ML20248E050
| ML20248E050 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 08/02/1989 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20248E054 | List: |
| References | |
| NUDOCS 8908110222 | |
| Download: ML20248E050 (12) | |
Text
--
[p ua,,,k UNITED STATES y
3m
.g NUCLEAR REGULATORY COMMISSION
'r l
W ASHINGTON, D. C. 20555
%,.*..../
VIRGINI A ELECTRIC AND POWER COMPAN_Y_
OLD DOMINION ELECTRIC COOPERATIVE DOCKET NO. 50-338 NORTH ANNA POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY CPERATING LICENSE Amendment No. 121 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 licensee) dated June 8,1989, 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 (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 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.
8908110222 890802 PDR ADOCK 05000338 P
FDC
T..
n L-.
2.
Accordingly, the license is anended by changes to the Technical Speci-fications as indicated in the attachment to this license amendment, and paragraph 2.D.(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 Arendment No.121, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendnent is effective as of the date of issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION
. 4.k
.n f
rbert N. Ber
, Director Project Directorate 11-2 Division of Reactor Projects-1/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
August 2, 1989 1
l l
l l
i
_-____-----___J
ll
' ATTACHMENT TO LICENSE AMERDMENT NO.121 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 lir.es indicating the area of change.
The corresponding overleaf page is also provided to maintain document completeness.
Page 3/4'3-47 3/4 3.
4
- e m
ne x,
TABLE 3.3-9 AUXILIARY SHUTDOWN PANEL MONITORING INSTRI.lMENTATION*
l MINIMUM MEASUREMEN.T CHANNELS INSTRUMENT RANGE OPERABLE
-1.
Reactor Coolant Temperature -
530 - 630'F
-1 Average 2.
Pressurizer Pressure 1700 - 2500 psig 1
3.
Pressurizer Level 0 - 100%
1
.4.
- Auxiliary Feed Pump 500 - 1500 psig i
Discharge Header. Pressure 5.
Emergency Condensate 0 - 100%
1 Storage Tank Level 6.
Charging Flow 0 - 180 gpm 1
-7 Main Steam Line Pressure 0 - 1400 psig 1
- 8., Steam Generator Level 0 - 100%
1
- 9.. Relay Room Positive 0 - 0.00 inches H O 1
2 Ventilation
- Located at Elevation 254' in the Emergency Switchgear and Relay Room.
i at0RTH ANNA - UNIT 1 3/4 3-47 Amendment No.121
._A_-
___m__________._.
7~~
o L
l.
TABLE 4.3-6 i
i AUXILIARY SHUTDOWN PANEL MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL INSTRUMENT CHECK CALIBRATION 1.- Reactor Coolant Temperature - Average M
R-2.
Pressurizer Pressure M
R 3.
Pressurizer Level M
R 4
Auxiliary Feed Pump M
R' Discharge Header Pressure 5.
Emergency Condensate M
R dtorage Tank Level 6.
Charging Flow M
R 7.
Main Steam Line Pressure M
R 8.
Steam Generator Level M
R 9.
Relay Room Positive Ventilation M
R t
NORTt: ANNA - UNIT 1 3/4 3-48 Amendment No.121 t
O
a.
.. caync
./
'o UNITED STATES g.
p.
jj g
NUCLEAR REGULATORY COMMISSION j
WASHINGTON, D. C. 20555 r
(,, /
- ...+
VIRGINIA ELECTRIC AND POWER COMPANY OLD DOMINION ELECTRIC COOPERATIVE DOCKET NO. 50-339 NORTH ANNA POWER STATION, UNIT NO. 2 AMENDMENT TO FACILITY OF4 RATING LICENSE Amendment No. 105 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 Jure 8,1989, 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; E.
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 (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 not be inimical to the comon defense and security or to the health and safety of the public; and E.
The issuance of this anendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable reouireme=ts have been satisfied.
9 u-
.-.___------n-----___a_.
_-~.__,__,-,.x_a.---a---x_-_--
2-2.
Accordir. gly, 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. 104, are hereby incorporated in the license. The licenu.se 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 T E NUCLEAR REGULATORY COMMISSION dJ
&L He ert N. Berk, Director Project Directorate 11-2 Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: August 2, 1989 i
P.
v
~
- ATTACHMENT TO LICENSE AMENDMENT NO.105 TO FACILITY OPERATING LICENSE NO. NPF-7 DOCKET NO. 50-339 Replace the following pages of the Appendix "A" Technical Specifict.tions with the enclosed page as. indicated. The revised pages are identified by arendment nunter and contain vertical lines indicating the area of change.
The corresponding overleaf pages are also provided to maintain document completeness.
Page f
3/4 3-44 3/4 3-45 O O 9
4
_.__a__
b, l
INSTRUMENTATION AUXILIARY SHUTDOWN PANEL HONITORING INSTRUMENTATION i
-LIMITING CONDITION FOR OPERATION 3.3.3.5 The auxiliary shutdown panel monitoring instrumentation channels shown in Table 3.3-9 shall be OPERABLE with readouts displayed external to the Coiltrol room.
APPLICABILITY:
MODES 1, 2 and 3.
ACTION:
a..
With the number of OPERABLE auxiliary shutdown panel monitoring channels less than required by Table 3.3-9, either restore the inoperable channel (s) to OPERABLE status within 7 days, or be in 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.
The provisions of Specification 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.3.3.5 Each auxiliary shutdown panel monitor.ing instrumentation channel shall be demonstrated OPERA 8LE by performance of the CHANNEL CHECK, and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3-6.
NORTH ANNA - UNIT 2 3/4 3-43
TABLE 3.3-9 AUXIEIARY SHUT 00WN PANEL MONITORING INSTRUMENTATION
- MINIMUM MEASUREMENT CHANNELS INSTRUMENT RANGE OPERABLE 1.
Reactor Coolant Temperature -
530 - 630'F 1
Average 2.
Pressurizer Pressure 1700 - 2500 psig 1
3.
Pressurizer Level 0 - 100%
1 4.
Auxiliary Feed Pump 500 - 1500 psig 1
Discharge Header Pressure 5.
Emergency Condensate 0 - 100%
1 Storage Tank Level 6.
Charging Flow 0 - 180 gpm 1
7.
Main Steam Line Pressure 0 - 1400 psig 1
~
8.
Steam Generator Level 0 - 100%
1 9.
Relay Room Positive 0 - 0.50 inches H 0
- 1 2
Ventilation
- Located at Elevation 254' in the Emergency Switchgear and Relay Room.
l 1
l NORTH ANNA - UNIT 2 3/4 3-44 Amendment No. 105 l
l
lJ ~
- l I^
TABLE 4.3-6 4
AUXILIARY SHUTDOWN PANEL MONITORING INSTRUMENTATION.
i l
SURVEILLANCE REQUIREMENTS 1
CHANNEL CHANNEL INSTRUMENT CHECK CALIBRATION 1.
Reactor Coolant Temperature - Average M
R 2.
Pressurizer Pressure M
R i
3.
Pressurizer Level M
R 4
Auxiliary Feed Pump M
R Discharge Header Pressure 5.
Emergency Condensate M
R Storage Tank Level 6.
Charging Flow M
R 7.
Main Steam Line Pressure M
R 8.
Steam Generator Level M
R 9.
Relay Room Positive Ventilation M
R NORTH ANNA - UNIT 2 3/4 3-45 Amendment No. 105
.A
INSTRUMENTATION ACCIDENT MONITORING IN.iiRUMENTATION 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 instrumentation channels less then the total 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 monitsring instrumentation channels less than the MINIMUM CHANNELS OPERA 8LE 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 /> or be in at Idast 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.
SURVEILLANCE REQUIREMENTS 4.3.3.6 Each accident monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL. CHECK and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3-7.
l 1
l i
1
' ORTH ANNA - UNIT 2 3/4 3-46 i
t:
_ _ _ _ _ _ _ - - _ _ _ _ _ _ - _ _ _ _ _ _ _