ML20114D067
| ML20114D067 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 08/20/1992 |
| From: | Marsh L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20114D069 | List: |
| References | |
| GL-87-09, GL-87-9, NUDOCS 9209040122 | |
| Download: ML20114D067 (12) | |
Text
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3 12 < ii NUCLEAR REGULATORY COMMISSION UNITED STATES
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NORTHERN STATES POWER COMPANl i
DQ(KfT NO 50-282 fBAIRIE ISLAND NUCLEAR GENERATING PLANT. UNIT N0 1 l
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 101 8.icense No. DPR-42 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Northern States Pcwer Company (the i
licensee) cated June 15, 1992, complies with the standards and l
requiiements 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.
TF2 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 (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 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 Specifica-tions as indicated in the attachment to this license amendment, and para-4 graph 2.C.(2) of facility Operating License No. OPR-42 is hereby amended to read s follows:
9209040122 920820 ADOCK0500g2 PDR P
. Technical SDecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.101 are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the
'ech11 cal Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION r.<
sdyard B arsh, Director Project Di ectorate 111-1 Division of Reactor Projects lil/lV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: August 20, 1992 a
ATTACHMENT T0 tICENSE AMENDMENT NO. In1 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 vertical lines indicating the area of change.
11EMOVE 1t151111 TS-v TS-v TS.4.0-1 TS.4.1-1 TS.4.1-1 h
4 TS v TABLE OF CORTERTS (Continued)
TS SECTION TITLE PACE 4.0 SURVEILLANCE REQUIREt(ENTS 75.4.0 1 l
4.1 Operational Safety Review TS.4.1-1 4.2 Inservice Inspection and Testing of Pumps and Valves Requirements 75.4.2 1 A. Inspection Requirements TS.4.2-1 B. Corrective Measures TS.4.2 2 C. Records 75.4.2 3 4.3 Primary coolant System Pressure Isolation Valves 75.4.3 1 4.4 Containment System Tests 75.4.4 1 A. Containment Leakage Tasts TS.4.4 1 B. Emergency Charcoal Pilter Systems T5.4.4 3 C. Containment Vacuum Breakers TS.4.6*4 1
D. Residual Heat Removal System TS.4.4 4 E. Containment Isolation Valves 75.4.4 5 T. Post Accident Containment Ventilation System TS.4.4 5 C. Containment and Shield Building Air Temperature TS.4.4 5 H. Containment Shell Temperature 75.4.4 5
- 2. Electric Hydrogen Recombiners 75.4.4 5 4.5 Engineered Safety restures TS.4.5 1 A.
System Tests TS.4.5 1
- 1. Safety Injection System TS.4.5 1
- 2. Containment Spray System TS.4.5 1
- 3. Containment ran Coolers 75.4.5 2 4 Compenent Cooling Water System TS.4.5 2
- 5. Cooling Water System
-T5.4.5 2 B. Component Tests T5.4.5 2
- 1. Pumps TS.4.5 2
- 2. Containment Pan Motors 75.4.5 '
- 3. Valves 75.4.5 3 4.6 Periodic Testing of Emergency Power System TS.4.6 1 A. Diesel Generators TS.4.6 1 B. Station Batteries TS.4.6 3 C. Pressurizer Heater Emergency Power Supply TS.4.6 3 4.7 Main Steam Isolation Valves TS.4.7 1 4.8 Steam and Power Conversion Systems TS.4.8 1 A. Auxiliary 7eedwater System TS.4.8 1 B, Steam Cenerator Power Operated Relief Valves TS.4.8 2 C. Steam Exclusion System TS.4.8 2 4.9 Reactivity Ar.omalie, TS.4.9 1 4.1u racia' tion Environmental Monitoring Program TS.4.10 1 A. Sample Collection and Analysis 75.4.10 1 B. Land Use Census TS.4.10 2
- c. Interlaboratory Comparison Program TS.4.10 2 4.11 Radioactive Source Leakage Test TS.4.11 1 Prairie Island Unit 1 - Amendment No. ES,73,$1,101 Prairie Island Unit 2 - Amendment No. EE,EE E!,94-
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TS.4.0 1 4.
SURVEILIANCE REOUIREMENTS 4.0 Annlicability A.
Each surveillance Requirement shall be performed within the specified time interval with the following exceptions:
1.
Specific time intervals between tests may be adjusted plus or minus 25% to accommodate normal test schedules.
2.
The intervals betveen tests scheduled for refueling shutdowns shall not exceed tvo years.
B.
Failure to perfern a Surveillance Requirement within the allowed surveillance interval, defined by Specification 4.0 A, shall constitute noncompliance with the OPEPA511.17Y requirements for a Limiting conditicn for Operation.
The time limits of the ACTION-requirements are applicable at the time it is identified that a Surveillance Requirement has not been performed. The ACTION requirements may be delayed for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to permit the completion of the surveillance when the allevable outage time limits of the Aw'710N requirements are less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Surveillance Requirements do not have to be perforned on inoperable equipment.
W 1
Prairie-Island Unit 1 - Amendment ho.101 Prairie Island Unit 2 - Amendment No. 94
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TS.4.1 1 3
4.1 QgEBATIONAL SATETY REVIEV t
AcelicE lity 7;;"*,
w ia; to items directly related to safety limits and limiting conditions for
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'f3 che minimum frequency and type of surveillance te he applied
, ipment and conditions.
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A.
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. tion, test e g, and checking of instrumentation channele and
.ng of logic channels shall be performed as specified in Tabla 1.
3.
Equig ant tests shall be conducted as specif4'o in Table c.
S ampi.
- ests shall be conducted as specified in Table A
I,.
Wenever the plant condition is such that a system or coy onent is not required to be operable the surveillance testing as#*cisted with that system or co ponent may be discontinuac'.
The asterirsed items in Tables 4.1 1, 4.1 2A, and 4,1 2B are requirsd a; 411 tirec. hewever, Disconti id.urveillance tests shall be resumed a rs t. ban one test interval
-fore establishing plar.t conditions requ2 *:n; OPERASILITY of the associated my:. m -
cepone r:t, unless such testing is nat practicable (i.e.
nuclec..ser ranp calibration cannot be done prior to reaching pusc. op e ra ti e t., 5 which case the testing will be retumed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> c f. ; t.aining the plant cond! tion which permits testing to be accomplished.
4 Prairie Island ' nit 1 - Amentnant No JJ,31,1UI J
Prairie Island Unit 2 - Amendment No II.M,34
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UNITED STATES
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WASHINGTON, D C 20%5 ILO3THERN STATES POWER COMPANY DOCKET NO. 50-306 PRAIRIE ISLAND NUCLEAR GENERATING PLANT. UNIT NO. 2 AMENDMENT TO FACILITY OPER4 TING LICENSE Amendment No. 94 License No. DPR-60 1.
The Nuclear Pegulatory Commission (the Commission) has found that:
A.
The application for amendment by Northern States D -
Company (the licensee) dated June 15, 1992, complies with the atendards and requirements of the Atomic Energy Act of 1954, as :,nended (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.
There is reasonable assurance (i) that the activities author. zed by i
d 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 regelations;
[
D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the publim; 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 Specifica-tlorr as indicated in the attachment to this license amendment, and pa m-graph 2.C.(2) of Facility Operating License No OPR-60 is hereby mnded to read as follows:
)
. Technital Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 94 are hereby incorporated in the license.
The licensee shall operate tbo 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 Y
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Director Prcject Director; 1 111-1 Division of Reacter Projects Ill/IV/V Office of Nuclear Reactor Pegulation
Attachment:
Changes to the Technical Specifications Date of Issuance: August 20, 1992 1
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ATTACHMENT TO LICENSE AMENDMENT N0. 94 FACILITY OPERATING LICENSE NO. DPR-60 DOCKET N0. 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.
i.
REMCVE INSERT TS-v TS-v TS.4.0-1 TS.4.1-1 TS.4.1-1 5
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TS v TABLE OF CORTENTS (Continued)
TS SECTION TITLE PACE 4.0 SURVEIL 1ANCE REQUIREMENTS TS.4.0 1 l
4.1 Operational Safety Review TS.4.1-1 4.2 Inservice Inspection and Testing of Pumps and Valves Requirements TS.4.2 1 A. Inspection Requirements TS.4.2-1 B. Corrective Measures
'1S.4.22 C. Records TS.4.2-3 4.3 Primary Coolant System Pressure Isolation Valves TS.4.3 1 4.4 Containment System Tests TS.4.4 1 A. Containment leakage Tests TS.4.4-1 B. Emergency Charcoal Filter Systems TS.4.4 3 C. Containment Vacuum Breakers TS.4.4 4 D. Residual Heat Removal System TS.4.4 4 E. Containment Isolation Valves TS,4.4 5 F. Post Accident Containment Ventilation System TS.4.4-5 G. Containment and Shield Building Air Temperature TS.4 4-5 4
H. Containment Shell Tempersture TS.4.4-5
- 1. Electric Hydrogen Recombiners TS.4.4 5 4.5 Engineered Safety Features TS.4.5 1
-A. System Tests TS.4.5-1
- 1. Safety Injection System TS.4.5 1
- 2. Containment Spray System TS.4.5 1 3, Containment Fan Coolers TS.4.5 2 4 Compcnent cooling Water System TS.4.5 2
- 5. Cooling Vater System 75.4.5 2 B. Component Tests 75.4.5 2
- 1. Pumps TS.4.5-2
- 2. Containment Fan Motors 75.4.5-3
- 3. Valves TS,4.5 3 4.6 Periodic Testing of Emergency Power System TS.4.6 1 A. Diesel Generators TS.4.6 1 B. Station Batteries TS.4.6 3 C. Pressurizer Heate.r Emergency Power Supply TS.4.6 3 4.7 Main Steam Isolation Va 6
TS.4,7-1 4.B Steam r.d Power Conversicu fysters TS.4.8-1 A. Auxiliary Feedwater System TS.4.8 1 B. Steam Generator Power Operated Relief Valves TS.4.8 2 C. Steam Exclusion System TS.4.8-2 4.9 Reactivity Anomalies TS.4.9-1 4.10 Radiation Environmental Monitoring Program TS.4.10-1 A. Sample Co11ercion and Analysis T5.4.10 1 B. Land Uss Census TS.4.10 2 C. Interlaboratory Comparison Program TS.4.10 2 4.11 Radioactive Source Leakage Test TS.4.11-1 Prairie Island Unit 1 - Amendment No. E9,73.91,101 Prairie Island Unit 2 - Amendment No. E3,6E,$9,94 J
TS.4.0 1 4.
EURVEILIA E 2EOUIREMENTS 4.0 Amelicabilin A.
F.ach surveillance Requirement shall be performed within the specified time interval with the following exceptions:
1.
Specific time intervals between zests may be adjusted plus or minus 25% to accommodate normal test achedules.
2.
The intervals between tests scheduled for refueling shutdowns shall not exceed two years.
B.
Failure to perforu a Surveillance Requirement within the allowed surveillance interval, defined by Specification 4.0.A, shall constitute noncompliance with the OPT.RASILITY requiretients for a Limiting Condition for Oparation. The time limits cf the ACTION rsquirements are applicable at the time it is identified that a Surveillance Requirement has not been performed.
The ACTION requirements may ba delayed for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to permit the completion of the surveillan:e when the allowable outage time limits of the ACTION requirements are less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Surveillance Requirements do not have to be performed on' inoperable equipeent.
Prairie Island Unit 1 - Amendment No.101 Prairie Island Unit 2 - Amendment No. 94
.n TS.4.1-1 4.1 OPERATIONAL SAFETY REVIEV Anblicability Applies to items directly related to safety limits and limiting conditions for operation.
Obinetive To specify the minimum frequency and type. of surveillance to be ~ applied to plant equipment and conditions.
Soeeification
~
A.. Calibration, testing, and checking of instrumentation channels and testing of logic channels shall be performed as 'specified in Table TS.4.1 1.
3.
Equipment tests shall'be conducted'as specified in Table TS.4,1-2A.
C.
Sampling -tests shall be conducted as specified in Table TS.~4.1-28.
D.
LTenever :.be plant condition is such that a system or component =is not required to be operable the surveillance testing associated with that.
system or component may be discontinued.
The asterisked items in Tables-4.1-1, 4.1 2A, and 4.1-2B are required at:all times,-however.
Discontinued surveU ltuce tests shall be resumed less-than one test interval.before establishing plant' conditions.recuiring-OPERABILITY of the associated system or component, unless such, testing-is not practicable (i.e., nuclear power ranSe calibratior, cannot be done prior to ' reaching power operation) in which case:the testing will'be resumed within 48. hours-of attaining the plant condition which permits-testing to be accomplished.
i Prairie Island Unit.1 -- Amendment-No. J7,H,101 i
Prairie Island Unit 2 Amendment No JJ,M,94 l'
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