moderation is assumed ORAINAGE 5.6.2 The spent fuel pit is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 288.83 feet Mean Sea Level, USGS datum.
. CAPACITY l
5.6.3 The fuel storage pool is designed and shall be maintained with a storage capacity 1.imited to no more than 966 fuel assemblies.
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NORTH ANNA - UNIT 2 5-5 Amendment No.a r
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