ML20198S407
| ML20198S407 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 10/21/1997 |
| From: | Wetzel B NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20198S411 | List: |
| References | |
| NUDOCS 9711140037 | |
| Download: ML20198S407 (12) | |
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NUCLEAR REGULATORY COMMISSION
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NORTHERN STATES POWER COMPANY DOCKET NO. 50 282 PRAIRIE ISLAND NUCLEAR GENERATING PLANT. UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.131 License No. DPR 42 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Northem States Power Company (the licensee) dated November 6,1996 as supplemented April 10 and October 1, 1997, 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 Cummission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safet/ 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.
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:
9711140037 971021 PDR ADOCK 05000292 P
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Technical Soecifications l
The Technical Specifications contained in Appendix A, as revised through Amendment No.131, are hereby incorporated in the license. The licensea shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of issuance, with full r
implementation within 90 days.
FOR THE NUCLEAR REGULATORY COMMISSION
'Ol Beth A. Wetzel, Senior Project Manager Project Directorate lil 1 Division of Reactor Projects - Ill/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technica' Specifications Date of issuance:
October 21, 1997
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ATTACHMENT TO LICENSE A'.4ENDMENT NO.131 i
FACILITY OPERATING LICENSE NO DPR 42 QQCKET 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 vertical lines indicating the area of change.
BEMOVE INSERT i
TS 4.5 3 TS 4.5 3 TS 5.41 TS 5.4-1 t
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3.3.D.
goelino Water System 1.
A reactor shall not be ma#1 or maintained critical nor shall reactor coolant system everage temperature exceed 200'F, unless the following conditions are satisfied (except as speelfied in 3.3.D.2 below).
a.
Tour of the five cooling water pumps are OPERABLE, and if one diesel-driven cooling water pump is inoperable, then 122 cooling water pump shall be aligned as shown in the table below or apply 3.3.D.2.a.
All changes in the valve positions shall be under direct adminic+ :stive c '3 trol.
Ineperable Valve Alignment Power Supply to Pump Bus 27 (#121 cooling water Pump)
- 12 NV-32037 ct MV-32036 closed; and Cooling asseelated Bkr Leeked off Bus 25 Water Pump NV-32034 and MV-32035 open; and both Bkra Locked off
- 22 NV-31034 or NV-32035 elosed; and Cooling the associated Skr Leeked off Bus 26 Water Pump MV-32037 and MV-32036 open; and both Bkre Locked off b.
Two safeguards traveling screens are OPERAELE.
c.
Two cooling water headers are OPERABLE.
d.
A fuel oil supply of 19,000 gallons is available for the diesel-driven cooling water pumps in the interconnected Unit I diesel fuel oil storage tanks. Note that the 19,000 gallon requirement is included in the 70,000 gallon total diesel fuel oil requirement of specification 3.7.A.5 for Unit 1.
Prairic Island Unit 1 Amandment No. 91, 103,131 Prairie Island Unit 2 Amendment No. 84, 96,123
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coweenent Terts 1.
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The safety injection pumps, residual heat removal pumps and containment spray pumps shall be tested pursuant to specification 4.2.
Acceptable levels of performance shall be that the pumps start and resci. their required developed head on minimum recirculation flow and the control board indications and visual observations indicate that the pumps are operating properly for at least 15 minutes.
b.
A test consisting of a manually-initiated start of.each diesel engine, and assumption of load within one minute, shall be conducted monthly.
c.
The vertical motor-driven cooling water pump shall be operated at quarterly intervals. An accep6able level of performance shall be that the pump starts and reaches its required developed head and the control board indications and visual observations indicate that the pump is operating properly for at least 15 minutes.
2.
Centainment Fan Motors The Containment Tan Coil Units shall be run on low motor speed for at least 15 minutes at intervals of one month. Motor current shall be measured and compared to the nominal current expected for the test conditions.
3.
Valves a.
The refueling water storage tank outlet valves shall be tested in accordance with section 4.2.
b.
The accumulator check valves will be checked for CPERABILITY during each refueling shutdown.
c.
The boric acid tank valves to the safety Injection system shall be tested in accordance with section 4.2.
d.
The spray chemical additive tank valves shall be tested in accordance with section 4.2.
e.
Actuation circuits for cooling Water system valves that irolate non-essential equipment from the system shall be tested each refueling outage. Unit 1 SI actuation circuits for Train A and Train 3 valves shall be tested during Unit 1 refueling outages. Unit 2 31 actuation circuits for Train A and Train B valves shall be tested during Unit 2 refueling outages.
f.
All motor-operated valves in the SIS, RNR, Containment spray, cooling Water, and component cooling Water system that are designed for operation during the safety injection or rocirculation phase of emergency core cooling, shall be tested for OPERABILITY at each refueling shutdown.
Prairie Island Unit 1 Amendment No. 103, 104, 131 Prairie Island Unit 2 Amendment No.
96, 97, 123 s
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1 5.4 ENGINEERED SAFETY FEATURES The engineered safety features include the containment system described in Specification 5.2, the emergency core cooling system, the containment air cooling system, the containment spray system, the post-accident combustible gas control system, emergency power supplies, component cooling water system, and the coating water system. These systems are designed to applicable industry codes, the NRC General Design Criteria in Aroendix A to 10CFR50, and NRC Safety Guides. Particular features for the Prairie
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Island plant include the following:
1.
Several of the features are shared between the two units, includirig the onsite diesel generators, the cooling water system, and the motor.
driven pumps of the auxiliary feedwater system. Shared systems are designed to mitigate the effects of an accident in one unit and simultaneously provide for a hot shutdown in the other unit (Reference 1).
2.
The emergency cooling water pumps are driven by diesel engines. These diesel engines are designed and will be tested to the same reliabi!ity criteria as those for the diesel generators that supply emergency electrical power (Reference 2).
3.
The cooling water system is automatically divided into two (2) redundant loops by motor-driven valves which are actuated by a safety injection signal. Branc.hes ;erving non-safety related equipment in the turbine rooms are isolated from the class I cooling water loops by motor operated valves. These valves are closed by an SI signal coincident with low header pressure.
Reference
- 1. FSAR, Table 1.2 2
- 2. USAR, Section 10.4 Prairie Island Unit 1 Amendment No. 80,131 Prairie Island Unit 2 Amendment No. iG,123
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UNITE] STATES j
NUCLEAR REGULATORY COMMISSION
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'%,*... *,o NORTHERN STATES POWER COMPANY POCKET NO 50-306 PRAIRIE ISLAND NUCLEAR GENERATING PLANT. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.123 License No. DPR-60 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Northem States Power Company (the licensee) dated November 6,1996 as supplemented April 10 and October 1, 1997, 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 appl: cat!on, 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 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 Operating License No. DPR-60 is hereby amended to read as follows:
t r
Iggh.nical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.123 are hereby incorporated in the license, The licensee shall i
operate the facility in accordance with the Technical Specifications.-
3.
This license amendment is effactive as of the date of issuance, with full implementation within 90 days, FOR THE NUCLEAR REGULATORY COMMISSION hv b
~
Beth A. Wetzel, Senior Project Manager Project Directorate 1111 Division of Reactor Projects -Ill/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications i
Date nf lasuance:
October 21, 1997 i
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l ATTACHMENT TO LICENSE AMENDMENT NO,123 FACILITY OPERATING LICENSE NO. DPR-60 DOCKET NO. 50-306 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 vertical lines indicating the area of change.
REMOVE INSERT TS 3.3 7 TS 3.3-7 TS 4.5-3 TS 4.5-3 TS 5.41 TS 5.41
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l Ts.3.3-7 3.3.D.
Cooline Water svetam 1.
A reactor shall not be made or maintained critical nor shall reactor coolant system average temperature exceed 200*F, unless the following conditions are satistled (except as specified in 3.3.D.2 below).
a.
Four of the five cooling water pumps are OPERABLE, and if one diesel-driven cooling water pump is inoperable, then 121 cooling water pump shall be aligned as shown in the table below or apply 3.3.D.2.a.
All changes in the valve positions shall be under direct administrative control.
Inoperable Valve Aligrw,ent Power supply to Pump Bus 27 (#121 Cooling Water Pump)
- 12 NV-32037 or MV-32036 closed; and Cooling 1112einted Bkr Locked off Bus 25 Water Pump NV-32034 and MV-32035 open; and both Bkre Locked off
- 22 NV-32034 or NV-32035 closed: and
. Cooling the asseeinted Bkr Locked off Bus 26 Water Pump MV-32037 and MV-32036 open; and occh Bkra Locked off b.
Two safeguards traveling screens are OPERABLE.
c.
Two cooling water headers are OPERABLE.
d.
A fuel oil supply of 19,000 gallons is available for the diesel-driven cooling water pumps in the interconnected Unit I diesel fuel oil storage tanks. Note that the 19,000 gallon requirement is included in the 70,000 gallon total diesel fuel oil requirement of Specification 3.7.A.5 for Unit 1.
Prairie Island Unit 1 Amendment No. 91, 103.131
- Prairie' Island Unit 2 Amendment No. 84, 96,123 4
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gpreenent Tests 1.
Purcs a.
The safety injection pumps, residual heat rwmoval pumps and containment spray pumps shall be tested pursuant to specification 4.2.
Acceptable levels of performance shall be that the pumps start and reach their required developed head on minimum recirculation flow and the control board indications and visual observations indicate that the pumps are operating properly for at least 15 minutes.
b.
A test consisting of a manually-initiated start of.each diesel engine, and assumption of load within one minute, sha.1 be conducted monthly.
c.
The vertical motor-driven cooling water pump shall be operated at quarterly intervals. An acceptable level of performance shall be that the pump starts and reaches its required developed head and the control board indications and visual observations indicate that the pump is operating properly for at least 15 minutes.
2.
Containment ran Motqrg The Containment Tan Coil Units shall be run on.1.ow motor speed for at least 15 minutes at intervals of one month. Motor current shall be measured and compared to the nominal current expected for the test conditions.
3.
Valves a.
The refueling water storage tank outlet valves shall be tested in accordance with Section 4.7.
b.
The accumulator check valves will La checked for OPERABILITY during each refueling shutdown.
c.
The boric acid tank valves to the Safety Injection System shall be tested in accordance with Section 4.2.
d.
The spray chemical additive tank valves shall be tested in accordance with Section 4.2.
e.
Actuation circuits for Cooling Water System valves that isolate non-essential equipment from the system shall be tested each refueling outage. Unit 1 SI actuation circuits for Train A and Train B valves shall be tested during Unit 1 refueling outages. Unit 2 SI actuation circuits for Tre.in A and Train B valves shall be tested during Unit 2 refueling
- outages, f.
All motor-operated valves in the SIS, RHR, Containment Spray, cooling Water, and Compont..i Tooling Water System j
that are designed for operation during the safety injection or recirculation phase of emergency core cooling, shall be tested for OPERABILITY at each refueling shutdown.
Prairie Island Unit 1 Amendment No. 103, 104, 131 Prairie Island Unit 2 Amendment No.
96, 97, 123
l TS.5.4 1 5.4 ENG!NEERED SAFETY FEATURES The engineered safety features include the containment system described in Specification 5.2, the emergency core cooling system, the containment l
air cooling system, the containment spray system, the post-accident combustible gas control system, emergency power supplies, component cooling water system, and the cooling water system. These systems are designed to applicable industry codes, the NRC General Design Criteria in Appendix A to 10CFR50, and NRC Safety Guides. Particular features for the Prairie Island plant include the following:
1.
Several of the features are shared between the two units, including the onsite diesel generators, the cooling water system, and the motor.
driven pumps of the auxiliary feedwater system. Shared systems are designed to mitigate the effects of an accident in one unit and s:multaneously provide for a hot shutdown in the other unit (Reference 1).
2.
The emergency cooling water pumps are driven by diesel engines. These diesel engines are designed anJ will be tested to the same reliability criteria as those for the diesel generators that supply emergency electrical power (Reference 2).
3.
The cooling water system is automatically divided into two (2) redundant loops by motor-driven valves which are actuated by a safety injection signal. Branches serving non safety related equipment in the turbine rooms are isolated from the class I cooling water loops by motor operated valves. These valves are closed by an $1 signal coincident with low header pressure.
Reference
- 1. FSAR, Table 1.2-2
- 2. USAR, Section 10.4 Prairie Island Unit 1 Amendment No. 80,131 Prairie Island Unit'2 Amendment No. ;:4,123 y
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