ML20214A828
| ML20214A828 | |
| Person / Time | |
|---|---|
| Site: | North Anna  (NPF-07-A-061, NPF-7-A-61) |
| Issue date: | 02/12/1986 |
| From: | Rubenstein L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20214A831 | List: |
| References | |
| NUDOCS 8602200419 | |
| Download: ML20214A828 (5) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION o
c WASHWGTON, D. C. 20066
\\.....J VIRGINIA ELECTRIC AND POWER COMPANY OLD DOMINION ELECTRIC COOPERATIVE DOCKET NO. 50-339 NORTH ANNA POWER STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICEtiSE Amendment No. 61 License No. NPF-7 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment by Virginia Electric and Power campany, et al., (the licensee) dated January 20, 1986, complies with,he 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;
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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.
B602200419 860212 '
PDR ADOCK 05000339
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2.
Accordingly, the license is amended by changes to the Technic'al 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 The Technical Specifications contained in Appendices.A and B, as revised through Amendment No. 61., are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective January 21, 1986.
f FOR THE NUCLEAR REGULATORY COMMISSION i
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i Lester ubenstein, Director PWR Project Directorate #2 Division of PWR Licensing-A i
Attachment:
Changes to the Technical Specifications 4
Date of Issuance: February 12, 1986 i
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ATTACHMENT TO LICENSE AMENDMENT NO.61 TO FACILITY OPERATING LICENSE NO. NPF-7 DOCKET NO. 50-339 Replace page 3/4 1-6 of the Appendix "A" Technical Specifications with the enclosed page 3/4 1-6.
The revised area is identified by amendment number and contains a vertical line indicating the area of change. The corresponding overleaf page is also provided to maintain document completeness.
Page 3/4 1-6 e
l REACTIVITY CONTROL SYSTEMS j
MODERATOR TEMPERATURE COEFFICIENT LIMITING CONDITION FOR OPERATION 3.1.1.4 The moderator temperature coefficient (MTC) shall be:
i a.
For the a11 rods withdrawn, beginning of core life condition 1 0.6 x 10-4 ak/k/ F below 70 percent RATED THERMAL POWER i
1 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.
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. APPLICABILITY:
Specification 3.1.1.4.a - MODES 1 and 2* onlyf.
Specification 3.1.1.4.b - MODES 1, 2 and 3 onlyf.
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.
Centrol rod withdrawal limits are established and maintained i
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 i
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 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 b.
With the MTC more negative than the limit of 3.1.1.4.b 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 greater than or equal to 1.0
- See Special Test Exception 3.10.3 NORTH ANNA - UNIT 2 3/4 1-5 Amendment No. #7,59
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REACTIVITY CONTROL SYSTEMS MODERATOR TEMPERATURE COEFFICIENT SURVEILLANCE REQUIREMENTS
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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 geasured 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 baron concentration of 300 ppm.
In the event t negative than -3.1 x 10 gis comparisgn indicated the MTC is moredelta k/k/
1 and compared to the EOL MTC limit of specification 3.1.1.4.b.,(1)t a
least once per 14 EFPD during the remainder of the fuel cycle.
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(1)
For fuel cycle 4 only, further measurements may be suspended once an equilibrium boron concentration (all rods withdrawn, RATED THERMAL I-POWER condition) of 20 ppm or less is reached.
NORTH ANNA - UNIT 2 3/41-6 Amendment No. 61
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