Text

Change a to Rev 1 to JNS-PTN-200, Second Ten-Yr Inservice Insp Interval Inservice Testing Program for Pumps & Valves.
	ML17347B285
Person / Time
Site:	Turkey Point
Issue date:	08/17/1989
From:	Anderson E, Hays J, Southworth F; FLORIDA POWER & LIGHT CO.
To:	;
Shared Package
ML17347B284	List: ML17347B283; ML17347B285;
References
	JNS-PTN-200, NUDOCS 8908300069
	Download: ML17347B285 (540)
	v • d • e

PLORZDA POWER and LIGHT COMPANY NUCLEAR ENERGY SERVICES 700 Universe Blvd.

Juno Beach, Plorida 33408 SECOND TEN YEAR ZNSERVZCE INSPECTION INTERVAL ZNSERVZCE TESTING PROGRAM POR PUMPS AND VALVES TURKEY POINT NUCLEAR POWER PLANT UNIT NO 3/4 PION BOX 3088 PLORIDA CITY'LORIDA 33034 COMMERCIAL SERVICE DATE PTN-3 DECEMBER 14p 1972 COMMERCIAL SERVICE DATE PTN 4 SEPTEMBER 7p 1973 NRC DOCKET NUMBER! 50-250 / .50-251 DOCUMENT NUMBER: JNS-PTN-200 REV. 1 ADMINISTRATIVE APPROVALS:

PREPARED BY:

- DATE: - I- 8 ISI ENGINEER CODEES & PROGRAMS PREPARED E I EE PLANT SUPPORT

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REVIEWED BY ~ DATE: L2. 8 APPROVED BY:

J ER - MCI DATE: /

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APPROVED BY: DATE! i489 J MANA ER - PLANT SUPPORT APPROVED BY: DATE: /

- NUCLEAR ENERGY PLANT REVIEWS AND APPROVALS:

REVIEWED BY: DATE:

PLANT IST C R INATOR APPROVED BY: DATE:

T C DEPARTME T SUPERVISO PNSC /

APPROVAL DATE ~

'PLT. MGR.

APPROVAL OP~T OVPEEE 8qpg300069 0500PP50 j DATE pDR ~DOC" pNU

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TUEGCEY POINT UNIT NO. 3/4 DATE:12-12-88 SECOND TEN-YEAR ZNSERVICE TESTING PROGRAM REVISION: 1 TABLE OP CONTENTS TITLE PAGE/COVER SHEET......... ~ ~ ~ 1 TABLE OF CONTENTS.............. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 2 RECORD OF REVISION............. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 14 ABSTRACT ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 15 ABBREVIATIONS.................. ~ 16 DEFINITIONS.................... ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

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~ ~ ~ 18 SECTION I

1.0 INTRODUCTION

.'.......................................20 1.1 PROGRAM APPLICABILITY............... ...........20 1 ~ 1 ~ 1 TLGOCEY POINT UNIT NO. 3 '. ~ ~ ... ~ ~ ~ .. ......20

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1.1.1.1 OPERATING LICENSE..................20 1.1.1.2 AMENDMENT TO OPERATING LICENSE.....20

1. 1. 1. 3 NRC APPROVAL... ~.................. 20 ..

1.1.2 TUMMY POINT UNIT NO. 4.. ~ ~................20'

~ 1~ 2. 1 OPERATING LICENSE. ~ ~ ~ ~ . ~ ~ ~ ~ ~ ~ ~ ~... ~ 20

1. 1 ~ 2 ~ 2 AMENDMENT TO OPERATING LICENSE.... 20 ~

1~ 1.2.3 NRC APPROVAL ~ . ~ ~ ~ ~ ~ . ~ ' ~ .. ~.....21

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1.2 INSPECTION INTERVAL... ~ ............ .... ........21 1.2.1 FIRST INSERVICE INSPECTION INTERVAL........21 1' '.1 TUEQXY POINT UNIT NO 3 ' .... .....21 ~

1.2.1.2 TURKEY POINT UNIT NO. 4............21 1.2 ' FIRST ZNSERVICE INSPECTION, INTERVAL EXTENSION..................................21 1.2 ' ' TURKEY POINT UNIT NO. 3...... .....21 ~

1.2 ' ' TURKEY POINT UNIT NO. 4............21 1.2.3 SECOND INSERVZCE INSPECTION INTERVAL.......22 1 ' ' ' X%JEGCEY POINT, UNIT NO. 3 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 22 1.2 ~ 3 ~ 2 TURKEY POINT UNIT NO. 4... ~ ~ ~ ~ ~ ~ ~ ..22

4' TUEL"Y POINT UNIT NO. 3/4 DATE:12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 TABLE OP CONTENTS 1.3 APPLICABLE DOCUMENTS.............................22 1.4 APPLICABLE EDITIONS AND ADDENDA TO SECTION XZ....22 1.4.1 FIRST ZNSERVICE INSPECTION INTERVAL........22 1.4.2 SECOND INSERVZCE INSPECTION INTERVAL.......23 1.5 SUBSEQUENT CODE EDITIONS 6 ADDENDA...............23 1.6 SYSTEM CLASSIFICATIONS...........................23 1 ~ 6 ~ 1 CLASS 1 ~ ~ ~ ~ ~

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~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 2 3" 1.6.2 CLASS 2 AND 3. . . ...... .. ..... ........23 SECTION ZZ 2.0 DEVELOPMENT OF THE INSERVZCE PUMP TEST PROGRAM.......24 2.1 PUMP PROGRAM IWP-1100............................24 2.1.1 PUMPS EXEMPT FROM TESTING IWP-1200.........24 2 1~2 IWP-1400 BYPASS LOOPS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ . .. 24

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2.1.3 ZNSERVICE TEST IWP-3100 ..............24 2.1.4 REFERENCE VALUES IWP-3110..................25 2' ~ 5 EFFECT OF PUMP REPAIRS, REPLACEMENTS & ROUTINE SERVICING OF REFERENCING VALUES IWP-3111...25 2 ~ 1 ~ 5 ~ 1 REPLACED PUMPS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 25 F 1.5 ' REPAIRED PUMPS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ .... ~ ~ ...25 2.1.6 ROUTINE SERVICING OF PUMPS.................25 2' ~ 7 DEVIATIONS.................................26 2.1.8 ESTABLISHING ADDITIONAL SET OF REFERENCE VALUES ZWP 3112 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 26

2. 2 ANALYSIS OF RESULTS ZWP-3200........................ 26 2.2.1 ALLOWABLE RANGES OF INSERVZCE TEST QUANTITIES IWP-3210...... ................26 2.2.2 ANALYSIS OF TESTS IWP-3220.................29

D i TURKEY POINT UNIT NO. 3/4 DATE: 12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 TABLE OP CONTENTS 2.3 CORRECTIVE ACTION IWP-3230........,............,....29 2.3.1 ALERT RANGE.. ~ ~ -.. ~ ~ ~ ~ ~ ~ ~ .. . ...........29

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2.3.2 REQUIRED ACTION RANGE......................29 2.3.3 CORRECTIVE ACTION.... .....................29 2.4 SCOPE OF TESTS IWP-3300.. . ~ ~ ~ ~ ... ~ . ~ ~ ..... ......29

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2 5 FREQUENCY OF TEST IWP-3400... ......................29 2.6 BEARING TEMPERATURES IWP-3500.......................30 2.7 DIFFERENTIAL PRESSURE IWP-4240......................30 2.8 FLOW MEASUREMENTS ZWP-4600..........................30 2 ' TEMPERATURE MEASUREMENT (BEARINGS IWP-4310 ~ ~ ~ ~ ~ . ~ ~ ~ 32 2.10 VIBRATION (VIBRATION AMPLITUDE IWP-4510)...........32 SECTION ZZZ 3.0 DEVELOPMENT OF THE INSERVICE VALVE TEST PROGRAM.........33 3.1 VALVE PROGRAM ZWV-1100...........................33 3 '.1 VALVES EXEMPT FROM TESTING IWV-1200 ~ ~ ~ ~ ~ ~ ~ ~ 33 3.2 VALVE CATEGORIES ZWV-2200........................33 3.2.1 CATEGORY A................ ........ .......33 3.2.2 CATEGORY B............... ..... . .........34 ~

3.2.3 CATEGORY C.................................34 3.2.4 CATEGORY D.................................34 3.3 VALVE REPLACEMENT, REPAIR Ec MAINTENANCE IWV-3200.34 3.4 VALVE POSITION INDICATOR .VERIFICATION IWV-3300...34 3.5 INSERVZCE TEST CATEGORY A & B VALVES IWV-3400....34 3.5.1 TEST FREQUENCY IWV-3411......... .........',.34 ~

3.5.2 EXERCISING ZWV-3412........................35

TURKEY POINT UNIT NO. 3/4 DATE:12-12-88 SECOND TEN-YEAR INSERVXCE TESTING PROGRAM REVISION: 1 TABLE OF CONTENTS 3.5.2.1 STROKE.............................35

3. 5. 2. 2 VALVE DISK MOVEMENT................ 35 3.5.3 POWER OPERATED VALVES IWV-3413............. 36 3.5.3.1 FULL STROKE.....................-..36 3.5.3.2 STROKE TIME........................36 3 ~ 5 ~ 4 VALVES ZN REGULAR USE IWV-3414 ~ ~ ~ ~ ~ ~ . ~ ~ ....36 3 ' ' FAIL SAFE VALVES ZWV-3415 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ . ~ ~ 36 3.5.6 VALVES ZN SYSTEMS OUT OF SERVICE ZWV-3416..36 3.5.7 CORRECTIVE ACTION IWV-3417 ~ ~ ~ ~ ~ ~ ~ ... .....38

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FAILURES' 3.5.7.1 POWER OPERATED VALVES. ~ .. .........38:

3.5 '.2 VALVE . ~ ~ ~ ~ ~ ~ ~ . ~ ~ ;. ... .38

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3.6 VALVE LEAK RATE TEST IWV-3420 ~ ~ ~ ~ . ~ ~ ~ ~ . ... .... 38

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3.6 ' VALVE LEAK RATE TEST CATEGORY A IWV-3421...38 3.6 2 FREQUENCY IWV-3422.... ........ ..........38 3.6.3 DIFFERENTIAL TEST PRESSURE IWV-3423........39 3 '.F 1 GLOBE. ~ ~ ~ ~ ~ ~ ~ .. ~ ~ ~ .. ~ ~ ~ .. ~ .. ~ ~ ... ~ 39 3 '.3.2 BUTTERFLY........ ~ . ~ . ~ .............39 3 ' ' ' GATE ~ ~ ~ ~ ~ ~ ~ ~ ~ . ~ . ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ .. ~ ~ ....39 3.6.3 4 VALVES GENERAL TEST DIRECTION......39 3.6.3 ' PRESSURE DIFFERENTIALS ~ ~ ~ ~ .... ....39

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3 '.3.6 REDUCED PRESSURE TESTING ..........40 3.6.4 SEAT LEAKAGE MEASUREMENT IWV-3424..........40 A. GENERAL. ~ ..........................40 B. GATE VALVE...... ~ .... .. ..........40

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3.6.5 ANALYSIS OF LEAKAGE RATES IWV-3426...... -. -40

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TURKEY POINT UNIT NO ~ 3/4 DATE:12-12-88 SECOND TEN-YEAR ZNSERVICE TESTING PROGRAM REVISION: 1 TABLE OP CONTENTS 3.6.5.1 WATER..... .... ..................41 3 ~ 6 ~ 5 ~ 2 AZRo ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 41 3.6.6 CORRECTIVE ACTION IWV-3427................41 A. LEAKAGE RATES' ~ ~ .. .~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 41 B. VALVES 6" AND LARGER. . .. ~ ~ . ~ ~ . .41

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3.7 CATEGORY C VALVES IWV-3500 ' .. ..... . . .......41

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3.7.1 SAFETY AND RELIEF VALVE TESTS IWV-3510....41 3.7.1.1 TEST FREQUENCY IWV-3511 ... ......41 3.7.1.2 TEST PROCEDURE IWV-3512...........43 3.7.1.3 ADDITIONAL TESTS IWV-3513.........43 3.7.1 ' CORRECTIVE ACTION IWV-3514 '......44 3.8 TESTS FOR CHECK VALVES IWV-3520....... ........44 3.8.1 TEST FREQUENCY IWV-3521.... ..... .......44 3.8.2 EXERCISING IWV-3522.......;..............44 3.8 ' NORMALLY OPEN VALVES ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ . ~ ~ ~ .' .44 ~ ~

3.8.4 NORMALLY CLOSED VALVES' ~ . ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ .45 3.8 ORRECTIVE ACTION IWV-3523 '.............45 3.9 CATEGORY D VALVES IWV-3600.....................46 3 '.1 EXPLOSIVELY ACTUATED VALVES IWV-3610.....46 3.9.2 RUPTURE DISK TESTS ZWV-3620..............46 3.10 INSERVZCE TEST REQUIREMENTS IWV-3700..........46

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TURKEY POINT UNIT NO ~ 3/4 DATE: 12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 TABLE OP CONTENTS SECTION IV 4.0 RELIEF REQUESTS........................... ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 48 4.1 NE% AND IMPROVED TECHNIQUES...... ..-............48 4.2 FORMAT FOR RELIEF REQUESTS ...-.. ... ...........48 RELIEF REQUEST STATUS TABLE......................49 JUMP ~P~~G ~RiJ~E'S.

RELIEF REQUEST NO. 1.............................50 RELIEF REQUEST NO. 2......-.............. .......51 RELIEF REQUEST NO ~ 3. ~ . ... ~ . ~ ~ ... ~ ~ ~ . ~ ~ .... ...52

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RELIEF REQUEST NO. 4.. ..... ...... .............53 RELIEF REQUEST NO. 5.........,...................54 RELIEF REQUEST NO. 6.... ...... .................55 RELIEF REQUEST NO. 7.............................56 RELIEF REQUEST NO. 8.............................57 RELIEF REQUEST NO. 9.. .. .....................58

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RELIEF REQUEST NO. 10. ..........................59 RELIEF REQUEST, NO. 11.............. .............60 RELIEF REQUEST NO. 12 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ..61

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RELIEF REQUEST STATUS TABLE. ~ ~ ~ ~ ~ ~ ~ ~ .. ~ ~ ~ ~ .. ~.... 62 REEZQR MQLhHX ~SAKS RELIEF. REQUEST NO. 1~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ .. ~ ~ ~ ~ ..... ~ ....67 RELIEF REQUEST NO. 2 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 68 RELIEF REQUEST NO. 3'.. . ........................69 RELIEF REQUEST NO. 4.......<.... ... ...... .....'.70~ ~

RELIEF REQUEST NO. 5 ~ ~ ~ l~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 71 7

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TURKEY POINT UNIT NO. 3/4 DATE:12-12-88 SECOND TEN-YEAR ZNSERVICE TESTING PROGRAM REVISION: 1 TABLE OP COMTENTB RELIEF REQUEST NO. 6... ....... ... .............72 RELIEF REQUEST NO. 7.............................73 RELIEF REQUEST NO. 8...... . ....................74

~CHEMECA & ~VO ~g g~OT~O ~g'~g RELIEF REQUEST NO. 1 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 75 RELIEF REQUEST NO. 2 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 76 RELIEF REQUEST NO. 3 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 77 RELIEF REQUEST NO. 4 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 78 RELIEF REQUEST NO. 5 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

79 RELIEF REQUEST NO. 6 ~ ~ ~ ~ ~ ~ ~ ~ ~ vo ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 80 RELIEF REQUEST NO. 7 ~

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~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 81 RELIEF REQUEST NO. 8 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 82 RELIEF REQUEST NO. 9 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 83 RELIEF REQUEST NO. 10.................... ~ ~ ~ ~ ~ ~ ~ ~ 84 RELIEF REQUEST NO. 11.................... ~ ~ ~ ~ ~ ~ ~ ~ 85 RELIEF REQUEST NO. 12 ~ ~ ~ ~ '.. ~ ~ .. ...

~ ....;.......86 RELIEF REQUEST NO. 13............................87 RELIEF REQUEST NO. 14 ' . ~ .. ~ . ~ ~ ~ .... ~ ........ ~ ~ ...88 RELIEF REQUEST NO. 15...... ......... .. . .....89 RELIEF REQUEST NO. 1 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 90 RELIEF REQUEST NO. 2 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 91 RELIEF REQUEST NO. 3 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 92 RELIEF REQUEST NO. 4 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 93 RELIEF REQUEST NO. 5 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ 94

At TKUCEY POINT UNIT NO. 3/4 DATE: 12-12-88 SECOND TEN-YEAR INSERVXCE TESTING PROGRAM REVISION: 1 TABLB OP CONTBNTS RFJ(IEF REQUEST NO. 6.............................95 ttttlot ooottt. Hl~oltt tttt ttt At, RELIEF REQUEST NO. 1 ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ 96 RELIEF REQUEST NO. 2 ~ ~ ~ o ~ ~ ~ ~

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~ ~ ~ ~ ~ ~ o ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 97 RELIEF REQUEST NO. 3 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ 'o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 98

~S FETY YNJECTYON RELIEF REQUEST NO. 1 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 100 RELIEF REQUEST NO. 2 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 101 RELIEF REQUEST NO. 3 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 102 RELIEF REQUEST NO. ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 103 '

RELIEF REQUEST NO. 5 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o 104 RELIEF REQUEST NO. 6 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 105 RELIEF REQUEST NO. 7 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 106 RELIEF REQUEST NO. 8 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 107

'RELIEF REQUEST NO. 9 ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 108 t

RELIEF REQUEST NO. 1 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 1 09 RELXEF REQUEST NO. 11............................110 RELXEF REQUEST NO. 12.......... .................111 RELIEF REQUEST NO. 13...o........................112 RELIEF REQUEST NO. 14......... ..................113

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RELXEF REQUEST NO. 15..... .. ...................115 RELIEF REQUEST NO. 16............................116 RELIEF REQUEST NO. 17............... ............117 RELIEF REQUEST NO. 18........ ..................118

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RELIEF REQUEST NO. 19................ ...........119 ~

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TURKEY POINT UNIT NO. 3/4 DATE:12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 TABLE OP CONTENTS RELIEF REQUEST NO. 20.....-. . . ... ......'.....120 RELIEF REQUEST NO. 21.. ~ ......... ~ ~ ~ . ~ ~ ~ . ~ .. ~ ~ ~ ~ ~ 121 RELIEF REQUEST NO. 22 '.... ...-... .............122

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RELIEF REQUEST NO. 1 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 124 RELIEF REQUEST NO ~ 2 ~ ~ s ~ ~ ~ ~ ~ . ~ .... ~ . ~ .. ..~ ~ ~ ...125

~IN STEAg ~SS~TE RELIEF REQUEST NO. 1 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ . ~ ~ ~ ~ ~ ~ ~ ~ ~ .. ~ ~ ~ ~ ~ 126 RELIEF REQUEST NO. 2 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 127 JutEH~ZZ k ZEK~ula RELIEF REQUEST NO. 1............ ................128 RELIEF REQUEST NO. 2 ~ ~ ~ ~ ~ . ~ ~ ~ ~ ~ ~ ~ . ~ ~ . ~ ~ ..........129 RELIEF REQUEST NO. 3......... ....'..............130

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RELIEF REQUEST NO. 4 ~ ~ ~ ~ ~ .. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ . ~ ~ . ~ ~ ~ . ~ 131 RELIEF REQUEST NO. 5 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ . ~ ~ . ~ ~ ~ ~ ~ 132 RELIEF REQUEST NO. 6 ' . ~ .. ~ ~ . ~ ... ..........

~ ~ ~ . F 133 IMKIHEIZ gjgU~ubq oOO s~~~cq g s 41Xl RELIEF REQUEST NO. 1 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ .....134 RAWLY ~

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RELIEF REQUEST 1.............................135 NOo RELIEF REQUEST NO. 2 ~ ~ .. ~ ~ ~ ~ ... .. ..

~ ~ ~ ~ ~ ~ .....136 RELIEF REQUEST NO. 3.............................137 2BIIR8X HhKEIIR RELIEF REQUEST NO. 1.............................138 CONT 10

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TUESDAY POINT UNIT NO. 3/4 DATE:12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 TABLE OP CONTENTS RELIEF REQUEST NO. 1 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 139 RELIEF REQUEST NO. 2 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 140 RELIEF REQUEST NO ~ 3 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

14 1 RELIEF REQUEST NO. 4 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 142 RELIEF REQUEST NO. 5 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 143 RELIEF REQUEST NO. 6 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 144 RELIEF REQUEST NO. 7 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 145 RELIEF REQUEST NO. 8 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

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RELIEF REQUEST NO. 1 ~ ~ ~ ~ ~ ~ ~ ~ ~ vo ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 147 RELIEF REQUEST NO. 2 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ 148 RELIEF REQUEST NO. 3 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 150 SECTION V 5.0 10 CFR 50, APPENDIX J. ~ ~ ~ . ~ ~ ~ ~ ~ ~ ~

VALVES'

.. ~ ~ ~ . ~ ~ ............151 5.1 APPENDIX J TESTING......... ~ ....... .............151 5.2 SEAT LEAKAGEo.o .oo..oo.oooo.ooo.o. .oo.o..o....151 5.3 CONTAINMENT ISOLATION ... ................151

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SECTION VZ 6.0 RCS PRESSURE ISOLATION VALVES....... ...............155 SECTION VIZ 7.0 PIPING AND INSTRUMENTATION DIAGRAMS..............157 SECTION VZZZ 8.0 RECORDS IWP-6000o-.ooo........oo.o...... ..............160 F 1 PUMP RECORDS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 160 8 ~ 1 ~ 1

SUMMARY

LISTING ZWP-6210, ..................160 11

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TUEDCEY POINT UNIT NO. 3/4 - DATE:12-12-88 SECOND TEN-YEAR ZNSERVICE TESTING PROGRAM REVISION: 1 TABLE OP CONTENTS 8.1.2 PUMP RECORDS IWP-6220.......... ..............160 8.1.Y'ZNSERVZCE TEST PLAN ZWP-6230.................160 8.1.4 RECORDS OF TESTS IWP-6240....................160 8.1.5 RECORDS OF CORRECTIVE ACTION IWP-6250........161 8.2 VALVE RECORDS ZWV-6000.............. ~ ~ ~ ~ ~ ~ ~ ........161 8.2 '

SUMMARY

LISTING ZWV-6210 '...................161 8.2.2 PRESERVICE TESTS IWV-6220.... ...............161 8.2.3 TEST RESULTS IWV-6230.............-.. .......161 SECTION EX 9.0 ZNSERVZCE TESTING PROGRAM.........;...... ........ ...162 9.1 PROGRAM PLAN TABLES ~ ~ ~ ~ ~ . ~ ~ ~ . ~ ... .... .........162

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9 '.1 DESCRIPTION OF TABLES ~ ~ ~ ~ ~ . ~ ~ ~ ~ .. ... ...162

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9.1.2 SECTIONS........... .. ... ............ ....162 9 ' PUMP & VALVE PROGRAM TABLES ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ . ~ ~ ~ ~ .162 9.2.1 PUMP TEST TABLES............................162 9.2.2 VALVE TEST TABLES.................. ........164 TABLES F 1 INSERVICE TEST QUANTITIES IWP-3100-1.....................27 2.2 ALLOWABLE RANGES OF TEST QUANTITIES IWP-3100-2...........28 2.3 ACCEPTABLE INSTRUMENT ACCURACY IWP-4110-1................31 3.5 CATEGORY C SAFETY & RELIEF VALVE TESTING SCHEDULE........'42 3 ~ 5~2 MEASMMNT OF FULL STROKE TIME. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~.... ~ ~ ~ ~ ~ ~ 37 3.6.1 VALVE LEAK RATE TESTS'. ~ .'. ~ ~ -- ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ - ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 39 3.7.2 TEST PARAMETERS (SAFETY & RELIEF VAJVES)................'.43

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3.10 INSERVZCE TEST REQUIREMENTS..............................47 12

TUMMY POINT UNIT NO. 3/4 DATE '2-12-88 SECOND TEN-YEAR 'INSERVICE TESTING PROGRAM REVISION: 1 TABLE OP CONTENTS 4.1 PUMP RELIEF REQUEST STATUS TABLE......... ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 49 4.2 VALVE RELTRF REQUEST STATUS TABLE......... ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 62

5. 1-1 CONTAINMENT ISOLATION VALVES........................... 152 5.1-2 CONTAINMENT ISOLATION VALVES. ~ ~ .. ~ .............'....-...153 5.1-3 CONTAINMENT ISOLATION VALVES............................154 6.1 REACTOR COOLANT PRESSURE ISOLATION VALVES...............156 7.1 PIPING & INSTRUMENTATION DRAWING LIST...................158 9.1 PUMP PROGRAM TABLE. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 163 9.2 VALVE PROGRAM TABLE ~ ~ ~ ~ ~ ~ ~ ~ ~ . ~ ~ ~.... ~................. 166 13

TURKEY POINT UNIT NO. 3/4 DATE:12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 RECORD OF REVISION REV.~ CHANGE DESCRIPTION OF REVISION DATE APPROVALS NO.~ NUMBER REASON FOR THE CHANGE REVISED ORIGINAL ISSUE OF PTN3/4 IST 06-01-85 PUMP & VALVE PROGRAM TURKEY POINT PLANT g UNIT 3/4 g 12-12-88 PUMP AND VALVE TESTING PROGRAM MODIFIED RELIEF REQUEST NO. 11 08-17-89 PAGE 60.

MODIFIED RELIEF REQUEST NO. 5 08-17-8 PAGE 132 14

TURKEY POINT UNIT NO. 3/4 DATE: 12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 ABSTRACT This docuqgnt describes the bases and plans for the second TEN-YEAR INSERVICE TESTING PUMP & VALVE PROGRAM for Turkey Point Plant Unit No. 3/4. This program addresses the requirements of the ASME Boiler and Pressure Vessel Code,Section XI, 1980 Edition through the Winter 1981 Addenda, and subject to the limitations and modifications as stated in 10 CFR 50.55a (b) (2) (i).

Additional requirements for Augmented Testing are also addressed. This program contains Tables identifying all..

items subject to Inservice Testing for the second P

inservice inspection interval.

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TUMEY POINT UNIT NO ~ 3/4 DATE: 12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 ABBREVIATIONS LISTED BELOW ARE THE ABBREVIATIONS UTILIZED IN THIS DOCUMENT:

A/0 AIR OPERATOR ASME AMERICAN SOCIETY OF MECHANICAL ENGINEERS B&PV BOILER AND PRESSURE VESSEL CODE BUTFY BUTTERFLY CFR CODE OF FEDERAL REGULATIONS CS CONTAINMENT SPRAY DIAPH DIAPHRAGM FO FAIL OPEN FC FAIL CLOSE FAI FAIL AS IS FP&L FLORIDA POWER AND LIGHT COMPANY FINAL SAFETY ANALYSIS REPORT HHSZ HIGH HEAD SAFETY INJECTION ISI INSERVICE INSPECTION IST INSERVICE TESTING JNS JUNO NUCLEAR ENERGY SERVICES LOCKED CLOSED LOCKED OPEN LPSI LOW PRESSURE SAFETY INJECTION MCI MATERIALS, CODES AND INSPECTIONS MAIN FEEDWATER SYSTEM MO ELECTRIC MOTOR OPERATOR MS MAIN STEAM SYSTEM MSIV MAIN STEAM ISOLATION VALVE 16

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TURKEY POINT UNIT NO. 3/4 DATE:12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 ABBREVZATZONB NC NORMALLY CLOSED N/A NOT APPLICABLE NDE NONDESTRUCTIVE EXAMINATION NRC NUCLEAR REGULATORY COMMISSION NO NORMALLY OPEN

, P&ID PIPING AND INSTRUMENTATION DIAGRAM PS PLANT SUPPORT PSZ PRESERVICE INSPECTION PTN-3/4 TUEGCEY POINT PLANT UNIT NO. 3/4 RC REACTOR COOLANT SYSTEM RCPB REACTOR COOLANT PRESSURE BOUNDARY RCS MAIN REACTOR COOLANT SYSTEM SAFE SAFETY VALVE/RELIEF VALVE SIS SAFETY INJECTION SYSTEM S/CHK STOP CHECK SO SOLENOID OPERATOR S/A, SA SELF ACTUATED OR SELF VISUAL TESTING (EXAMINATION) 17

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TUREKY POINT UNIT NO. 3/4 DATE: 12-12-88 SECOND TEN-YEAR ZNSERVICE TESTING PROGRAM REVISION: 1 DBPZNZTZONS ACTIVE VALVES - valves which are required to change position to accomplish a specific function COLD SHUTDOWN is when the Reactor Coolant system reaches Mode (5) five and the Reactor Coolant system temperature is less than 200 degrees F.

EXERCISING - the demonstration based on direct or indirect visual or other positive indication that the moving parts of a valve function satisfactorily.

EO EXERCISE VALVE OPEN EC EXERCISE VALVE CLOSED SLT SEAT LEAKAGE TESTING FS FAIL-SAFE DEMONSTRATION (IWV-3415)

V VALVE POSITION INDICATOR VERIFICATION IWV-3300 INSP DISASSEMBLE . AND INSPECT VALVE INTERNALS FOR FREEDOM OF MOVEMENT TF SAFETY AND RELIEF VALVE TESTS (SEE APPLICABLE SETPOZNTS PAGE 42 OF PROGRAM)

FULL STROKE Zs the valve stem or disk movement to the position required (to open or to close) to function.

fulfill its INSERVICE LIFE the period of time from installation and acceptance until retired from service INSERVICE TEST a special test to obtain information through measurement or observation to determine the operational readiness of a pump or valve.

These tests are not designed to establish complete pump performance.

MAINTENANCE - routine valve servicing or work on a valve undertaken to correct or prevent an abnormal or unsatisfactory condition.

NORMAL PLANT the conditions of startup, hot shutdown, OPERATION operation within the normal power range, or cooldown and shutdown of the power plant.

OPERATIONAL - the capability of a pump or valve to fulfill READINESS its function PASSIVE VALVE - valves which are not required to change position to accomplish a specific function 18

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TURKEY POINT UNIT NO. 3/4 DATE: 12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 DEFINITIONS REFERENCE VALUQS are defined as one or more fixed sets of values of the quantities as shown in Figure No. 2.1 as measured or observed when the equipment is known to be operating acceptably.

ROUTINE SERVICING - the performance of planned, preventive maintenance which does not require disassembly of the pump or replacement of the pump parts, such as changing flushing the cooling system, adjusting oil, packing, adding packing rings, or mechanical seal maintenance.

SYSTEM RESISTANCE - the hydraulic resistance to flow in a system TEST FREQUENCY - The frequency of test associated with each pump or valve.

1 ~ REFUELING SHUTDOWN

2. COLD SHUTDOWN

3. OPERATION EVERY 3 MONTHS

4. COLD SHUTDOWN WHEN THE REACTOR COOLANT SYSTEM IS DEPRESSURIZED AND VENTED 5 ~ AT LEAST ONCE EVERY TWO YEARS

6. PRIOR TO RETURN TO SERVICE (IWV-3416) 7 ~ ONCE EVERY 10 YEARS

8. IN ACCORDANCE WITH TABLE IWV-3510-1 VALVE CATEGORIES see valve .text for definitions of category A, B, C and D valves 19

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TURKEY POINT UNIT NO. 3/4 DATE:12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM'EVISION: 1

1.0 INTRODUCTION

1.1 PROGRAM APPLICABILITY This document details the Florida Power & Light Inservice Testing Program for the SECOND Ten Year Inservice Inspection Interval for Turkey Point Nuclear Power Plant, Unit No. 3/4.

1.1.1 TURKEY POINT UNIT NO. 3 1.1.1.1 OPERATING LICENSE The operating License for Turkey Point Unit no. 3 was issued on July 19, 1972, and Florida Power and Light Company is the owner of record.

1 '.1 ' AMENDMENT Amendment no. 119 to Operating. License no. DPR-31 was submitted on April 2, 1984 and supplemented:

on April 18, 1984, October 11, 1985, and February 21, 1986, in accordance 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.

1' ' ' NRC APPROVAL This amendment was approved by letter dated October 27, 1986 to change Technical Specifications to reflect revised Inservice Inspection (ISI) programs.

1 ~ 1 ~ 2 TUEGG~Y POINT UNIT NOe 4

1. 1 ~ 2 ~ 1 OPERATING LICENSE The operating License for Turkey Point Unit No. 4 was issued on April 10, 1973, and Florida Power and Light Company is the owner of record.

1.1.2.2 AMENDMENT Amendment no. 113 to Operating License no. DPR-41 was 'ubmitted on April 2, 1984 and supplemented on April 18, 1984, October 11, 1985, and February 21, 1986, in accordance 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.

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TURKEY POINT UNIT NO. 3/4 DATE:12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 1.1.2.3 NRC APPROVAL This amendment was approved by letter dated October 27, +86 to change Technical Specifications to reflect revised Znservice Inspection (ZSZ) programs.

1.2 INSPECTION INTERVALS 1.2.1 FIRST INSERVICE INSPECTION INTERVAL 1' ' ' TURKEY POINT UNIT 3 The First Inservice Inspection Interval became effective on December 14, 1972 and was scheduled to end on December 13, 1982.

1.2 ' ' TURKEY POINT UNIT 4 The First Inservice Inspection Interval became effective on September 7, 1973 and was scheduled to end on September 6, 1983.

1' ' FIRST INSPECTION INTERVAL EXTENSION 1 '.2 ' TURKEY POINT UNIT 3 The First Inservice Inspection Interval was extended from 'ecember 14, 1982 to February 22, 1984 due to the Turkey Point Unit No. 3 Steam Generator Repair and Replacement Activity.

Request for extension was submitted to the Nuclear Regulatory Commission on October 3, 1983, and was approved on March 1, 1984.

1.2 '.2 TURKEY POINT UNIT 4 The First Inservice Inspection Interval was extended from September 7, 1983 to April 15, 1984 due to the Turkey Point Unit No. 4 Steam Generator Repair and Replacement Activity.

Request for extension was submitted to the Nuclear Regulatory Commission on October 3, 1983, and was approved on March 1, 1984.

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TURKEY POINT UNIT NO. 3/4 DATE: 12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 1.2.3 SECOND INSERVICE INSPECTION INTERVAL 1.2.3.1 TURKEY POINT UNIT NO. 3 The Second Znservice Inspection Interval became effective on February 22, 1984 and ends on February 21, 1994.

1.2.3.2 TURKEY POINT UNIT NO. 4 The Second Znservice Inspection Interval became effective on April 15, 1984, and ends on April 14, 1994.

1 ' APPLICABLE DOCUMENTS The Inservice Testing Program for Class 1, 2 and 3 Pumps and Valves .was developed after giving due consideration to the following documents:

10 CFR 50.55a CODE OF FEDERAL REGULATIONS ASME BOILER AND PRESSURE VESSEL CODE g SECTION XIg 1980 EDITION THROUGH THE WINTER 1981 ADDENDA, "RULES FOR ZNSERVICE INSPECTION OF NUCLEAR POWER PLANT COMPONENTS~'.

ST NUCLEAR REGULATORY GUIDE 1.26 QUALITY GROUP CLASSIFICATIONS AND STANDARDS FOR WATER-, STEAM, AND RADIOACTIVE -WASTE - CONTAINING COMPONENTS OF NUCLEAR POWER PLANTS'.68 PREOPERATIONAL TEST PROGRAM Turkey Point Unit. 3/4 FINAL SAFETY ANALYSIS REPORT

- TKQXY POINT PLANT UNIT NO. 3 TECHNICAL SPECIFICATIONS, DOCKET NO. 50-250

- TlHGG"Y POINT PLANT UNIT NO. 4 TECHNICAL SPECIFICATIONS, DOCKET NO. 50-251 1.4 APPLICABLE EDITIONS AND ADDENDA TO SECTION XI 1.4.1 FIRST INSERVICE INSPECTION INTERVAL The First Ten - Year'nservice Inspection Interval was conducted in accordance with the 1970 Edition through the Winter 1970 Addenda, and then updated to the 1974 Edition through the Summer 1975 Addenda of Section XI of the ASME Boiler and Pressure Vessel Code.

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TURKEY POINT UNIT NO. 3/4 DATE '2-12-88 SECOND TEN-YEAR ZNSERVZCE TESTING PROGRAM REVISION: 1 1.4.2 SECOND INSERVZCE INSPECTION INTERVAL As required by Title 10 of the Code of Federal Regu+tions paragraph 55 a Inservice Inspections requirements applicable(g) to(4) inservice testing of Pumps and Valves at Turkey Point Unit 3/4 are based on the rules set forth in the 1980 Edition of Section XZ through the Winter 1981 Addenda, hereafter referred to as the Code.

(SEE NOTE AT BOTTOM OF PAGE) 1.5 SUBSEQUENT CODE EDITIONS AND ADDENDA As permitted by 10 CFR 50.55a (g) (4) (iv) Florida Power and Light (FPL) may elect to meet the requirements set forth in subsequent Editions and Addenda that are incorporated by reference into 10 CFR 50.55a (b) (2) subject to the Nuclear Regulatory Commission (NRC) approval.

Portions of Editions and Addenda may also be used provided that all related requirements of the respective:

Editions and Addenda are met. FPSL intends to continually evaluate and apply, as appropriate, changes in adopted Code Editions and Addenda which assure the Quality and Safety of the Turkey Point Nuclear Power Plant.

1.6 SYSTEM CLASSIFICATIONS The system classification used as the basis for the Znservice Test, Program are based on the requirements of 10 CFR 50 and Regulatory Guide 1.26.

1.6.1 Class 1 system boundaries are developed based on 10 CFR 50.2 (v) of the Code of Federal Regulations.

1.6.2 Class 2 and 3 system boundaries are developed based on Regulatory Guide 1.26 and the PTN-3/4 Final Safety Analysis Report.

NOTE FPL submitted proposed Inservice Inspection and Testing Programs and requests for relief on October 27, 1982, March 7, 1983, June 30, 1983, March 30, 1984, April 2 and 18, 1984, July 26, 1984, September 14, 1984, October 24 and 25, 1984 and November 20, 1984.

On February 4, 1985 The NRC sent a interm approval for implementation of submitted programs. After this FPL submitted additional correspondence on May 20 and 31, 1985, December 26, 1985, August 20, 1986, March 2, e 1987, June 5, 1987 and November 10, 1987.

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TUESDAY POINT UNIT NO ~ 3/4 DATE-12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION:

Reference TAC Nos. 49133, 49936, 54677, 54678, 54973 and 54974.

2.0 DEVELOPMENT OF THE INSERVICE PUMP TEST PROGRAM Following is the detailed description of the Testing Program outline for all pumps to be tested:

2.1 PUMP PROGRAM IWP-1100 The Pump test program shall be conducted in accordance with article IWP of the ASME Code, except where specific Relief i;s requested in accordance with 10 CFR 50.55a (g) (5) (iii).

Class 1, 2 and 3 centrifugal and positive displacement type pumps requiring inservice testing at Turkey Point are classified as those pumps required to perform a specific function in shutting down a reactor or in mitigating the consequences of an accident, and that are provided with an emergency power source.

r The results of these tests are to be used in assessing:

operational readiness of the pumps during their service life.

NOTE: On October 24, 1984 FPL submitted document number L-84-238 which added additional components to the Pump and Valve Test Program. These components where added based on negotiations between FPL and the NRC.

2.1.1 PUMPS EXEMPT FROM TESTING IWP-1200 (a) Drivers are excluded from the requirements of IWP,

'xcept where the pump and driver form an integral unit and the pump bearings are in the driver.

(b) Class 1, 2, and 3 pumps that are supplied with emergency power solely for operating convenience are excluded.

2.1 ~ 2 IWP-1400 BYPASS LOOPS

%here a pump cannot practically be tested in its regular circuit, a bypass loop may be used.

2.1.3 INSERVICE TEST IWP-3100 An Inservice test shall be conducted with the pump operating at nominal motor nameplate speed for constant speed drives and at a speed adjusted to the reference speed for variable speed drives. The resistance of the system shall be varied until either the measured 24

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TtGOCEY POINT UNIT NO. 3/4 DATE:12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 differential pressure or the measured flow rate equals the corresponding reference value. The test quantities shown in Table No. 2.1 shall then be measured or obse~ed and recorded. Each measured test quantity shall then be compared with the reference value of the same quantity.

Any deviations determined shall be compared with the limits given in Table No. 2.2 and the specified corrective action taken.

2.1.4 REFERENCE VALUES IWP-3110 Reference values are defined as one or more fixed sets of values of the quantities shown in Table 2.1 as measured or observed when the equipment is known to be operating acceptably. All subsequent test results shall be compared to the reference values or with new reference values established in accordance with 2.1.5 or 2.1.8. Reference values shall be determined from the results of an inservice test which may be run during preoperational testing, or from the results of the:

first inservice test run during power operation.

Reference values shall be at points of "operation readily duplicated during subsequent inservice testing; 2.1.5 EFFECT of PUMP REPLACEMENT, REPAIR, AND ROUTINE SERVICING ON REFERENCE VALUES IWP-3111 2.1 ~ 5 ~ 1 REPLACED PUMPS After a pump has been replaced, a new set or sets of reference values shall be determined from the results of the first inservice test run after the pump is put into service.

2.1 ' ' REPAIRED PUMPS When a reference value or set of values may have been affected by repair, a new reference value or set of values shall be determined or the previous value reconfirmed b'y an inservice test run prior to, or within'6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months after, return of the pump to normal service.

2.1.6 ROUTINE SERVICING OF PUMPS When a reference value or set of values may have been affected by routine servicing of the pump, a new reference value or set of values shall be determined or the previous value reconf irmed by an inservice test run prior to, 25

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TURKEY POINT UNIT NO. 3/4 DATE:12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 or within 96 hours after, return of the pump to

'normal service.

2.1.7 DEVIATIONS Deviations between the previous and new set of reference values shall be identified, and verification that the new values represent acceptable pump operation shall be placed in the record of tests.

2.1 ' ESTABLISHING ADDITIONAL SET OF REFERENCE VALUES IWP-3112 When necessary or when desirable for reasons other than those stated in 2.1.5 to establish an additional set of reference values, an inservice test shall first be run at the conditions of an existing set of reference values and the results analyzed. If satisfactory, a second test run at the new referenceis operation conditions shall follow as sopn as practical. The results of the test shall establish the additional set..

of reference values.

Whenever an additional set of reference values is established, the reason for so doing shall be justified and documented in the record of tests.

2.2 ANALYSIS OF RESULTS IWP-3200 2.2.1 ALLOWABLE RANGES OF INSERVICE TEST QUANTITIES IWP-3210 The allowable ranges of inservice test quantities in relation to the reference values are tabulated in Table.

No. 2.2. If these ranges can not be met, FPL shall specify in the record of tests the reduced range limits to allow the pump to fulfillits function, and those limits shall be used in 'ieu of the ranges given in Table No. 2.2.

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TRBLE NO ~ 2 ~ 1 INSERVICE TEST QURNTITIES REFERENCE IWP-3i88-i QURNTITY NERSURE OBSERVE SPEED N (IF VARIABLE SPEED)

INLET PRESSURE P,

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I DIFFERENTIAL PRESSURE P FLOW RATE Q VIBRATION %AMPLITUDE V PROPER LUBRICANT LEVEL OR PRESSURE ~ ~ ~ 8 BEARING TEMPERATURE T~

1 I1ERSURE BEFORE PUNP STRRTUP RND DURING TEST.

PAGE 27

w>i s TRBLE NO. 2.2 ALLOlIABLE RANGES OF TEST 4UANTITIES IWP-SISB-2 8 8 ALERT RANGE REQUIRED RCTIOH RRHGE TEST QURHITY ACCEPTABLE RANGE LOll VALUES HIGH VALUES LOW VALUES HIGH VALUES pI CHOTE (1>>

hP 8 88 TO 1 ~ 88 DP 8 88 TO 8.88 hP 1 ~ BB TO t 88$ p

~ <B. 88$ p >1 88$ p 8 ~ 8% TO 1 ~ BBQ 8 ~ SB TO 8 894

~ 1 ~ BR TO 1 ~ 884<8.98 4 >1 8840 V, lIHEH 8< V < 8 ' I1IL 8 TO 1 I1IL HONE 1TO15I1IL NONE >1 ~ 5 I1IL V lIHEN 8.5 I1IL <V< 8 8 l1IL 8 TO RV~I1IL HONE RVI1IL TO NONE >8VI1IL SV I1 I L V,IIHEH P. 8 I1IL < V<5 8 l1IL 8 TO (8+V > I11L HOHE (8+V > I1IL TO HONE >C'>+V >liIL C'(+V"> I1IL VilIHEH V> 5 8 t1IL 8 TO 1.'IVI1IL NONE 1 'IVI1IL TO HONE >1 ~ BV PlIL 1 BVI1IL Tl (NOTE CB>

NOTES (1> PISHALL BE lIITHIH THE LII1ITS SPECIFIED BY THE OlIHER IH RECORD OF TESTS C IMP-8888>

CB> T~SHALL Bf IIITHIH THE LII1ITS SPECIFIED BY THE OlINER IH RECORD OF TESTS C IIIP-8888>

C8> SEE IWP-8888 PACE 28

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TURKEY POINT UNIT NO. 3/4 DATE:12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAN REVISION: 1 2.2.2 ANALYSIS OF TESTS IWP-3220 All test data shall be analyzed within 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months after completion of a test.

2.3 CORRECTIVE ACTION IWP-3230 2.3 ' ALERT RANGE If deviations fall within the ALERT RANGE of Table No.

2.2, the frequency of testing specified in paragraph 2.5 shall be doubled until the cause of the deviation is determined and the conditions corrected inaccordance with 2 '.3 ~

2 ' ' REQUIRED ACTION RANGE If deviations fall within Table No. 2.2, the the REQUIRED ACTION RANGE of pump shall be declared inoperative and not returned to service .until the cause of the deviation has been determined and the conditions:

corrected in accordance with 2.3.3.

2.3.3 CORRECTIVE ACTION Correction shall be either replacement or repair per paragraph 2.1.5, or shall be an analysis to demonstrate that the condition does not impair pump operability and that the pump will still fulfillits function.A new set of reference values shall be established after such analysis.

When a test shows deviations greater than allowed by Table No. 2.2, the instruments involved may be calibrated and the test rerun.

2.4 SCOPE OF TESTS IWP-3300 Each inservice test shall include the measurement and observation of all quantities in Table No. 2.1., except bearing temperature, which shall be measured during at least one inservice test. each year.

2.5 FREQUENCY OF TEST IWP-3400 An inservice test shall be run on each pump nominally every three (3) months during normal plant operation. Although not mandatory FPL will maintain the test frequency during shutdown periods, provided these tests can be reasonably be accomplished.

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TURKEY POINT UNIT NO. 3/4 DATE: 12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 these tests can not be accomplished during plant shutdowns, The pump will be tested within one (1) week after the plant is returned to normal operation.

Pumps that're operated more frequently than every three (3) months need not be run or stopped for a special test, provided the plant log shows each such pump was operated at least every three (3) months at the reference conditions and the quantities specified were measured, observed, recorded and analyzed.

2.6 DURATION OF TEST IWP-3500 When measurement of bearing temperature is not required, each pump shall be run at least five (5) minutes under conditions as stable as the system permits. At the end of this time at least one measurement or observation of each of the quantities specified shall be made and recorded.

When measurement of bearing temperature is required, each pump shall be run until the bearing temperatures stabilize, and then the quantities specified shall be measured and recorded. or-'bserved A bearing temperature shall be considered stable when three successive readings taken at. ten (10) minutes intervals do not vary more than 34.

2.7 DIFFERENTIAL PRESSURE IWP-4240 The differential pressure across a pump shall be determined by use either of a differential pressure gage or a differential pressure transmitter that provides direct measurement of pressure difference, or by taking the difference between the pressure at a point in the inlet pipe and the pressure at a point in the discharge pipe.

2.8 FLOW MEASUREMENTS IWP-4 600 Flow rate shall be measured using a rate or quantity meter installed in the pump test circuit. The meter may be in any class that, provides an overall readout repeatability within the accuracy limits of Table 2.3. Where the miter does not, indicate the flow rate directly, the record shall include the method used to reduce the data.

30

, ~3 TRBLE NO. 2.3 RCCEPTRBLE INSTRUI1ENT RCCURRCY REFERENCE IWP-'t118-1 PRESSURE 2'l OF FULL SCRLE DIEFERENTIRL PRESSURE 2'l OE FULL SCRLE ELOW RATE 2/ OF FULL SCRLE SPEED 2/ OF FULL SCRLE TENPERRTURE 5/ OE FULL SCRLE V I BRAT ION RI1PL I TUDE 5/ OF FULL SCRLE PAGE 31

TURKEY POINT UNIT NO. 3/4 DATE:12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 2 ' TEMPERA'HQE MEASUREMENT (BEARINGS IWP-4310)

The temperature of all centrifugal pump bearings outside the main flow path and of the main shaft bearings of reciprocating pumps shall be measured at points selected to be responsive to changes in the temperature of the bearing. Lubricant temperature,,when measured after passing through the bearing, and prior to entering a cooler, shall be considered the bearing temperature.

2.10 VIBRATION (VIBRATION AMPLITUDE IWP-4510)

At least one displacement vibration amplitude (peak-to-peak composite) shall be read during each inservice test.

The direction of displacement shall be measured in a plane approximately perpendicular to the rotating shaft, and in the horizontal or vertical direction that has the largest deflection for the particular pump installation. The location shall generally be on a bearing housing or its:

structural support, provided it is not seperated from the pump by any resilient mounting. On a pump coupled to the driver, the measurement shall be taken on the bearing housing near the coupling; on close-coupled pumps, the measurement point shall be as close as possible to the inboard bearing. On reciprocating pumps, the location shall be on the bearing housing of the main pump drive shaft, approximately perpendicular to both the shaft and the line of plunger travel.

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TURKEY POINT UNIT NO. 3/4 DATE: 12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 3.0 DEVELOPMENT OF THE INSERVICE VALVE TEST PROGRAM Following is the detailed description of the Testing program outline for all valves to be tested:

3.1 VALVE PROGRAM IWV-1100 The Valve test program shall be conducted in accordance with article IWV of the ASME Code, except where specific Relief is requested in accordance with 10 CFR 50.55a (g) (5) (iii) ~

Class 1, 2 and 3 valves (and their actuating and position indicating systems) requiring inservice testing at Turkey Point are classified as those valves required to perform a specific function in shutting down a reactor to the cold shutdown condition or in mitigating the consequences of an accident.

3.1.1 VALVES EXEMPT FROM TESTING IWV-1200 (a) Valves used only for operating convenience (such as manual vent, drain, instrument, and test valves), valves used for system control ( such as pressure regulating valves ), and valves used only for maintenance; (b) external control and protection system responsible for sensing plant conditions and providing signals for valve operation.

(c) non-nuclear safety valves 3 ' VALVE CATEGORIES IWV-2200 Each valve subject to testing has been placed in one or more of the following categories. When more than one distinguishing category characteristic is applicable, all requirements of each of the individual categories are applicable, although duplication or repetitions of common testing requirements is not necessary.

3 ~ 2 ~ 1 CATEGORY A Valves for which seat leakage is limited to a specific maximum amount in the closed position for fulfillment of their function.

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TUESDAY POINT UNIT NO. 3/4 DATE:12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 3.2.2 CATEGORY B Valves for which seat leakage in the closed position is inconsequential for fulfillment of their function.

3.2.3 CATEGORY C Valves which are self-actuating in response to some system characteristic, such as pressure (relief valves) or flow direction (check valves) 3.2.4 CATEGORY D Valves which are actuated by an energy source capable of only one operation, such as rupture disks or explosively actuated valves.

3. 3 VALVE REPLACEMENT, REPAIR AND MAINTENANCE IWV-3200 When a valve or its control system has been replaced or repaired or has undergone maintenance (See note) that. could:

affect its performance, and prior to the time returned to service, it shall be tested to demonstrate it is that the performance parameters which could be affected.

by the replacement, repair, or maintenance are within acceptable limits.

NOTE: Ad]ustment of steam packing, removal of the bonnet, stem assembly, or actuator, and disconnection of hydraulic or electrical lines are examples of maintenance that could affect valve performance parameters.

3.4 VALVE POSITION INDICATOR VERIFICATION IWV-3300 Valves with remote position indicators shall be observed at least once every two ( 2 ) years to verify that valve operation is accurately indicated.

3.5 INSERVICE TESTS CATEGORY A AND B VALVES IWV-3400 3 '.1 TEST FREQUENCY IWV-3411 Category A and B valves shall be exercised at least once every three (3) months, except as provided in paragraphs 3.5.2.1, 3.5.5, and 3.5.6.

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TURKEY POINT UNIT NO. 3/4 DATE:12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 3.5.2 EXERCISING PROCEDURES INV-3412 3 ' ' ' 'TROKING Valves shall be exercised to the position required to fulfill their function unless such operation is not practical during plant operation. If only limited operation is practical during plant operation, the valve shall be part stroke exercised during plant operation and full stroke exercised during cold shutdowns.

Valves that cannot be exercised during plant operation shall be specifically identified and shall be full-stroke exercised during cold shutdowns. Full-stroke exercising during cold shutdowns for all valves not full-stroke exercised during plant operation shall be on a frequency determined by the intervals between..

shutdowns as follows:

a. for intervals of three (3 ) months or longer, exercising during each shutdown:

b. for intervals of less than three (3) months, full-stroke exercise is not required unless three ( 3 ) months have passed since last shutdown exercise.

3~5~2~2 ~ VALVE DISK MOVEMENT The necessary valve disk movement shall be determined by exercising the valve while observing an appropriate indicator which signals the required change of disk positions, or by observing indirect evidence, such as changes in system pressure, flow rate, level, or temperature, which reflect stem or disk position.

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TURKEY POINT UNIT NO. 3/4 DATE: 12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 3.5.3 POWER OPERATED VALVES IWV-3413 3.5.F 1 FULL STROKE The limiting value of full-stroke time of each power operated valve shall be specified. Full-stroke time is that time interval from initiation of the actual signal to the end of the actuating cycle.

3.5.3.2 STROKE TIME The stroke time of all power operated valves shall be measured to the nearest second, for stroke times 10 sec or less, or 104 of the specified limiting stroke time for full-stroke times longer than 10 sec whenever such a valve is full-stroke tested.

3 '.4 VALVES IN REGULAR USE IWV-3414 Valves which operate in the course of plant operations at a frequency which would satisfy the need not be additionally exercised, exercising'equirements, provided that the observations otherwise required for testing are made and analyzed during such operation and are recorded in the plant record at intervals no greater than those identified in paragraph 3.5.1.

3.5.5 FAIL-SAFE VALVES IWV-3415 When practical, valves with fail-safe actuators shall be tested by observing the operation of the valve upon loss of actuator power. If these valves cannot be tested once every three (3) months, they shall be tested during each cold shutdown: in case of frequent shutdowns, these valves need not be tested more often than once every three (3) months.

3.5.6 VALVES IN SYSTEMS OUT OF SERVICE IWV-3416 For a valve in a system declared inoperable or not required to be operable, the exercising test schedule need not be followed. Within thirty (30) days prior. to return of the system to operable status, the valves-shall be exercised and the schedule resumed.

36

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TUREKY POINT UNIT NO. 3/4 DATE: 12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 Denoted below are the Exercise Codes for those valves identified within the program tables:

TABLE NO. 3 ' 2 MEASUREMENT OF FULL STROKE TIME EXERCISE DEFINITION OF CODE CODE EO Exercise valve, Full Stroke in the open direction.

EC Exercise valve, Full Stroke in the closing direction 37

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TKUZY POINT UNIT NO. 3/4 DATE:12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 3,5 ' CORRECTIVE ACTION IWV-3417 3.5.7 ' POWER OPERATED VALVES If, for power operated valves, an stroke time of 254 or more from increase the previous in test for valves with full-stroke times greater than 10 sec or 504 or more for valves with full-stroke times less than or equal to 10 sec is observed, test frequency shall be increased to once each month until corrective action is taken, at which time the original test frequency shall be resumed.

3.5.7.2 VALVE FAILURES If a of valve valve stem fails to exhibit the required change or disk position or exceeds its specified limiting value of full-stroke time by this testing, then corrective action shall be initiated immediately.. If the condition is not, or cannot be, corrected within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ,:

the valve shall be declared inoperative. When corrective action is required as a result of tests made during cold shutdowns, the condition.

shall be corrected before startup. A retest showing acceptable operation shall be run following any required corrective action before the valve is returned to service.

3.6 VALVE LEAK RATE TEST IWV-3420 3.6.1 VALVE LEAK RATE TEST IWV-3421 Category A valves shall be leak tested except that valves which function in the course of plant operation in a manner that demonstrates functionally adequate seat tightness need not be leak tested. In such cases, the valve record shall provide the basis for the conclusion that operational observations constitute satisfactory demonstration.

3.6.2 FREQUENCY IWV-3422

'I Tests shall be conducted at least once every two (2) years.

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TURKEY POINT UNIT NO. 3/4 DATE -'2-12-88 SECOND TEN-YEAR ZNSERVICE TESTING PROGRAM REVISION: 1 Denoted below are the definition of the valve leak rate test for those valves identified within the program tables:

TABLE NO. 3 ~ 6-1 VALVE LEAK RATE TESTS LEAK RATE DEFINITION OF CODE CODE SLT Seat leakage test valve during refueling but at least once every 2 years (Code).

3.6.3 DIFFERENTIAL TEST PRESSURE ZWV-3423 Valve seat leakage tests shall be made with the pressure differential in the same direction as when the valve is performing its function, with the following exceptions.

3 '.3.1 GLOBE VALVES Globe type valves may be tested with pressure under the seat.

3.6.3.2 BUTTERFLY VALVES Butterfly valves may be tested in either direction, provided their seat construction is designed for sealing against pressure on either side.

3 ' ' ' GATE VALVES Gate valves with two-piece disks may be tested by pressurizing them between the seats.

3.6.3.4 TEST DIRECTION Valves (except check valves) may be tested in either direction pressure is 15 psi if the function differential (100 kPa) or less.

3 ' ' ' PRESSURE DIFFERENTIAL Leakage tests involving pressure differentials lower than function pressure differentials are permitted in those types of valves in which service pressure will tend to diminish the overall leakage channel opening, as by pressing the disk into or onto. the seat with greater 39

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TKOCEY POINT UNIT NO. 3/4 DATE:12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 force. Gate valves, check valves, and globe type valves having function pressure differential applied over the seat, are examples of valve applications satisfying this requirement. When leakage tests are made in such cases using pressures lower than function maximum pressure differential, the observed leakage shall be adjusted to function maximum pressure differential value. This adjustment shall be made by calculation appropriate to the test media and the ratio between test and function pressure differential, assuming leakage to be directly proportional to the pressure differential to the one-half power.

3.6.3.6 REDUCED PRESSURE TESTING Valves not qualifying for reduced pressure testing as defined in 3.6.3.5 above shall be leak tested at full maximum function pressure differential, with adjust'ment by calculation if needed to compensate for a difference between:

service and test media.

3 ' ' SEAT LEAKAGE MEASUREMENT IWV-3424 seat leakage may be determined

'alve by one of the following:

A. draining the line, closing th'e valve, bringing one side to test pressure, and measuring leakage through a downstream telltale connection, or B. by measuring the feed rate required to maintain pressure between two valves or between two seats of a gate valve, provided the total apparent leak rate is charged to the valve or gate valve seat being tested, and that. the conditions required by 3.6.3 are satisfied.

3 ' ' ANALYSIS OF LEAKAGE RATES IWV-3426 Leakage rate measurements shall be compared with previous measurements and with the permissible leakage rates for a specific valve. If leakage rates are not Light Company the specified by Florida Power and following rates shall be permissible:

For Check valves see note number 2.

40

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TURKEY POINT UNIT NO. 3/4 DATE:12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 3.6.5.1 WATER for water, at function pressure differential, 30 D ml/hr; (see note 1) 3.6.5.2 AIR For air, at function pressure differential, 7.5 D standard cu ft/day. (see note 1)

NOTES: 1. D is the nominal valve size, inches

2. for .check valves, use double the listed values 3.6.6 CORRECTIVE ACTION IWV-3427 A. Valves with leakage rates exceeding the values specified by FPL, or the rates given in 3.6.5, where values have not been specified by FPL, shall be replaced or repaired.

B. For valves 6 inch nominal pipe size and larger, if a leakage rate exceeds the rate determined by the previous test by an amount that reduces the margin between measured leakage rate and the maximum permissible rate by 504 or greater, the test frequency shall be doubled; the test shall be rescheduled to coincide with a cold shutdown until corrective action is taken, at which time the original test frequency shall be resumed.

tests show leakage rate increasing with time, If a projection based on three or more tests 'nd indicates that the leakage rate of the next scheduled test will exceed the maximum permissible leakage rate by greater than 10%,the valve shall be replaced or repaired.

3.7 CATEGORY C VALVES IWV-3500 3.7.1 SAFETY VALVE AND RELIEF VALVE TESTS IWV-3510 3.7.1.1 TEST FREQUENCY IWV-3511 Valves shall be tested at the end of each time period as defined in Table No. 3.5.

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TABLE NO. 3.5 CRTEGORY C: SRFETY RND RELIEF VRLVES TESTING SCHEDUI E REF ERENCE I WV-3518-1 STARTUP THROUGH 1ST REFUELIHC tiIHItlUtl OF H / BI tt TOTAL VALVES IH THIS CATECORY HOTE (1)g 1ST REFUELINC THROUCH RHD REFUELIHC ~ ADDITIONAL VALVES TO tlAXK CUtlULATIVE TESTED AT LEAST H p/ BB t( TOTAL VALVES IH THIS CATEGORY NOTE (1)l RHD REFUELIHC THROUGH SRD REFUELIHCt ~ tc ~ ADDITIONAL VALVES TO IfAKE CUtlULATIVE TE8TED AT LEAST H / Bi )t TOTAL VALVKS IH THIS CATEGORY' tc ~ HOTE ( 1 )]

NOTE+

(1) H gi N AH at etc ~ i ARE THE HUtlBER OF tlONTH8 FROtl STARTUP TO FIRST REFUELIHCi SECOND REFUELIHGe THIRD REFUELIHGe etc ~ NHEH H IS A HUtlBER LARGER THAH BIe ALL VALVES NHICH HAVE HOT BEKH TESTED DURIHC THE PRKCKDIHC 5 YEAR PERIOD SHALL BE TESTED. THE FOLLONIHC PERIOD SHALL THEH BE COHSIDERED TO BE THE SANE AS STARTUP TO FIRBT REFUELIHG FOR PURPOSES OF DETKRtllHIHC TEST FREOUEHCY NITH THE ADDED RE4UIREtiEHT THAT AT EACH REFUELIHC ALL VALVES NHICH HAVE HOT BEEN TESTED DURINC THE PRKCEDIHC 5 YEAR PKRIOD 8HALL BK TE8TED. THE SUBSEQUENT PERIOD NILL BE COH8IDERED THE SAtlE AS THE FIRST REFUELIHC TO THE SECOND REFUELING i ~ tc ~ i NITH H DETERtllHED BY COUNTIHC tlONTHS FROtl THE HEN STARTIHG POINT.

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c TURKEY POINT UNIT NO. 3/4 DATE:12-12-88 SECOND TEN-YEAR ZNSERVICE TESTING PROGRAM REVISION: 1 3.7.1.2 TEST PROCEDURES IWV-3512 Safety valves and Relief valve set points shall be tested in accordance with ASME PTC 25.3-1976-Bench testing, with suitable hydraulic or pneumatic equipment, or testing in place with hydraulic or pneumatic assist equipment, is an acceptable method under PTC 25.3-1976. Valves so tested are not required to be additionally leak tested in accordance with 3.6.

Denoted below are the test parameters for Safety and Relief valves identified within the program tables:

TABLB NO 3 '-2 TEST PARAMETERS (SAFETY & RELIEF VALVES)

EXERCISE DEFINITION OF CODE.

CODE TF Safety and Relief valve tests (Set Point) to ASME Table IWV-3510-1 (Code) (see Program Table 3.5).

TF-1 SET POINT TO 1085 psig TF-2 SET POINT TO 1100 psig TF-3 SET POINT TO 1115 psig TF-4 SET POINT TO 1130 psig TF-5 SET POINT TO 2485 psig 3.7.1.3 ADDITIONAL TESTS IWV-3513 When any valve in a system fails to function properly during a regular test, additional valves in the system shall be tested as determined by arbitrary assumption that a 12 month operating period has passed to another refueling, and the additional valves shall be tested to make the cumulative total tested at least N/60 X total valves in this category, where N now includes the additional 12 months. (see Table 3.5 for definition of N.) If any of these additional valves fail to function properly on test, then all valves in the system in this category shall be tested.

43

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TURKEY POINT UNIT NO. 3/4 DATE:12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 3.7.1.4 CORRECTIVE ACTION IWV-3514 A valve failing to function properly during test shall be repaired or replaced.

3.8 TESTS FOR CHECK VALVES IWV-3520 3.8.1 TEST FREQUENCY IWV-3521 Check valves shall be ,exercised at least once every three (3) months, except as provided by 3.8.2.

3.8.2 EXERCISING PROCEDURE 1WV-3522 Check valves shall be exercised to the position required to fulfill their function unless such operation is not practical during plant operation. If only limited operation is practical, during plant.

operation, the check valve shall be part-stroke.

exercised during plant operation and full-stroke.

exercised during shutdowns. Valves that: cannot be.

exercised are identified in the attached tables, and shall be full stroke exercised during cold shutdowns.

Full stroke exercising during cold shutdowns for all valves not full-stroke exercised during plant operation shall be on a frequency determined by the intervals between shutdowns as follows:

a. for intervals of 3 months or longer, exercise during each shutdown;

b. for intervals of less than 3 months, full stroke exercise is not required unless 3 months have passed since the last shutdown exercise.

3.8.3 NORMALLY OPEN VALVES Valves that are normally open during plant operation and whose function is to prevent reversed flow shall be tested in a manner that proves that the disk travels to the seat promptly on cessation or reversal of flow.

Confirmation that the disk is on its seat shall be by visual observation, by an electrical signal initiated by a position indicating device, by observation of appropriate pressure indications in the system, or by other positive means.

44

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TUEUCEY POINT UNIT NO. 3/4 DATE:12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 3.8.4 NORMALLY CLOSED VALVES Valves that are normally closed during plant operation and whose function is to open on reversal of pressure differential shall be tested by proving that the disk moves promptly away from the seat when. the closing pressure differential is removed and flow through the valve is initiated, or when a mechanical opening force is applied to the disk. Confirmation that the disk moves away from the seat shall be by visual observation, by electrical signal initiated by position indicating device, by observation of substantially free

'flow through the valve as indicated by appropriate pressure indications in the system, or by other positive means. This test may be made with or without flow through the valve. If it is made without flow through the valve, a mechanical exerciser shall be used to move the disk. The force or torque delivered to the disk by the exerciser must be limited to less than 10%

of the equivalent force or torque. represented by the minimum emergency condition pressure differential acting on the disk, or to 2004 of the actual observed.

force or torque required to perform the exercise on the.

valve when the valve is new and in good operating.

condition, whichever is less, except that for vacuum breaker valves the exerciser force or torque delivered to the disk may be equivalent to the desired functional pressure differential force. The disk movement shall be sufficient to prove that the disk moves freely off the seat. For swing or tilting disk valves, made by use if the test is of fluid flow through the valve, the pressure differential for equivalent flow shall be no greater than That observed during the preoperational test. For other types of check valves, it be shown that disk movement is sufficient to provide shall a flow area at least 504 of the area of the seat port, or to permit flow adequate for the function of the valve.

3.8.5 CORRECTIVE ACTION IWV-3523 If a check valve fails to exhibit the required change of disk position by this testing, corrective action shall be initiated immediately. If the condition is not or can not be, corrected within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , the check valve shall be declared inoperative. When corrective action is required as a result of tests made during cold shutdown, the condition shall be corrected before startup. A retest showing acceptable performance shall be run following any required corrective action before the valve is returned to service.

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TKGCEY POINT UNIT NO. 3/4 DATE: 12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 3.9 CATEGORY D VALVES IWV-3600 3.9.1 EXPLOSIVELY ACTUATED VALVE TESTS IWV-3610 FPL has no explosively actuated valves identified within this program.

3.9 ' RUPTURE DISK TESTS IWV-3620 FPL has no rupture disk valves identified within this program.

3.10 INSERVICE TEST REQUIREMENTS IWV-3700 Active and passive valves in the categories defined in paragraph 3.2 shall be tested in accordance with the procedures contained in this program specified in Table 3.10.

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TABLE No. 3 ~ le INSERVICE TEST REQUIREI1ENTS 1 REFERENCE IWV-3788-1 VALVE LEAK ENERC lSE SPEOlAL FUNCTlON TEST TEST TEST CATEGORY ( lMV-8188 ) PROCEOURE PROCEOURE PROCEOURE ACTlVE NONE A PASSlVE 3.8 NONE NONE 8 ACTlVE NONE 3 5 NONE C-SAFETY 4 RELlEF ACTlVE NONE 3.7 1 NONE C-CHECK ACT KVE NONE 3.8 NONE D ACTlVE NONE NONE 3 8 NOTE (1) NO TESTS REQUlREO FOR CATEGORY Be Cr ANO O PASSlVE VALVES

<ei cNLNlttQH cATEcQRY I: clKcK NLvEs 8INU. 8E LGN lE$TEG llN-8%R (3.6)

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TURKEY POINT UNIT NO. 3/4 DATE: 12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 4.0 RELIEF REQUESTS 4.1 In cases where parts of the required IST Testing areas cannot be effectively tested because of a combination of component design or current testing technique limitations, Florida Power and Light Company will continue to evaluate the development of new or improved testing techniques with the intent of applying these techniques where a practical improvement in the testing can be achieved.

4.2 FORMAT Relief Requests are arranged in order by Relief Request Number, component/system and brief description of the relief subject.They are numbered sequentially. Each Relief Request contains the following information:

A. COMPONENT IDENTIFICATION describes the code class, Section XI requirements, table, category, item description and item identification.

B. TEST REQUIREMENTS - provides a description of the relief from the testing requirements of the code that can not be complied with.

C. FUNCTION - a brief description of the function (If applicable)

D. RELIEF REQUESTED a brief description of the requirements that are being requested for relief.

E. BASIS FOR RELIEF -self explanatory F. ALTERNATIVE TESTING - describes examinations or tests that FP&L proposes to use in lieu of the current requirements.

G.'IMPLEMENTATION SCHEDULE 48

TARRY POINT UNIT NO. 3/4 DATE:12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 RELIEF REQUEST STATUS TABLE TABLE NO ~ 4 '

RELIEF REQUEST DESCRIPTION NUMBER PUMP RELIEF REQUESTS:

FLOW MEASUREMENTS IWP-4600 WITHDRAWN WITHDRAWN FLOW MEASUREMENTS IWP-4600 and DURATION OF TESTS IWP-3500 DIFFERENTIAL PRESSURE IWP-4240 BEARING TEMPERATURE MEASUREMENTS IWP-4310 WITHDRAWN WITHDRAWN 9 ~

IWP-4120, INSTRUMENT RANGE 10 IWP-4120, INSTRUMENT RANGE IWP-4310, BEARING TEMPERATURE MEASUREMENT 12 IWP-3100, PUMP INLET PRESSURE MEASUREMENT NOTES'ee paragraph 1.4.2 and note at bottom of page for FPL submittal dates and NRC reference TAC numbers.

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TURKEY POINT UNIT NO. 3/4 DATE: 12-12-88 SECOND TEN-YEAR ZNSERVICE TESTING PROGRAM REVISION: 1 RELZEP REQUEST NO. 1 A. COMPONENT/SYSTEM ITEM NO. COMPONENT DESCRIPTION IDENTIFICATION

1. RESIDUAL HEAT REMOVAL PUMP A *-P2 10A

2. RESIDUAL HEAT REMOVAL PUMP B *-P210B

3. BORIC ACID TRANSFER PUMP A *-P203A

4. BORIC ACID TRANSFER PUMP .. B *-P203B

5. CONTAINMENT SPRAY PUMP A 4-P214A

6. CONTAINMENT SPRAY PUMP B 4-P214B B.SECTION XI REQUIREMENTS IWP-4 600 FLOW MEASUREMENT Co PUNCTION N/A D RELIEF REQUESTED Relief is requested from the flow rate measurement using a rate or quantity meter installed in the pump test circuit.

ZWP-4600 ED BASIS POR RELIEP These pumps use a fixed hydraulic resistance system with an orifice installed in the pump recirculation line.

IWP-1400 States where a pump cannot practically be tested in its regular circuit, a bypass loop may be used.

Instrumentation does not exist P. ALTERNATIVB TESTING Measure differential pressure (IWP-4240) across the pump during the quarterly pump test. Measured differential pressure across the pump shall then be compared to the established reference value.

This provides for an indirect measure of flow rate and verifies the operational readiness of the pump (IWP-1500) 6o IMPLEMENTATION SCHEDULE SECOND INSPECTION INTERVAL 50

I C Y POINT UNIT NO ~ 3/4 DATE:12-12-88 SECOND TEN AR INSERVICE TESTING P RAM REVISION: 1 RELZEP REQUEST NO Ao COMPONENT/SYSTEM ITEM NO. COMPONENT CRIPTION &DEN ICATION BE SECTZON XZ REQUZ CD PUNCTZON D RELIEF REQUESTED ED BASIS POR RELZEP F ~ ALTERNATZVS TESTZ 6 IMPLEMENTATION S

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Y POINT UNIT NO. 3/4 DATE:12-12-88 SECOND TEN- INSERVICE TESTING P RAM REVISION: 1 RELZEP REQUEST NO ~

AD COMPONBNT/SYSTEM ITEM NO. COMPONENT SCRIPTION IFICATION BISECTION XZ REQUIRE NTS C PUNCTZON D RELZEP REQUESTED ED BASZS POR RELZEP P ALTERNATIVE TESTZ LLI 6 ~ IMPLEMENTATION S DU 52

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TURKEY POINT UNIT NO. 3/4 DATE: 12-12-88 SECOND TEN-YEAR INSERVZCE TESTING PROGRAM REVISION: 1 RELZEP REQUEST NO. 4 A. COMPONENT/SYSTEM ITEM NO. COMPONENT DESCRIPTION IDENTIFICATION

1. DIESEL OIL TRANSFER NO. 3 3-P10

2. DIESEL OZL TRANSFER NO. 4 4-P10 BISECTION XZ REQUIREMENTS IWP-4600 FLOW MEASUREMENT IWP-3500 DURATION OF TESTS C PUNCTZON N/A D. RELZEP REQUESTED Relief is requested from the flow rate measurement using a rate or quantity meter installed in the pump test circuit.

IWP-4600 Relief is requested from the bearing temperature measurement requirements.

~

ED~ BASIS POR RELZEP The Diesel Oil Transfer Pumps have no installed recirculation flow path. The Diesel Oil Tank level control system provides for a direct flow path from the Diesel Oil Storage Tank to the Day Tank.

With automatic pump start on low level in the Diesel Oil Day Tank and automatic pump stop when the high level setpoint is reached, the typical operating time for these pumps is less than 10 minutes.

Therefore, operation of the Diesel Oil Transfer pumps for the 30 minute minimum run time required by ZWP-3500 is impractical.

P. ALTERNAVIVS TESTZNQ Flow rate will be calculated based on change in diesel oil day tank level and measured time.

The Diesel Oil Transfer Pump bearing temperature will be measured during a normal pump test, after a minimum of 5 minute run.

6 IMPLEMENTATION SCHEDULE SECOND INSPECTION INTERVAL 53

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TURKEY POINT UNIT NO. 3/4 DATE:12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 RELIEP REQUEST NO ~ 5 Ao'OMPONENT/SYSTEM ITEM NO. COMPONENT DESCRIPTION IDENTIFICATION

1. BORIC ACID TRANSFER PUMP A *-P203A

2. BORIC ACID TRANSFER PUMP B *-P203B

3. DIESEL OIL TRANSFER PUMP 3-P10

4. DIESEL OIL TRANSFER PUMP 4-P10 BISECTION XZ REQUIREMENTS IWP-4240 DIFFERENTIAL PRESSURE CD FUNCTION N/A D. RELZEP REQUESTED Relief is requested from the Differential pressure requirements as denoted'n IWP-4240.

ED BASZS POR RELZEP Pump suction pressure taps were not provided in the original design of these systems. Therefore, measurement of the pump suction pressure or measurement of differential pressure is impractical.

P. ALTERNATIVE TESTING Boric Acid Transfer and Diesel Oil Transfer Pump suction pressure will be calculated, based on tank level and the fluid elevation above the centerline of the pump.

G. IMPLEMENTATION SCHEDULE SECOND INSPECTION INTERVAL 54

s TURKEY POINT UNIT NO. 3/4 DATE: 12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 RELZEP REQUEST NO+ 6 A. COMPONENT/SYSTEM ITEM NO. COMPONENT DESCRIPTION IDENTIFICATION

1. BORIC ACID TRANSFER PUMP A *-P203A

2. BORIC ACID TRANSFER PUMP B *-P203B B ~ SECTZON XZ REQUZREMENTS IWP-4310 BEARING TEMPERATURE MEAStH&MENT C. PUNCTZON N/A Do RELZEP REQUESTED r

Relief is requested from the Bearing Temperature Measurements of IWP-4310.

ED BASIS POR RELZEP The Boric Acid Transfer Pumps are partially enclosed with thermal insulation and heat traced to prevent precipitation of boric acid from the solution. Therefore, the Bearing Temperature measurements are not fully implemented.

P. ALTERNATIVE TESTING Measurement of vibration amplitude and other required parameters during each pump test will provide for the early detection of changes in the mechanical characteristics of the pump.

Pump outboard bearing temperature will be measured. The inboard bearing temperature will not. be measured since inaccessible due to thermal insulation and heat tracing.

it is

6. IMPLEMENTATION SCHEDULE SECOND INSPECTION INTERVAL 55

0 Y POINT UNIT NO. 3/4 DATE: 12-12-88 SECOND TEN AR INSERVICE TESTING P RAM REVISION: 1 RELZEP REQUEST NO A o COMPONENT/SYSTEM ITEM NO. COMPONENT SCRIPTION IFICATION CY B.SECTION XI REQUZ

'O CD FUNCTION D RBLZBP REQUESTED E BASIS FOR RELIBP P. ALTERNATIVB TBSTI 6 IMPLEMENTATION S 56

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Y POINT UNIT NO. 3/4 DATE:12-12-88 SECOND TEN EAR INSERVICE TESTING P GRAM REVISION: 1 RELIEF REQUEST NO.

A. COMPONENT/SYSTEM ITEM NO. COMPONENT ESCRIPTION NTIFICATION B.SECTION XZ REQUZ C. PUNCT ION D RELIEP REQUESTED ED BASIS FOR RELZEP PE ALTERNATIVE TEST

6. 1MPLEMENTATZON S 57

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TUEuKY POINT UNIT NO ~ 3/4 DATE:12-12-88 SECOND TEN-YEAR ZNSERVICE TESTING PROGRAM REVISION: 1 RELZEP REQUEST NO 9 A>> COMPONENT/SYSTEM ITEM NO. COMPONENT DESCRIPTION IDENTIFICATION

1. RESIDUAL HEAT REMOVAL PUMP A *-P210A 2 ~ RESIDUAL HEAT REMOVAL PUMP '

-P210B B ~ SECTION XZ REQUIREMENTS IWP-4120 The full-scale range of each instrument shall be three times the reference value or less.

C. PUNCTZON Removes Residual Heat from the Primary System.

D. RELIEP REQUESTED Relief is requested from the requirement that inlet and outlet pressure gage full scale range be three times the:

reference value.

Eo BASIS POR RELZEP Suction pressure for all RHR pumps can vary from approximately 4 450 Psig. The full scale range for inlet and Discharge pressure gages for all four pumps is 0 600 Psig. Since there is such great variability in Suction pressure conditions, the pumps require a gage with a larger scale range.

P. ALTERNATIVE TESTZNO Since the inlet pressure varies on the RHR pumps, gages with larger scale ranges are required to accomodate pressure rises of pump suction.

Qe IMPLEMENTATION SCHEDULE SECOND INSPECTION INTERVAL 58

4'7 TURKEY POINT UNIT NO. 3/4 DATE 12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 RELZEP REQUEST NO+ 10 Ao COMPONENT/SYSTEM ITEM NO. COMPONENT DESCRIPTION IDENTIFICATION 1~ FLUKE DIGITAL PYROMETER 2 ~ SHIMPO DIGITAL TACHOMETER 3 ~ THERMAZZPDIGITAL PYRO-METER B. SECTION XI REQUIREMENTS IWP-4120 The full-scale range of each instrument shall be three times the reference value or less.

CD FUNCTION The instruments are used to measure Bearing Temperature and Speed on various pumps in the IST Program.

D. RELIEP REQUESTED Relief is requested from the requirement that the full scale range of each instrument shall be three times the. reference value.

ED BASIS POR RELZEP The Tachometer has an overall range of 5 to 30,000 RPM. In the 5 to 5,000 RPM range the specified accuracy limits are plus or minus 1 RPM. From 5000 to 30,000 RPM the specified accuracy limits are plus or minus 2 RPM.

The Fluke pyrometer temperature ranges from 328 degrees to 2400 degrees fahrenheit with an accuracy of plus or minus 0.14 of the reading. The Thermazip pyrometer temperature ranges from -100 degrees to 2000 degrees fahrenheit with an accuracy of 0.054 plus or minus 1 digit. Due to the varying values being read with these instruments it is not practical to use instruments which meet the requirements of IMP-4120.

PE ALTERNATIVE TESTZNO No alternative test methods are proposed since both instruments provide sufficiently accurate data to utilize in the pump monitoring program to assess pump degradation.

6. IMPLEMENTATION SCHEDULE SECOND INSPECTION INTERVAL 59

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TURKEY POINT UNIT NO. 3/4 DATE:12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 CHANGE NO: A DATE:08-17-89 RELIEF REQUEST NO ~ 11 Ao COMPONENT/SYSTEM ITEM NO. COMPONENT DESCRIPTION IDENTIFICATION 1~ RESIDUAL HEAT REMOVAL PUMP A

P210A 2~ RESIDUAL HEAT REMOVAL PUMP B

P210B B ~ SECTION XI REQUIREMENTS IWP-4310 BEARING TEMPERATURE MEASUREMENT CD FUNCTION Removes residual heat from the Primary system D RELIEF REQUESTED Relief is requested from measuring temperature on the lower radial bearing on the pump.

ED BASIS FOR RELIEF The lower ra dial bearing temperature cannot be measured since there is no accessible point of measurement.

Furthermore, vibration measurements are a significantly more reliable indication of pump bearing degradation. These pumps are subject to vibration measurements, in accordance with IWP-4500.

F~ ALTERNATIVE TESTING None G~ IMPLEMENTATION SCHEDULE SECOND INSPECTION INTERVAL 60

TUEOCEY POINT UNIT NO. 3/4 DATE 12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 RELIEP REQUEST NO, 12 Ao COMPONENT/SYSTEM ITEM NO. COMPONENT DESCRIPTION IDENTIFICATION 1~ INTAKE COOLING WATER PUMP A

P9A 2~ INTAKE COOLING WATER PUMP B

P9B

3. INTAKE COOLING WATER PUMP C

P9C B ~ SECTZON XZ REQUIREMENTS IWP-3 100 PUMP INLET PRESSURE MEASUEKMENT CD PUNCTZON Provides cooling water to safety related equipment.

De RELZEP REQUESTED r

Relief is requested from the pump inlet pressure measurement:

of Section XI.

ED BASIS POR RELZEP The Intake Cooling Water Pumps are vertical line shaft pumps with no direct means to obtain the inlet pressure measurement as required by IWP-4200. The Inlet pressure cannot be measured because there are no installed pressure instruments in the intake to the pumps. The pump inlet pressure is currently determined by measuring the water level above the pump inlet and calculating the pump inlet pressure. Using a calculated pump inlet pressure and a measured pump discharge pressure, will allow FPL to determine the pump differential pressure. With pump differential pressure and measured pump flov rate, FPL should have adequate information to assess the hydraulic condition of the pump in order to detect any hydraulic degradation.

PE ALTERNATIVE TESTZNO The inlet pressure will be calculated based on the water level above the pump inlet. The water level above the inlet vill be obtained by measurement with respect topumpa reference point on the operating deck.

6 ~ IMPLEMENTATION SCHEDULE SECOND INSPECTION INTERVAL 61

TUREKY POINT UNIT NO. 3/4 DATE:12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 RELZEP REQUEST STATUS TABLE TABLE NO 4 2 RELIEF REQUEST DESCRIPTION VALVE RELIEF REQUESTS:

REACTOR COOLANT ZWV-3410 IWV-3520 IWV-3300 IWV-3410 & ZWV-3300 ZWV-3410 & IWV-3300 IWV-3410 WITHDRAWN ZWV-34 10 CHEMICAL & VOLUME CONTROL IWV-3410 IWV-3410 IWV-34 10 WITHDRAWN IWV-34 10 IWV-3410 IWV-34 10 IWV-3410 WITHDRAWN 10 IWV-352 0 IWV-3520 12 IWV-3520 13 IWV-3520 62

h n

TUREKY POINT UNIT NO ~ 3/4 DATE:12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 RELZEP REQUEST STATUS TABLB TABLB MO+ 4 ~ 2 DESCRIPTION VALVE RELIEF REQUESTS:

14 IWV-3520 IWP-3520 AUXILIARY COOLANT'ESIDUAL HEAT REMOVAL ZWV-3410 ZWV-3520 ZWV-3420 & IWV-3410 I

AUX LIARY COOLANT ~ COMPONENT COOLING WATER WITHDRAWN WITHDRAWN IWV-3410 WITHDRAWN IWV-34 10 IWV-34 10 SAFETY INJECTION WITHDRAWN WITHDRAWN IWV-3410

. 4 IWV-3410 IWV-3410 IWV-34 10 IWV-352 0 IWV-3520 63

'I'4 e

TUREKY POINT UNIT NO. 3/4 DATE:12-12-88 SECOND TEN-YEAR ZNSERVICE TESTING PROGRAM REVISION: 1 RELIEF REQUEST STATUS TABLE TABLE NO ~ 4 ~ 2 RELIEF REQUEST DESCRIPTION VALVE RELIEF REQUESTS:

ZWV-3520 10 IWV-3410 IWV-3410 12 ZWV-3410 13 IWV-3410 & IWV-3300 14 IWV-3520 15 IWV-3520 16 IWV-3520 17 ZWV-3520 18 WITHDRAWN 19 IWV-3520 20 WITHDRAWN 21 IWV-3410 22 IWV-3520 SAMPLING WITHDRAWN IWV-3300 MAIN STEAM XWV-352 0 IWV-3520 CONDENSATE AND FEEDWATER WITHDRAWN WITHDRAWN 64

fa f

TURKEY POINT UNIT NO. 3/4 DATE:12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 RELZEP REQUEST STATUS TABLE TABLE NO. 4 ~ 2 RELIEF REQUEST DESCRIPTION VALVE RELIEF REQUESTS:

IWV-3520 IWV-34 10 IWV-34 10 ZWV-3 3 00 INSTRUMENT AIR(LUBE OIL, SERVICE AND INSTRUMENT AZR)

IWV-352 0 DIESEL OIL IWV-34 13 IWV-3413 3 IWV-34 13 PRIMARY MAKE-UP AND CONTAINMENT COOLING WATER IWV-3410 CONTAINMENT VENTILATION IWV-3410 IWV-3410 IWV-3520 IWV-3410 IWV-3300 ZWV-3410 IWV-3520 8 ZWV-3410

0 l~

S

TURKEY POINT UNIT NO. 3/4 DATE:12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 RELIEF REQUEST STATUS TABLE TABLE NO ~ 4 ~ 2 RELIEF REQUEST DESCRIPTION VALVE RELIEF REQUESTS'ARIOUS IWV 34 17 ~ IWV 3427 I ZWV 3523 AND ZWP-3230 IWV-3423 AND ZWV-3424 IWV-3420 66

4% J

. f

TURKEY POINT UNIT NO. 3/4 DATE: 12-12-88

.SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVIS ION: 1 RELIEP REQUEST NO, 1 A COMPONENT/SYSTEM REACTOR COOLANT VALVE IDENTIFICATION NUMBER CATEGORY CLASS CV-*-519A A 2 BISECTION XZ REQUIREMENTS IWV-3410 CD FUNCTION Provides a primary water path to either the pressurizer relief tank or the Reactor coolant pumps standpipes.

D RELZEP REQUESTED Relief is requested from exercising during normal plant operation.

ED BASIS FOR RELIEF Failure of this valve in the non-closed position, by testing during plant operation, would cause a loss of containment integrity requiring Reactor Shutdown per Technical Specification (3.3) .

PE ALTERNATIVE TESTING This valve will be tested during cold shutdowns.

Ge IMPLEMENTATION SCHEDULE SECOND INSPECTION INTERVAL 67

4th 0

TURKEY POINT UNIT NO. 3/4 DATE:12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 RELZBP REQUEST NO 2 A. COMPONENT/SYSTEM REACTOR COOLANT VALVE IDENTIFICATION NUMBER CATEGORY CLASS

-518 AC

-519 AC B. SECTION XZ REQUIREMENTS IWV-3520 CD PUNCTZON Provides flow from the Nitrogen system to the Pressurizer Relief Tank.

D. RELIBP REQUESTED Relief is requested from exercising during normal plant operation.

E~ BASIS POR RBLIEP Failure of this valve in the non-closed position, by testing during plant operation, would cause a loss of containment integrity requiring Reactor shutdown per Technical Specification (3.3).

P ALTERNATIVE TESTZNO This valve will be tested during cold shutdowns.

6e IMPLBMBNTATION SCHBDULE SECOND INSPECTION INTERVAL e 68

pg S

TURKEY POINT UNIT NO. 3/4 . = DATE:12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 RELZEP REQUEST NO 3 A COMPONENT/SYSTEM REACTOR COOLANT VALVE IDENTIFICATION NUMBER CATEGORY CLASS SV-*-6385 A 2 BISECTION XI REQUIREMENTS IWV-33 00 C PUNCTION provides flow path from pressurizer relief tank to gas analyzer.

D. RELZEP REQUESTED Relief is requested from direct valve position indication verification.

ED BASZS POR RELIEF This self contained, completely enclosed solenoid valve has no external valve position indication. Therefore, direct observation of valve position indication is impractical.

PE ALTERNATIVE TESTING This valve will be tested by connecting an external air supply with sufficient air pressure to verify the main disk moves to the open position at least once every 2 years.

6 IMPLEMENTATION SCHEDULE SECOND INSPECTION INTERVAL 69

I' "4%

lt

~

aw

,P~

TURKEY POINT UNIT NO. 3/4 DATE:12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 RELZEP RE{}UEST NO+ 4 A. COMPONENT/SYSTEM REACTOR COOLANT VALVE IDENTIFICATION NUMBER CATEGORY CLASS SV-*-6319A SV-*-6319B BISECTION XZ REQUIREMENTS IWV-34 10 IWV-33 00 C P UNCT ION Provides for redundant flow paths from the pressurizer to the Reactor Coolant Vent System.

DE RELZEP REQUESTED r

Relief is requested from exercising the valves during normal-plant operation and from valve position indication verification.

ED BASZS POR RELZEP These valves are required to be positioned closed and key locked to prevent inadvertent operation of these valves during unit operation.

Failure of either of these valves in the non-closed position coupled with the failure of either SV-*-6320A or SV->>-6320B, while testing during plant operation, could result in loss of reactor coolant in excess of Plant Technical Specification 3.1.3. This would result in unit shutdown.

These self contained, completely enclosed solenoid valves have no local valve position indication. Therefore, observation of the valve position indication is impractical; P. ALTERNATIVE TESTING These valves will be tested during cold shutdowns when the Reactor Coolant System is depressurized and vented.

During refueling shutdowns, valve disk position will be determined by exercising the valve while observing changes in pressure, temperature or flow to the containment atmosphere, flow to the containment sump, or level increase in the pressurizer relief tank.

8 ~ IMPLEMENTATION SCHEDULE SECOND INSPECTION INTERVAL 70

Ee I

TUESDAY POINT UNIT NO. 3/4 DATE:12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 RELIEP REQUEST NO 5 A. COMPONENT/SYSTEM REACTOR COOLANT VALVE IDENTIFICATION NUMBER CATEGORY CLASS SV-*-6318A B SV-*-6318B B SV-*-6320A B SV-*-6320B B B ~ SECTION XZ REQUIREMENTS IWV-34 10 IWV-33 00 C. PUNCTION Provide for redundant flow paths from the reactor vessel closure head to the Reactor Coolant Vent System.

J D. RELZEP REQUESTED Relief is requested from exercising during normal plant operation and from valve position indication verification.

E ~ BASIS POR RELIEP These valves are required locked to prevent inadvertent operation during normal unit operation.

'f to be positioned closed and key these valves Failure of either SV-*-6318A or SV-*-6318B in the non-closed position coupled with the failure of either SV-*-6320A or SV-*-6320B, while testing during plant operation, could result in loss of reactor coolant in excess of Technical Specification 3.1.3. This would result in a unit shutdown.

These self contained , completely enclosed solenoid valves have no local valve position indication. Therefore, observation of valve position indication is impractical.

P ~ ALTERNATIVE TESTINO These valves will be tested during cold shutdown when the Reactor Coolant System is depressurized and vented.

During refueling shutdowns, valve disk position will be determined by exercising the valve while observing changes in pressure, temperature, flow to the containment atmosphere, flow to the containment sump, or level increase in the pressurizer relief tank.

6 IMPLEMENTATION SCHEDULE SECOND INSPECTION INTERVAL 71

Il

'S~

1~

x

TURKEY POINT UNIT NO. 3/4 DATE:12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 RELIEP REQUEST NO. 6 AD COMPONENT/SYSTEM REACTOR COOLANT VALVE IDENTIFICATION NUMBER CATEGORY CLASS PCV>>*-455C PCV-*-456 B.SECTION XZ REQUIREMENTS INV-3410 C PUNCTZON Power Operated Relief Valve (PORV). Provides for low temperature overpressure mitigation during cold shutdown operation. No credit is taken for PORVs during power operation.

D RELIEF REQUESTED Relief is requested from exercising during normal plant operation.

ED BASIS POR RELIEF Failure of cather of these valves in the non-closed position coupled with the failure of the associated'isolation (Block) valve, by testing during plant operation, would result in a plant shutdown per Plant Technical Specification 3.2.2.

F o ALTERNATIVE TESTING These valves will be tested during cold shutdowns when the Reactor Coolant System is depressurized and vented.

Go IMPLEMENTATION SCHEDULE SECOND INSPECTION INTERVAL 72

a Y POINT UNIT NO. 3/4 DATE:12-12-88 SECOND TEN AR INSERVICE TESTING P RAM REVISION: 1 e

RELZBP REQUEST NO A COMPONENT/SYSTEM ACTOR COOLANT VALVE IDENTZFICATIO BER CATEGOR SS BISECTION XZ REQUZ NTB

~

C. PUNCTZON D RBLZEP REQUESTBD ED BASIS POR RELZBP PE ALTBRNATZVB'ESTZ 6 IMPLEMENTATION S DU 73

0 TURKEY POINT UNIT NO. 3/4 DATE'12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 RBLZEP REQUEST NO ~ 8 A. COMPONENT/SYSTEM REACTOR COOLANT VALVE IDENTIFICATION NUMBER CATEGORY CLASS CV-*-516 A SV-*-6385 A B ~ SECTION XZ REQUIREMENTS IWV-3410 CD PUNCTZON Provides flow path from pressurizer relief tank to the gas analyzer.

D~ RELZEP REQUESTED r

Relief is requested from exercising during normal plant'peration.

ED BASIS POR RELIBP Failure of these valves in the non-closed testing during plant operation, would causeposition,a loss of by containment integrity requiring Reactor shutdown per Plant Technical Specification (3.3).

P ALTERNATIVE TESTZN6 These valves will be tested during cold shutdown.

6 ~ IMPLEMENTATION SCHEDULE SECOND INSPECTION INTERVAL 74

15~

TURKEY POINT UNIT NO. 3/4 DATE:12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 RELZEP REQUEST NO 1 A. COMPONENT/SYSTEM CHEMICAL & VOLUME CONTROL VALVE IDENTIFICATION NUMBER CATEGORY CLASS CV-*-200A A CV-*-200B A CV-*-200C A B ~ SECTION XI REQUIREMENTS IWV-34 10 Co PUNCTION Provides parallel letdown flow paths through the associated letdown 'orifices to control Chemical and Volume Control System letdown flow rate.

D. RELZEP REQUESTED Relief is requested from exercising during normal plant operation.

E~ BASIS POR RELIEP Failure of any one of these valves in the non-closed position, by testing during plant operation, would require a shutdown per Technical Specification (3.3).

P. ALTERNATIVE TESTING l

These valves will be tested during cold shutdowns.

6. IMPLEMENTATION SCHEDULE SECOND INSPECTION INTERVAL 75

1"

'E tI

TKGCEY POINT UNIT NO. 3/4 DATE: 12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 RELZEP REQUEST NO+ 2 A. COMPONENT/SYSTEM CHEMICAL & VOLUME CONTROL VALVE IDENTIFICATION NUMBER CATEGORY CLASS CV-*-204 A 2 BISECTION XI REQUIREMENTS IWV-34 10 C~ FUNCTION Provides the letdown flowpath during plant operation.

Do RELIEP REQUESTED Relief is requested from exercising during normal plant operation.

E ~ B)LSZS POR RBLIBP Testing this valve during plant operation would cause an unbalance flow condition in the Chemical and Volume Control System. The loss of the letdown flow path will result in the loss of the regenerative heat exchanger function. This could subject the Reactor Coolant System'piping to thermal shock due to cooler charging return flow from the Chemical and Volume Control System.

F ~ ALTERNATIVE TESTZNQ This valve will be tested during cold shutdowns.

Oo IMPLEMENTATION SCHEDULE SECOND INSPECTION INTERVAL 76

0 0 4 /

lg1 i

l

<<c

TUlucEY POINT UNIT NO. 3/4 DATE-12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 RELZBP RBQUEST NO+ 3 A COMPONENT/SYSTEM CHEMICAL & VOLUME CONTROL VALVE IDENTIFICATION NUMBER CATEGORY CLASS MOV-*-381 A MOV-*-6386 A B ~ SECTION XZ REQUIREMENTS IWV-3410 C~ PUNCT ION Provides the Reactor Coolant Pump seal injection return flow path to the Chemical and Volume Control Tank. In addition, provides the excess letdown flow path from the Reactor Coolant System to the Chemical and Volume Control System Volume Control Tank.

D. RELZBP REQUESTED Relief is requested from exercising during normal plant operation.

E. BASIS POR RELIEP Testing either of these valves during plant operations would interrupt flow to the Reactor Coolant Pump Controlled Leakage Seal Systems, which could result in damage to the Reactor Coolant Pumps; thereby, placing the plant in an unsafe mode of operation.

PE ALTERNATIVE TESTING These valves will be tested during cold shutdowns when the

.Reactor Coolant System is depressurized and vented.

6 ~ IMPLEMENTATION SCHBDULB SECOND INSPECTION INTERVAL 77

t f'

POINT UNIT NO ~ 3/4 DATE:12-12-88 SECOND TEN INSERVICE TESTING P RAM REVISION: 1 RELIEP REQUEST NO+

A COMPONENT/SYSTEM EMICAL & VOL TRO VALVE IDENTIFICATIO BER CATEGO SS BISECTION XZ REQUI CD RUNCTZON D. RELZEP REQUESTED ED BASIS POR RELIEP P. ALTERNATIVE TEST 6 ~ IMPLEMENTATION S 78

1'~

"l

'E 0

TURKEY POINT UNIT NO, 3/4 DATE:12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 RELIEP REQUEST NO+ 5 A COMPONENT/SYSTEM CHEMICAL & VOLUME CONTROL VALVE IDENTIFICATION NUMBER CATEGORY CLASS HCV-*-121 BISECTION XZ REQUIREMENTS IWV-3410 CD PUNCTZON Provides the charging flow path to the Reactor Coolant System. This valve is used to proportion flow between the seal injection supply to the Reactor Coolant pump Controlled Leakage Seal System and the charging flow to the Reactor Coolant System.

D RELZEP REQUESTED Relief is requested from exercising during normal plant operation. Relief is also requested from stroke time testing this control valve.

ED BASIS POR RELZEP Testing this valve during plant operation would cause an unbalance flow condition in the Chemical and Volume Control System. This would interrupt flow to the Reactor Coolant Pump Controlled Leakage Seal System, which could result in damage to the Reactor Coolant Pumps; thereby, placing the plant in an unsafe mode of operation.

Stroke time testing is not essential for fullfillment of the safety function of this valve.

During normal plant operation the valve is positioned, using a potentiometer on the control console to maintain sufficient backpressure in the charging header to ensure adequate RCP seal water injection flow.

PE ALTERNATIVE TESTING This valve will be tested during cold shutdowns, after the charging pumps have been secured. During normal plant operation valve operational readiness is verified when charging and letdown are in'ffect.

6. IMPLEMENTATION SCHEDULE SECOND INSPECTION INTERVAL 79

l

~ <

TURKEY POINT UNIT NO ~ 3/4 DATE'12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION 1 RELZEP REQUEST NO>> 6 A. COMPONENT/SYSTEM CHEMICAL & VOLUME CONTROL VALVE IDENTIFICATION NUMBER CATEGORY CLASS CV-*-310A CV-*-310B BISECTION XI REQUIREMENTS IWV-3410 CD FUNCTION Provides redundant charging flow paths to the Reactor Coolant System.

D>> RELIEF REQUESTED Relief is requested from exercising during normal plant:

operation.

ED BASIS POR RELZEP Testing these valves during normal operation could result in loss of pressurizer level control or thermal shock to the Chemical and Volume Control System injection nozzles.

P ALTERNATIVE TESTING These valves will be tested during cold shutdowns.

6 ~ IMPLEMENTATION SCHEDULE SECOND INSPECTION INTERVAL 0

80

-/41 TURKEY POINT UNIT NO. 3/4 DATE-'12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 RELIEP REQUEST NO 7 A COMPONENT/SYSTEM CHEMICAL & VOLUME CONTROL VALVE IDENTIFICATION NUMBER CATEGORY CLASS LCV-*-115C B 2 BISECTION XZ REQUIREMENTS IWV-34 10 C~ P UNCTION Provides the flow path from the Volume Control Tank to the charging pump suction header.

D. RELZEP REQUESTED Relief is requested from exercising during normal plant operation.

ED BASIS POR RELZEP Testing this valve during plant operation would cause an unbalance flow condition in the Chemical and Volume Control System. This would interrupt flow to the Reactor Coolant Pump Controlled Leakage Seal System. Which would result in damage to the Reactor Coolant Pumps; thereby, placing the plant in an unsafe mode of operation. Further, the failure of this valve in the closed position, by testing during plant operation, would isolate normal charging pump make-up.

PE ALTERNATIVE TESTING This valve will be tested during cold shutdowns.

6 ~ 1MPLEMENTATZON SCHEDULE SECOND INSPECTION INTERVAL 81

p' TUREKY POINT UNIT NO. 3/4 DATE '2-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION-'

RELIEF REQUEST NO ~ 8 A. COMPONENT/SYSTEM. CHEMICAL & VOLUME CONTROL VALVE IDENTIFICATION NUMBER CATEGORY CLASS LCV-*-115B BISECTION XI REQUIREMENTS IWV-3410 C FUNCTION Provides a flow path from the Refueling Water Storage Tank to the charging pump suction header.

D RELIEF REQUESTED Relief is requested from exercising during normal plant operation.

ED BASIS POR RELZEP This valve is interlocked with LCV-*-115C. Testing valve during plant operation would result in closure of this LCV-

-115C. This would result in loss of charging pump flow from the Volume Control Tank or overboration of the Reactor Coolant System'from the refueling water storage tank.

PE ALTERNATIVE TESTING This valve will be tested during cold shutdowns.

6. IMPLEMENTATION SCHEDULE SECOND INSPECTION INTERVAL 82

0 0

"4 L

~ ~

POINT UNIT NO. 3/4 DATE:12-12-88 SECOND TEN INSERVICE TESTING P RAM REVISION: 1 RELIEP REQUBST NO, Ao COMPONENT/SYSTEM EMICAL & VOL RO VALVE IDENTIFICATIO BER CATEGOR SS CE BISECTION XZ REQUZ

'C3 O U Z C PUNCTZON Do RBLZBF REQUESTBD ED BASIS FOR RELIEF Po ALTERNATIVE TBSTI ao IMPLEMENTATION S DU 83

H

'+i'

~

C$

gV+

ra

TURKEY POINT UNIT NO. 3/4 DATE:12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 RELIBP RE{}UEST NO ~ 10 Ao COMPONENT/SYSTEM CHEMICAL & VOLUME CONTROL VALVE IDENTIFICATION NUMBER CATEGORY CLASS

-312A

-312B B. SECTION XZ RE{}UZREMENTS IWV-3520 Co PUNCTZON Provides flow from the Chemical Volume and Control system to the RCS Hot and Cold legs.

D RELZEP RE{}UESTED Relief is requested from exercising during normal plant:

operation.

BE BASIS POR RBLZEP Testing this valve during plant operation would cause an unbalance flow condition in the Chemical and Volume Control System. This would interrupt flow to the Reactor Coolant Pump Controlled Leakage Seal System, which could result in damage to the Reactor Coolant Pumps; thereby, placing the plant in an unsafe mode of operation.

P ALTERNATIVE TESTING These h

valves will be tested during cold shutdowns.

6. IMPLEMENTATION SCHBDULE SECOND INSPECTION INTERVAL 84

~J

TUEQCEY POINT UNIT NO. 3/4 DATE:12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 RELZEP REQUEST NO. 11 A. COMPONENT/SYSTEM CHEMICAL & VOLUME CONTROL VALVE IDENTIFICATION NUMBER CATEGORY CLASS

-351 BISECTION XZ REQUIREMENTS IWV-3520 C RUNCTZON Provides the Boron addition flow path from the Boron addition (Boric Acid Makeup) system to the Reactor Coolant System.

Do RELZEP REQUESTED Relief is requested from exercising during normal plant operation.

ED BASIS POR RELZEP Testing this valve during plant operation could result in addition of excess boron to the Reactor Coolant System resulting in a reactor shutdown.

PE ALTERNATIVE TESTING This valve will be tested during cold shutdowns.

Go IMPLEMENTATION SCHEDULE SECOND'INSPECTION INTERVAL 85

ll F,+

TURKEY POINT UNIT NO. 3/4 DATE:12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 RELZEP REQUEST NO. 12 A. COMPONENT/SYSTEM CHEMICAL & VOLUME CONTROL VALVE IDENTIFICATION NUMBER CATEGORY CLASS

-357 C 2 B ~ SECTION XZ REQUIREMENTS IWV-352 0 C~ FUNCTION Provides the alternate Boron addition flow path from the refueling water storage tank to the Reactor Coolant system.

D. RELXEP REQUESTED Relief is requested from exercising during normal plant operation.

Eo BASZS FOR RELIEF Testing this valve during plant operation would result in the addition of boron to the Reactor Coolant System. This could place the plant in an unsafe mode of operation.

P ALTERNATIVE TESTXNQ This valve will be tested during cold shutdowns.

G. IMPLEMENTATION SCHEDULE SECOND INSPECTION INTERVAL 86

lilr Iyg f

K4 j%

TUEQXY POINT UNIT NO. 3/4 DATE:12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 RBLZBP RBQUEST NO. 13 A. COMPONENT/SYSTEM CHEMICAL & VOLUME CONTROL VALVE IDENTIFICATION NUMBER CATEGORY CLASS

-298A AC

-298B AC

-298C AC B ~ SECTION XZ REQUIREMENTS IWV-3520 C. PUNCTZON Prevents reverse flow from the Reactor Coolant pump seal injection system to the chemical and volume control system.

D. RELZEP REQUBSTBD r

Relief is requested from testing these valves during normal:.

plant operation as well as cold shutdowns.

Eo BASIS POR RBLZEP Testing these valves during plant operation would interrupt flow to the Reactor Coolant Pump Seal injection system, which would result in damage to the Reactor Coolant Pumps; thereby, placing the plant in an unsafe'ode of operation.

Further, the testing of these valves during cold shutdown is impractical since it would require draining the Reactor Coolant Pump Seal Injection System to check the position of these valves.

This would increase the possibility of causing damage to the Reactor Coolant pump seals due to the added frequency of venting the system prior to plant operation.

PE ALTERNATIVE TESTZNS These valves will be tested at least once every 2 years.

Go IMPLEMENTATION SCHEDULE SECOND INSPECTION INTERVAL 87

s I

Cw')

~7

TURKEY POINT UNIT NO. 3/4 DATE:12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 RELIBP REQUEST NO 14 A COMPONENT/SYSTEM CHEMICAL & VOLUME CONTROL VALVE IDENTIFICATION NUMBER CATEGORY CLASS

-312C AC B ~ SECTION XZ REQUIREMENTS IWV-3520 Co PUNCTION Prevents reverse flow from the Reactor Coolant System charging flow path to the chemical and Volume Control System.

D. RELZBP REQUESTBD Relief is requested from exercising during normal plant operation.

ED BASIS POR RELZEP

'I Testing this valve during plant operation would cause an unbalance flow condition in the Chemical and Volume Control System. This could result in damage to the Reactor Coolant Pumps; thereby, placing the plant in an unsafe mode of operation.

Testing this valve during cold shutdown is impractical because check the itposition would require draining the charging system to of the valve. This would cause a loss of the charging flow path that is routinely used to meet the Technical Specification requirements to have a boron injection flow path to the Reactor Coolant System during cold shutdown.

P ~ ALTERNATIVE TBSTINO This valve will be tested at least once every 2 years.

6o IMPLEMENTATION SCHEDULE SECOND INSPECTION INTERVAL 88

'4 r~ l

~

C>

TUEOCEY POINT UNIT NO ~ 3/4 DATE:12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 RELZEF REQUEST NO+ 15 R. COMPONENT/SYBTEM CHEMICAL & VOLUME CONTROL VALVE IDENTIFICATION NUMBER CATEGORY CLASS 3-397A C 3-397B C 4-397C C 4-397D C B ~ SECTION XI REQUIREMENTS INV-352 0 C~ FUNCTION provides flow from Boric Acid Transfer pumps to the CVCS makeup and blending station.

D RELIEF REQUESTED Relief is requested from testing these valves during normal plant operation.

E~ BASIS FOR RELIEF Testing any of these valves during .plant operation would cause an addition of excess boron to the Reactor Coolant System resulting in a reactor shutdown.

F. ALTERNATIVE TESTING These valves will be tested during cold shutdowns.

Q. IMPLEMENTATION SCHEDULE SECOND INSPECTION INTERVAL 89

~ et at%

0

DATE: 12-12-88 SECOND TEN INSERVICE TESTING RAM REVISION: 1 RELIBP REQUEST NO, A. COMPONENT/SYSTEM XILIARY COOLANT, OMPO COOLING WATER VALVE IDENTIFICATIO BER CATEGOR SS BISECTION XZ REQUI CD PUNCTZON Do RBLZBP REQUESTED B. BASIS POR RBLZEP P ALTBEQQgZVB TBST 6 IMPLEMENTATION S DULB 90

II'v

DATE: 12-12-88 SECOND TEN INSERVICE TESTING RAM REVISION: 1 RELZEF REQUEST NO+

A. COMPONENT/SYSTEM ILIARY COOLANT, OMPO COOLING WATER VALVE IDENTIFICATIO BER CATEGOR S BISECTION XZ RE{}UI C PUNCTZON D RELIEP REQUESTED ED BASIS POR RELZEP F. ALTERNATIVE TEST

6. IMPLEMENTATION S DULif=l 91

f

=

@ted 4

0

TUEQZY POINT UNIT NO. 3/4 DATE:12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 RELZEP REQUEST NO ~ 3 A COMPONENT/S~TEM AUXILIARY COOLANT g COMPONENT COOLING WATER VALVE IDENTIFICATION NUMBER CATEGORY CLASS MOV-*-716A B 2 MOV-*-716B B 2 B ~ SECTZON XZ REQUIREMENTS IWV-34 10 C. PUNCTZON Provides the component cooling water supply flow path for the heat exchangers located in the Reactor Coolant pumps.

(motors and thermal barriers)

D RELZEP REQUESTED Relief is requested from exercise testing during normal plant operation.

Eo BASZS POR RELZEP Testing either of these= valves during plant operation would cause interruption of cooling water to the Reactor Coolant pumps heat exchangers. This action could result in damage to the Reactor Coolant pumps; placing the plant in an unsafe mode of operation.

PE ALTERNATZVE TESTING These valves will be tested during cold shutdowns.

6 ~ IMPLEMENTATION SCHEDULE Second Inspection Interval 92

'f 4

Y POINT UNIT NO. 3/4 DATE 12-12-88 SECOND TEN AR INSERVICE TESTING P RAM REVIS ION: 1 RELIEF REQUEST NO+

A. COMPONENT/SYBTEM MPONENT COOLING TER VALVE IDENTIFICATIO BER CATEGOR SS B SECTION XZ REQUZ ms+

C FUNCTION D RBLZBF REQUESTBD ED BASIS FOR RBLZBF Fo ALTERNATIVE TEST 6 ~ IMPLEMENTATION S DULd 93

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TURKEY POINT UNIT NO. 3/4 DATE: 12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 RELIEP REQUEST NO. 5 A I COMPONENT/SYSTEM AUX LIARY COOLANT g COMPONENT COOLING WATER VALVE IDENTIFICATION NUMBER CATEGORY CLASS MOV-*-730 B 2 B ~ SECTION XZ REQUIREMENTS IWV-3410 C FUNCTION provides the component cooling water return flow path for the Reactor Coolant pumps motor heat exchangers.

D RELIEF REQUESTED r

Relief is requested from exercise testing during normal:.

plant operation.

ED BASIS POR RELIEF Testing this valve during plant operation would cause interruption of cooling water to the Reactor Coolant pumps motor heat exchangers. This action could result in damage to the Reactor Coolant pumps; thereby, placing the plant in an unsafe mode of operation.

P. ALTERNATIVE TESTING This valve will be tested during cold shutdown.

6 ~ IMPLEMENTATION SCHEDULE SECOND INSPECTION INTERVAL 94

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TUEOCEY POINT UNIT NO. 3/4 DATE:12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 RELZEP REQUEST NO 6 A. COMPONENTlSYSTEM AUXILIARY COOLANT, COMPONENT COOLING MATER VALVE IDENTIFICATION NUMBER CATEGORY CLASS FCV-*-626 BISECTION XI REQUIREMENTS IWV-3410 CD PUNCTZON Provides the component cooling return flow path for the Reactor Coolant pumps controlled leakage seal system thermal barriers.

D RELIEP REQUESTED Relief is requested from exercise testing during normal plant operation.

ED BASIS POR RELIEP Testing this valve during plant operation would cause interruption of cooling water to the Reactor Coolant pumps Controlled Leakage Seal System heat exchangers. This action could result in damage to the Reactor Coolant pumps; thereby, placing the plant in an unsafe mode of operation.

P. ALTERNATIVE TESTING This valve will be, tested during cold shutdowns.

6 ~ IMPLEMENTATION SCHEDULE SECOND INSPECTION INTERVAL 95

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TURKEY POINT UNIT NO. 3/4 DATE:12-12-88 SECOND TEN-YEAR INSERV1CE TESTING PROGRAM REVISION: 1 RELZEP REQUEST NO 1 R. COMPONENT/SYSTEM AUXILIARY COOLANT, RESIDUAL HEAT REMOVAL VALVE IDENTIFICATION NUMBER CATEGORY CLASS MOV-*-744A MOV-*-744B B.SECTION XI REQUIREMENTS IWV-3410 C. PUNCTION Provides a flow path from the low pressure safety injection system to the Reactor Coolant System.

D. RELIEP REQUESTED Relief is requested from exercising during normal plant operation.

ED BASIS POR RBLZBP The testing of these valves during plant operation, coupled with the failure of valves *-876A, *-876B, or *-876C, could subject the Low Pressure Safety Injection System to pressures in excess of its design pressure.

P ALTERNATIVE TESTING These (MOVs) valves will be tested during cold shutdowns.

6. IMPLEMENTATION SCHBDULE SECOND INSPECTION INTERVAL 96

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TURKEY POINT UNIT NO. 3/4 DATE: 12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 RELIEP REQUEST NO, 2 A 0 COMPONENT/SYSTEM AUXILIARY COOLANT g RESIDUAL HEAT REMOVAL VALVE IDENTIFICA'TION NUMBER CATEGORY CLASS

-753A C

-753B C B SECTION XZ REQUIREMENTS IWV-3520 C PUNCTZON Provides flow from the low pressure safety injection (Residual Heat Removal) pump to the Low Pressure Safety Injection (Residual Heat Removal) system supply header.

D RELIEP REQUESTED Relief is requested from testing these valves during normal:

plant operation.

ED BASIS POR RELZEP These valves cannot be tested during plant operation because the Low Pressure Safety Injection (Residual Heat Removal) pumps do not develop sufficient discharge head to establish a flow path to the Reactor Coolant System.

PE ALTERNATIVE TESTING These check valves will be Full Stroke exercised during cold shutdown.

In addition, these check valves will be exercised quarterly during the performance of associated pump tests with flow through the pump minimum flow recirculation line.

6 o IMPLEMENTATION SCHEDULE SECOND INSPECTION INTERVAL 97

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TURKEY POINT UNIT NO. 3/4 DATE:12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 RELIEP REQUEST NO+ 3 A COMPONENT/SYSTEM AUXILIARY COOLANT, RESIDUAL HEAT REMOVAL VALVE IDENTZFICA'TION NUMBER CATEGORY CLASS MOV-*-751 A MOV-*-750 A B ~ SECTION XZ REQUIREMENTS IWV-3420 IWV-34 10 Co FUNCTION Provides a flow path from the Reactor Coolant System to the Residual Heat Removal System for removal of decay heat from the reactor core.

D. RELIEF REQUESTED Relief is requested from testing during normal plant operation for the IWV-3410 requirements and from IWV-3420 requirements for leak testing.

ED BASIS FOR RELIEF IWV-3420 BASIS These valves are not required to be tested to 10 CFR Part 50, Appendix J, Type C tests. These valves will be tested as pressure isolation valves.

IWV-3410 BASIS These valves are provided with pressure interlocks from PL 403 to prevent opening these valves when: (1) RCS pressure is greater than 525 psig and (2) Either MOV-*-862A, MOV-*-862B, MOV-*-863A or MOV-*-863B of the associated unit is open, sensed through proximeter switches internal to the valves.

P ALTERNATIVE TESTING IWV-3420 These valves will be tested as Reactor Coolant pressure isolation valves using methods, procedures, and acceptance criteria in Table II and Technical= Specification 4.17.

98

TUREKY POINT UNIT NO. 3/4 DATE:12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION- 1 RELIEF REQUEST NO. 3 CONTINUED F. ALTERNATIVE TESTING CONTINUED IWV-3410 These valves will be tested during cold shutdown.

Go ZMPLEMENTATZON SCHEDULE SECOND INSPECTION INTERVAL 99

C I1 k'%

Y POINT UNIT NO ~ 3/4 DATE: 12-12-88 SECOND TEN AR INSERVICE TESTING P RAM REVIS ION: 1 RELZEP REQUEST NO Ao COMPONENT/SYSTEM FETY INJECTION VALVE IDENTIFICATIO BER CATEGOR SS B ~ SECT1ON XZ REQUZ ms+

U Co FUNCTZON Ee BASIS POR RELIEF P ALTERNMIVE TESTI ae IMPLEMENTATION S DUL~

100

)

0

Y POINT UNIT NO. 3/4 DATE '2-12-88 SECOND TEN AR INSERVICE TESTING P RAM REVIS ION: 1 RELZEP REQUEST NO.~

Za ~ COMPONENT/SYSTEM FETY INJECTION Z

VALVE IDENTIFICATIO BER CATEGOR SS BISECTION XZ REQUZ

"'CI CD FUNCTION D. RELZBP REQUESTED ED BASIS POR RBLZBP P. ALTERATIVE TBSTZ 6 IMPLEMENTATION S DU~

101

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TKVXY POINT UNIT NO. 3/4 DATE:12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 RELIES REQUBST NO 3 A. COMPONENT/SYSTEM SAFETY INJECTION VALVE IDENTIFICATION NUMBER CATEGORY CLASS MOV-*-863A B MOV-*-863B B B ~ SECTION XZ REQUIREMENTS IWV-34 10 C FUNCTION Provides the alternate flow path from the Low Pressure Safety Injection System to the Reactor Coolant System. Also, provides the flow path to the High Pressure Safety Injection System during the recirculation phase.

D RELZBP REQUESTED Relief is requested from exercising during normal plant operation.

ED BASIS FOR RELIEF The failure of either of these valves in the open position, by testing during normal operation, would result in diverting flow from the reactor core in the event of a safety injection signal.

Fo ALTERNATIVE TESTING These valves will be tested during cold shutdowns when the RCS is depressurized and vented and during each refueling outage.

6 IMPLEMENTATION SCHEDULE SECOND INSPECTION INTERVAL 102

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TURKEY POINT UNIT NO. 3/4 DATE:12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 RELIBP REQUBST NO+ 4 A. COMPONENT/SYSTEM SAFETY INJECTION VALVE IDENTIFICATION NUMBER CATEGORY CLASS MOV-*-872 A 2 B ~ SECTION XI REQUIREMENTS IWV-34 10 C P UNCT ION Provides the alternate flow path from the Low Pressure Safety Injection System to the Reactor Coolant System.

D. RELIBP REQUESTED Relief is requested from exercising during normal plant operation.

ED BASIS POR RELZEP The failure of this valve in the non-closed position, by testing during plant operation, renders high pressure long term Safety In)ection System recirculation unavailable.

P. ALTERNATIVE TESTING These valves will be tested during cold shutdown when the RCS is depressurized and vented and during each refueling outage.

6 o IMPLEMENTATION SCHBDULB SECOND INSPECTION INTERVAL 103

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TURKEY POINT UNIT NO. 3/4 DATE:12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 RELIEF REQUEST NO. '-5 A. COMPONENT/SYSTEM SAFETY INJECTION VALVE IDENTIFICATION NUMBER CATEGORY CLASS

-945E AC 2 BE SECTZON XZ REQUIREMENTS IWV-3410 CD FUNCTION Prevents reverse flow of nitrogen from the Safety Injection Accumulators to the nitrogen supply.

D. RELIEF REQUESTED Relief is requested from exercise testing during normal operation (quarterly)

ED BASIS FOR RELIEF The failure of this valve in the non-closed position, by testing during normal operation, would require a plant shutdown per Technical Specification (3.3).

F. ALTERNATIVE TESTING This valve will- be exercise tested during cold shutdowns and seat leak tested at least every two years.

G. IMPLEMENTATION SCHEDULE SECOND INSPECTION INTERVAL 104

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TURKEY POINT UNIT NO ~ 3/4 DATE: 12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION- 1 RELZBP REQUEST NO+ 6 A COMPONENT/SYSTEM SAFETY INJECTION VALVE IDENTIFICXTION NUMBER CATEGORY CLASS MOV-*-866A MOV-*-866B B.SECTION XI REQUIREMENTS IWV-3410 CD PUNCTZON Provides High Pres'sure Safety In)ection redundant flow paths to the Reactor Coolant System Hot Legs.

D RELIEP REQUESTED Relief is requested from exercising during normal plant operation.

ED BASIS POR RBLZEP These valves are required by Technical Specifications to be closed and locked out at the breaker during plant operation.

0 The positioned testing of these valves during plant operation, coupled with the failure of valve *-874A or *-

874B, could sub)ect the Safety Injection System to pressures in excess of its design pressures.

P AMERNMIVB TESTING These valves will be tested during cold shutdowns.

6 ~ IMPLEMENTATION SCHEDULE SECOND INSPECTION INTERVAL 105

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TURKEY POINT UNIT NO ~ 3/4 DATE:12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 RELZEP REQUEST NO 7 A. COMPONENT/SYSTEM SAFETY INJECTION VALVE IDENTIFICATION NUMBER CATEGORY CLASS

-876A A/C

-876B A/C

-876C A/C B ~ SECTZON XZ REQUIREMENTS IWV-3520 C FUNCTION Provides flow from the low pressure safety injection to the cold legs of the Reactor Coolant system. These valves also perform a pressure isolation function. (See Relief Request

<<Various number 3<<)

D RELIEF REQUESTED Relief 'is requested from testing during normal plant'peration.

ED BASZS POR RELIEP These valves cannot be tested during operation because the Low Pressure Safety Injection pumps do not develop sufficient discharge head to establish a flow path to the Reactor Coolant System.

PE ALTERNATIVE TESTING These valves will be tested during cold shutdowns. Valves *-

876B and *-876C are tested together since their parallel lines do not contain isolation valves. In order to verify that these two valves function properly additional inspections will be performed on these valves as described in Relief Request number 22.

G. IMPLEMENTATION SCHEDULE SECOND INSPECTION INTERVAL 106

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TURKEY POINT UNIT NO. 3/4 DATE 12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION-'

RELIEF REQUEST NO, 8 A COMPONENT/SYSTEM SAFETY INJECTION VALVE IDENTIFICATION NUMBER CATEGORY CLASS

-876D C

-876E C BISECTION XZ REQUIREMENTS IWV-3520 C FUNCTION Provides flow from the alternate Low Head Safety Injection to the cold legs of the Reactor Coolant system. Also performs a pressure isolation function (see Relief Request "Various number 3").

D. RELZEP REQUESTED Relief is requested from testing during normal plant operation.

ED BASIS FOR RELIEP These valves cannot be tested during operation because the Low Pressure Safety Injection pumps do not develop sufficient discharge head to establish a flow path to the Reactor Coolant System.

Po ALTERNATIVE TESTING These valves will be tested during cold shutdowns when the RCS is depressurized and vented and during each refueling outage. These valves are tested together, since their parallel lines do not contain isolation valves. In order to verify that these valves function properly additional inspections will be performed on these valves as described in Relief Request number 22.

6 o IMPLEMENTATION SCHEDULE SECOND INSPECTION INTERVAL 107

0'0 J ~

TURKEY POINT UNIT NO. 3/4 DATE: 12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 RELIEF REQUEST NO 9 A. COMPONENT/SYSTEM SAFETY INJECTION VALVE IDENTIFICATION NUMBER CATEGORY CLASS

-875A A

-875B A

-875C A B ~ SECTION XZ REQUIREMENTS IWV-3520 CD FUNCTION Provides flow from the Accumulator Safety Injection System, High Pressure Safety Injection System, and Low Pressure Safety Injection System to the Reactor Coolant System Cold Legs. Also perform a Pressure Isolation function.(. see Relief Request,"Various number 3")

D RELIEF REQUESTED Relief is requested from testing during normal plant operation.

ED BASIS FOR RELIEF These valves cannot be tested during operation because neither the High Pressure Safety Injection nor the Low Pressure Safety Injection pumps develop sufficient discharge head to establish a flow path to the Reactor Coolant System.

P. ALTERNATIVE TESTING These valves will be part stroke tested during cold shutdowns. Valves *-875B, *-875C, which are in series with valves *-876B, and *-876C respectively are all tested together since the parallel lines associated with each set of valves cannot be isolated from each other. In order to verify that valves *-875B, *-875C function properly, additional inspections will be performed on these valves as described in Relief Request number 22. Valve 875A will also be inspected per Relief Request number 22 since the cold shutdown test is only a part - stroke test.

Go IMPLEMENTATION SCHEDULE SECOND INSPECTION INTERVAL 108

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TKGKY POINT UNIT NO. 3/4 DATE:12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 RELIEP REQUEST NO ~ 10 A. COMPONENT/SYSTEM SAFETY INJECTION VALVE ZDENTZFZCATZON NUMBER CATEGORY CLASS MOV-878A B 2 MOV-878B B 2 B ~ SECTION XZ REQUIREMENTS IWV-3410 C. FUNCTION Provides a flow path to either Unit 3 or 4 with any combination of two of the four High Pressure Safety Injection pumps to the Reactor Coolant System of either unit. Normally open; closed following an accident once the units SI Pumps are verified to be operating.

RELZEP REQUESTED t

D Relief is requested from testing during normal plant operation.

ED BASIS POR RELZEP Four (4) High Pressure Safety Injection pumps are required to be operable for either dual unit operation or single unit operation. Failure of either valve in the non-open position, while testing during either dual unit operation, or single unit, operation would isolate two of the required High Pressure Safety Injection syatem to support a LOCA on the accident unit.

Po ALTERNATIVE TESTING These valves will be tested during cold shutdowns.

G IMPLEMENTATION SCHEDULE SECOND INSPECTION INTERVAL 109

J l~

TUEL(EY POINT UNIT NO. 3/4 DATE 12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 RELZEP REQUEST NO+ ll A. COMPONENT/SYSTEM SAFETY INJECTION VALVE IDENTIFICATION NUMBER CATEGORY CLASS MOV-*-864A MOV-*-864B BISECTION XZ REQUIREMENTS IWV-3410 CD PUNCTZON provides the flow path from the Refueling Water Storage Tank to the associated High Pressure Safety Injection pumps, Low pressure Safety Injection pumps, Containment Spray pumps.

DE RELIEP REQUESTED Relief is requested from exercising during normal plant:

operation.

E~ BASIS POR RELIEP e These valves are to be positioned plant operation.

required by Plant Technical Specifications open and the breakers locked-out during The failure of either of these valves in the non-open position, by testing during plant operation, would result in a total loss of system function for the associated Containment Spray System and Low Pressure Safety Injection System. Further, this could jeopardize the ability of the associated High Pressure Safety Injection pumps to support LOCA.

The failure of either of these valves in the non-open position, by testing during cold shutdown of the associated unit, could jeopardize the ability of the associated High Pressure Safety Injection pumps to support a LOCA on the operating unit.

PE ALTERNATIVE TESTING These valves will be tested during refueling shutdown of the associated unit.

6 ~ IMPLEMENTATION SCHEDULE SECOND INSPECTION INTERVAL 110

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TURKEY POINT UNIT NO ~ 3/4 DATE: 12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 RELZEP REQUEST NO. 12 A. COMPONENT/SYSTEM SAFETY INJECTION VALVE IDENTIFICATION NUMBER CATEGORY CLASS MOV-*-862A B MOV-*-862B B BISECTION XZ REQUIREMENTS IWV-3410 CD PUNCTZON Provides the flow path from the Refueling Water Storage Tank to the Low Pressure Safety Injection pumps.

Do RELIEP REQUESTED Relief is requested from exercising during normal plant.-

operation.

ED BASIS POR RELZEP These valves are required by Plant Technical Specifications to be positioned open and the breakers locked-out during plant operation.

The failure of either of these valves in the non-open position, by testing during plant operation, would result in a total loss of the Low Pressure Safety Injection System function.

PE ALTERNATIVE TESTING These valves will be tested during cold shutdowns.

G. IMPLEMENTATION SCHEDULE SECOND INSPECTION INTERVAL 111

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TURKEY POINT UNIT NO ~ 3/4 DATE:12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 RELIEP REQUEST NO ~ 13 A COMPONENT/SYSTEM SAFETY INJECTION VALVE IDENTIFICATION NUMBER CATEGORY CLASS SV-*-2905 B SV-*-2906 B SV-*-2907 B SV-*-2908 B SV-*-2909 B SV-*-2910 B B ~ SECTION XZ REQUIREMENTS IWV-34 10 IWV-33 00 C~ P UNCTION provides for redundant flow paths. from the operating Containment Spray Headers to the associated Emergency:

Containment Filter.

D RELZEP REQUESTED Relief is requested from exercising during normal plant operation and valve position indication verification.

ED BASIS POR REL1EP These redundant, self -contained, completely enclosed solenoid valves have no external valve position indicators.

Therefore, valve position verification is impractical.

Functional testing of these redundant valves by placing the containment spray system in operation would result in dousing the filters and other components located inside the containment building. Testing these valves by connecting an external water source to the containment spray header would also result in dousing the filters and other components located inside the containment building.

P. ALTERNATIVE TESTING These redundant valves will be tested by connecting an external air supply with sufficient air pressure to verify the main disk moves to the open position.

These valves will be tested during refueling shutdowns.

G. IMPLEMENTATZON SCHEDULE SECOND INSPECTION INTERVAL 112

. ~

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TURKEY POINT UNIT NO. 3/4 DATE: 12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 RELZEP REQUEST NO. 14 A. COMPONENT/SYSTEM SAFETY INJECTION VALVE IDENTIFICATION NUMBER CATEGORY CLASS

-2918 C

-2921 C

-2919 C

-2922 C

-2920 C

-2923 C

-890A C

-890B C B ~ SECTION XZ REQUIREMENTS IWV-3520 C. FUNCTION r

provides flow from Containment Spray spray pumps to:

Containment Spray header and onto the Emergency Containment Filters.

D. RELZEP REQUESTED Relief is requested from testing during normal plant operation.

ED BASIS POR RELZEP Functional testing of these redundant valves by placing the containment spray system in operation would result in dousing the components located inside the containment building. Testing these redundant valves by connecting an external water source to the containment spray system would also result in dousing the components located insid e the containment building.

F ~ ALTERNATIVE TESTZNO Each of these redundant check valves will be disassembled to inspect the valves internals and to physically verify the valves freedom of motion to the open and closed position, at least once each 120 month Inservice Inspection Interval.

These valves will be grouped by size, type and function. One valve in each group will be inspected during each refueling shutdown. Any problems found during this inspection would be cause for inspecting all other valves in the group. This provides for an inspection og at least one valve in each group during refueling shutdowns over the 120 month 113

0 I

TURKEY POINT UNIT NO. 3/4 DATE:12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 RELIEF REQUEST NO. 14 CONTINUED Inservice Inspection Interval.

6 ~ IMPLEMENTATION SCHEDULE SECOND INSPECTION INTERVAL e

114

IO ~

I )

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0

TURKEY POINT UNIT NO. 3/4 DATE:12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 RELIEP REQUEST NO+ 15 A. COMPONENT/SYSTEM SAFETY INZECTION VALVE IDENTIFICATION NUMBER CATEGORY CLASS

-874A

-874B B.SECTION XI REQUIREMENTS IWV-3520 C. FUNCTION Provides High Pressure Safety Injection flow from the alternate High Head Safety Injection to Hot Legs. These valves also perform a Pressure Isolation function (see Relief Request, " Various number 3").

D RELIEF REQUESTED Relief is requested from testing during normal plant operation.

ED BASIS FOR RELZEP These valves cannot be tested during plant operation because the High Pressure Safety Injection pumps do not develop sufficient discharge head to establish a flow path to the Reactor Coolant System.

Further, testing of these valves during cold shutdown is impractical since't could subject the Reactor Coolant System to conditions exceeding Pressure-Temperature limits.

Physical inspection of these valves is impractical due to their design which would require valve replacement after dissassembly.

F ~ ALTERNATIVE TESTING These valves will be tested .'uring refueling shutdowns.

Sufficient flow will be passed through these valves demonstrating that the required safety function is accomplished. The flow required to demonstrate the safety function will be based on a written evaluation being prepared by the NSSS vendor.'.

IMPLEMENTATION SCHEDULE SECOND INSPECTION INTERVAL 115

P Af A

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TURKEY POINT UNIT NO. 3/4 DATE: 12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION- 1 RELIEP REQUEST NO+ 16 A COMPONENT/SYSTEM SAFETY INJECTION VALVE IDENTIFICATION NUMBER CATEGORY CLASS

-873A A/C

-873B A/C

-873C A/C B ~ SECTION XZ REQUIREMENTS IWV-352 0 C~ PUNCTION Provide flow from the High Head Safety Injection System to the Reactor Coolant System Cold Legs. Also perform a Pressure Isolation function. (see Relief Request,"Various number 3")

D RELZEP REQUESTED Relief is requested from testing during normal plant operation.

ED BASIS POR'RELIEP These valves cannot be tested during operation because the High Pressure Safety Injection pumps do not develop sufficient discharge head to establish a flow path to the Reactor Coolant System.

Further, testing of these valves during cold shutdown is impractical since it could subject the Reactor to conditions exceeding Pressure-Temperature limits.

PE ALTERNATIVE TESTZNQ These valves will be tested during refueling shutdowns.

6 ~ IMPLEMENTATION SCHEDULE SECOND INSPECTION INTERVAL 116

f S ~

TUREKY POINT UNIT NO. 3/4 DATE:12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION- 1 RELZEP REQUEST NO+ 17 A. COMPONENT/SYSTEM SAFETY INJECTION VALVE IDENTIFICATION NUMBER CATEGORY CLASS

-875D C

-875E C

-875F C B ~ SECTION XZ REQUIREMENTS IWV-352 0 C~ PUNCTZON Provide flow from the Accumulator Safety Injection system to the Reactor Coolant system cold legs.

D. RELZEP REQUESTED r

Relief is requested from testing during normal plant-operation.

ED BAS1S POR RELIEP These valves cannot be tested during operation because the Accumulator pressure is insufficient differential pressure required to establish toa flow provide the path to the Reactor Coolant System.

Further, testing of these valves during cold shutdown is impractical since it could subject the Reactor Coolant System to conditions exceeding Pressure-Temperature limits.

P ALTERNATIVE TESTING These valves will be part stroke tested during refueling shutdowns. In addition these valves will be inspected per Relief Request number 22.

6 IMPLEMENTATION SCHEDULE SECOND INSPECTION INTERVAL 117

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DATE 12-12-88 SECOND TEN- INSERVICE TESTING PR RAM REVISION: 1 RELIEP REQUEST NO+

Ao COMPONENT/SYSTEM FETY INJECTION VALVE IDENTIFICXTION BER CATEGOR S BISECTION XZ REQUIRE NTS C PUNCTZON DE RELIEP REQUESTED E~ BASIS POR RELIEP P. ALTERNATIVE TBSTI 6 ~ IMPLEMENTATION SC 118

0 l9 fJ

TURKEY POINT UNIT NO. 3/4 DATE:12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 RELZEF REQUEST NO ~ 19 A. COMPONENT/SYSTEM SAFETY INJECTION VALVE IDENTIFICATION NUMBER CATEGORY CLASS 3-879A C 3-879B C 4-879C C 4-879D C B. SECTION XZ REQUIREMENTS IWV-3520 CD FUNCTION Provides flow from the Associated High Head Safety Injection System Pump to the Reactor Coolant system.

DE REL1EF REQUESTED Relief is requested from exercising during normal plant operation.

ED BASIS FOR RELIEF These valves .cannot be tested during plant operation because the High Pressure Safety Injection System Pumps do not develop sufficient discharge head to establish a flow path to the Reactor Coolant System.

Further, testing of these valves during cold shutdown is impractical since it could subject the Reactor Coolant System to conditions exceeding Pressure-Temperature limits.

F. ALTERNATIVE TESTING These check valves will be Full Stroke Exercised during refueling shutdowns.

In addition, these check valves will be part strok exercised quarterly during the performance of associated pump tests with flow through the High Pressure Safety Injection System test line.

6 ~ IMPLEMENTATION SCHEDULE SECOND INSPECTION INTERVAL 119

DATE 12-12-88 SECOND TEN- INSERVICE TESTING RAM REVISION: 1 RELZEP REQUEST NO.

Ao COMPONENT/SYSTEM FETY INJECTION VALVE IDENTIFICATION BER CATEGOR SS BISECTION XZ REQUIRE Co PUNCTZON D. RELZEP REQUESTED ED BASIS POR RELZEP PE ALTERNATIVE TESTZ 6.'IMPLEMENTATION S 120

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TURKEY POINT UNIT NO. 3/4 DATE:12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REV1SION: 1 RELIEF REQUEST NO ~ 21 A. COMPONENT/SYSTEM SAFETY INJECTION VALVE IDENTIFICATION NUMBER CATEGORY CLASS MOV-*-856A B MOV-*-856B B BISECTION XZ REQUIREMENTS IWV-3410 C. FUNCTION Isolation valves for High Pressure Safety Injection System test line Return to the Refueling Water Storage Tank (RWST).

D. RELIEF REQUESTED Relief is requested from exercising during normal plant operation.

ED BASIS FOR RELIEF The failure of either of these valves in the non-open position, by testing during either dual unit operation or single unit operation, would result in the isolation of the minimum flow recirculation from at least two High Pressure Safety Injection pumps. The isolation of the minimum recirculation flow path, concurrent with a Safety Injection Signal and High Pressure in the reactor coolant system, would result in damage to the associated High Pressure Safety Injection pumps.

F. ALTERNATIVE TESTING These valves will be tested during refueling shutdowns of the associated unit when the High Pressure Safety Injection System pumps are aligned to the RWST of the operating unit.

G. IMPLEMENTATION SCHEDULE SECOND INSPECTION INTERVAL 121

~ 5 TURKEY POINT UNIT NO. 3/4 DATE:12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 RELIEF REQUEST NO ~ 22 A. COMPONENT/SYSTEM SAFETY INJECTION VALVE IDENTIFICATION NUMBER CATEGORY CLASS

1. *-876B A/C LOW HEAD SAFETY ZNJ 2'. *-876C A/C LOW HEAD SAFETY INJ

3. ,*-875A A/C LOW HEAD SAFETY INJ

4. *-875B A/C LOW HEAD SAFETY INJ

5. *-875C A/C LOW HEAD SAFETY INJ

6. *-876D A/C ALT LOW HEAD SI

7. *-876E A/C ALT LOW HEAD SI

8. *-87SD C ACCUMULATOR

9. *-875E C DISCHARGE

10. *-875F C CHECK VALVES BISECTION XZ REQUIREMENTS IWV-3520 CD FUNCTION Valves 1 through 12 provide flow from the accumulator.

Safety Injection system and High /Low and alternate Safety Injection systems to the Hot and Cold legs of the Reactor Coolant system.

D. RELIEF REQUESTED Relief is requested from exercising during normal plant operation. Full stroke verification is also not possible alternate tests proposed in Relief Request numbers 7, 8, per 9, and 17.

E. BASIS FOR RELIEF As indicated in Relief Request numbers 7, 8, 9 and 15, check valves *-876B and C are tested together since the two parallel lines associated with these valves do not contain individual Isolation valves.

Valves *-875B and C, which are in series with *-876B and C respectively, are also tested together since their two parallel lines do not contain individual isolation valves.

One other set of valves in this system, *-876D and E is also tested together due to similar Lack of isolation valves.

In order to reliably test each valve major system modifications would be required at a significant cost.

122

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TURKEY POINT UNIT NO. 3/4 DATE:12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 RELIEF REQUEST NO. 22 CONTINUED Check valves *-875D, E, and F are only part stroke tested during refuelings and *-875A, is only part stroke tested during cold shutdowns. In order to full stroke test these valves Major system modifications would be required at significant cost to FPL.

F. ALTERNATIVE TESTING All valves included in this Relief Request are currently tested as described in Relief Requests 7, 8, 9, and 17.

In addition, in order to verify full stroke capability each valve will be disassembled to inspect the valves internals and to physically verify the valves freedom of motion to the open and closed position, at least once each 120 month Inservice Inspection Interval. These valves will be grouped by size, type and function. One valve in each group will be inspected during each refueling shutdown. Any problems found during this inspection would be cause for inspecting all other valves in the group. This provides inspection of at least one valve in each group during Refueling Shutdowns, over the 120-Month Inservice Inspection Interval.

G~ IMPLEMENTATION SCHEDULE SECOND INSPECTION INTERVAL e

123

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POINT UNIT NO. 3/4 DATE: 12-12-88 SECOND TEN- INSERVICE TESTING P RAM REVIS ION: 1 RELZEP REQUEST NO ~

A. COMPONENT/SYSTEM PLING VALVE IDENTIFICATION BER CATEGOR SS BISECTION XI REQUIRE NTS CD PUNCTZON D RELZEP REQUESTED E~ BASIS FOR RELIEF P o ALTERNATIVE TESTZ 6 IMPLEMENTATION S DU 124

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TURKEY POINT UNIT NO. 3/4 DATE:12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 RELZBP REQUEST NO ~ 2 A. COMPONENT/SYSTEM SAMPLING VALVE IDENTIFICATION NUMBER CATEGORY CLASS SV-*-6427A A SV-*-6427B A SV-*-6428 A B ~ SECTION XZ REQUIREMENTS IWV-3300 CD PUNCTZON Provides the flow path from the Reactor Coolant System to the Sample System.

D~ RELZEP REQUESTED Relief is requested from valve position indication verification.

ED BASIS POR RBLZBP 0 These have no self contained, completely enclosed solenoid valves external valve position indicators. Therefore, observations of valve position is impractical.

PE ALTERNATIVE TESTZNG These valves will be tested by connecting an external air supply with sufficient air pressure to verify the main disk moves to the open position or by verifying sample flow at least once every 2 years.

Go IMPLEMENTATION SCHBDULB SECOND INSPECTION INTERVAL 125

TURKEY POINT UNIT NO. 3/4 DATE: 12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 RELZEP REQUEST NO 1 A COMPONENT/SYSTEM MAIN STEAM VALVE IDENTZFXCXTZON NUMBER CATEGORY CLASS POV-*-2604 C 2 POV-*-2605 C 2 POV-*-2606 C 2 B SECTION XZ REQUIREMENTS IWV-3520 C PUNCTION Provides the flow path from the associated steam generator to the main steam line header.

D RELZEP RE{}VESTED Relief is requested from exercising these valves during..

normal plant operation.

ED BASIS POR RELIEF Testing any one of these valves during plant operation would isolate the associated steam generator from the main steam line header which would result in a reactor trip.

P. ALTERNATIVE TESTING These valves will be tested during cold shutdown.

6. IMPLEMENTATION SCHEDULE SECOND INSPECTION INTERVAL 126

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TURKEY POINT UNIT NO. 3/4 DATE:12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 RELZBP REQUEST NO 2 A. COMPONENT/SYSTEM MAIN STEAM VALVE IDENTIFICATION NUMBER CATEGORY CLASS

-004 C

-005 C

-006 C B. SECTION XI REQUIREMENTS IWV-352 0 C~ P UNCTION provides the flow path from the associated steam generator to the main steam line header.

D RELZBP REQUESTED Relief is requested from exercising these valves during..

normal plant operation.

ED BASIS POR RBLZEP The design, fabrication, arrangement, and installation of this valve does not provide for testing this valve.

PE ALTERNATIVE TESTZN6 Each of these check valves will be disassembled, to inspect the valve internals and to physically verify freedom of motion in the open and closed position, at least once each

'20 month Inservice Inspection will be performed during refuelingInterval. This inspection shutdowns. Any. problems found during this inspection would be cause for inspecting the other check valves.

Q. IMPLEMENTATION SCHBDULE SECOND INSPECTION INTERVAL 127

Y POINT UNIT NO. 3/4 DATE:12-12-88 SECOND TEN- AR INSERVICE TESTING P RAM REVISION: 1 RELZEP REQUEST NO+

Ao COMPONENT/SYSTEM NDENSATE and F TER VALVE IDENTIFICATIO BER CATEGOR SS

"'3 a C

B.SECTION XZ REQUIRE PUNCTZON I

Do RELZEP REQUESTED ED BASIS POR RELZEP PE ALTERNATIVE TESTZ G. IMPLEMENTATION S DU 128

Y POINT UNIT NO. 3/4 DATE'- 12-12-&8 SECOND TEN- INSERVICE TESTING PR RAM REVISION: 1 RELZBP REQUEST NO A COMPONENT/SYSTEM NDENSATE and F TER VALVE IDENTIFICATION BER CATEGOR B ~ SECTZON XZ REQUZRE C PUNCTZON D RELZBP REQUESTED ED BASZS POR RBLZEP P ALTERNATIVE TESTZ 6>> IMPLEMENTATION S DUKE e 129

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TURKEY POINT UNIT NO. 3/4 DATE:12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION- 1 RELZEP REQUEST NO ~ 3 VALVE IDENTIFICATION NUMBER CATEGORY CLASS CV-*-2900 CV-*-2901 CV-*-2902 BISECTION XZ REQUIREMENTS IWV-3520 C. PUNCTZON prevents reverse flow from the associated steam generator to the feedwater system.

D RELZEP REQUESTED Relief is requested from exercising these valves during normal plant operation.

ED BASIS POR RELZEP Testing anyone of these valves, during plant operation would cause an interruption of feedwater flow to the associated steam generator; thereby, placing the plant in an unsafe mode of operation.

P. ALTERNATIVE TESTING These valves will be. tested during cold shutdown.

Go IMPLEMENTATION SCHEDULE SECOND INSPECTION INTERVAL 130

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TURKEY POINT UNIT NO. 3/4 DATE 12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 RELZEP REQUEST NO 4 COMPONENT/SYSTEM CONDENSATE and FEEDWATER VALVE IDENTIFICATION NUMBER CATEGORY CLASS CV-*-2816 B CV-*-2817 B CV-~-2818 B CV-*-2831 B CV-*-2832 B CV-~-2833 B B ~ SECTZON XI REQUIREMENTS IWV-34 10 C. P UNCTION Provide a flow path from the Auxiliary Feedwater Pump Discharge Header to Steam Generator *A, *B, or *C.

D RELZEP REQUESTED Relief is requested from stroke time testing of these valves during normal plant operation.

E~ BASIS POR RELIEP These valves are flow controlled modulating valves, therefore, valve stroke-time testing of this individual component is not essential to fulfill their safety related function. The valve safety function of modulating to the required open position to deliver flow to each steam generator is verified monthly in performance of the AFW system operability test.

P o ALTERNATIVE TESTING Exercising these valves monthly will demonstrate that the moving parts of the valve function satisfactorily. The integrated system test for all components within AFW will verify that the control valves perform .their safety function in the required time.

Go IMPLEMENTATION SCHEDULE SECOND INSPECTION INTERVAL 131

0

TURKEY POINT UNIT NO. 3/4 DATE:12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 CHANGE: A DATE:08-17-89 RELIEF REQUEST NO ~ 5 A. COMPONENT/SYSTEM CONDENSATE and FEEDWATER VALVE IDENTIFICATION NUMBER CATEGORY CLASS FCV-*-478 B FCV-*-488 B FCV-*-498 B FCV-*-479 B FCV-*-489 B FCV-*-499 B B ~ SECTION XI REQUIREMENTS IWV-3410 CD FUNCT10N The Feedwater flow Control valves and Bypass Feedwater flow Control valves must isolate Feedwater to Steam Generators in response to a Main Steam Line Break accident and receive signals to do so in response to changing system parameters.

D>>~ RELIEF REQUESTED Relief is requested from stroke time testing of these valves

~

during normal plant operation.

ED BASIS FOR RELIEF Testing any of these valves during plant operation would cause interruption of Feedwater to the Steam Generators followed by Steam Generator level transients and possible Reactor trip. This test is impractical during plant operation.

F ALTERNATIVE TESTING These valves will be tested during Cold Shutdowns.

G>> IMPLEMENTATION SCHEDULE SECOND INSPECTION INTERVAL 132

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TUEOCEY POINT UNIT NO. 3/4 DATE: 12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 RBLIBP REQUEST NO+ 6 A. COMPONENT/SYSTEM CONDENSATE and FEEDWATER VALVE IDENTIFICATION NUMBER CATEGORY CLASS SV-*-6275 A-1 SV-*-6275 B-1 SV-*-6275 C-1 BISECTION XZ REQUIREMENTS IWV-3300 C. PUNCTZON These valves are the bypass blowdown isolation valves. They Isolate on a Phase "A" containment Isolation signal.

D. RELIEF REQUESTED Relief is requested from valve position indication..

verification.

E BASIS POR RBLZEP These 0.75 inch Solenoid Operated Globe valves are self contained, completely enclosed valves. They have no external valve position indicators. Due to these considerations, It is impractical to observe valve position.

P. ALTERNATIVE TESTING These valves will be exercise tested to verify their operability. This testing includesquarterly stroke timing to the closed position and is conducted often enough to be able to detect any anomalies in remote position indication.

G. ZMPLEMBNTATZON SCHEDULE SECOND INSPECTION INTERVAL 133

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TURKEY POINT UNIT NO. 3/4 DATE:12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 RELZEP REQUEST NO+ 1 A COMPONENT/SYSTEM INSTRUMENT AIR (LUBE OIL, SERVICE AND INSTRUMENT AIR)

VALVE IDENTIFICATION NUMBER CATEGORY CLASS

-40-336 AC

-40-340A AC B ~ SECTION XZ REQUIREMENTS IWV-3520 C FUNCTION prevents reverse flow from instrument air system inside containment, to the Instrument Air system located outside containment.

Do RELIEP REQUESTED Relief is requested from exercising these valves during.

normal plant operation.

E~ BASIS POR RELIEP Testing these valves during plant operation would interrupt the instrument air supply to the components located inside containment that require instrument air for proper operation; thereby, placing the plant in an unsafe mode of operation.

Testing either of these valves during cold shutdown would interrupt the instrument air supply to the components located inside containment that require instrument air to maintain the plant in a safe shutdown condition; thereby, placing the plant in an unsafe mode of operation.

PE ALTERNATIVE TESTING These valves will be tested at least once every 2 years.

G. IMPLEMENTATION SCHEDULE SECOND INSPECTION INTERVAL 134

0

TURKEY POINT UNIT NO. 3/4 DATE:12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 RELIEP REQUEST NO+ 1 A COMPONENT/SYSTEM DIESEL OIL VALVE IDENTIFICATION NUMBER CATEGORY CLASS SV-3522A B SV-3522B B B.SECTION XZ REQUIREMENTS IWV-3413 C. PUNCTION Provides the flow path from the emergency diesel-Generator Diesel Oil Day Tanks to the skid-mounted Diesel Oil Tank.

D RELIEP REQUESTED Relief is requested from stroke time. measurement for these valves.

ED BASIS POR RELIEP These self-contained, completely enclosed solenoid valves have no external valve position indicators. Therefore, stroke-time measurements and valve position verification is impractical.

P. ALTERNATIVE TESTING An increase in level in the skid-mounted Diesel Oil Tank while exercising these valves quarterly will demonstrate that the moving parts of the valve function satisfactorily.

6 IMPLEMENTATION SCHEDULE SECOND INSPECTION INTERVAL 135

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TURKEY POINT UNIT NO ~ 3/4 DATE:12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 RELIEF REQUEST NO ~ 2 A. COMPONENT/SYSTEM DIESEL OIL VALVE IDENTIFICATION NUMBER CATEGORY CLASS CV-2046A CV-2046B BISECTION XI REQUIREMENTS IWV-3413 CD PUNCTION Provides the flow path from the emergency diesel-Generator Diesel Oil Transfer Pump Discharge Header to the Diesel Oil Tanks.

D. RELZBP REQUESTED Relief is requested from stroke time testing.

8 ~ BASIS FOR RELIEP These Solenoid Powered Control Valves are actuated from level switches located on the associated Day Tank. The valves have no remote position indication, therefore, stroke time measurements and valve position verification is impractical.

F. ALTERNATIVE TESTING An increase in level in the Diesel Oil Tank while exercising these valves quarterly will demonstrate the moving parts of the valve function satisfactorily.

The Day Tanks have sufficient capacity to allow for maintenance on the valve, if the valve should fail closed.

G~ IMPLEMENTATION SCHEDULE SECOND INSPECTION INTERVAL 136

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TtHGCEY POINT UNIT NO. 3/4 DATE: 12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 RELIEP REQUEST NO ~ 3 A COMPONENT/SYSTEM DIESEL OIL VALVE IDENTIFICATION NUMBER CATEGORY CLASS SV-2051 A SV-2051 B B SECTION XZ REQUIREMENTS IWV-3413 CD PUNCTION Provides the flow path from the Diesel Oil Storage Tank to the Diesel Oil Day Tank.

D. RELZEP REQUESTED Relief is requested from stroke time t'.esting these valves.

ED BASIS POR REL1'EP These self-contained, completely enclosed solenoid valves have no external valve position indicators. Therefore, 0 F stroke-time measurements and valve position verification is impractical.

ALTERNATIVE TESTING An increase in level in the Diesel Oil Day Tank while exercising these valves quarterly will demonstrate the moving parts of the valve function satisfactorily.

Further, there is sufficient capacity in the Diesel Oil Day Tanks to allow for maintenance on the valve, should fail closed.

if the valve 6 IMPLEMENTATION SCHEDULE SECOND INSPECTION INTERVAL 137

~

TURKEY POINT UNIT NO. 3/4 DATE:12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 RELIEF REQUEST NO ~ 1 i

A COMPONENT/SYSTEM PRIMARY MAKE-UP AND CONTAINMENT COOLING WATER VALVE IDENTIFICATION NUMBER CATEGORY CLASS MOV-*-1417 MOV-*-1418 BISECTION XI REQUIREMENTS IWV-3410 C~ FUNCTION Provides the component cooling water supply (MOV-*-1407) and return (MOV-*-1408) flow paths for normal containment coolers, the control rod drive mechanism coolers, and the primary shield cooling coils.

D RELIEP REQUESTED Relief is requested from exercising these valves during Normal Plant operation.

ED BASIS FOR RELZEP Testing either of these valves during plant operation would cause interruption of cooling water to the normal containment cooler, the control rod drive mechanism coolers, and the primary shield cooling coils. This action could result in damage to the control rod drive mechanisms and associated equipment; thereby, placing the plant in an unsafe mode of operation.

PE ALTERNATIVE TESTING These valves will be tested during cold shutdowns.

Q. IMPLEMENTATION SCHEDULE SECOND INSPECTION INTERVAL 138

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TURKEY POINT UNIT NO. 3/4 'ATE:12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 RELZEP REQUEST NO+ 1 A. COMPONENT/SYSTEM CONTAINMENT VENTILATION VALVE IDENTIFICATION NUMBER CATEGORY CLASS HV-*-1 A HV-*-2 A PAHM-*-002A A B ~ SECTION XZ REQUIREMENTS IWV-3410 C P UNCT ZON Provides redundant flow paths to Post Accident Hydrogen Monitoring and Control System.

DE RELZEP REQUESTED Relief is requested from testing during normal plant:

operation.

ED BASIS POR RELZEP The failure of either of these valves in the non-closed position, by testing during 'plant operation, would result in a loss of containment integrity per Technical Specification (3.3) .

P. ALTERNATIVE TESTING These valves will be tested during cold shutdowns.

G IMPLEMENTATION SCHEDULE SECOND INSPECTION INTERVAL 139

fl TURKEY POINT UNIT NO. 3/4 DATE:12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 RELZEP REQUEST NO. 2 A. COMPONENT/SYSTEM CONTAINMENT VENTILATION VALVE IDENTIFICATION NUMBER CATEGORY CLASS HV-*-3 A HV-*-4 A PAHM-*-002b A B ~ SECTION XZ REQUIREMENTS IWV-34 10 CD PUNCTZON Provides redundant flow paths to Post Accident Hydrogen Monitoring and Control System.

D RELZEP REQUESTED r

Relief is requested from exercising these valves 'during:

normal plant operation.

ED BASIS POR RELZEP The failure of either of these valves in the non-closed position, by testing during plant operation, would result in a loss of containment integrity per Technical Specification (3.3) .

P. ALTERNATIVE TESTING These valves wil'l be tested during cold shutdowns.

Go IMPLEMENTATION SCHEDULE SECOND INSPECTION INTERVAL 140

TURKEY POINT UNIT NO. 3/4 DATE: 12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 RELIEF REQUEST NO+ 3 A. COMPONENT/SYSTEM CONTAINMENT VENTILATION VALVE IDENTIFICXTION NUMBER CATEGORY CLASS

-11-003 AC 2 BISECTION XZ REQUIREMENTS IWV-3520 C FUNCTION Prevents reverse flow from the containment atmosphere to the containment gas and particulate radioactivity detection system.

D. RELIEF REQUESTED Relief is requested from exercise tesging this valve during normal plant operation.

E. BASIS FOR RELIEF Plant Technical Specification 3.1.3 requires two independent systems to monitor reactor coolant system leakage; one of which has to be sensitive to radioactivity. Testing this valve during plant operation would cause an interruption of the Reactor Coolant System Leak Detection System which is sensitive toradioactivity.

Similarily, testing this, valve during cold shutdown would result in an interruption of the Detection System which is sensitive to radioactivity.

F ~ ALTERNATIVE TESTING These valves will be tested closed by seat leak testing at least once every 2 years.

G. IMPLEMENTATION SCHEDULE SECOND INSPECTION INTERVAL 141

TURKEY POINT UNIT NO. 3/4 DATE:12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 RELZEP REQUEST NO+

0 4

A. COMPONENT/SYSTEM CONTAINMENT VENTILATION VALVE IDENTIFICATION NUMBER CATEGORY CLASS PAHM-*-001A A 2 PAHM-*-001B A 2 B ~ SECTION XZ REQUIREMENTS IWV-34 10 C PUNCTION Provides redundant flow paths to Post Accident Hydrogen Monitoring and Control System.

Do RELZEP REQUESTED Relief is requested from exercise .testing these valves during normal plant operation.

ED BASIS POR RELIEP The failure of either of these valves in the non-closed position, by testing during plant operation, would result in a loss of containment integrity per Technical Specification (3.3) .

PE ALTERNATIVE TESTING These valves will be tested during cold shutdowns.

6. IMPLEMENTATION SCHEDULE SECOND INSPECTION INTERVAL 142

I TURKEY POINT UNIT NO. 3/4 DATE:12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 RELZEP REQUEST NO ~ 5 A. COMPONENT/SYSTEM CONTAINMENT VENTILATION VALVE IDENTIFICATION NUMBER CATEGORY CLASS SV-*-2911 A SV-*-2913 A SV-*-2912 A BISECTION XZ REQUIREMENTS IWV-3300 CD PUNCTZON Provides flow path from the containment atmosphere to the containment gas and particulate radioactivity detection system and return to containment.

Do RELIEP REQUESTED 4

Relief is requested from valve position indication verification.

ED BASIS POR RELZEP These self-co ntained, completely enclosed solenoid 'alves have .no external valve position indicators. Therefore, direct observation of valve position indication is impractical.

P. ALTERNATIVE TESTING These redundant valves will be tested by connecting an external air supply with sufficient air pressure to verify the main disk moves to the open position.

These valves will be tested during refueling shutdowns.

G IMPLEMENTATION SCHEDULE SECOND INSPECTION INTERVAL 143

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TURKEY POINT UNIT NO. 3/4 DATE:12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 RELZEP REQUEST NO+ 6 A COMPONENT/SYSTEM CONTAINMENT VENTILATION VALVE IDENTIFICATION NUMBER CATEGORY CLASS

-40-204 A HV-*-17 A B ~ SECTION XZ REQUIREMENTS IWV-34 10 C FUNCTION Provides the flow path for the Service Air Supply or the Hydrogen Recombiner Return to the containment.

Do RELZEP REQUESTED Relief is requested from exercise testing during normal plant operation.

ED BASIS POR RELZEP The failure of either of these valves in the non-closed position, by testing during plant operation, would cause a loss of containment integrity requiring a plant shutdown per Technical Specification (3.3).

P. ALTERNATIVE TESTING These valves will be tested during cold shutdowns.

Ge IMPLEMENTATION SCHEDULE SECOND INSPECTION INTERVAL 144

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TURKEY POINT UNIT NO. 3/4 DATE: 12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 RELIEF REQUEST NO. 7 A. COMPONENT/SYSTEM CONTAINMENT VENTILATION VALVE IDENTIFICATION NUMBER CATEGORY CLASS

-40-205 AC 2 BISECTION XZ REQUIREMENTS IWV-3520 C~ FUNCTION Prevents reverse flow from the containment atmosphere to the Service Air System located outside containment.

D. RELIEF REQUESTED Relief is requested from exercise testing during normal plant operation.

ED BASIS POR RELZEP The failure of this valve in the non-closed testing during plant operation, would cause position, a loss of by containment integrity requiring a plant shutdown per Technical Specification (3.3).

PE ALTERNATIVE TESTING This valve will be tested during cold shutdowns and leak tested at refueling shutdowns.

G. IMPLEMENTATION SCHEDULE SECOND INSPECTION INTERVAL 145

0

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TURKEY POINT UNIT NO. 3/4 DATE:12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 RELZEP REQUEST NO+ 8 A. COMPONENT/SYSTEM CONTAINMENT VENTILATION VALVE IDENTIFICXTION NUMBER CATEGORY CLASS POV-*-2600 A POV-*-2601 A POV-*-2602 A POV-*-2603 A B ~ SECTION XZ REQUZREMENTS IWV-34 10 C. PUNCT ION Containment Purge Air Supply (POV-*-2600 & POV-*-2601) and exhaust (POV-*-2602 & POV-*-2603) valves.

Do RELZEP REQUESTED Relief is requested from exercise testing during normal plant operation.

ED BASIS POR RELIEP The failure of any one of these valves in the non-closed position, by testing during plant operation, would result in a loss of containment integrity requiring a plant shutdown per Technical Specification (3.3).

P. ALTERNATIVE TESTING These valves will be tested during cold shutdowns.

C

6. IMPLEMENTATION SCHEDULE SECOND INSPECTION INTERVAL 146

P TURKEY POINT UNIT NO. 3/4 DATE: 12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 RELIEF REQUEST NO. 1 A. COMPONENT/SYSTEM VARIOUS VALVE IDENTIFICATION NUMBER CATEGORY CLASS VARIOUS VARIOUS VARIOUS BISECTION XZ REQUIREMENTS IWV-34 17 IWV-3427 IWV-3523 IWP-3230 CD PUNCTION VARIOUS D RELZEP REQUESTED See basis ED BASZS POR RELIEF Paragraph Nos. IWV-3417, IWV-3427, IWV-3523, and IWP-3230 prescribe actions to be taken, limiting time periods for actions to be completed, or limiting conditions for operability if certain conditions are not met. This could be in conflict with the PLant Technical Specifications. In addition, certain CODE definitions or terminology may be in conflict with the Plant Technical Specifications.

Fo ALTERNATIVE TESTING Corrective Action - Where a valve or pump fails to meet the requirements of the program and/or the reference CODE; the

- condition(s) shall be reviewed by the Plant Nuclear Safety Committee (PNSC) for disposition and determination of whether it involves an unreviewed safety question prior to commencing with plant startup or continuing with plant operation.

6 ZMPLEMENTATZON SCHEDULE SECOND INSPECTION INTERVAL 147

0 eg Q

TURKEY POINT UNIT NO. 3/4 DATE 12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 RELZEP REQUEST NO ~ 2 A. COMPONENT/SYSTEM VARIOUS VALVE IDENTIFICATION NUMBER CATEGORY CLASS CV-*-519B A 2 CV-*-522A A 2 CV-*-522B A 2 CV-*-522C A 2 HV-*-1 A 2 HV-*-3 A 2 CV-*-4659A A 2 POV-*-2601 A 2 POV-*-2603 A 2 CV-*-4668A A 2 MOV-*-860A A 2

-10-582 A 2 MOV-*-860B A 2 MOV-*-872 A 2 B ~ SECTION XZ REQUIREMENTS IWV-3423 IWV-3424 CD FUNCTION These valves provide for containment isolation.

Do RELZEP REQUESTED Relief is requested from seat leakage measurement requirements of IWV-3423, 3424.

ED BASIS POR RELIEF The containment isolation valves identified above are tested by pressurizing the piping or ducting between two or more valves installed in the associated containment penetration.

This vill result in performing the CODE Category A, valve seat leakage test in the reverse direction from that specified in IWV-3423, on one or more of the valves installed in the associated containment penetration.

P. ALTERNATZVE TESTING Continue to perform the CODE Category A valve seat leakage test by pressurizing the piping or ducting between two or more valves installed in the associated containment penetration.

148

TURKEY POINT UNIT NO. 3/4 DATE:12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 RELIEF REQUEST NO+ 2 CONTINUED Ge IMPLEMENTATION SCHEDULB SECOND INSPECTION INTERVAL 149

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TUEL(EY POINT UNIT NO. 3/4 DATE:12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 RELIEF REQUEST NO 3 A. COMPONENT/SYSTEM VARIOUS VALVE IDENTIFICATION NUMBER CATEGORY CLASS

-873A AC 2

-874A AC 2

-875A AC 2

-876A AC 2

-876D AC 2

-873B AC 2

-874B AC 2

-875B AC 2

-876B AC 2

-876E AC 2

-873C AC 2

-875C AC 2

-876C AC 2 B ~ SECTION XZ REQUIREMENTS IWV-3420 C FUNCTION These valves provide for reactor coolant pressure isolation between the High Pressure Safety Injection System, Low Pressure Safety Injection System, and Residual Heat Removal System.

D. RELIEF REQUESTED Relief is requested from leak test requirements of IWV-3420 E~ BASIS FOR RELIEF These valves are required to be tested in accordance with Plant Technical Specification 4.17.

F. ALTERNATIVE TESTING Continue testing these valves in accordance with Plant Technical Specification 4.17.

6 ~ IMPLEMENTATION SCHEDULE SECOND INSPECTION INTERVAL 150

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TUEGCEY POINT UNIT NO. 3/4 DATE: 12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 5, 0 10

~ CFR 50 APPENDIX J 5.1~ APPENDIX J TESTING primary reactor containments shall meet the containment leakage test requirements set forth in Appendix J. These tests requirements provide for periodic verification by tests of the leak-tight integrity of the primary reactor.

containment, and system and components which penetrate containment and the establishment of the acceptance criteria for such tests. The purpose of the tests are to assure that

a. leakage through the primary reactor containment and systems and components penetrating primary containment shall not exceed allowable leakage rate values as specified by FPL, and 10 CFR 50 Appendix J.

b. periodic surveillance of reactor containment penetrations and isolation valves is performed.

5 ~ 2 SEAT LEAKAGE Seat leakage test parameters are determined in accordance with FPL requirements.

i Seat leakage rates are based on air tests:

49.9 PSI = Delta P at Pa Where:

Pa = Accident Pressure 5.3 CONTAINMENT ISOLATION VALVES Containment isolation valve means any valve which is relied upon to perform a containment isolation function.

Table No. 5.1-1 through 5.1-3 provide a listing of those containment isolation valves tested to Appendix J,10 CFR 50 requirements.

151

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TURKEY POINT UNIT NO. 3/4 DATE:12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 TABLE NO ~ S ~ 1 CONTAINMENT ISOLATION VALVES CONTAINMENT SERVICE VALVE PENETRATION NUMBER(S)

NUMBER GAS ANALYZER SAMPLE PRT CV-*-516 SV-*-6385 NITROGEN SUPPLY TO PRT *-518

-519 PW SUPPLY TO PRT AND RCP CV-*-519A STANDPIPES CV-*-519B CV-*-522A CV-*-522B CV-*-522C SAMPLE PRZ

'V-*-95 SAMPLE PRZ STEAM SPACE LIQUID SPACE 1

CV.-*-956A CV-*-953 CV-*-956B 10 VENT & N2 SUPPLY FOR RCDT PCV-*-1014 CV-*-4658A CV<<*<<4658B

-4656 ALT. LOW HEAD SAFETY INZ. MOV-*-872 14 LETDOWN FROM REACTOR CV-+-200A COOLANT SYSTEM CV-*-200B CV-*-200C CV-*-204 15 CHARGING TO REACTOR HCV-*-121 COOLANT SYSTEM

333

-312C 16 POST ACCIDENT HYDROGEN HV-*-1 CONTROL SYSTEM HV-*-2 PAHM-*-002A 17 SIS TEST LINE *-895V 19A CONTAINMENT SPRAY SYSTEM MOV-*-880A

-890A 19B MOV-*-880B

-890B 152

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TUMMY POINT UNIT NO. 3/4 DATE: 12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 TABLE NO 5+i 2 CONTAINMENT ISOLATION VALVES CONTAINMENT SERVICE VALVE PENETRATION NUMBER(S)

NUMBER 20 REACTOR COOLANT SYSTEM SV-*-6427A (955A)

SAMPLE SV-*-6427B (955B)

SV-*-6428 (956C) 23 CONTAINMENT SUMP CV-*-2821 DISCHARGE CV-*-2822 24A RCP SEAL INJECTION SUPPLY *-298A 24B *-298B 24C *-298Ca 25 RCP SEAL LEAKOFF RETURN MOV-*-381 MOV-4-6386 29 INSTRUMENT AIR SUPPLY *-40-336

-40-340A 30 BREATHING AIR SYSTEM CV-*-6165

-BA-201 RCDT GAS ANALYZER SAMPLE CV-*-4659A CV-*-4659B 32 CONTAINMENT AZR SAMPLE SV-*-2912 RETURN *-11-003 PAHM-+-00 1B PAHM-*-001A 33 CONTAINMENT AZR SAMPLE SV-*-2911 SV-*-2913 34 POST ACCIDENT HYDRGEN HV-*-17 CONTROL SYSTEM 4-40-204

-40-205 35 CONTAINMENT PURGE SUPPLY POV-*-2600 POV-*-2601 36 CONTAINMENT PURGE EXHAUST POV-*-2602 POV *-2603 42 NITROGEN SUPPLY TO CV-*-855 ACCUMULATORS *-945E 153

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TURKEY POINT UNIT NO. 3/4 DATE:12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 TABLE NO ~ 5 ~ 1 3 CONTAINMENT ISOLATION VALVES CONTAINMENT SERVICE VALVE PENETRATION NUMBER(S)

NUMBER 47 PW SUPPLY TO WASH HEADER *-10-567

-10-582 52 RCDT PUMP DISCHARGE CV-*-4668A CV-*-4668B 51 PTN-4 53 PTN-3 POST ACCIDENT HYDROGEN HV-*-3 CONTROL SYSTEM HV-*-4 PAHM-*-002B 54A CONTAINMENT RECIRCULATION MOV-0-860A SUMP A AND B MOV-*-861A 54B MOV-*-860B MOV-*-86 1B 55 ACCUMULATOR SAMPLE CV-*-955C CV-*-955D CV-*-955E CV-*-956D 61B PRZ DEADWEIGHT TESTER *-2023

-2024 63 INSTRUMENT AIR BLEED CV-*-28 19 CV-*-282 6 65B ILRT TEST CONNECTION *-2025 65C ILRT TEST CONNECTION *-2026 154

TURKEY POINT UNIT NO. 3/4 DATE: 12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION- 1 6.0 REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVES Table No. 6.1 identifies those Reactor Coolant system pressure Isolation valves and the maximum allowable leakage rates for each of the valves listed.

155

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TURKEY POINT UNIT NO. 3/4 DATE '2-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 TABLE NO ~ 6 ~ I REACTOR COOLANT SYSTEM PRESSURE ZSOLATZON VALVES MAXIMUM (a) (b)

SYSTEM VALVE NUMBER ALLOWABLE LEAKAGE -gpm HIGH HEAD SAFETY INJECTZON LOOP A, HOT LEG *-874A 5.0 COLD LEG *-875A 5.0 COLD LEG *-873A 5.0 LOOP B, HOT LEG *-874B 5.0 COLD LEG *-875B 5.0 COLD LEG *-873B 5.0 LOOP C, COLD LEG *-875C 5.0 COLD LEG *-873C 5.0 RESIDUAL HEAT REMOVAL LOOP A, COLD LZG *-876A 5.0 4-876E LOOP B, COLD LEG *-876B 5.0

-876D 5.0 LOOP C, COLD LEG *-876C 5.0 3-876E 5.0 LOOP A, HOT LZG MOV-*-750 5.0 51 'OV-*-7

5.0 NOTES

MAXIMUM (a)(b) ALLOWABLE LZAKAGE - gpm (a) 1. Leakage rates less than or equal to 1.0 gpm are considered acceptable.

2. Leakage rates greater than 1.0 gpm but less than or equal to 5.0 gpm are considered acceptable measured if rate has not exceeded the previous test by an the latest amount that reduces the margin between measured leakage rate and the maximum permissible rate of 5.0 gpm by 504 or greater.

3. Leakage rates greater than 1.0 gpm but less than or equal to 5.0 gpm are considered unacceptable latest measured rate exceeded the rate determined by the if the previous test by an amount that reduces the margin

~ between measured leak rate and the maximum permissible rate of 5.0 gpm by 504 or greater.

4. Leakage rates ,greater than 5.0 gpm are considered unacceptable.

(b) Minimum differential test pressure shall be not less than 150 psid.

156

TURKEY POINT UNIT NO ~ 3/4 DATE: 12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 7.0 PIPING AND INSTRUMENTATION DIAGRAMS pumps a~d Valves that require inservice testing in accordance with IWP and IWV are referenced to the specific Plant piping and instrumentation diagrams. The Pump and Valve testing tables include the coordinates for locating each pump and valve included within this program.

The attached list includes those P & IDs that are applicable to the Pump and Valve Program.

157

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TURKEY POINT UNIT NO. 3/4 DATE: 12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 TABLE 7 ~ 1 PIPING 4 INBTRUMENTATION DRAWINGS DRAWING NUMBER REV NO. SHEETS TITLE 5610-M-420-3 8 3 CHEMICAL & VOLUME CONTROL SYSTEM (FPL NO. F-503184 7 5610-M-470-5 8 SAFETY INJECTION SYSTEM (FPL NO. E-503185 7 5610-M-450-57 9 AUXILIARY COOLANT SYSTEM (FPL NO F-503187

~ 7 COMPONENT COOLING 5610-M-450-57 9 AUXILIARY COOLANT SYSTEM (FPL NO. F-503188 7 COMPONENT COOLING 5610-M-500-27 9 WASTE DISPOSAL SYSTEM (FPL NO. F-503189 8 5610-M-410-91 7 REACTOR COOLANT SYSTEM (FPL NO. F-503191 6 5610-M-480-1 9 SAMPLING SYSTEM (FPL NO. F-503193 7 5610-M-450-53 8 AUXILIARY COOLANT SYSTEM (FPL NO. F-503194 6 RESIDUAL HEAT REMOVAL 5610-M-450-54 6 AUXILIARY COOLANT SYSTEM (FPL NO. F-503195 4 SPENT FUEL PIT COOLING SYSTEM 5610-M-1 14 STEAM SYSTEM (FPL NO. F-502027 14 5610-M-2 18 CONDENSATE AND FEEDWATER SYSTEM (FPL NO. F-502028 15 5610-M-4 18 LUBE OIL SERVICE AND INSTRUMENT AZR (FPL NO. F-502030 14 5610-M-5 17 CIRCULATING WATER, SALT WATER AND (FPL NO. F-502031 14 CHLORMATION SYSTEMS (INTAKE COOLING WATER SYSTEM 5610-M-7 10 DIESEL OIL (FPL NO. F-502033 8 5610-M-10 18 FIRE ~ PRIMARY MAKE UP~ CONTAINMENT (FPL NO. F-502036 14 COOLING WATER & CHEMICAL INJECTION 158

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TIMEY POINT UNIT NO ~ 3/4 DATE:12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 TABLE 7 ~ 1 PIPING fi INSTRUMENTATION DRAWINGS DRAWING NUMBER REU NO. SHEETS TITLE 5610-M-11 11 CONTAINMENT VENTILATION SYSTEM (FPL NO. F-502037 10 5610-M-12 9 CONTAINMENT AND RADWASTE DRAINS (FPL NO. F-502038 10 AND VENTS (5177-074-M-2 6 1 BREATHING AIR SYSTEMS NOTE: FPL draving number shovn in parentheses has been superseded by the architect engineer number.

159

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TURKEY POINT UNIT NO. 3/4 DATE: 12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 8.0 RECORDS 8.1 PUMP RECORDS IWP-6000 Records of Inservice Tests in accordance with IWP-6000 vill be of the developed and maintained ASME Boiler and Pressure Vessel Code.

8.1.1

SUMMARY

LISTING IWP-6210 A list of pumps shall be maintained to record the current status of the test program. When the quantities measured NQ 2 ',

during the test are within the acceptable range of Table Only the date of the successful test is required to be listed.

8.1.2 PUMP RECORDS IWP-6220 FPL shall maintain a record, vhich will include the following, for each pump covered by this program.

a. the manufacturer and the manufacturer's model and serial or other identification number.

b. a copy or summary of the manufacturer's acceptance report, if available. 'est 8.1.3 INSERVICE TEST PLANS IWP-6230 The test plans shall include the following:

a. the hydraulic circuit to be used

b. the location and type of measurement for each of the required test quantities

c. the, reference values (Table 2.1),'imits of Pi and Tb (Table 2.2), and any other values required.

8.1.4 RECORDS OF TESTS IWP-6240 The records shall include the following:

a. date of test

b. measured and observed quantities

c. identification of instruments used

'I

d. comparisons with allowable ranges of test values and analysis of deviations 160

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TURKEY POINT UNIT NO ~ 3/4 DATE: 12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION:

e. requirements for corrective. action

f. signature of the person or persons responsible for conducting and analyzing the test 8.1.5 RECORDS OF CORRECTIVE ACTION IWP-6250 The record shall include a summary of the corrections made and the subsequent inservice test and confirmation of operational adequacy, and the signature of the individual responsible for corrective action and verification of results.

8.2 VALVE RECORDS IWV-6000 8 ~ 2 ~ 1

SUMMARY

LISTING IWV-62 10 A list of valves status of shall be maintained to record the the test program.

current 8.2.2 PRESERVICE TESTS IWV-6220 Preservice test results and manufacturer's results shall be included in the documentation, functional'est When available.

8.2.3 TEST RESULTS IWV-6230 The record of test results shall include the dated signature of the person responsible for the action.

161

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TTHQXY POINT UNIT NO ~ 3/4 DATE:12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 9.0 INSERVICE TESTING PROGRAM

9. 1 PROGRAM PLAN TABLES 9.

1.1 DESCRIPTION

OP TABLES The Inservice Testing Program Tables for the Inservice testing of the major components of Florida Power and Light, Turkey Point Unit 3/4 Nuclear Power Station vill be in a format as described below:

9.1.2 The program has been divided into sections. Section nine (9), has been divided into two (2) sets of tables.

(See figure number 9.1 and 9.2) 9.2 PUMP AND VALVE PROGRAM TABLES The =Inservice Pump Testing tables will provide the following information:

9.2.1 PUMP TESTING TABLES PUMP NUMBERS - The pump number identification is a unique identification number assigned by the fabricator or the installer.

PUMP DESCRIPTION - The pump description is a brief description of the of the pump system.

CLASS - Identifies the Code Class of the pump P & ID NUMBER - Defines the piping and instrument drawing that the pump is on.

COORDINATES - Provides the coordinates on a particular P & ID that the pump is located.

TEST PARAMETERS - The next six (6) columns are included to provide the test parameters for the following SPEED, INLET PRESSURE, DIFFERENTIAL PRESSURE, FLOW RATE, VIBRATION and BEARING TEMPERATURE. These columns provide a yes or no remark under each column heading. The number next to the Y or N identifies the Relief Request associated with each parameter if applicable.

RELIEF REQUEST - Identifies by number the request for relief from the code requirements for a specific pump.

REMITS - This column is provided for input to any additional information applicable to that pump.

162

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TURKEY POINT UNIT NO. 3/4 DATE:12-12-88 SECOND TEN-YEAR ZNSERVICE TESTING PROGRAM REVISION: 1 FIGURE NUMBER 9 ~ 1 PLANT/UNIT INSERVICE TESTING PROGRAM REVISION NO PUMP TABLES DATE:

PAGE:

PUMP INLET DIFF FLOW BEAR NO. DESC CL COORD SPEED PRES PRES RATE VIB TEMP 1 2 3 4 5 6: 7: 8: 9 10:

1. PUMP IDENTIFICATION NUMBER

2. DESCRIPTION OF PUM5 SYSTEM

3. ASME CODE CLASS

4. COORDINATES FOR LOCATION OF THE PUMP ON THE DRAWING TEST PAEVMETERS ARE IDENTIFIED BY A YES OR NO UNDER EACH COLUMN..

EXAMPLE (Y:) Y~ YES, THE : FOLLOWED BY A NUMBER IS THE RELIEF REQUEST APPLICABLE TO THAT PAMAETER.

5- SPEED 6 ~ INLET PRESSURE 7 ~ DIFFERENTIAL PRESSURE 8 ~ FLOW RATE

9. VIBRATION

10. BEARING TEMPERATURE 11 REMARKS SECTION FOR ANY APPLICABLE ADDITIONAL INFORMATION 163

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TUEuCEY POINT UNIT NO ~ 3/4 DATE: 12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 9.2.2 VALVE TESTING TABLES The valve testing tables provide the following information:

P 6 ID NUMBER - Defines the piping and instrument drawing that the valve is on.

SYSTEM - Identifies the system that each valve is on VALVE NUMBERS - The valve number identification is a unique identification number assigned by the fabricator or the installer.

COORDINATES - Provides the coordinates on a particular P & ID where that. valve is located.

CLASS - Identifies the Code Class of the valve 1, 2, 3 CATEGORY - Identifies the valve category A-B-C (or combination of categories ACTIVE/PASSIVE - A OR P see Table No. 2.2 (IWV-3700-1 SIZE Denotes the size of the valve TYPE - Identifies the type of valve ( Globe, Gate, Check, Relief, Ball) etc.

SAFE - SAFETY S/CHK STOP CHECK DIAPH - DIAPHRAGM POWER - POWER ASSISTED BUTFY - BUTTERFLY ASS~T CHECK CHECK ACTUATOR TYPE - Defines the actuator type if applicable.

A/0 AIR OPERATOR MO ELECTRIC MOTOR OPERATOR SO - SOLENOID OPERATOR S/A - SELF ACTUATED NORMAL POSITION - Identifies the normal position of the valve LO - LOCKED OPEN LC - LOCKED CLOSED NO - NORMALLY OPEN NC NORMALLY CLOSED 164

TURKEY POINT UNIT NO. DATE: 12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION: 1 FAILURE MODE - Identifies the mode of failure FO - FAIL OPEN FC - FAIL CLOSED FAZ - FAIL AS IS REMOTE POSITION INDICATOR - YES OR NO EXAM Identifies the type of examination required TEST FREQUENCY - Identifies the test frequency associated with each valve

1. REFUELING SHUTDOWN

2. COLD SHUTDOWN 3 ~ OPERATION EVERY 3 MONTHS 4 ~ COLD SHUTDOWN WHEN THE REACTOR COOLANT SYSTEM IS DEPRESSURIZED AND VENTED 5 ~ AT LEAST ONCE EVERY TWO YEARS

6. PRIOR TO RETURN 'ZO SERVICE (IWV-3416)

7. ONCE EVERY 10 YEARS

8. IN ACCORDANCE WITH TABLE IWV-3510-1 RELIEF REQUEST - "Identifies by number the request for relief from the code requirements for that valve.

REMARKS - This column is provided for input to any additional information or alternate testing applicable to that valve.

165

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TURKEY POINT UNIT NO ~ 3/4 DATE:12-12-88 SECOND TEN-YEAR INSERVICE TESTING PROGRAM REVISION:

FIGURE NUMBER 9 ~ 2.

PLANT/UNIT INSERVICE TESTING PROGRAM VALVE TABLES P & ZD 1 SYSTEM: 2 I C C ACT/ S T A T N P F RPI V C LD0LAPASZYCYOO VRSTZPTPRS A 0 M

ID M D EON S

E X

A EREEK T F S E R R L Q R

K D E E E M L E M T Q S 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 1~ IDENTIFIES THE APPLICABLE P 6 ID DRAWING NUMBER 2~ IDENTIFIES THE SYSTEM ASSOCIATED NITH EACH VALVE

3. DENOTES THE VALVE IDENTIFICATION NUMBER 4 ~ PROVIDES THE COORDINATES FOR LOCATION OF THE VALVE ON THE DRAWING

5. IDENTIFIES THE CODE CLASS

6. IDENTIFIES THE VALVE CATEGORY 7 ~ DENOTES IF THE VALVE IS ACTIVE OR PASSIVE

8. DENOTES THE SIZE OF EACH VALVE

9. IDENTIFIES THE TYPE OF VALVE 10 ~ IDENTIFIES THE TYPE OF ACTUATOR 11 ~ IDENTIFIES THE NORMAL POSITION OF EACH VALVE 12 ~ IDENTIFIES THE FAILURE MODE OF EACH VALVE 13 DENOTES IF THE VALVE HAS A REMOTE POSITION INDICATOR

'4 IDENTIFIES THE EXAM REQUIRED

'5 IDENTIFIES THE TEST FREQUENCY

'6 IDENTIFIES THE RELIEF REQUEST APPLICABLE TO EACH VALVE REMAEGCS SECTION FOR ANY APPLICABLE ADDITIONAL INFORMATION

'7

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166

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g gggag'0 AC 10RO HOCH SSS55R 4C5S CRC SIC'555 I SCNSONC5 RON RS 151ggg gigg Sg g Florida Poser & Light ConT$ any REVI SIGH $ 1 INSERVICE TESTING - PUMP TABLFS DATE '2/12/88 rkey Point Nuclear Plant - Unit 3 PAGE : I A5 RS NH SmSRSSSS1'5$ RSSSQRSRS10'RR 01IRS 51SSSSSSS ICE SX01$ 5 501551 CSRSC SCC15 5 SCCZ N SS SCC5 INLET DIFF. FLOW BEARING PUMP NUMBER DESCRIPT ION CL COORD SPEED PRES. PRES. RATE VIBRA~ TEMP. REMARKS 3-P10A DIESEL OIL TRANSFER H H$ 5 H$ 5 N$ 4 Y Y:4 3.P201A CHARGING Y Y Y Y Y 3 ~ P201B CHARGING Y Y Y 3 ~ P201C CHARGING Y Y Y 3 '203A BORIC ACID TRANSFER N N$ 5 N$ 5 H$ 1 Y N$ 6 3-P2038 BORIC ACID TRANSFER N H5 N$ 5 N1 Y H$ 6 3.P210A RESIDUAL HEAT REMOVAL N Y:9 Y H:1 Y H$ 11 3-P2108 RESIDUAL HEAT REMOVAL N Y9 Y N1 Y H $ 11 3-P211A COMPONENT COOLING N Y Y Y 3-P2118 CCMPONEHT COOLING Y Y Y Y 11C COMPONENT COOLING Y Y Y Y

-P212A SPENT FUEL PIT COOLING Y Y Y '

3-P212B SPEHT FUEL PIT COOLING Y Y Y 3-P214A CONTAIHMEHT SPRAY Y Y Y Y 3-P214B CONTAIHMEHT SPRAY Y Y Y Y 3-P215A HIGH MEAD SAFETY Y Y Y Y 3-P215B HIGH HEAD SAFETY v v v

3. PQA IHTAKE COOLING WATER N N12 H12 v v 3.P9B INTAKE COOLING WATER H H 12 N$ 12 Y Y 3-P9C IHTAKE COOLIHG WATER H H 12 N 12 Y Y PZA AUXILIARY FEED Y Y Y Y COMMOH TO BOTH AUXILIARY FEED Y Y Y Y COMMON TO BOTH AUXILIARY FEED Y Y Y Y COMMON TO BOTH

5 5 5555 55 5 5 5 5 5 5 5 5 5 5 5 5 Florida PoMer 8 Light Cetpany REVISION: 1 RVICE TESTING - PUMP TABLES DATE: 12/12/88 ey Point Nuclear Plant . Unit 4 PAGE : 1 5 5 5 5 555 5 5 5 S 55 55 555 5 INLET DIFF. FLOW BEARING PUMP NUMBER DESCRIPTION CL COORD SPEED PRES. PRES. RATE VlBRA. TEMP. REMARKS 4-P108 DIESEL OIL TRAHSFER N N:5 N:5 H:4 Y Y 4 4-P201A CHARGING Y Y Y Y Y 4-P2018 CHARGING Y Y Y Y 4-P201C CHARGING Y Y Y 4.P203A BORIC ACID TRANSFER N N:5 N:5 Y H:6 4.P2038 BORIC ACID TRANSFER N N:5 N:5 N:1 Y H:6 4-P210A RESIDUAL MEAT REMOVAL N Y:9 Y N:I Y H:11 4.P2108 RESIDUAL HEAT REMOVAL N Y:9 Y N:1 Y N:11 4-P211A COMPONENT COOLING Y Y Y Y 4.P2118 COMPONENT COOLING Y Y Y I IC COMPONENT COOLING Y Y Y Y 4.P212A SPENT fUEL PIT COOLING Y Y Y Y 4-P2128 SPENT FUEL PIT COOLING Y Y . Y 4-.P214A CONTAINMENT SPRAY Y Y H:I 4-P2148 CONTAINMENT SPRAY Y Y H:1 4-P215C HIGH HEAD SAFETY Y Y Y Y 4-P215D HIGH HEAD SAFETY Y Y Y 4-P9A INTAKE COOLiNG WATER N N:12 N:12 Y Y 4.P98 INTAKE COOLING WATER N N:12 N:12 Y Y 4.P9C INTAKE COOLING WATER N N 12 N 12 Y Y P2A AUXILIARY FEED Y Y Y Y Y CCMHON TO BOTH AUXILIARY FEED Y Y Y Y COMMON TO BOTH AUXILIARY FEED Y Y Y Y Y COMHON TO BOTH

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aa $ 55 Z5XRs5Q 5 CRSR 'R << <<5 5 xc 0 ~S Florida PoMer 8 Light Conpany REVISION: 1 VICE TESTING . VALVE TABLES DATE: 12/'12/88 ay Point Nuclear Plant

- Unit 3 PAGE : 1 P S 10: 5177-074-H-2 SYSTEH: BREATHING AIR SYSTEH (BA)

ACT. NORH REH FAIL TEST RELIEF VALVE NUHBER COORD. CL CAT. SIZE TYPE A/P TYPE POS. IND NODE EXAH FRED RED. REHARKS 3.BA-201 B-3 2 AC 2.500 CHECK P S/A NC NO ---- SLT 5 IN-3700-1 CV-3-6165 B-4 2 A 2.500 GATE P A/0 LC YES FAI SLT 5 I W-3700-1 V 5 IN-3700-1

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aa s~5 C5 $1 Florida Power 8, Light Conpany REVISION: 1 RVICE TESTING - VALVE TABLES DATE : 12/12/88 ey Point Nuclear Plant - Unit 3 PAGE : 2 CCCCR55S5 0~~ >> 0 5 C S5 4 RISC@?SCCS P 8 ID: 5610.M-1 SYSTEM: STEAM SYSTEM ACT. HORN REM FAIL TEST RELIEF VALVE HUMBER COORD. CL CAT. SIZE TYPE A/P TYPE POS. IND MODE EXAM FREQ REQ. REMARKS 3.10.004 8.9 2 C 26.000 S/CHK A S/A NO HO ---- IHSP 7 2 3.10 F 005 B. 10 2 C 26.000 S/CHK A S/A NO NO ---- IHSP 7 2 3-10-006 8-11 2 C 26.000 S/CHK A S/A NO NO ---- INSP 7 2 3-10-083 E-12 3 C 4.000 CHECK A S/A NC NO ---- EO 3 3.10.085 E-12 3 C 4.000 CHECK A S/A HC NO ---- EO 6 3-10.087 F 12 3 C 4.000 CHECK A S/A HC HO ---- EO 6 3-10.375 C-12 3 C 3.000 CHECK A S/A NC NO ---- EO 3 3-10.376 0-12 3 C 3.000 CHECK A S/A HC NO ---- EO 3 3-10-377 0-12 3 C 3.000 CHECK A S/A NC NO .--- EO 3 381 C.12 3 C 4.000 CHECK A S/A NC NO ---- EO 3 3.10.382 0-12 3 C 4.000 CHECK A S/A NC NO ---- EO 3 3.10.383 0-12 3 C 4.000 CHECK A S/A NC NO .--- EO 3 AFSS ~ 003A 0 12 3 C 4.000 CHECK A S/A NC NO --.- EO 3 TRAIN 2 AFSS-0038 D. 12 3 C 4.000 CHECK A S/A HC NO ---- EO 3 TRAIN 2 AFSS-003C 0-12 3 C F 000 CHECK A S/A HC NO ---- EO 3 TRAIN 2 AFSS-3 005 C-12 3 C 4.000 CHECK A S/A HC HO --- EO 3 MOV-3-1400 8-3 2 8 2.000 GLOBE A MO NC YES FAI EC V 5 MOV-3-1401 8.2 2 8 F 000 GLOBE A MO HC YES FAI EC 3 V 5 MOV.3-1402 8 1 2 8 2.000 GLOBE A MO NC YES FAI EC 3 V 5

-1403 C-12 2 8 4.000 GLOBE A MO NC YES FAI EO 3 V 5

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Florida Po~er 8 Light Company REVISION:

%VICE TESTING - VALVE TABLES OATE: 12/12/88 ey Point Nuclear Plant - Unit 3 PAGE : 3 P 8, IO: 5610-M-1 (cont) SYSTEM: STEAM SYSTEM ACT. HORN REM FAIL TEST RELIEF VALVE NUMBER COORS CL CAT. SIZE TYPE A/P TYPE POS. IHO MOOE EXAM FREQ REQ. REMARKS MOV.3.1404 0 12 2 B 4.000 GLOBE A MO HC YES FAI EO 3 V

MOV-3-1405 0 12 2 B 4.000 GLOBE A MO NC YES FAI EO 3 V 5 POV-3-2604 B 9 2 C 26.000 PA/CHK A A/0 HO YES FC EC 2 1 FS V 5 POV.3.2605 8.10 2 C 26.000 PA/CHK A A/0 NO YES FC EC 2 FS 2 V 5 POV-3-2606 BE 11 2 C 26.000 PA/CHK A A/0 NO YES FC EC 2 1 FS 2 V 5 1400 C.10 2 C 6.000 SAFE A S/A HC NO ---. TF.1 8 RV-3.140'1 C.9 2 C 6.000 SAFE A S/A HC NO .". TF-2 8 RV.3.1402 C.\0 2 C 6.000 SAFE A S/A HC NO ---- TF-3 8 RV.3.1403 C-9 2 C 6.000 SAFE A S/A NC NO ---- TF-4 8 RV-3-1405 B. 10 2 C 6.000 SAFE A S/A NC HO ---- TF-1 8 RV-3-1406 B-10 2 C 6.000 SAFE A S/A HC NO .--- TF-2 8 RV-3. 1407 B-11 2 C 6.000 SAFE A S/A HC HO ".- TF-3 8 RV.3.1408 8.10 2 C 6.000 SAFE A S/A HC HO ~ .-- TF-4 8 RV-3-1410 C- 11 2 C 6.000 SAFE A S/A HC NO --- TF-1 8 RV-3-1411 C-11 2 C 6.000 SAFE A S/A HC NO "-- TF.2 8 RV.3. 1412 C-11 2 C 6.000 SAFE A S/A NC HO ---- TF-3 8 C-10 6.000 S/A ---- TF.4 8 0

2 C SAFE A HC HO

Florida Power 8 Light Company REVISION: 1

$ RVICE TESTING - VALVE TABLES DATE: 12/12/88 ey Point Nuclear Plant - Unit 3 PAGE : 4 P 8 ID: 5610.M-10 SYSTEM: PRIMARY MAKEUP & CONT. COOL.

ACT. NORM REM FAIL TEST RELIEF VALVE HUMBER COORO. CL CAT. SIZE TYPE A/P TYPE POS. IND MCOE EXAM FREO REQ. REMARKS 3.10 567 0-6 2 AC 2.000 CHECK P S/A HC NO .--- SLT 5 3-10.582 0.6 2 A 2.000 GATE P MAN HC NO FAI SLT 5 CV-3-2810 A-11 2 B 6.000 GLOBE A A/0 HO YES FC EC 3-FS 3 V 5 CV-3-2812 8-11 2 B 6.000 GLOBE A A/0 HO YES FC EC FS 3 V 5 CV-3. 2814 8-11 2 B 6.000 GLOBE A A/0 NO YES FC EC 3 FS 3 V 5 CV.3 2903 A.B 2 B 10.000 BUTFY P A/0 HO YES FO V IlN-3700-1 2904 8-8 2 B 10.000 BUTFY P A/0 HO YES FO V IN.3700-1 CV-3 '905 B 8 2 B 10.000 BUTFY P A/0 NO YES FO V IIIV-3700.1 CV-3.2906 A-11 2 8 10.000 BU'TFY A A/0 NC YES FO EO 3 FS 3 V 5 CV-3.2907 8-11 2 8 10.000 BUTFY A A/0 NC YES FO EO 3 FS 3 V 5 CV-3.2908 C-11 2 B 10.000 BUTFY A A/Oi NC YES FO EO 3 FS 3 V 5 MOV.3. 1417 8-8 2 8 10.000 GATE A MO NO YES FAI EC 2 V 5 MOV-3-1418 C.10 2 8 10.000 GATE A MO NO YES FAI EC 2 1 V 5

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Florida Power & Light Cenpany REVISION: 1

'RVICE TESTING - VALVE TABLES DATE: 12/12/88 ey Point Nuclear Plant - Unit 3 PAGE : 5 ale $S 1 0 NlCS5C << CC R SCCC CCCXC ZC P & ID: 5610.M-11 SYSTEM: CONTAINMEHT VENTILATION aaaaaz 1 551%1555 I 5 5 RR COO S <<0 2 5 5 H0551 5 SZSSCCRO mgS ACT. NORH REM FAIL TEST RELIEF VALVE NUMBER COORS CL CAT. SIZE TYPE A/P TYPE POS. IND MODE EXAM FREQ REQ. REMARKS 3.11-003 F-13 2 A/C 1.000 CHECK A S/A NO NO -"- EC 5 3 SLT 5 3.40.204 D-11 2 A 2.000 GATE A MAH LC NO FAI EO 2 6 SLT 5 3.40-205 E-13 2 AC 2.000 CHECK A S/A NC NO ---- EO 2 7 SLT 5 CV.3.2819 0-2 2 A 2.000 GLOBE A A/0 NC YES FC EC 3 FS 3 SLT 5 V 5 CV-3-2826 D-1 2 A 2.000 GLOBE A A/0 HC YES FC EC 3 FS 3 SLT 5 V 5 1 F. 10 2 A F 000 DIAPH A MAH LC NO FAI EO 2 1 SLT 5 HV-3-17 0 11 2 A 2.000 GLOBE P MAH NC NO FAI EO 2 6 SLT 5 HV.3.2 F-10 2 A 2.000 DIAPH A MAH LC NO FAI EO 2 1 SLT 5 HV.3-3 F.10 2 A 2.000 DIAPH A MAN LC NO FAI EO 2 2 SLT 5 HV-3-4 F.10 2 A 2.000 OIAPH A MAN LC NO FAI EO 2 2 SLT 5 PANH.3.001A F 13 2 A 0.750 GLOBE A MAN NC NO FAI EO 2 4 SLT 5 PANH-3-0018 F 13 2 A 0.750 GLOBE A MAH NC NO FAI EO 2 4 SLT 5 PAHM-3-002A F.11 2 A 0.750 GLOBE A MAN NC NO FAI EO 2 1 SLT 5 M-3.0028 E.12 2 A 0.750 GLOBE A MAN NC NO FAI EO 2 2 SLT. 5

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F lorida Pouer 8 Light Company REVISION: 1

'VICE TESTING - VALVE TABLES OATE: 12/12/88 ey Point Nuclear Plant - Unit 3 PAGE: 6 S H SSSSSRCSSORSCZSHSSSSI SSRS CS 0 Zg R 0 CA 55XC1515 0 ISO 01CR P 8 IO: 56'IO-H-11 l cont) SYSTEH: COHTAINNEHT VENTILATION CRR5$ 5 CSRRRS1C 1C ICE 1 5 5 5 I5 C5 CR10C1C11 5 SCSCCC ACT. HORN REH FAIL TEST RELIEF VALVE HUNBER COORD. CL CAT. S!ZE TYPE A/P TYPE POS. IHD NOOE EXAH FREQ REQ. REHARKS POV-3-2600 8.2 2 A 48.000 BUTFY A A/0 HC YES FC EC 2 8 FS 2 SLT 5 V 5 POV.3.2601 8-3 2 A 48.000 BUTFY A A/0 NC YES FC EC 2 8 FS 2 SLT 5 V 5 POV.3.2602 0-2 2 A 54.000 BUTFY A A/0 NC YES FC EC 2 8 FS 2 SLT 5 V 5 POV-3-2603 0-3 2 A 54.000 BUTFY A A/0 NC YES FC EC 2 8 FS 2 SLT 5 V 5 SV-3-2911 0.8 2 A 1.000 GLOBE A SO NO 3 5 3

5 5

SV-3-2912 0.8 2 A 1.000 GLOBE A SO NO YES FC EC 3 5 FS 3 SLT 5 V 5 SV-3.2913 C-8 2 A 1.000 GLOBE A SO NO YES FC EC 3 5 FS 3 SLT 5 V 5

4 Z 5 1 Z X 1 ZC Florida Po~er & Light Ccepany REVISION: 1 RVICE TESTING - VALVE 1'ABLES DATE: 12/12/88 y Point NUclear Plant - Unit 3 PAGE : 7 g CSCSC SC COORS 5 XR QCRLSS NRCCSCSSSC1 2 1 0 5555$

P & ID: 5610-M-12 SYSTEH: CONT. & RAD. DRAINS & VENTS ACT. NORH REH FAIL TEST RELIEF VALVE NUHBER COORD. CL CAT. SIZE TYPE A/P TYPE POS. IND HODE EXAH FREQ REQ: REMARKS CV-3.2821 C-9 2 A 3.000 GLOBE A A/0 NO YES FC EC 3 FS 3 SLT 5 V 5 CV.3-2822 C.9 2 A 3.000 GLOBE A A/0 NO YES FC EC 3 FS 3 SLT 5 V 5

Fiorida PoHer 4 Light Company REVISION: 1 FRVICE TESTING VALVE TABLES DATE: 12/12/88 ey Point Nuclear Piant . Unit 3 PAGE : 8 CSISSCS S1ZCS 5 0 CC 0 5S C5 CC ~5ÃZC>>

P 5 ID: 5610.M-2 SYSTEM: COHDENSATE AHD FEEDWATER OSSCXZ45 5 SIX'1$ CCS 150 555 C5CSC 1$ 5 5 SIC ACT. HORM REM FAIL TEST RELIEF VALVE NUMBER COORD. CL CAT. SIZE TYPE A/P TYPE POS. IHD MODE EXAM FREQ REQ ~ REMARKS20-143 8-12 3 C 6.000 CHECK A S/A HC HO ~ .-- EO 3 20 '43 C-12 3 C 6.000 CHECK A S/A HC HO ---- EO 3 20-343 0-12 3 C 6.000 CHECK A ,S/A HC HO ---. EO 3 3-20.140 8.10 2 C 4.000 CHECK A S/A NC HO .--. EO 3 3-20.240 8-10 2 C 4.000 CHECK A S/A HC NO ---- EO 3 3-20 '40 C-11 2 C 4.000 CHECK A S/A HC NO ---- EO 3 3.20.401 A-11 3 C 8 F 000 CHECK A S/A NC NO -- ~ - EO 3 AFPD.3-010 F-4 3 C 4.000 CHECK A S/A HC NO "-- EO 3 TRAIN 2 AFPD.3.012 F.4 3 C 4.000 CHECK A S/A NC NO "-- EO 3 TRAIN 2

.3.014 F 4 3 C 4.000 CHECK A S/A HC NO ---. EO 3 TRAIN 2 CV-3-2816 8-10 2 B 4.000 GLOBE A A/0 NC NO FC EO 3 4 FS 3 CV-3-2817 B 11 2 8 4.000 GLOBE A A/0 HC NO FC EO 3 4 FS 3 CV-3-2818 C-11 2 8 4.000 GLOBE A A/0 HC NO FC EO 3 4 FS 3 CV-3-2831 8-10 2 8 F 000 GLOBE A A/0 HC HO FC EO 3 4 FS 3 CV.3-2832 8-11 2 8 4.000 GLOBE A A/0 HC NO FC EO 3 4 FS 3 CV-3-2833 C-11 2 B 4.000 GLOBE A A/0 HC HO FC EO 3 4 FS 3 CV-3-2900 0-7 2 C 14.000 CHECK A A/0 NO HO ---. EC 2 3 0-8 2' 14 F 000 CHECK A A/0 NO HO ---. EC 2 3

.2902 0-9 2 C 14.000 CHECK A A/0 NO HO ---. EC 2 3

a a 0 4 5 555 1R 1 c5 a 5 ac sss&ssc 5s ss Florida Power 8 Light Conpany REVISION: 1 VICE TESTING - VALVE TABLES DATE: 12/12/88 y Point Nuclear Plant - Unit 3 PAGE: 9 xssm csosccssc$ 15 a 1551aSRt aRRsccssx&05 s ssRNssssRsss$ 45aassss P & ID: 5610-H-2 (cont) SYSTEH: CONDENSATE AND FEEDVATER cocs aaRsccI5154 sc cRca05 sslsRR$ $ 50552 cc RsRRsscaas51 cc ?la cs 5 ACT. HORII REH FAIL TEST RELIEF VALVE NUNBER COORD. CL CAT. SIZE TYPE A/P TYPE POS INO NODE EXAM FREQ REQ. REHARKS CV-3-6275A C-10 2 8 6.000 GLOBE A A/0 NO YES FAI EC 3 V 5 CV-3-6275B C-10 2 8 6.000 GLOBE A A/0 HO YES FAI EC 3 V 5 CV-3-6275C C.11 2 8 6.000 GLOBE A A/0 HO YES FAI EC 3 V 5 FCV-3.478 C-3 2 8 14.000 GLOBE A A/0 HO YES FC EC 2 FS 2 V 5 5 FCV-3.479 C-4 2 8 4.000 GLOBE A A/0 NC YES FC EC 2 FS 2

'-5 V 5 5 2 8 14.000 GLOBE A A/0 NO YES FC EC 2 FS 2 V 5 5 FCV-3-489 C-6 2 8 4.000 GLOBE A A/0 NC YES FC EC 2 FS 2 v 5 5 FCV-3-498 C-B 2 8 14.000 GLOBE A A/0 HO YES FC EC 2 FS 2 V 5 5 FCV-3.499 C-8 2 8 4.000 GLOBE A A/0 HC YES FC EC 2 FS 2 V 5 5 NOV.3-1425 E-11 2 8 1.000 GATE A HO HO YES FAI EC 3 V 5 HOV.3-1426 F- 11 2 8 1.000 GATE A HO HO YES FAI EC 3 V 5 NOV-3. 1427 C-5 2 B 1.000 GATE A HO NO YES FAI EC 3 V 5 275A-1 E-4 2 8 0.750 GLOBE A SO NC YES FC EC 3 FS 3 V 5 6

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Florida Power B Light Company REVISION: 1 ERVlCE TESTING - VALVE TABLES OATE 12/12/88 key Point Nuclear Plant - Unit 3 PAGE 10 gs QC RES CCS NC I 0 SRPC 5 CCDCRCR<<Z 0 QICRC1$ 1ÃSCCXKHSX5 P B IO: 5610-H-2 (cont) SYSTEH: CONOENSATE 8 FEEDMATER S R RZXRC R XR S 2C ACT. NORH REH FAIL TEST RELIEF VALVE NUHBER COORO. CL CAT. SIZE TYPE A/P TYPE POS. IND HOOE EXAH FREQ REQ. REHARKS SV.3-62758-1 0-4 2 B 0.750 GLOBE A SO NC YES FC EC 3 FS 3 V 5 6 SV-3-6275C-1 C-4 2 B 0.750 GLOBE A SO NC YES FC EC 3 FS 3 V 5 6

t Florida Power 8 Light Ccepany REVISIOH: 1 IH~ TESTIHG - VALVE TABLES DATE: 12/12/88 Tu int Huclear Plant - Unit 3 PAGE : 11 gaaac a c5505 Cc 0 c4Ccs1 Scz>> ox N5C c I ASM Nc 1R1S I Sa aa gled PS ID: 5610H4 SYSTEN: LUBE OIL, SERVICE & IHSTR. AIR ggggaa1HCSSOSCCSS 55$ ISRSC I 1SNRCNSSNRSCSCOCSC R OSCCSRNS1 CSRSCSNSRNCISRS SXIaeggasaagaa ACT. HORH REH FAIL TEST RELIEF VALVE HUHBER COORO. CL CAT. SIEE TYPE A/P TYPE POS. IHD HOOE EXAM FREO REQ. REHARKS 3.40.336 C 8 2 AC 2.000 CHECK A S/A HO HO --- EC 5 1 SLT 5 3 '0.340A C.8 2 AC 2.000 S/CHK A S/A HO HO ---- EC 5 1 SLT 5

v-3-2803 C-8 2 B 2.000 GLOBE P A/0 HO YES FO V 1 IMV.3700-1

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s~saaasa ssaassassasaaaassaasassssssasasssasa aaaasass ssaassasasaasas assssssssss sasssa ass F@n ida Power & Light Cotpany REVISION: 1 RVICE TESTING VALVE TABLES DATE: 12/12/88 key Point Huclear Plant - Unit 3 PAGE: 12 s sa a ssssas sas sssasss s asasssas s s s s sssasss asa sssas asaasasss sa P & ID: 5610.H-410.9'I SYSTEH: REACTOR COOLAHT (RCS) a sssss a sass s sa a a sas ss aasssss assssasssa ACT. HORN REH FAIL TEST RELIEF VALVE HUHBER COORD. CL CAT. SIZE TYPE A/P TYPE POS. IND NODE EXAH FREQ REO. REHARKS 3-518 A-11 2 AC 0 '50 CHECK A S/A HC NO ---- EO 2 SLT 5 3.519 A 11 2 AC 0.750 S/CHK A S/A HC HO ---- EO 2 2 SLT 5 CV-3-516 A.12 2 A 0.375 GLOBE A A/0 NC YES FC EC 2 FS 2 8 SLT 5 V 5 CV>>3-519A A-12 2 A 3 ~ 000 DIAPH A A/0 HC YES FC EC 2 1 FS 2 SLT 5 V 5 CV-3-5198 8-11 2 A 3.000 DIAPH P A/0 HC YES FC SLT 5 V 5 522A 8-12 2 A 0.750 OIAPH P A/0 HC YES FC SLT 5 V 5 CV.3-5228 8.12 2 A 0.750 DIAPH P A/0 HC YES FC SLT 5 V 5 CV-3-522C 8-11 2 A 0.750 DIAPH P A/0 NC YES FC SLT 5 V 5 HOV-3.535 A.5 1 8 3.000 GATE A HO HO YES FAI EC 3 V 5 HOV-3.536 A-S 1 8 3.000 GATE A HO HO YES FAI EC 3 V 5 PCV-3-455C A-5 1 8 2.000 GLOBE A A/0 HC YES FC EO 4 6 FS 4 V 5 PCV-3-456 A-5 1 8 2.000 GLOBE A A/0 HC YES FC EO 4 6 FS 4 V 5

-551A A-7 1 C 4.000 SAFE A S/A NC HO ---- TF-5 8 RV-3 5518 A.7 1 C 4.000 SAFE A S/A HC HO ---- TF-5 8

sasaaassas saaaa s saa aaa aaaaaas s sa aa s aaaaaaaaaaaassaasaa asasas saaaaa sass Florida PoMer S Light Conpany REVISION: 1 RVICE TESTING - VALVE TABLES GATE: 12/12/88 ey Point Nuclear plant - Unit 3 PAGE: 13 assasssaasaaaaaasasssasaaassssaaasaaaaasa a a a sass a aasasaassasassaasassssasssass aa a aa asasassasssassaasassssss P 8 ID: 5610-H.C10-91 (cont) SYSTEH: REACTOR COOLANT (RCS) a s s s a s sa aa a a a sass sass aaaassasssaaaaaa a saaaasa assaaaaaa ACT. NORH REH FAIL TEST RELIEF VALVE NUHBER COORD. CL CAT. SI2E TYPE A/P TYPE POS. INO HOOE EXAH FREO REQ. REHARKS RV-3-551C A-6 1 C 4.000 SAFE A S/A NC NO ---- TF-5 8 SV.3.6318A A-8 2 8 1.000 GLOBE A SO LC YES FC EC 4 5 FS 4 V 5 SV.3.63188 A-8 2 8 1.000 GLOBE A SO LC YES FC EC C 5 FS 4 V 5 SV.3-6319A A-9 2 8 1.000 GLOBE A SO LC YES FC EC 4 4 FS 4 V 5 SV-3-63198 A-9 2 8 1.000 GLOBE A SO LC YES FC EC 4 4 FS 4 V 5 6320A A.9 2 8 1.000 GLOBE A SO LC YES FC EC 4 5 FS 4 V 5 SV-3.63208 A-9 2 8 1.000 GLOBE A SO LC YES FC EC 4 5 FS 4 V 5 SV-3.6385 A-12 2 A 0.375 GLOBE A SO NC YES FC EC 2 3 FS 2 SLT 5 V 5 8

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Florida Power & Light Car@any REVISION: 1 ERVICE TEST IHG - VALVE TABLES DATE : 12/12/88 ey Point Nuclear Plane - Unit 3 PAGE : 14 e x<< 0 >> 0 50 0 sQ<<N ssc I s SSRcsccco P & ID: 5610.H-420.3 SYSTEH: CHEN. VOL. CONT. (CVCS)

JC5 << >> >> 5 R 5C cQ Cs 5 5551$ c~skRIOCcss 50 CR ACT. NORH REN FAIL TEST RELIEF VALVE HUNBER COORD. CL CAT. SIZE TYPE A/P TYPE POS. IHD NODE EXAN FREQ REQ. REHARKS 3-298A A-20 1 AC 2.000 CHECK A S/A NO NO ---- EC 5 13 SLT 5 3-2988 A-19 1 AC 2.000 CHECK A S/A NO NO --" EC 5 13 SLT 5 3.298C A-19 1 AC 2.000 CHECK A S/A HO NO --" EC 5 13 SLT 5 3-312A C-19 1 C, 3.000 CHECK A S/A NC NO --.- EO 2 10 3.312B C-19 1 C 3.000 CHECK A S/A NC NO - -- EO 2 10 3-312C C-17 1 AC 3.000 CHECK A S/A HO NO -"- EC 5 14 SLT 5 C-17 2 A 3.000 GLOBE P NAN NC NO FAI SLT 5 A.12 2 C 2.000 CHECK A S/A NC NO .-.- EO 2 11 3 '57 A.13 2 C 4.000 CHECK A S/A NC NO --.- EO 2 12 3.397A A-9 2 C 2.000 CHECK A S/A NC HO "-- EO 2 15 3 '978 A 9 2 C 2.000 CHECK A S/A NC NO --- EO 2 15 CV-3-200A 0. 19 1 A 2.000 GLOBE A A/0 HC YES FC EC 2 FS 2 SLT 5 V 5 CV-3-2008 0-18 1 A 2.000 GLOBE A A/0 2 1 2

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Florida Po~er & Light Canpsny REVISION:

RVICE TESTING . VALVE TABLES DATE : 12/12/88 ey Point Nuclear Plant - Unit 3 PAGE: 15 P & ID: 5610-H-420-3 (cont) SYSTEM: CNEH. VOL. CONT. (CVCS)

S S5 0 CC0 SCCCC S JS ACT. NORH REH FAIL TEST RELIEF VALVE NUHBER COORD. CL CAT. SIZE TYPE A/P TYPE POS. IND HODE EXAM FRED REQ. REMARKS CV-3-204 0-17 2 A 2.000 GLOBE A A/0 NO YES FC EC 2 2 FS 2 SLT 5 V 5 CV-3-310A C-19 1 B 3.000 GLOBE A A/0 NO YES FO EO 2 6 FS 2 V 5 CV-3-310B C-19 1 B 3.000 GLOBE A A/0 NC YES FO EO 2 6 FS 2 V 5 NCV 121 C-17 2 A F 000 GLOBE A A/0 NO NO FO EO 2 5 FS 2 SLT 5

.1158 A-14 2 8 4.000 BUTFY A A/0 NC YES FC EO 2 FS 2 V 5 8 LCV.3-115C C-14 2 B 4.000 GATE A HO NO 'YES FAI EC 2 7 V 5 MOV.3-350 A-12 2 8 2.000 GATE A MO NC YES FAI EO 3 V 5 HOV.3.381 8-16 2 A 3.000 GATE A HO NO YES FAI EC 4 3 SLT 5 V 5 HOV-3-6386 8-16 2 A 3.000 GATE A MO NO YES FAI EC 4 3 SLT 5 V 5

ggggggg Cga'RAN s 0 xs 5 CC sxSsx 5 555$ $ RRNCS OSCC2SSSSOÃ!SSSRCCCSSSCOSCssgggs Florida power 8 Light Cceqany ~ REVISION: 1 RVICE TESTIHG VALVE TABLES DATE: 12/12/88'y Point Nuclear Plant - Unit 3 PAGE: 16 gg gag g g S S WC Cg XRS XC1 CCS<<C25CQ I CNCSOCSI SQSRCNCS 0 15gggg P S, ID: 5610-H-450-53 SYSTEll: AUX. COOL. RES. HEAT REH.

SRRCC5 5 ROCOSC ZCS '5 SSSCS ACT. HORN REH FAlL TEST RELIEF VALVE NUNBER COORD. CL CAT ~ SIZE TYPE A/P TYPE POS. IND NODE EXAH FRED REQ. RENARKS 3-753A F-7 2 C 10.000 CHECK A S/A NC NO --- EO 2 2 3-7538 H-7 2 C 10.000 CHECK A S/A NC HO .--- EO 2 2 HCV-3-758 G-11 2 8 12.000 BUTFY P A/0 LO NO FO I lN-3700.1 HOV.3 744A 8-12 2 8 10.000 GATE A NO NC YES FAI EO 2 1 V 5 NOV-3 '448 8-12 2 8 10.000 GATE A MO HC YES FAI EO 2 1 V 5 NOV 3 750 8-5 1 A 14.000 GATE A MO LC YES FAI EO 2 3 SLT 5 V 5 HOV.3.751 C-5 1 A 14.000 GATE A HO LC YES FAI EO 2 3 SLT 5 V 5,

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Florida Po~er 8 Light Con@any REVISION: 1 RVICE TESTING - VALVE TABLES DATE: 12/12/88 y Point Nuclear Plant - Unit 3

$$ $ $ $ $ $ $ $ $$$ $ $$ $ '$ PAGE : 17 P S ID: 5610.H-450-54 SYSTEII: SPENT FUEL PIT COOLIHG ACT. NORM REH FAIL TEST RELIEF VALVE HUHBER COORD. CL CAT. SIZE TYPE A/P TYPE POS. IND NODE EXAH FRED REQ. RENARKS 3-911 F 5 3 C 8.000 CHECK A S/A NO HO --- EO 3 3-914 E-5 , 3 C 8.000 CHECK A S/A HO HO -.-- EO 3

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SS I>> C I I Florida Poster & Light Compeny ERVICE TESTING - VALVE TABLES DATE: 12/12/88 key Point Nuclear Plant - Unit 3 PACE: 18 III I 55 5555555555SSSSCSCSS SSSSSS 55555 I I 555555555555 CCSSSSS SSSSSSSSC55555555555 5$

P & ID: 5610.M.470-5 SYSTEM: SAFE'TY INJECTION SYSTEM (SIS) 5555$ 5$ $ 55$ 55555555555ISSSSSSSSSSSISSSCSSSSSSSS SSISSSSSSS 5$ 55555555555 $ 5555555$ 555555555555SSSSSS ACT. NORM REM FAIL TEST RELIEF VALVE NUMBER COORD. CL CAT. SIZE TYPE A/P TYPE POS. IND MODE EXAM FRED REQ. REMARKS 3-2918 8-10 2 C 2.000 CHECK A S/A NC Ho ---- INSP 7 14 3.2919 8-9 2 C 2.000 CHECK A S/A NC No --- IHSP 7 14 3-2920 B-9 2 C 2.000 CHECK A S/A NC NO -- - INSP 7 14 3-2921 B-10 2 C 2.000 CHECK A S/A NC No --- INSP 7 14 3-2922 8-9 2 C 2.000 CHECK A S/A HC NO --- INSP 7 14 3-2923 8.9 2 C 2.000 CHECK A S/A NC No -.-. INSP 7 14 3.873A C-15 1 AC 2.000 CHECK A S/A HC Ho ---- Eo I 16 SLT 5 3.8738 C-15 1 Ac 2.000 CHECK A S/A Nc No ---. Eo 1 16 SLT 5 C-14 1 AC 2.000 CHECK A S/A HC NO ---- EO 1 16 SLT 5 3-874A 0-17 1 Ac 2.000 CHECK A S/A HC No ---. Eo 1 15 IHSP 7 22 SLT 5 3-874 B D.17 1 Ac 2.000 CHECK A S/A Nc Ho ---- Eo 1 15 IHSP 7 22 SLT 5 3.875A A-16 1 AC 10.000 CHECK A S/A NC Ho ---- EO 2 9 INSP 7 22 SLT 5 3-8758 A.17 1 Ac 10.000 CHECK A S/A Nc No ---- Eo 2 9 IHSP 7 22 SLT 5 3.875C A-17 1 Ac 10.000 CHECK A S/A Nc No ---- Eo 2 9 IN SP 7 22 SLT 5

'-15 1 C 10.000 CHECK A S/A Nc No ---- Eo IN SP 1

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am s RR 5 Csc 0 1 x 0 2 0 ZQ 151 NCOC RI CCSCRC 0 ORCC Florida Power & Light Company REVISION: 1

'ERVICE TESTING - VALVE TABLES DATE: 12/12/SS ey Point Nuclear Plant - Unit 3 PAGE:

l11X52 5 CSC5$ C 0 2 5 5 CR RQ CXC 55'SC11 19 CCgagaCCCS P & I0: 5610-M-470-5 (cont) SYSTEM: SAFETY INJECTION SYSTEM (SIS) 1N51$ $ $ $ 15 SSSORCI515SCNSRCCN CZ 5S C1S HXHCSISORS SSCSCSOSSRSI10$ CSS ACT. NORM REM FAIL TEST RELIEF VALVE NUMBER COORO. CL CAT. SIZE TYPE A/P TYPE POS. IND MODE EXAM FREQ REQ. REMARKS 3-875 E 8-13 1 C 10.000 CHECK A S/A NC NO ---- EO 1 17 INSP 7 22 3-875 F 8-11 1 C 10.000 CHECK A S/A NC HO ---- EO 1 17 IN SP 7 22 3-876A 8.15 1 AC 8.000 CHECK A S/A NC HO ---- EO 2 7 SLT 5 3-8768 A-13 1 AC 8.000 CHECK A S/A HC HO ---- EO 2 '7 INSP 7 22 SLT 5 3-876C A.11 1 AC 8.000 CHECK A S/A NC HO ---- EO 2 7 INSP 7 22 SLT 5 60 A.13 1 AC 8.000 CHECK A S/A HC NO "-- EO 4 8 IN SP 7 22 SLT 5 3.876E A-11 1 AC 8.000 CHECK A S/A HC NO ---- EO 4 8 INSP 7 22 SLT 5 3-879A 0.7 2 C 3.000 CHECK A S/A HC NO .- ~ - EO 1 19 3-8798 C-7 2 C 3.000 CHECK A S/A HC NO ---- EO 1 19 3-890A 8-8 2 AC 6.000 CHECK A S/A HC HO ---- INSP 7 14 SLT 5 3-8908 8.8 2 AC 6.000 CHECK A S/A HC HO ---- IHSP 7 14 SLT 5 3-895V 0-12 2 A 0.750 GLOBE P MAH LC NO FAI SLT 5 3-945E C-9 2 AC 1.000 S/CHK A S/A NC NO ---- EC 2 5 SLT 5 5 C-9 2 A 1.000 GLOBE A A/0 HO YES FC EC 3 FS 3 SLT 5 V 5

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HRCISZVZR V i SCHORSSOOCSS 1505055iSS SCRAORR5 52 5550 ggCOSSRSSX1 SS ACT. NORH REH FAIL TEST RELIEF VALVE NUHBER COORO. CL CAT. SIZE TYPE A/P TYPE POS. INO HOOE EXAM FRE4 REQ. REMARKS MOV.3-843A C-13 2 8 4.000 GATE A MO NC YES FAI EO 3 V 5 MOV-3-8438 C-13 2 B 4.000 GATE A MO NC YES FAI EO 3 V 5 HOV-3-856A 0-3 2 8 2.000 GLOBE A HO NO YES FAI EC 2 21 V 5 MOV.3.8568 0-3 2 8 2,000 GLOBE A MO NO YES FAI EC' ?1 V 5 HOV-3-860A A 9 2 A 14.000 GATE A HO NC YES FAI EO 3 SLT 5 V 5 HOV-3.860B A-9 2 A 14.000 GATE A MO NC YES FAI EO 3 SLT 5 HOV.3.861A A-8 2 A 14.000 GATE A HO NC YES FAI EO 3 SLT 5 V 5 HOV.3-8618 A-8 2 A 14.000 GATE A MO NC YES FAI EO 3 SLT 5 V 5 HOV-3-862A A-5 2 B 14.000 GATE A HO LO YES FAI EC 2 12 V 5 MOV.3.862B A-5 2 B 14.000 GATE A HO LO YES FAI EC 2 12 V .5 HOV.3-863A 8-8 2 8 8.000 GATE A MO LC YES FAI EO 4 3 V 5 MOV.3-8638 8.8 2 8 8.000 GATE A MO LC YES FAI EO 4 3 V 5 0-2 2 8 16.000 GATE A HO LO YES FAI EC 1 11 V 5

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SERVICE 'IESTING - VALVE TABLES OATE: 12/12/88 rkey Point Nuclear Plant - Unit 3 PAGE: 21 aaasssasaasa ==

=-= " == ssaaasssa assaaaassasaaa s-ss sss a-a-sa s s-s-ss aaaaaaa P & IO: 5610.H-470-5 (cont) SYSTEM: SAFETY INJECTION SYSTEH <SIS) a as sss sssaa s aaaaasaaass aaaaaaaa ssaaaa s a s >> aa ssa ss sass ACT. NORH REH FAIL TEST RELIEF VALVE NUHBER COORO. Cl. CAT. SIZE TYPE A/P TYPE POS. IND HCOE EXAM FREO REQ. REMARKS HOV-3-8648 0-2 2 8 16.000 CATE A HO LO YES FAI EC 1 11 V 5 MOV-3-865A 8-15 2 8 10.000 GATE P HO LO YES FAI V 5 I W.3700.1 HOV-3-8658 8-13 2 8 10.000 GATE P HO LO YES FA I V 5 IMV-3700.1 HOV 3-865C 8-11 2 8 10.000 CATE P HO LO YES FAI V 5 IN-3700-1 MOV 3-866A 0-15 1 8 2.000 GLOBE A MO LC YES FAI EO 2 6 V 5 MOV.3.8668 0-15 I 8 2.000 GLOBE A HO LC YES FAI EO 2 6 V 5 HOV-3-869 0-12 2 8 3.000 GATE A MO NC YES FAI EO 3 V 5

~ 3.872 A 7 2 A 8.000 GATE A MO NC YES FAI EO 4 4 SLT 5 V 5 HOV-3-880A 8-7 2 A 6.000 GATE A HO NC YES FAI EO 3 SLT 5 V 5 HOV-3.8808 8-7 2 A 6.000 GATE A MO NC YES FAI EO 3 SLT 5 V 5 HOV-878A C-7 2 8 4.000 GATE A HO NO YES FAI EC 2 10 V 5 SV-3-2905 C-10 2 8 2.000 GLOBE A SO NC YES FC EO 1 13 FS 1 V 5 SV.3-2906 C-10 2 8 2.000 GLOBE A SO NC YES FC EO 1 13 FS 1 V 5

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FAIL RI4 Qz e TEST RELIEF cI z5 Os'CT.

VALVE NUMBER COORD. CL CAT. SIZE TYPE A/P TYPE POS. IND HODE EXAH FREQ RED. REMARKS SV-3-2908 C.9 2 B 2.000 GLOBE . A SO NC YES FC EO 1 13 FS 1 V 5 SV.3-2909 C-9 2 8 2.000 GLOBE A SO NC YES FC EO 1 13 FS 1 V 5 SV.3-2910 C.9 2 B 2.000 GLOBE A SO NC YES FC EO 1 13 FS 1 V 5

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F(orida Power &, Light Company REVISION: 1

'SERVICE TESTING - VALVE TABLES OATE: 12/12/88 rkey Point Nuclear Plant - Unit 3 PAGE : 23 CXt CCSCC SIC SR15 P & ID: 5610.H-470-57 SYSTEM: AUX. COOL. COHP. COOL. (ACCC) aggssgzg 5 SIZRQRONs 55RCN54 iÃssRssss5540$ 055Ã Rs r R 551ZRcos ACT. NORM REH FAIL TEST RELIEF VALVE NUHBER COORD. CL CAT. SI2E TYPE A/P TYPE POS. IND HOOE EXAH FREO REQ. REHARKS 3-702A C-11 3 C 16.000 CHECK A S/A NO NO ---- EC 3 3-7028 8-11 3 C 16.000 CHECK A S/A NO NO --- EC 3 3-702C 8-11 3 C 16.000 CHECK A S/A NO NO -.-- EC 3 CV-3-739 G-7 3 8 3.000 GLOBE A AO NO NO FC EC 3 FS 3 FCV.3.626 8-13 2 8 3.000 GATE A MO NO YES FAI EC 2 6 V 5 MOV-3-716A 8-18 2 8 6.000 GATE A MO NO YES FAI EC 2 3 V 5 HOV-3-7168 8.17 2 8 6.000 GATE A HO NO YES FAI EC 2 3 V 5 3 '30 C.13 2 8 6.000 GATE A HO NO YES FAI EC 2 5 V 5 HOV-3-749A 0-5 3 8 16.000 GATE A HO NC YES FAI EO 3 V 5 HOV.3.7498 C.6 3 8 16.000 GATE A MO NC YES FAI EO 3 V 5

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pygmy SSSR SSRRXSSSRCOOSSQS SCLCC1i 5 5 5 S>> R55S S CX S RC I NCSRQ Florida Pager 8 Light Company REVISION: 1 ERVICE TESTING - VALVE TABLES DATE: 12/12/88 key Point Nuclear Plant . Unit 3 PAGE : 24 mam 5 0 as@SSRS 5SCR0 2 0 0 0 5 2 5 5 L 5 0 z P. & IO: 5610 H-480-1 S 0 SYSTEH: SAHPLIHG (SS)

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HORN REH 1 1 FAII.

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VALVE HUHBER COORD. CI. CAT. SIZE TYPE A/P TYPE POS. IND HCOE EXAH FREO REQ. REHARKS CV-3-951 H-12 2 A 0.375 GLOBE P A/0 HC YES FC SLT 5 CV-3-953 H.12 2 A 0.375 GLOBE P A/0 NC 'ES FC SLT 5 CV.3-955C F-12 2 A 0.375 GLOBE P A/0 HC YES FC SLT 5 CV.3-9550 F-12 2 A 0.375 GLOBE P A/0 HC YES FC SLT 5 V 5 CV.3.955E F-12 2 A 0.375 GLOBE P A/0 HC YES FC SLT 5 V 5 CV-3-956A H.11 2 A 0.375 GLOBE A A/0 NC YES FC EC 3 FS 3 SLT 5 V 5 CV-3-956B H-11 2 A 0.375 GLOBE A A/0 3 3

5 5

CV.3.9560 F-11 2 A 0.375 GLOBE A A/0 3 3

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SV.3 6427A 0 '2 2 A 0.375 GLOBE A SO HC YES FC EC 3 2 FS 3 SLT 5 V 5 SV-3.64278 G.12 2 A 0.375 GLOBE A SO NC YES FC EC 3 2 FS 3 SLT 5 V 5 SV.3-6428 G-11 2 A 0.375 GLOBE A SO 3 2 3

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Florida Power B, Light Ceapany REVISION: 1 ERVICE TESTING VALVE TABLES OATE: 12/12/88 key Point Nuclear Plant - Unit 3 PAGE : 25 P 8 ID: 5610-H-5 SYSTEN: INTAKE COOL 'WATER ACT. NORH REN FAIL TEST RELIEF VALVE NUHBER COORD CL CAT. SIZE TYPE A/P TYPE POS. IND MOOE EXAII FREO REO. REHARKS 3-50-311 F-3 3 C 24.000 CHECK A S/A NO NO .---'EC 3 3-50-321 F-5 3 C 24.000 CHECK A S/A NO NO ---- EC 3 3-50.331 F-5 3 C 24.000 CHECK A S/A NO NO ---- EC 3

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Florida Po~er 8 Light Conyany REVISION: 1 ERVICE TESTING - VALVE TABLES DATE: 12/12/88 key Point Nuclear Plant - Unit 3 PAGE : 26 gggg $ 55 ii 1$ 5N C>>CSSSXC 5<< ~ ~ ~ 5 i Rgb 5 i 0 gg P 8 ID: 5610-M-500-27 SYSTEM: IJASTE DISPOSAL-LIOUID g 5 5 S2S RSSC'RSSR 5 CSC ACT. NORM REM FAIL TEST RELIEF VALVE NUMBER COORD. CL CAT. SIZE TYPE A/P TYPE POS. IND MODE EXAM FREQ REO. REMARKS CV-3.4658A C.7 2 A 0.750 OIAPH A A/0 HO 3 3

5 5

CV-3.46588 C.6 2 A 0.750 DIAPH A A/0 NO YES FC EC 3 FS 3 SLT 5 V 5 CV-3-4659A C.7 2 A 0.750 OIAPH A A/0 NO 3 3

5 5

CV-3-46598 C-6 2 A 0.750 OIAPH A A/0 NO YES FC EC 3 FS 3 SLT 5 V 5 CV-3-4668A B-7 2 A 3.000 OIAPH A A/0 NO YES FC EC 3 FS 3 SLT 5 V 5 CV.3-4668B B.6 2 A 3.000 OIAPH A A/0 NO YES FC EC 3 FS 3 SLT 5 V 5 PCV-3-1014 0-6 2 A 1.000 GLOBE P A/0 NC NO FC SLT 5

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5 sssls 5z siÃ5 >Qcsc 5 xHsx5 sIs5z sszx1sIR <<a R0c 55gggg s Florida Paver & Light Ccepany REVISION: 1 ERVICE TESTING - VALVE TABLES DATE: 12/12/SS key Point Nuclear Plant - Unit 3 PAGE: 27 P & ID: 5610-H-7 SYSTEH: DIESEL OIL ACT. NORH REH FAIL TEST RELIEF VALVE NUHB'ER COORD. CL CAT. SIZE TYPE A/P TYPE POS. IND HODE EXAH FRED REQ. REHARKS TO 006A 8-4 3 C 2.000 CHECK A S/A NC NO ---- EO CV-2046A C-3 3 8 F 000 GLOBE A A/0 NC NO FC EO 3 2 SV-2051A 8-3 3 8 2.000 GLOBE A SO NC NO FC EO 3 3

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SV-3522A D-4 3 8 1 F 500 GLOBE A SO NC NO "-- EO 3 1

~ S%1+'g Florida Power & Light Company REVISION: 1 ERVICE TESTIHG - VALVE TABLES OATE: 12/12/88 key Point Nuclear Plant . Unit 3 PAGE : 28 SS 5 CCS 5 H2g ~CZS 5 5 0 2 I1 5 0 0005 P & IO: VARIOUS SYSTEH: TEST CONNECTION aa I0 SC 5>> 2 5R ~Ã~R 0 4 2 <<M 0 0 0 S ACT. HORN REH FAIL TEST RELIEF VALVE NUNBER COORO. CL CAT* SIZE TYPE A/P TYPE POS. IHO HOOE EXAM FREQ REQ. REHARKS 3-2023 2 A 0.375 GLOBE P NAN NC HO FA I SLT 5 3.2024 2 A 0.375 GLOBE P HAH HC HO FAI SLT 5 3-2025 2 A 0.375 GLOBE P MAN NC NO FAI SLT 5 3.2026 2 A 0.375 GLOBE P NAN NC NO FAI SLT 5

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Florida Power & Light Company REVISION: 1 ERVICE TESTING - VALVE TABLES DATE : 12/12/88 ey Point Nuclear Plant - Unit 4 PAGE : 1 P & ID: 5177 074.M 2 SYSTEM: BREATHING AIR SYSTEM (BA) a 5S 5 5 5555550 015555 ACT. NORM REM FAIL TEST RELIEF VALVE NUMBER COORD. CL CAT. SIZE TYPE A/P TYPE POS. IHD MODE EXAM FREQ REQ. REMARKS 4.BA.201 B-3 2 AC 2.500 CHECK P S/A HC NO .--- SLT 5 Iiiv.3700. 1 CV.4-6165 B-4 2 A 2.500 GATE P A/0 LC YES FAI SLT 5 IN.3700-1 V 5 INI.3700-1

Florida Poger 8 Light Company REVISIOH: 1 ERVICE TESTING . VALVE TABLES DATE : 12/12/88 y Point Nuclear Plant - Unit 4 PAGE : 2

$5 RI155155 551$ 5$ 555005$ 0 QS X5 5 0 I R5 CC55 5S 551551 $ 555055 P & ID: 5610.M.1 SYSTEM: STEAM SYSTEM LOCA CC ZC 5 S R555$ CCSCC ACT. NORM REM FAIL TEST RELIEF VALVE HUMBER COORD. CL CAT. SIZE TYPE A/P TYPE POS. IND MODE EXAM FREQ REQ. REMARKS 4-10-004 8-9 2 C 26.000 S/CHK A S/A HO HO ---- IHSP 7 2 4.10.005 8-10 2 C 26.000 S/CHK A S/A NO HO ---- IHSP 7 2 4-10.006 8-11 2 C 26.000 S/CHK A S/A HO HO --- INSP 7 2 4-10-083 E-12 3 C 4.000 CHECK A S/A NC NO - EO 3 4-10-085 E-12 3 C F 000 CHECK A S/A HC NO ---- EO 6 4.10.087 F-12 3 C 4.000 CHECK A S/A HC NO ---- EO 6 4-10-375 C-12 3 C 3.000 CHECK A S/A HC HO ---- EO 4-10-376 0-12 3 C 3.000 CHECK A S/A* NC HO ---- EO 3 4-10.377 D-12 3 C 3.000 CHECK A S/A HC HO ---- EO 3

.381 C-12 3 C 4.000 CHECK A S/A HC HO ---- EO 3 382 0-12 3 C 4.000 CHECK A S/A NC HO ---- EO 3 4.10-383 0-12 3 C 4.000 CHECK A S/A HC HO ---- EO 3 AFSS-003A 0-12 3 C 4.000 CHECK A S/A HC HO .--. EO 3 TRAIN 2 AFSS.0038 D-12 3 C 4.000 CHECK A S/A HC HO ---- EO 3 TRAIN 2 AFSS.003C D-12 3 C 4.000 CHECK A S/A HC HO ---- EO 3 TRAIN 2 AFSS-4.005 C-12 3 C 4.000 CHECK A S/A HC HO ---- EO 3 MOV-4-1400 8-3 2 8 2.000 GLOBE A MO HC YES FAI EC 3 V 5 MOV-4.1401 8-2 2 8 F 000 GLOBE A MO HC YES FAI EC 3 V 5 MOV-4-1402 8-1 2 8 2.000 GLOBE A MO HC YES FAI EC 3 V 5 HOV.4-1403 C-12 2 8 3.000 GATE A MO NC YES FAI EO 3 V 5

Florida Poger 8, Light Company REVISION: 1 ERVICE TESTING . VALVE TABLES DATE: 12/12/88 ey Point Nuclear Plant - Unit 4 PAGE : 3 P S ID: 5610.M.1 (cont) SYSTEM: STEAM SYSTEM ACT. NORM REM FAIL TEST RELIEF VALVE HUMBER COORD. CL CAT. SIZE TYPE A/P TYPE POS. IND MODE EXAM FREQ REQ. REMARKS MOV.4. 1404 0.12 2 B 3.000 GATE A MO NC YES FAI EO 3 V 5 MOV-4-1405 0-12 2 B 3.000 GATE A MO NC YES FAI EO 3 V 5 POV-4-2604 8-9 2 C 26.000 PA/CHK A A/0 NO YES FC EC 2 1 FS 2 V

POV.4-2605 B-10 2 C 26.000 PA/CHK A . A/0 NO YES FC EC 2 1 FS 2 V 5 POV.4-2606 B-11 2 C 26.000 PA/CHK A A/0 HO YES FC EC 2 1 FS 2 V 5

-1400 C-10 2 C 6.000 SAFE A S/A HC NO ---- TF-1 8

.4-1401 C.9 2 C 6.000 SAFE A S/A HC HO -- - TF-2 8 RV 4-1402 C-10 2 C 6.000 SAFE A S/A HC NO ---. TF.3 8 RV.4.1403 C-9 2 C 6.000 SAFE A S/A NC HO .-.- TF-4 8 RV.4.1405 8-10 2 C 6.000 SAFE A S/A HC 'O ---- TF-1 8 RV 4-1406 8-10 2 C 6.000 SAFE A S/A NC HO ---- TF-2 8 RV.4-1407 8-11 2 C 6.000 SAFE A S/A NC HO ---- TF-3 8 I

RV.4.1408 8.10 2 C 6.000 SAFE A S/A HC HO --.- TF-4 8 RV.4-1410 C-11 2 C 6.000 SAFE A S/A HC NO ---- TF-1 8 RV.4-1411 C-11 2 C 6.000 SAFE A S/A HC HO ---- TF-2 8 RV-4-1412 C-11 2 C 6.000 SAFE A S/A HC HO ---- TF-3 8 RV-4-1413 C-10 2 C 6.000 SAFE A S/A NC NO ---- TF-4 8

f Florida Power 8 Light Company REVISION: 1 ERVICE TESTING VALVE TABLES DATE : 12/12/88 y Point Nuclear Plant - Unit 4 PAGE : 4 P 8 ID: 5610-M-10 SYSTEM: PRIMARY MAKEUP 8 CONT. COOL.

ACT. NORM REM FAIL TEST RELIEF VALVE NUMBER COORD CL CAT SIZE TYPE A/P TYPE POS IHD MODE EXAM FRED REQ. REMARKS 4.10-567 D-6 2 AC 2.000 CHECK P S/A NC HO ---- SLT 5

4. 10.582 0-6 2 A 2.000 GATE P MAN NC NO FAI SLT 5 CV-4-2810 A-11 2 B 6.000 GLOBE A A/0 NO YES FC EC 3 FS 3 V 5 CV.4.2812 8-11 2 8 6.000 GLOBE A A/0 NO YES FC EC 3 FS 3 V 5 CV-4-2814 8-11 2 8 6.000 GLOBE A A/0 HO YES FC EC 3 FS 3 V 5 CV.4-2903 A-8 2 8 10.000 BUTFY P A/0 NO YES FO V 5 I W-3700. 1

.2904 8-8 2 8 10.000 BUTFY P A/0 NO YES FO V 5 IW-3700.1

-4.2905 8-8 2 8 10.000 BUTFY P A/0 NO YES FO V 5 I W-3700-1 CV-4-2906 A-11 2 8 'I0.000 BUTFY A A/0 HC YES FO EO 3 FS 3 V 5 CV.4.2907 8.11 2 8 10.000 BUTFY A A/0 HC YES FO EO 3 FS 3 V 5 CV-4.2908 C.11 2 8 10.000 BUTFY A A/0 HC YES FO EO 3 FS 3 V 5 MOV.4-1417 8-8 2 8 10.000 GATE A MO HO YES FAI EC 2 1 V 5 MOV.4. 1418 C. 10 2 8 10.000 GATE A MO HO YES FAI EC 2 1 V 5

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Florida PoHer & Light Company REVISION: 1 ERVICE TESTING - VALVE TABLES DATE: 12/12/88 ey Point Nuclear Plant - Unit 4 PAGE : 5 P & IO: 5610-M-11 SYSTEM: CONI'A INMENT VENTILATION ACT. NORM REM FAIL TEST RELIEF VALVE NUMBER COORD. CL CAT. SIZE TYPE A/P TYPE 'OS. IND MODE EXAM FREQ REQ. REMARKS 4-11-003 F-13 2 A/C 1.000 CHECK A S/A NO NO ---- EC 5 3 SLT 5 4-40-204 D-11 2 A 2.000 GATE A MAN LC NO FAI EO 2 6 SLT 5 4-40-205 E-13 2 AC 2.000 CHECK A S/A NC NO ---- EO 2 7 SLT 5 CV-4-2819 0-2 2 A 2.000 GLOBE A A/0 NC YES FC EC 3 FS 3 SLT 5 V 5 CV-4-2826 0-1 2 A 2.000 GLOBE A A/0 NC YES FC EC 3 FS 3 SLT 5 V 5 F-10 2 A 2.000 DIAPH A MAN LC NO FAI EO 2 1 SLT 5 HV-4-17 D-11 2 A 2.000 GLOBE P MAH NC NO FAI EO 2 6 SLT 5 HV.4.2 F-10 2 A 2.000 OIAPH A MAN LC NO FAI EO 2 1 SLT 5 HV-4-3 F-10 2 A 2.000 OIAPH A MAN LC HO FAI EO 2 2 SLT 5 HV-4-4 F-10 2 A 2.000 DIAPH A MAN LC NO FAI EO 2 2 SLT 5 PAHM.4.001A F-13 2 A 0.750 GLOBE A MAN NC NO FAI EO 2 4 SLT 5 PAHM-4-001B F-'13 2 A 0.750 GLOBE A MAN NC NO FAI EO 2 4 SLT 5 PAHM-4-002A F-11 2 A 0.750 GLOBE A MAN NC NO FAI EO 2 1 SLT 5 0 4-002B E-12 2 A 0.750 GLOBE A MAN NC NO FAI EO SLT 2

5 2

Florida Power 8, Light Company REVISIOH: 1 ERVICE TESTING - VALVE TABLES DATE: 12/12/88 y Point Nuclear Plant - Unit 4 PAGE : 6 P & ID: 5610-M-11 (cont) SYSTEM: CONTAINMENT VENTILATIOH ACT. NORM REM FAIL TEST RELIEF VALVE NUMBER COORD. CL CAT. SIZE TYPE A/P TYPE POS. IND MODE EXAM FREQ REQ. REMARKS POV.4.2600 B-2 2 A 48 F 000 BUTFY A A/0 HC YES FC EC 2 8 FS 2 SLT 5 V 5 POV-4-2601 8-3 2 A 48.000 BUTF'Y A A/0 HC YES FC EC 2 8 FS 2 SLT 5 V 5 POV.4-2602 D-2 2 A 54.000 BUTFY A A/0 NC 2 8 2

5 5

POV-4-2603 0-3 2 A 54.000 BUTFY A A/0 NC 2 8 2

5 5

S .4-2911 D-8 2 A 1.000 GLOBE A SO HO 3 5 3

5 5

SV.4-2912 D-8 2 A 1.000 GLOBE A SO HO 3 5 3

5 5

SV-4-2913 C-B 2 A 1.000 GLOBE A SO HO YES FC EC 3 5 FS 3 SLT 5 V 5

Florida Power 8 Light Company REVISION: 1 RVICE TESTING - VALVE TABLES OATE : 12/12/88 ey Point Nuclear Plant - Unit 4 PAGE : 7 RR 5 0 0 Z << >> 0 0 1'5 P 8 IO: 5610-H-12 SYSTEH: CONT. & RAO. DRAINS 8 VENTS ACT. NORM REH FAIL TEST RELIEF VALVE NUMBER COORO. CL CAT. SIZE TYPE A/P TYPE POS. INO HOOE EXAM FREQ REQ. REMARKS CV-4-2821 C.9 2 A 3.000 GLOBE A A/0 NO YES FC EC 3 FS 3 SLT 5 V 5 CV.4.2822 C.9 2 A 3.000 GLOBE A A/0 NO YES FC EC 3 FS 3 SLT 5 V 5

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Florida Pe~or 8 Light Company REVISIOH: 1

' ERVICE TESTING ~ VALVE TABLES DATE : 12/12/88 y Point Nuclear Plant - Unit 4 PAGE : 8 55$ 055C!$ 511555555 5J 5 155 0 1 51555 P & ID: 5610.M-2 SYSTEM: CONDENSATE AND FEEDWATER 5SR 55 0 1CSOZ 515 5511555SIIC 55 $ 50 ACT. NORM REM FAIL TEST RELIEF VALVE NUMBER COORS CL CAT ~ SIZE TYPE A/P TYPE POS ~ IND MODE EXAM FRED REQ. REMARKS 20.143 8-12 3 C 6.000 CHECK A S/A HC NO ---- EO 3 20.243 C-12 3 C 6.000 CHECK A S/A HC NO ---- EO 3 COMMON 20.343 0-12 3 C 6.000 CHECK A S/A NC NO ---- EO 3 COMMON 4-20.140 B-10 2 C 4.000 CHECK A S/A NC HO ---- EO 3 4-20-240 B-10 2 C 4.000 CHECK A S/A NC NO ---- EO 3 4-20.340 C-11 2 C 4.000 CHECK A S/A NC NO ---- EO 3 4-20-401 A 11 3 C 8.000 CHECK A S/A HC NO ---- EO 3 AFPD 4-009 F-4 3 C 4.000 CHECK A S/A HC NO ---- EO 3 TRAIN 2 AFPD.4.011 F-4 3 C 4.000 CHECK A S/A NC NO ---- EO 3 TRAIN 2

.4-013 F-4 3 C 4.000 CHECK A S/A HC HO ---. EO 3 TRAIH 2

.4-2816 '-10 2 B 4.000 GLOBE A A/0 NC NO FC EO 3 4 FS 3 CV.4-2817 8-11 2 8 " 4.000 GLOBE A A/0 NC NO FC EO 3 4 FS 3 CV.4.2818 C.11 2 8 4.000 GLOBE A A/0 HC HO FC EO 3 4 FS 3 CV-4-2831 B-10 2 8 4.000 GLOBE A A/0 NC HO FC EO 3 4 FS 3 CV-4.2832 8-11 2 8 4.000 GLOBE A A/0 HC NO FC EO 3 4 FS 3 CV.4-2833 C-11 2 8 4.000 GLOBE A A/0 NC NO FC EO 3 4 FS 3 CV-4-2900 D-7 2 C 14.000 CHECK A A/0 NO HO ---- EC 2 3 CV 4.2901 0-8 2 C 14.000 CHECK A A/0 HO HO .--- EC 2 3

-2902 D-9 2 C 14.000 CHECK A A/0 HO NO ---- EC 2

"I Florida Poaer & Light Company REVISION: 1 ERVICE TESTING - VALVE TABLES DATE: 12/12/88 y Point Nuclear Plant - Unit 4 PAGE: 9 gag 5 5S SQ 2 5R 5C 0 2 RZ 0 Ct5C5 1 551CSS P 8 ID: 5610-M-2 (cont) SYSTEM: COHDEHSATE AHD FEEDMATER mam a a a asm a@a s aaa aa aasaam m aa aaasg ACT. NORM REM FAIL TEST RELIEF VALVE NUMBER COORD. CL CAT. SIZE TYPE A/P TYPE POS. IHD MODE EXAM FREQ REQ ~ REMARKS CV.4-6275A C-10 2 B 6.000 GLOBE A A/0 NO YES FAI EC 3 V 5 CV-4-62758 C-10 2 B 6.000 GLOBE A A/0 NO YES FAI EC 3 V 5 CV.4-6275C C-11 2 8 6.000 GLOBE A A/0 NO YES FAI EC 3 V 5 FCV.4-478 C-3 2 8 14.000 GLOBE A A/0 HO YES FC EC 2 FS 2 5 V 5 FCV-4-479 C-4 2 8 F 000 GLOBE A A/0 HC YES FC EC 2 FS 2 5 V 5 FCV.4.488 C-5 2 8 14.000 GLOBE A A/0 NO YES FC EC 2 FS 2 5 V 5 FCV.4.489 C.6 2 8 4.000 GLOBE A A/0 NC YES FC EC 2 FS 2 5 V 5 FCV-4-498 C-8 2 B 14.000 GLOBE A A/0 HO YES FC EC 2 FS 2 5 V 5 FCV-4-499 C-8 2 B 4.000 GLOBE A A/0 HC YES FC EC 2 FS 2 5 V 5 MOV.4.1425 E-11 2 B 1.000 GATE A MO HO YES FAI EC 3 V 5 MOV.4.1426 F.11 2 8 1.000 GATE A MO HO YES FAI EC 3 V 5 MOV-4-1427 C-5 2 B 1.000 GATE A MO NO YES FAI EC 3 5

6275A-1 E-4 2 8 0.750 GLOBE A SO HC YES FC EC 3 FS 3 6 V 5

Florida Po~er 8 Light Company REVISION: 1 RVICE TESTING - VALVE TABLES DATE: 12/12/BS y Point Nuclear Plant - Unit 4 PAGE: 10 S 5 51$ 5$ 5$ 5$ $ $ RRSSCSSSSSSSOSS'JSISSR P S IO: 5610-H-2 (cont) SYSTEM: CONDENSATE & FEEDMATER 21R 5 5 5 CR 5$ 5555 550 C5X RCS SC C5RZ ACT. NORH REH FAIL TEST RELIEF VALVE NUHBER COORD. CL CAT. SIZE TYPE A/P TYPE POS ~ IND MODE EXAH FREQ REQ. REMARKS SV-4-6275B-1 D-4 2 8 0.750 GLOBE A SO NC YES FC EC 3 FS 3 6 V 5 SV-4-6275C-1 C-4 2 B 0.750 GLOBE A SO NC YES FC EC 3 FS 3 6 V 5

+51 Florida Power 8 Light Company REVISION: 1 SERVICE TESTING - VALVE TABLES DATE : 12/12/88 y Point Nuclear Plant - Unit 4 PAGE : 11 A 4M P 8 ID: 5610 M-4 SYSTEM: LUBE OIL, SERVICE 8 INSTR. AIR ACT. NORM REM FAIL TEST RELIEF VALVE NUMBER COORD. CL CAT. SIZE TYPE A/P TYPE POS. IND MODE EXAM FREQ REQ. REMARKS 4-40-336 C-B 2 AC 2.000 CHECK A S/A NO NO -- - EC 5 1 SLT 5 4.40.340A C.8 2 AC 2.000 S/CHK A S/A NO NO ---- EC 5 1 SLT 5 CV.4-2803 C-B 2 8 2.000 GLOBE P A/0 HO YES FO V 5 IN-3700. 1

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FIorida Poser S Light Cerpany REVISION: 1 ERVICE TESTING - VALVE TABLES DATE : 12/12/88 y Point Nuclear Plant - Unit 4 PAGE : 12 P 8 ID: 5610-M.410-91 SYSTEM: REACTOR COOLANT (RCS)

ACT. NORM REM FAIL TEST RELIEF VALVE NUMBER COORD. CL CAT. SIZE TYPE A/P TYPE POS. IHD MODE EXAM FREQ REQ. REMARKS 4-518 A-11 2 AC 0.750 CHECK A S/A NC NO ---- EO 2 2 SLT 5 4.519 A.11 2 AC 0.750 S/CHK A S/A NC NO ---- EO 2 2 SLT 5 CV.4.516 A.12 2 A 0.375 GLOBE A A/0 NC YES FC EC 2 FS 2 SLT 5 V 5 8 CV.4.519A A-12 2 A 3.000 DIAPH A A/0 HC 2 1 2

5 5

CV.4.5198 8-11 2 A 3.000 DIAPH P A/0 NC YES FC SLT 5 V 5 522A B-12 2 A 0.750 D IAPH P A/0 HC YES FC SLT 5 V 5 CV.4.5228 8-12 2 A 0.750 DIAPH P A/0 HC YES FC SLT 5 V 5 CV-4-522C 8-11 2 A 0.750 DIAPH P A/0 NC YES FC SLT 5 V 5 MOV 4 535 A-5 1 8 3.000 GATE A MO HO YES FAI EC 3 V 5 MOV-4-536 A-5 1 B 3.000 GATE A MO HO YES FAI EC 3 V 5 PCV-4-455C A.5 1 8 F 000 GLOBE A A/0 HC YES FC EO 4 6 FS 4 V 5 PCV-4.456 A 5 1 B 2.000 GLOBE A A/0 NC YES FC EO 4 6 FS 4 V 5

.551A A 7 1 C 4.000 SAFE A S/A HC NO ---- TF-5 8

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Florida Power 8 Light Ccepany REVISION: 1 SERVICE TESTING - VALVE TABLES OATE : 12/12/88

'ey Point Nuclear Plant - Unit 4 PAGE : 13 QSSS~XR ZCSSSSS0555 P 8 ID: 5610-H-410-91 (cont) SYSTEH: REACTOR COOLANT (RCS))

ACT. NORH REM FAIL TEST RELIEF VALVE NUHBER COORS CL CAT. SiZE TYPE A/P TYPE POS ~ INO HOOE EXAH FREQ REO. REMARKS RV.4.5518 A 7 1 C 4.000 SAFE A S/A NC NO ---- TF-5 8 RV.4.551C A-6 1 C 4.000 SAFE A S/A NC NO ---- TF.S 8 0

SV-4.6318A A-8 2 8 1.000 GLOBE A SO LC YES FC EC 4 5 FS 4 V 5 SV-4-63188 A-8 2 B 1.000 GLOBE A SO LC YES FC EC 4 5 FS 4 V 5 SV 4 6319A A-9 2 8 1.000 GLOBE A SO LC YES FC EC 4 4 FS 4 V 5 SV.4.63198 A-9 2 8 1.000 GLOBE A SO LC YES FC EC 4 4 FS 4 V 5 6320A A-9 2 8 1.000 GLOBE A SO LC YES FC EC 4 5 FS 4 V 5 SV-4-6320B A.9 2 8 1.000 GLOBE A SO LC YES FC EC 4 5 FS 4 V 5 SV.4-6385 A.12 2 A 0.375 GLOBE A SO NC YES FC EC 2 3 FS 2 SLT 5 V 5 8

Florida Power & Light Company REVISION: 1 ERVICE TESTING - VALVE TABLES 'ATE : 12/12/88 y Point Nuclear Plant - Unit 4 PAGE: 14 P 8 IO: 5610-M-420.3 SYSTEM: CHEM. VOL. CONT ~ (CVCS)

ACT. NORM REM FAIL TEST RELIEF VALVE HUMBER COORD. CL CAT. SIZE TYPE A/P TYPE POS. IND MODE EXAM FREQ REQ. REMARKS 4.298A A-20 1 AC 2.000 CHECK A S/A HO NO -- - EC 5 13 SLT 5 4 '988 A-19 1 AC 2.000 CHECK A S/A HO NO --- EC 5 13 SLT 5 4.298C A-19 1 AC 2.000 CHECK A S/A HO NO ---- EC 5 13 SLT 5 4.312A C-19 1 C 3.000 CHECK A S/A HC NO ---- EO 2 10 4-3128 C-19 1 C 3 ~ 000 CHECK A S/A NC NO ---- EO 2 10 4-312C C-17 1 AC 3.000 CHECK A S/A HO NO ---- EC 5 14 SLT 5 4-333 C-17 2 A 3.000 GLOBE P MAN NC HO FAI SLT 5 A-12 2 C 2.000 CHECK A S/A NC HO ---- EO 2 11

- 57 A-13 2 C 4.000 CHECK A S/A NC NO ---- EO 2 12 4-397C A 7 2 A 2.000 CHECK A S/A NC NO ---- EO 2 15 4-3970 A-7 2 A 2.000 CHECK A S/A NC NO .--- EO 2 15 CV-4-200A 0 19 1 A 2.000 GLOBE A A/0 HC YES FC EC 2 1 FS 2 SLT 5 V 5 CV-4-2008 0-18 1 A 2.000 GLOBE A A/0 NC YES FC EC 2 1 FS 2 SLT 5 V 5 CV.4.200C 0-18 1 A 2.000 GLOBE A A/0 NO YES FC EC 2 1 FS 2 SLT 5 V 5

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Florida Power 8 Light Carpany REVISION: 1 RVICE TES T IHG VALVE TABLES DATE: 12/12/88 y Point Nuclear Plan t - Unit 4 PAGE: 15 P 8 ID: 5610-M-420-3 (cont) SYSTEM: CHEM. VOL. CONT. (CVCS) a a a 55RSSRS SR?LRSCS555$ ?IC55 CSLC RCR aa aa ACT. NORM REM FAIL TEST RELIEF VALVE NUMBER COORD. CL CAT. SIZE TYPE A/P TYPE POS. IHD MODE EXAM FREQ REQ. REMARKS CV-4-204 D-17 2 A 2.000 GLOBE A A/0 2 2 2

5 5

CV-4-310A C-19 1 8 3.000 GLOBE A A/0 NO YES FO EO 2 6 FS 2 V 5 CV.4 '108 C-19 1 8 3.000 GLOBE A A/0 NC YES FO EO 2 6 FS 2 V 5 HCV-4.121 C-17 2 A 3.000 GLOBE A A/0 HO HO FO EO 2 5 FS 2 SLT 5 CV.4-1158 A-14 2 8 4.000 BUTFY A A/0 HC YES FC EO 2 8 FS 2 V 5 LCV.4.115C C.14 2 8 4.000 GATE A MO NO 'YES FAI EC 2 7 V 5 MOV.4-350 A-12 2 8 2.000 GATE A MO NC YES FAI EO 3 V 5 MOV-4.381 B- 16 2 A 3.000 GATE A MO NO YES FAI EC 4 3 SLT 5 V 5 MOV-4-6386 8-16 2 A 3.000 GATE A MO NO YES FAI EC 4 3 SLT 5 V 5

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4

Florida Power F Light Company REVISION: 1 RVICE TESI'ING - VALVE TABLES DATE : 12/12/88

~y Point Nuclear Plant - Unit 4 PAGE : 16 P B ID: 5610-M-450-53 SYSTEM: AUX. COOL. RES. HEAT REM.

ACT. NORM REM FAIL TEST RELIEF VALVE NUMBER COORD. CL CAT. SIZE TYPE A/P TYPE POS. IND MODE EXAM FREQ REQ. REMARKS 4.753A F-7 2 C 10.000 CHECK A S/A NC NO ---- EO 2 2 4.7538 H-7 2 C 10.000 CHECK A S/A NC NO --- EO 2 2 HCV-4-758 G.11 2 B 12.000 BUI'FY P A/0 LO NO FO IMV-3700-1 MOV.4.744A B-12 2 8 10.000 GATE A MO NC YES FAI EO 2 V 5 1 MOV-4-7448 B-12 2 B 10.000 GATE A MO NC YES FAI EO 2 1 V 5 MOV 4-750 8-5 1 A 14.000 GATE A MO LC YES FAI EO 2 3 SLT 5 V 5 MOV 4-751 C.5 1 A 14.000 GATE A MO LC YES FAI EO 2 3 SLT 5 V 5

Florida Poaer & Light Carpany REVISION: 1 RVICE TESTING - VALVE TABLES DATE : 12/12/88 ey Point Nuclear Plant - Unit 4 PAGE : 17 P & IO: 5610-M.450-54 SYSTEM: SPENT FUEL PIT COOLING ACT. NORM REM FAIL TEST RELIEF VALVE NUMBER COORD. CL CAT. SIZE TYPE A/P TYPE POS. IHD MOOE EXAM FREQ REO. REMARKS 4-911 F-5 3 C 8.000 CHECK A S/A HO NO ---- EO 3 4-914 E-5 3 C 8.000 CHECK A S/A NO HO ---- EO 3

Florida Power & Light Con@any REVISION: 1 ERVICE TESj'ING . VALVE TABLES DATE: 12/12/88 y Point Nuclear Plant

- Unit 4 PAGE: 18 P 8 ID: 5610-M-470.5 SYSTEM: SAFETY INJECTION S'STEM (SIS)

ACI'. NORM REM FAIL TEST RELIEF VALVE NUMBER COORD. CL CAT. SIZE TYPE A/P TYPE POS ~ IND MODE EXAM FREQ REQ. REMARKS 4-2918 8-10 2 C 2.000 CHECK A S/A NC NO ---- IHSP 7 14 4-2919 8-9 2 C 2.000 CHECK A S/A HC HO ---- INSP 7 14 4.2920 8.9 2 C 2.000 CHECK A S/A NC NO ---- INSP 7 14 4.2921 B 10 2 C 2.000 CHECK A S/A HC HO ---- IHSP 7 14 4.2922 B-9 2 C 2.000 CHECK A S/A NC HO "- INSP 7 14 4-2923 8-9 2 C 2.000 CHECK A S/A NC HO ---- INSP 7 14 4-873A C-15 1 AC 2.000 CHECK A S/A HC NO ---- EO 1 16 SLT 5 4-8738 C-15 1 AC 2.000 CHECK A S/A NC NO ---- EO 1 16 SLT 5 C-14 1 AC 2.000 CHECK A S/A HC NO ---- EO 1 16 SLT 5 4.874A D-17 1 AC 2.000 CHECK A S/A NC NO ---- EO 1 15 IHSP 7 22 SLT 5 4.8748 0.17 1 AC 2.000 CHECK A S/A HC NO ---- EO 1 15 INSP 7 22 SLT 5 4-875A A 16 1 AC 10.000 CHECK A S/A HC NO --- EO 2 9 INSP 7 22 SLT 5 4-8758 A-17 1 AC 10.000 CHECK A S/A NC NO ---- EO 2 9 IHSP 7 22 SLT 5 4.875C A-17 1 AC 10.000 CHECK A S/A NC HO ".- EO 2 INSP 7 22 SLT 5 8.15 1 C 10.000 CHECK A S/A NC HO .-.- EO 1 17 IHSP 7 22

aaa a xaa aa a aa aa a x a aaa a a a aa Florida Po~er & Light Company REVISION: 1

.RVICE TESTING - VALVE TABLES OATE : 12/12/88 ey Point NUclear Plant . Unit 4 PAGE : 19 axaaaaaaaaaaaaaaaaaaaaaaaaaaaaaaaaaaaaaaaaaaaaaaaaaaa aa aaaaaaaaaaaaaaaxaaaaaaaaaaaaaaaaaaaaaaaaaaa P & IO: 5610-N-470-5 (cont) SYSTEH: SAFETY INJECTION SYSTEN (SIS) aaaaaaaaaaaaaa 'a a a aa aa a a aaaa sass aa aaaaxaaaasaaa ACT. HORN REN FAIL TEST RELIEF VALVE NUHBER COORD. CL CAT. SIZE TYPE A/P TYPE POS. IND HOOE EXAII FREO REQ. RENARKS 4.875E 8-13 1 C 10.000 CHECK A S/A NC HO ---- EO 1 17 IN SP 7 22 4.875 F 8-11 1 C 10 F 000 CHECK A S/A HC NO ---- EO 1 17 INSP 7 22 4.876A 8.15 1 AC 8.000 CHECK A S/A NC HO .--- EO 2 7 SLT 5 4.8768 A-13 1 AC 8.000 . .CK A S/A HC NO ---- EO 2 7 INSP 7 22 SLT 5 4-876C A-11 1 AC 8.000 CHECK A S/A NC NO ---- EO 2 7 IHSP 7 22 SLT 5 A-13 1 AC 8.000 CHECK A S/A NC NO ---. EO 4 8 INSP 7 22 SLT 5 4-876E A-11 1 AC 8.000 CHECK A S/A NC NO ---- EO 4 8 IHSP 7 22 SLT 5 4.879C C.7 2 C 3.000 CHECK A S/A NC NO ---- EO 1 19 4.8790 C 7 2 C F 000 CHECK A S/A HC HO ---- EO 1 19 4.890A 8-8 2 AC 6.000 CHECK A S/A NC HO .--- IHSP 7 14 SLT 5 4.8908 8-8 2 AC 6.000 CHECK A S/A HC NO ---- INSP 7 14 SLT 5 4-895V 0 12 2 A 0.750 GLOBE P HAH LC NO FAI SLT 5 4.945E C.9 2 AC 1.000 S/CHK A S/A HC NO .--- EC 2 5

'LT 5 CV-4-855 C.9 2 A 1.000 GLOBE A A/0 3 3

5 5

0 I 1

Florida Power 8 Light Company REVISION: 1 ERVICE TESTING - VALVE TABLES DATE : 12/12/88 ey Point Nuclear Plant - Unit 4 PAGE : 20 P 8, ID: 5610-H-470-5 (cont) SYSTEM: SAFETY INJECTION SYSTEH (SIS)

ACT. NORH REH FAIL TEST RELIEF VALVE NUMBER COORD. CL CAT. SIZE TYPE A/P TYPE POS. IND HODE EXAH FREQ REO. REMARKS CV.4.855 C-9 2 A 1.000 GLOBE A A/0 NO 3 3

5 5

MOV 4 843A C-13 2 B 4.000 GATE A HO NC YES FAI EO 3 V 5 HOV.4-8438 C.13 2 B 4.000 GATE A MO NC YES FAI EO 3 V 5 HOV 4-856A C-3 2 B 2.000 GLOBE A HO NO YES FAI EC 1 21 V 5 HOV-4.856B C-3 2 B 2.000 GLOBE A MO NO YES FAI EC 1 21 V 5 HOV-4.860A " A-9 2 A 14.000 GATE A HO NC YES FAI EO 3 SLT 5 V 5 MOV-4-860B A-9 2 A 14.000 GATE A HO NC YES FAI EO 3 SLT 5 V 5 MOV-4 86'IA A-8 2 A 14.000 GATE A MO NC YES FAI EO 3 SLT 5 V 5 HOV 4 8618 A-8 2 A 14.000 GATE A MO NC YES FAI EO 3 SLT 5 V 5 HOV-4.862A A.5 2 8 14.000 GATE A HO LO YES FAI EC 2 12 V 5 HOV.4.8628 A-5 2 B 14.000 GATE A HO LO YES FAI EC 2 12 V 5 MOV.4-863A 8-8 2 B 8.000 GATE A MO LC YES FAI EO 4 3 V 5 8638 B.8 2 B 8.000 GATE A HO LC YES FAI EO 4 3 V, 5

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g I 0 cj g e ~ 201 52 5 so 155100 5 egg Florida Power 8 Light Company REVISION: 1 INSERVICE TESTING ~ VALVE TABLES DATE: 12/12/88 Turkey Nuclear Plant - Unit 4 PAGE: 21 e zs 5 555'$05 cc55 ss c1 5 e c1 5 2 e ID: 5610 H 470-5 (cont) SYSTEM: SAFETY INJECTION SYSTEH (SIS)

SSRRSCQ'0 5CC5CS 0 5 0 %50$ S OCR ICE 0 COCA ACT. NORH REM FAIL TEST RELIEF VALVE NUMBER COORD. CL CAT ~ SIZE TYPE A/P TYPE POS. IND MODE EXAM FREQ REQ. REMARKS MOV.4 864A 0 2 2 8 16.000 GATE A MO LO YES FAI EC 1 11 V 5 MOV.4.8648 D-2 2 8 16.000 GATE A HO LO YES FAI EC 1 11 V 5 HOV-4-865A 8.15 2 8 10.000 GATE P HO LO YES FAI V 5 IMV-3700-1 HOV-4-8658 8-13 2 8 10.000 GATE P HO LO YES FAI V 5 IWV-3700-1 MOV.4.865C 8.11 2 8 10.000 GA'TE P HO LO YES FAI V 5 IMV-3700-1 MOV.4. 866A 0-15 1 8 2.000 GLOBE A MO LC YES FAI EO 2 6 V 5 HOV-4-8668 D-15 1 8 2.000 GLOBE A MO LC YES FAI EO 2 6 V 5 HOV-4 869 0-12 2 8 3.000 GATE A HO NC YES FAI EO 3 V 5

.4.872 A 7 2 A 8.000 GATE A MO NC YES FAI EO 4 4 SLT 5 V 5 HOV-4.880A 8.7 2 A 6.000 GATE A HO NC YES FAI EO 3 SLT 5 V 5 HOV.4 8808 8.7 2 A 6.000 GATE A HO NC YES FAI EO 3 SLT 5 V 5 HOV-878B C-7 2 B 4.000 GATE A HO NO YES FAI EC 2 10 V 5 SV-4-2905 C-10 2 8 2.000 GLOBE A SO NC YES FC EO 1 13 FS 1 V 5 SV-4.2906 C.10 2 8 2.000 GLOBE A SO NC YES FC EO 1 13 FS 1 V 5

Florida Po~er & Light Company REVISION: 1 ERVICE TESTING . VALVE TABLES DATE : 12/12/88 y Point Nuclear Plant - Unit 4 iS 555 <<55 <<5 RSC1501$ 5$ $ 5C SS5CZR 5 R555C PAGE : 22 P & ID: 5610-M-470.5 (cont) SYSTEH: SAFETY INJECTION SYSTEH (SIS)

ACT. NORH REH FAIL TEST RELIEF VALVE NUMBER COORD. CL CAT. SIZE TYPE A/P TYPE POS. IND HODE EXAM FREQ REQ. REMARKS SV.4-2907 C.9 2 8 2.000 GLOBE A SO NC YES FC EO 1 13 FS 1 V 5 SV.4.2908 C.9 2 8 2.000 GLOBE A SO NC YES FC EO 1 13 FS 1 V 5 SV-4-2909 C 9 2 8 2.000 GLOBE A SO NC YES FC EO 1 13 FS 1 V 5 SV.4.2910 C-9 2 8 . 2.000 GLOBE A SO NC YES FC EO 1 13 FS 1 V 5

Florida Power 8 Light Company REVISION: 1 IHSERVICE TESTING . VALVE TABLES DATE : 12/12/88 key Point Nuclear Plant - Unit 4 PAGE : 23

& ID: 5610.M.470-57 SYSTEM: AUX. COOL. COMP. COOL. (ACCC)

ACT. NORM REM FAIL TEST RELIEF VALVE NUMBER COORS CL CAT ~ SIZE TYPE A/P TYPE POS ~ IND MODE EXAM FRED REQ. REMARKS 4-702A C-11 3 C 16.000 CHECK A S/A HO NO ---- EC 3 4.7028 8 11 3 C 16.000 CHECK A S/A HO NO ---- EC 3 4.702C 8 11 3 C 16.000 CHECK A S/A NO NO ---- EC 3 CV-4-739 G-7 3 8 3.000 GLOBE A A/0 HO HO FC EC 3 FS 3 FCV.4.626 8-13 2 8 3.000 GATE A MO HO YES FAI EC 2 6 V 5 MOV-4-716A 8.18 2 8 6.000 GATE A MO HO YES FAI EC 2 3 V 5 MOV.4-7168 8.17 2 8 6.000 GATE A MO NO YES FAI EC 2 3 V 5

.4-730 C-13 2 8 6.000 GATE A MO NO YES FAI EC 2 5 V 5 MOV.4 '49A 0-5 3 8 16.000 GATE A MO NC YES FAI EO 3 V 5 MOV-4-7498 C.6 3 8 16.000 GATE A MO HC YES FAI EO 3 V 5

E4 1 '

Florida Power 8 Light Company REVISION: 1 ERVICE TESTIHG - VALVE TABLES OATE: 12/12/88

- Unit 4 y Point Nuclear Plant PAGE : 24 P & ID: 5610-M-480-1 SYSTEM: SAMPLIHG (SS)

ACT. NORM REM FAIL TEST RELIEF VALVE NUMBER COORD. CL CAT. SIZE TYPE A/P TYPE POS. IND MODE EXAM FREQ REO. REMARKS CV.4-951 H-12 2 A 0.375 GLOBE P A/0 HC YES FC SLT 5 V 5 CV.4.953 H-12 2 A 0.375 GLOBE P A/0 NC YES FC SLT 5 V 5 CV-4 955C F-12 2 A 0.375 GLOBE P A/0 HC YES FC SLT 5 V 5 CV-4.9550 F-12 2 A 0.375 GLOBE P A/0 NC YES FC SLT 5 V 5 CV.4.955E F-12 2 A 0.375 GLOBE P A/0 NC YES FC SLT 5 V 5 CV-4.956A H.11 2 A 0.375 GLOBE A A/0 NC YES FC EC 3 FS 3 SLT 5 V 5

.4.956B H-11 2 A 0.375 GLOBE A A/0 HC YES FC EC 3 FS 3 SLT 5 V 5 CV-4.9560 F-11 2 A 0.375 GLOBE A A/0 HC YES FC EC 3 FS 3 SLT 5 V 5 SV.4-6427A 012 2 A 0.375 GLOBE A SO NC YES FC EC 3 2 FS 3 SLT 5 V 5 SV.4.64278 G-12 2 A 0.375 GLOBE A SO HC 3 2 3

5 5

SV.4-6428 G-11 2 A 0.375 GLOBE A SO 3 2 3

5 5

I'4 "

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Florida Power & Light Company REVISIOH: 1 SERVICE TESTIHG - VALVE TABLES OATE : 12/12/88 ey@JANPoint Huclear Plant - Unit 4 PAGE : 25 P & ID: 5610-M.5 SYSTEM: IHTAKE COOL 'WATER 5 0 5 I J JJ ACT. HORM REM FAIL TEST RELIEF VALVE HUMBER COORD. CL CAT. SIZE TYPE A/P TYPE POS. IHO MOOE EXAM FREQ REQ. REMARKS 4-50.311 F-3 3 C 24.000 CHECK A S/A HO HO ---- EC 3 4-50.321 F-5 3 C 24.000 CHECK A S/A HO HO ---- EC 4-50.331 F-5 3 C 24.000 CHECK A S/A HO HO ---- EC 3

Florida Pouer 8 Light Company REVISION: 1 ERVICE TESTING i VALVE TABLES DATE : 12/12/88 y Point Nuclear Plant - Unit 4 PAGE : 26 P & ID: 5610.M.500-27 S'STEM: HASTE DISPOSAL-LIQUID ACT. NORM REM FAIL TEST RELIEF VALVE NUMBER COORD. CL CAT. SIZE TYPE A/P TYPE POS. IHD MODE EXAM FREQ REQ. REMARKS CV.4-4658A C-7 2 A 0.750 OIAPH A A/0 HO YES FC EC 3 FS 3 SLT 5 V 5 CV-4-46588 C-6 2 A 0.750 DIAPH A A/0 NO YES FC EC 3 FS 3 SLT 5 V 5 CV 4 4659A C-7 2 A 0.750 DIAPH A A/0 HO YES FC EC 3 FS 3 SLT 5 V 5 CV 4-4659B C 6 2 A 0.750 OIAPH A A/0 HO YES FC EC 3 FS 3 SLT 5 V 5 4668A 8-7 2 A 3.000 DIAPH A A/0 NO YES FC EC 3 FS 3 SLT 5 V 5 CV.4.46688 8-6 2 A 3.000 DIAPH A A/0 HO YES FC EC 3 FS 3 SLT 5 V 5 PCV.4-1014 D.6 2 A 1.000 GLOBE P A/0 HC NO FC SLT 5

Florida PoNer & Light,Ccepany REVISION: 1 SERVICE TESTING . VALVE TABLES DATE: 12/12/88 ey Point Nuclear Plant - Unit 4 PAGE: 27 P & ID: 5610.M-7 SYSTEM: DIESEL OIL ACT. NORM REM FAIL TEST RELIEF VALVE NUMBER COORD. CL CAT. SIZE TYPE A/P TYPE POS. IND MODE EXAM FREQ REQ. REMARKS 70.0068 8 4 3 C 2.000 CHECK A S/A NC NO ---- EO 3 CV-20468 C-3 3 8 2.000 GLOBE A A/0 HC NO FC EO 3 2 SV-20518 8-3 3 8 2.000 GLOBE A SO HC NO FC EO 3 3 SV-35228 0-5 3 8 1.500 GLOBE A SO HC NO ---. EO 3 1

0 Florida Power & Light Company REVISION: 1 NSERVICE TESTING - VALVE TABLES DATE: 12/12/88 ey Point Nuclear Plant . Unit 4 PAGE : 28 aa s5CS CCCRC 1 5 5 aaaa Z P & ID: VARIOUS SYSTEM: TEST COHHECTIOH ACT. NORM REM FAIL TEST RELIEF VALVE HUMBER COORD. CL CAT. SIZE TYPE A/P TYPE POS. IND MODE EXAM FREQ REQ. REMARKS 4.2023 2 A 0.375 GLOBE P MAN HC HO FAI SLT 5 4-2024 2 A 0.375 GLOBE P MAN NC HO FAI SLT 5 4.2025 2 A 0.375 GLOBE P MAN HC HO FAI SLT 5 4-2026 '2 A 0.375 GLOBE P MAN HC NO FAI SLT 5

~

7

0 ENCLOSURE I LIST OF ATTENDEES NRC H. N. Berkow, Director, Project Directorate II-2, NRR R. W. Borchardt, Regional Coordinator, OEDO R. C. Butcher, Senior Resident Inspector, Turkey Point S. D. Ebneter, Regional Administrator, RII G. E. Edison, Licensing Project Manager, NRR B. K. Grimes, Deputy Regional Administrator (Acting), RII C. W. Hehl, Deputy Director, Division of Reactor Projects, RII G. A. Schnebli, Resident Inspector, Turkey Point M. V. Sinkule, Branch Chief, Division of Reactor Projects, RII S. A. Varga, Director, Division of Reactor Projects I/II, NRR FPSL.

R. J. Acosta, Acting Vice President, Nuclear Energy ,

J. Arias, Jr., Technical Assistant to Plant Manager K. E. Beatty, Training Superintendent L. W. Bladow, guality Assurance Superintendent D. A. Chancy, Director, Nuclear Licensing J. E. Cross, Plant Manager R. J. Earl, guality Control Supervisor S. T. Hale, Engineering Project Manager K. N. Harris, Site. Vice President, PTN J. B. Hosmer, Director, Nuclear Engineering V. A. Kaminskas, Technical Department Supervisor L. W. Pearce, Operations Superintendent

0. F. Pearson, Vice President C. A. Pell, Assistant to Senior VP - Nuclear Operations D. R. Powell, Supervisor - Regulation Compliance (effective 8/I/89)

G. Smith, Services. Manager - Nuclear R. J. Stevens, Manager, Plant Licensing R. E. Talion, President M. Wayland, Assistant Maintenance Superintendent J. G. West, Manager, Nuclear Security C. 0. Woody, Acting Senior Vice President - Nuclear H. T. Young, Project Site Manager

l.,

,I).i<) W t e ~

ENCLOSURE 2 AGENDA NRC/FPL SENIOR MANAGEMENT MEETING JULY 19, 1989 12:30 PM TRAINING BUILDING - ROOM 123 INTRODUCTION Plant Status J. E. Cross Operating Events MANAGEMENT ISSUES General IMA Status K. N. Harris QA's IMA Assessment L. W. Bladow INPO Exit Overvie~ C. A. Pell MAINTENANCE MTI Findings, Status of Implementation J. E. Cross/M. Wayland and Improvements ENGINEERING Draving Update Progress and Controls S. T. Hale PRA TRAINING

- Fifth Shift of Operators K. E. Beatty SECURITY Turnover J. G. West Overtime Maintenance Support Softvare Refurbishment (Adjourn by 4:00 pm)

0 ENCLOSURE 3 MEETING

SUMMARY

This meeting was the twelfth in a series of management meetings between the NRC and Florida Power and Light following the issuance of Confirmatory Order 87-85 in October 1987. The previous meeting was held on May 10, 1989.

A plant tour was conducted by the Resident Inspectors to update NRC management on plant conditions. The formal meeting was opened by Mr. K. Harris.

Mr. J. Cross gave a brief summary of plant status and recent operational events'. He emphasized the demonstration of cooldown from outside the control room, the pressure binding of the residual heat removal suction valves, 4-750/4-751, a 100 percent pass rate for the'perations fundamentals test conducted at Atlanta, Georgia, and two inadvertent safety injection actuations due to switch labeling and post maintenance testing deficiencies. Mr . Harris discussed the IMA status. Mr. Bladow discussed gA's assessment of the IMA

. implementation and Mr. Pell discussed the INPO exit in terms of major concerns and good practices. Mr. Cross addressed improvement in several key indicators in maintenance. Mt . Wayland discussed maintenance indicators in general and assessed progress. Mr. Hale discussed the drawing update progress and the PRA status. Mr. Beatty discussed training issues and efforts to improve the training program. Mr. Beatty is now the Training Superintendent. Mr. West discussed key indicators in the security area'nd actions taken to stabilize the security force.

Mr. Ebneter made the following closing remarks regarding impressions gained during this meeting period:

The physical condition of the plant has improved.

The NRC has confidence in Mr. Harris and Mr. Cross.

Engineering is vital to helping improve Turkey Point.

Incentive programs appear to be well planned/developed.

FP&L has a good drug program. The recent drug allegations were proven inaccurate by the extensive actions taken by FPSL.

NRC, needs to see. more progress to. justify confidence.

Encouraged by what we see.

0 ENCLOSURE 4 Page 1 of 2 TABLE 1 OVERALL EFFECTIVENESS INDICATORS OF IMA ACTIVITY Z TRIP RATE ZZ. 'UTONATZC IJNPLANNKD DAYS OFF LZNK XX'V EOUZVALKNT AVAZLABZLZTY PERSONNEL EXPOSURE V NRC VZOLATZONS VX LOST TZMK INJURY RATE

'zz 0&M BUDGET VARZANCK VXX'X SAFETY SYSTEM ACTZVATZONS SZGNZFXCANT EVENTS X SAFETY SYSTEM FAZLURKS XX FORCED OUTAGE RATE

'XX EaUZPHENT FORCED OUTAGKS/

1000 CRZTZCAL HOURS

4 TABLE 2 E Y T RED I I DI R NOTE: THIS LIST OF INDICATORS NAY CHANGE DUK TO llEW CHALLEMGESt CHANGES ZN PRZORZTY OR PROCESS R RA E D IT I DI R L P RT LCO HOURS AT POWER LCO HOURS BY SYSTEN LER's PC/M's UNPLANNED SHUTDowNs PER SAFETY SYSTEM UNAVAILABILITY OPKRATZMG MONTH (D/6, AFM, SI)

MEAN TINE BETWEEN FAILURE HEAT RATE (THERMAL Ef FZCZEMCY)

PERSONNEL CONTAMINATION CONTAMINATED FLOOR SPACE OVKRTZNE TOTAL DRAWING UPDATE WORK-OFF PLANT OPERATING DOCLNENT STATUS INPO SCHEDULE INDICATOR SECURITY FORCE OVERTIICK SKCURZTY FORCE TURNOVER MANNING LEVEL TOTAL LOGGABLK EVENTS TASK CERTIFICATION COMPENSATORY HOURS LICENSED OPERATOR REOllaL EXAM PASS RATE NON-LICENSED OPERATOR EXANI Pass RaTE CONTROl. ROON DEFICIENCY TAGS INZTZAL OPERATOR LICENSE. EXAM CORRECTIVE MAZNTKMANCK BACKLOG Pass RaTE PM/CM RaTIo (PM/PN+CM) NRC. SRO UPGRanE Bus Pass RaTE NRC RKauaL ExAN Pass RaTE TRAZNZNG ATTENDANCE RATES NtmBKR oF QuaLIFIED RO's/SRO's INITIAL LICENSE OPERATOR COKPLETZON RATE OVERTIME PERATI FUEL RELIABILITY SQLID (RADIQAcTIYK) MasTE DzsPosKD

RE 6 QNI IlY 0 INDEPENDENT CHECK MECHANISM 0 TOP PRIORITY JOB

'0 OBJECTIVES IMP LEMENTATION QUAI ITY EFFECTIVENESS 0 PERFORMED TWO ASSESSMENTS MARCH 22, 1989 JULY 12, 1989

o DO YOU KNOW OP, OR ARE YOU PAHILIAR MITH YOUR OEPARTNRMP'8 GOALS AND ASSOCIATED TARGETS'P o DO YOU KNOW WHERE TO FIND THE STATUS OF EACH OF YOUR DEPARTMENT'S GOALS?

o DO YOU BEXIEVE THAT THEY ARE o DURING DEPARTMENT MEETINGS, ARE GOALS AND TARGETS DISCUSSED?

o IS YOUR INPUT SOLICITED?

o DO YOU BELIEVE THAT YOU Qgf CONTRIBUTE TO MEETING YOUR DEPARTMENT'S GOALS?

o ARE YOU SATISFIED WITH THE AMOUNT OF INFORMATION YOU RECEIVE REGARDING DEPARTMENTAL AND SITE GOALS?

o DO YOU KNOW WHAT YOUR SUPERVISOR EXPECTS FROM . YOU REGARDING THESE GOALS?

o DO YOU KNOW WHAT DIRECTION YOUR DEPARTMENT IS GOXNG (BETTER OR WORSE)?

Page l of 3 hill ~a a: MAJl A ACIfIPVIE1GES IRlEMAIIMINQ IESlflIMA'If Rcv. C J2'J Jg9 AREAS l989 l99l l992 lt} M} st} it} <<} it} 2f} lV St} it> <<} lt} lt J Leadership Effort tu cnhancc uals, indicators and pcr funnancc mc ucs duwn through thedcparuttcntal Ic l,complctcd I

July 3l Corporate Staff

~

Actions in phtcc whii t unprovc mechanisms for transfer of nuwlcdgc bclwccn plants Junc l Maintenance

~Vacant su Octo rvisuty/management pusitiuns filled r2 fmplcm nt funhcr systematic material conditi upgrades tobcr 3I Training

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peag Icrnt rcqualificatiun ccovcry plan dcvclopcd May lS Si tulator certification Dcccmbcr 3l

~Simulator c ginccrs on board Sept nbcr 30

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Special training Junc 30 fw aintcnancc h4 Planners complete Sl 'clat uatuuig tul technical Speclttceu vis uNuplcte Dcccmbcr 3 l ial training fur instructor Dcvclopm a and Ccrufication Program (IDCP) P lot (ShT Courses) complete Dcccmbcr 3l

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Special training fur S stem Enginccrs and Engineerin Staff omplctc June30

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Actions tu reduce July 30 acklug of uaining material changes ci uplctc

4'

.. ACHRMMMIRIRMAMIN4 of 3 IMI'IINIA'ii'IESCGMlPKIm Rcv. 4/27/59 AREAS l9$ 9 l990 1991 l992 2Q 3Q 4Q tQ Jt) 3Q 4Q 2Q 3t) ~Q Engineering Dcstgo Basta Rccunst tuuun wutk un currently sclcctcd systc <<s cumplclc

~. Junc 30 ign Basis Reconstitution wutk on add 'onal sclcctcd systems cutnplctc Dcccmbcr 3l

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PRA in place and util Junc 30 Drawing Update Backlog climinatcd Dcccntbcr 3l Jn lcmcnl PC/M process improvcmcnls Technical Support Dcccmbcr 31 Complctc proccdurca Rout Cause Anal Progr

~Junc 30 Drawing Change Rcq csl Process standardized

~Junc 30 Ct nplctc Tcchnical Supporl staffing (in luding System Enginccrs)

Dcccmbcr 3l l

i Rcd<< tI<<<<arhiovcd in conuactur are <<lily fw ~ turn<<vcl lit less thNl llc cital 1<<jllv Sccttriry ILcct<<her Jl pictc Security System Upgrades Dcccmbcr 3l A( attdatiuns front SPEE analyzed andre punsivc aclion implcmcnlcd tobcr 3l

.pjpeuQl~ II; gAJI .~ ~~9flIVIIIESlRIENIAIINjtgQ Page 3 IESlI'Il IEIOt tLGMPILIElllIGN SAVES Rcv. CmW AREAS l989 199l l992 2Q 4(J lg (j 4Q l lQ 2Q )() It)

Aclluns ul (Ilal c wlllt(l utquvc Illlclu4(ruttatllzatlutlfor a Nlll cd eltltuuachluNRC (tuc>(sic Licettsittg lunc ($

~Hcw Technical Specific lions sublniucd to NRC luncS !

Eapcctcd 4 uancc uf ncw Tcchnical Specification hy NRC 0'll f2 Pl l staffed up to authxizcd complc , allowing for FPUs historical Dade C unty personnel turnover rale Resource Management Dcccmbcr 3l Analyze and initi~ actions to cffcctivcly prioritize on.si work acuvitics,

~

including acuons t improve integrated Schedule System July 3l rfurmance

~Analysis and c untcrn>casurcs in place to achieve ~ rc uclion uf overtime August Nuclear Computerized Data gcmcnt System (NlMS) cututjlc teat December 3I

~

Position of Sccuruy lunc l Opc ations Manager lillcd

0 e

ENCLOSURE 6 Page 1 of 23 P RIMARY REASONS OF IMPLEMENTATION INADEQUACY NRC MAINTENANCE INSPECTION DEC 88 1

HIGH EQUIPMENT FAILURE RATES 2 POOR PLANT APPEARANCE 8c EQUIPMENT CONDITION 3 =AVOCATION OF RESOURCES, PARTS, PERMANENT--STAFF- " --.

4 INADEQUATE ENGINEERING SUPPORT 5 INSUFFICIENT QC INSPECTORS 6.= PfGRK ORDER. CONTROLS 8c JOB PLANNING 7 PROCEDURE DEVELOP MENT 8 PARTS CONTROL 9 TURNOVER, OVERTIME 8c PERFORMANCE APPRAISALS

INDICATORS o KEY INDICATORS FOR MAINTENANCE UNPLANNED DAYS OFF LINE BACKLOG PLANT WORK ORDERS (PWO)

CONTROL ROOM DEFICIENCY TAGS o REWORK PM/PM+CM RATIO o VIOLATIONS o PERSONNEL EXPOSURE o INJURY RATE BUDGET vs ACTUAL

gJ 0

PRESENTATION OVERVIEW MAINTENANCE STATUS UPDATE/INDICATORS UNPLANNED DAYS OFF LINE BACKLOG o STAFFING o MATER IAL o PLANNING SCHEDULING REWORK o TECHNICAL SUPPORT PM/PM+CM RATIO PROCEDURES PEOPLE ISSUES o INJURY RATE o EXPOSURE o TURNOVER o OVERTIME MAINTENANCE MONITORING o MATERIAL CONDITION o ACCOUNTABILITY

PLANT CM BACKLOG TREND CURVE MECHANICAL CM BACKLOG TREND CURVE-JUIK 29, 1969 49K 29, 1989 1.5 1.7 1.6 1.5 IA 1.3.

1.2 1.1 0.7 a6 0.5 OA 04 02 al 0

'I/12/6$ 1/26 2/9 2/23 3/9 3/23 4/6 4/20 5/4 5/24 6/I 6/15 6/29 I/12/6$ 1/26 2/9 2/23 3/9 3/23 4/6 4/20 5/4 5/24 6/I 6/15 6/2$

0 roQL 0 roQL IAC CM BACKLOG TREND CURVE ELECTRICAL CM BACKLOG TREND CURVE JQC 29, 1969 AJI6: 29, 1969 I/12/691/26 2/9 2/23 3/9 3/23 4/6 4/20 5/4 5/24 6/I 6/15 6/29 I/12/691/26 2/9 2/23 3/11 3/23 4/6 4/20 S/4 5/24 6/I 6/I 5 6/29 a ropL 0 rom pcs rRtsprII

()i

PLANT CM BACKLOG TREND CURVE TROUBLE Bc BREAKDOWN 2500 GOOD

~ TOTAL 2000

~ GOAL 1500 1000 500 0

9/86 12/86 3/87 6/87 9/87 12/87 3/88 6/88 9/88 12/88 3/89 6/89 DATE U3 U4 OUTAGES~

OUTAGES~

l~

18cC STAFFING AUTHORIZED l8cC SPECIALISTS 65 l8cC SPECIALISTS ASSIGNED TO SIMULATOR 3 I8cc POSITIONS AVAILABLE FOR PLANT MAINTENANCE 62 STATUS OF 62 AUTHORIZED POSITIONS 42 QUALIFIED ISAAC SPECIALISTS 4 . NOT QUALIFIED 2 AP PR ENTICES 48 - TOTAL FP&L 10 CONTRACT TECHNICIANS WORKING 58 - TOTAL WORKING - 7/19/89 8 ADDITIONAL CONTRACT COMPLEMENT 88 - TARGET POSITIONS AVAILABLETO WORK BACKLOG & EMERGENT WORK

l CONTROL ROOM DEFICIENCY TAGS JANUARY 1988 JULY 1989 300 280 GOOD 260 240 220 V)

(3 200 O

180 Z

EJJ 160 O

la LLI 140 O

4 120 O

O 100 Z

80 60 40 20 0

CO CO CO C3 C3 CO CO CO g~)

PO PO C3 C3 C3 C3 CO CO CO CO CO C3 CO N V) + IO 4 4 CO Ol CV 6 + 6 4 WEEK OF THE YEAR a TOTAL + 12 MONTH POLI;1RtOTAC I

l

CONTROL ROOM INSTRUMENT OUT OF SERVICE TURKEY POINT UNIT 3 dc COMMON 120 109 110 GOOD 90 87 78 0 78 w 80 76 8 70 66 60 8 5

51 50 48 47 48 44 44 K 40 40 30 20 10 M J J A S 0 N 0 J F M A M J J A S 0 N 0 J F M A M J 1987 1988 1989 CONTROL ROOM INSTRUMENT OUT OF SERVICE POINT UNIT 4 120 110 GOOD 79'URKEY "101 100 90 80 70 70 67

'9 63 64 60 58 53 5 50 47 47 41 41 40 31 30 7 20 10 M J J A S 0 N 0 J F M A M J J A S 0 N 0 J F M A M J 1987 1988 1989 PC LI 'CR SNOP

4 PWO'S AWAITING PARTS AS OF 7/7/89 350 300

~ MECH O

250

~ l&C 200

~ ELEC O ~ TOTAL 150 100 ~TARGET l 50 0 Ch IQ CO c4 WRW 7/7/89 DATE l PQ4 PWOLNE1

PLANNING NEED FOR BETTER INDICATORS PLANNING 8c WORK CONTROL REVIFW EVALUATING TRAINING ADEQUACY

TURKEY POINT NUCLEAR PLANT TOTAL JOB STARTS ON PLAN OF THE DAY'00 90 ACTUAL.

80 I

70 O

60 50 40 30 20 GOOD 10 Ql Ol OQ 00 07/07/89 ECK DATE PGil POKFFEC

0 TURKE Y P OINT NUCLEAR P LANT SCHEDULE START CLEARANCE DELAYS, 100K 90%

80%

~ CLEARANCE OELAYS

>- 70%

60%

o 50%

40%

O 26%

30% 23%

20% 13%

10% 5%

0% Ch IQ 00 CV DATE 1989

SYSTEM ENGINEERS PERMANENT FP8cL STAFFING CONTRIBUTIONS EMERGENCY DIESEL GENERATORS RHR PUMP SEALS CCW HEAT EXCHANGERS LCO ANALYSIS r SYSTEM ENGINEER / MAINTENANCE TEAMWORK

'0 PLANT MAINTENANCE PM/PM+CM RATIO'00 JUNE 1987 TO JUNE 1989 90'0 GOOD o TOTAL GOAL 70 60 o 50 40 30 20 10 0

I, IO h CO ~ 0 4 CAC g y IO IO c3 ca I ol co co 6

>6 co co 4

co co

+

co 4

co co co co l U3 U4 OUTAGF~ I GUIAGES-~ I ,

DATE l~ I

PROCEDURES PREPARATION CHECKLIST PLANT CHANGE UPDATE. PROCESS F,IRST USE VALIDATION MAINTENANCE FEEDBACK SESSIONS REVIEW OF "PROBLEM" PROCEDURES

/

TURKE Y P OINT NUC MAR 1989 LOST TIME INJURIES 0.9 M GOOD LLI LLI Or8 O

Or7 CL LLI Or6 D 0.53 O r

.ch 0.5 ~

EL 0 0.4 Or3 Or2 0.13 0.13.-" 0.13 0.13 r

0.1 ~ r rr 0 ..-r"0 0

JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC DATE: 6/30/89 BY: J. Pizzotelli SOURCE: STAFF

e TURKEY POINT PLANT MAN REM BY YEAR I

~

1400 I.

g 1297 1200 1200 1200 1000 89

~ TOTAL SITE 800 691 600 '

'-, 456 400 GOAL SITE 200 0

1984 1985 1986 1987 1988 1989 YEAR 4g '+ i i' ll 0

TLJRNOVER INC TROUBLE SPOT STAFFING VARIANCES APPROVED OVERTIME MODERATED OPERATOR RETENTION COUNTERMEASURES

TURKEY POINT NUCLEAR UNITS 3 8c 4 MONTHLY OVERTIME PERCENTAGES BY DEPARTMENT 60 X LEQEHQ'ECHANICr4L MAINTENANCE GOOD

~~~ ~ IIOMTILY YQR-~K 60 X 40 X 1989 TJJCET 20 X 0+ 0 e 23 X JFM A MJJ'A'S 1989 ON D 3ZGEZlQ'ONIII.Y GOOD YKAR-TO~K

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 22 ~ ~

29 X

'20 X J F M A M J J A S 0 N D 1989 LECKRh ELECTRICPI. MAINTENANCE

~ IKNMY

%4 70&%

GOOD Q

40 5

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ oe ~ ~ ~ ~ ~ ~ A ~ ~

10'K&

gO 20 X J F M A M J J A S 0 N 0 19&9 PC II'OTCOIJB&9

MATERIAL CONDITION SYSTEM WALKDOWNS CONTAMINATED FLOOR SPACE EQUIP MENT IDENTIFICATION AP P EARANCE PAINT UP, FIX UP ACCOUNTABILITY STANDARDS

TURKEY POINT UNITS 3 8c 4 CONTAMINATED FLOOR SPACE 89865

~ CONTAMINATED FLOOR SPACE 78631 LIJ (3

--- EXCLUDED CL 67398 NOTES CONTAINMENTS ARE NOT INCLUDED O 56165 O

44932 C)

LLJ 33699 5

22985 22126 20446 22466 16&11 15206 16767 16273 18680 6 8 13978 O 13088 13183 13248 O 17679 11233 11239 14248 11064 0

1 2 3 4 5 6 7 8 9 101112 1 2 3 4 5 6 7 8 9 101112 1988 1989 MONTH

MATERIAL CONDITION SYSTEM WALKDOWNS CONTAMINATED FLOOR SPACE

.EQUIP MENT IDENTIFICATION AP P EARANCE PAINT UP,,FIX UP ACCOUNTABILITY STANDARDS

ACCOUNTABILITY COMMUNICATE RESPONSIBILITIES MEASURE PERFORMANCE IND IVIDUALS MANAGERS SELF EVALUATION EXTERNAL ASSISTANCE IN EVALUATIONS

ENCLOSURE 7 Page 1 of 17 N INEER!N 0 MAINTENANCE SUPPORT 0 DRAWING PROGRAM UPDATE 0 PRA UPDATE 0 IMA INDICATORS 0 OTHER ACTIYITIES

MAINTENANCE SUPPORT 0 FEEDBACK/PARTICIPATION OF MAINTENANCE IN TECHNICAL DEPARTMENT/NUCLEAR ENGINEERING P R I OR ITIZATI0 N OF ENGINEERING WORK REQUESTS.

0 GREEN TAG REDUCTION EFFORTS 0 SPARE PARTS

CONTRQL ROOM GREEN TAGS

~ Daily Interface with Maintenance

~ Dedicated Design Engineering Resources

~ Support Procurement Activities

0' SPARE PARTS

~ Commercial Grade Dedication

~ Backlog Reduction

~ Standardization of Process

~ Development of Screening Criteria

~ Daily Procurement Coordination Meetings

0 Unit 3 Outage Committed Material Evaluation status thru 7/t/89 Remaining Items 1/89 2/89 3/89 4/89 5/89 6/89 Date

~ Evaluations issued

PDRT Backlog Reduction Project Status Indicator thru Week Ending 7/17/89 Ac ual erf rm nc S eNote Ta get 4/10 4/17 4/24 5/1 5/8 5/15 5/22 5/29 6/5 6/12 6/19 6/26 7/3 7/10 7/17 Date Note: Actual evaluations remaining in project scope. An additional 110 items assigned to backlog project after scope defined.

PORT Backlog Reduction Project Manhours per Evaluation Indicator thru Week Ending 7/17/89 Aver ge n-ho rs p eval ation ctual an-h urs r ev luatio (we kly)

Dat Coll ed 4/10 4/17 4/24 5/1 5/8 5/15 5/22 5/29 6/5 6/12 6/19 6/26 7/3 7/10 7/17 Date

DRAWIN PR RAM UPDATE 0 COMPLETED COMMITMENTS 0 INDICATORS DRAWING WORKOFF CURVE STAFFING

MPLETED MMITMENT 0 MANAGER NAMED DE 0 I GATED BECHTEL GROUP CONTRACTED 0 DRAWING CHANGE TRACKING SYSTEM IMPLEMENTED ON MAINFRAME COMPUTER. ON-LINE TRACKING OF ALL CHANGE PAPER AGAINST PLANT RECORD DRAWINGS (EP, DEEP, DCR, CRN).

RESPONSIBLE DEPARTMENTS INPUT DATA TO TRACK PROGRESS FROM DESIGN THROUGH UPDATING.

,0 PROCEDURE ISSUED TO IDENTIFY RESPONSIBILITIES, INTERFACES, AND INSURE ON-GOING PROCESS AFTER COMPLETION OF BACKLOG WORKOFF.

IMPROVED COMMUNICATION,TEAMWORK.

'4 t

TOTAL DRAWING UPDATE WORKOFF

- TURKEY PONT UNITS 3 dc 4 28 26 24 22 g 20 18 16 14 Do 10 FORECAST~'

TARGEf ACTUAL DWGS WORKED 4047 0

2/17 6/30 12/29 6/29 12/28 6/28 12/27 6/26 12/25 1989 1990 199i 1992

~ ACTUAL

Reperl DalrI 06/2 Report Nurqber 7 DRAWING UPDATE GROUP PROPOSED STAFFING TURKEY POINT UNITS 3 8c- 4 Z ~

20 10 0

2/17 6/30 12/29 6/29 12/28 6/28 12/27 6/26 12/25 i989 i990 199i i992

~ ACTUAL FORECAST

PRA PDATE 0 CONTRACT AWARDED TQ SAIC ON 8/23/89 0 DETAILED SCHEDULE DUE FIRST WEEK IN AUGUST MANAGEMENTDECISIQN TO INCLUDE FIRE PRQTECTIQN AND HURRICANES OVER AND ABOVE PRESENT NRC REQUIREMENTS (GENERIC LE%I ER 88-20) e 0 PERMANENT GROUP WITHIN ENGINEERING BEING FORMED TO:

USE AND MAINTAINTHE TURKEY POINT PRA I

CONDUCT, USE AND MAINTAIN THE ST. LUCIE PRA MEETING WITH NRC IN APPROXIMATELY TWO MONTHS TO DISCUSS DETAIL'"

0 . PRA USEAGE AND BENEFITS

PRA EAGE AND BENEFITS

'.WILL ASSIST IN FOCUSING AND PRIORITIZING MAINTENANCE ACTIVITIES WILL IMPROVE OUR ABILITYTO EVALUATE AND PRIORITIZE ENGINEERING WORK REQUESTS WILL SIGNIFICANTLY IMPROVE OUR ABILITY TO ADDRESS KEY REGULATORY ISSUES MOST IMPORTANTLY, WIL'L PROVIDE A

. CONSISTANT LEVEL OF UNDERSTANDING THROUGHOUT NUCLEAR ENERGY OF THE SYSTEMS AND EQUIPMENT IMPORTANTTO SAFETY

l 0

IMA INDICATORS 0 TURKEY POINT DRAWING UPDATE WORK-OFF (SHOWN PREVIOUSLY) 0 EP OUTAGE INDICATOR

{UNIT 3 CYCLE 12 OUTAGE PCM's}

e DEPARTMENT PERFORMANCE INPO EP OUTAGE INDICATOR ST. LUCIE PERCENTAGE OF TOTAL REFUELlNG OUTAGE PACKAGES ISSUED 2 MONTHS PRlOR TO OUTAGE 100%

90%

TARGET~95% (HI 80% I g I I

60% I I

40%

I 0

I l

I 2ox I I

IJMT 1 LNT 2 LNT 1 AL 88 FEB 89 JAN 90 (FOR ECAST)

TURKEY POINT 100%

TARGET~95% I 80% l g l l

I l

35% l l

l l

l 0%

UMT 4 (NO SCHEDULEO UNT 3 SEP 88 FEB 90 OUTAGE) (FORECAST) 1989

e UNIT 3 CYCLE 12 OUTAGE RELATED PCM'S LEAD TIME STATUS REPORT PTN I 70

/

60 r r STATUS AS OF JULY 11, 19B9 I

// FORECAST TOTAL PCM'S I PCLI'S SSUEO TO gATE 22 I PC@'S AHEAD OF SCHEDULE 63 50 I m I

I V 4J PCll'S BERM) SCfKOULE 2 4

I a 4J X COlPLDE PARGET 95J') 971~

I I Q.

I

.40 I I 0 0 I O I (3 I

I Z Z I K LLJ I 4J 30 I 4J I

I Z

I C9 K Z

4J C4 20 t

4J O

O LECEND CIIIIL.ISSLCO TO OITE ~

10 I- ASCII'S FCST ISQXO IIONlHLT Q K

~ ~

LIT PCLFS eeao SXaXAZ Q 0

M J J ASOND J FMAM J J ASOND J FMA 1988 1989

OTHER A TIVITIES 0 NEW AGGOUNTABILITIES 0 STAFFING 0 50.59 ACTIVITIES

e ENCLOSURE 8 Page 1 of 6 Turkey Point Nuclear Plant MONTHLY MANAGEMENT MEETING Training, Overview July 19, 1989 STAFFING:

~ COMMENCED FIFTH SHIFT ROTATION (OPERATIONS) 6l24l89

~ PROVIDED NEW CREW WITH 1 WEEK OF SIMULATOR TEAM TRAINING PRIOR TO SHIFT ASSIGNMENT

~ SENIOR MANAGEMENT PARTICIPATED IN EVALUATIONS OF ALL CREWS

~ SIX SHIFT ROTATION SHOULD OCCUR BY MID-DECEMBER

~ LICENSE EXAM SCHEDULED FOR NOVEMBER

~ CROUP 11 1/2; SIX RO's UP-GRADE GROUP; FOUR SRO's TOTAL: 10 INDIVIDUALS

'ADDITIONAL LICENSE CLASS ADDED (GROUP 13)

~ GOAL ~ 15-25 OPERATOR CANDIDATES (INSTANT SRO's)

~ COMPLETED INTERVIEW PROCESS 6/1.7/89; 29 CANDIDATES ACCEPTED I'

CLASS START DATE: AUGUST 1989

~ TENTATIVE LICENSING DATE:

OCTOBER 1990

e

~ IMPROVE NLO SUCCESS RATE IN BECOMINC RCO's

~ REFORMATTED AND EXPANDED FUNDAMENTALS TRAININC LATEST RESULTS (NRC FUNDAMENTALS EXAM): 1 00% (32/32)

~ STUDENT FEEDBACK: "OUR TRAININC PREPARED US WELL FOR BOTH THE COMPANY AND NRC FUNDAMENTALS EXAM"

~ INCREASED "P.O.S.S." APTITUDE CUTOFF SCORE FROM+TO Q

% MONITORINC OPERATOR CAREER PATH PROGRAM FOR ADDITIONAL IMPROVEMENT OPPORTUNITIES

REQUALIFICATION REMEDIATION:

~ 1 00% SUCCESSFUL ON N RC ADMINISTERED RE-EXAM

~ PROVIDED INCREASED SIMULATOR PRACTICE ON COMPLEX MALFUNCTIONS AND PROCEDURES USAGE ..

EMPHASIZED TEAM BEHAVIOR

~ TRAINED AND EVALUATED STUDENTS ON ALL NEW JPM's .

~ PROVIDED >120 HOURS ADDITIONAL CI.ASS ROOM TRAINING AND EXAMINED STUDENTS USINC "OPEN REFERENCE" EXAM QUESTIONS

0 REQUALIFICATION REMEDIATION:

~ 1989-90 REQUALIFICATION PROGRAM MODIFIED

~ INCREASED SIMULATOR TRAINING TIME

~ ADDED JPM TRAINING AND EVALUATIONS TO EACH CYCLE

~ USING OPEN REFERENCE EXAM FORMAT

~ THIRD PARTY ASSESSMENTS -TRAINING EFFECTIVENESS~ WESTINGHOUSE'NERCON~

AND INPO i 1989-90 REQUALIFICATION PROGRAM OBJECTIVE: 90% PASS RATE ON NEXT NRC REQUALIFICATION EXAM (MARCH 1990)

LICENSE RETENTION COMPENSATION

REQUALIFICATION REMEDIATION:

0 INTERMEDIATE PROGRAM INDICATORS

, ~ ACHIEVE AND MAINTAIN95% SUCCESS RATE ON WEEKLY EXAMS AT LEAST 95% OF ALL LICENSE HOLDERS PASS THEIR ANNUAL FP&L WRITl EN EXAMS WITHOUT REMEDIATION

~ CREWS MUST PERFORM CRITICAL STEPS WITHOUT ERROR DURING SIMULATOR EVALUATIONS AND BE EVALUATED SATISFACTORY OVERALL

~ INDIVIDUALSSUCCESSFULLY COMPLETE ALL ASSIGNED

)PM's

~ IMPROVE/MAINTAININSTRUCTOR COMPETENCY

+ INSTRUCTORS GIVEN ADDITIONALTRAINING IN EVALUATIONAND CRITIQUING TECHNIQUES

+ EVALUATE AND DISPOSITION STUDENT FEEDBACK WEEKLY

+ ACTIVE INSTRUCTORS MUST DEMONSTRATE THElR TECHNICAL AND INSTRUCTIONAL COMPETENCIES AT LEAST ANNUALLY

Enclosur

THE SECURITY FORCE TURNOVER PERCENT

]00 80 60 ~~ ~ ~~

~ ~ ~ ~~~~ ~ ~ 0 0 ~ ~

20 0

JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DE

'1988 1989

t I

0 0

0

SECURITY FORCE OVERT ME FOR 1988 AND .1989 PERCENTAGE 100 80 ~~ ~~4 %tO ~ ~ ~ ~ ~ ~ ~ ~ ~ ~~~ ~ ~ (I ~ e ~~ ~~ ~ ~ ~ ~ ~ ~ i ~~~~ ii

~

~ ho ~ ~ oo ~ ~ ~ ~ ~ ~ ~

60 ~~~~ ~~~ ~F0 ') ~ ~~ ~ ~ A ~~~ ~ ~

40 ~ ~~ ~~~~ ~ ~ ~ ~ ~~ ~ ~ ~ ~ ~ ~ ~ ~ ~~ ~~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~~ ~ ~

20 ~~ ~~~ ~~

0 JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC MONTHS 1988 1989

I V

~

~ wee el ~ ~ ~ . ~ a ~ pl ~

i ~ ~ ~ ~ q, COMPENSATORY HOURS WORKED SY TI-IK SKCVRITY FORCE DUE TO EQUIPMENT I'AILURKS FOR 1988 AND 3044 HOURS 5,000 4,000 3,000 2,000 1,000 0

JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC MONTHS 1988 1989

TOTAL LOGGABLE EVENTS BY QUARTER 1S88 THRU 1980 EVENT TOTAL 170 160 ~ ~ I~~ ~ 0 ~

150 140 ~ sgl ~ ~ ~ ~ ~ ~~ ~

130 120 110 1ST QTR '88 3RD QTR '85 1ST QTR '89 2ND QTR '88 4TH QTR '55 2ND QTR

'VENTS

D e

ML17347B285

Contents

Text

1.0 INTRODUCTION

SUMMARY

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1.0 INTRODUCTION

5.0 NOTES

SUMMARY

SUMMARY

1.1 DESCRIPTION

SUMMARY

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ML17347B285

Text

1.0 INTRODUCTION

SUMMARY

SUMMARY

1.0 INTRODUCTION

5.0 NOTES

SUMMARY

SUMMARY

1.1 DESCRIPTION

SUMMARY

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