ML20128P472
| ML20128P472 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 02/05/1993 |
| From: | Marsh L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20128P476 | List: |
| References | |
| NUDOCS 9302240345 | |
| Download: ML20128P472 (14) | |
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.[R/ **%g UNITED STATES NUCLEAR REGULATORY COMMISSION g
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WASHINGTON,0. C. 20555
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NORTHERN STATES POWER ~ COMPANY DOCKET NO. 50-282 1
PRAIRIE ISLAND NUCLEAR GENERATING PLANT. UNIT NO. 1 AE NDMENT TO FACILITY OPERATING LICENSE Amendment No.104 License No. DPR-42 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Northern States Power Confany (the licensee) dated January 21, 1992, 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.
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 t.
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 1icense is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment, and para-graph 2.C.(2) of Facility Operating License No. DPR-42 is hereby amended to read as follows:
93022403AS 930205 PDR ADOCK 05000282 P
PDR n.
Iec.hpical Snecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.104, are hereby incorporated in the license.
The' licensee shall operate the facility in accordance with the Technical i
Specifications.
)
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION l
W Ledyard B. Marsh, Director Project Directorate 111-1 Division of Reactor Projects III/IV/V Office of Nuclear. Reactor Regulation -
Attachment:
Changes to the Technical Specifications Date of Issuance: February 5, 1993 s
4 ATTACHMENT TO LICENSE AMENDMENT NO. 104-FACILITY OPERATING LICENSE NO. OPR-42 DOCKET NO. 50-282 Revise Appendix A Technical S >ecifications by~ removing the pages identified below and inserting the attacled pages. The revised pages are identified by-amendment number-and contain marginal lines indicating the area of change R@01E INSERT TS.4.5-3 TS.4.5-3 TS.4.8-1 TS.4.8 TS.B.4.2-1 TS.B.4.2-1 TS.B.4.8-1 TS.B.4.8-1 J
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T8.4.5 3 4,5.B.
Component Tests
- 1. Isgs,1 i
- a. 'ihe safety injection pumps, residual heat removal pumps and containment spray pumps shall be tested pursuant to.
Specification 4.2.
Acceptable levels of performance shall-ba thtt the pumps start and reach the;r 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 lead within one minute, shall be conducted monthly.
- c. The vertical motor driven coolin5 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 indict.tions and visual observations indicate that the pump is operatin5 Properly for at least 15 minutes.
2.
Containment ran Motors The Containment Fan Coil-Units shall be run on low motor speed for at least 15 minutes at intervals of one month. Motor l
current shall be neasured and compared to the nominal current expected for the test conditions.
l 3.
valves i
- a. The refueling water storage tank outlet valves shall be tested in accordance with Section 4.2 l
- b. The accumulator check valves will be checked for OPERABILI1Y during each refueling shutdown.
l
- c. The boric acid tank valves to the Safety Injection System 1
shall be tested in accordance with caction 4.2.
- d. The spray chemical addit" e 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 in accordance with Section 4.2.
Spray, CoolinS Vater, and Component Cooling Water System l-that are desi ned for operation durin5 the safety injaccion 5
or recirculation phase of emersency core cooling, shall be tested for OPEP, ABILITY at each refuelitig shutdown.
Prairie Island Unit No. 1 - Amendemnt No 21, 30, 91, JOA, - 104 Praitie Island Unit No. 2 - Amendment No. JE, 74, $#, Pf, 97 i
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TS.4.8-1;
- 4. 8 - S. TEAM-AND POWER CONVERSION SYSTgg j
Aeolicability Applies to periodic testing requirements of tho' Auxiliary Feedwater Steam-:
(
Generator Power Operated Relief Valves, and Steam Exclusion Systems..
l Obiective el To verify the OPERABILITY of the steam and power conversion systems required 4 for emergency shutdown cooling of the plant.
Scocificacion A.
Auxiliary Feedwat3I System l
1.
Each uotor driven auxiliary feedwater pump shall be. started ~at
" l intervals of one month and full flow to the steam generators shall be-demonstrated once every refueling shutdown.
2.
The steam turbine-driven auxiliary feedwater pump shall-be' started at intervals of one month
- and full flow to the steam generators shall be2 demonstrated once wery refueling shutdown._
j 3.
The auxiliary feedwater pumps dischcrge' valves shall be tested'by a
operator action in accordance with Section 4.2.
- l, H
e 4.
Motor-operated valves rc. quired to fua.: tion during accident conditions shall be tested'in accordance-with Section 4.2.
l-These tests shall be considered' satisfactory if control board indication and subsequent visual' observation of the equipment demon.
strate that all' components have operated properly.
6.
During POWER OPERATION, for the manual. valves'outside4 containment,..
that could reduce auxiliary feedwater flow, if improperly positionedi to less than assumed in the accident analysis,-monthly inspections arei
~
required to verify the valves are Iceked in the proper position required for emergency use.
7.
After each COLD SHUTDOWN and prior to-exceeding <104 power, a test'is required to verify.the normal flow path from the primary auxiliary' feedwater source to the steam. generators. 1his test'may consist of naintaining-steam generator level during starcup with the auxiliary-feed pumps.'
j 8.
At least once every 18 months during shutdown verify that.each pump-i starts as desigred. automatically and each automatic-valve in the flow path actuates to its correct position upon receipt of each auxiliary-feedwater actuatien test rJgnal.
- If the test comes due during a reactor shutdown the test shall bo performed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of entering POWER OPERATION.
Prairie Island Unit No.
1-- Amendment No. 46,= 91,104 Prairie Island Unit No. 2 - Amendment No. 40. 84, 97 gr-4:
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B,4.2 #
4.2 INSERVICE INSPECTION AND TESTING OF PUMPS ' AND VALVFS REOUIREMENTS a
' EAEta i
The inservice inspection program for the _ Prairie Island plant conforms to the requirements of 10 CFR 50, Section 50.55a(g). Where_ practical the inspection of ASME Code Class 1. Cle.ss 2, and Class' 3 components. is performed in accordance with Section XI of. the ASME Code. A program of inservice testing of ASME Code Class pumps and valves is also in effect in and is contained in the current Prairie Island ASME Section XI Inservice Testing Program.
If a code required inspection is impractical for the-n Prairie Island facility, a request for~a deviation from that requirement His submitted to the Commission it, accordance with 10 CFR 50, Section-j 50.55a(g)(6)(1).
Deviations which are needed from the-procedures prescribed in Section
~
XI of the ASME Code and applicable Addenda will be reported ~to the j
Commission prior to the beginning of each 10 year inspection period if they are known to be required at that time. Deviations which ata identified during the course cf inspection will-be reported quarterly throughout the inspection period.
l i
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d Prairie Island Unit No. 1 - Amendment No. 91, 104 Prairie Island Unit No. 2 - Amendment No. 84, 97
B.4.8-1
-- 4. 8 STEAM AND POWER CONVERSION SYSTE4S Bases l
Monthly testin5 of the auxiliary feedwater pumps, valve inspections in-accordance with Section 4.2, and startup flow verification ~ provide assurance that the Auxiliary Feedwater. System will meet emergency demand requirements. The full flow test is done once a cycle associated with the refueling shutdown to minimize the thermal shock to the auxiliary ;
feedvater piping..The discharge valves of the-pumps are normally open, as are the suction valves from the condensate storage tanks.--
Proper opening-of the steam admission valve on each'eurbine-driven pump vill be demonstrated each time a turbine-driven pump is tested. Ventilation system isolation dampers required to function for the postulated rupture.
of a high energy line will also be tested.
At 18-month intervals, pump starting and valve positioning is verified using test signals to simulate each of the automatic actuation parameters.
Re fe renen USAR, Sections 11.9, 14, and Appendix I.
Prairie. Island Unit No. 1 - Amendment No. 91, 10'.
Prairie Island Unit No.12 - Amendment No. 84, 97
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-- UNITED STATES d
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- NUCLEAR REGULATORY COMMISSION =
. WASHINoTON, D.C. 20066 -
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NORTHERN STATES POWER COMPANYL DOCKET'NO. 50-306-PRAIRIE ISLAND NUCLEAR GENERATING PLANT. UNIT NO. 2=
MiENDMENT TO FACILITY OPEPATING~ LICENSE -
Amendment No. 97 -
[
License No.- DPR-60:
m 1.
The Nuclear. Regulatory Commission (the Commission) has found that:
A. The application for-amendment by NorthernLStates Power Company.'(thei licensee) dated A nuary 21,--1992, complies with the standards and>
requirements of the-A_tomic Energy Act of 1954, as_ amended (the Act),
and the Comission's rules and regulations set forth in'-10 CFR Chapteri I;
B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and. regulations of _ the.
Commission; j
.C. There is reasonable assurai;ce (i) that the:actf,vitiestauthoHzed byl this amendment can be conducted without endangering the health:and p
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 inimicalLto the! common
~
defense and security.or'to the-health andLsafety of the public; Land j
E. The' issuance of this amendment is in-accordance with:10 CFR Part 51 of 3
m the Commission's regulations and 'all applicable requirements-have been? ~
satisfied.
1 2.
Accordingly, the license is. amended by changes to:the Technical--
Specifications _as indicated;in the attachment-to this license 4 amendment, g
- and paragraph 2.C.(2) of Facility Operating; License No. DPR-60 is'herebyL amended'to read as follow's:
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9
" Technical Spacifications -
The Technical' Specifications contained in Appendix A,- as revised through _ Amendment No. 97, are hereby incorporated in the license. The licensee shall operate the facility in acordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION l
CL Ledyard B. Marsh, Director.
Project Directorate 111 Division of Reactor Projects III/IV/V.
Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: February 5, 1993
ATTACHMENT TO LICENSE AMENDMENT NO. 97 FACILITY OPERATING LICENSE N0.1DPR-60 00CKfT NO. 50-306 0
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 marginal lines-indicating the area _ of change REMOVE INSERT-TS.4.5-3 TS.4.5-3 TS.4.8-1 TS.4.8-1 TS.B.4.2-1 TS.B.4.2-1 TS.B.4.8-1 T S. B. 4 '. 8-1
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1 TS.4.5 3 4.5.B.
. Component Tosts
- 1. Esit
- a. 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 ba 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 lead within ons ninute, shall be conducted monthly,
- c. The vertical motor driven cooling water r_ep 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 boerd indications and visual observations indicate that the pump is operatin8 Properly for a* 1 east 15 minutes.
2.
Containnent Fan Motors The Containment Fan Coil Units s' all be run on low motor speed for at least 15 minutes n intervals of one month. Motor current shall be measured eud compated to the nominat current expseted for the test conditions.
3.
Velves
- 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 OPERABILITY during each refueling shutdown.
- c. The beric 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 in accordance with Section 4.2.
- f. All mo*.or-operated valves in the SIS, RRR, Containment Spray, coolins Water, and Conponent Cooling Water System that are desi ned for operation durin5 the safety injecticn 5
or recirculation phase of emergency core cooling, shall be tested for OPERABILITY at each refueling shutdown, t
Prairie Island Unit No. 1 - Amendment No. 21, 20, 91, 103, 104 Prairie Island Unit No. 2 - Amendment No. 15, 24, 84, 96, 97
.2 IS.4.8-l' 4.8 STEAM'AND POWER CONVERSION SYSTEMS Apnlicability Applies to periodic testing requirements of'the Auxiliary _Feedwater,' Steam Generator Power Operated Relief Valves, and Steam Exclusion Systems.
Obiective To verify the OPERABILITY of'the steam and power conversion systems required for emergency shutdown cooling of the plant.
Seccification A.
Auxiliary Feedwater' System 1.
Each motor-driven' auxiliary feedwater pump shall be started ad
~
intervals of-one month and full flow to the steam generators _ shall be demonscrated once every refueling shutdown.
2.
The steam turbine-drive:. auxiliary feedwater pump shali be started at intervals of one mon.n* and full flow to the steam generators saall be demonstrated once every refueling shutdown.
3.
The auxiliary feedwater pumps discharge valves shall be. tested by operator action -in accords: ce with Section 4.2.
[..
4.
Motor-opera :ed valves required to function durin5 accident conditions shall be tested in accordance with Section 4.2.
_l 5.
These tests shall be considered -satisfactory if control board indication and subsequent visual observation of the equipment demon- -
strate that all components have operated properly.
6.
During POWER OPERATION, for_the manual _ valves outside containment, that could-reduce auxiliary feedwater flow, if improperly positioned, to less than assumed in the accident analysis, monthly inspections are required to verify the valves are locked in the proper position required for emergency use.
7.
After each COLD SKUTDOWN and prior to exceedingL10% power, a test 1:
required to verify the normal flow path from the primary auxiliary.
.feedwater source to the steam generators.
This_ test.may consist of.
maintaining steam. generator level during startup with the auxiliary feed pumps, i
I 8.
At least once every 18 months. during shutdown verify -that each pump starts as designed automatically and each automatic valve in the flow-path actuates to its correct' position upon receipt of each' auxiliary
~
feedwater actuation test signa'i.-
- If the test comes' due during a reactor shutdown.the test shall be performed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of entering POWER OPERAlION.
Prairie-IslandjUnit-No. 1 - Amendmert.No. 46, 91,,104' Prairie Island Unti No. 2 - Amendment.No. 40, 54,'97 2
L
+
B.4.2 4.2 INSERVICE INSPECTION AND TEFTING OF PUMPS AND VALVES REOUIPIMZNTS EAEfia The inservice inspection program IEor the Prairie Island plant conforms to the requirements of 10 CFR 50, Section 50.55a(g). Where practical-the -inspection of ASME Code Class 1, Class 2, and Class 3 components is-performed in accordance with Sectf.on XI of the ASME Code. A program of inservice testing of ASME Code Class pumps and valves is also in effect in ar.d is contained in the current Prairie Island ASME Section XI Inservice Testing Progres. If a code required inspection is impractical for the Prairie Island facility, a request for a deviation from that requirement is submitted to the CoAvission in accordance with 10 CFR 50, Section 50.55a(g)(6)(1).
Deviations which-are needed from the procedures prescribed in Section XI of ths ASME Code and applicable Addenda will be reported to the Commission prior to the beginning of each 10 year inspection period if they are known to be required at that time. Deviations which are-identified during the course of inspection will be reported quarterly throughout the inspection period.
Prairie Island Unit No. 1 - Amendment No. 91, 104-Prairie Island Unit No. 2 - Amendment No. 54, 97 ~
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- . 4 -
--5.4.8-1 48-STEAM AND POWER CONVERSION SYSTEMS:
i Bases Monthly testing of the : auxiliary feedwater_ pumps, valve inspections-in I
accordance with Section 4.2, and startup flow verification provide-;
assurance that the Auxiliary Feedwater_ System will meet emergency demand' requirements. The = full' flow test is' done once aLcycle ~ associated with the..
refueling shutdown to minimize the thermal shock to-the auxiliary feedwater piping. - The discharge valvest of the pumps are normally open, as-are the suction valves from the. condensate storage -tanks.. _ - Proper opening.
of the steam admission valve on each turbine driven puen will be--
demonstrated each tips s.'turbir.e-driven pump is tested. " Ventilation-system isolation-dampers required to function for the postulated rupture of a high energy line.will also be tested.
q At-18 month intervals, pump starting and valve positioning:is verified--
using test signala to simuiste each of the. automatic actuation parameters.
Reference USAR, Sections 11.9, 14, and Appendix 1.
Prairie Island Unit No. 1 - Amendment No. 91,-104 Prairie Island Unit No. ? - Amendment No. 84, 97
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