ML20083Q841

Rewrite of Rev 2 to Engineering Work Instruction (Ewi) EWI-09.04.01, Inservice Testing Program

ML20083Q841
Person / Time
Site:	Monticello
Issue date:	05/18/1995
From:	Carstens D NORTHERN STATES POWER CO.
To:
References
EWI-09.04.01, EWI-9.04.01, NUDOCS 9505260221
Download: ML20083Q841 (129)

Text

18-MAY-1995 Northern States Power Ccxnpany Page 1 .

Monticello Nuclear Generating Plant Document Control Distribution System

• s Document Distribution Manifest Controlled Documents - Current

• 014 Name: . . US NRC Manifest Number: 95-0119 Date Mailed:

g 81995' M

Title:

ATTN: DOCUMENT CONTROL DESK Distribution Type: M '

N Company: U.s. NUCLEAR REGULATORY AGENCY Manual Number: 195 M Location: WASHINGTON, DC 20555 ID Number: YYYYO9 .

00 ATTN: DOCUMENT CONTROL DESK Ru- - . .

x* Document Type Document Number Revision Title

• i O

Ug NOTE: Please insert the following issues in your manual, remove and destroy superceded material low 8o0 3C15 INDEX 8 ENGINEERING WORK INSTRUCTIONS INDEX 3005 EWI-09.04.01 2 INSERVICE TESTING PROGRAM 3",.M D ,

u Your IST Manual is superseded by the distribution of EWI-09.04.01.'

Please destroy your IST Manual.

f m -

AnF Receipt Acknowledgment Note: All previous issues have been removed and replaced with issues received.

MD 95-0119 Received by:

Signature Date:

M YYYYO9 Q 195 Return within two weeks to: Document Control, Monticello Plant, P.O. Box 600, Monticello, MN. 55362

. _ _ _ _ _ _ _ _ _ _ _ . - _ _ _ - _- - _ - - - - - - __--,~-n ,m<a - --~~-,e- --,.ma. ..en. ..-e , ..s-e , , , - -

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MONTICELLO NUCLEAR GENERATING PLANT INDEX TITLE: ENGINEERING WORK INSTRUCTIONS Revision 8

(~) (EWI) Page 1 of 1 V

. REVIEW AND APPROVALS .

Prepared By: M ,gaf n p  ; y Approved By: [j/6 / g ' l ')d , l'g/ g M Effective Date: % // 7 /B j g Hesp Supv: GSE lAssde Rot: EW6 MAN / ' J SR: N Frea: 0 ivrs f.

ARMS NA l Doc Type: 3005 l Admin Initials- l Of - Date A ll9 /l, .-

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EWl.El TITLE REVISION EWl 01.04.04 SYSTEM ENGINEERING GROUP ORGANIZATION AND RESPONSIBILITY ASSIGNMENT 0 EWl-03.13.10 PLANT ENGINEERING TRAINING PLAN 0 EWi-04.05.01 THERMOGRAPHY PREDICTIVE MAINTENANCE PROGRAM 0 EWi 08.02.01 SNUBBER PROGRAM 0 EWl-08.02.02 STRATEGIC REFRIGERANT PLAN 0 EWl-08.04.02 RELIEF VALVE TESTING AND REPAIR 0 EWl-08.05.01 EROSION / CORROSION PROGRAM 0 EWl-08.09.01 SYSTEM ENGINEERING GROUP TRENDING PROGRAM 1 EWi-09.04.01 INSERVICE TESTING PROGRAM 2* l

• Inservice Testing Program, Rev.1, issued 12/2/92, was assigned number EWl 09.04.01, Rev. O, on 8/8/94 to make the INSERVICE TESTING PROGRAM a part of the Controlled Documents for ,

Monticello Nuclear Plant. We are bypassing EWl-09.04.01, Rev 1, and issuing Rev. 2 to maintain consecutive revisions for the Inservice Testing Program Third Ten-Year Inspection Interval, May 31,1992-May 31, 2002.

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MONTICELLO NUCLEAR GENERATING PLANT EWi-09.04.01 TITLE: INSERVICE TESTING PROGRAM Revision 2*

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Page 1 of 126 ENGINEERING WORK INSTRUCTION - TABLE OF CONTENTS SECTION PAGE 1.0 I N T R O D U CTI O N . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 1.1 Relationship with Technical Specifications . . . . . . . . . . . . . . . . . . . . . . . . . . 5 1.2 Qualification of Test Personnel . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 1.3 IST Program Component Selection Criteria . . . . . . . . . . . . . . . . . . . . . . . . . 5 1.4 Component Tables and Figu res . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 2.0 PUMP INSERVICE TESTING PROGRAM . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 3.0 VALVE INSERVICE TESTING PROGRAM . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 3.1 Containment Isolation Valves . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 3.2 Pressu re Isolation Valves . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 3.3 C R D Va l v e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 3.4 D e f e rre d Te st i n g . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 3.5 Pa rt-st roke Te stin g . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 3.6 Fail-S afe Act u at o rs . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 3.7 Valve Position Indication Verification . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8

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3.8 Pa s s ive Va lve s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 3.9 S t ro k e Ti m e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 4.0 R E LI E F R EQ U E STS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10 4.1 Pump Testing Relief Requests . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10 4.1.1 P R-1 (TEST M ETH O D) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10 4.1.2 P R-3 (I N STR U M E N T R A N G E) . . . . . . . . . . . . . . . . . . . . . . . . . . . 11 4.1.3 P R-6 (H PCI VIB RATION) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12 4.1.4 PR 8 (CALCULATING INLET PRESSURE) . . . . . . . . . . . . . . . . 14 4.1.5 PR-9 (INSTRUMENT RANGE) . . . . . . . . . . . . . . . . . . . . . . . . . . . 15

'This is a major rewrite, therefore, no sidelines are required.

REVIEW AND APPROVALS n Prepared By:(()g CM Reviewed BM[gQ OC Review Req'd: YES j OC Meeting Number: /q35 Date g jf 9g Approved By:

(( h _) Date:.pp- f[

p . _. a Jiu.di . amFOR ADMIN _lSTR,ATIV,E_,Us,E,0N,LL .

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Q 3087 (PROCEDURE / FORM CHANGE AND HOLD NOTICE) incorporated:

Resp Supv: GSE 9 h, . ;_gEdo3 N_OIlh l I Assoc Ref: AWi-09.04.01 l \ flSR: Y Frea: 2/ yrs i ARMS: 09.04.01 l Doc Type: 3005 I Admin Initials:l 8 7 Date:6/ /i//)6 I

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MONTICELLO NUCLEAR GENERATING PLANT EWl-09.04.01 l l

TITLE: INSERVICE TESTING PROGRAM Revision 2* l Page 2 of 126 I l

ENGINEERING WORK INSTRUCTION - TABLE OF CONTENTS (Cont'd)

SEC1LOH PADR 4.2 Valve Testing Relief Requests . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 17 4.2.1 RBCW-1 (EXERCISE EACH REFUELING) . . . . . . . . . . . . . . . . 17 4.2.2 ESW-1 (TEST CHECK VALVES AS PAIRS) . . . . . . . . . . . . . . . . 18 4.2.3 SC-1 (DISASSEMBLY TEST OF CHECK VALVE GROUP) . . 19 4.2.4 N B-1 (S RV TESTI N G) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 20 4.2.5 REC-1 (EXERCISE EACH REFUELING) . . . . . . . . . . . . . . . . . . 22 4.2.6 CRD-1 (TESTING DURING SCRAM TEST) . . . . . . . . . . . . . . . 23 4.2.7 CRD-2 (TEST EACH REFUELING) . . . . . . . . . . . . . . . . . . . . . . . 24 4.2.8 RHR-1 (DISASSEMBLY TEST OF CHECK VALVE GROUP) . 25 4.2.9 CS-1 (TEST CHECK VALVES AS PAIR) . . . . . . . . . . . . . . . . . . . 26 i

4.2.10 SLC-1 (TEST EACH REFUELING) . . . . . . . . . . . . . . . . . . . . . . . 27 4.2.11 RWCU 1 (TEST EACH REFUELING) . . . . . . . . . . . . . . . . . . . . . 28 4.2.12 IA-2 (TEST EACH REFUELING) . . . . . . . . . . . . . . . . . . . . . . . . . 29 4.2.13 SW-1 (TEST CHECK VALVES AS PAIRS) . . . . . . . . . . . . . . . . . 30 4.2.14 ESW-2 (TEST CHECK VALVES AS PAIRS) . . . . . . . . . . . . . . . . 31 4.2.15 GR-2 (LRT INCREASED FREQUENCY) . . . . . . . . . . . . . . . . . . 32 4.2.16 GR-3 (LRT DURING APP J TEST) . . . . . . . . . . . . . . . . . . . . . . . 33 4.2.17 GR-4 (STROKE TIME ACCEPTANCE BANDS) . . . . . . . . . . . . 34 4.2.18 GR-5 (COLD SHUTDOWN TESTING) . . . . . . . . . . . . . . . . . . . . 35 4.2.19 GR-7 (SP TEST LESS THAN 70 PSI) . . . . . . . . . . . . . . . . . . . . . 36 4.2.20 RSW-1 (CONTROL VALVE TESTING) . . . . . . . . . . . . . . . . . . . . 37 5.0 DEFERRED TESTING JUSTIFICATIONS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 40 5.1 Mechanical Vacuum Pump Isol Valves . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 40 5.2 R BCCW lsolation Valves . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 40 5.3 Feedwater Check Valves Backflow Test . . . . . . . . . . . . . . . . . . . . . . . . . . . . 40 5.4 M S IV Fail S afe Test . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 41 5.5 RECIRC Pump Discharge Valves . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 41 5.6 AO Testable C h eck Valves . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 42 5.7 R H R I n t e rloc k s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 42 l 5.8 H P C I Backflow Te sts . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 43 l

5.9 RCIC Backflow Tests . . .. ............. .... ...... .......... 43 l 5.10 Air to DW . . . . . . . . . ...........................................

5.11 PAS S X FV Tests . . . . . . . . . . . . . . . . . . . . . . . . .................

44 44 h i 1

5.12 Backfill C heck Valves . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 45 l l/pir 1

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ENGINEERING WORK INSTRUCTION - TABLE OF CONTENTS (Cont'd)

SECTION PAGE 5.13 X FV Te s t s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 45 5.14 AirtoDWll..................................................... 46 5.15 Air t o T- R in g Seals . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 46 5.16 Air Supply Check Valves . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 46

6.0 REFERENCES

......................................................, 47 7.0 R EQU IR ED R ECO R DS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 48 8.0 FIGURES............................................................ 49 8.1 M a in S t ea m . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 49 8.2 Fe e dwa t e r . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 50 8.3 R ea ctor R ecirculation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 51 8.4 C o re S p r a y . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 52 8.5 RHRLoopA.................................................... 53 8.6 R H R Lo o p B . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 54 8.7 HPCI(Steam)................................................... 55

% 8.8 H P C I (Wa t e r) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 56

) 8.9 R C IC (Ste a m ) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 57 8.10 R C I C (Wa t e r ) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 58 8.11 SBLC......................................................... 59 8.12 Primary Containment Atmospheric Control . . . . . . . . . . . . . . . . . . . . . . . . . . 60 8.13 EDG-ESW.................................................... 61 8.14 ESW.......................................................... 62 8.15 RHRSW....................................................... 63 8.16 CRD-HCU..................................................... 64 8.17 CRD SDV ..................................................... 65 8.18 Com pre ssed Air /FPCC . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 66 8.19 R B C C W/C ST . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 67 8.20 Liq uid Radwaste/RWC U . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 68 8.21 TIP ............................ ............................... 69 8.22 Excess Flow Check Valves . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 70 8.23 CGC, DIVI..................................................... 71 8.24 CGC, DIV ll ................................... ................ 72 8.25 Primary Containment Sampling . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 73 O

( 8.26 Diesel Generator Auxiliaries . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 74 8.27 Mechanical Vac Pump /Recirc Seal Inj . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 75 1/pir

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ENGINEERING WORK INSTRUCTION - TABLE OF CONTENTS (Cont'd)

SECTiOE PAG _Ei 8.28 Level Inst Backfill / Hard Pipe Vent . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 76 8.29 S a fe t y G ra d e N 2 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 77 9.0 ATTAC H M E N TS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 78 9.1 Pu m p Te stin g Table . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 78 9.2 Valve Table Sym bols . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 79 9.3 Val v e Te s t i n g Ta b le . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 82 l

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1.0 INTRODUCTION

This program identifies the pump and valve inservice testing that will be performed at the Monticello Nuclear Generating Plant to comply with the requirements of 10CFR50.55a and Technical Specification 4.15.B. This program applies to the Third Ten Year Inservice Inspection Interval beginning May 31,1992, and ending May 31, 2002. As specified in 10CFR50.55a(b) (1-1-91 Edition), the effective edition of Section XI of the ASME Boiler and Pressure Vessel Code applied to this program is the 1986 Edition.

In lieu of Section XI, this program invokes certain ASME OM Code pump and valve testing requirements as allowed by Regulatory Guide 1.147 and 10CFR50.55a(f)(4)(iv).

Hereafter in this document, the inservice testing requirements of ASME Section XI and ASME OM will be collectively referred to as "the Code" unless a more specific reference is necessary.

1.1 Relationship with Technical Specifications Monticello will meet all requirements of both the Code and plant Technical Specifications unless there is a s 3ecific conflict between the two. In such cases, plant Technical Specifications wil govern. Code requirements that cannot be met due to Technical Specification guidance will be identified in relief requests or g Technical Specification changes will be prepared.

V 1.2 Qualification of Test Personnel Personnel performing pump and valve testing per the Code will be qualified in accordance with the Monticello Nuclear Plant Quality Assurance Program. This is in keeping with the requirements of ASME Section XI, as clarified by ASME Code Interpretation XI-1-82-06R.

1.3 IST Program Component Selection Criteria The components selected for this program are limited to Code Class 1,2, or 3 pumps and valves as stated in 10CFR50.55a. The document that identifies Class 1,2, and 3 components at Monticello is the Color Coded P&lD Q-List Extension. This document shows components that are Quality Groups A, B and C which correspond Code Classes 1,2, and 3 respectively. These components are then judged as to whether they meet the Code scope criteria or if they are exempted from testing by the Code.

Component functions that mitigate the consequences of accidents that are beyond single failure criteria (i.e., beyond the design basis) are not included in this program. For example, valve positions that apply exclusively to Emergency Operating Procedure actions are not included as safety positions that must meet Code testing requirements.

Subcomponents of safety related pumps or equipment are not identified as I separate items and will be tested as an integral part of the inservice test. For l O example, the operational readiness of subcomponents of the HPCI pump, such V as the auxiliary oil pump and the turbine driven oil pump, is verified oy the satisfactory completion of the HPCI pump's inservice test. Similarly, subcomponents of the emergency diesel generator, such as the jacket water I/pir

MONTICELLO NUCLEAR GENERATING PLANT EW1-09.04.01 1 TITLE: INSERVICE TESTING PROGRAM Revision 2*

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cooling pump and the engine fuel transfer pump, are not included in the IST l program because they are considered to be an integral part of the emergency diesel generator and are verified by surveillance testing done on the diesel generator. In addition, such subcomponents are not designed to be individually tested in accordance with Code rules.

1.4 Component Tables and Figures The components selected for testing are listed in the Tables of Attachments 9.1 and 9.3. This program also provides system figures in Section 8.0 to be used as i schematic aides in understanding the pump testing loop and active valve function. These figures are simplified and not controlled drawings, therefore, the P&lD referenced in the tables should be used in lieu of the figures when a detailed understanding of the system is desired.

2.0 PUMP INS _ERVICE TESTING PROGRAM 1

The pump test program is conducted in accordance with Part 6 of ASME/ ANSI OMa-1988 as allowed by ASME Code Case N-465, except for relief requested under the provisions of 10CFR50.55a. Attachment 9.1 identifies the pump inservice testing performed at Monticello. This table lists each pump required to be tested, each parameter to be measured, and applicable relief requests. These relief requests are included in Section 4.1 of this program. ,

The 10CFR50.55a specification of Class 1,2, and 3 components has been used as criteria for including pumps in this program. Non-Class 1,2, or 3 pumps jud ed important to safety"are also included in the program. These pumps are easi identified  :

by the word "None in the ASME class column of the Jump testing table. Te ing of non-class pumps will be performed in accordance wit 1 the Code to the extent practical.

Relief requests will not be submitted for non-class pumps if the Code requirements can not be met.

3.0 YALVE INSERVICE TESTING PROGRAM The s ilve test 3rogram for Monticello is conducted in accordance with Subsection IWV of Section XI o the 1986 Edition of the ASME Boiler and Pressure Vessel Code, except for relief requested under the provisions of 10CFR50.55a and where all applicable  ;

portions of OMa-1988 Part 10 have been invoked. The valve testing performed is shown in the tables of Attachment 9.3. These tables are ordered by P&lD number.

Symbols used to abbreviate the valve test tables are explained in Attachment 9.2.

Valves judged important to safety but outside the scope of Subsection IWV are also l included in the 3rogram. These valves are easily identified by the word "None" in the ASME class co umn of the valve testing table. Testing of these non-code valves will be l 3erformed in accordance with the Code to the extent practical. Relief requests will not l 3e submitted for non-code valves if Code requirements cannot be met. '

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MONTICELLO NUCLEAR GENERATING PLANT EWi-09.04.01 l TITLE: INSERVICE TESTING PROGRAM Revision 2*

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Page 7 of 126 l 3.1 Containment isolation Valves Containment isolation valves (CIV) falling within the scope of the Code are tested in accordance with the Section XI requirements of IWV-3400, Category A, l with the exception of the seat leakage tests (IWV-3420). The seat leakage testing performed on these valves meets the intent of Section XI, but the actual test procedures will be conducted in accordance with the 10CFR50, Appendix J, Type C, CIV test program. See relief request GR-3 in Section 4.2.16.

All CIVs have been categorized as A-Active or A-Passive, and will, as a minimum, be leak tested per 10CFR50, Appendix J. Passive valves willin general have no other testing performed.

3.2 Pressure Isolation Valves The purpose of the plant Pressure Isolation Valves (PlVs) is to reduce the possibility of an inter-system LOCA which would occur by pressurizing low pressure systems to pressures exceeding their design limits. These Category A valves will be fully tested per IWV-3420, with the exception of relief requested under GR-2 (see Section 4.2.15).

3.3 CRD Valves The CRD valves included in this program are the scram discharge volume vent and drain valves, the scram inlet and outlet valves, the scram discharge header check valves, the charging water header check valves and the cooling water header check valves. These valves will be functionally tested during the individual rod scram time test required by Technical Specifications to be performed once each operating cycle. An additional test will be performed for the charging water header check valves each refueling.

The coolin,g water header check valve is also tested by normal control rod motion. Since each partially or fully withdrawn operable control rod is exercised one notch at least once a week in accordance with Technical Specifications, this valve will be tested at least quarterly.

3.4 Deferred Testing Valves that cannot be tested during power operation are identified by reference to a Deferred Testing Justification (DTJ)in Attachment 9.3. They are also generally identified by an FC or FR under " Tests Pfrmd". The deferred testing justifications are contained in Section 5.0 of this program.

3.5 Part-stroke Testing The goal of this program is to perform full stroke tests of all appropriate valves in order to assess the operational readiness of the valves via evaluation of valve degradation. With the exception of those valves for which specific relief has been requested, all valves will be full stroke tested.

Part stroke testing of power-operated valves is often not possible, due to valve logic circuitry which only allows full-open or full-closed valve movement.

Moreover, the intent of the Code is to assess valve operability through inservice 1/ptr

MONTICELLO NUCLEAR GENERATING PLANT EWi-09.04.01 TITLE: INSERVICE TESTING PROGRAM Revision 2*

Page 8 of 126 testing; while a part-stroke exercise does provide some measure of confidence in valve operability, it does not provide assurance of valve safety-related function. In addition, a part-stroke of a power-operated valve has the possibility, through huraan or mechanical error, to cause adverse plant consequences (isolation of cooling water, plant transients, etc.) via an inadvertent Mi-stroke.

Therefore, quarterly part stroke testing of the power-operated valves that are full stroke tested during Cold Shutdowns will not be performed.

Check valves whose safety function is to open will be full-stroked when possible.

Since disk position is not always observable, the NRC staff has stated that

" verification of the plant's safety analysis flow rate through the check valve would be an adequate demonstration of full-stroke requirement. Any flow rate less than design will be considered part-stroke exercising." Based on this position, check valves within the scope of this test program will be at least part-stroke exercised whenever any flow is passed through the valve. Check valves are full-stroke tested on at least the Code required frequency unless identified by relief request. Check valves for which a full-stroke exercise can not be confirmed, therefore, will be identified by an appropriate relief request.

3.6 Fall-Safe Actuators No special tests will be performed for the valves with fail-safe actuators where normal cycling of the valve by the control switch removes the actuator power source. For these valves, the fail-safe function is tested by normal valve exercise testing. All other fail-safe valves will be tested in accordance with IWV-3415, 3.7 Valve Position Indication Verification Verification of valve position indicator accuracy will be performed in accordance with Section XI IWV-3300 with the exception of those valves for which specific relief has been requested.

3.8 Passive Valves These valves, which have no Code operability testing requirements, are valves in safety-related system which are not required to change position in order to accomplish their required safety-function. Monticello has categorized as B-Passive all non-containment isolation valves which are required by procedure to be maintained in their safety-related position. Any valves which are related position are administratively also considered Category locked-open or locked-closed B Passive. Due to the lack of test in their safety ing requ these valves may be excluded from Attachment 9.3.

3.9 Stroke Times Valves with extremely short stroke timos (less than 2 seconds) have stroke times of such short duration that comparison of measurements with previous data for specified percentage increases is not indicative of degrading valve performance.

With measurement of stroke times to the nearest second per IWV-3413(b), a very small increase in stroke time will result in an extremely large percentage change. Verification that valves meet a specified maximum stroke time of short duration provides adcquate assurance of operability.

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Page 9 of 126 Also, the comparison of valve stroke times to the previous test results, without any evaluation of overall change in stroke time from initial test data, is not the o3timum method of gauging valve performance. Therefore, relief has been o atained (GR-4) from comparing the current valve stroke time with previous stroke time data per IWV-3417 and as an alternative, the current valve stroke ,

time data will be compared with a reference value stroke time taken when the valve is known to be in good condition.

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Page 10 of 126 4.0 RELIEF REQUESTS 4.1 Pump Testing Relief Requests 4.1.1 PR-1 (TEST METHOD)

System: Standby Liquid Control (SBLC)

P&lD: M-127 Pumps: P-203A and P-203B Class: 2 Function: To inject liquid poison into the reactor.

Impractical Test Requirement: OM-6-4.6.5; Flow Rate Measurement: l OM-6-5.6; Duration of Tests l Basis for Relief: The positive displacement SBLC pumps are designed to pump a constant flow rate regardless of system resistance. The SBLC system was not l designed with a flow meter in the flow loop. The system was designed to be tested '

using a test tank where the change in level can be measured over time. This test methodology also limits the pump run time based on the size of the test tank. The cost W ;

associated with installing a flow meter would be impractical since changes in tank level over time is an accurate way to measure flow. The orifice used by flow meters could also result in an area where sodium pentaborate crystals accumulate and possibly restrict flow.

Alternative Testing: Determine pump flow rate by measuring changes in tank level over time. The pump will be started with suction from the condensate storage system and will discharge to the test tank. After approximately two minutes of operation the pump will be stopped and the change in level over the measured time will be converted to flow rate by the following formula:

O(GPM) = 261.8 X AL (In)/At (Sec) where 261.8 includes tank dimensions and unit conversions The vibration testing will be performed while recirculating an adequately filled test tank.

Therefore, the duration of test code requirements for vibration testing will be met.

Approval: Relief granted in SER dated July 6,1993.

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_ TITLE: INSERVICE TESTING PROGRAM Revision 2*

I)

V Page 11 of 126 4.1.2 PR-3 (INSTRUMENT RANGE)

System: RHR and RHRSW P&lD: M-120, M-121 Instruments: FT-10-111 A, FT-10-111B, FT-10-97A and FT-10-97B Class: 2 and 3 Function: Provides a flow signal to an indicating device.

Impractical Test Requirement: OM 6-4.6.1.2(a); Full scale range of each analog instrument SHALL NOTbe greater than three times the reference value.

Basis for Relief: Flow transmitters FT-10-111 A, FT-10-111B, FT-10-97A, and FT-10-97B are each designed to indicate flow while two parallel pumps are operating (RHR and RHRSW) Dunng inservice testing,,only one pump operates at a time. The resulting reference value of flow for one pump is less than one third of the instrument's range. Replacing the flow transmitter to meet this requirement would not meet the design intent of providing a flow signal for two pump operation. Installing a second flow transmitter in parallel is impracticaiand a burden that does not increase the public's O. -

safety. These existing transmitters are very reliable. Past calibration records show the typical AS FOUND accuracy is 0.25% of full scale.

Alternative Testing: Use the existing station instruments to measure pump inservice test parameters. Perform a loop check on the flow instrumentation for these systems that verifies the AS FOUND accuracy is within 2% of 3 times the reference value of any RHR or RHRSW pump. This will be done as part of the routine calibration schedule.

Approval: Relief granted in SER dated July 6,1993.

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TITLE: INSERVICE TESTING PROGRAM Revision 2*

Page 12 of 126 h

4.1.3 PR-6 (HPCI VIBRATION)

System: High Pressure Coolant injection (HPCI)

P&lD: M-124 Pump: P-209 Class: 2 Function: Injects coolant into the reactor vessciindependent of AC power.

Code Test Requirement: OM-6 Table 3a and paragraph 6.1; Vibration Alert limit of 0.325 in/Sec for the horizontal vibration data points and the resulting increased pump test frequency.

Basis for Relief: 10CFR Part 50, Section 50.55a(a) (3) states (in part):

" Proposed alternatives to the requirements of paragra ahs (c), (d), (e), (f),

and (h) of this section or portions thereof may be usec when. . . (ii)

Compliance with the specified requirements of this section would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety."

1 The HPCI pump consists of a centrifugal main pump, a separate centrifugal booster O

W pump, a speed reducing gear for the booster pump, and a Terry turbine steam driver.

All these components are mounted horizontally along the same drive train. Therefore, there are four independently balanced and aligned rotating assemblies that are coupled together. This configuration is significantly different than the typical single pump and electric motor that the OM 6 limits are based on. As a result, the normal (baseline) vibration readings in the horizontal direction on both the booster pump and main pump are approximately 0.325 in/Sec.

Application of a 0.325 in/See alert limit would require us to enter accelerated test frequency each time the pump was tested because one or more of these points measured would exceed this limit. Prior to the third ten year interval, the alert limit of 0.325 in/Sec was not a code requirement at Monticello. We have many years of in service test data showing that baseline vibrations at 0.325 in/Sec represent acceptabh pump operation and that vibration levels have not trended up. We have also had these vibration levels analyzed by an Engineering Consultant that specializes in vibration analysis. Their analysis shows that this pump can operate at vibration levels up to 0.700 in/Sec.

NPRDS component history was reviewed for this type of pump. No failures attributed to extended hours of pump operation at vibration levels exceeding 0.325 in/Sec were i found. The pump manufacturer, Byron-Jackson, also stated that these vibration levels did not require corrective action, implementing the alert limit of 0.325 in/Sec would rec uire us to constantly have the l

HPCI pump on accelerated test frequency. This wou d result in a monthly pump inservice test instead of quarterly. The intent of increased test frequency is to closely g

monitor a pump that is deteriorating from its baseline values. In this case, the pump would be operating at its normal vibration range and no change would be seen. The I/ptr l

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O V Page 13 of 126 additional 8 tests a year would require a significant amount of time and resources and only create additional maintenance due to normal wear of the system. Modifications to try and reduce the vibration levels, such as installing new shafts and impellers, are extremely expensive and may not reduce the vibration levels. Therefore, requiring an alert limit of 0.325 in/Sec on the HPCI pump is an extreme hardship without a compensating increase in public safety.

An appropriate alert limit for these vibration data points is 0.500 in/Sec. This is based on previous test history, a review of industry data, the vibration analysis performed, and discussions held with the pump's manufacturer.

Alternative Testing: A vibration alert limit of 0.500 in/Sec will be used for the pump horizontal vibration data points. The OM-6 Code's required action limit of 0.700 in/Sec will be adhered to.

Approval: Relief granted in SER dated September 9,1994.

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Page 14 of 126 h

4.1.4 PR-8 (CALCULATING INLET PRESSURE)

System: Em ergency Service Water, RHR Service Water P&lD: M-811 Pump: P-111 A-D and P-109A-D C!sss: 3 Function: To provide cooling to safety related equipment; to provide decay heat l removal. I impractical Test Requirement: Measuring pump inlet pressure directly.

Basis for Relief: These pumps are verticalline shaft pumps submersed in the plant intake basin. By design, there is no inlet to the pump that can provide pressure measurement instrumentation.

Alternative Testing: Determine pump inlet pressure by converting the static head of water above the pump inlet to pressure with the following formula l

P (PSI) = (H (FT) - PEL (FT) X 0.433 i where H is the basin level elevation, and PEL is the pump inlet elevation The 0.433 factor is based on the density of water at 40 F. The same factor at the design basis temperature of 90 F is 0.431. The difference of 0.002 LB/in2 .FT is considered negligible.

The basin level elevation will be measured from an instrument that is calibrated per l OM-6 requirements.

Approval: In a letter dated July 6,1993, the NRC stated this relief request was not required. However, this relief request was written in response to a previous NRC SER, dated September 24,1992, Action item 5.9. Therefore, this relief request will remain in the program and be considered approved by NRC.

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( Page 15 of 126 1

4.1.5 PR-9 (INSTRUMENT RANGE)

System: High Pressure Coolant injection (HPCI) and Reactor Core Isolation Cooling (RCIC)

P&lD: M-124 HPCI and M-126 RCIC Pumps: P-209 HPCI and P-207 RCIC Class: 2 Function: To inject coolant into the reactor independent of AC power.

Test Requirement from which Relief is Sought: OMa-1988 Part 6 paragraph 4.6.1.2(a), analog instrument range SHALL NOTexceed 3 times the reference value.

Basis for Relief: 10CFR Part 50, Section 50.55a(a)(3) states (in part):

" Proposed alternatives to the requirements of paragra ahs (c), (d), (e), (f), (g),

and (h) of this section or portions thereof may be usec when . . .

s (i) The proposed alternatives would provide an acceptable level of quality

) and safety, . . ."

Inservice pump testing is performed in accordance OMa-1988 Part 6. The differential pressure 1or the HPCI and RCIC pumps is determined by subtracting the indicated suction pressure from the indicated discharge pressure. The HPCI pump suction pressure is read in the Control Room from instrument PI-23-116, which is sent a 10 to 50 mAmp signal from local transmitter PT-23-100. The RCIC pump suction pressure is read locally from instrument PI-13-66. The relevant data for the instruments is as follows:

REFERENCE INSTRUMENT PUMP RANGE VALUE RATIO PI-23-116 P-209 30" Hg Vacuum 33.7 PSI 114.7/33.7 = 3.4 to 100 PSI (See NOTE 1)

PT-23-100 P-209 10 to 50 mAmps 21.7 mAmps 40/11.7 = 3.4

{

(See NOTE 2) i PI-13-66 P-207 30" Hg Vacuum 33.7 PSI 114.7/33.7 = 3.4 to 100 PSI (See NOTE 1)

RQIEJ: The vacuum range for the pressure indicators was converted to PSI for determining the ratio. 30" HG  ;

Vacuum = 14.7 PSl; thus the RANGE = 100 + 14.7 = l 114.7 PSI. The same principle was applied to the  :

O, ) reference value (REF VAL). With a reference value  !

V of 19 PSI indicated on the instrument, the  ;

reference value used for the ratio determination is 1 19 + 14.7 = 33.7 PSI.

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Page 16 of 126 ,

MOTE 2: The pressure transmitter has a 10 to 50 mAmp range, or a span of 40 mAmps. The ratio for this instrument must be determined by reducing the reference value to its value on the 40 mAmp s pan (i.e.,21.7 mAmps equates to 11.7 mAmps on tl1e 40 mAmp span).

The code requires the instrument range to be less than 3 times the test parameter reference value. The 2% code allowable instrument tolerance is then taken from this range requirement. The same instrument calibration tolerance can be applied to these instruments by simply calculating the code required tolerance from the code equivalent range as follows:

2% OF CODE REFERENCE CODE EQUIVALENT EQUIVALENT INSTRUMENT VALUE RANGE RANGE PI-23-116 33.7 PSI 3 x 33.7 = 101 PSI i2 PSI PT-23-100 21.7 mAmps 3 x 11.7 = 35.1 mAmps i 0.7 mAmps PI-13-66 33.7 PSI 3 x 33.7 = 101 PSI i2 PSI The existing instrument calibration tolerances are i 2 PSI for the pressure indicators and i 0.8 mAmps for the pressure transmitter. The calibration history for these gi instruments shows that they easily meet these existing tolerances. Recent calibration records show the instruments' AS FOUND accuracy of 1% or less of the code equivalent range.

Under the provisions of 10CFR50.55a(a)(3), this altemative to the Code requirement is proposed in that the alternative provides an equivalent level of quality and safety. The proposed alternative satisfies the code intent in that the accuracy of the instrumentation i to assess the operational readiness of the HPCI and RCIC pumps will be maintained within Code requirements.

Alternative Testing: The instruments identified above will be calibrated to 2% of a ,

code equivalent range. The code equivalent range will be calculated by multiplying the j test parameter reference value by three. For pressure indicators PI-23-116 and Pl 13-66 this will result in a allowable tolerance equal to i 2 PSI on the output or10.7 mAmps on the input (Note: PI-23-116 may be calibrated by determining the mAmps input signal required to establish a set PSI output).

Pressure transmitter PT-23-100 will be calibrated to i 0.7 mAmps for the reasons discussed above.

Approval: Relief granted in SER dated December 8,1994.

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Page 17 of 126 4.2 Valve Testing Relief Requests 4.2.1 RBCW-1 (EXERCISE EACH REFUELING)

System: Reactor Building Cooling Water Valve: RBCC-15 Category: A, C-1 Class: 2 Function: System check valve for system penetrating primary containment.

impractical Test Requirement: IWV-3521; Test Frequency - exercise at least once every three months, quarterly.

Basis for Relief: This check valve is the inboard primary containment isolation valve for a system considered in service during plant operation. The normally open check valve requires an exercise in the reverse flow direction which can only be verified by leak testing. Primary containment leak testing performed each refueling, i.e.,

10 CFR 50 Appendix J, constitutes proper valve exercising. Closing this valve during power operation would result in temperature transients in the equipment it supplies, including Recirc pump seals, possibly resulting in equipment damage. Also, this valve C supplies drywell cooling during power operation and cold shutdown. Performing leak testing per Appendix J during Cold Shutdown would require de-inerting, entering containment, and shutdown of drywell cooling for an extended period, causing equipment damage and personnel hazard.

Alternative Testing: Exercise valve during refueling (at least once every two years) in conjunction with Appendix J leak testing.

Approval: Relief granted SER dated September 24,1992.

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System: Emergency Service Water Valve: SW-101, SW-102, SW-103, SW-104 Category: C-1 Class: 3 .

I Function: To prevent diversion of ESW flow to non-safety related systems. l l

Impractical Test Requirement: Individual valve closure testing per IWV-3520.

Basis for Relief: Each pair of valves, SW-101/SW-102 and SW-103/SW-104, are in series with no test taps installed between them. Safety function is assured if either one of the pair of valves will provide safety function. This means that testing of the pair of valves will verify system safety function.

Alternative Testing: Test each pair of valves, SW-101/SW-102 and SW-103/SW-104 quarterly by back flow testing each pair. If the pair fails a test, corrective action will be taken on both valves.

Approval: Relief granted in SER dated September 24,1992.

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,O Page 19 of 126 V

l 4.2.3 SC-1 (DISASSEMBLY TEST OF CHECK VALVE GROUP)

System: Condensate Storage Transfer (a.k.a. Service Condensate) l Valve: CST-88, CST-92, CST-94, CST-98 Category: C-1 Class: 2 Function: These are the boundary valves between the safety related RHR pumps discharge piping and the non-safety related service condensate keep fill I system. I Code Test Requirement: IWV-3520; Full stroke exercise, frequency and method. l 1

Basis for Relief: 10CFR50, Section 50.55a(f) (5) & (6) states (in part): l l

(5) (i,ii) If the licensee has determined that conformance with certain code i requirements is impractical for its facility, the licensee SHALL notify the commission . . . l (6) (i) . . . The commission may grant relief and may impose alternative

(] requirements . . . giving due consideration to the burden upon the licensee . . .

U These valves have a closed safety position since they prevent diversion of RHR flow I into the service condensate system. There are no test taps or instrumentation installed i that would allow testing that proves by positive means that the disc moves to the seat on cessation or reversal of flow. Installation of test taps and isolation valves to reverse flow test these valves is a burden. 1 1

Generic Letter 89-04 position 2 allows grouping identical valves and testing them by disassembly and inspection on a refuel frequency.

Alternative Testing: These valves will be grouped and tested in accordance with Generic Letter 89-04 positic 12 as follows:

1 Group: CST-88, CST-92, CST-94, CST-98 l All these check valves are the same size, type, and manufacturer. They all perform identical functions and have the same fluid through them. CST-92 and CST-94 interface with the A loop RHR discharge piping while CST-88 and CST-98 interface with B loop RHR discharge piping. Over the course of a refuel cycle, the valves experience the same sen/ ice conditions through the same number of RHR system inservice tests and roughly the same RHR loop operating time in shutdown coofing. The valves are all in the same orientation. Therefore, they meet the design and service condition grouping criteria of Generic Letter 89-04, position 2.

p Approval: Relief granted in SER dated September 9,1994.

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Page 20 of 126 4.2.4 NB-1 (SRV TESTING)

System: Nuclear Boiler / Main Steam Valve: RV-2-71 A, RV-2-71 B, RV-2-71 C, RV-2-71 D, RV-2-71 E, RV-2-71 F, RV-2-71G, RV-2-71 H Category: B, C-1 Class: 1 1

Function: To provide automatic depressurization or overpressure protection for the reactor coolant pressure boundary.  !

Code Test Requirement: IWV-3410, Valve Exercising Test i Basis for Relief: 10CFR50, Section 50.55a(f) (5) & (6) states (in part): 1 (5) (iii) If the licensee has determined that conformance with certain code requirements is impractical for its facility, the licensee SHALL notify the commission . . . )

(6) (i) . . . The commission may grant relief and may impose alternative requirements . . . giving due consideration to the burden upon the licensee . . . j in addition,10CFR Part 50, Section 50.55a(a) (3) states (in part):

" Proposed alternatives to the requirements of paragraphs . . . may be used when (i) The proposed alternatives would provide an acceptable level of quality and safety, . . ."

l These valves have an active, self actuation safety function to open and relieve an overpressurization condition in the reactor vessel. The valves also have an I auxiliary actuating device (as defined in OM-1-1981) that acts to open the valves and depressurize the reactor vessel. This function allows low pressure emergency core cooling systems to inject during a LOCA (ADS) and also controls reactor pressure in certain design transients (Iow low set). The ADS automatic actuation provides for depressurizing the reactor vessel to permit low pressure ECCS system injection during a loss of coolant accident. The low low set automatic actuation provides control of the opening and closing setpoint following a scram during pressurization transients.

Although these valves have an auxiliary actuating device, they can not be treated and tested as category B, power operated valves. The requirements to stroke time them quarterly is not within the design capability of the valves or the plant. First of all, these valves have a passive safety function to remain closed and provide reactor coolant pressure boundary. Exercising them during power operation would cause a severe reactor power and pressure transient that could result in a reactor scram. It also increases the potential for secor,d stage or pilot stage leakage due to seat wear or fouling. If this leakage is high enough, it can cause a spurious SRV lift and prevent reclosure of the valve. This condition is 1/pir

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r TITLE: INSERVICE TESTING PROGRAM Revision 2* I O Page 21 of 126 G j i

equivalent to an unisolable small break LOCA event. The NRC states in several i documents that such challenges to the ADS function of the main steam '

safety / relief valves should be minimized. Therefore, justification to perform an exercise test on a once-per-cycle frequency is well established.

The reason the valves can not be stroke timed is that there is no direct indication of valve position. Their stroke time can only be measured by indirect means such as changes in turbine bypass valve position indication. This results in a high degree of variability in the measured stroke times due to other plant variables such as reactor pressure, turbine bypass valve position, measuring instrumentation response time, etc. This prohibits repeatable test conditions without a heavy burden on the licensee to fix these parameters each time. This burden is not offset by an increase in public safety since it is the consensus of the entire industry that stroke time testing is not a valuable indicator of margin to failure, for any valve.

Alternative Testing: These valves will be monitored for degradation by testing them in accordance with all applicable sections of OM-1-1981, including the requirements for auxiliary actuating devices. The valves will also be tested in accordance with Technical Specification 4.6.E which includes disassembly and inspection of at least two SRVs each refueling outage, p All SRVs will be exercised at reduced system pressure, in place, each operating cycle t i to verify the open and close capability of the valve.

<J Approval: Based on previous third ten year approval of the previous version of NB-1 in SER dated July 6,1993, and approval of Technical Specification Amendment No. 92, this relief request will be implemented immediately and be subject to change when final approvalis granted by the NRC.

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Page 22 of 126 4.2.5 REC-1 (EXERCISE EACH REFUELING)

System: Recirc Loops Pumps and Motors Nuclear Boiler System Valve: XR-27-1, XR-27-2, XR-25-1, XR-25-2 Category: A, C-1 Class: 2 Function: Prevents reversal of flow from recirc seals to the CRD System.

Impractical Test Requirement: IWV-3521, Test Frequency - exercise at least once every three months, quarterly.

Basis for Relief: These valves are the inlet valves for the lower recirc pump seals.

Exercising could result in loss of seal water to lower seals of the Reactor Coolant Recirculation pumps causing plant trip or equipment damage. The reactor coolant recirculation pumps are normally operated during all plant operating conditions except refueling. Testing during Cold Shutdown would require entering containment, de-inerting, and performing testing identical to 10CFR50 Appendix J testing, which contributes to an unnecessary burden on the Licensee with no corresponding increase in plant safety.

Alternative Testing: Exercise the valves closed during refueling, in conjunction with Appendix J leak testing.

1 Approval: Relief granted in SER dated September 24,1992. l l

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Page 23 of 126 V(N l 4.2.6 CRD-1 (TESTING DURING SCRAM TEST)

System: Control Rod Hydraulic System Valve: CRD-114, CV-126, CV-127 Category: C-1, B-1, B-1 Class: 2 Function: CRD-114; Exhaust scram discharge flow from the CRD during a scram.

CV-126; Provide a scram accumulator control rod drive piston during a scram. pressure to the bottom of the CV-127; Exhaust scram discharge water from the top of the control rod drive piston during a scram.

Impractical Test Requirement: IWV-3411, IWV-3521; Test Frequency - exercise at least once every three months, quarterly.

Basis for Relief: The above listed valves are located on each of the 121 hydraulic control units. There is no practical method of testing these valves in accordance with O Section XI requirements. Testing these valves during power operation requires rapid

( insertion of each control rod. This introduces rapid reactivity transients and unreasonable wear of the control rod drive mechanism.

Alternative Testing: Proper operation of these valves will be verified by the individual control rod scram time test performed each refueling.

Approval: Relief granted in SER dated September 24,1992.

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Page 24 of 126 hI 4.2.7 CRD-2 (TEST EACH REFUELING)  ;

System: Control Rod Hydraulic System l Valve: CRD-115 Category: C-1 Class: 2 Function: Prevents depressurization of accumulator charges on cessation of flow. '

lmpractical Test Requirement: IWV-3521; Test Frequency - exercise at least once every three months, quarterly.

Basis for Relief: The above listed valve is located on each of the 121 hydraulic control I units. These valves can be tested to verify proper seating only by doing a special test l during cold shutdown / refueling.

J Alternative Testing: The test would involve depressurizing the accumulator charging water header and watching for accumulator low pressure a arms. Depressurizing the charging water header would cause a reversal of flow and the ball discs of the CMD-115 valves should move to their seats. If a ball disc did not move to its seat, the associated accumulator would rapidi depressurize and an alarm on low accumulator pressure would be received shortl thereafter. This test will be performed at least once each operating cycle, i.e., ref ling.

Approval: Relief granted in SER dated September 24,1992.

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(] Page 25 of 126 4.2.8 RHR-1 (DISASSEMBLY TEST OF CHECK VALVE GROUP)

System: Residual Heat Removal Valve: RHR-8-1, RHR-8-2 Category: C-1 Class: 2 Function: Provide minimum flow recirculation from the RHR pumps, impractical Test Requirement: Full flow test open quarterly per IWV-3520.

Basis for Relief: There is no means of measuring flowrate through this valve during quarterly pump testing. Operating the pump with only the minimum flow recirculation line available is not good operating practice, as recommended by the NRC for pump protection. This means there is no normal test method to examine these valves condition except disassembly.

Alternative Testing: These valves have been disassembled and manually exercised with no discernible degradation detected. Based on the results of these inspections, one valve will be inspected each refueling outage alternating between the valves. If fsJ degradation is detected, repairs will be made and the remaining valve SHALL also be U inspected.

Approval: Relief granted in SER dated September 24,1992.

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Page 26 of 126 ,

4.2.9 CS-1 (TEST CHECK VALVES AS PAIR)

System: Core Spray Valve: CST-103-1, CST-104-1 Category: C-1 Class: 2 Function: To prevent diversion of core spray flow to condensate storage system.

Impractical Test Requirement: Individual valve closure testing per IWV-3520.

Basis for Relief: Valves CST-103-1 and CST-104-1 are in series with no test taps installed between them. Safety function is assured if either one of the valves will provide safety function. This means that testing of the pair of valves will verify system safety function.

Alternative Testing: Test the pair of valves, CST-103-1 and CST-104-1, quarterly by back flow testing the pair. If the pair fails a test, corrective action will be taken on both valves.

Approval: Relief granted in SER dated September 24,1992.

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Page 27 of 126 4.2.10 SLC-1 (TEST EACH REFUELING)

System: Standby Liquid Control System Valve: XP-6, XP-7 Category: A, C-1 Class: 1 Function: Standby Liquid Control Injection Check Valves impractical Test Requirement: IWV-3521; Test Frequency - exercise at least once every three months, quarterly.

Basis for Relief: To verify forward flow operability during normal operation would require firing a squib valve and injecting water into the reactor vessel using the SLC pumps. This is impractical due to the extensive maintenance and cost required to replace squib valves. The SLC system would also be inoperable while changing the squib valves.

Alternative Testing: Verify forward flow operability during refueling while performing g) g v

the standby liquid control system injection test, which pumps demineralized water into the reactor vessel. Reverse flow testing will be performed during Appendix J leak rate testing.

Approval: Relief granted in SER dated September 24,1992, l

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Page 28 of 126 4.2.11 RWCU-1 (TEST EACH REFUELING)

System: Reactor Water Cleanup Valve: RC-6-1, RC-6-2 Category: C-1 Class: 2 Function: Prevent flow diversion from HPCl/RCIC injection.

Impractical Test Requirement: Full stroke quarterly per IWV-3520.

Basis for Relief: Closure testing these valves requires testing identical to Local Leak Rate Testing. Closing these valves interrupts RWCU flow, which is required in all modes except refueling to maintain water chemistry and reduce radioactivity. Closure testing would require an extended period of inoperability of the primary feedwater system, as well as HPCl/RCIC dunng power operation. In Cold Shutdown, RWCU operates to reduce reactor coolant system contamination.

Alternative Testing: Verify closure at refueling by performance of back flow testing.

Approval: Relief granted in SER dated September 24,1992.

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Page 29 of 126 4.2.12 lA-2 (TEST EACH REFUELING)

System: Instrument Air - Reactor Building Valve: Al-226-1 and Al-625 Category: A, C-1 Class: 2 Function: Prevent reversal of flow in TIP purge line, impractical Test Requirement: IWV-3521; Test Frequency - exercise at least once every three months, quarterly.

Basis for Relief: Check valves Al-226-1 and Al-625 are normally open check valves that are in service during all modes of operation. In addition, there is no practical means available to verify their discs travels promptly to the seat on cessation or reversal of flow.

Alternative Testing: Exercise valve by performance of 10CFR50 Appendix J leak testing during refueling.

Approval: Relief granted in SER dated September 24,1992.

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MONTICELLO NUCLEAR GENERATING PLANT EWI-09.04.01 TITLE: INSERVICE TESTING PROGRAM Revision 2*

Page 30 of 126 4.2.13 SW-1 (TEST CHECK VALVES AS PAIRS)

System: RHR Service Water Systems and Makeup Intake Structure Valve: SW-21-1, SW-22-1; SW-21-2, SW-22-2 Category: C-1 Class: 3 Function: Prevents reversal of RHRSW flow into the service water system.

Impractical Test Requirement: Individual valve closure testing per IWV-3520.

Basis for Relief: Each pair of valves, SW-21-1/SW-22-1 and SW-21-2/SW-22-2, are in series with no test taps installed between them. Safety function is assured if either one of the pair of valves will provide safety function. This means that testing of the pair of valves will verify system safety function.

Alternative Testing: Test each pair of valves, SW-21-1/SW-22-1 and SW-21-2/SW-22-2, quarterly by back flow testing each pair. If the pair fails a test, corrective action will be taken on both valves.

Approval: Relief granted in SER dated September 24,1992.

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4.2.14 ESW-2 (TEST CHECK VALVES AS PAIRS)

System: Service Water Systems and Makeup intake Structure Valve: SW-15, SW-16; SW-17, SW-18; ESW-13, ESW-14; ESW-15, ESW-16 Category: C-1 Class: 3 Function: Prevents reversal of flow from emergency water system into the service water system.

Impractical Test Requirement: Individual valve closure testing per IWV-3520.

Basis for Relief: Each pair of valves are in series with no test taps installed between them. Safety function is assured if either one of the pair of valves will provide safety function. This means that testing of the pair of valves will verify system safety function.

Alternative Testing: Test each pair of valves quarterly by back flow testing each pair.

If the pair fails a test, corrective action will be ta ken on both valves.

Approval: Relief granted in SER dated September 24,1992, 1

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4.2.15 GR-2 (LRT INCREASED FREQUENCY)

System: Various Valve: Various Category: A and AC pressure isolation valves (PlV)

Class: As applicable Function: Various impractical Test Requirement: IWV-3427(b); Trending and Corrective action for leakage rates for valves 6 inch nominal pipe size and larger.

Basis for Relief: These valves are located inside containment or inside radiation areas during operation and testing on an increased frequency would increase radiation exposure for testing personnel. Testing is now being performed during refueling to minimize exposure. With increased frequency, operational constraints would be placed upon the plant during cold shutdown. Monticello Nuclear Plant feels that the leakage rates for valves 6 in, and larger do not show enough consistency in the level of degradation prior to reaching the maximum leakage limit to justify maintaining these additional corrective action and trending requirements. This is in keeping with the NRC a nroved OM-10 code on Inservice Testing of Valves, which does not require trending ol eakage rates.

Alternative Testing: Test in accordance with OMa-1988 part 10 paragraph 4.2.2.

Approval: Relief granted in SER dated September 24,1992.

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MONTICELLO NUCLEAR GENERATING PLANT EWl-09.04.01 TITLE: INSERVICE TESTING PROGRAM Revision 2*

Page 33 of 126 4.2.16 GR-3 (LRT DURING APP J TEST) l System: Various Valve: Various Category: All those identified category A or A/C containment isolation valves in the valve testing tables.

Class: As Applicable Function: Various impractical Test Requirement: IWV-3421 through 3425 regardin methodology, and IWV-3427(b) g leak rate test Basis for Relief: In keeping with NRC Staff position, all CIV testing SHALL be performed under 10CFR50 Appendix J in addition to IWV-3426 and IWV-3427(a) of Section XI. Testing per 10CFR50 Appendix J meets the intent of leak rate testing per Section XI, but will be controlled via the Local Leak Rate Testing Program.

Alternative Testing: Monticello SHALL test all CIVs under the requirements of 10CFR50 Appendix J, in addition to IWV-3426 and IWV-3427(a) of Section XI.

Approval: Relief granted in SER dated September 24,1992.

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4.2.17 GR-4 (STROKE TIME ACCEPTANCE BANDS)

System: Various Valve: Various Category: A, B Class: Various Function: Various impractical Test Requirement: IWV-3414; Power Operated Valves Corrective Action, IWV-3417; Corrective Action Basis for Relief: Generic Letter 89-04 Position 6 recognizes that measuring changes in stroke times from a reference value as opposed to measuring changes from the previous test is a better way to detect valve degradation. Generic Letter 89-04 Position 5 and OMa-1988, Part 10 provide NRC approved methodology for establishing a stroke time reference value, an acceptable stroke time band, and a limiting stroke time value.

The alternative testing is in accordance with this methodology.

Alternative Testing: The power operated valve testing will be performed in accordance with OMa-1988, Part 10, paragraphs 4.2.1.4,4.2.1.8, and 4.2.1.9. The acceptable band and Limiting Stroke Time (LST) will be determined as follows (RV time in Sec):

Operator Tyo_a Ref_WILya Acc Band LSI Motor RV > 10 0.85RV - 1.15RV 1.3RV 2 s RV s 10 0.75RV - 1.25RV 1.5RV Other RV > 10 0.75RV - 1.25RV 1.5RV 2 s RV s 10 0.50RV - 1.50RV 2.0RV All RV < 2 s2 2 in addition, if a more restrictive value of stroke time exists in the Technical Specifications or the Updated Safety Analysis Report, it will be used as the LST instead of the value calculated above.

Approval: Relief granted in SER dated September 24,1992.

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Page 35 of 126 4.2.18 GR-5 (COLD SHUTDOWN TESTING)

System: See Valve Testing Table Valve: See Valve Testing Table Category: Various Class: Various Function: Various impractical Test Requirement: IWV-3412; Complete all cold shutdown frequency exercise testing prior to plant startup.

Basis for Relief: IWV-3412 has no allowance to startup the plant prior to completing the cold shutdown frequency exercise testing. The NRC approved OM-10 code on valve testing states that it is not the intent of the Code to keep the plant in cold shutdown in order to complete cold shutdown testing and it allows valve exercising to be deferred to refueling outages if quarterly and cold shutdown testing is not practical.

Monticello has changed the frequency of many check valve exercise tests from refueling to cold shutdown in response to the Technical Evaluation Report comments in p) this program's SER dated September 24,1992. This makes a large number of reverse flow check valve tests which are quite labor and time intensive required at cold shutdown. Requiring that all cold shutdown tests be completed prior to startup is impractical and a burden especially for unplanned and short outages. ,

Alternative Testing: Cold shutdown valve exercising for unplanned or forced outages, SHALL commence not later than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after cold shutdown is achieved. All valve testing does not have to be completed prior to subsequent plant startup. For extended outages, including refueling, where all required testing can be completed, exception to the above start time may be taken. However, during these extended outages, all cold shutdown frequency testing will be completed prior to plant startup.

In the event cold shutdown doesn't require specific de-inerting of containment, those j valves requiring containment access for cold shutdown testing will be deferred until the next cold shutdown that provides containment access. l Approval: Relief granted in SER dated September 9,1994.

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MONTICELLO NUCLEAR GENERATING PLANT EWl-09.04.01 TITLE: INSERVICE TESTING PROGRAM Revision 2*

Page 36 of 126 h 4.2.19 GR-7 (SP TEST LESS THAN 70 PSI)

System: Various Valve: Various Relief Valves Category: C Class: Various Function: To provide overpressure protection at 70 PSI or less.

Impractical Test Requirement: IWV-3512, Test Procedure and OM-1-1981 3aragraphs 1.3.3.1.5(b) and 1.3.4.1.5(b), Valves Not Vleeting Acceptance Criteria Basis for Relief: OM-1-1981 requires that if a relief valve exceeds its stamped set pressure by 3% or greater, then the valve requires corrective action. This requirement is unnecessarily restrictive for valves with a set pressure of 70 PSI or less as it is smaller than the design and construction tolerances. The ASME Boiler and Pressure Vessel Code, Section Ill, specifies a tolerance of plus or minus 2 PSI for the design and operation of overpressure protection safety valves with a setpoint up to 70 PSI.

Applyi.ng a 2 PSI tolerance for periodic testing of relief valves with a setpoint up to and including 70 PSI is within the requirements of Section Ill of the Code and is of no threat to the pressure boundary of power piping designed to nuclear quality standards.

Alternative Testing: For relief valves with a setpoint less than or equal to 70 PSI, the setpoint acceptance criteria will be i 2 PSI. For relief valves with setpoints greater than 70 PSI, the setpoint acceptance criteria will not exceed 3% of the stamped set 3ressure. If a more restrictive acceptance band is required by the system design or icense basis, then that criteria SHALL govern.

Approval: Relief granted in SER dated October 25,1993.

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4.2.20 RSW-1 (CONTROL VALVE TESTING)

System: Residual Heat Removal Service Water (RHRSW)

Valve: CV-1728 and CV-1729 Category: B-1 Class: 3 Function: To open, providing a flow path for RHRSW through the RHR heat exchanger.

Test Requirement from which Relief is Sought:

Section XI, paragraph IWV-3413, (a) The limiting value of Full-stroke time of each power operated valve SHALL be specified by the Owner. Full stroke time is that time interval from initiation of the actuating signal to the end of the actuating cycle.

(b) The stroke time of all power operated valves SHALL be measured to the nearest second. . .whenever such a valve is full-stroke tested.

Section XI, Paragraph IWV-3417, (a) If, for power operated valves, an increase in stroke time of 25% or more from the previous test, ... test frequency SHALL be increased to once each month until corrective action is taken....

Basis for Relief:

10CFR Part 50, Section 50.55a(f) (5) and (6) states, (in part):

(5)(iii) If the licensee has determined that conformance with certain code requirements is impractical for its facility, the licensee SHALL notify the commission....

(6)(i) ... The commission may grant relief and may impose alternative requirements ... giving due consideration to the burden upon the licensee....

In addition,10CFR Part 50, Section 50.55a(a)(3) states (in part):

" Proposed alternatives to the requirements of paragraphs ... may be  !

used when...

(i) The proposed alternatives would provide an acceptable level of

]p quality and safety,..." ,

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MONTICELLO NUCLEAR GENERATING PLANT EWl-09.04.01 TITLE: INSERVICE TESTING PROGRAM Revision 2*

Page 38 of 126 IWV-3413 requires that a limiting value of full stroke time be established for a power operated valve and that the stroke time be measured whenever such a valve is full stroke tested. Performing full stroke time testing of these valves is impractical based on the control scheme design of the valves, adverse plant impact, and the functional requirements of the valves.

IWV-3413 states that full stroke time is that time interval from initiation of the actuating signal to the end of the actuating cycle. The control scheme design of these valves does not receive an actuation signal (neither by manual handswitch nor by automatic logic) to stroke to the position required to fulfill their safety function. RHRSW valves CV-1728 and CV 1729 are air operated control valves on the outlet line of the RHRSW side of the "A" and "B" RHR heat exchangers, respectively. These control valves maintain a differential pressure between the RHRSW process stream and the RHR process stream during RHRSW system operation. The valves are controlled by a positioner, controlled by a differential aressure indicating controller (DPIC). The DPIC senses pressure on the RHRSW disc 1arge line and the RHR inlet line to the RHR heat exchanger. The desired differential pressure control point, and thus the desired valve position for system flow, is manually set by the operator by manual adjustment of the l DPIC setpoint. The valve positioner positions the valve and modulates the valve I position as necessary to maintain this control point. Stroke time testing of these valves on quarterly basis is not consistent with the design of the valve's control scheme and is not in the interest of plant safety.

These valves are interlocked to receive a closed signal when the Residual Heat Removal Service Water (RHRSW) pumps are de-energized. This interlock is provided i to ensure that system water inventory is not lost during system shutdown. Stroke time I testing of valves CV-1728 and CV-1729 when the Residual Heat Removal Service Water pumps are de-energized would result in the loss of liquid fill for a significant portion of the RHRSW system as well as require the bypassing of an interlock designed to minimize the potential for water hammer. Such testing increases the possibility of an adverse water hammer during startup of the RHRSW system as well as requires filling and venting of the system following the stroke time testing. In addition to the adverse impact on plant operation, such testing results in an undesirable burden on plant resources via the expenditure of person-hours and person-rem to perform system filling and venting.

Stroke time testing of the valves during RHRSW aump operation negates the loss of '

system fill concern; however, this testing would a so have an adverse impact on plant l safety and equipment integrity. Stroke time testing during pump operation would require the valve be initially in the closed position during pump operation. Establishing the initial test conditions of a closed valve during pump operation would result in an undesirable deadheading of the pump. Subsequent opening of the valve to perform stroke time testing will result in pump runout if a single RHRSW pum a is in operation, i an undesirable condition which adversely impacts pump integrity anc performance. l The pump runout concern can be addressed by stroke timing the valve open during operation of both RHRSW pumps; however, this exacerbates the pump deadheading concerns and would result in undesirable transients on the system.

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1 MONTICELLO NUCLEAR GENERATING PLANT EWl-09.04.01 TITLE: INSERVICE TESTING PROGRAM Revision 2" l Page 39 of 126 j Proper stroke time testing would require t,he plant to modify the control logic of the valves. This hardship is not offset by an increase in public safety. In addition, the application of stroke time testing r,equirements to control valves has recently become an issue with the OM code committee and is subject to change and/or clarification. The proposed alternative testing is an effective means to ensure the valves perform their safety function and is consistent with other valve category test requirements, such as check valve exercising.

Alternative Testing:

IWV-3412 provides for demonstrating the necessary valve disk movement by observing indirect evidence (such as changes in system pressure, flow rate, level, or temperature), which reflect stem or disk position. The most representative test of the capability of valves CV-1728 and CV-1729 to perform their intended function is performed during inservice testing of the RHRSW pumps. Quarterly testing of the RHRSW pumps verifies the capability of the valves to operate properly to pass the maximum required accident flow as well as the valve position necessary to achieve required flow conditions. Testing of the valves in this manner demonstrates valve performance capability and provides a means to monitor for valve degradation.

Approval: Interim approval granted in NRC letter dated December 23,1994.

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MONTICELLO NUCLEAR GENERATING PLANT EWi-09.04.01 TITLE: INSERVICE TESTING PROGRAM Revision 2*

Page 40 of 126 5.0 DEFERRED TESTING JUSTIFICATIONS 5.1 Mechanical Vacuum Pump Isol Valves System: Steam Jet Air Ejectors P&lD: M-104, SH 2 Valves: AO-1825A, AO-1825B Justification: These valves are not required to be inservice tested by 10CFR50.55a.

They are normally closed during power operation and have a closed safety position. To cycle and stroke time the valves, the mechanical vacuum pump must be star 1ed and stopped. Plant operating procedures prohibit operation of the mechanical vacuum pump above 5% power for safety reasons, therefore, the valves will be tested on a cold shutdown frequency.

5.2 RBCCW lsolation Valves System: Reactor Building Cooling Water System P&lD:

Valves:

M-111 MO-1426, MO-4229, MO-4230 g

Justification: These valves are normally open to supply cooling water to critical drywell components such as recirculation pump seals and the drywell coolers. They have a closed safety, position as primary containment isolation valves. Full stroke testing these valves interrupts cooling flow to the Drywell and the system is non-redundant. Therefore, cycling those valves risks losing cooling to the Drywell which will result in equipment damage and plant shutdown due to high Drywell pressure or temperature. The valves will be tested on a cold shutdown frequency.

5.3 Feedwater Check Valves Backflow Test System: Feedwater P&lD: M-115 Valves: FW-91-1, FW-91-2, FW-94-1, FW-94-2, FW-97-1, FW-97-2 Justification: These valves are open during power operation as feedwater injection check valves. FW-97-1,2 and FW 94-1,2 have an open safety position because they are in the HPCI or RCIC injection flow path. They have a closed safety position as containment isolation valves. These valves are verified open quarterly as part of normal plant operation. The only method of cycling these valves closed is to perform a reverse flow test. That requires isolating and venting the system and installing temporary bypasses (hoses, gages, etc). This cannot be 3erformed without shutting down the plant and entering the Drywell. Therefore, the c osed position of these valves will be tested on a cold shutdown frequency.

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(O Page 41 of 126 L.)

l FW 91-1,2 have a closed safety position to prevent the diversion of HPCI or RCIC injection away from the vessel. The only method of cycling these valves closed is to perform a reverse flow test. That requires iso!ating and venting the system and installing temporary bypasses (hoses, gages, etc). This cannot be performed without shutting down the plant and entering the Drywell. Therefore, these valves will be tested on a cold shutdown frequency.

5.4 MSIV Fall Safe Test System: Main Steam P&lD: M-115 Valves: AO-2-80A through D Justification: These vaives have a closed safety position as primary containment isolation valves. They have a safety related air supply that acts to open and close them. The valves also have a spring to assist them closed. The safety related air supply and springs are taken credit for closing the valves in accident analyses. Since the fail safe function of the valve spring is not independently tested during the quarterly exercise test, a special test to vent the air supply and locally monitor valve stem movement is required. This test cannot be done during power operation since the

\ valves are located inside the Drywell which is not accessible dunng power operations.

The fail safe test of these valves will be performed on a cold shutdown frequency.

5.5 RECIRC Pump Discharge Valves System: Recirc Loops Nuclear Boiler P&lD: M-117-1 Valves: MO-2-53A, MO-2-53B Justification: These are the reactor recirculation pump discharge valves which are normally open during power operation to allow reactivity control using the recirculation pumps. Their safety cannot be cycled dun, position ng power is closed operation withouttosedirect LPCI flow into the reactor. The va severely interrupting core flow. This can cause ec u,tpment curingdamage the associated and also pump resultsand in severe changes in power level which can cause p ant shutdown. The valves will be ,

tested on a cold shutdown frequency. l O

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Page 42 of 126 h

5.6 AO Testable Check Valves System: RHR P&lD: M-120, M-121 Valves: AO-10-46A, AO-10-46B System: Core Spray P&lD: M-122 Valves: AO-14-13A, AO-14-13B System: RCIC P&lD: M-126 Valves: AO-13-22 Justification: These testable check valves have full reactor pressure holding them closed during power operation. The air operator on the check valve is for test purposes only and cannot lift the disc against full reactor precsure. To ensure full stroke using the air operator, the valves will be tested when the reactor is depressurized on a cold shutdown frequency.

5.7 RHR Interlocks System: RHR P&lD: M-121 Valves: MO-2026, MO-2027, MO-2029, MO-2030 Justification: These RHR valves are normally closed and have a closed safety position. They have interlocks in their open direction logic that prevents thera from opening above a certain reactor pressure, approximately 75 PSIG. This interlock protects the low pressure piping of the RHR system from the high pressure reactor coolant on the other side of these valves. Since these valves are impractical to test during power operation, they will be tested on a cold shutdown frequency.

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5.8 HPCI Backflow Tests System: HPCI P&lD: M-123, M-124 I Valves: HPCI-9, HPCI-10, HPCI-14, HPCl-15, HPCI-31, HPCI-65, HPCI-71 Justification: The only way to test the closed safety position of these valves is by using a reverse flow test. Testing them at power requires isolating and venting the system which includes manual valve realignments, opening motor operated valve I breakers, and defeating auto start logic which is a significant burden on plant resources. This total loss of system function dramatically reduces the level of safety during power operation. Therefore, the closed position of these valves will be verified by doing a reverse flow test on a cold shutdown frequency.

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The opentest safety b)osition of HPCl-9 (

inservice of t e HPCI system. The and openHPCI-10 will beofverified safety position HPCI-31 during will be the quarterly verified '

on a refuel outage frequency by disassembly and inspection as allowed by OM-10 and 10CFR50.55a (f) (4) (iv). A partial stroke of HPCI-31 will also be performed on a cold i shutdown frequency with the same justification as stated in the preceding paragraph. I l

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5.9 RCIC Backflow Tests System: RCIC P&lD: M-125, M-126 Valves: RCIC-9, RCIC-10, RCIC-16, RCIC-17, RCIC-31, RCIC-57, RCIC-59 Justification: The only way to test the closed safety position of these valves is by using a reverse flow test. Testing them at power requires isolating and venting the system which includes manual valve realignments, opening motor operated valve breakers, and defeating auto start logic which is a significant burden on plant resources. This total loss of system function dramatically reduces the level of safety during power operation. Therefore, the closed position of these valves will be verified by doing a reverse flow test on a cold shutdown frequency.

The open safety position of RCIC-9 and RCIC-10 will be verified during the quarterly inservice test of tie RCIC system. The open safety position of RCIC-31 will be verified on a refuel outage fre b disassembly and inspection as allowed by OM-10 and l

10CFR50.55a (f) (4 iv). A partial stroke of RCIC-31 will also be performed on a cold shutdown frequency) w(quency y ith the same justification as stated in the preceding parag:aph.

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Page 44 of 126 5.10 Air to DW System: Safety Grade N2 to DW P&lD: M-131, SH-10 Valves: Al-598, Al-708, Al-713, Al-714, Al-730, SV-4235 Justification: These valves must be open to su aply safety grade nitrogen for critical component functions inside the Drywell, among t1em holding the inboard MSIVs open.

Since the inboard MSIVs fail closed, any interruption of the air supply to them during power operation risks a plant transient from the MSIVs drifting closed. All of these valves, installing except SV-4235, temporary bypassescan only (hoses, be exercised gages, by), isolating etc. and verifying full or no and venting reverse flow the sys across the check valve. Therefore, these valves will be tested on a cold shutdown frequency.

SV-4235 among others) is not required to be inservice tested by 10CFR50.55a, however,(it is included in this test program as good operating practice. Cold shu testing frequency is judged to be appropriate to adequately monitor the condition of this valve. Since there are administrative advantages to including SV-4235 in the same test procedure as the other valvet in the system, it will be tested on a cold shutdown frequency.

5.11 PASS XFV Tests System: PASS P&lD: NF-96042 Valves: PAS-59-5, PAS-59-6 Justification: These valves are normally open and have a closed safety position to ,

isolate the non-safety post accident sampli,ng (PAS) system from the safety related 1 RHR system. These valves are tested by isolating the system, installing temporary bypasses (hoses, gages, etc.) and performing steps similar to, but more extensive than, a check valve seat leakage test. Since this test is done in a high radiation area and it renders the non-redundant PAS system out of service, these valves will be tested on a cold shutdown frequency.

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Page 45 of 126 5.12 Backfill Check Valves System: CRD P&lD: M-116 Valves: BF-12, BF-14, BF-24, BF-26, BF-35, BF-37, BF-46, BF-48 Justification: These valves are normally open and have a closed safety position to separate the non-safety control rod drive system from the safety related reactor coolant pressure boundary. The lines containing these valves tie into sensitive reactor vessel instrumentation that is important during both power operation and cold shutdown operation. These valves are verified closed by isolat,ng i and venting the system, installing temporary bypasses (hoses, gages, etc.), and performing a reverse flow, seat leakage test. Therefore, these valves will be verified closed on a refuel outage frequency as part of their seat leakage test. This frequency is allowed by OM-10 and 10CFR50.55a (f) (4) (iv).

5.13 XFV Tests System: Various P&lD: Various Valves: XFV-1 thru 89 Justification: These valves are normally open and have a closed safety position as a primary containment barrier. The closed position of these valves is tested by installing temporary bypasses (hoses, gages, etc.) and performing steps similar to, but more extensive than, a check valve seat leakage test. The isolation of the lines containing these excess flow check valves takes instrumentation out of service that is im aortant during both power operation and cold shutdown operation. These valves will 3e tested on a refuel outage frequency as allowed by OM-10 and 10CFR50.55a (f) (4) (iv).

This frequency is consistent with the Technical Specification requirement to verify proper operation of these valves once per cycle.

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Page 46 of 126 I

5.14 Air to DW 11 '

System: Instrument Air P&lD: M-131, SH-12 Valvos: Al-571 Justification: This valve is normally open to supply instrument air to certain Drywell components, including the ADS and LLS function of two safety relief valves. It has a closed safety position as a primary containment isolation valve. Its closure test is performed by isolating and venting the system, installing temporary bypasses (hoses, gages, etc.) and performing a reverse flow, seat leakage test. Therefore, this valve will be tested on a cold shutdown frequency.

l 5.15 Air to T-Ring Seals System: Instrument Air - Reactor Building P&lD: M-131, SH-14 Valves: Al-613 thru 613, Al 663, Al-666, Al-669, Al-672, Al-675, Al-678, Al-681, Al-683, Al-685, Al-694, Al-695 Justification: These check valves are not required to be inservice tested by 10CFR50.55a. They are included in the program as good operating practice. The valves either open or close to ensure safety grade nitrogen is directed to the primary containment atmospheric control valves. The check valves are tested by isolating and venting the system, installing temporary bypasses (hoses, gages, etc.), and verifying full or no reverse flow across them. Due to the burden of this testing, these valves will be tested on a refuel outage frequency. This is consistent with OM-10 and 10CFR50.55a(f)(4)(iv).

5.16 Air Supply Check Valves System: Various P&lD: Various Valves: See Valve Testing Tables Justification: These check valves are not required to be inservice tested by 10CFR50.55a. They are included in this program as good practice. Their closed 30sition is important to safety by ensuring air is not rapidly lost after a postulated air line areak. The check valves are tested by isolating and venting the system, installing temporary bypasses (hoses, gages, etc), and verifying no reverse flow across them.

Due to the burden of this testing, these valves will be tested on a refuel outage frequency. This is consistent with OM-10 and 10CFR50.55a(f)(4)(iv).

1/plr

I MONTICELLO NUCLEAR GENERATING PLANT EWl-09.04.01 TITLE: INSERVICE TESTING PROGRAM Revision 2*

[ i Page 47 of 126 V

6.0 BEEERENCES 6.1 10CFR50.55a(g); Inservice Inspection 6.2 1986 Edition ASME Boiler and Pressure Vessel Code - Section XI: Rules for Insewice Inspection of Nuclear Power Plant Components 6.3 Monticello Nuclear Plant; Piping and Instrument Diagrams 6.4 Monticello Nuclear Plant; Technical Specifications 6.5 Regulatory Guide 1.26 6.6 ANSI /ASME OM Standards

- OM-1-1981 Relief Valve Inservice Testing

- OM-6 Pump Inservice Testing

- OM-10 Valve Inservice Testing 6.7 Monticello Updated Safety Analysis Report

- Section 5, Containment isolation

- Section 6, Plant engineered Safeguards

- Section 14, Plant Safety Analysis 6.8 ust 12,1982, from D.M. Musolf to Northern Director NRR;States Power

Subject:

Letter Dated Supplemental i Aukformation Concerning inservice Program 6.9 Northern States Power and NRC correspondence on Event V valves 6.10 NRC Generic Letter No. 89-04," Guidance on Developing Acceptable Insewice Testing Programs" 6.11 4 awl-01.03.03 (COLOR CODED P&lD Q-LIST EXTENSION) 6.12 Regulatory Guide 1.147 (O) 1/pir

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MONTICELLO NUCLEAR GENERATING PLANT EWI-09.04.01 TITLE: INSERVICE TESTING PROGRAM Revision 2* l Page 74 of 126 O,

EIGURE 8.26 DieselGenerator Auxillaries  ;

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l MONTICELLO NUCLEAR GENERATING PLANT EWl 09.04.01 TITLE: INSERVICE TESTING PROGRAM Revision 2*

Page 76 of 126 ,

FIGURE 8.28 kg_ygl Inst Backfill / Hard Pipe Vent r,

l V

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MONTICELLO NUCLEAR GENERATING PLANT EWi 09.04.01 TITLE: INSERVICE TESTING PROGRAM Revision 2*

Page 77 of 126 FIGURE 8.29 Safatv Grade N2 sv RV-2-71A RV-2-718

) RV-2-71C RV-2-71E SV-4234 A6-700 Al-599 SV-4235 Al-708 RVZ 2 1 Al-598 A 29 ',

Al-730 x N N X AL12-1

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MONTICELLO NUCLEAR GENERATING PLANT EWi-09.04.01 TITLE: INSERVICE TESTING PROGRAM Revision 2*

Page 78 of 126 9.0 ATTACHMENTS ATTACHMENT 9.1 P_ ump _Taslina Tahle Parameter to be Measured Pump Pump Pump ASME Deltn2 Relief P&lD No. Number Name Class Speed 1 Press Vibration Fiow ReqNo.

M 120 P-2028 RHR 2 NA X X X 4.1.2 M-120 P-202D RHR 2 NA X X X 4.1.2 M 121 P 202A RHR 2 NA X X X 4.1.2 M-121 P-202C RHR 2 NA X X X 4.1.2 M-122 P-208A Core Spray 2 NA X X X M-122 P-208B Core Spray 2 NA X X X M-124 P-209 HPCI 2 X X X X 4.1.3,4.1.5 M-126 P-207 RCIC 2 X X X X 4.1.5 M 127 P-203A SLC 2 NA X X X 4.1.1 M-127 P-203B SLC 2 NA X X X 4.1.1 M-133 P-11 DOTP NONE NA X X X M-811 P-109A RHRSW 3 NA X X X 4.1.2,4.1.4 M-811 P-109B RHRSW 3 NA X X X 4.1.2,4.1.4 M-811 P 109C RHRSW 3 NA X X X 4.1.2,4.1.4 M-811 P-109D RHRSW 3 NA X X X 4.1.2,4.1.4 M-811 P-111 A ESW 3 NA X X X 4.1.4 M-811 P-111B ESW 3 NA X X X 4.1.4 M-811 P-111C ESW 3 NA X X X 4.1.4 M-811 P 111D ESW 3 NA X X X 4.1.4 NH 94896 CGCP-1 A CGC 3 NA X X X NH-94897 CGCP-1 B CGC 3 NA X X X NQIR_1: Not applicable to constant speed pumps.

NQTfJ: Discharge pressure is used for positive displacement pumps P-203A, P-203B and P-11.

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i MONTICELLO NUCLEAR GENERATING PLANT EWl-09.04.01 TITLE: INSERVICE TESTING PROGRAM Revision 2* I

~( Page 79 of 126 ATTACHMENT 9.2 Valve Table Symltola SYMBOLS USED TO DESIGNATE VALVE TYPE Symbol Meaning CK Check Valve BF Butterfly Valve GT Gate Valve GL Globe Valve RV Pressure Relief Valve RD Rupture Disk AN Angle Valve PL Plug Valve SC Stop Check XP Explosive Shear Valve

/^ DI Diaphragm L AR Air Relief BA Ball Valve FV Excess Flow Check Valve SYMBOLS USED TO DESIGNATE VALVE ACTUATOR TYPE Symbol Meaning MO Motor AO Air  !

SO Solenoid MA Manual i

SA Self Actuating I l

SYMBOLS USED TO DESIGNATE VALVE POSITION Symbols Meaning O Open  !

C Closed RQIE: Monticello Nuclear Plant may revise, without notice, the

( identified positions listed in ' Normal Position" and " Safety ,

Position" based on changes in valves function / system l configuration. l 1

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MONTICELLO NUCLEAR GENERATING PLANT EWi-09.04.01 TITLE: INSERVICE TESTING PROGRAM Revision 2*

Page 80 of 126 l

ATTACHMENT 9.2 Valve Table Sydo_la (cont'd) l SYMBOLS USED TO DESIGNATE TESTING REQUIREMENT Symt.iql Meaning CE Control valve exercise per IWV-3412, performed quarterly.  ;

DI Disassemble and inspect the valve each refueling outage as allowed by OM-10 and 10CFR50.55a(f)(4)(iv), unless otherwise noted.

EX Explosive valve test per IWV-3610.

FC Stroke Test per IWV-3400/3520, on a cold shutdown frequency (with stroke time measurement, as appropriate).

FE Full stroke test on a quarterly frequency (with stroke time measurement as appropriate) per IWV-3400, or full stroke test of check valves per IWV-3520.

FR Stroke test per IWV-3400, on a refueling frequency (with stroke time measurement, as appropriate), as allowed by OM-10 and 10CFR50.55a(f)(4)(iv),

or a relief request. g FS Fail safe test per IWV-3415.

LJ Leak test per 10CFR50, App J, performed during refueling outages.

LK Leak test per IWV-3420, performed during refueling outages.

PC Partial stroke exercise test on a cold shutdown frequency as allowed by OM-10 and 10CFR50.55a(f)(4)(iv).

Pl Position indicator test per IWV-3300, performed during refueling outages.

RD Rupture disk test per IWV-3620.

RR See relief request for testing details.

SP Periodic relief valve test per IWV-3510.

SYMBOLS USED TO DESIGNATE SECTION XI VALVE CATEGORY Symbol M u nias A Valves with specified maximum seat leakage rate.

B Valves with no specified maximum seat leakage rate.

C Self-actuating (check, relief valves).

D Actuated by energy source capable of only one operation (rupture disks, explosive valves).

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MONTICELLO NUCLEAR GENERATING PLANT EWi-09.04.01 TITLE: INSERVICE TESTING PROGRAM Revision 2*

Page 81 of 126 ATTACHMENT 9.2 Valve Table Symbols (cont'd)

SYMBOLS USED TO DESIGNATE ACTIVE AND PASSIVE VALVES Symbol Meaning 1 Active - valves which are required to change position to accomplish a specific function.

2 Passive - valves which are not required to change position to accomplish a specific function.

O O

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MONTICELLO NUCLEAR GENERATING PLANT EWl 09.04.01 TITLE: INSERVICE TESTING PROGRAM Revision 2*

l Page 82 of 126 h

ATTACHMENT 9.3 Valve Testing Table SYSTEM: Steam Jet Air Ejectors P&lD NO.: M-104 2 ASME P&lD Sect XI Size Viv Act Norm Safety Req'd RelReq Tests Valve No. Class Coord Cat (in.) Type Type Pos Pos Tests or DTJ Pfrmd AO-1825A None B-3 B-1 6 BF AO C C FE 5.1 FC AO-18258 None B3 B-1 6 BF AO C C FE 5.1 FC l

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MONTICELLO NUCLEAR GENERATING PLANT EWl 09.04.01 TITLE: INSERVICE TESTING PROGRAM Revision 2*

p Rj Page 83 of 126 ATTACHMENT 9.3 Valve Testing Table (cont'd)

SYSTEM: Condensate & Demineralized Water Storage System P&lD NO.: M 108 ASME P&lD Sect XI Size Viv Act Norm Safety Req'd RelReq Tests Valve No. Class Coord Cat (in.) Type Type Pos Pos Tests or DTJ Pfrmd DM-151 2 E-1 A-2 1 GT MA C C LJ LJ DM 152 2 E-1 A-2 1 GT MA C C LJ LJ O

o G

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MONTICELLO NUCLEAR GENERATING PLANT EWi-09.04.01 TITLE: INSERVICE TESTING PROGRAM Revision 2*

Page 84 of 126 h

ATTACHMENT 9.3 yfive Testing Table (cont'd)

SYSTEM: Reactor Building Cooling Water System P&lD NO.: M-111 ASME PalD Sect XI Size Viv Act Norm Safety Req'd Rol Req Tests Valve No. Class Coord Cat (in.) Type Type Pos Pos Tests or DTJ Pfrmd MO-1426 2 E-4 A-1 8 GT MO O C FE,LJ, 5.2 FC,LJ, Pl l Pl i MO-4229 2 E-4 A-1 8 GT MO O C FE,LJ, 5.2 FC,LJ, ,

Pl Pl l MO-4230 2 E3 A-1 8 GT MO O C F E,LJ, 5.2 FC,LJ, Pl PI RBCC-15 2 E-3 A,C-1 8 CK SA O C FE,LJ 4.2.1 FR,LJ O

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MONTICELLO NUCLEAR GENERATING PLANT EWl-09.04.01 TITLE: INSERVICE TESTING PROGRAM Revision 2*

Page 85 of 126

(

ATTACHMENI 9.3 Valve Testing Table (cont'd)

SYSTEM: RHR Service Water P&lD NO.: M 112 ASME P&lD Sect XI Size Viv Act Norm Safety Req'd RelReq Tests Valve No. Class Cocrd Cat (in.) Type Type Pos Pos Tests or DTJ Pfrmd RV-3202 3 C-5 C-1 2.5 RV SA C O SP SP RV-3203 3 C-4 C-1 2.5 RV SA C O SP SP CV-1728 3 A-5 B-1 12 GL AO C O CE 4.2.20 CE CV-1729 3 A-4 B1 12 GL AO C O CE 4.2.20 CE l

l l

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1 MONTICELLO NUCLEAR GENERATING PLANT E'Ni 09.04.01 TITLE: INSERVICE TESTING PROGRAM Revision 2*

Page 86 of 126 ATTACHMENT 9.3 Valve Testing Table (cont'd)

SYSTEM: Emergency Service Water Systems P&lD NO.: M 112 ASME P&lD Sect XI Size ' Viv Act Norm Safety Req'd RetReq Tests Valve No. Class Coord Cat (in.) Type Type Pos Pos Tests or DTJ Pfrmd ESW 4-1 3 E1 C-1 3 CK SA C O FE FE ESW-4 2 3 E3 C-1 3 CK SA C O FE FE SW-101 None E1 C-1 3 CK SA O C FE 4.2.2 RR SW 102 3 E-1 C-1 3 CK SA O C FE 4.2.2 RR SW-103 None E-3 C-1 3 CK SA O C FE 4.2.2 RR SW-104 3 E-3 C-1 3 CK SA O C FE 4.2.2 RR O

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MONTICELLO NUCLEAR GENERATING PLANT EWl-09.04.01 TITLE: INSERVICE TESTING PROGRAM Revision 2* '

Page 87 of 126 f]

ATTACHMENT 9.3 Valve Testing Table (cont'd)

SYSTEM: Service Condensate System P&lD NO.: M 1141 ASME P&lD Sect XI Size Viv Act Norm Safety Req'd RelReq Tests I Valve No. Class Coord Cat (in.) Type Type Pos Pos Tests or DTJ Pfrmd CST 88 2 B-5 C-1 2 CK SA O C FE 4.2.3 RR CST-90 2 B-5 C-1 2 CK SA O C FE DI CST 92 2 B-5 C-1 2 CK SA O C FE 4.2.3 RR CST-94 2 B5 C1 2 CK SA O C FE 4.2.3 RR CST 96 2 B-6 C-1 2 CK SA O C FE DI CST-98 2 B-6 C-1 2 CK SA O C FE 4.2.3 RR CST 189 2 B-6 C-1 1 CK SA O C FE D1 1

i I

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4 MONTICELLO NUCLEAR GENERATING PLANT EWI-09.04.01 TITLE: INSERVICE TESTING PROGRAM Revision 2* 4 Page 88 of 126 ,

1 ATTACHMENT 9.3 Valve Testing Table (cont'd)

SYSTEM: Nuclear Boller System Steam Supply P&lD NO.: M 115 ASME P&lD Sect XI Size Viv Act Norm Safety Req'd RelReq Tests Valve No. Class Coord Cat (in.) Type Type Pos Pos Tests or DTJ Pfrmd

)

FW-91 -1 2 A-3 C-1 14 CK SA O C FE 5.3 FC  !

FW 91-2 2 A-5 C-1 14 CK SA O C FE 5.3 FC FW 94-1 1 A-3 A,C 1 14 CK SA O O/C FE,LJ 5.3 FE(O), l FC(C),

LJ FW 94 2 1 A-4 A C-1 14 CK SA O O/C FE,LJ 5.3 FE(O),

FC(C),

LJ FW 97-1 1 A-3 A,C 1 14 CK SA O O/C FE,LJ 5.3 FE(0),

FC(C),

LJ FW-97-2 1 A-4 A,C-1 14 CK SA O O/C FE,LJ 5.3 FE(0),

C(C),

XFV-1 2 E-2 A,C-1 1 FV SA O C FE,LK 5.13 FR,LK XFV-2 1 D-2 A,C-1 1 FV SA O C FE,LK 5.13 FR,LK XFV-3 1 D-5 A,C-1 1 FV SA O C FE,LK 5.13 FR,LK XFV-4 1 D-5 A,C-1 1 FV SA O C FE,LK 5.13 FR,LK XFV5 1 D2 A.C-1 1 FV SA O C FE,LK 5.13 FR,LK XFV-6 1 B-2 A,C-1 1 FV SA O C FE,LK 5.13 FR,LK XFV 7 1 C-2 A,C-1 1 FV SA O C FE,LK 5.13 FR,LK XFV-8 1 B-5 A,C-1 1 FV SA O C FE,LK 5.13 FR,LK XFV 9 1 C-5 A,C-1 1 FV SA O C FE,LK 5.13 FR,LK O

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1 MONTICELLO NUCLEAR GENERATING PLANT EWi-09.04.01 ,

TITLE: INSERVICE TESTING PROGRAM Revision 2*

( Page 89 of 126 l

ATTACHMENT  !

9.3 y_alye Testing Table (cont'd)

SYSTEM: Nuclear Boller System Steam Supply P&lD NO.: M 115 ASME P&lD Sect XI Size Viv Act Norm Safety Req'd RelReq Tests Valve No. Class Coord Cat (in.) Type Type Pos Pos Tests or DTJ Pfrmd AO-2-80A 1 C-5 A-1 18 GL AO O C FE,LJ, 5.4 FE,LJ, Pl,FS Pl,FS AO-2-80B 1 E-5 A-1 18 GL AO O C FE,LJ, 5.4 FE,LJ, Pl,FS Pl,FS AO-2-80C 1 E-2 A-1 18 GL AO O C FE.LJ, 5.4 FE,LJ, Pl,FS Pl,FS AO-2 80D 1 C-2 A-1 18 GL AO O C FE,LJ, 5.4 FE,LJ, Pl,FS PI,FS AO-2-86A 1 C-5 A-1 18 GT AO O C FE,LJ, FE LJ, Pl Pl AO-2-868 1 E-5 A-1 18 GT AO O C FE,LJ, FE,LJ, Pl Pl O. AO-2-86C 1 E-2 A-1 18 GT AO O C FE,LJ, Pl FE,LJ, Pl AO-2-86D 1 C-2 A-1 18 GT AO O C FE,LJ, FE,LJ, Pl Pl MO 2373 1 B-5 A-1 3 GT MO C C FE,LJ, FE,LJ, Pl Pl MO 2374 1 B-6 A-1 3 GT MO C C FE,LJ, FE,LJ, Pl Pl RV-2-71 A 1 B-4 B,C-1 6 RV SA/AO C O SP,FE 4.2.4 SP,FR, RR RV-2-718 i D-4 B,C-1 6 RV SA/AO C O SP,FE 4.2.4 SP,FR, RR RV-2-71 C 1 D-3 B C-1 6 RV SA/AO C O SP,FE 4.2.4 SP,FR, RR RV-2-71 D 1 B-3 B,C 1 6 RV SA/AO C O SP,FE 4.2.4 SP,FR, RR RV-2 71E 1 B-4 B,C-1 6 RV SA/AO C O SP,FE 4.2.4 SP,FR, l RR j RV-2-71 F 1 B-3 B,C-1 6 RV SA/AO C O SP,FE 4.2.4 SP,FR, RR RV-2 71G 1 D-4 B,C-1 6 RV SA/AO C O SP,FE 4.2.4 SP,FR, o RV 2-71H 1 D-3 B,C-1 6 RV SA/AO C O SP,FE 4.2.4 RR SP,FR, RR 1/pir

MONTICELLO NUCLEAR GENERATING PLANT EWl-09.04.01 TITLE: INSERVICE TESTING PROGRAM Revision 2*

Page 90 of 126 ATTACHMENT 9.3 Valve Testing Table (cont'd)

SYSTEM: Reactor Pressure Relief P&lD NO.: M 115-1 ASME PalD Sect XI Size Viv Act Norm Safety Reg'd RelReq Tests Valve No. Class Coord Cat (in.) Type Type Pos Pos Tests or DTJ Pfrmd RV-3242A None A-5 C-1 8 RV SA C O SP SP RV 3243A None C-6 C-1 8 RV SA C O SP SP RV-3244A None C-4 C-1 8 RV SA C O SP SP RV-3245A None A-4 C-1 8 RV SA C O SP SP RV-7440A None A-6 C-1 8 RV SA C O SP SP RV-7441 A None A-4 C-1 8 RV SA C O SP SP RV-7467A None C-5 C-1 8 RV SA C O SP SP RV-7468A None C-4 C-1 8 RV SA C O SP SP XFV 10 2 C-7 A,C-1 1 FV SA O C FE,LK 5.13 FR,LK XFV-11 2 C-7 A,C-1 1 FV SA O C FE,LK 5.13 FR,LK XFV-12 2 A7 A,C-1 1 FV SA O C FE,LK 5.13 FR,LK XFV-13 2 A-7 A,C-1 1 FV SA O C FE,LK 5.13 FR,LK XFV 14 2 C-3 A,C-1 1 FV SA O C FE,LK 5.13 FR,LK XFV-15 2 C-3 A,C-1 1 FV SA O C FE LK 5.13 FR,LK XFV-16 2 A-3 A,C-1 1 FV SA O C FE,LK 5.13 FR,LK XFV-17 2 A-3 A,C-1 1 FV SA O C FE,LK 5.13 FR,LK XFV-18 2 A-3 A.C-1 1 FV SA O C FE,LK 5.13 FR,LK XFV-19 2 C-3 A,C-1 1 FV SA O C FE,LK 5.13 FR,LK XFV 20 2 A-7 A,C-1 1 FV SA O C FE,LK 5.13 FR,LK XFV-21 2 C-7 A,C-1 1 FV SA O C FE,LK 5.13 FR,LK O

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MONTICELLO NUCLEAR GENERATING PLANT EWl-09.04.01 TITLE: INSERVICE TESTING PROGRAM Revision 2*

[]

V Page 91 of 126 ATTACHMENT 9,3 Valve Testing Table (cont'd)

SYSTEM: Vessel Instrumentation Nuclear Boller System P&lD NO.: M-116 ASME P&lD Sect XI Size Viv Act Norm Safety Req'd RelReq Tests Valve No. Class Coord Cat (in.) Type Type Pos Pos Tests or DTJ Pfrmd BF-12 2 B-3 A,C-1 0.37 CK SA O C FE,LK 5.12 FR,LK BF-14 2 B-3 A,C-1 0.37 CK SA O C FE,LK 5.12 FR,LK BF-24 2 B-3 A,C-1 0.37 CK SA O C FE,LK 5.12 FR,LK BF 26 2 B-3 A,C 1 0.37 CK SA O C FE,LK 5.12 FR,LK BF-35 2 A3 A,C-1 0.37 CK SA O C FE,LK 5.12 FR,LK BF-37 2 A-3 A,C 1 0.37 CK SA O C FE,LK 5.12 FR,LK BF-46 2 A-3 A,C-1 0.37 CK SA O C FE,LK 5.12 FR,LK BF-48 2 A3 A,C-1 0.37 CK SA O C FE,LK 5.12 FR,LK XFV 22 1 C-5 A,C-1 1 FV SA O C FE,LK 5.13 FR,LK

() XFV-23 1 C5 A,C-1 1 FV SA O C FE,LK 5.13 FR,LK XFV-24 1 D-5 A C-1 1 FV SA O C FE,LK 5.13 FR,LK XFV 25 1 D-6 A,C-1 1 FV SA O C FE,LK 5.13 FR,LK XFV-26 1 D-3 A,C-1 1 FV SA O C FE,LK 5.13 FR,LK XFV-27 1 C-5 A,C-1 1 FV SA O C FE,LK 5.13 FR,LK XFV-28 1 C-5 A,C-1 1 FV SA O C FE,LK 5.13 FR,LK j XFV-29 1 C-5 A,C-1 1 FV SA O C FE,LK 5.13 FR,LK XFV-30 1 C-5 A.C-1 1 FV SA O C FE,LK 5.13 FR,LK  !

1 XFV-31 1 C-5 A,C-1 1 FV SA O C FE,LK 5.13 FR,LK XFV-32 1 C-5 A,C-1 1 FV SA O C FE,LK 5.13 FR,LK XFV-33 1 C-5 A,C-1 1 FV SA O C FE,LK 5.13 FR,LK XFV 34 1 C-5 A,C-1 1 FV SA O C FE,LK 5.13 FR,LK XFV-35 1 C-5 A,C-1 1 FV SA O C FE,LK 5.13 FR,LK XFV-36 1 C-5 A,C-1 1 FV SA O C FE,LK 5.13 FR,LK XFV-37 1 C-5 A,C-1 1 FV SA O C FE,LK 5.13 FR,LK XFV-38 1 C-5 A,C-1 1 FV SA O C FE,LK 5.13 FR,LK r

XFV-39 1 C-3 A,C-1 1 FV SA O C FE.LK 5.13 FR,LK

\ XFV 40 1 C-3 A,C-1 1 FV SA O C FE,LK 5.13 FR,LK XFV-41 1 C-3 A,C-1 1 FV SA O C FE,LK 5.13 FR.LK I/pir

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l Page 92 of 126 h

ATTACHMENT 9.3 Valve Testing Table (cont'd)

SYSTEM: Vessel Instrumentation Nuclear Boller System P&lD No.: M-116 (cont'd)

ASME PalD Sect XI Size Viv Act Norm Safety Req'd RetReq Tests Valve No. Class Coord Cat (in.) Type Type Pos Pos Tests or DTJ Pfrmd XFV-42 1 C3 A,C-1 1 FV SA O C FE,LK 5.13 FR,LK XFV-43 1 C-3 A,C-1 1 FV SA O C FE,LK 5.13 FR,LK XFV-44 1 C-3 A,C-1 1 FV SA O C FE,LK 5.13 FR,LK XFV-45 1 C-3 A,C-1 1 FV SA O C FE,LK 5.13 FR,LK XFV-46 1 C-3 A,C-1 1 FV SA O C FE,LK 5.13 FR,LK XFV-47 1 C-3 A,C-1 1 FV SA O C FE,LK 5.13 FR,LK XFV-48 1 C-3 A,C-1 1 FV SA O C FE,LK 5.13 FR,LK XFV-49 1 C-3 A,C-1 1 FV SA O C FE,LK 5.13 FR,LK XFV-50 1 C-3 A,C-1 1 FV SA O C FE LK 5.13 FR,LK XFV-51 1 C-3 A,C-1 1 FV SA O C FE,LK 5.13 FR,LK XFV-52 1 D-5 A,C-1 1 FV SA O C FE,LK 5.13 FR,LK XFV-53 1 D-3 A,C-1 1 FV SA O C FE,LK 5.13 FR,LK XFV-54 1 D-5 A,C-1 1 FV SA O C FE,LK 5.13 FR,LK XFV-55 1 D-3 A,C-1 1 FV SA O C FE,LK 5.13 FR,LK XFV-56 1 D5 A,C-1 1 FV SA O C FE,LK 5.13 FR,LK XFV-57 1 D-3 A,C-1 1 FV SA O C FE,LK 5.13 FR.LK XFV-88 1 D-5 A,C-1 1 FV SA O C FE,LK 5.13 FR,LK XFV-89 1 D-3 A,C-1 1 FV SA O C FE,LK 5.13 FR,LK O

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[] Page 93 of 126 v

ATTACHMENT 9.3 Valve Testing Table (cont'd)

SYSTEM: Recirc Loops Nuclear Boiler System P&lD NO.: M-117-1 ASME P&lD Sect XI Size Viv Act Norm Safety Reg'd RelReq Tests Valve No. Class Coord Cat (in.) Type Type Pos Pos Tests or DTJ Pfrmd CV-2790 2 D-5 A-1 0.75 GT AO O C FE,LJ, FE,LJ, Pl Pl CV-2791 2 D-6 A-1 0.75 GL AO O C FE,LJ, FE,LJ, Pl Pl MO-2-53A 1 B-2 B-1 28 GT MO O C FE,PI 5.5 FC,PI MO-2-538 1 B6 B-1 28 GT MO O C FE,PI 5.5 FC,PI XFV-58 1 B-2 A,C-1 1 FV SA O C FE,LK 5.13 FR,LK XFV-59 1 B-2 A,C-1 1 FV SA O C FE.LK 5.13 FR,LK XFV 60 1 A3 A,C-1 1 FV SA O C FE,LK 5.13 FR,LK XFV-61 1 B-6 A C-1 1 FV SA O C FE,LK 5.13 FR,LK XFV-62 1 B-6 A,C-1 1 FV SA O C FE,LK 5.13 FR,LK XFV 63 1 A-5 A,C-1 1 FV SA O C FE,LK 5.13 FR.LK XFV-64 1 D-5 A,C 1 1 FV SA O C FE,LK 5.13 FR,LK XFV-65 1 D-5 A,C-1 1 FV SA O C FE LK 5.13 FR,LK XFV-66 1 E-2 A C-1 1 FV SA O C FE,LK 5.13 FR LK XFV-67 1 C-5 A,C-1 1 FV SA O C FE,LK 5.13 FR,LK XFV-68 1 C-5 A,C 1 1 FV SA O C FE,LK 5.13 FR,LK XFV-69 1 E-6 A,C-1 1 FV SA O C FE,LK 5.13 FR,LK XFV-70 1 E-6 A,C 1 1 FV SA O C FE,LK 5.13 FR,LK EV-71 1 E-2 A C-1 1 FV SA O C FE LK 5.13 FR,LK XFV-72 1 E-6 A,C-1 1 FV SA O C FE.LK 5.13 FR,LK XFV-73 1 E-6 A,C-1 1 FV SA O C FE.LK 5.13 FR,LK XFV-74 1 E-2 A,C-1 1 FV SA O C FE,LK 5.13 FR,LK XFV-75 1 E-2 A,C-1 1 FV SA O C FE,LK 5.13 FR,LK XFV-76 1 D-2 A.C-1 1 FV SA O C FE,LK 5.13 FR,LK XFV-77 1 D-2 A.C-1 1 FV SA O C FE,LK 5.13 FR,LK O

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MONTICELLO NUCLEAR GENERATING PLANT EWi-09.04.01 TITLE: INSERVICE TESTING PROGRAM Revision 2' Page 94 of 126 ATTACHMENT 9.3 Valve Testing Table (cont'd)

SYSTEM: Recirc Loops Pumps and Motors Nuclear Boller System P&lD NO.: M-117-2 ASME P&lD Sect XI Size Viv Act Norm Safety Reg'd RelReq Tests Valve No. Class Coord Cat (in.) Type Type Pos Pos Tests or DTJ Pfrmd XR-27-1 2 D-3 A,C-1 1 CK SA O C FE,LJ 4.2.5 FR,L.I XR-27-2 2 D-5 A,C-1 1 CK SA O C FE,LJ 4.2.5 FR,LJ XFV-78 1 C3 A,C-1 1 FV SA O C FE,LK 5.13 FR,LK XFV-79 1 C-3 A,C-1 1 FV SA O C FE,LK 5.13 FR,LK XFV-80 1 C-4 A.C-1 1 FV SA O C FE,LK 5.13 FR,LK

~

XFV 81 1 C-4 A,C 1 1 FV SA O C FE,LK 5.13 FR,LK ,

l O

l O

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ATTACHMENT  ;

9.3 yalye Testing Table (cont'd) l SYSTEM: Control Rod Hydraulic System (Recirc) P&lD NO.: M 118 ASME P&lD Sect XI Size Viv Act Norm Safety Req'd RelReq Tests Valve No. Class Coord Cat (in.) Type Type Pos Pos Tests or DTJ Pfrmd XR-25-1 2 A-4 A,C-1 1 CK SA O C FE,LJ 4.2.5 FR,LJ XR-25-2 2 A-4 A,C-1 1 CK SA O C FE,LJ 4.2.5 FR,LJ O

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Page 96 of 126 ,

ATTACHMENT 9.3 Valve Testing Table (cont'd)

SYSTEM: Control Rod Hydraulle System P&lD NO.: M-119 ASME P&lD Sect XI Size Viv Act Norm Safety Req'd RelReq Tests Valve No. Class Coord Cat (in.) Type Type Pos Pos Tests or DTJ Pfrmd CRD-114* 2 B-6 C-1 0.75 CK SA O/C O FE 4.2.6 FR CRD-115* 2 B-4 C-1 0.50 CK SA O/C C FE 4.2.7 FR CRD-138* 2 E-4 C-1 0.50 CK SA O/C C FE FE CV-126* 2 C-5 B-1 1 GL AO C O FE 4.2.6 FR CV-127* 2 C-6 B-1 0.75 GL AO C O FE 4.2.6 FR CV-3-32A 2 E3 8-1 1 GL AO O C FE,PI FE,PI CV 3-32B 2 E-1 B1 1 GL AO O C FE,PI FE,PI CV-3 32C 2 E-4 B1 1 GL AO O C FE,PI FE,PI CV-3-32D 2 E1 B-1 1 GL AO O C FE,PI FE,PI CV-3 33A 1 D-3 B-1 2 GL AO O C FE,PI FE,PI CV-3-338 1 D2 B1 2 GL AO O C FE,PI FE,PI CV-3-33C 1 D-3 B1 2 GL AO O C FE,Pl FE,PI CV-3-33D 1 D2 B1 2 GL AO O C FE,PI FE,PI

• Typical of 121 control rod drive units O

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ATTACHMENT 9.3 Valve Testing Table (cont'd)

SYSTEM: Residual Heat Removal System P&lD NO.: M-120 ASME P&lD Sect XI Size Viv Act Norm Safety Req'd RelPeq Tests Valve No. Class Coord Cat (in.) Type Type Pos Pos Tests or DTJ Pfrmd Al-243-2 None A-5 A,C-1 0.75 CK SA O C FE,LK 5.16 FR,LK Al-244-2 None A-5 A,C 1 0.75 CK SA O C FE,LK 5.16 FR,LK Al 610 2 None B-4 A,C 1 0.75 CK SA O C FE,LK 5.16 FR,LK Al-610-4 None C-4 A,C-1 0.75 CK SA O C FE LK 5.16 FR,LK AO-10-46B 1 D-2 A,C-1 16 CK SA C O/C FE,PI, 5.6 FC,PI, LK LK CV-1995 2 B-4 B-1 2 GL AO C O/C FE,PI FE,PI CV-1997 2 C-4 B1 2 GL AO C O/C FE,PI FE,PI MO-1987 2 C-3 B1 20 GT MO O O FE,PI FE,PI MO 1989 2 A2 B1 18 GT MO C C FE,PI FE,PI MO-2003 2 C-5 B1 14 GL MO O O/C FE,PI FE,PI MO-2007 2 D-6 B-1 12 GT MO C O/C FE.Pl FE,PI MO-2009 2 D-6 B1 10 GL MO C O/C FE,PI FE,PI MO-2011 2 D-5 A-1 4 GL MO C O/C FE,LJ, FE,LJ, Pl Pl MO 2013 2 D-3 A-1 16 GL MO O O/C FE,LJ, FE,LJ, Pl Pl MO-2015 1 D3 A-1 16 GT MO C O/C FE,LJ, FE,LJ, Pl,LK Pl,LK MO 2021 2 E-3 A1 10 GT MO C O/C FE,LJ, FE,LJ, Pl PI MO-2023 2 E-2 A-1 10 GT MO C O/C FE,LJ, FE,LJ, Pl Pl MO-40858 1 D-1 B-1 4 GT MO C O/C FE,PI FE,PI RHR-2-2 2 A5 C-1 10 CK SA C O/C FE FE I RHR-2-4 2 B-5 C-1 10 CK SA C O/C FE FE RHR-6-2 1 D-2 B-2 16 GT MA O O Pl Pl RHR-8-2 2 C-3 C-1 3 CK SA C O FE 4.2.8 RR l

/"' RV-1991 2 B-3 C1 1 RV SA C O SP SP l RV-1993 2 C-3 C1 1 RV SA C O SP SP

~

l RV 2005 2 E6 C-1 1 RV SA C O SP SP l

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Page 98 of 126 ATTACHMENT 9.3 Valve Testl.ng Table (cont'd)

SYSTEM: Residual Heat Removal System PalD NO.: M 120 (cont'd) 1 ASME PalD Sect XI Size Vlv Act Norm Safety Reg'd RelReq Tests l Valve No. Class Coord Cat (in.) Type Type Pos Pos Tests or DTJ Pfrmd RV 4282 2 B-6 C1 2.50 RV SA C O SP SP RV-4908B None A-5 C-1 0.25 RV SA C O SP SP 1

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Page 99 of 126 (v) ,

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i ATTACHMENT l

9.3 Valve Testing Table (cont'd)

SYSTEM: Residual Heat Hemoval System P&lD NO,: M-121 ASME PalD Sect XI Size Viv Act Norm Safety Req'd RelReq Tests Valve No. Class Coord Cat (in.) Type Type Pos Pos Tests or DTJ Pfrmd Al-243-1 None A3 A,C-1 0.75 CK SA O C FE,LK 5.16 FR,LK Al 2441 None A3 A,C-1 0.75 CK SA O C FE,LK 5.16 FR,LK Al-610-1 None A-4 A,C-1 0.75 CK SA O C FE,LK 5.16 FR,LK Ai 610 3 None C-6 A,C-1 0.75 CK SA O C FE.LK 5.16 FR,LK AO-10-46A 1 D-5 A,C-1 16 CK SA C O/C FE,PI, 5.6 FC,PI, LK LK CV-1994 2 B-4 B-1 2 GL AO C O/C FE,PI FE,Pl CV-1996 2 C-5 B-1 2 GL AO C O/C FE,Pl FE,PI MO 1986 2 B-6 B-1 20 GT MO O O FE,PI FE,PI MO 1988 2 B-6 B-1 18 GT MO C C FE,PI FE,PI MO 2002 2 B3 B1 14 GL MO O O/C FE,PI FE,PI MO-2006 2 D-3 B-1 12 GT MO C O/C FE,PI FE,PI MO-2008 2 C-3 B1 10 GL MO C O/C FE,PI FE,PI MO 2010 2 C-3 A1 4 GL MO C O/C FE,LJ, FE,LJ, Pl Pl MO-2012 2 D5 A-1 16 GL MO O O/C FE,LJ, FE,LJ, Pl Pl MO-2014 1 D-5 A-1 16 GT MO C O/C F E,LJ, FE,LJ, Pl,LK Pl,LK MO 2020 2 E5 A-1 10 GT MO C O/C FE,LJ, F E,LJ, Pl Pl MO-2022 2 E-5 A-1 10 GT MO C O/C FE,LJ, FE,LJ, Pl Pl MO-2026 1 E-6 A-1 4 GT MO C C FE,LJ, 5.7 FC,LJ, Pl,LK Pl,LK MO 2027 1 E-6 A1 4 GT MO C C FE,LJ, 5.7 FC,LJ, Pl,LK Pl,LK MO 2029 1 D-6 A-1 18 GT MO C C FE,LJ, 5.7 FC,LJ, PI,LK Pl,LK j MO-2030 1 C-6 A1 18 GT MO C C FE,LJ, 5.7 FC,LJ, I PI,LK Pl,LK MO 2032 2 C4 B-1 4 GT MO C C FE,PI FE,PI MO-2407 None C-4 B-1 4 GT MO O C FE,PI FE,PI 1/pir l

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MONTICELLO NUCLEAR GENERATING PLANT EW1-09.04.01 TITLE: INSERVICE TESTING PROGRAM Revision 2*

Page 100 of 126 h ATTACHMENT 9.3 Valve Testing Tabig (cont'd)

SYSTEM: Residual Heat Removal System P&lD NO.: M 121 (cont'd)

ASME P&lD Sect XI Size Viv Act Norm Safety Reg'd RelReq Tests Valve No. Class Coord Cat (in.) Type Typo Pos Pos Tests or DTJ Pfrmd MO-4085A 1 C-6 B-1 4 GT MO C O/C FE,PI FE,PI RHR 2-1 2 A4 C-1 10 CK SA C O/C FE FE RHR-2-3 2 B-4 C1 10 CK SA C O/C FE FE RHR-6-1 1 D-6 B-2 16 GT MA O O Pi Pl RHR 81 2 C5 C-1 3 CK SA O O FE 4.2.8 RR RV-1990 2 B-5 C-1 1 RV SA C O SP SP RV-1992 2 C-5 C1 1 RV SA C O SP SP RV-2004 2 D-2 C1 1 RV SA C O SP SP RV 2025 2 E-4 C-1 1 RV SA C O SP SP RV-2031 2 B-6 C-1 1 RV SA C O SP SP RV-4281 2 B-2 C-1 2.50 RV SA C O SP SP RV 4908A None A-4 C-1 0.25 RV SA C O SP SP O

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ATTACHMENT 9,3 yalve Testing Table (cont'd)

SYSTEM: Core Spray System P&lD NO.: M 122 ASME P&lD Sect XI Size Viv Act Norm Safety Reg'd RelReq Tests Valve No. Class Coord Cat (in.) Type Type Pos Pos Tests or DTJ Pfrmd AO-14-13A 1 E-3 A,C-1 8 CK SA C O FE,PI, 5.6 FC,PI, LK LK AO-14-13B 1 E4 A,C-1 8 CK SA C O FE,PI, 5.6 FC,PI, LK LK CS-9-1 2 C-2 C-1 10 CK SA C O FE FE CS 9-2 2 C-5 C-1 10 CK SA C O FE FE CS-131 1 E-3 B2 8 GT MA O O Pl Pl CS 13 2 1 E-4 B-2 8 GT MA O O Pl Pl CST-103-1 None E2 C-1 2 CK SA O C FE 4.2.9 RR CST-1041 2 E-2 C-1 2 CK SA O C FE 4.2.9 RR MO-1741 2 A-3 B1 12 GT MO O O FE,Pl FE,PI MO 1742 2 A-4 B-1 12 GT MO O O FE,PI FE,Pl MO 1749 2 D-2 B-1 6 GL MO C C FE,PI FE,PI MO 1750 2 D5 B1 6 GL MO C C FE,PI FE,PI MO 1751 2 E-3 A1 8 GT MO O O/C FE,LJ, FE,LJ, Pi Pt MO-1752 2 E-5 A-1 8 GT MO O O/C FE,LJ, FE,LJ, Pl PI MO-1753 1 E-3 A-1 8 GT MO C O/C FE,LJ, FE,LJ, Pl,LK PI,LK MO-1754 1 E-5 A1 8 GT MO C O/C FE,LJ, FE,LJ, Pl,LK Pl,LK RV 1745 2 E-2 C-1 2 RV SA C O SP SP RV 1746 2 E-6 C-1 2 RV SA C O SP SP XFV-82 1 C3 A,C-1 1 FV SA O C FE,LK 5.13 FR,LK l

XFV-83 1 D-4 A,C-1 1 FV SA O C FE,LK 5.13 FR,LK l

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l MONTICELLO NUCLEAR GENERATING PLANT EWl-09.04.01 TITLE: INSERVICE TESTING PROGRAM Revision 2*

Page 102 of 126 ATTACHMENT 9.3 MaliR_. Testing Table (cont'd)

SYSTEM: High Pressure Coolant injection System (Steam Side) P&lD NO.: M 123 ASME P&lD Sect XI Size Viv Act Norm Safety Reg'd RelReq Tests Valve No. Class Coord Cat (in.) Type Type Pos Pos Tests or DTJ Pfrmd CV-2046A 2 C1 B-1 1 GL AO O C FE,PI FE,PI CV-2394A None A-3 B-1 1 GL AO O/C C FE,PI FE,PI HPCI9 2 C-5 A.C-1 16 CK SA C O/C FE,LJ 5.8 FE(O),

FC(C),

LJ HPCI-10 2 C-5 A,C-1 16 CK SA C O/C FE,LJ 5.8 FE(O),

FC(C),

LJ HPCI 14 2 B-4 C-1 2 CK SA C C FE 5.8 FC HPCI-15 2 B-5 C-1 2 CK SA C C FE 5.8 FC HPCI-18 2 A-2 C-1 2 CK SA C O FE FE HPCI20 2 A-3 C-1 2 CK SA C O FE FE HPCI-65 2 B-6 C-1 2 CK SA C C FE 5.8 FC HPCI-71 2 B-6 C-1 2 CK SA C C FE 5.8 FC MO-2034 1 D5 A1 8 GT MO O O/C FE,LJ, F E,LJ, Pl Pl MO 2035 1 D-4 A-1 8 GT MO O O/C FE,LJ, FE,LJ, l Pl PI MO-2036 2 D2 B-1 8 GT MO C O FE,PI FE,PI j PSD-2038 2 C-5 D-1 16 RD SA C O RD RD ]

PSD 2039 None C5 D-1 16 RD SA C O RD RD l RV-2056 3 B-3 C-1 1.50 RV SA C O SP SP XFV-84 1 D-5 A,C-1 1 FV SA O C FE,LK 5.13 FR,LK l XFV 85 1 D-5 A,C-1 1 FV SA O C FE,LK 5.13 FR,LK ,

i O

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Page a'3 of 126 O)

ATTACHMENT 9.3 yalve Testing Table (cont'd)

SYSTEM: High Pressure Coolant Injection System (Water Side) P&lD NO.: M 124 ASME PalD Sect XI Size Viv Act Norm Safety Reg'd RelReq Tests Valve No. Class Coord Cat (in.) Type Type Pos Pos Tests or DTJ Pfrmd Al-611 None C-4 A,C-1 0.75 CK SA O C FE,LK 5.16 FR LK AO-2318 2 B-5 C-1 12 CK SA C O/C FE,PI FE,PI CV 2065 2 B-4 B-1 2 GL AO C O/C FE,PI FE,PI HPCI-31 2 A-4 C1 14 CK SA C O/C FE 5.8 DI(O),

FC(C),

PC(O)

HPCI32 2 E-4 C-1 14 CK SA C O FE FE HPCI-42 2 A4 C-1 4 CK SA C O FE DI MO 2061 2 A-5 B-1 14 GT MO C O/C FE,PI FE,PI MO-2062 2 A-4 B1 14 GT MO C O/C FE,Pl FE,PI MO-2063 2 D-3 B1 14 GT MO O O/C FE,PI FE,PI MO-2067 2 B5 B-1 12 GT MO C O FE,PI FE,PI MO-2068 2 B5 B-1 12 GT MO C O FE,PI FE,PI MO 2071 2 C-5 B-1 8 GL MO C C FE,PI FE,PI RV-2064 2 D-3 C-1 1 RV SA C O SP SP

()

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l MONTICELLO NUCLEAR GENERATING PLANT EWl-09.04.01 j TITLE: INSERVICE TESTING PROGRAM Revision 2* I Page 104 of 126 l

ATTACHMENT i 9.3 Valve Testing Table (cont'd)

SYSTEM: RCIC (Steam Side) P&lD NO.: M 125 ASME P&lD Sect XI Size Viv Act Norm Safety Req'd RelReq Tests Valve No. Class Coord Cat (in.) Type Type Pos Pos Tests or DTJ Pfrmd

~

CV-2082A 2 C-1 B1 1 GL AO O C FE,PI FE,PI CV-2848 None A-4 B-1 1 GL AO O/C C FE,PI FE,PI MO-2075 1 D-5 A1 3 GT MO O O/C FE,LJ, FE,LJ, Pl Pl MO-2076 1 D-4 A1 3 GT MO O O/C FE,LJ, FE,LJ, Pl Pl MO-2078 2 D-2 B-1 3 GL MO C O/C FE,PI FE,PI MO-2096 2 A-3 B-1 2 GL MO C O FE,PI FE,Pi RCIC-9 2 B-6 A,C-1 8 CK SA C O/C FE,LJ 5.9 FE(O),

FC(C), j LJ  !

RCIC-10 2 B-6 A,C-1 8 CK SA C O/C FE,LJ 5.9 FE(O), l FC(C),  !

LJ l RCIC-14 2 A-4 C-1 2 CK SA C O FE FE RCIC-16 2 A-5 C-1 2 CK SA C C FE 5.9 FC RCIC-17 2 B5 C-1 2 CK SA C C FE 5.9 FC RCIC-57 2 B-6 C-1 1.50 CK SA C C FE 5.9 FC  !

1 RCIC-59 2 B-6 C1 1.50 CK SA C C FE 5.9 FC j RV-2097 3 B-3 C-1 1 RV SA C O SP SP PSD 2089 2 C-5 D-1 8 RD SA C O RD RD PSD-2090 None C-5 D1 8 RD SA C O RD RD XFV 86 1 D5 A,C-1 1 FV SA O C FE,LK 5.13 FR,LK XFV-87 1 D-5 A,C-1 1 FV SA O C FE,LK 5.13 FR,LK l O

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MCNTICELLO NUCLEAR GENERATING PLANT EWl-09.04.01 TITLE: INSERVICE TESTING PROGRAM Revision 2'

{} Page 105 of 126 ATTACHMENT 9.3 Yalve Testing Table (cont'd)

SYSTEM: RCIC (Water Side) P&lD NO.: M-126 ASME P&lD Sect XI Size Viv Act Norm Safety Req'd RetReq Tests Valve No. Class Coord Cat (in.) Type Type Pos Pos Tests or DTJ Pfrmd Al 612 None C-5 A,C-1 0.75 CK SA O C FE,LK 5.16 FR,LK AO 13-22 2 B5 C-1 4 CK SA C O/C FE,Pl 5.6 FC,PI CV-2104 2 A-3 B1 2 GL AO C O/C FE,PI FE,Pl MO-2100 2 A-5 B-1 6 GT MO C O FE,PI FE,PI MO-2101 2 D-4 B1 6 GT MO C O FE,PI FE,PI MO-2102 2 D-4 B-1 6 GT MO O O/C FE,PI FE,PI MO-2106 2 B5 B1 4 GT MO C O FE,Pl FE,PI MO-2107 2 B-5 B-1 4 GT MO C O FE,PI FE,PI MO 3502 2 D-5 B-1 4 GT MO C O FE,PI FE,PI RCIC-31 2 A-4 C-1 6 CK SA C O/C FE 5.9 DI(O),

FC(C),

PC(O)

RCIC 37 2 A-4 C-1 2 CK SA C O FE Di RCIC 41 2 D-4 C-1 6 CK SA C O FE FE RV-2103 2 D-3 C-1 1 RV SA C O SP SP I/pir

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MONTICELLO NUCLEAR GENERATING PLANT EWl-09.04.01 TITLE: INSERVICE TESTING PROGRAM Revision 2*

Page 106 cf 126 ATTACHMENT 9.3 Valve Testing Table (cont'd)

SYSTEM: Standby Liquid Control System P&lD NO.: M 127 ASME PalD Sect XI Size Viv Act Norm Safety Req'd RelReq Tests Valvo No. Class Coord Cat (in.) Type Type Pos Pos Tests or DTJ Pfrmd XP 11 14A 2 D5 D-1 1.50 XP SA C O EX EX XP-11-14B 2 E-5 D-1 1.50 XP SA C O EX EX RV 11-39A 2 C-4 C1 1.50 RV SA C O SP SP RV 11-39B 2 B-4 C-1 1.50 RV SA C O SP SP XP-3-1 2 C4 C-1 1.50 CK SA C O FE FE XP-3-2 2 B4 C-1 1.50 CK SA C O FE FE

'XP-6 1 D-6 A,C-1 1.50 CK SA C O/C FE,LJ 4.2.10 FR,LJ XP-7 1 C-6 A,C-1 1.50 CK SA C O/C FE,LJ 4.2.10 FR,LJ O

l l

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MONTICELLO NUCLEAR GENERATING PLANT EWl-09.04.01 TITLE: INSERVICE TESTING PROGRAM Revision 2*

Page 107 of 126 (v)

ATTACHMENT 9.3 Valve Testing Table (cont'd)

SYSTEM: Reactor Water Cleanup System P&lD NO.: M 128 ASME P&lD Sect Xl Size Viv Act Norm Safety Req'd RelReq Tests Valve No. Class Coord Cat (in.) Type Type Pos Pos Tests or DTJ Pfrmd MO 2397 1 D8 A-1 4 GT MO O C FE.LJ, FE,LJ, Pl Pl MO-2398 1 D7 A-1 4 GT MO O C FE,LJ, FE,LJ, Pi PI RC-6-1 2 D-6 A,C-1 1.5 CK SA O C FE,LK 4.2.11 FR,LK RC-6-2 2 D-7 A,C-1 1.5 CK SA O C FE,LK 4.2.11 FR,LK O l l

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MONTICELLO NUCLEAR GENERATING PLANT EWl 09.04.01 TITLE: INSERVICE TESTI.NG PROGRAM Revision 2*

Page 108 of 126 ATTACHMENT 9.3 Valve Testing Table (cont'd)

SYSTEM: Primary Containment Nitrogen Control System P&lD NO.: M 130 ASME PalD Sect XI Size Viv Act Norm Safety Req'd RelReq Tests Valve No. Class Coord Cat (in.) Type Type Pos Pos Tests or DTJ Pfrmd CV 3267 2 C-4 A-1 1 GL AO O C FE,LJ, FE,LJ, Pl Pi CV 3268 2 C4 A1 1 GL AO O C FE,LJ, FE,LJ, Pl Pl CV 3269 2 D-4 A-1 1 GL AO O C FE,LJ, F E,LJ, Pl Pl CV-3311 2 C-5 A1 1 GL AO O C FE,LJ, FE,LJ, Pl Pl CV-3312 2 C-5 A-1 1 GL AO O C FE,LJ, FE,LJ, Pl Pl CV-3313 2 C-4 A1 1 GL AO O C FE,LJ, FE,LJ, Pl Pl CV 3314 2 C-5 A-1 1 GL AO O C FE,LJ, FE,LJ, Pl Pl SV-3307 2 C-5 A1 0.75 GL SO O C FE,LJ, FE,LJ, Pl Pl SV-3308 2 C5 A-1 0.75 GL SO O C FE,LJ, FE,LJ, Pl PI e

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MONTICELLO NUCLEAR GENERATING PLANT EWI-09.04.01 TITLE: INSERVICE TESTING PROGRAM Revision 2*

Page 109 of 126 (O')

ATTACHMENT 9.3 V3lve Testing Table (cont'd)

SYSTEM: Containment Atmosphere Monitoring System P&lD NO.: NH 91197 ASME P&lD Sect XI Size Viv Act Norm Safety Req'd RelReq Tests Valve No. Class Coord Cat (in.) Type Type Pos Pos Tests or DTJ Pfrmd SV 4001 A 2 B6 A-1 0.75 GL SO C C FE,LJ, FE,LJ, Pl PI SV-40018 2 B6 A1 0.75 GL SO C C FE,LJ, FE,LJ, Pl Pl SV-4002A 2 A5 A-1 0.75 GL SO C C FE,LJ, FE,LJ, Pl Pi SV-4002B 2 A-4 A1 0.75 GL SO C C FE,LJ, FE,LJ, Pl PI SV 4003A 2 A5 A1 0.75 GL SO C C FE LJ, FE,LJ, Pl Pl SV-4003B 2 A-4 A-1 0.75 GL SO C C FE,LJ, FE,LJ, Pl PI r~N SV 4004A 2 A-4 A1 0.75 GL SO C C FE,LJ, FE,LJ, Q SV-4004B Pl PI 2 A-4 A-1 0.75 GL SO C C FE,LJ, FE,LJ, Pl Pi SV-4005A 2 B-4 A1 0.75 GL SO C C FE,LJ, FE,LJ, Pl Pl SV-4005B 2 B-4 A-1 0.75 GL SO C C FE,LJ, FE,LJ, Pl Pl SV-4020A 2 A-6 A-1 0.75 GL SO C C FE,LJ, FE LJ, Pl Pl SV 4020B 2 A-6 A-1 0.75 GL SO C C FE,LJ, FE,LJ, Pl PI l

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1 MONTICELLO NUCLEAR GENERATING PLANT EWl-09.04.01 '

TITLE: INSERVICE TESTING PROGRAM Revision 2*

Page 110 of 126 l

ATTACHMENT 9.3 Yalve Testing Table (cont'd)

SYSTEM: Post Accident Sampling PalD NO.: NF-96042 ASME P&lD Sect XI Size Viv Act Norm Safety Reg'd RetReq Tests Valvo No. Class Coord Cat (in.) Type Type Pos Pos Tests or DTJ Pfrmd PAS-58-1 2 B-7 C-1 0.75 CK SA C C FE FE PAS-58-2 2 A-7 C-1 0.75 CK SA C C FE FE PAS-59-5 2 B-6 C-1 0.75 FV SA O C FE 5.11 FC PAS-59-6 2 B-6 C-1 0.75 FV SA O C FE 5.11 FC SV-4081 2 C-5 A-1 0.75 GL SO C C FE,LJ, FE,LJ, Pl Pi SV 4082 2 C-5 A-1 0.75 GL SO C C FE,LJ, FE,LJ, Pl Pt O

O l

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MONTICELLO NUCLEAR GENERATING PLANT EWl-09.04.01 TITLE: INSERVICE TESTING PROGRAM Revision 2*

!^)

V Page 111 of 126

,. ATTACHMENT 9.3 Valve Tecting Table (cont'd)

SYSTEM: Service Air System P&lD NO.: M-131 SH4 ASME P&lD Sect XI Size Viv Act Norm Safety Reg'd RelReq Tests Valve No. Class Coord Cat (in.) Type Type Pos Pos Test:3 or DTJ Pfrmd AS-78 2 D-8 A2 1 GT MA C C LJ LJ AS 79 2 D7 A2 1 GT MA C C LJ LJ O

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MONTICELLO NUCLEAR GENERATING PLANT j EWi-09.04.01 TITLE: INSERVICE TESTING PROGRAM Revision 2*

Page 112 of 126 h 1 ATTACHMENI 9.3 Valve Testing Table (cont'd)

SYSTEM: MSIV/SRV Pneumatic Supply System P&lD NO.: M-131 SH10 ASME P&lD Sect XI Size Viv Act Norm Safety Roq'd RelRoq Tests Valve No. Class Coord Cat (in.) Type Type Pos Pos Tests or DTJ Pfrmd Al 12-9 2 A-3 C-1 1 CK SA O O FE FE Al-12-10 2 A3 C-1 1 CK SA O O FE FE Al-12-11 2 B-3 C-1 1 CK SA O O FE FE Al-1212 2 A3 C-1 1 CK SA O O FE FE Al-598 2 B-5 A,C-1 1 CK SA O O/C FE,LJ 5.10 FC,LJ Al599 2 C-5 A,C-1 1 CK SA O O/C FE,LJ FE,LJ Al700 2 C5 A,C-1 1 CK SA O O/C FE,LJ FE,LJ Al705 None D-6 A.C-1 1 CK SA O C FE,LK FE,LK Al-706 None D-6 A,C-1 1 CK SA O C FE,LK FE,LK Al708 2 B5 A,C-1 1 CK SA O O/C FE,LJ 5.10 FC.LJ Al713 None B6 A,C 1 1 CK SA O C FE,LK 5.10 FC,LK Al714 None B6 A,C 1 1 CK SA O C FE,LK 5.10 FC,LK Al729 None C-7 A,C-1 0.75 CK SA C O FE,LK FE,LK Al730 Nono B-7 A,C 1 0.75 CK SA C O FE,LK 5.10 FC,LK SV-4234 None C-5 A1 1 GL SO O O FE,PI, FE,PI, LK LK SV-4235 None B-5 A1 1 GL SO O O FE,PI, 5.10 FC,PI, LK LK O

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(';

v Page 113 of 126 ATTACHMENT 9,3 .V3.1ve Testing Table (cont'd)

SYSTEM: Instrument Alr Reactor Building P&lD NO.: M 131 SH12 ASME P&lD Sect XI Size Viv Act Norm Safety Reg'd RelReq Tests Valve No. Class Coord Cat (in.) Type Type Pos Pos Tests or DTJ Pfrmd Al 13 4 None D3 A,C 1 0.75 CK SA C C FE,LK 5.16 FR,LK Al-13 7 None A3 A C-1 0.75 CK 'SA C C FE,LK 5.16 FR,LK Al571 2 C-5 A,C 1 2 CK SA O C FE LJ 5.14 FC LJ CV 1478 2 C-5 A-1 2 GL AO O C FE,LJ, FE,LJ, Pl Pl

("\

V y

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l MONTICELLO NUCLEAR GENERATING PLANT EWl-09.04.01 TITLE: INSERVICE TESTING PROGRAM Revision 2*

Page 114 of 126 ATTACHMENT 9.3 Valve Testing Table (cont'd)

SYSTEM: Instrument Air Reactor Building P&lD NO.: M 131 SH14 ASME P&lD Sect XI Size Viv Act Norm Safety Reg'd RelReq Tests Valve No. Class Coord Cat (in.) Type Type Pos Pos Tests or DTJ Pfrmd Al 226-1 2 C-4 A,C-1 0.25 CK SA O C FE,LJ 4.2.12 FR,LJ Al-613 None D-7 A,C-1 0.37 CK SA C C FE,LK 5.15 FR,LK Al 614 None C-7 A,C-1 0.37 CK SA C C FE,LK 5.15 FR,LK Al 615 None C-6 A,C-1 0.37 CK SA C C FE,LK 5.15 FR,LK Al 616 None C-6 A,C-1 0.37 CK SA C C FE,LK 5.15 FR,LK Al-617 None B6 A,C-1 0.37 CK SA C C FE,LK 5.15 FR,LK Al618 None B-1 A,C-1 0.37 CK SA C C FE.LK 5.15 FR,LK Al-619 None B-1 A,C-1 0.37 CK SA C C FE,LK 5.15 FR,LK Al-625 2 C-4 A,C-1 0.37 CK SA O C FE,LJ 4.2.12 FR LJ Al 629 2 B-6 A,C-1 0.37 CK SA C C FE,LJ FE,LJ Al 663 None C-6 C-1 0.37 CK SA O O FE 5.15 FR Al-666 None C-5 C1 0.37 CK SA O O FE 5.15 FR Al-669 None C6 C-1 0.37 CK SA O O FE 5.15 FR Al 672 None A-6' C-1 0.37 CK SA O O FE 5.15 FR Al-675 None B1 C-1 0.37 CK SA O O FE 5.15 FR Al-678 None B-1 C-1 0.37 CK SA O O FE 5.15 FR Al-681 None B-6 C1 0.37 CK SA O O FE 5.15 FR Al 683 None B5 A,C 1 0.37 CK ' SA C C FE,LK 5.15 FR.LK Al-685 None C-4 A,C-1 0.37 CK SA C C FE,LK 5.15 FR,LK Al-694 None B5 C-1 0.37 CK SA O O FE FE Al 695 None C-4 C-1 0.37 CK SA O O FE FE CV-7956 2 B6 A1 0.75 GL AO C C FE,LJ, FE,LJ, Pl Pl O

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MONTICELLO NUCLEAR GENERATING PLANT EWl-09.04.01 TITLE: INSERVICE TESTING PROGRAM Revision 2*

( Page 115 of 126 ATTACHMENT 9.3 Valve Testing Table (cont'd)

SYSTEM: Diesel Oil P&lD NO.: M 133 ASME PalD Sect XI Size Viv Act Norm Safety Req'd RelReq Tests Valve No. Class Coord Cat (in.) Type Type Pos Pos Tests or DTJ Pfrrnd FO-2 None C-3 C-1 1 CK SA O C FE FE FO-5 None D3 C1 2 CK SA O/C O FE FE FO 43 None B2 C1 1.5 CK SA O/C O FE FE FO 44 None B-2 C-1 1.5 CK SA O O FE FE GSA-321 None B4 C-1 0.75 CK SA O/C C FE FE GSA-32 2 None B3 C-1 0.75 CK SA O/C C FE FE GSA-32 3 None E2 C-1 0.75 CK SA O/C C FE FE GSA 32 4 None E-2 C-1 0.75 CK SA O/C C FE FE RV 1523 None D3 C1 0.75 RV SA C O SP SP RV 3216 None B3 C-1 0.50 RV SA C O SP SP RV 3217 None B3 C1 0.50 RV SA C O SP SP RV 3218 None A-3 C-1 0.50 RV SA C O SP SP RV-3219 None B3 C1 0.50 RV SA C O SP SP RV 3220 None B-3 C-1 0.50 RV SA C O SP SP RV-3221 None A3 C-1 0.50 RV SA C O SP SP RV-3224 None E-2 C1 0.50 RV SA C O SP SP RV-3225 None E-3 C1 0.50 RV SA C O SP SP RV-3226 None E-3 C-1 0.50 RV SA C O SP SP RV-3227 None E-2 C-1 0.50 RV SA C O SP SP RV-3228 None E3 C-1 0.50 RV SA C O SP SP RV-3229 None E-3 C-1 0.50 RV SA C O SP SP O

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MONTICELLO NUCLEAR GENERATING PLANT EW1-09.04.01 TITLE: INSERVICE TESTING PROGRAM Revision 2*

Page 116 of 126 ATTACHMENT 9.3 Valve Testing Table (cont'd)

SYSTEM: Fuel Pool Cooling & Cleanup System P&lD NO.: M 135 ASME P&lD Sect XI Size Viv Act Norm Safety Req'd RelReq Tests Valve No. Class Coord Cat (in.) Type Type Pos Pos Tests or DTJ Pfrmd PC-20-1 None E3 C-1 6 CK SA O C FE DI PC-20-2 None E3 C-1 6 CK SA O C FE Di MQTR: These valves are not required to be tested by 10CFR50.55a and are included in the IST Program as good practice. Since the Code requirements for IST are not mandatory, these valves will be tested by grou sing them together and performing a disassembly and nspection of one each refueling outage without including a relief request.

O O

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MONTICELLO NUCLEAR GENERATING PLANT EWi-09.04.01 TITLE: INSERVICE TESTING PROGRAM Revision 2*

Page 117 of 126 ATTACHMENI 9.3 Valve Testing Table (cont'd)

SYSTEM: Open (Dirty) Radwaste Sump System P&lD NO.: M-137 ASME P&lD Sect XI Size Viv Act Norm Safety Reg'd RelReq Tests Valve No. Class Coord Cat (in.) Type Type Pos Pos Tests or DTJ Pfrmd AO-2541 A 2 E-2 A-1 2 GT AO O C FE,LJ, FE,LJ, Pi Pl AO-2541B 2 E-1 A1 2 GT AO O C FE,LJ, FE,LJ, Pl PI O

~h (V

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MONTICELLO NUCLEAR GENERATING PLANT EWl-09.04.01 TITLE: INSERVICE TESTING PROGRAM Revision 2*

Page 118 of 126 ATTACHMENT 9.3 Vaive Testing Table (cont'd)

SYSTEM: Closed (Clean) Radwaste Sump System P&lD NO.: M 138 ASME PalD Sect XI Size Viv Act Norm Safety Req'd RelReq Tests Valve No. Class Coord Cat (in.) Typo Type Pos Pos Tests or DTJ Pfrmd AO-2561 A 2 E-2 A-1 2 GT AO O C FE,LJ, FE,LJ, Pl Pl AO-25618 2 E-1 A-1 2 GT AO O C FE,LJ, FE,LJ, Pl PI O

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MONTICELLO NUCLEAR GENERATING PLANT EWl-09.04.01 TITLE: INSERVICE TESTING PROGRAM Revision 2* l n'

Page 119 of 126 lV)

ATTACHMENT 9.3 Valve Testing Table (cont'd)

SYSTEM: Primary Containment & Atmospheric Control System P&lD NO.: M 143 ASME P&lD Sect XI Size Viv Act Norm Safety Req'd RelReq Tests Valvo No. Class Coord Cat (in.) Type Type Pos Pos Tests or DTJ Pfrmd AO 2377 2 C2 A-1 18 BF AO C C FE,LJ, FE,LJ, Pl Pl AO-2378 2 B3 A-1 18 BF AO C C FE,LJ, FE,LJ, Pi Pl AO-2379 2 C-2 A-1 20 BF AO C O/C FE,LJ, FE,LJ, Pi Pi AO-2380 2 B2 A-1 20 BF AO C O/C FE,LJ, FE,LJ, Pl Pl AO-2381 2 C3 A1 18 BF AO C C FE,LJ, FE,LJ, Pl Pl AO-2382A None B-4 A,C-1 18 CK SA C O/C FE,LK, FE,LK, Pl Pl AO 23828 None B4 A,C-1 18 CK SA C O/C FE,LK, FE,LK, Pl Pl AO-2382C None B-4 A,C-1 18 CK SA C O/C FE,LK, FE,LK, Pl Pl AO 2382E None B-4 A,C-1 18 CK SA C O/C FE,LK, FE,LK, Pl Pl AO-2382F None B-4 A,C-1 18 CK SA C O/C FE,LK, FE,LK, Pl Pl AO 2382G None B-4 A C-1 18 CK SA C O/C FE,LK, FE,LK, Pl Pl AO 2382H Yone B4 A,C-1 18 CK SA C O/C FE,LK, FE,LK, Pl Pl AO 2382K None B-4 A,C-1 18 CK SA C O/C FE,LK, FE,LK, Pl Pl AO-2383 2 B-6 A-1 18 BF AO C C FE,LJ, FE,LJ, Pl Pl AO 2386 2 D-6 A-1 18 BF AO C C F E,LJ, FE,LJ, Pl PI AO 2387 2 D-6 A1 18 BF AO C C FE,LJ, FE,LJ, Pl Pl g- AO-2896 2 C-6 A-1 18 BF AO C C FE,LJ, FE,LJ,

( Pi Pi i

CV-2384 2 A-6 A-1 2 GL AO C C FE.LJ, FE.LJ, Pl Pl 1/pir

MONTICELLO NUCLEAR GENERATING PLANT EWl-09.04.01 TITLE: INSERVICE TESTING PROGRAM Revision 2*

Page 120 of 126 h ATTACHMENT 9.3 Valve Testing Table (cont'd)

SYSTEM: Primary Containment & Atmospheric Control System P&lD NO.: M 143 (cont'd)

ASME P&lD Sect XI Size Viv Act Norm Safety Req'd RetReq Tests Valve No. Class Coord Cat (in.) Type Type Pos Pos Tests or DTJ Pfrmd CV 2385 2 C6 A-1 2 GL AO C C FE,LJ, FE,LJ, Pl PI D W V-8-1 2 B-2 A.C-1 20 CK SA C O/C FE,LJ FE,LJ D W V-8-2 2 C-2 A,C-1 20 CK SA C O/C FE,LJ FE,LJ O

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/O Page 121 of 126 V

ATTACHMENT 9.3 Valve Testing Table (cont'd)

SYSTEM: Service Water Systems and Makeup intake Structure P&lD NO.: M-811 (RHRSW)

ASME P&lD Sect XI Size Viv Act Norm Safety Req'd RelReq Tests Valve No. Class Coord Cat (in.) Type Type Pos Pos Tests or DTJ Pfrmd AV-3147 3 C-4 C-1 3 'AR SA O C FE FE AV-3148 3 B8 C1 3 AR SA O C FE FE AV 3149 3 B4 C-1 3 AR SA O C FE FE AV-3150 3 B-8 C-1 3 AR SA O C FE FE RHRSW 1-1 3 C-4 C-1 12 CK SA C O/C FE FE RHRSW-1-2 3 C-8 C-1 12 CK SA C O/C FE FE RHRSW-1-3 3 C4 C-1 12 CK SA C O/C FE FE RHRSW-1-4 3 C8 C-1 12 CK SA C O/C FE FE RHRSW-3-1 3 C-4 B1 18 GT MA C O FE FE D RHRSW-3 2 3 C-7 B-1 18 GT MA C O FE FE RHRSW-21-1 3 C-4 B-1 0.5 GL MA C O FE FE RHRSW-21-2 3 C-8 B1 0.5 GL MA C O FE FE RHRSW-21-3 3 C-4 B-1 0.5 GL MA C O FE FE RHRSW-21-4 3 C-8 B1 0.5 GL MA C O FE FE RV-3038 3 C-4 C-1 1 RV SA C O SP 4.2.19 SP RV 3039 3 C7 C1 1 RV SA C O SP 4.2.19 SP SW-21-1 3 C-3 C-1 1 CK SA O C FE 4.2.13 RR SW-21 2 3 C7 C-1 1 CK SA O C FE 4.2.13 RR SW 221 None C-3 C-1 1 CK SA O C FE 4.2.13 RR SW 22-2 None C-7 C1 1 CK SA O C FE 4.2.13 RR C

b l I

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l l MONTICELLO NUCLEAR GENERATING PLANT \ EWl-09.04.01 l TITLE: INSERVICE TESTING PROGRAM Revision 2*

l Page 122 of 126 ATTACHMENT 9.3 . Valve Testing Table (cont'd) l SYSTEM: Service Water Systems and Makeup Intake Structure P&lD NO.: M-811 l (ESW) l ASME P&lD Sect XI Size Viv Act Norm Safety Req'd Rel Req Tests i Valve No. Class Coord Cat (in.) Type Type Pos Pos Tests or DTJ Pfrmd l AV-3155 3 B-5 C-1 2 AR SA O C FE FE l AV 3156 3 B6 C-1 2 AR SA O C FE FE AV-4024 3 C-4 C-1 1 AR SA O C FE FE AV-4026 3 C-6 C-1 1 AR SA O C FE FE ESW 1-1 3 B-5 C-1 4 CK SA C O FE FE ESW 12 3 B-6 C-1 4 CK SA C O FE FE ESW 21 3 C5 B1 4 GT MA C O FE FE E SW-2-2 3 C-5 B1 4 GT MA C O FE FE ESW-3-1 3 C-5 B-1 4 GT MA C O FE FE E SW-3-2 3 C-6 B1 4 GT MA C O FE FE ESW-5 2 3 C7 B-1 4 GT MA O C FE FE ESW 13 None D-6 C-1 4 CK SA O C FE 4.2.14 RR ESW-14 3 D-6 C-1 4 CK SA O C FE 4.2.14 RR ESW 15 None D5 C-1 4 CK SA O C FE 4.2.14 RR ESW 16 3 D4 C-1 4 CK SA O C FE 4.2.14 RR ESW-17 None C-6 C1 4 CK SA C O FE FE ESW-18 3 C-4 C-1 4 CK SA C O FE FE ESW-19 3 C-6 B-1 4 GT MA C O FE FE ESW-20 3 C-4 B-1 4 GT MA C O FE FE SW 15 None D-7 C-1 4 CK SA C C FE 4.2.14 RR SW 16 3 D-7 C-1 4 CK SA C C FE 4.2.14 RR l SW 17 None D-7 C-1 4 CK SA C C FE 4.2.14 RR SW 18 3 D-7 C-1 4 CK SA C C FE 4.2.14 RR O

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MONTICELLO NUCLEAR GENERATING PLANT EWI-09.04.01 TITLE: INSERVICE TESTING PROGRAM Revision 2*

f') Page 123 of 126 v

ATTACHMENT 9.3 Valve Testing Table (cont'd)

SYSTEM: Combustible Gas Control System Div i (East) P&lD NO.: NH-94896 ASME P&lD Sect XI Size Viv Act Norm Safety Req'd Rol Req Tests Valve No. Class Coord Cat (in.) Type Type Pos Pos Tests or DTJ Pfrmd AO-7422A 2 D7 A1 4 GL AO C O/C FE.LJ, FE,LJ, Pi,FS Pl,FS AO-7423A 2 D7 A-1 4 GL AO C O/C FE,LJ, FE.LJ, Pl,FS PI,FS AO 7424A 2 B7 A1 6 GL AO C O/C FE.LJ, FE,LJ, PI,FS PI,FS AO 7425A 2 B7 A1 6 GL AO C O/C FE,LJ, FE,LJ, Pl,FS Pl,FS CGC 12-1 3 A-5 C-1 1.50 CK SA C O/C FE FE MO-4043A 3 D-5 B1 3 GL MO C O FE,PI FE,PI MO-4044A 3 C5 B-1 3 GL MO C O FE,PI FE,PI MO-4047A 3 B4 B1 0.75 GL MO C O FE,PI FE,PI RV-4032A 3 B5 C1 1 RV SA C O SP SP SV-4033A 2 A-6 B1 2 GL SO C O FE,PI FE,PI SV 4034A 2 A-6 B1 2 GL SO C O FE,PI FE,PI SV-4054A 3 A5 B1 0.75 GL SO C O FE,PI FE,PI 1/pir

MONTICELLO NUCLEAR GENERATING PLANT EWi-09.04.01 TITLE: INSERVICE TESTING PROGRAM Revision 2*

Page 124 of 126 AUACHMENT 9.3 Valve Testing Table (cont'd)

SYSTEM: Combustible Gas Control System Div ll (West) P&lD NO.: NH-94897 ASME P&lD Sect XI Size Viv Act Norm Safety Reg'd RelReq Tests Valvo No. Class Coord Cat (in.) Type Type Pos Pos Tests or DTJ Pfrmd AO-7422B 2 D-7 A1 4 GL AO C O/C FE,LJ, FE,LJ, Pl,FS Pl,FS AO 7423B 2 D7 A-1 4 GL AO C O/C FE,LJ, FE,LJ, Pl,FS Pl,FS AO-74248 2 Bi A-1 6 GL AO C O/C FE,LJ, FE,LJ, Pi,FS Pl,FS AO 74258 2 B-7 A-1 6 GL AO C O/C FE,LJ, FE,LJ, Pl,FS Pl,FS CGC-12-2 3 A-5 C-1 1.50 CK SA C O/C FE FE MO-4043B 3 D-5 B1 3 GL MO C O FE,PI FE,PI MO 4044B 3 C-5 B1 3 GL MO C O FE,PI FE,PI MO-40478 3 B-4 B1 0.75 GL MO C O FE,PI FE,PI RV 4032B 3 B5 C-1 1 RV SA C O SP SP SV-4033B 2 A-6 B-1 2 GL SO C O FE,Pl FE,PI SV-40348 2 A6 B1 2 GL SO C O FE,PI FE Pl SV-4054B 3 A-5 B1 0.75 GL SO C O FE,PI FE,PI O

1/pir l

' MONTICELLO NUCLEAR GENERATING PLANT EWi-09.04.01 TITLE: INSERVICE TESTING PROGRAM Revision 2*

f^) Page 125 of 126 V

ATTACHMENT 9.3 Valve Testing Table (cont'd)

SYSTEM: Traversing incore Probe System l

P&lD NO.: GE0719E520 l ASME P&lD Sect XI Size Viv Act Norm Safety Reg'd RelReq Tests Valve No. Class Coord Cat (in.) Type Type Pos Pos Tests or DTJ Pfrmd TIP-1-1 2 D-5 A1 0.25 BA SO C C FE,PI, FE,PI, LJ LJ TIP-2-1 2 D-5 A-1 0.25 BA SO C C FE,PI, FE,PI, LJ LJ TIP-3 1 2 D5 A1 0.25 BA SO C C FE,Pl, FE,PI, LJ LJ TIP-1-2 2 D-5 D-1 0.25 XP XP O C EX EX TIP 2 2 2 D-5 D-1 0.25 XP XP O C EX EX TIP-3-2 2 D-5 D-1 0.25 XP XP O C EX EX O

O 1/pir

i MONTICELLO NUCLEAR GENERATING PLANT EWl-09.04.01 TITLE: INSERVICE TESTING PROGRAM Revision 2*

Page 126 of 126 K[IACHMENT 9.3 Valve Testing Table (cont'd)

SYSTEM: Hard Pipe Vent P&lD NO.: NH 116029 ASME P&lD Sect XI Size Viv Act Norm Safety Req'd RelReq Tests Valvo No. Class Coord Cat (in.) Type Type Pos Pos Tests or DTJ Pfrmd AO-4539 2 C-3 A-2 8 BF AO C C LJ LJ AO-4540 2 C-4 A-2 8 BF AO C C LJ LJ PSD-4543 None B-6 D-1 10 RD SA C O l RD RD O

l 9

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