ML20080E529
| ML20080E529 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 09/01/1983 |
| From: | John Miller Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20080E532 | List: |
| References | |
| NUDOCS 8309130480 | |
| Download: ML20080E529 (8) | |
Text
[gaasc, o
o, UNITED STATES
, f ) * '.,,f[,g NUCLEAR REGULATORY COMMISSION l
WASHINGTON, D. C. 20555 k..;. /
NORTHERN STATES POWER COMPANY DOCKET N0. 50-282 PRAIRIE ISLAND NUCLEAR GENERATING PLANT UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 65 License No. DPR-42 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Northern States Power Company (the licensee) dated June 10, 1983, 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 Comission's regulations and all applicable requirements have been satisfied.
8309130480 830901 PDR ADOCK 05000282 P
1
- 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-42 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 65, are hereby iricorporated 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 its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION E. lllY!JPLC yl James R. Miller, Chief Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
September 1,1983 i
>D CE Gy
,,f h
UNITED STATES j
g g
NUCLEAR REGULATORY COMMISSION
- 3 N
,. E WASHINGTON, D. C. 20555 49.....,o NORTHERN STATES POWER COMPANY DOCKET NO. 50-306 PRAIRIE ISLAND NUCLEAR GENERATING PLANT UNIT N0. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 59 License No. DPR-60 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Northern States Power Company (the licensee) dated June 10, 1983, 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.
1
)
{
L.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-60 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 59, 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 its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION i
kbi.,IA.-lrin%.Y James R. Miller, Chief Operating Reactc.n Branch #3 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: September 1, 1983 l
I
ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NOS. 65 AND 59 TO FACILITY OPERATING LICENSE NOS. DPR-42 AND DPR-60 DOCKET NOS. 50-282 AND 50-306 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 changes.
Remove Insert TS.3.3.3 TS.3.3.3 TS.3.3.4 TS.3.3.4 Table TS.4.1-1 (pg. 5 of 5)
Table TS.4.1-1 (pg. 5 of 5)
)
i TS.3.3-3 l
c.
(1) The spray additive tank contains not less than 1950 gallons of solution with a sodium hydroxide concentration of not less than 30% by weight.
(2)
The spray additive tank contains not less than 2590 gallons of
- solution with a sodium hydroxide concentration of 9% to 11% by i
weight inclusive.
- Technical specification c(2) above will be applicable when modifications to the spray additive tank are operational for that unit and c(1) will not be applicable.
When the modifica-tions are operational for both units, technical specification c(1) will be deleted.
d.
Manual valves in the above systems that could (if improperly positioned) reduce spray flow below that assumed for accident analysis, shall be blocked and tagged in the proper position. During power opera-tion, changes in valve position will be under direct administrative control.
Automatic valves, interlocks, ducts, dampers, controls and piping-e.
associated with the above components and required for accident condi-tions are operable.
f.
The following motor-operated valve conditions shall exist:
(1)
The Unit 1 operation, cos,cainment spray system motor-operated valves MV32096 and MV32097 shall be closed and shall have the motor control center supply breakers open.
(2)
For Unit 2 operation, containment spray system motor-operated valves MV32108 and MV32109 shall be closed and shall have the motor control center supply breakers open.
2.
During startup operation or power operation, any one of the following conditions of inoperability may exist for each unit provided startup operation is discontinued until operability is restored.
The reactor shall be placed in the hot shutdown condition if during power operation operability is not restored within the time specified.
The reactor shall be placed in the cold shutdown condition if operability is not restored within an additional 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
One fan cooler unit or one duct for a fan cooler unit may be out of a.
service for a period not to exceed 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. Prior to initiating repairs and once every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter, both containment spray pumps and the remaining three fan cooler units shall be demonstrated to be operable.
b.
One containment spray pump may be out of service for a period not to exceed 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. The remaining containment spray pump and the four fan units shall be demonstrated to be operable before initiating repairs and once every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereaf ter.
Prairie Island Unit 1 Amendment No. 65 Prairie Island Unit 2 Amendment No. 59
.J
l TS.3.3-4 l
c.
Any redundant valve or damper required for functioning of the contain-ment air cooling system and the containment spray system during and following accident conditions may be inoperable provided it is restored to operable status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Prior to initiating repairs, all valves in the system that provide redundancy shall be demonstrated to be operable.
i d.
The sodium hydroxide concentration of the spray additive tank may be out of specification for a period not to exceed 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
C.
Component Cooling Water System l.
Single Unit Operation a.
A reactor shall not be made or maintained critical nor shall it be heated or maintained above 200*F, unless the following conditions are satisfied, except as permitted in Specification 3.3.C.1.b. below.
(1)
The two component cooling pumps assigned to that unit are operable.
(2)
The two component cooling heat exchangers assigned to that unit are operable.
(3) All valves, interlocks, instrumentation and piping associated with the above components, and required for the functioning of the system during accident conditions, are operable.
b.
During startup operation or power operation, any one of the following conditions of inoperability may exist provided startup operation is discontinued until operability is restored.
The reactor shall be placed in the hot shutdown condition if during power operation opera-bility is not restored within the time specified, and it shall be placed in the cold shutdown condition if operability is not restored within an additional 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
(1) One of the assigned component cooling pumps may be out of service for a period no.t to exceed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
I (2)
One of the assigned component cooling heat exchangers may be j
out of service for a period not to exceed 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
2.
Two-Unit Operation f
a.
A second reactor shall not be made or maintained critical nor shall it be heated or naintained-above 200*F, unless the following conditions are satisfied, except as provided by Specification 3.3.C.2.b. below.
Prairie Island Unit 1 Amendment No. 49, 65 Prairie Island Unit 2-Amendment No. 43, 59
. ~,. - - -
- = _ _ -
??
TABLE TS.4.1-1 EE (Page 5 of 5) ee EE Channel Functional
Response
EE Description Check Calibrate Test Test Remarks oo
&G i
ec 40.
Auxiliary Feedwater SE Pump Suction Pressure NA R
R NA nn
" " 41.
Auxiliary Feedwater Pump Discharge Pressure NA R
R NA 42.
NaOH Caustic Stand Pipe Level W
R M**
NA gg S
- Each Shift D
- Daily H
m5O' " W - Weekly e
oa M
""M
- Monthly y
??
Q
- Quarterly
$U R
- Each refueling shutdown
[
gg P
- Prior to each startup if not done previous week p
t T
- Prior to each startup following shutdown in excess of 2 days if not done in the previous EE 30 days..
u o
-g g NA
- Not applicable m
u
- See Specification 4.1.D v
- Will be effective 60 days from issuance date of Amendment Nos. 65_ and 59.
.