ML20087H823
| ML20087H823 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 03/06/1984 |
| From: | John Miller Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20087H827 | List: |
| References | |
| NUDOCS 8403210206 | |
| Download: ML20087H823 (9) | |
Text
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UNITED STATES E
NUCLE AR REGULATORY COMMISSION i
E WASHING i ON, D. C. 20555
- f o\\...../
VIRGINIA ELECTRIC AND POWER COMPANY CLD DOMINION ELECTRIC COOPERATIVE DOCKET N0. 50-338 NORTH ANNA POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 52 License No. NPF-4 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Virginia Electric and Power Company (the licensee) dated August 24, 1983, 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 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 (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 Comission'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 Comission's regulations and all applicable requirements have been satisfied.
8403210206 840306 PDR ADOCK 05000338 P.
PM F-
. 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 2
The Technical Specifications contained in Appendices A and 8, as revised through Amendment No. 52,- 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 b
/
James R. Miller, Chief Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: March 6, 1984 i
r
I ATTACHMENT TO LICENSE AMENDMEili AMENDMENT NO. 52' TO FACILITY OPERATING LICENSE NO. NPF-4 1
i DOCKET NO. 50-338 Replace the following page of the Appendix "A" Technical 5pecifications with the enclosed page as indicated. The revised page is identified by Amemdment number and contains vertical lines indicating the area of change.
The corresponding overleaf page is provided to maintain document completeness.
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r TABLE 3.6-1 (Cont.)
2 SM VALVE ISOLATION TIME tiUMBER FUNCTION (SEC.)
E D
G.
STEAM LINE ISOLATION E
1.
TV-MS-101A#
Main Steam Line Trip Valve 5
Q 2.
TV-MS-101B#
Main Steam Line Trip Valve 5
3.
TV-MS-101 C#
Main Steam Line Trip Valve 5
R E
TABLE 3.6.-l (Cont.)
VALVE ISOLATION TIME gj NUMBER FUNCTION (SEC.)
2-H.
RELIEF l.
RV-1203 Letdown Line Relief Valve NA Ea R
a
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- Valve not subject to Type "C" leakage test.
- Valve position maintained by administrative control 3,
8il NA - Not applicable R
~
E
- - Requires testing per Technical Specifications 4.6.3.1.la or 4.6.3.1.2d.
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UNITED STATES y'
',g NUCLEAR REGULATORY COMMISSION 7,.
c WASWNG TON, D. C. 20555
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VIRGINIA ELECTRIC AND POWER COMPANY OLD DOMINION ELECTRIC COOPERATIVE DOCKET NO. 50-339 NORTH ANNA POWER STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 36 License No. NPF-7 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Virginia Electric and Power Company (the licensee) dated August 24, 1983, 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 CFR Chapter I; B.
The facility will operate in confonnity 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 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 conmon 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 Concission's regulations and all applicable requirements have been satisfied.
. 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.C.(2) of Facility Operating License No. NPF-7 is hereby amended to read as follows:
(2) Technical Specifications e
The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 36, 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 1
ou
/ James R. Miller, Chief Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: March 6, 1984 i
i ATTACHMENT TO LICENSE AMENDMENT 1
AMENDMENT N0. 36 TO FACILITY OPERATING LICENSE NO. NPF-7 DOCKET NO. 50-33.,
Replace the following page of the Appendix "A" Technical Specifications with the enclosed page as indicated.
The revised page is identified by Amemdment number and contains vertical lines indicating the area of change.
The corresponding overleaf page is also provided to maintain document completeness.
4 Page 3/4 6-31 i
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TABLE 3.6-1 (Cont.)
?
E MAXIMUM g
VALVE ISOLATION TIME NUMBER FUNCTION (SEC.)
[
t 37.
2-FW-94#
Feedwater to Steam Generators NA 38.
2-FW-1268 Feedwater to Steam Generators NA 39.
2-WT-41#
Chemical feed Lines NA 40.
2-WT-53#
Chemical Feed Lines NA y
41.
2-WT-69#
Chemical Feed Lines NA
[
42.
2-FW-70#
Auxiliary Feedwater to Steam Generator NA
[;
43.
2-FW-102#
Auxiliary Feedwater to Steam Generator NA 44.
2-FW-134#
Auxiliary feedwater to Steae Generator NA 45, 2-RS-103#
Casing Cooling to Outside Recirculation Spray Pump NA 46.
2-RS-Il8#
Casing Cooling to Outside Recirculation Spray Pump NA 47.
NA Fire Protection Supply (Penetration 34)
NA 8
an O
E 4
I TABLE 3.6-1 (Cont.)
E MAxrMun VALVE ISOLATION TIME c
NUMBER FUNCTION (SEC.)
m G.
STEAM LINE ISOLATION 1.
TV-MS201A#
Main Steam Line Trip Valve 5
2.
TV-MS2018#
Main Steam Line Trip Valve 5
3.
TV-MS201C#
Main Steam Line Trip Valve 5
Y
[
ll.
RELIEF d:
1.
RV-2203 Letdown Line Relief Valve NA Ng
- Valve not subject to Type "C" leakage test.
{
- Valve position maintained by administrative control S
NA - Not applicable p
- - Requires testing per Technical Specifications 4.6.3.1.la or 4.6.3.1.2d.
.