ML20091L399

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Proposed Tech Specs Re Surveillance Testing Frequency for ESF Equipment
ML20091L399
Person / Time
Site: Prairie Island  Xcel Energy icon.png
Issue date: 01/21/1992
From:
NORTHERN STATES POWER CO.
To:
Shared Package
ML20091L375 List:
References
NUDOCS 9201280035
Download: ML20091L399 (12)
v • d • e


Text

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Exhibit B PRAIRIE ISLAND NUCLEAR CENERATING PIANT 1

License Amendment Reauest dated January 21. 1992 MARKED UP TECHNICAL SPECIFICATION PAGES Exhibit-B consists of marked up pages for the Prairie Island Nuclear

' Generating Plant Technical Specifications with the proposed changes

! incorporated _as.~ listed below:

, e IA&R TS.4.5-2 TS.4.5-3 TS.4.8-1

-B.4.2 1 B.4.8-1

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.9201280035 920121 PDR. ADOCK 05000282 P PDR

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- TS.4.5 2

3. Containment Fan Coolers Each fan cooler unit shall be tested during each reactor refueling shutdown to verify proper operation of all essential features including low motor speed, cooling water valves, and normal ventilation system dampers. Individual unit performance will be monitored by observing the terminal temperatures of the fan coil unit and by verifying a cooling water flow rate of greater than or equal to 900 gpm to each fan coil unit.
4. Component Cooline Water System
a. System tests shall be performed during each reactor refueling shutdown. Operation of the system will be initiated by tripping the actuation instrumentation.
b. The_ test will be considered satisfactory if control board indica-tion and visual observations indicate that all components have operated satisfactorily.
5. Cooling Vater system
a. System tests shall be performed at each refueling shutdown. Tests shall consist of an automatic start of each diesel engine and automatic operation of valves required to mitigate accidents including those valves that isolate non essential equipment from the system. Operation of the system will be initiated by a simulated accident signal to the actuation instrumentation. The tests will be considered satisfactory if control board indication and visual observations indicate that all components have ope ited satisfactorily and if cooling water flow paths required for accident mitigation have been established.
b. At least once each 18 months, subject each diesel engine to a thorough inspection in accordance with procedures prepared in conjunction with the manufacturer's recommendations for this class of standby secvice. ,

B. Component Tests

1. Pumps
a. The safety injection pumps, residual hect removal pumps and containment spray pumps shall be started ced cperated at intervale cf enc menthtsted?pMsuunt@t6]5pii61flEat:iyiq432. Acceptable levels of performance shall be that the pumps start and reacc 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.

l 1

i A 4 TS.4.5-3 4.5.8

2. Containment Fan Motors The Containment Fan 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 OPERABILITY during each refueling shutdown,
c. The boric acid tank valves to the Safety-Injection System shall be tested at-4* tere 1: er cao-eenthlnia666rdsnee?;witMSocti6nS472.
d. The spray chemical additive tank valves shall be cycled by
pe: ster action at int-ervate-ef-ene centhi.sytsdiini%c6fdalrice]yldi 584AioNIEIE-
e. Actuation circuits for Cooling Water System valves that isolate non-essential equipment from the system shall be tested monthly"is byjgdhijpe[MithlSectiarQ.3
f. All motor-operated valves in the SIS, RHR, Containment Spray, Cooling Water, and Component Cooling Water System 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,
g. The correct position of the throttle valves below shall be verified as follows:
1. Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> following completion of each valve stroking operation.
2. Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> following maintenance on the valve when the Safety Injection System is required to be OPERABLE, and
3. Periodically at least once per 18 months to the extent not verified in accordance with 1 and 2 above within this time period.

Unir 1 Valves ' Unit 2 Valves SI-15-6 2SI-15-6 SI-15-7 2SI-15-7 SI-15-8 2SI-15-8 SI-15-9 2SI-15-9

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TS,4.8-1 4.8 SIEAM AND POWER CONVERSION SYSTEMS 6pplicability 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.

Specification A. Auxiliary Feedwater System

1. Each motor-driven auxiliary f?rdwater pump shall be started at 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 4ato the steam generators shall be demonstrated once er:E year-Gjerf]rsfvoling[sh6fdoQn-when-ateoa: frc=

the team gen + ret-or in avcilable.

3. The auxiliary feedwater pumps discharge valves shall be tested by operator action at-4*t+rv 10 c f-ene-eent-h in{a'c[c o r da.n6e f w ith T S o c t i a n F;2.
4. Motor-operated valves required to function during accident conditions shall be tested at--4et+rvc1 ef ne month litf ahdordanceTwithjection

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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 auxilia*y 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 SHUTDOWN and prior to exceeding 10% power, a test is 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.
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 feodwater actuation test signal.
  • If the test comea 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 OPERATION.

4 e

B.4,2-1 4,2 INSERVICE INSPECTION AND TESTING OF PUMPS AND VALVES REQUIREMENTS Bases The inservice inspection program for the Prairie Island plant conforms to the requirements of 10 CFR 50. Section 50,55s(g). Where practical the inspection of ASME Code Class 1, Class 2, and Class 3 components is performed in accordance with Section XI of the ASME Code. 6" program'of inseryIF#.TtistinsioffASHETCodsTClassf pumps ?snd ?vsliefTs falso il'n effe'ct1in ~

s;nd;is ?.c'onlt'ainQ inithe .SurrentiPf airiejIMand ASME;' .Sestion;XI;, Inservice Testing; Program!.jlf a code required inspection is impractical for the Prairie Island facility, a request for a deviation from that requirement is submitted to the Commission in accordance with 10 CFR 50, Section 50.55a(g)(6)(1),

Deviations which are needed from the procedures prescribed in Section XI of the ASME Code and applicabla 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, l

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+ . - - - . . -. ~. . . - .~ .. , - , . . - . - . - _ , - - . . - - - _

,.. --p B.4.8 1 ,

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4.8  : STEAM AND POWER' CONVERSION SYSTEMS Bases .;

Monthly testing of the auxiliary .feedwater pumps, meetMy-valve inspections [liQsic6pdisiejjith]Seict M M -and atartup flow verification .

provide. assurance that-the Auxiliary Feedwater System will meet emergency -

demand' requirements.~Ths3fnlUIf16witeettikTdose%ndWTs7cy616?sisociated 9t t. hitE. dnef6s1.'i..'~T.sh_u.t_d..o_wh%.i_

< m- ~ -  %. min _im_is_@he._f th4rman sh..o_cO_ tolt..h. s_taus.i..l_iary

-he discharge-valves of the pumps are normally open, as feedwater1 piping ,

are the suction valves from the condensate storage-tanks. Proper opening:

'of the' steam admission valve:on each turbine-driven pump will be-

' demonstrated:each time a-turbine-driven pump is tested. Ventilation system isolation' dampers required to function for the postulated tupture-- *

of a high energy line will.;also be. tested.

1 At 18-month intervals, pump starting and valve positioning is verifico

-using test signals to simulate each of the automatic actuation parameters. ,

i.

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l. ,. Refereneg i

k .USAk, Sections;11.9, 14,;and Appendix I._

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11

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a f' Exhibit C PRAIRIE ISiAND NUCLEAR GENERATING PIANT License Arnendgent .tteouest dated January 21. 1992 REVISED TECHNICAL SPEC 1FICATION PAGES Exhibit C consists of revised pages for the Prairie Island Nuclear Generating Plant Technical Specifications with the proposed changes incorporated as listed below:

faTA TS.4.5-2 TS,4.5-3 TS.4.8 1 B.4.2-1 B.4.8 1 l

l-l l

l l

I. "

- ~_ . _ - _ _ -- . . . ~ . . . . . --

TS,4.5-2 3 Containment Fan Coolers Each fcn cooler unit shall be tested during each reactor refueling shutdown to verify proper operation of all essential features including low motor speed, cooling water valves, and normal ventilation system dampers, Individual unit performance will be monitored by observing-the terminal temperaturce of the fan coil unit and by verifying a cooling water flow rate of greater than or equal to 900 gpm to each fan coil unit.

4, Cpmponent Coolinc Water System

a. System tests shall be performed during each reactor refueling shutdown. Operation of the system will be initiated by tripping the actuation instrumentation. ,
b. The test will be considered satisfactory if control board indica-tion and visual observations indicate that all components have operated satisfactorily, 5, Cooline Water System
a. System tests shall be performed at each refueling shutdown, Tests-shall consist of-an automatic start of each diesel engine and automatic operation of valves required to mitigate accidents including those valves that isolate non essential equipment from the system, Operation of the system will be initiated by a simulated accident signal to the actuation instrueentation. The tests will be

. considered satisfactory if control board indication and visual

, observations indicate that all components have operated satisfactorily and if cooling watet flow paths required for accident

. mitigation have been established.

b, At least once each- 18 months, subject each diesel engine to a thorough inspection in accordance with procedures prepared in

! conjunction with the manufacturer's recommendations for this class

! of standby service, B. Component Tests 1, Pumps a, The safety injection pumpa, residual heat removal pumps and containment spray pumps-shall be tested pursuant to Specification 4.2. inceptable levels of performance shall be that the pamps start and reach their required developed head on minimum recirculation

_".ow and the control beard indications and visual observations indicate that the pumps are operating properlyffor at least 15 minutes, 1

b. A test.consistirg of a manualiy-initiated start of each diesel engine, and assumption of load within one minate, shall be conducted monthly.

TS 4.5-3 4.5,B

2. Containment Pan Mot;gn The Containment Fan 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. Valses
a. The refueling water storage tank outlet valves shall be tested in accordance with Section 4.2,
b. The accumulator check vaives will be checked for OPERABILITY during wach refueling shutdown,
c. The boric acid tank vrives to the Safety Injection System shall be tested in accordance with Section 4.2. I
d. The spray chemical additive tank valves shall be tested in [

accordance with Section 4.2,

e. Actuation. circuits for Cooling Watet System valv 5 that isolato non essential equipment from the system shall be cested in l

-accordance-with Section 4.2,

f. All motor-operated valves in the SIS, RHR, Containment Spray, Cooling Water,' and Component Cooling Water System that are designed for operation during the safety injection or recirculation phase of emergency core couling, shall be tested for-OPERABILITY.at each refueling shutdown,
s. The cortect position of_the throttle valves below shall be f verified as follows:

9 1, Within'4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> following completion of each valve stroking operation.

Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> following maintenance on the valve when the

~

2.

Safety Injection System-is required to be OPERABLE, and Periodically'at least once per 18 months to the extent not i

3.

verified in recordance with'l and 2 above within this time-perl.od.

Unit i Valves Unit 2 Valves I

SI-15-6 2SI 15-6

, SI-15-7 2SI-15-7 SI-15-8 2SI-15-8 SI-15-9 2SI-15-9 h

m J 1

\

TS 4.8 1 l I

4.8 S.IIAM AND POWER CONVERSION SYSTEMS 6policab111tv App 11es to periodic testing requirements of the Auxiliary Feedwater, Steam Generator Power Operated Relief Valves, and Steam Exclusion Systemn, ph,jective To verify the OPERABILITY of the steam and power conversion systems required for emergency shutdown coolleg of the plant.

Specification A. Auxiliary Feedwater System

1. Each motor-driven auxiliary feedvater pump shall be started at intervals of one month and full flow to the steam generators shall be demonstrated once every refueling shutdeva,
2. The steam turbine-driven auxiliary feedwater pump shall be started at intervals of one month
  • and full flow to the steam generators shall be demonstrated once every refuelinC shutdown.
3. The auxiliary feedwater pumps discharge valves shall be tested by operator action in accordance with Section 4.2. l
4. Motor-operated valven required to function during 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 equipnent demon-strate that all components have operated properly, i

6. During POWER OPERATION, for the manual valves outside containment, t 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. Af ter each COLD SliUTDOWN and prior to exceeding 10% power, a test is required to "orify the normal flow path from th. 2rimary auxiliary feedwater ~ 4 9 to the steam generators. This .est may consist of

-b maintainit( , sam pnerator level during startup with the auxiliary feed pumps.'

8. At least orme every 18 months during shutdown verify that each pump starts ac designed automatically and each automatic vatve in the flow path actuates to its correct position upon receipt of each auxiliary feedwater actuation test signal.
  • 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 OPERATION.

-_ __ _ m _ _ . . _. . . . _ _ _ ~ _ _ - . _ . ~ . . . _ . . _ _ _ _ _ _ . _ .

B.4.2-1 ,

. 4.2 INSERVICE INSPECTION AND TESTING OF PUMPS AND._VALNES REOUIREMENTS DAAEE The inservice inspection program for the Prairie Island plant conforms to the requirements of 10 CIR 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 Sec+, ion 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 Prairie Inland facility, a request for a deviation from that requirement is submitted to the Commission in accordance with 10. CFR 50, Section 50.55a(g)(6)(i).

Deviations which are needed from the procedures prescribed in Section XI of the ASME Code and applicable Addenda will oe reported to the Commission prior-to the beginning of each 10 year inspection period if they are known to-be requited at that time. Deviations which are identified during the course of inspection will be reported quarterly throughout che inspection period.

L L .

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> 3 B.4.8 1=

4.8 L 3M AND POWER CONVERSION SYSTEMS Baset Monthly testing of the auxiliary feedwater pumps, valve inspections in accordanco 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 tho refuelirg shutdown to minimize the thermal shock to the auxiliary fendwater piping. 'The discharge valves of the pumps are normally open, as cre the succion valves from the condensate storage tanks. Proper opening 4

of the steam admission valve on each turbine drf"en pump will be demonstrated each time a turbine driven pump is tested. Ventilation c system isolation dampets required to function for the postulated rupturo of a high energy line will also be tested.

At 18+tnonth intervals, pump starting and valve positioning is verified using test signsis to simulate each or the automatic actuation parameters.

Reference USAR,-Sections 11.9, 14. and Appendix I.

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