ML20206D594
| ML20206D594 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 11/10/1988 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20206D599 | List: |
| References | |
| NUDOCS 8811170145 | |
| Download: ML20206D594 (10) | |
Text
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o, UNITED STATES i
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NUCLEAR REGULATORY COMMISSION WASHINGTON. D. C. 20048
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VIRGINIA ELECTRIC AND POWER COMPANY OLO DOMINION ELECTRIC COOPERATIVE DOCKET NO. 50-338 f
NORTH ANNA POWER STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE J
Amendment No. 106 License No. NPF-4 1.
The Nuclear Regulatory Comission (the ComhJion) has found t'nat-A.
The application for amendment by VirgM. c. ectric and Power Company et al., (the licensee) dated Septee e 8, 1988, as supplemented October 6, 1988, complies with the standaids and requirements of the r
Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I-l B.
The facility will operate in conformity with the application, the provisions of tne 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 (11) 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 connon defense and security or to the health and safety of the public; i
and E.
The issuance of this amendment is in accordance.with 10 CFR Part l
51 of the Comission's regulations and all applicable requirements I
have been satisfied.
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Accordingly, the license is amended by changes to the Technical Speci-fications as indicated in the attachment to this license amendment, and paragraph 2.0.(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, 4
j as revised through Amendment No.106, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
a 3.
This license amendment is effective as of the date of issuance.
FOR TliE HUCLEAR REGULATORY C0tti!SSION
.erbert H. Berkow, Director l
Project Directorate 11-2 Division of Reactor Projects-1/11 Office of Huclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: November 10, 1988
i:
ATTACHMENT TO LICENSE AMENDMENT NO.106 TO FACILITY OPERATING LICENSE NO. NPF-4 00CXET 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 numer and contains vertical lines indicating the area of change.
P,,gge 3/4 6-2
i 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 CONTAINMENT CONTAINMdNT INTEGRITY LIMITING CONDITION FOR OPERATION 3.6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained.
APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION.
Without primary CONTAINMENT INTEGRITY, restore CONTAINMENT INTEGRITY within one hear or be in at least HOT STAN0BY within the next ' -)urs 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 4.6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated:
a.
At least once per 31 days by verifying that:
1.
All penetrations
- not capable of being closed by OPERABLE containment automatic isolation valves and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured in their positions, except as provided in Table 3.6-1 of :ipecification 3.6.3.1.,
and 2.
All equipment hatches are closed and scaled b.
By verifying that each containment air lock is OPERABLE per Specificai. ion 3.6.1.3.
"Except valves, blind flanges and deactiviated automatic valves which are located inside the containment and are locked sealed or otherwise sealed in the closed position. These penetrations shall be verified closed ouring each COLD SHUTDOWN except that such verification ne31 not be perfomed more often than once per 92 days.
, NORTH ANNA - UNIT 1 3/4 6-1
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CONTAINMENT SYSTEMS CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited to:
a.
An overall integrated leakage rate of:
1.
s L, 0.1 percent by weight of the containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at$,,a40.6psig,or A combined leakage rate of s 0.60 L, pressurized to P,,
a 40.6 psig.
b.
for all penetrations and valves subject to Type B and C tests, when APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION:
With either (a) the measured overall integrated containment leakage rate exceeding 0.75 L, valves subject (b) with the measured combined leakage rate for all or penetrations and to Type B and C tests exceeding 0.60 L restore the leakage rate (s) to within the limit (s) prior to increasing t$e, Reactor Coolant System temperature above 200'F.
SURVEILLANCE REOUIREMENTS 4.6.1.2 The containment leakage rates shall be demonstrated at the allowing test schedule and shall be determined in conformance with the criteria specified in Appendix J of 10 CFR 50 using the methods and provisions of ANSI N45.4 1972:
a.
Three Type A tests (Overall Integrated Containment Leakage Rate) shall be conducted at 40 t 10 month intervals during shutdown at P a 40.6 psig during each 10 year service period.
The third test of each set shall be conducted during the shutdown for the 10 year l
plant inservice inspection.*
l
- The third test of the first 10 year service period shall be conducted during
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the 1989 Refueling /10-Year ISI Outage.
NORTH ANNA - UNIT 1 3/4 6 2 bendnent No. 106
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k n UNITED STATES NUCLEAR REGULATORY COMMISSION 3
WASHINGTON, D. C. 20606 VIRGINIA ELECTRIC AND POWER COMPANY OLD DOMINION ELECTRIC COOPERATIVE DOCKETNO.50-33 h0RTH ANNA POWER STATION, UNIT NO. 2 AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendment No. 92 1.icense No. NPF-7 1.
The Nuclear Regulatory Cornission (the Commission) hai found that:
A.
The application for amendment by Virginia Electric and Power Company, et al., (the licensee) dated September 20, 1988, es supplemented October 6,1988, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Cosmission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conforr' with the application, the provisions of the Act, and the les and regulations of the Cosmission; C.
There is reasonable assurance (i) that the d'ctivities 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 amnor.ent will not be inimical to the cossnon 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.
s v
2-4 2.
Accordingly, the license is amended by changes to the Technical Speci-fications as indicated in the attachment to this license amend:nent, 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. 92
, 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.
FOR THE NUCLEAR REGULATORY COMMISSION erbert N. Berkow, Director i
Project Directorate 11-2 Division of Reactor Projects-1/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
November 10, 1988 1
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l ATTACHMENT TO LICENSE AMEN 0 MENT NO. 92 TO FActLITY OPERATING LICENSE NO. NPF-7 DOCKET NO. 50-339 Replace the following page of the Appendix "A" Technical Specifications with the enclosed page as indicated. The revised page is identified by 1
amendee.it nuster anc contains vertical lines indicating the pres of change.
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i 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 CONTAINMENT CONTAINMENT INTEGRITY LIMITING CONDITION FOR OPERATION 3.6.1.1 Primary CONTAllNENT INTEGRITY shall be maintained.
APPLICABILITY:
MODES 1, 2, 3 and 4.
ACTION:
Without primary CONTAINMENT INTEGRITY, restore CONTAINMENT INTEGRITY within one hour or be in at least HOT STAN08Y 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 4.6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated:
a.
At least once per 31 days by verifying that all penetrations
- not capable of being closed by OPERABLE containment automatic isolation valves and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured in their positions, except as provided in Table 3.6-1 of Specification 3.6.3.1., and b.
By verifying that each containment air lock is OPERA 8LE per Specification 3.6.1.3.
c.
After each closing of the equipment hatch, by leak rate testing the equipment hatch seals with gas at Pa, greater than or equal to 40.6 psig, and verifying that when the measured leakage rate for these seals is added to the leakage rates determined pursuant to Specification 4.6.1.2.d for all other Type 8 and C penetrations, the combined leakage rate is less than or equal to 0.60 La.
"Except valves, blind flanges and deactiviated automatic valves which are located inside the containment and are locked sealed or otherwise sealed in the closed position.
These penetrations shall be verified closed during each COLD SHUTDOWN except that such verification need not be performed more often than once per 92 days.
NORTH ANNA - UNIT 2 3/4 6-1
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CONTA!NMENT SYSTEMS CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited to:
a.
An overall integrated leakage rate of:
I 1.
Less than or equal to L 0.1 percent by weight of the containment air per 24 houPs, at P,, greater than or equal to 40.6 psig, or b.
A combined leakage rate of less that: or equal to 0.60 L for all penetrations and valves subject to Type B and C telts, when pressurized to P,, greater than or equal to 40.6 psig, t
i APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION:
With either (a) the measured overall integrated containment leakage rate exceeding 0.75 L, alves(b) with the measured combined leakage rate for all or penetrations and v subject to Type B and C tests exceeding 0.60 L,
restore the overall integrated leakage rate to less than 0.75 L and t$e combined leakage rate for all penetrations subject to Type B and d tests to less than or equal to 0.60 L, prior to increasing the Reactor Coolant System temperature above 200'F.
SURVEILLANCE REOUIREMENTS 4.6.1.2 The containment leakage rates shall be demonstrated at the following test schedule and shall be determined in conformance with the criteria specified in Appendix J of 10 CFR 50 using the methods and provisions of ANSI N45.4 1972:
a.
Three Type A tests (overall Integrated Containment Leakage Rate) shall be conducted at 40 10 month intervals during shutdown at P greater than or equal to 40.6 psig, during each 10 year serviel i
period.
The third test of each set shall be conducted during the shutdown for the 10 year plant inservice inspection.*
l i
- The third test of the first 10-year service period shall be conducted during the 1989 Refueling /10 Year ISI Outage.
i NORTH ANNA - UNIT 2 3/4 6-2 Amendment No. 92
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