ML20214T116
| ML20214T116 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 05/13/1987 |
| From: | Rubenstein L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20214T117 | List: |
| References | |
| NUDOCS 8706100132 | |
| Download: ML20214T116 (10) | |
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a gv.....f VIRGINIA ELECTRIC AND POWER COMPANY OLD DOMINION ELECTRIC COOPERATIVE DOCKET NO. 50-338 NORTH AhNA POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE I
Amendment No. 95 License No. NPF-4 Y.
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 April 10, 1986, 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 CiR' 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 (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 Commission's regulations; D.
The issuance of this amendment will not-be inimical to the common oefense 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.
8706100132 E70513 7
PDR ADOCK 05000338 P
PDR l
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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, as revised through Amendment No. 95
, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective within 14 days of the date of its issuance.
FOR THE NUCLEAR P,EGULATORY COMMISSION
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~ Lester S. Rubenstein, Director y
FWR Project Directorate #2 Division of PWR Licensing-A Office of Nuclear Reactor Regulation
Attachment:
Chances to the Technical Specifications Date of Issuance: May 13, 1987
i ATTACHMENT TO LICENSE AMEN 0 MENT NO. 95 TO FACILITY OPERATING LICENSE NO. NPF-4 i
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 pace is also provided to maintain document completeness.
Pace 3/4 3-52 J
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21 TABLE 4.3-7 fs ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIRENENTS b
CHANNEL CHANNEL CHECK CALIBRATION g
INSTRUMENT M
R I.
Containment Pressure M
R 2.
Reactor Coolant Inlet Temperature-Tg (wide range)
M R
3.
Reactor Coolant Inlet Temperature-Teold (wide range) 4.
Reactor Coolant Pressure-Wide Range M
R M
R 5.
Pressurizer Water Level M
R 6.
Steam Line Pressure 7.
Steam Generator Water Level-Narrow Range M
R R
8.
Refueling Water Storage Tank Water Level M
R T$
9.
Boric Acid Tank Solution Level M
R M
R 10.
Auxiliary Feedwater Flow Rate
- 11. Reactor Coolant System Subcooling Margin Monitor M
R M
R y
12.
PORY Position Indicator Ea
- 13. PORV Block Valve Position Indicator M
R g
E M
R 14.
Safety Valve Position Indicator E
- 15. Reactor Vessel Coolant Level Monitor M
R
- 16. Containment Water Level (narrow range)
M R
.2
- 17. Containment Water Level (wise range)
M R
4
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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. 80 s
License No. NPF-7
- c.
1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by Virginia Electric and Power Company, et al., (the licensee) dated April 10, 1986 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 i
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; t
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 notIbe 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.
i
.)
?.
Accordingly, the license is amended by chances 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 contaired in Appendices A and B, as revised through Amendw nt ho.
80, are hereby incorporated in the license. The licensee shall operate the facilit,v in accordance with the Technical Specifications.
3.
This license amendment is effective within 14 days of the date of its issuance.
~
FOR THE NUCLEAR REGULATORY COMMISSION f
e
!f-O j.'%
Lester S. Rubenstein. Director PWR Pro.iect Directorate #2 Division of PWR Licensing-A Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical t
Specifications Date of Issuance: May 13, 1987 4
l ATTACHMENT TO LICENSE AMENOMENT NO. 80 TO FACILITY OPERATING LICENSE NO. NPF-7 DOCKET NO. 50-334 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.
Pace 3/4 3-49 i
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INSTRUMENTATION FIRE DETECTION INSTRUMENTATION LIMITING CONDITION FOR OPERATION As a minimum, the fire detection instrumentation for each fire 3.3.3.7
-detection zone shown in Table 3.3-11 shall be OPERABLE.
Whenever equipment protected by the fire detection instrument APPLICABILITY:
is required to be OPERABLE.
ACTION:
With the number of OPERABLE fire detection instrument (s) number OPERABLE requirement of Table 3.3-11:
Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> establish a fire watch patrol to inspect the zone (s) with the inoperable instrument (s) at least once per hour, unless the a.
instrument (s) is (are) located inside the containment, then inspect the containment at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or monitor the containment air temperature at least once per hour at the locations listed in Specification 4.6.1.5.1.
Restore the inoperable instrument (s) to OPERABLE status within 14 days or prepare and submit a Special Report to the Commission b.
pursuant to Specification 6.9.2 within the next 30 da schedule for restoring the instrument (s) to OPERABLE status.
The provisions for Specifications 3.0.3 and 3.0.4 are not applicable.
t c.
s SURVEILLANCE REQUIREMENTS Each of the above required fire detection instruments which are outside containment shall be demonstrated OPERABLE at least once pe 4.3.3.7.1 by performance of a CHANNEL FUNCTIONAL TEST.
are inside containment shall be demonstrated OPERABLE by the performanc CHANNEL FUNCTIONAL TEST during each COLD SHUTDOWN exceeding l
performed in the previous 6 months.
The NFPA Code 72D supervised circuits supervision associated with the detector alarms of each of the above required fire detection instruments 4.3.3.7.2 j
shall be demonstrated OPERABLE at least once per 6 months.
l The non-supervised circuits between the local panels in Speciff-cation 4.3.3.7.2 and the control room shall be demonstrated 4.3.3.7.3 once per 31 days.
Amendment No. #7,80
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3/4 3-49 NORTH ANNA - UNIT 2 1
TABLE 3.3-11 FIRE DETECTION INSTRUMENTATION MINIMUM DETECTORS REQUIRED INSTRUMENT LOCATION-HEAT SM0KE 1.
Reactor Containment a.
Reactor Coolant Pumps 3
1/ pump
- i b.
Residual Heat Removal Pump Area c.
Cable Penetration Area-7 8
'd.
Recirculation Air' System 2
2.
Control Room a.
Under Floor - Loop 1
,2 2-i b.
Under Floor - Loop 2 2
1 c.
Normal Air Supply #
1 d.
Emergency Air Supply 1
e.
Ceiling Area 10 f.
Return Air Duct 1
3.
Cable Spreading Room 3
4 l
4.
Primary Cable Vault and Tunnel 2
3
)
- 5. -Service Building Cable Vault and j
Tunnel 5
4 i
4 6.
Emergency Switchgear Rooms i-k l
a.
Emergency Air Supply I
b.
Emergency Switchgear and Air t
i Conditioning Rooms 7
7.
Station Battery Room 1/ room l
1 8.
Diesel Generators 2/ room 9.
Fuel Oil Pump House #
I a.
Room 1 1
1 b.
Room 2 1
1 c.
Motor Control Center Room 1
- 10. Rod Control Equipment and Motor Control Center Room (Elevation 280.0) 2
- 11. Auxiliary Building i
I a.
Charging Pump Cubicles 1/ cubicle b.
ExhaustDuct(Northeast-Cubicles)#
1 i.
c.
Exhaust' Duct (, South Central-Cubicles)#
1 d.
ExhaustDuct(Northwest-Cubicles)#
1 NORTH ANNA - UNIT 2 3/4 3-50 Amendment No. 35 4
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