ML20138Q116
| ML20138Q116 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 12/13/1985 |
| From: | Rubenstein L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20138Q120 | List: |
| References | |
| NUDOCS 8512270056 | |
| Download: ML20138Q116 (10) | |
Text
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'o, UNITED STATES 8
NUCLEAR REGULATORY COMMISSION o
E WASHINGTON, D. C. 20065
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VIRGINIA ELECTRIC AND POWER COMPANY OLD DOMINION ELECTRIC COOPERATIVE DOCKET NO. 50-338 NORTH ANNA POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 73 License No. NPF-4 i
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Virginia Electric and Power Company, et al., (the licensee) dated February'7, 1985, 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) 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; 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 l
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements i
have been satisfied.
8512270056 851213 PDR ADOCK 05000338 P
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l 1.
l l l 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 The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 73, 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 CDPMISSION h
b Lester S.-
enstein, Director PWR Project irectorate #2 Division of PWR Licensing-A t
Attachment:
Changes to the Technical Specifications Date of Issuance:
December 13, 1985
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ATTACHMENT TO LICENSE AMENDMENT NO. 73 TO FACILITY OPERATING LICENSE NO. NPF-4 DOCKET NO. 50-338 Replace the following page of the Appendix "A" Technical Specifications with the enclosed page as indicated.
The revised page is identified by amendment number and contains vertical lines indicating the area of change.
The corresponding overleaf page is also provided to maintain document completeness.
Remove Page Insert Page 3/4 1-6 3/4 1-6 i
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REACTIVITY CONTROL SYSTEMS BORON NLUTION VALVE POSITION LIMITING CONDITION FOR OPERATION 3.1.1.3.2 The following valves shall be locked, sealed or otherwise l
secured in the closed position except during planned boron dilution or makeup activities a.
1-CH-217 or b.
1-CH-220, 1-CH-241, FCV-1114B and FCV-1113B.
APPLICABILITY: MODES 3, 4, 5, and 6 ACTION:
With the above valves not locked, sealed or otherwise secured in the l
closed position:
a.
In MODES 3 and 4 be in COLD SHUTDOWN within 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> b.
In MODES 5 and 6 suspend all operations involving positive reactivity changes or CORE ALTERATIONS and lock, seal or otherwise secure the valves in the closed position within 15 minutes.
SURVEILLANCE REQUIREMENTS 4.1.1.3.2 The above listed valves shall be verified to be locked, sealed or otherwise secured in the closed position within 15 minutes after a planned boron dilution or makeup activity.
NORTH ANNA-UNIT 1 3/4 1-5 Amendment No. 3
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. (.a REACTIVITY CONTROL SYSTEMS MODERATOR TEMPERATURE COEFFICIENT j
LIMITING CONDITION FOR OPERATION l
3.1.1.4 The moderator temperature coefficient (MTC) shall be:
a.
For the all rods withdrawn, beginning of core life condition
< 0.6 x 10-4 ak/k/ F below 70 percent RATED THERMAL POWER
< 0.0 x 10-4 ak/k/*F at or above 70 percent RATED THERMAL POWER b.
Less negative than -4.0 x 10-4 ak/k/*F for the all rods withdrawn, end of core life at RATED THERMAL POWER.
APPLICABILITY: Specification 3.1.1.4.a - MODES 1 and 2* only#
Specification 3.1.1.4.b - MODES 1, 2 and 3 only#
ACTION:
a.
With the MTC more positive than the limit of 3.1.1.4.a above:
1.
Establish and maintain control rod withdrawal limits sufficient to restore the MTC to within its limit within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
These withdrawal limits shall be in addition to the insertion limits of Specification 3.1.3.6.
2.
Maintain the control rods within the withdrawal limits established above until subsequent measurement verifies that the MTC has been restored to within its limit for the all rods withdrawn condition.
3.
Prepare and submit a Special Report to the Comission pursuant to Specification 6.9.2 within 10 days, describing l
the value of the measured MTC, the interim control rod withdrawal limits and the predicted average core burnup necessary for restoring the positive MTC to within its limit for the all rods withdrawn condition.
4.
With the MTC more negative than the limit of 3.1.1.4b above, be in HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
- With K,ff >_ l.0
- See Special Test Exception 3.10.3 l
NORTH ANNA - UNIT 1 3/4 1-6 Amendment No. 73
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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. 59 License No. NPF-7 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Virginia Electric and Power Company, et al., (the licensee) dated February 7,1985, 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) 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; 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.
l i
l
2.
Accordingly, the license is amended by changes to the Technical Speci-fications as inoicated 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 The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 59, 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
.k.
N Lester S'. Rubenstein, Director PWR Project Directorate #2 Division of PWR Licensing-A
Attachment:
Changes to the Technical Specifications Date of Issuance:
December 13, 1985 i
I
ATTACHMENT TO LICENSE AMENDMENT NO. 59 TO FACILITY OPERATING LICENSE N0. NPF-4 DOCKET NO. 50-338 Replace the following page of the Appendix "A" Technical Specifications with the enclosed page as indicated. The revised page is identified by amendment number and contains vertical lines indicating the area of change.
The corresponding overleaf page is also provided to maintain document completeness.
Remove Page Insert Page 3/4 1-5 3/4 1-5 i
t l
FTT
REACTIVITY CONTROL SYSTEMS MODERATOR TEMPERATURE COEFFICIENT 9
LIMITING CONDITION FOR OPERATION 3.1.1.4 The moderator temperature coefficient (MTC) shall be:
a.
For the all rods withdrawn, beginning of core life condition 5,0.6 x 10-4 ak/k/ F below 70 percent RATED THERMAL POWER
- 5. 0.0 x 10-4 ak/k/ F at or above 70 percent RATED THERMAL POWER b.
Less negative than -4.0 x 10-4 delta k/k/*F for the all rods withdrawn, end of core life at RATED THERMAL POWER.
APPLICABILITY:
Specification 3.1.1.4.a - MODES 1 and 2* only#.
Specification 3.1.1.4.b - MODES 1, 2 and 3 only#.
ACTION:
a.
With the MTC more positive than the limit of 3.1.1.4.a above, operations in MODES 1 and 2 may proveed provided:
1.
Control rod withdrawal limits are established and maintained sufficient to restore the MTC to less positive than 0 delta k/k/*F within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. These withdrawal limits shall be in addition to the insertion limits of Specification 3.1.3.6.
2.
The control rods are maintained within the withdrawal limits established above until subsequent measurement verifies that the MTC has been restored to within its limit for the all rods withdrawn condition.
3.
Prepare and submit a Special Report to the Commission pursuant to Spr.cification 6.9.2 within 10 days, describing the value of the aeasured MTC, the interim control rod withdrawal limits and the predicted average core burnup necessary for restoring the positive MTC to within its limit for the all rods withdrawn condition.
b.
With the MTC more negative than the limit of 3.1.1.4.b above, be in H0T SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
i i
- With K,ff greater than or-equal to 1.0
- See Speciel Test Exception 3.10.3 NORTH ANNA - UNIT 2 3/4 1-5 Amendment No. 47,59 l
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REACTIVITY CONTROL SYSTEMS MODERATOR TEMPERATURE COEFFICIENT SURVEILLANCE REQUIREMENTS 4.1.1.4 The MTC shall be determined to be within its limits during each fuel cycle as follows:
a.
The MTC shall be measured and compared to the BOL Limit of Specifica-tion 3.1.1.4.a. above, prior to initial operation above 5% of RATED THERMAL POWER, after each fuel loading.
b.
The MjC shall be pasured at any THERMAL POWER and compared to -3.1 x 10- delta k/k/ F (all rods withdrawn, RATED THERMAL POWER condition) within 7 EFPD after reaching an equilibrium boron concentration of 300 ppm.
In the event t negativethan-3.1x10giscomparisonindicatedtheMTCismore 0
delta k/k/ F, the MTC shall be remeasured, and compared to the E0L MTC limit of specification 3.1.1.4.b., at least once per 14 EFPD during the remainder of the fuel cycle.
i NORTH ANNA - UNIT 2 3/41-6
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