ML20101P127

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Proposed TS Section 4.0 Re Applicability of Surveillance Requirements
ML20101P127
Person / Time
Site: Prairie Island  Xcel Energy icon.png
Issue date: 06/15/1992
From:
NORTHERN STATES POWER CO.
To:
Shared Package
ML20101P110 List:
References
NUDOCS 9207100295
Download: ML20101P127 (8)
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o Exhibit B Prairie _ Island Nuclear Generating Plant License Amendment Request Dated June 15, 1992 Proposed Changes Marked Up On Existing Technical Specification Pages Exhibit B consists of existing and new Technical Specification pages with the proposed changes highlighted on those pages. The existing pages affected by this License Amendment Request are list.ed below:

TS v TS.4.0 1 TS.4.1-1 l

l l

9207100295 920615 PDR ADOCK 05000282 P pop

TS v l TABLE OF CONTENTS (Continued)

TS SECTION TITLE PACE 4.0 SURVEILLANCE REQUIREMENTS TS.4.0-1 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

  • TS.4.2-2 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 C. Containment and Shield Building Air Temperature TS.4.4 5 H. Containment Shell Temperature TS.4.4-5 I. 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. Component Cooling Water System TS.4.5-2
5. Cooling Water System TS.4.5-2 B. Component Tests TS.4.5 2
1. Pumps TS.4.5 2
2. Containment Fan Motors TS.4.5-3
3. Valves TS.4.5-3 4.6 Periodic Testing of Emergency Power System TS.4.6-1 A. Diesel Cenerators 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 l

! 4.8 Steam and Pouer Conversion Systems TS.4.8-1 A. Auxiliary Feedwater System TS.4.8-1

., B. Steam r enerator 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 l

A. Sample Collection and Analysis TS.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 l-l t

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4 TS.4 0-1 g SURVEILIANCE REOUIREMENTS 4.0 p5511EEtii1~in uiremener shallybei performed within : thal specified WC*33iDII[SEnfsniadbiiRsq'jlf o115wingl.e xc} p,t ions :

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$lifi 19:nsvaljiithjh Q Specific time intervals between tests may be adjusted plus or minus 25% to accommodate normal test schedules w4-sh-sh: : n::ptier sheer. -

E The intervals between tests scheduled for refueling shutdowns shall not exceed two years.

11'stsTf6;'~p'sif6r' ETaiSGBrs 111ade c elRe quir emeht'; withinithe iallo wed

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MsWs i !?definediby Specification 4.0iA;, shall

"'Ifiinteni$nddeplianisiwithithef0PERABILITY requirements forfa siittiiiglCohditioniforiOperationy (The$timejlimits lof tthe ACTION

""issmentsfitesspplicable'atithe~t'ime it is identified that'a FAT 11iindefRAqhiremehtihssinot$been' performed. ifhe ACTION gibi bom[Giresentsyasyj giliEibM6f4 thei snrve111ance ta:Tdslayed)(for when jthe tup^?allowable' to 24 : hours outageto: permit'* the

timeTlimits h'fiths?ACTIONfreq$irementsgare le'sM than 241 hours0.00279 days <br />0.0669 hours <br />3.984788e-4 weeks <br />9.17005e-5 months <br />, : Surveillance hjgijjmeMs3f)p have } to; bi; performed lon f inope rable L equipment ,

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TS.4.1 1

4. 0 ' E"""EILL'?EE "E^"IR"MENH Sp::ific tire' int:re:1: 5:te::: t:: : ::y b: edju:::d plu: :: :!nue 25t : :::: rc ht: ::::1 :::t ::h:dul:: ri:F th: :::::p t ir th::, th:

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4.1 OPERATIONAL SAFETY REVIEW Aenlicability Applies _ to-items directly related to safety limits and limiting conditions for operation.-

Obiective To specify the minimum frequency and type of surveillance to be applied to plant equipment and conditions.

'ggeeification A. Calibration, testing, and checking of instrumentation channels and testing of logic channels shall be performed as.specified in Table TS.4.1-1.

B. ' Equipment tests shall'be conducted as specified in Table TS.4,1-2A.

.C. Sampling 1 tests shall be conducted as specified in Table TS.4.1 2B, D. :Whenever the plant condition is such that a system or component is not

-required _to be operable the surveillance testing associated with that

- sy. stem- or component ' may be discontinued. The asterisked items in Tables 4.1-l', 4.1-2A, and 4.1-2B are required at- all - times, however.

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l Discontinued surveillance tests shall be' resumed-less than one test

-interval before establishing plant conditions requiring OPERABILITY of.:the associated-system or component,'unless such testing-is not practicable (i.e. , nuclear' power range calibration cannot be done prior to reaching power operation) in which case the testing vill-be resumed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of attaining the plant' condition which permits testing to be accomplished l

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Exhibit C Prairie Island Nuclear Generating Plant License Amendment Request Dated June 15, 1992 Revised Technical Specification Pages Exhibit C consists of revised pages for the Prairie Island Nuclear Generating Plant Technical Specification with the proposed changes incorporated. The.

revised pages are listed below:

TS-v TS.4.0-1 TS.4.1-1 l.

l l

?. . - ,

TS v

-TABLE OF CONTENTS (Continued)

TS SECTION TITLE __Pn0E 4.0 SURVEILLANCE REQUIREMENTS IS.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 -

TS.4 2-2 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 Pemoval 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 H. Containment Shell Temperature TS.4.4-5 I. 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 l 4. Component Cooling Water System TS.4.5 2
5. Cooling Water System TS.4.5-2 B. Component Tests TS.4.5-2
1. Pumps TS.4.5-2
2. Containment Fan Motors TS.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 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 Feedwater System TS.4.8-1 B. Steam Cenerator Power Operated Relief Valves TS.4.8-2 C. Steam Exclusion System TS.4.8 4.9 Reactivity Anomalies TS.4.9 1 l

4.10 Radiation Environmental Monitoring Program TS.4.10-1 l A. Sample Collection and Analysis TS.4.10 1 l B. Land Use Census TS.4.10 2 C. Interlaboratory Comparison Program TS.4.10 2 4.11 Radioactive Source Leakage Test TS.4.ll-1 l

i

TS.4.0-1

4. SURVEILIANCE REOUIREMENTJ 4.0 Apolicability 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 between tests scheduled for refueling shutdowns shall not exceed two years.

B. Failure to perform a Surveillance Requirement within the allowed surveillance interval, defined by Specification 4.0. A, shall constitute noncompliance with the OPERABILITY requirements for a Limiting Condition 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 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 inoperab!e equipment.

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TS.4.1 1 4.1 OPER\TIONAL SAFETY REVIEW Aeolicability Applies to items directly related to safety limits and limiting conditions for operation. ,

Obiective

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To specify the minimum frequency and type of surveillance to be applied to plant equipment and conditions.

Specification A. Calibration, testing, and checking of instrumentation channels and testing of logic channels shall be performed as specified in Table TS.4.1-1.

B. Equipment tests snall be conducted as specified in Table TS.4.1-2A.

C. Sampling tests shall be conducted as specified in Table TS.4.12B.

D. Whenever the plant condition is such that a system or component is not required to be operable the surveillance testing associcted 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 surveillance tests shall be resumed less than one test interval before establishing plant conditions requiring OPERABILITY of the associated system or component, unless such testing is not practicable (i.e. , nuclear power range calibration cannot be done prior to reachin;; -

power operation) in wF 2h case the testing will be resumed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of attaining the plant condition which permits testing to be accomplished.

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.. FORD 1

-.. ' REGULATORY 2NFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR: 9206120239- DOC.DATE: 92/06/05 NOTARIZED: NO DOCKET i ,

FACILt50-358 William H. Zimmer Nuclear Station, Unit l~, Cincinnati 05000358 l 50-364 Joseph M. Parley Nuclear Plant, Unit 2, Alabama Power 05000364 AUTH.NAME AUTHOR' AFFILIATION MILLER,J.B. Alabama Power Co.

MILLER,J.H. Balch & Bingham-(formerly Balch, Bingham, Baker, Hawthorne, RECIP.NAME RECIPIENT AFFILIATION BOLLWERK,G.P. Atomic Safety & Licensing Board Panel CARPENTER,J.H. Atomic Safety & Licensing Board Panel MORRIS,P.A. Atomic Safety & Licensing Board Panel

SUBJECT:

Forwards proposed correcticns to transcripts for 920518-21 hearing session.W/ Certificate of Sve. E DISTRIBUTION CODE: DS03D COPIESRECEIVEDLTR[ ENCL SIZE: [ 3 TITLE: SECY/DSB Dist Filinos (Not Orig by NRC)

NOTES:OI/ WARD,W. E/ STONE Icy all Matl. LPDR 2cys Transcripts. 05000358 d E RECIPIENT COPIES RECIPIENT COPIES , h ID CODE /NAME- LTTR ENCL ID CODE /NAME LTTR ENCL PD2-1 LA 1 1 PD2-1 PD 1 1 C HOFFMAN,S 1 1 E

INTERNAL: ASLBP 01 1 1 CAA-16B-13 2 2 NUDOCS-ABSTRACT 1 1 OGC/PSB 15-B-18 1 1 I RGN2 1 1 RGN3 1 1

~ EXTERNAL: NRC PDR- 1 1 3 NOTES:- 4 4 I

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Gd QLCsL3% ><r coyn m 6/nf12 TOTAL NUMBER OF COPIES REQUIRED: LTTR 15 ENCL 15

FORD E. 1

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  • t REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION'NBR:9206120103 DOC.DATE: 92/05/05 NOTARIZED: No DOCKET f FACIL:50-324 Brunswick Steam Electric Plant, Unit 2, Carolina Powe 05000324 50-325 Brunswick Steam Electric Plant, Unit-1,' Carolina.Powe 00000325 AUTH.NAME ' AUTHOR AFFILIATION REYES,L.A.- _ Region 2 (Post 820201)

RECIP.NAME RECIPIENT AFFILIATION NATSON,R.A.- Carolina Power & Light Co.

SUBJECT:

Forwards info received by NRC,for review so appropriate action can-be taken. Requests util findings within 45 days of receipt If ltr. Encl withheld,ref 10CFR2.790a(6)(7).

DISTRIBUTION CODE: IE55D COPIES RECEIVED LTR ENCL ff SIZE: sj7 RegionResponsetoLicenseereAllegati]_ns(SensitiveEnclW/

o held TITLE:

I NOTES:

I RECIPIENT COPIES RECIPIENT COPIES ID CODE /NAME LTTR ENCL ID CODE /NAME LTTR ENCL E!

PD2-1 LA- 1 (I PD2-1 PD 1 0 j LE,N. 1  : g L

INTERNAL: W )b I 1 h NRR/DRIS LEE,J l I c REG FILE -02 1 ,

RES/DSIR/EIB 1 1 RGN2 FILE 01 1 't 33 L'

' EXTERNAL: NRC PDR 1 NSIC 1 ( I

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7 I D TOTAL NUMBER OF COPIES REQUIRED: LTTR 10 ENCL 'S N.

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