ML20246E626
| ML20246E626 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 07/07/1989 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20246E630 | List: |
| References | |
| NUDOCS 8907120323 | |
| Download: ML20246E626 (10) | |
Text
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UNITED STATES Y
NUCLEAR REGULATORY COMMISSION n-5 WASHINGTON, D. C 2456 s.,...../
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.118 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 et al., (the ifcensee) dated July 20, 1988, 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 ruies and regulations of the Comission; C.
Thereisreasonableassurance(i)thattheactivitiesauthorized 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 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 51 of the Commission's regulations and all applicable requirements have been satisfied.
e907120323 890707 DR ADOCK 0500
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-2 2.
Accordingly, the license is amended by changes to the Technical Speci-fications as indicated in the attachment to this license amendment, dnd paragraph 2.D.(2) of Facility Operating License No. NPF-4 is hereby amended to read as follows:
(2) TechnicalSpecificationg i
The Technical Specifications contained in Appendices A and B, as revised through Amendment No.118, 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 issuance and shall
-be implemented within 30 dayr.
FOR THE NUCLEAR REGULATORY C0!HISSION D-Herbert N. Berkow, Director Project Directorate II-2 Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: July 7, 1989 l
ATTACHMENT TO LICENSE AMENDMENT NO.118 i.
TO FACILITY OPERATING LICENSE NO. NPF-7 DOCKET NO. 50-339 Replace the following page af the Appendix "A" Technical Specifications with the enclosed page as indicated. The revised page is identified by amendment nunber find contains vertical lines indicating the area of change.
The corres-ponding overleaf page is also provided to maintain document completeness.
- f. ate 3/4 4-16 l
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3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE 1
1.
LEAKAGE DETECTION SYSTEMS l
LIMITING CONDITION FOR OPERATION j
l 3.4.6.1 The following Reactor Coo'lant System leakage detection systems shall be OPERABLE:.
1 The containment att.0 sphere particulate and gaseous radioactivity l]
a.
monitoring system, and l
b.
The containment sump level and discharge flow measurement system.
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APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION:
With one of the above required leakage detection ' systems' inoperable, operation may continue for up to 30 days provided a RCS leakrate calculation (Specification 4.4.6.2.1.d) is performed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Otherwise, be in at least HOT STANOBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.4.6.1 The leakage detection systems shall be demonstrated OPERABLE by:
a.
Containment atmosphere particulate and gaseous radioactivity
-l monitoring system - performance of CHANNEL CHECX, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL. TEST at the frequencies
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specified in Table 4.3-3, b.
Containment sump level and discharge flow measurement system -
l performance of CHANNEL CALIBRATION at least once per 18 months.
NORTH ANNA - UNIT 1 3/4 4-16 Amendment No.118
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%,j UNITED STATES h-7 NUCLEAR REGULATORY COMMISSION n
WASHINGTON, D. C. 20655 -
- y **...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 LICENSE Amendment No.102 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, et al., (the licensee) dated July 20, 1988, 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 (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 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 51 of the Comission's regulations and all applicable requirements have been satisfied.
_m____-_______
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 ~
The Technical Specifications contained in Appendices A and B, as revised through Amendment No.102
, 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 issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION Herbert N.. Berkow, Director
' Project Directorate II-2 Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: July 7, 1989 O
p O
l
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ATTACHMENT TO LICENSE AMENDMENT NO.102 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 corres-ponding overleaf page is also provided to maintain document completeness.
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l REACTOR COOLANT SYSTEM l-3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE LEAKAGE DETECTION SYSTEMS LIMITING CONDITION FOR OPERATION t
~
3.4.6.1 The following Reactor Coolant System leakage detection systems shall be OPERABLE:
The containment atmosphere particulate and gaseous radioactivity l
a.
monitoring system, and b.
The containment sump level and discharge flow measurement system.
APPLICABILITY: MODES 1, 2, 3 and 4.
I ACTION:
With one of the above required leakage detection systems inoperable, operation may continue for up to 30 days provided a RCS leakrate calculation (Specification 4.4.6.2.1.d) is performed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Otherwise, be in at least 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 /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.4.6.1 The leakage detection systems shall be demonstrated OPERABLE by:
Containment atmosphere particulate and gaseous radioactivity
(
a.
monitoring system - performance of CHAhNEL CHECK, CHANNEL i
CALIBRATION, and CHANNEL FUNCTIONAL TEST at the frequencies
[
specified in Table 4.3-3, b.
Containment sump level and discharge flow measurement system -
[
performance of CHANNEL CALIBRATION at least once per 18 months.
NORTH ANNA - UNIT 2 3/4 4-16 Amendment No.102 i
o