ML20198L001
| ML20198L001 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 12/17/1998 |
| From: | Kim T NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20198L004 | List: |
| References | |
| NUDOCS 9901040023 | |
| Download: ML20198L001 (12) | |
Text
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't UNITED STATES 3$
NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D.C. *** "1 NORTHERN STATES POWER COMPANY DOCKET NO. 50-282 PRAIRIE ISLAND NUCLEAR GENERATING PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.142 License No. DPR-42 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Northern States Power Company (the licensee) dated September 4,1998, 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; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
Th,ere 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 Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and 4
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 Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility j
Operating License No. DPR-42 is hereby amended to read as follows:
1 9901040023 981217 PDR ADOCK 05000282 P
hr s
2 i
Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 142
. are hereby incorporated in the license. The licensee 4
l shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of issuance, with full implementation within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION 1
/EC Tae Kim, Senior Project Manager Project Directorate 111-1 Division of Reactor Projects - lil/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
December 17, 1998 1
l l
V ATTACHMENT TO LICENSE AMENDMENT NO.142 FACILITY OPERATING LICENSE NO. DPR-42 DOCKET NO. 50-282 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by amendment number and contain verticallines indicating the area of change.
REMOVE INSERT TS.3.1-5 TS.3.1-5 TS.4.18-1 TS.4.18-1 B.4.18-1 B.4.18-1 1
1 I
s TS.3.1-5 1
.*. e 3.1. A. 2. c. (2 ). (a) One PORV may be inoperable for 7 days.
If these conditions y
cannot be met, depressurize and vent the reactor coolant system through at least a 3 square inch vent within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
(b) With both PORVs inoperable, complete depressurization and venting of the RCS through at least a 3 square inch vent within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
(3) Reactor Coolant System average temperature below the temperature specified in the PTLR for disabling both safety injection pumps With Reactor Coolant System temperature less than the temperature specified in the PTLR for disabling both safety injection pumps, when the head is on the reactor vessel and the reactor coolant system is not vented through a 3 square inch or larger vent; both Pressurizer power operated relief valves (PORVs) shall be OPERABLE (except as specified in 3.1. A.2.c. (3). (a) and 3.1. A. 2. c. (3 ). (b) below) with the Over Pressure Protection System enabled, the associated block valve open, and the associated backup air supply charged.
(a) One PORV may be inoperable for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
If these conditions cannot be met, depressurize and vent the reactor coolant system through at least a 3 square inch vent within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
(b) With both PORVs inoperable, complete depressurization and venting of the RC9 through at least a 3 square inch vent within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
3.1.A.3 Reactor Coolant Vent System
- a. A reactor shall not be made or maintained critical nor shall reactor coolant system average temperature exceed 200*F unless Reactor Coolant Vent System paths from both the reactor vessel head and pressurizer steam space are OPERABLE and closed (except as specified in 3.1.A.3.b and 3.1.A.3.c below),
- b. During STARTUP OPERATION and POWER OPERATION, any one of the following conditions of inoperability may exist for each unit provided STARTUP OPERATION is discontinued until OPERABILITY is restored.
If any one of these conditions is not restored to an OPERABLE status within 30 days, be in at least HOT SHUTDOWN 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 hour3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />s:
(1) Either both of the parallel vent valves in the reactor vessel head vent path are inoperable, or the associated vent path segment is inoperable, or (2) Either both of the parallel vent valves in the pressurizer vent path are inoperable, or the associated vent path segment is inoperable, or (3) The vent valve to the pressurizer relief tank discharge line or the associated vent path segment is inoperable, or l
(4) The vent valve to the containment atmospheric discharge line or the associated vent path segment is inoperable.
j
- c. With no Reactor Coolant Vent System path OPERABLE, restore at least one vent path to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT SHUTDOWN within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and 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 />.
Preirie Island, Unit 1 Amendment NO.
406,13&,142 Prairie Island, Unit 2 Amendment NO. 4G3127,133
TS.4.18-1 g
4.1B REACTOR COOLANT VENT SYSTEM PATHS Applicability Applies to the surveillance performed on the Reactor Coolant Vent System paths to verify OPERABILITY.
Objective To assure that the capability exists to vent noncondensible gases from the Reactor Coolant System that could inhibit natural circulation core cooling.
Specification Each Reactor Coolant System vent path shall be demonstrated OPERABLE at least once each refueling cycle interval by a.
Verifying all manual isolation valves in each vent path are blocked and tagged in the open position, b.
Cycling each solenoid operated valve in each vent path through at least one complete cycle of full travel from the control room, and c.
Verifying flow through each Reactor Cooldnt System vent path.
Prairie Island, Unit 1 Amendment No. 4W4,44,142 Prairie Island, Unit 2 Amendment No. hee B4,133 r
l N
s
B.4.18-1 6
v 4.18 REACTOR COOLANT VENT SYSTEM PATHS Bases The manual valves in the Reactor Coolant Vent System are blocked and tagged in the open position to eliminate the possibility that operation of the system could be blocked by the inadvertent closure of any of the system manual valves.
The cycling of each solenoid operated vent valve once each refueling cycle interval snsures the ability of these valves to open if required l
to vent the Reactor Coolant System. More frequent cycling of the valves is not practical because they cannot be isolated from the neactor Coolant System while the plant is operating.
Reactor Coolant Vent System flow will be determined qualitatively to l
assare that there are no blockages in the Reactor Coolant Vent System I
piping. This may be done in a piecewise fashion, where the flow j
verification for different pipe segments may be performed by different procedures using different fluids.
1 l
l Prairie Island, Unit 1 Amendment No. 4Et,142 Prairie Island, Unit 2 Amendment No. 44,133
' W ar uq h
t UNITED STATES l
,f j
NUCLEAR RE2ULATORY COMMISSION e
WASHINGTON, D.C. 306064 201
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NORTHERN STATES POWER COMPANY DOCKET NO. 50-306 PRAIRIE ISLAND NUCLEAR GENERATING PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE 1
Amendment No. 133 License No. DPR-60 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Northern States Power Company (the licensee) dated September 4,1998, complies with the standarcT and requirements of the Atomic Energy Act of 1954, as amendec'(tha Act), and the Commission'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 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 defense and security or to the health and safety of the public; and j
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 Specifications as i
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:
4
o g
4 2
Technical Soecificatigng The Technical Specifications contained in Appendix A, as revised through Amendment No.133
. 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, with full implementation within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION
/
/t Tae Kim, Senior Project Manager Project Directorate Ill-1 Division of Reactor Projects -lil/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: December 17, 1998
s.
ATTACHMENT TO LICENSE AMENDMENT NO. ill FACILITY OPERATING LICENSE NO. DPR-60 DOCKET NO. 50-306 Revise Appendix A Technical Specifications by removing the pages identified below and i
inserting the attached pages. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
REMOVE INSERT I'
TS.3.1-5 TS.3.1-5 i-TS.4.18-1 TS.4.18-1 B.4.18-1 B.4.18-1 i
g TS.3.1-5 3.1. A.2.c. (2). (c) On3 PORV may be inoperablo fer 7 dry 3.
If these conditions cannot be met, depressurize and vent the reactor coolant system through at least a 3 square inch vent within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
(b) With both PORVs inoperable, complete depressurization and venting of the RCS through at least a 3 square inch vent within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
(3) Reactor Coolant System average temperature below the temperature specified in the PTLR for disabling both safety injection pumps With Reactor Coolant System temperature less than the temperature specified in the PTLR for disabling both safety injection pumps, when the head is on the reactor vessel and the reactor coolant system is not vented through a 3 square inch or larger vent; both Pressurizer power operated relief valves (PORVs) shall be OPERABLE (except as specified in 3.1. A.2.c. (3). (a) and 3.1. A. 2. c. (3 ). (b) below) with the Over Pressure Protection System enabled, the associated block valve open, and the associr.ted backup air supply charged.
(a) One PORV may be inoperable for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
If these conditions cannot be met, depressurize and vent the reactor coolant system through at least a 3 square inch vent within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
(b) With beti PORVs inoperable, complete deprecsurization and venting of the RCS through at least a 3 square inch vent within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
3.1.A.3 Reactor Coolant Vent System
- a. A reactor shall not be made or maintained critical nor shall reactor coolant system average temperature exceed 200*F unless Reactor Coolant Vent System paths from both the reactor vessel head and pressurizer steam space are OPERABLE and closed (except as specified in 3.1.A.3.b and 3.1.A.3.c below).
- b. During STARTUP OPERATION and POWER OPERATION, any one of the following conditions of inoperability may exist for each unit provided STARTUP OPERATION is discontinued until OPERABILITY is restored.
If any one of these conditions is not restored to an OPERABLE status within 30 days, be in at least HOT SHUTDOWN 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 hour3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />s:
(1) Either both of the parallel vent valves in the reactor vessel head vent path are inoperable, or the associated vent path segment is inoperable, or (2) Either both of the parallel vent valver in the pressurizer vent path are inoperable, or the associated vent path segment is inoperable, or (3) The vent valve to the pressurizer relief tank discharge line or the associated vent path segment is inoperable, or l
(4) The vent valve to the containment atmospheric discharge line or the associated vent path segment is inoperable.
l
- c. With no Reactor Coolant Vent System path OPERABLE, restore at least one vent path to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT SHUTDOWN within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and 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 />.
Prairie Island, Unit 1 Amendment NO.
4GG FB&,142 3
Prairie Island, Unit 2 Amendment NO. 44%447,133 m
w
TS.4.10-1 4.18 REACTOR COOLANT VENT SYSTEM PATHS Applicability Applies to the surveillance perfomed on the Reactor Coolant Vent System paths to verify OPERABILITY.
Objective To assure that the capability exists to vent noncondensible gases from the Reactor Coolant System that could inhibit natural circulation core cooling.
Specification I
Each Reactor Coolant System vent path shall be demonstrated OPERABLE at least once each refueling cycle interval by:
a.
Verifying all manual isolation valves in each vent path are blocked and tagged in the open position, b.
Cycling each solenoid operated valve in each vent path through at least one complete cycle of full travel from the control room, and l
c.
Verifying flow through each Reactor Coolant System vent path.
i Prairie Island, Unit 1 Amendment No. #,M,142 Prairie Island, Unit 2 Amendment No. 6h64,133
e B.4.18-1 i
e 4.1L REACTOR COOL 7Mr VENT SYSTEM PATHS Bases The manual valves in the Reactor Coolant
...it System are blocked and tagged in the open position to eliminate the possibility that operation of the system could be blocked by the inadvertent closure of any of the system manual valves.
The cycling of each solenoid operated vent valve once each refueling cycle interval ensures the ability of these valves to open if required l
to vent the Reactor Coolant System. More frequent cycling of the valves is not practical because they cannot be isolated from the Reactor coolant System while the plant is operating.
Reactor Coolant Vent System flow will be determined qualitatively to l
assure that there are no blockages in the Reactor Coolant Vent System piping. This may be done in a piecewise fashion, where the flow verification for different pipe segments may be performed by different procedures using different fluids.
hr.
Y Prairie Island, Unit 1 Amendment No. 44,142
}
Prairie Island, Unit 2 Amendment No. -84,133
____M.