ML20011B090

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Amends 50 & 44 to Licenses DPR-42 & DPR-60,respectively, Clarifying Snubber Surveillance Requirements & Correcting Administrative Errors
ML20011B090
Person / Time
Site: Prairie Island  
Issue date: 10/28/1981
From: Clark R
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20011B091 List:
References
NUDOCS 8111090134
Download: ML20011B090 (23)
v • d • e


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fg UNITED STATES NUCLEAR REGULATORY COMMISSION e

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N_0RTHERN STATES-POWER GOMPANY-

-fj0EKET NGv 50-282 --

PRAIRIE ISLAND NUCLEAR GENERATING PLANT UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 50 License No. DPR-42 1.

The Nuclear Regulatory Commission (the Commission) has fou,nd that:

A.

The application f'or amendment by Northern States Power Company (the licensee) dated August 14,'1981, 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 confonnity 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 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.

9 8111090134 811028 PDRADOCK05000g

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., 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) cf Facility Operating License No. DPR-42 is hereby amended to read,as_followsj (2). Techrdcal hecif.igations _.

The Technical Specifications contained in Appendices A' and B, as revised through Amendment No. 50, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

.3.

This license amendment is effective as of the date of i*s issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Robert A. Clark, Chief

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Operating Reactors Branch #e Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: October 28, 1981 l

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NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555

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NORTHERN STATES POWER COMPANY DOCKET NO~. 50:306 PRAIRIE 75LARITRUCLEAR GENERATING PLANT UNIT NO. '2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 44 License No. DPR-60 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Northern States Power. Company (the licensee) dated August 14, 1981, 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 E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicab.le requirements have been satisfied.

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2-2.

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:

(2)- Technical becifitattons 1 - -- ---

The Technical Specifications. contained in Appendices A and,B, as revised through Amendment No. 44, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR PEGULATORY COMMISSION J

obert A. Clark, Chief Operating Reactors Branch d3 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance:

October 28, 1931 s

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-n ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 50 TO FACILITY OPERATING LICENSE N0..DPR-42 AMENDMENT NO. 44 TO FACILITY OPERATING LICENSE NO. DPR-60 ~

DOCKET NOS. 50-282 AND 50-306 n

Replace the following pages and insert the new pages of the Appendix A Technical Specifications with the enclosed pages as indicated. The revised pages are identified by Amendment number and contain vertical lines indicating t.he area of change.

TS-i TS-tii

-Table TS.3.5 6 TS.3.12-1 Table TS.3.12-1, (pg 1 of 8)

Table'TS.3.12-1, (pg 2 of 8)

Table TS.3.12-1, (pg 3 of 8)

Table TS.-3.12-1, (pg 4 of 8)

Table TS.3.12-1, (pg 5 of 8)

Table TS.3.12-1, (pg 6 of 8)

Table TS.3.12-1, (pg 7 of 8)

TS.4.13-1 TS.4.13-2 TS.4.13-3 TS.4.13-4 (new)

Table TS.4.1-1 (pg 1 of 5)

Table TS.4.1-1 (pg 5 of 5)

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APPENDIX A TECICIICAL SPECIFICATIONS TABLE OF'CONTETIS TS SECTION TITLE PAGE 1.0 Definitions TS.1-1 n

2.0 Safety Limits and Limiting Safety System settings TS.2.1-1 2.1 Safety Limit, Reactor Core TS.2.1-1 2.2 Safety Limit, Reactor Coolant System Pressure TS.2.2-1 2.3 Limiting Safety System Settings, Protective Instrumentation TS.2.3-1 3.0 Limiting Conditions for Operation TS.3.1-1 3.1 Reactor Coolant System TS.3.1-1 3.2 Cbemical and Volume Control System TS.3.2-1 3.3 Engineered Safety Features TS.3.3-1 3.4 Steam and Power Conversion System TS.3.4-1 3.5 Instrumentation System TS.3.5-1 3.6 Containment System

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TS.3.6-1 3.7 Auxiliary Electrical Systems TS.3.7-1 3.8 Refueling and Fuel Handling TS.3.8-1 3.9 Radioactive Effluents TS.3.9-1 3.10 Control Rod and Power Distribution Limits TS.3.10-1 3.11 Core Surveillance Instrumentation TS.3.11-1 3.12 Snubbers TS.3.12-1 l

3.13 Control Room Air Treatment System TS.3.13-1 3.14 Fire Detection and Protection Systems TS.3.14-1 3.15 Event Monitoring Instrumentation TS.3.15-1 4.0 Surveillance Requirements TS.4.1-1 4.1 Operational Safety Review TS.4.1-1

.4.2 Inservice Inspection Requirements TS.4.2-1 4.3 Primary Coolant System Pressure Isolation Valves TS.4.3-1 4.4 Containment System Tests TS.4.4-1 s

4.5 Engineered Safety Features TS.4.5-1 Periodic Testing of Emergency Power System TS.4.6-1 4.6 4.7 Main Steam Stop Valves TS.4.7-1 4.8 Steam and Power Conversion System TS.4.8-1 4.9 Reactivity Anomalies TS.4.9-1 4.10 Radiation Envirormental Monitoring Program TS.4.10-1 4.11 Radioactive Source Leakage Test TS.4.ll-1 4.12 Steam Generator Tube Surveillance TS.4.12-1 4.13 Snubbers TS.4.13-1 l

4.14 Control Room Air Treatment System Tests TS.4.14-1 4.15 Spent Fuel Pool Special Ventilation System TS.4.15-1 4.16 Fire Detection and Protection Systems TS.4.16,1

' Unit 1 - Amendment No. 26, 43, 46, 50 Unit 2 - Amendment No. 20, 37, 40, 44

TS-iii APPENDIX A TECHNICAL SPECIFICATIONS LIST OF TABLES TS TABLE TITLE 3.1,1 Unit 1 Reactor Vessel Toughness Data 3.1-2.

Unit,2.Reac. tar Veste.1 Toughness Data 3.5-1 Engineered Safety Features Initiation Instrument Limiting Set. Points 3.'5-2 Instr. ant Operating Conditions for Reactor Trip 3.5-3 Instrument Operating Conditions for Emergency Cooling System 3.5-4 Instrument Operating Conditions for Isolation Functions 3.5-5 Instrument Operating Conditions for Ventilation Systems 3.5-6 Instrument Operating Conditions for Auxiliary Electrical System 3.9-1 Radioactive Liquid Waste Sampling and Analysis 3.9-2 Radioactive Gaseous Waste Sampling and Aralysis 3.12-1 Safety Related Snubbers l

3.14-1 Safety Related Fire Detection Instruments

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3.15-1 Event Monitoring Instrumentation 4.1-1 Minimum Frequencies for Checks, Calibrations and Test of Instrument Channels

,4.1-2A Minimum Frequencies for Equipment. Tests 4.1-2B Minimum Frequencies for Sampling Tests 4.2 Special Inservice Inspection Requirements 4.4-1 Unit 1 and Unit 2 Penetration Designation for Leakage Tests 4.10-1 Prairie Island Nuclear Generat:.ng Plant-Radiation Environmental Monitoring Program Sample Collection and Analysis Environmental Monitoring Program' 4.12-1 Steam ~ Generator Tube Inspection 5.5-1 Anticipated Annual Release of Radioactive Material in Liquid Effluents From Prairie Island Nuclear Generating Plant (Per Unit) 5.5-2 Anticipated Annual Release of Radioactive Nuclides in Gaseous Effluent From Prairie Island Nuclear Generating Plant (Per Unit) 6.1-1 Minimum Shift Crew Composition 6.7-1 Special Reports Prairie Island Unit 1 Amandment No. 43, 46, Aa, 50 Prairie Island Unit 2 Amendment No. 37, 40, 43, 44 e

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Prairie Island Unit 1 A=end=ent No. 77, 50 Prairie Island Unit.i.

Amend =ent No. @, AA m

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TS.3.12-1 l

3.12 SNUB 8ERS Applicability Applies to the operability of safety related snubb,ers,.

. Objective To define those conditions of snubber operability necessary to assure safe reactor operation.

Specification A.

Except as permitted below, all snubbers listed in Table TS.3.12-1 shall be operable above Cold Shutdown.

Snubbers may be inoperable in Cold Shutdown and Refueling Shutdown whenever the supported system is not required to be Operable.

B.

With one or more snubbers made or found to be inoperable for any reason when Operability is required, within 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />s:

1.

Replace or restore the inoperable snubbers to Operable

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status and perform an engineeting' evaluation per Specifica-tion 4.13.E on the supported component (s), or '

2.

Declare the supported system inoperable and take the action required by the Technical Specifications for inoperability of that system.

C.

Snubber modifications may be made to safety related systems without prior License Amendment to Table TS.3.12-1 provided that a revision to the Table is included with the next License Amendment Request.

Basis All snubbers are required to be Operable above Cold Shutdown to ensure that the structural integrity of the reactor coolant system and all other safety related systems is maintained during ind following a seismic or other event initiating dynamic loads.

Unit 1 - Amendment No.14, 50 Unit 2 - Amendment No. 8, 44

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o IA3LE IS.3.12-1 (Page 1 of 3)

SAFETY REI.A ED SNU33ERS Snubbers - -

In~Eigh Accessible oor Especially Radiation S nub be r-

- Inac c es s ible Dif f _%1t-Area During No.

Location Elevation (A or I) to Remove Shutdown UNIT I AFSH-22 A&3-Main and Aux-773'-4-1/4" A

AFSH-36 iliary S tea =

745'-7-1/4" A

A?SH-39 699'-10-1/4" A

AFSH-a3 699'-6-1/4""

A MSDH-25 A&3 736'-6-7/16" A

MSDH-26 A&3 756'-7-1/4" A

MSDH-29 756'-7-1/4" A

MSDH-30 736-6-7/16" A

MSH-LS A&3 739'-1-11/16" A

l MSH-62 A&3 735'-6" A

MSH-68 A&B 755'-8" A

UNIT II ATSH-2 Main and Auxiliary 749'-4" A ~

AFSH-19 Stets 745'-7-1/4" A

AFSH-20 745'-7-1/4" A

AFSH-34 745'-6" A

AFSH-29 A&3 721'-1-9/16" A

ATSH-33 707'-5"-

A AFSH-39 696'-6-1/4" A

A?SH-40 696'-6-1/4" A

AFSH-04 750'-7-1/2" A

- AJSH-46 750'-7" A

MSDH-17 739'-0" A

MSDH-13 759'-0" A

+

MS 2 K-19 739'-0" A

MSDH-:0 759'-0" A

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l Unit 1 - Amendment No. 14, 49. 50 Unit 2 - Amendment No. 8, 43, 44 W

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IA3LE IS.3.12-1 (Page 2 of 3)

SATITY RELA ~ID SNU33ERS

..Snubburg

-*T Hig'n Acces sible or Especially Radiation Scubber-

- - ~ ~ - --~ ' -- -- Isac:essible - Dif ficul: ' Areas During No Lo;;: ion Eleva ion (A or I) to Recove Shutdown UNIT II f

MSH-23 A&3 Main and Auxiliary 739'-1-3/16" A

MSH-54 A&3 S:ess 756'-0-1/16" I

MSH-31 A&3 735'-9" A

XSE-32 A&3 755'-3" A

MSH-83 761'-13/16""

I UNIT I RERRE-5 Safety Injecrfen 723'-4-1/4" I

RERRE-41 698'-11" I

RERRF-58 670'-0" A

RERRE-60 670'-0" A

RPCH-160 718'-1/2" I

RSIE-92 714'-11" I

RSIE-93 714'-11"

I RSIH-95 711'-2" I

RS!E-96 711'-2" I

RS!n-98 701'-2" I

RSIH-163 717'-9" I

RSIE-l'7 717'-9" I

6 RSIH-sl3 A&3 722'-8" A

RS!H-ela 716'-10" I

KSIE-442 717'-9-1/2" I

RSIH-469 707'-6-1/2" I

RS;E-L69 707'-6-1/2" RS;H-476 707*-1-3/4" S!RE-9 737'-0" '

I S;RE-11 713'-6""

I SIRE-17 730'-0" I

SIRE-15 730'-0" I

S RE-!:

711'-a" S!RE-23 A&3 711'-4" 5:R5-!6 705'-0" Unit 1 - A=endnent No. 14, 49, 50 Unit 2 - Amend:ent No. 8, 43, 4A

TA31.E TS.3.12-1 (Page 3 of 3)

SAIETY ELA*ED SNU33ERS i

Snubbers In High Accessible ot* Ispecia11p'2adiacion

-+

Snubber Inaccessible Difficult Areas During No..

Lccetien.

-E-leva tiotr ---

(A or I) - " to Receve' Shut:!own UNIT II RHRH-13 Saf e:y Injection 673'-9" A

RERH-14 674'-0" A

RHRH-52 670'-6" A

RH M-54 670'-6" A

RERFJi-19 700'-11" 1

RHRRH-23 711'-2" I

RHRRH-28 707'-4" I

RSIH-265 699'-9" I

RSIH-268 713'-9-3/16" I

RSIH-343 719'-8-11/16" I

RSIH-349 703'-11" I

RSIH-350 702'-11" I

RSIH-353 A&3 701'-9" I

SIH-53 710'-3" A

  • SIRH-4A 711'-6-1/8" I

SIRH-4B 711'-3" I

SIRH-7 716'-3-1/16" I

SIRH-18 722'-6" I

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Unit 1 - Amendment No. 14, 49, 50 Unit 2 - Amendment No.

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TABLE TS.3 12-1 (Page 4 of 8)

SAFETY RELAND SHCCR SUPPRESSORS (SNU3BERS)

- Snubbers-In High Accessible or Especially Radiation Snubber.

Inaccessible - Difficult Areas During No.

Location Elevation

( A or I) to Remove Shutdown UNIT I RCRH-5 A&3 Reactor Coolant 732'-6" I

RCRH-12 A&B 720'-7" I

RCRH-26 76 2'-8" I

RCE-27 A&B 761'-7" I

RCRE-34 764'-7" I

RCRS-45 765'-1" I

FIRH-46 745'-10" I

765'-1" I

RCRH-47 RERRH-15 705'-6" I

RHRM-27 705'-6" 1

RH3'3-29 A&B 705'-6" I

UNIT II RCRH-3 Reactor Coolant 731'-6" I

RCRH-8 717'-6" I

RCFR-9 712'-0" I

RCRH-la 705'-9" I

RCRH-25 732'-2" I

RCRH-26 757'-7" I

RCRE-31 764'-1" I

RCRH-uS 724'-6" I

RCRE-;6 758'-3" I

RCRH-47 760'-3" I

RCF5-48 765'-1" I

RCRH-49 765'-l" I

RRCH-079 A&3 724'-9" I

RRCH-232 723'-2" I

RRCH-2S4 A&B 725'-8" I

RERRH-2 699'-0" I

REFJ2-4 705'-11" 1

RERRH-9 705'-11" 1

REKE-15 699'-0" I

Unit 1 - Amendment No. 14, 49, 50 Unit 2 - Amendment No. 8, 42, 44

-. ~.

TA3LE TS.3.12-1 (Page 5 of 8)

SAFETY REI.ATED Sb'iIBBERS

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"~ Snub 6ers In High Accessible or Especially Radiation Scubbe r-

- ~ - - - - ~

- ~ ~ - -

  • In~ccessible" Difficult Areas During a

No.

Loc at ion Clevation (A or I) to Remove Shutdown t.' NIT I C*a-359 Cooling ~4ater 705'-8" A

C*a-38 0 706'-11" A

C*a-3SS 709'-0" A

CLE-394 731'-0" A

C*a-39 5 746'-6" A

CL2-405 707'-10" A

C*a-429 722'-11" A

C*a-432 722'-11" A

C*a-433 735'-11" A

C*a-434 735'-11" A

C*a-436 737'-11" A

C*aH-80 730'-0" I

C*aH-81 729'-0" I

C*4RH-82 730'-0" I

UNIT II CA-34 Cooling Water 709'-3" A

C*a-35 746'-8" A

C'a-39 710'-6" A

C*a-40 710'-6" A

C*a-44 730'-11" A

C*a-45 709'-0" A

C*4-49 723'-0" A

C*a-50 723'-10"-

A C*a-5 736'-0" A

C*a-54 728'-0" A

Unit 1 Amendment No. 14, 49, 50 Unit 2 - Amendment No. 8, 43, 44 e

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TA3LE TS.3.12-1 (Page 6 of 8)

SAFETYRELANEDSNU3BERS Snubbers In High

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Accessible or Especially Radiation Stubber Inacc e s s i*o[e ' Diff'icult Areas During No.

Location Elevation

( A or I).

_to Remove Shutdown y

- - ~ -

AFWB-72 Feecvater 752'-0" I

AFWH-82 728'-11" A

~

AFWH-84 728'-11" A

UNIT II AFWH-72 A&3 Feecuater 706'-3/4" A

FWH-72 A&3 751'-0" I

UNIT I,

  • 25.12620.003 3

Steam Generator 760'-9-1/2" I

I

  • 25.12520.003 - 4 760'-9-1/2" I

I

  • 25.12620.003 - 5 760'-9-1/2" I

X

  • 25.12620.003 - 6 760'-9-1/2" I

I

  • 25.12620.003 - 7 760'-9-1/2" I

I

  • 25.12620.003 - S 760'-9-1/2" I

X

  • 25.126 2C-003 - 10 76O'-9-1/2" I

X

  • 25.12620.003 - 15 760'-9-1/2".

I I

UNIT II

  • 25.12620.003 - 1 760'-9-1/2" I

X

  • 25.12620.003 - 2 760'-9-1/2" I

I

  • 25.12620.003 - 9 760'-9-1/2" I

X

  • 25.12620.003 - 11 760'-9-1/2" I

X

  • 25.12620.003 - 12 760'-9-1/2" I

X

=25.12620.003 - 13 760'-9-1/2" I

X

  • 25.12620.003 - 14 760'-9-1/2" 2

X

  • 25.12620.003 - 16 760'-9-1/2" I

X UNIT I C7CE-182 Che=tcal & vol 707'-6" A

RCRE-16 A&3 Control 705'-2" I

RCRE-19 705'-2" I

RCRE-21 705'-7" I

RCRE-23 A&3 715'-11" I

RC7CE-907 A&B 717'-11" I

KC7CE-1293 712'-0" I

RPCE-22 703'-1" I

R?CH-23 703'-1" I

R?CE-121 707'-9" I

R?CE-139 704'-4" I

RPCH-140 707'-7" I

RPCH-146 714'-7" I

RPCE-147 714'-10" I

WDRE-24 707'-9" I

Notes

  • Preservice docu=ented testing of 900K Anker Holth snubbers has qualified their operability for all design conditions. Functional testing specified in 4.13 C is not required.

Unit 1 - Amendment No. 14, 49, 50 Unit 2 Amendment 30. 8, 43, 44 7

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TA3LE TS.3.12-1 (Page 7 of 8)

SATHTY RII.ATI3 SNU33ERS Scubbers In High Accessible or Especially Radiation Snubber Inaccessible Difficult Areas During No.

Loc ation Elevation (A or I) to Re=ove Shutdown

~

UNIT'IT

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RCVCH-1396 Che=1 cal & Vol 702'-10" I

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RCVCH-ISOS toutroI~ ~ ~ ' ~ 708';6"' ~

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RCVCH-1513 710'-1" I

RCVCH-1524 719'-1" I

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RCVCH-1574 721'-0" I

RCVCH-1668 705'-5" I

RCVCH-1373 722'-11" I

RCVCH-1389 706'-1" I

RICH-253 704'-4" 1

RRCH-255 704'-8" I

RRCH-261 707'-1" I

RRCH-288 707'-2" I

RRCH-291 704'-6" I

RRCH-292 704'-7" I

CVCH-166 708'-0" A

UNIT I

,CCH-304 Comp Cooling 717'-7" A

CCH-373 712'-4" A-CCH-376 A&3 700'-5" A

CCH-377 703'-0" A

CCH-378 708'-4" A

CCH-380 670'-8" A

CCH-381 A&3 671'-4" A

CCH-397 699'-3" A

CCH-398 A&3 671'-4" A

UNIT II

'CCH-161 Comp Cooling 717'-7" A

C CH-; 66 719'-11" A

CCH-167 720'-0" A

CCH-172 720'-0" A

CCH-173 708'-5" A

CCH-176 705'-3" A

CCH-179 A&3 671'-4" A

CCH-130 670'-8" A

CCH-I81-708'-4" A

CCH-IS2 704'-2" A

CCH-lSS A&3 671'-4" A

CCH-186 670'-10" A

UNIT I RCSH-81 Contain=ent Spray 76"'-9" I

FCSH-82 760'-8" I

RSCH-83 A&3 732'-1" I

UNIT II CSH-75 A&B Containment Spray 731'-10" I

CSH-76 752'-7" I

CSH-79 751'-9" I

CSH-82 A&3 731'-11" 1

CSH-83 767'-2" I

CSH-B4 767'-1" I

CSH-210 698'-0" I

C5H-215 698'-0" A

CSH-224 710'-6" A

Unit 1 - Amendment No. 14, 49, 50,

Unit 2 - Amendment No. 8, 43, 44

TS.A.13-1 4.13 SNU33ERS Amelicabili:y A.pplies to periodic tes. ting and s.ur.ve.il..l.ance require =e,nts of. safety related hyc.raElle scuobe

~

rs.

Ob j ective To verify the integri:y and operabili:y of hydraulic snubbers.

Soecification The following surveillance require en:s apply :o all snubbers listed in Table TS.3.12-1.

These requirements aug=ent the inspections required by Section II of the ASNI Code.

A.

Visual Inspection of snubbers shall be conducted in accordance vi:h the following schedule:

No. of Snubbers Found Nex Required Inoperable per Inspection Period Inseec: ion Period 0

18 monens + 25 1

12 =enths 7 25:

2 6 months 7 25:

3,4 124 days

  • I5:

5,6,7 62 days}[25:

8 or more 31 dav.s +.25:

The required inspec:ica interval shall not be leng:hened more

han one s:ep a: a :i=e.

Snubbers =ay be ca:egori:ed in :vo greups, "ac:essible" or

" inaccessible" based on their accessibili:y for inspec: ion during reae:cr cpera:icn. These two greups ay be inspec:ed indepe:dently according :o :he above schedule.

  • 3.

Visual inspections shall verify (1) : hat there are no visible indications of damage or 'i= paired operabili:y, (2) attach =ents to the supporting structure are secure, and (3) i: those locations unere snubber =ovement can be manually induced without disconnec:-

i=g the snubber, that :he snubber has freedom of move =ent and is not fro:en up.

Snubbers vnich appear inoperable as a result of visual inspee: ion ay be deter =ined Operable for the purpose of establishi:g the nex visual inspection in:erval by:

Unit 1 - Amendment No. 14, 50 Unit 2 - Amendment No. 8, 44

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- ~-

a

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,aw

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TS.4.13-2 i

Clearly establishing the caese of the rejection for that a.

particular. snubber and for others that may be generically susceptible; and l

b.

Functionally testing the 2Tfected'sndbber in the~as-fodsd

condition'and finding it operable per Specification 4.13.D.

~ -

However, when the fluid port of a hydraulic snubber is found to be uncovered, the snubber shall be considered inoperable for purposes of establishing the next visual inspection interval. All hydraulic

~

snu'ebers connected to an inoperable common hydraulic fluid reservoir shall be considered as inoperable snubbers.

C.

Except as specified below, functional testing of snubbers listed j

in Table TS.3.12-1 shall be conducted at least once per 18 months during cold shutdown. Ten percent of the total of each type 4

snubber shall be functionally tested either in place or in a bench test.

For each snubber that does not meet the functional test I

acceptance criteria in Specification 4.13.D below, an additional j

een percent of that type of snubber shall be functionally tested until no more failures are found or all snubbers of that type have been tested.

The representative sample selected for functional testing shall 4

include the various configurations, operating environments, and the range of size and capacity of the snubbers.

Twenty,five percent of the sample shall include snubbers from the following three categories.

4 a.

The first' snubber away from a reactor vessel nozzle 4

b.

Scubbers within five feet of heavy equipment (valve, pu=p, turbine, motor, etc) c.

Snubbers within ten feet of the discharge of a safety /

relief valve J

Snubbers identified in Table 75.3.12-1 as "High Radiation Area" or

+

" Difficult to Remove" are exempt frem functional testing provided

.a justifiable basis for exemption is presented for Commission review; snubber life testing is performed to qualify snubber operability I

for all' design conditions; or snubbers of the same type, configuration,-

and similar service have been tested for a ten year period and no f ailures i

have occurred.

In such exempt cases, a qualitative test report shall be

)

en file to substitute for the required functional testing.

In addition to the regular sample and specified re-sampling, a

snubbers which failed the-previous functional test shall be retested during the next test period.

If a spare snubber ',es been i=scalled in place of a failed snubber, r. hen bo-h the failed snubber, if it is repaired and installed in another position, and the spare snubber shall be retested.

Unit 1 - - Amendment No. 14, 50 Unit 2 - Amendment No. 8, 44

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TS.4.13-3 If any snubber selec:ed for functional testing ei:her fails

o lockup or fails to move (i.e. frocen in place) the caust~

shall be evaltIated'and all~ snubbers sTabject to ih'e s'ame' defecc

~

~

snall be functionally :ested. This testing is in. addi:i.on to the

~

~ regul'7e 'sa np'Te ' aid' spec'iiiedli' samples.

~

D.

Hydraulic snubber functional tests shall verify that:

a.

Activa: ion (restraining action) is achieved within the specified range of velocity or acceleracion in both :ension and compression.,

b.

Snubber bleed, or release race, where required, is within the specified range in compression or tension. For snubbers specifically required to not displace under continuous load, the ability of the snubber to withs:and load withput displace-ment shall be verified.

E.

An engineering evaluation shall be performed for all components supported by inoperable snubbers. The purpose of :his engineering evaluation shall be to determine if the components were adversely

~

affected by the inoperable snubber (s) :o ensure : hat the ecmponents remain capable of meeting the designed service.

F.

The installation and maintenance records for each snubber listed in Table TS.3.12-1 shall be reviewed at least once every la nonths to' verify : hat :he indicated service life vill not be exceeded prior to :he nex: scheduled snubber service life review.

If :he indica:ed service life vill be exceeded, the snubber service life shall be reevalua:ed or :he snubber shall be replaced or recondi-tiened to extend its service life beyond the date vf the nex:

scheduled service life reviev. This reevaluation, replace =en:,

or recondi:ioning shall be indicated in the records.

Basis The visual inspection frequency is based upon sain:aining a constant level of sn'ubber protec: ion to systema. Therefore, the required inspection interval varies inversely vich the observed snubber failures and is deter =ined by :he number of inope able snubbers fcund during an inspectiet.

Inspections performed before that interval has elapsed may be used as a nev reference point to deter =ine the 7ex: inspection. However, the resul:s of such early inspections performed before the original required ti=e interval has' elapsed (nominal time less 25%) may not be used to lengthen the' required inspec: ion interval. Any inspection whose results require a shorter inspec: ion interval vill override the previous schedule.

Unit 1 - Amendrent No. 14, 50 Unit 2 - Amendment No. 8, 44 e

T-

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o TS.4.13-4 When the cause of :he rejection of a snubber is clearly established and re=edied for that snubber and for any other snubbers that =ay be generically susceptible, and verified by inservic.e fune:ional te_ sting, that snubber =ay be exe=pted frem being counc,ed as inoperable. Gene:ically susceptible snubber,s are ;, hose which are of a sp,e,qi8ic, =ake.or model and.have -he same design features directly related :o rejection of the snubber by visual inspec:ica, or are similarly located or exposed to :he same environmental' conditions such as :emperature, radia: ion, and vibra: ion.

When a snubber is found inoperable, an engineering evaluation is perfor=ed, in addi:icn :o the de er=ination of :he snubber sede of failure, in order to detersi e if any safety-related component or sys:em has been adversly af fected by :he inoperability of the snubber. The engineering eva*uation shall ceter=ine whether or not the snubber mode of failure has impar:ed a

~

s ignificant effect or degradation on the suppor:ed component or system.

To provide assurance of snubber functional reliability, a representative sz=ple of 10% of the ins:alled snubbers will be functionally tes:ed' during plant shutdowns at 18 month intervals. ~Cbserved f ailures of these sample snubbers shall require func:ional testing of addi:ional units.

hhe service life of a snubber is evaluated via =anufac:uier input and infor=a: ion :hrough consideration of :he snubber service condi: ions and associa:ed installa: ion and =aintenance records (newly installed snubber',

seal replaced, spring replaced, in high radiation area, in high temperature area, etc.

.).

The requirement to monitor :he snubber service life is included to ensure : hat the snubbers periodically undergo a perfornance evaluation in view of their age and operating conditions.

These records vill pr: vide s:atis:ical bases for fu:ure :ensidera: ion of snubber service life.

All safety-rela:ed snubbers installed or planned for use at Prairie Island are hydraulic snubbers.

No =echanical snubbers 2:e used.

t 7

Unit 1 - Amendment No. 14, 50 Unit 2 - Amendment No. 8, 44

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TABLE TS.4.1-1 (Page 1 of 5)

'T MINIHUM FREQUENCIES FOR CIIECKS, CALIBRATIONS AND TEST OF INSTRUMENT CllANNELS s

E

^

2 Channel Functional hesponse T

Description Check Calibrate Test Test Remarks

'U

1) Once/ shift when in service E 1.

Nuclear Power S(l)

D(2)

M(3)

R

2) llent balance c:

Range M(4)

Q(4)'

M(5) 3)SignaltoaT;bisfableaction

!!(6)

(permissive, rod stop, trips),

S

~

n 2

.P(7) with the exception of the

l

'/.

items covered in temark #7.

4) Upper and lower c iamb' ears for axial of f-set using i'n-core i

i dete'ctors I

l

5) Simulated signal for testing positive and negakive rate bistable action I
6) Quadrant Power Tilt Monitor
7) P8 and P10 permis'sive's and the 25% High Flux *iLog Setpoint Trip.

2.

Nuclear Inter-

  • S(l)

NA T(2)

R

1) Once/ shift when in service mediate Range
2) Log Level; bistable action (permissive, rod stogi, trips) 3.

Nuclear Source

  • S(l)

NA T(2)

R

1) Once/ shift when in service

.2) Bistable action (alarm, trips)

Range 4.

Reactor Coolant S(1,2)

R(1,2,3)

M(1)

R(1)

1) Overtemperature AT

>g Temperature M(2)

R(2)

2) Overpower AT g!

T(3)

3) Control Rod Bank ' Insert, ion es N

aE Limit Monitor u

g g

5.

Reactor Coolant S

R H

NA Flow 4 g 6.

Pressurizer S

R H

NA Water Level i

y 7.. Pressurizer S

R H

HA mg Fressure w

e f

U1o 3

,3

~

I

,\\ ~

_3,,

O TABhE TS.4.1-1 (Page 5 of 5)

,t Channel Functional

Response

Dencriptfory Check Calibrate Test Test-Remarks s

' n

'.6 g p a NA NA Ireludes.all those.in FSAR r r 35.

Event Monitoring M

R 4

n n r.

Instrumentation Table 7.7-2 and Table TS.3.15-1

.not included.31sewhere in this.

UU

< Table I

s*

w w u u 0 0 2

. a a-36.

Steam Exclusion W

R H

NA See FSARrAppendix I, Section pp Actuation System I.14.6 /

s s

r r n.. n 37.

Pressurizer PORV NA R

R' NA Instrument Channels for PORV Control Control neluding Overpressure Mitigati n fryF.em 38.

Degrade 1 Voltage NA R

H NA 4KV Safeguard Busses j

t 39.

Loss of voltage NA R

M NA 4KV Safeguard Russes e

i t

I S

Each ShifL D

Daily N$

H-W Weekly g

gg

$S M

Monthly

?

E o a a

o o Q

Quarterly un n n a

s

' v.

v. 2 o o R

Each refueling shutdown gg P

Prior to each startup if not dt...e previous week

.w.

T Prior to each startup followin; shutdown in excess of 2 days if not done in the previous 30 days h

?I N5 Not Applicable u

mu o

e-t to-See Specification 4.1.D ml

s
  • TS. 6.6-2

.y 6.

Plant radiation and contamination surveyc.,

7.

Changes made to the plant as it is described in the Final Safety Analysis Report, reflected in updated, corrected and as-built drawings.

8.

Cycling beyond normal limits for those components

~ that Tave t u n~dasignFd ~to operate safely for"a limited number of cycles beyond such limits.

9.

Reactor coolant system in-service inspections.

10.

Minutes of meetings of the Safety Audit Co= mitt a.

11.

Records of invironmental Qualification which are covered under the provisions of paragraph 6.8.

12.

Records of the service lives of all safety-related snubbers, including the date at which the service life commences and associated installation and maintenance records.

Prftt frits ptttpht 01M/1920 Unit 1 - Amendment No. 50 Unit 2 - Amendment Ih). 44 m_.

,m

,

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