ML20196A855
| ML20196A855 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 06/20/1988 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20196A861 | List: |
| References | |
| NUDOCS 8806300133 | |
| Download: ML20196A855 (12) | |
Text
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o UNITED STATES g
[
g NUCLEAR REGULATORY COMMISSION 3
j WASHINGTON, D. C. 20555 j
%,...../
VIRGINTAELEQRI,CANDPOWERCOMPANY OLO 00MINTON E'.ErTRIC C00PERA7!VE OPCV'
.40. 50-338 NORTH ANNA POWER STATION, UNIf NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 104 License No. NPF-4 1.
The Nuclear Regulatory Commission (the Connission) has found that:
A.
The application for amendment by Virginia Electric and Power Company 1
et al., (the licensee) dated March 30, 1988, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the.ct), and the Connission'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 cnd 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.
8806300133 880620 PDR ADOCK 05000338 P
. 2.
Accordingly, the license is amended by changes to the Technical Speci-fications as indicated in the attachment to this license amendment, and paragraph 2.0.(2) of facility Operating License No. NPF 4 is hereby amended to read as follows:
(2) Technical Sgecifications The Technical Specifications contained in Appendices A and 8, as revised through Amendment No.104, 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 14 days.
FOR THE NUCLEAR REGULATORY COMMISSION f'
erbert N. Berkow, Director Project Directorate II-2 Division of Reactor Prujects-l/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance:
June 20, 1988
ATTACNMENT TO LICENSE AMENOMENT N0.104 TO FACILITY OPERATING LICENSE NO. NPF-4 DOCKET N0. 50-338 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages as indicated. -The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
The corresponding overleaf pages are also provided to maintain document completeness, Page 3/4 3-50 3/4 3-51
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INSTRUMENTATION ACCIDENT MONITORING INSTRUMENTATION I
LIMITING CONDITION FOR OPERATION 3.3.3.6 The accident monitoring instrumentation channels shown in Table 3.3-10 shall be OPERABLE.
)
APPLICABILITY:
MODES 1, 2 and 3.
ACTION:
a.
With the number of OPERABLE accident monitoring channels less than the tctal number of channels shown in Table 3.3-10, either restore the inoperable channel (s) to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
b.
With the number of OPERABLE accident monitoring instrumentation channels less than the MINIMUM CHANNELS OPERABLE requirements of Table 3.3-10, either restore the inoperable channel (s) to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> cr be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
c.
The provisions of Specification 3.0.4 are not applicable.
i SURVEILLANCE REQUIREMENTS 4.3.3.6 Each accident monitoring instrumentation channel shall be demonstrated i
OPERABLE by performance of the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3-7.
NORTH ANNA - UNIT 1 3/4 3-49 Arendment No. 64
TABLE 3.3 -10 5
g ACCIDENT MONITORING IJ1STRUMENTATION g
TOTAL NO.
MINIMUM g
0F CHANNELS CJHANNELS OPERABLE C*
1.
Containment Pressure 2
1 2.
Reactor Coolant Inlet Teinperature-Thot (wide range) 2 1
~
3.
Reactor r,oolant Inlet Temperature-Tcold (wide range) 2 1
4.
Reactor Coolant Pressure-Wide Range 1
1 S.
Pressurizer Water Level 1
1 6.
Steam Line Pressure 2/ steam generator 1/ steam generator 5
7.
Steam Generator Water Level-Narrow Range 2/ steam generator 1/ steam generator o
?
8.
Refueling Water Storage Tank Water Level 1
1 9.
Boric-Acid Tank Solution Level 1
1
- 10. Auxiliary Feedwater Flow Rate 1/ steam generator 1/ steam generator i
11.
Reactor Coolant System Subcooling Margin Monitor 2
1 23 12.
PORV Position Indicator 2/ valve 1/ valve
- 13. PORV Block Valve Position Indicator-1/ valve 1/ valve
.N 14.
Safety Valve Position Indicator 1/ valve
'./ valve 4
{
15.
Reactor Vessel Coolant Level Monitor 2
1 a
- 16. Containment Water Level (narrow range) 2 1
17.
Containment Water Level (tride range) 2 1
18.
In Core Thermocouples 4/ core quadrant 2/ core quadrant-
N5 TABLE 4.3-7
$s ACLIDENT MONITORING INSTRUMENTATION SURVElLLANCE REQUIREMENTS c-CHANNEL CifANNEL
.5 INSTRUMENT CHECK CALIBRATION
-4 1.
Containment Pressure M
R 2.
Reactor Coolant Inlet Temperature-T (wide range)
M R
3.
Reactor Coolant Inlet Temperature-Tcold (wi e range)
M R
4.
Reactor Coolant Pressure-Wide Range M
R 5.
Presr.urizer Water Level M
R 6.
Steam Line I'ressure M
R 7.
Steam Generator Water Level-Narrow Range M
R R
8.
Refueling Water Storage Tank Water Level M
R 9.
Boric Acid Tank Solution Level M
R 10.
Auxiliary Feedwater Flow Rate M
R 11.
Reactor Coolant System Subcooling Margin Monitor M
R g
12.
PORV Position Indicator M
R
$g 13.
PORV Block Valve Posit
.>n Indicator M
R 14.
Safety Valve Position Indicator M
R
??
15.
Reactor Vessel Coolant Level Monitor M
R 16.
Containment Water Level (narrow range)
M R
E
{
- 17. Containment Water Level (wise range)
M R
o*
}
18.
In Core Thermocouples M
R
INSTRUMENTATION FIRE DETECTION INSTRUMENTATION LINITING CONDITION FOR OPERATION
)
3.3.3.7 As a minimum, the fire detection instrumentation for each fire l
detection zone shown in Table 3.3-11 shall be OPERABLE.
APPLICABILITY: Whenever equipment protected by the fire detection instrument is required to be OPERABLE.
ACTION:
With the number of OPERABLE fire detection instrument (s) less than the minimum number OPERABLE requirement of Table 3.3-11:
a.
Within I hour establish a fire watch patrol to inspect the zone (s) with the inoperable instrument (s) at least once per hour, unless the 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 Speci fication 4.6.1.5.1.
b.
Restore the inoperable instrument (s) to OPERABLE status within 14 days or prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 30 days outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the instrument (s) to OPERABLE status, c.
The provisions for Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.3.3.7.1 Each of the above required fire detection instruments which are i
outside containment shall be demonstrated OPERABLE at least once per 6 months by performance of a CHANNEL FUNCTIONAL TEST.
Fire detection instruments which are inside containment shall be demonstrated OPERABLE by the performance of a i
CHANNEL FUNCTIONAL TEST during each COLD SHUT 00WN exceeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless performed in the previous 6 months, 4.3.3.7.2 The NFPA Code 720 supervised circuits supervision associated with the detector alarms of each of the above required fire detection instruments shall be demonstrated OPERABLE at least once per 6 months.
(
4.3.3.7.3 The non-supervised circuits between the local panels in Specifi-cation 4.3.3.7.2 and the control room shall be demonstrated OPERABLE at least once per 31 days, j
i NORTH ANNA - UNIT 1 3/4 3-52 Amendment No. 3, 76, 63,95 l
l
8
'o UNITED STATES l
~ ' g?,
NUCLEAR REGULATORY COMMISSION h
WASHINGTON, D. C. 20555 l
\\...../
VIRGINIA ELECTRIC AND POWER COMPANY OLO 00 MIN 10N ELECTRIC COOPERATIVE DOCKET NO. 50-339 NORTH ANNA POWER STATION UNIT N0. 2 n
AMENOMENT TO FACILITY,0PERATING LICENSE Amendment t'o. 91 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 March 30, 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; i
B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission 1
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 t. mmission's regulations; 0.
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.
~
. 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 Amen (,ent No.
91, are hereby incorporated in the license.
The lictslee shall operate the facility in accordance with the Technic Specifications.
3.
This license amendment is effective as of the date of issuance and shall be implemented within 14 days.
FOR THE NUCLEAR REGULATORY COMMISSION
)
I-l 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:
June 20, 1988
e ATTACHMENT TO LICENSE AMENDMENT N0. 91 TO FACILITY 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 amendment number and contains vertical lines indicating the area of change.
The corresponding overleaf page is also provided to maintain document completeness, i
Page 3/4 3-47 3/4 3-48 l
TA8LE 3.3-10 ACCIDENT MONITORING INSTRUMENTATION s
3 TOTAL NO.
MINIMUM OF CHANNELS
{
CHANNELS OPERABLE E
1.
Containment Pressure 2
1
.i 2.
Reactor Coolant Outlet Temperature-T (wide range) 2 1
n 3.
Reactor Coolant Ir.let Temperature-Tcold (w e' range) 2 1
4.
Reactor Coolant Pressure-Wide Range 1
1 S.
Pressurizer Water Level 1
1 6.
Steam Line Pressure 2/ steam generator 1/ steam generator 7.
Steam Generator Water Level-Narrow Range 2/ steam generator 1/ steam generator 8.
Refueling Water Storage Tank Water Level 1
1 9.
Boric Acid Tank Solution Level 1
1 10.
Auxiliary Feedwater Flow Rate 1/3 team generator 1/ steam generator 11.
Reactor Coolant System Subcooling Margin Monitor 2
1 1
12.
PORV Position Indicator 2/ valve 1/ valve
$g 13.
PORV Block Valve Position Indicator 1/ valve 1/ valve
,5 14.
Safety Valve Position Indicator 1/ valve 1/ valve f5.
Reactor Vessel Coolar.t Level Monitor 2
1 3
16.
Containment Water Level (narrow range) 2 1
17.
Containment Water Level (wide range) 2 1
18.
In Core Thermocouples 4/ core quadrant 2/ core quadrant
l TABLE 4.3-7 8g ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS 1
5g CHANNEL CilANNEL INSTRUMENT CilfCK CALIBRATION E
1.
Containment Pressure M
R U
m 2.
Reactor Coolant Outlet Temperature-Thot (wide range)
M R
3.
Reactor Coolant Inlet Temperature-Tcold (w de range)
R 4.
Reactor Coolant Pressure-Wide Range M
R S.
Pressurizer Water Level M
R F
Steam Line Pressure M
R 7.
Steam Generator Water Level-Harrow Range M
R 8
efueling Water Storage Tank Water Level M
R 9.
Boric Acid Tank Solution Level M
R 10.
Auxiliary Feedwater Flow Rate M
R 11.
Reactor Coolant System Subcooling Margin Monitor M
R k
12.
PORV Position Indicator M
R 13.
PORV Block Valve Position Indicator M
R f
14.
Safety Valve Position Indicator M
R g
15.
Reactor Vessel Coolant Level Monitor M
R 0
16.
Containment Water Level (narrow range)
M R
17.
Containment Water Level (wide range)
M R
18.
In Core Thermocouples M
R l
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