ML20211N687
| ML20211N687 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 09/16/1997 |
| From: | BOSTON EDISON CO. |
| To: | |
| Shared Package | |
| ML20211N679 | List: |
| References | |
| 8.I.1.1, NUDOCS 9710170072 | |
| Download: ML20211N687 (236) | |
Text
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0 Boston Edison RTYPE H6.08 PILGRIM NUCLEAR POWER STATION Procedure No. 6.l.1.1 INSERVICE PUMP AND VALVE TESTING PROGRAM
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REQUIRED REVIEWS REVIEWERS AND APPROVERS Stop 1 Lk Prt cMdure Writer
%Dat'e Th.k in STAR -"
Technicp'L Review UM '_
9/n/n Act Date Review L Tit edor g Da ,
T1 IST PROGRAM RELATED 1y, b L - dsb Date Q@ dure Owner SAFETY REVIEW REQUIRED QAG Manager Date ORC REVIEW REQUIRED OR MLhairman '
cp/gjq, Date A. .N' A3X slicfr ,
Resgble Managerg / Dste 7//h /f7 Effective Date:
080425 8. l.1.1 Rev. 9
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i REVISlQtLLOG REVISION 9 Date Originated 6/97
{
l- Paoes Affected Descriollon 6,27,55,59,61-70, Revise description of OM-10 justification, incorporate Section 7.4 3_
72-79,81-85,87-89, - for valve OM-10 justifications. Incorporate new valve justification -
- 91-97,99,100,104, OM(10)-01 for leak rate testing Appendix J valves in accordance 105,107,108,110, with ANSI /ASME OM-10 for implementation o1 performance based '
i 123,177-179,214 testing using Option B of Appendix J. Retram RV-28 to be i_
consistent with this change. Delete RV-28 from program valve j table for a pplicable LJ tested valves. Add O&M Part 10 justification i OM(10)-O' and revise test frequency to "OBJ" within valve program j table for all LJ and LJW tested valves.
l 8 Revise edition of ASME/ ANSI OM Part 6 and OM Part 10 in j References from "OM-1987" to "OMa-1988 Addenda to OM-1987".
i 10,32,81,88,93,96 Revise test description of Nonintrusive Testing (NIT) and identify i PNPS 8.l.37 as NIT Program Procedure. A:Id NUREG 1482 Nli
!- Section 4.1.2 to 4.0, Compliance. Reference PNPS 8.l.37 within l valve table for NIT valves (including NIT using a sample plan).
15-17 Revise pump postmaintenance work scope guideline to provide additional clarity. Revise pump postmaint2 nance example to incorproate RBCCW pump PWT
- pumps) for shutoff head testing. guidance (!nstead of SSW 20,26,130 Retract RP-05. Remove RP-05 from Pump Test Table, delete table
!- note for postmaintenance testing using shutoff head test method.
Revise SSW Pump Hydraulic Test Circuit (Section 5.3.1) to reflect i RP-05 retraction while maintaining the doncription of shutoff head test method. Add Ll-38010 and LI-38011 to SSW instrumentation.
L 21,24 Revise description of RBCCW Pump (Section 5.3.2) and SBLC l Pump (Section 5,3.8) hydraulic test paths i 26 Pump Test Table: Revise note for RBCCW Pumps to provide more l clarity. Correct column for SSW pump speed to show 'N/A".
j 27 Revise description of refuel outage justification.
29,30 Revise Inservice Valve Testing Program Table Steps 6.1[2](m) and -
' (n) descriptions for " Relief / Justification" and " Notes" to be more g descriptive.
31- _ Clarify Measurement of Test Quantities description for check valve j exercise practices.'
\ 31,35,36 '
Add exception statement to Measuremsnt of Test Quantities
- description for seat leakage that identifies CIVs as being tested
! using ASME/ ANSI OM-10J Revise Corrective Action description for
- seat leakage to be consistent. Revise descriphon of test definition for LJ, LJW, LP, and LX tests to be consistent with Valve i Justification OM(10)-01 and to provide additional clarity.
} 8l.1.1 Rev.9
- Page 2 of 236
L 1
- REVISIOMLOG (Continued) 4
?
j_ LREVISION 9(Cont.) Date Originated 5/97
- - Panes Affected Description 4 ,
32,81,169,170,209, Remove Check Valves 1001-2A and 1001-2C from the Check
[ 212; Valve Sample Disassembly Program. . Revise valve table, program j body, and RV-27 to reflect this change. These_ valves were -
! replaced during RFO 11 with a new model which can pass i increased flow and enables forward flow exercise to be verified r using NlT techniques incorporate RJO-08 for test frequency.
4- 32,88,93,96,171, Remove Check Valves 1301-47 and 230140 from the Check
- 172,209,212,213 _ Valve Sam le Disassembly Program. N!T techniques have been t successfu implemented on these valves. Revise valve table,
- program b y, and RV-27 to reflect these changes. Also revise i RV-27 to show that NIT methods will be performed on check valves i 1400-13A and 1400-13B in lieu of valve disassembly when i possible. Incorporate RJO-09 for test frequency of '.30147 and 2301-40.
. 39,40 Revise Program Test Frequency (Table 2):
! e to better clarify test frequencies to Code application and
[ component types,
- - to add frequency "OBJ" and define for leak testing using l Option B of Appendix J. Add Note (3) to clarify "OBJ" test frequency.
l 53,54,226 Remove valves 3880A through E from RV-38 since they can now be tested quarterly and correct valve table to reflect this change.
Remove Note referencing PNPS 8.l.11.20 from valve table since Procedure was retired.
7
[ 53-124 Program valve table: Change " Relief Request" column to read
" Relief / Justification". <
_ 55 -
Add PSV-4033 to the IST Program. Safety significance was increased IAW FRN 97-01-35.
- 55- Add Note 3 to valve table for CK-30-419 through CK-30-424 which provides addiilonal postmaintenance guidance.
> 94 Revisa Proced. > numbers for testing CK-2301-232 and l CK-2301-233 6 -
8 l.36 to 8.5.4.14, for testing CK-2301-218 from 8.l.36 to 8.5.4.u.
- 69,70,87,89,90, Revise RV-037 to provide additional justification, make cla-ifying i 92-94,96,97,100, changes, and remove Containment isolation Valves from this -
173-176,223-225 Relief. Incorporate RJO-10 to provide frequencyjustification for check valve exercising of CIVs (now leak tested using Option B of Appendix J) removed from RV-037. Revise Program Valve table to j- be consistent with changes.
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- l. Page 3 of 236
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REVISION LOG (Continu:d)
REVISION 9 (Cont.) Date Origlanted 5/97 Paoes Affected. Descriotion 138 Revise CS-02 to reflect PDC 94-12 change in Shutdown Cooling Valve Reactor Pressure Interlock (to prevent opening) from 100 psig to 70 psig.
155,156,158-160 Revise RJO-01 RJO-02, and RJO-03 to provide additional clarification and enable check valve exercise methods to be consistent with leak testing CIVs using Option B of Appendix J.
182 Revise RV-02 to identify that a reverse flow exercise (FC) is part of the required alternate testing.
REVISION 8 Date Originated 12/96 Paaes Affected Descriotion 16 Clarify pump postmaintenance test work scope guideline.
)
20,26 Revise hydraulic circuit and Pump Test Table to reflect change to perform quarterly full flow testing using ultrasonic flow measurement when plant conditions permit for SSW pumps.
i 24,25 Revise hydraulic circuit to show optional method to perform testing using ultrasonic flow meter for SBLC.
32,38 Provide description of nonintrusive testing (NIT) of check valves within general requirements.
35 Clarify corrective action guidelines for Appendix J seat leakage testing.
44 Revise cross-reference work scope table for check valve and MOV grease application work task exceptions.
45 Revise specified maintenance work scope for conduct of PI test.
71,171,172 Revise test frequency for 19-CK-235 and 19-CK-245 to once per RI. Revise valve table and create justification RJO-07 to support this change.
82 Move 8.l.30 reference to 21 valve Pl.
84,86,90 revision i(s complete. Remove *) from Procedure numbers to 86 Update Valve Test Table to reflect use of PNPS 8.l.34 for NIT Diagnostic Testing to 68A&688.
59,69,93,100,104 Revise test procedure numbers within valve testing table.
103 Remove Non-Code Class CRD hydraulic control unit rupture discs from the IST Program scope.
8.1.1.1 Rev. 9 Page 4 of 236
% == ==e- e e
REVISION LOG (Continu:d)
REVISION 7 Date Originated 12/95 Peaes Affected Descriotion 7,10,27,29,38,125, Create new Section 7.3 for Refuel Outage Justifications (RJO).
158 Add dascriptive information of RJO to Valve Compliance, General information, and Discussion sections.
5 Add ASME/ ANSI OM-1, OM-6, and OM 10 to Developmental References.
34 Correct referenced PNPS 1.3.34 Attachment number to be 9.
M 43-45 Provide additional clarification for postmaintenance test description of routine servicing and impacting Specified Maintenance for LJ, LP, LJW, LX, Pl, and RT postmaintenance test requirement.
55,62-65,70,72-81, Update Test Procedure and alternate Procedure numbers on valve
. 86-88,91,93-97,99, tables to reflect recent revisions. A"d PNPS 8.1.30 to Notes iL 101-103,107,108, section as alternate Pl test procedure. Remove (*) from certain 110,123 Procedure numbers to show that needed revision is complete.
82 Edit correction to Valve Test Table.
88,93,97,99 Clarify normal position for Stop Check Valves CK-1400-13A, CK-1400-138, CK-2301-74, CK-1301-64, and CK-1201-81.
144,152,153,165-170 Retract Cold Shutdown Justification CS-07, CS-15, and CS-16.
Add O&M-10 Refuel Outaga Justifications RJO-04, RJO-05, and RJO-06. Adjust valve table to reflect changes and new Procedure numbers.
156,157 Add Cold Shutdown Justification CS-19 for CK-2301-64 valve stroking and revise valve table to reflect change.
159-164,172,185,186 Retract Relief Requests RV-01, RV-12, and RV-13. Replace with O&M (10) Refuel Outage Justifications RJO-01, RJO-02, and RJO-03 respectively. Adjust valve tables to reflect changes.
202 Revise and clarify RV-27 justification wording for CK-1301-27 and CK-2301-39.
- 8. l.1.1 Rev. 9 Page 5 of 236
TABLE OF CONTENTS P_922 1.0 l ' P U R P O S E AN D S C O P E . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . .
2.0 DISCUSSION.....................................................................................................7 3.0 D EVE LO PM E NTA L R E F E R E N C E S............... ........ ................... .... ..................... 8 4.0 C O M P L I AN C E . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
5.0 I N S E RVI C E P U M P TE STI N G . . .. . . ... .. .. . .. . . . . . .. . .. .. . . . .. . .... . . . . . .. .. . . . . . . . . .. .. . . . . .. . . . . . . . . . . . 10 5.1 G E N E RAL I N F O RMATI O N ........................................... ... ................ 1 0 5.2 P U M P PO STMAINTE NAN C E TE STIN G ................................................. 14 5.3 HYD RAU L l C C l R C U ITS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . 2 0 5.4 P U M P P R O G RAM TAB L E. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 5 6.0 I N S ERVI C E VALVE TE STI N G . . . .. ... . .............. . ..... ... ...... . .... . . .. ...... . . . . . . . . ... . ... .. . .. .. 27 6.1 G E N E RAL I N F O RMATI O N ......... ... .. ..... ....... . ...... ... . . .... . . .. . ... . ... . .. . . ....... ... 27 6.2 VALVE POSTMAINTENANCE TESTIN G ....... ....................................... 41 6.3 VALVE P RO G RAM TAB L E ....... .. . . .. ... .... .. . .. .. .... . . .......... . .. .. .... . ...... . .. . . . . .. . 51 7.0 PROGRAM COLD SHUTDOWN JUSTIFICATIONS, REFUEL OUTAGE JU STlFICATION S, AND RELIEF REQU ESTS...................................................125 7.1 PUMP TESTING PROGRAM RELIEF REQUESTS ................................125 7.2 VALVE TESTING PROGRAM COLD SHUTDOWN J U ST I F I C ATI O N S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
7.3 VALVE TESTING PROGRAM REFUEL OUTAGE JUSTIFICATIONS....161 7.4 VALVE TESTING PROGRAM OPERATIONS AND MAINTENANCE (PART 10) J U STIFIC ATION S ......................... ........................................,177 _
7.5 VALVE TESTING PROGRAM RELIEF REQUESTS...............................180
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1.0 PURPOSE AND SCOPE i
i l This Procedure encompasses and controls the PNPS Inservice Testing (IST) Program, it i identifies the scope of components (pumps and valves) and testing requirements for l compliance with 10CFR50.55a(f), inservice Testing Requirements; and Generic Letter 89-04,
! Guidance on Developing Acceptable Inservice Testing Program. This Procedure will be i
utilized for the IST Program submittal to satisfy 10CFR50.55a(f)(4)(li) and also to identify impractical Code requirements in accordance with 10CFR50.55a(f)(5).
~ impractical Code requirements are reviewed and dispositioned by the Nuclear Regulatory
- Commission and documented in a Safety Evaluation Report authored by the Office of Nuclear i Reactor Regulation as related to the Inservice Testing Program and Requests for Relief. The
! Nuclear Regulatory Commission will grant program relief requests pursuant to i 10CFR50.55a(a)(3)(i),10CFR50.55a(a)(3)(li), or 10CFR50.55a(f)(6)(i). Granting of relief l cnsures that the IST Program has satisfactorily demonstra.,ed that either: 1)"The proposed
- alternative provides an acceptable level of quality and safety",2)" Compliance would result in l hardship or unusual difficulty without a compensating increase in the level of quality and 1 safety", or 3)"Conformance with certain requirements of the applicable code edition and j addenda is impractical for its facility".
1
- This Procedure also provides postmaintenance guidelines to aid Station personnel when determining test requirements for plant safety-related components.
2.0 DISCUSSION This Procedure applies to Class 1,2,3, and safety significant pumps and valves for conformance with ASME Boiler and Pressure Vessel Code,Section XI,1986 Edition. The Procedure details the following items: compliance requirements, general infctmation, postmaintenance testing guidelines, pump hydraulic circuits, and tables of the components (pumps and valves) tested. The last section (7.0) contains valve Cold Shutdown Justifications, valve Refuel Outage Justifications, and Relief Requests.
This Procedure's pump and valve tables provide a cross-reference between a component test requirement and a Station Procedure implementing the test. Additional information is provided within this component listing: safety class, category, test frequency, pump test parameters, valve test requirements, relief requests, valve justifications, and remarks. Newly incorporated component / test requirements will have implementing Procedures identified for future incorporation. All newly identified component / test requirements shall be initially tested during the next scheduled freq'uency (i.e., quarterly, Cold Shutdown, refueling, and two-year interval) following Procedure approval date.- These newly incorporated component / test requirements will be identified by an asterisk (*) next to the implementing Procedure. When using (*) Procedures for postmaintenance testing, the current approved Procedure should be reviewed for applicability (i.e., is the new test requirement or component incorporated).
8.l.1.1 Rev.9 Page 7 of 236 1
2.0 DISCUSSION (Continued) i The inservice tests identified in this program will verify the operational readiness of pumps and valves whose functions are required to mitigate the consequences of an accident or to bring the Reactor to a Cold Shutdown condition or maintain the Reactor in a safe shutdown condition. Additional components considered to have a safety significant function may be incorporated. The ISI safety classification of each pump and valve was determined in accordance with Regulatory Guide 1.26. Safety related components not classified as Group A, B, or C in accordance with Regulatory Guide 1.26 are included as nonclassed (NC).
Additionally, all containmr nt penetrations shall be classifed as ISI Class 1 or Class 2.
PNPS 8.l.1, ' Administration ofInservice Pump and Valve Testing", covers the administrative requirements for the development, performance, and maintenance of the PNPS Inservice Test
- Program in accordance with the ASME Code,Section XI, Subsections IWA, IWP, and IWV.
I PNPS 8.1.1 also details the following items: Developmental References, Responsibilities, Definitions, Tee Requirements, Compliance Requirements, Evaluation and Disposition, Postmaintenance Testing, and Administration.
3.0 DEVELOPMENTAL REFERENCES
[1] 10CFR50 Appendix J, Primary Reactor Containment Leakage Testing
~
[2] 10CFR50.55a(b), Code and Standards, Reference Applicability
[3] 10CFR50.55a(f), inservice Testing Requirements
[4] ASMFJANSI OM-1987 Part 1, Requirements For Inservice Performance Testing Of Nuclear Power Plant Pressure Relief Devices
[5] ASME/ ANSI OMa-1988 Addenda to OM-1987 Part 6, inservice Testing Of Pumps in Light-Water Reactor Power Plants
[6] ASME/ ANSI OMa-1988 Addenda to OM-1987 Part 10, inservice Testing of Valves in Light-Water Reactor Power Plants
[7] ASME Boiler and Pressure Vessel Code,Section XI (Rules for Inservice Inspection of Nuclear Power Plant Components),1986 Edition, Subsectinns IWA, IWV, and IWP
[8] BECo Letter 94-039 to NRR US NRC," Notes of Telecon Between NRR and BECo on
, IST Program implementation", dated April 20,1994 4
[9] Division 1 (Dra*t) Regulatory Guide and Value/ impact Statement, " Identification of Valves For inclusion in Inservice Test Programs"
[10] ESR Response Memo ERM-90-578
! [11) IEN 88-70, " Check Valve Inservice Testing Program Deficiencies" 8.l.1.1 Rev. 9
- Page 8 of 236
3.0 DEVELOPMENTAL REFERENCES (Continued)
[12) NRC Generic Letter 87-06, "Perioaic Venficauon of Leak Tight Integrity of Pressure isolation Valves"
[13] NRC Generic Letter 89-04, " Guidance on Developing Acceptable Inservice Testing Programs"
[14) NRC Publication: " Minutes of the Pub lic Meetings on Generic Letter 89-04", dated October 25,1989
[15] NUREG 1352, " Action Plans for Motor-Operated Valves and Check Valves"
[16] NUREG 1482, " Guidelines for Inservice Testing at Nuclear Power Plants", dated April,1995 (17) PNPS 8.l.1, " Administration ofInservice Pump and Valve Testir'g"
[18] PNPS "O"-List
[19) Safety Evaluation Report (with attached TER) by the Office of Nuclear Reactor Regulation related to the inservice Test Program and Requests for Relief, Pilgrim Nuclear Power Station Docket No. 50-293, dated 4/22/91 (TAC No. 74785) and Revision No.1 of the TER dated 2/3/92
[20] Safety Evaluation Report (with attached TER) by the Office of Nuclear Reactor Regulation related to the inservice Test Program and Requests for Relief, Pilgrim Nuclear Power Station Docket No. 50-293, dated 6/23/93 (TAC No. M85069).
[21] Standard Review Plan 3.9.6, " Inservice Testing of Pumps and Valves" 4.0 COMPLIANCE This ins.3rvice Pump and Valve Testing Program will be in effect through the third 120-month inspection interval (ending December 7,2002) and will be updated in accordance with the requirements of 10CFR50.55a(f).
This Proccdure complies with the evaluations, conclusions, and guidelines presented within the Safety Evaluation Report by the Office of Nuclear Reactor Regulation Related to the Inservice Testing Program and Requests for Relief Pilgrim Nuclear Power Station Docket No. 50-293, dated 4/11/91, and Revision No.1 of the TER dated 2/3/92; also, numerous cvaluations, conclusions, and guidelines presented within the Safety Evaluation Report by the Office of Nuclear Reactor Regulation related to the Inservice Testing Program and Requests for Relief Pilgrim Nuclear Power Station Docket No. 50-293, dated 6/23/93.
- 8. l.1.1 Rev.9 Page 9 of 236
4.0 COMPLIANCE (Continued)
This Procedure'ou!!ines the PNPS IST Program based on the requirements of Section XI of ASME Boiler and Pressure Vessel Code,1986 Edition An exclusion to the requirements of the 1986 Edition is that the IST Program shall comply with the ANSl/ASME OM-1-1987 in lieu 1
of the 1981 Edition of OM-1 (Reference ikW-3510, Safety Valve and Relief Valve Tests).
This substitution was made because of improvement in the 1987 Edition with regard to typographical errors in 1981. The use of the 1987 Edition conforms with the intent of 10CFR50.55a(f)(4)(iv) in that all safety, relief, and safety relief valves shall meet the requirements of the 1987 Edition.
The recent pump testing guidelines within NUREG 1482 (published April,1995);
Section 5.1.2, " Continued Measurement of Parameters Deleted From OM-6", Section 5.3,
" Allowable Variance From Reference (for fixed resistance systems)" Section 5.7, "Use of OM-6 Table 3b Ranges For Hydraulic Parameters", and Section 5.8, " Duration of Tests", have been adopted into this testing program.
The recent valve testing guidelines within NUREG 1482 (pubiished April,1995); Section 3.1.1,
" Deferring Valve Testing to Each Cold Shutdown or Refueling Outage"; Section 4.1.2,
" Exercising Check Valves with Flow and Nonintrusive Techniques"; and Section 4.1.4,
" Extension of Test Interval to Refueling Outage For Check Valves Verified Closed by Leak Testing", have been adopted into this test program.
If this Procedure conflicts with PNPS Technical Specifications, a Technical Specifications amendment shall be submitted to conform the Technical Specifications to this Procedure in
. accordance with 10CFR50.55a(f)(5)(ii). Until approval of the Technical Specifications amendment, the most limiting requirement shall be met.
5.0 INSERVICE PUMP TESTING 5.1 GENERAL INFORMATION
[1]- Acolicable Code _
Tnis inservice Testing Program for ISI Class 1,2,3, and NC Pumps meets the requirements of Subsection IWP of Section XI of the ASME Boiler and Pressure Vessel Code,1986 Edition. The guidelines within NUREG -1482 Sections 5.1.2,5.3,5.7, and 5.8 have also been adopted within this Pump Test Program. Where the above requirements are determined to be impractical, specific requests for relief have been written and included in Section 7.0.
- 8. l .1.1 Rev.9 Page 10 of 236
5.1 GENERAL INFORMATION (Continued)
[2] Pumo Procram Table Descnotion The table in Section 5.4 lists all pumps included in the Pilgrim Nuclear Power Station IST Program. This program defines pumps as mechanical devices used to move liquid, and addresses centrifugal and positive displacement pumps according to IWP-1100.
Non-Code class pumps that are tested within the IST Program are also listed. The data contained in the table identifies all pumps subject to inservice testing, the inservice test quantities, the inservice testing interval, and any applicable remarks The column headings of the table are listed and explained below:
(a) SYSTEM' System Title
, (b) PUMP #: Pump Identification Number (c) ISI CLASS: ISI Classification (Class 1,2,3, or NC)
(d) P&lD: PNPS drawing number (e) COORD: Coordinate location on the P&lD (f) SPEED DISCHARGE PRESS DIFF PRESS FLOW RATE VIBRATION:
- inservice Test Quantities to be measured in accordance with Table IWP 3100-1 and/or NUREG 1482 Section 5.1.2 as applicable (g) TEST FREQUENCY
- The frequency of inservice Tests es prescribed in IWP-3400
[3] "Insemice Test Ouantities" Columns PUMP SPEED (N). DISCHARGE PRESSURE (Pd) DIFFERENTIAL PRESSURE (DP).
FLOW RATE (Ot VIBRATION (V): When the symbol"Y" appears in a particular measured parameter column, that quantity will be measured during inservice testing in accordance with Subsection lWP and/or NUREG 1482 Section 5.1.2. Requests for relief are identified with the letters "RP" under the measured parameter column in the test table. The requests for relief are included in Section 7.1.
[4] Measurement of Inservice Test Quantities (a) Speed (N): In accordance with IWP-4400, shaft measurements are not applicable (NA) for pumps coupled to synchronous or induction type drivers. For variable speed pumps, the pump speed shall be set at the reference speed in accordance with IWP-3100.
(b) Discharoe Pressure (Pd): For positive displacement pumps, discharge pressure will be measured in lieu of differential pressure (all other pumps will have discharge pressure measured if it is needed to determine differential pressure).
- 8. l.1.1 Rev. 9 Page 11 of 236
4 5.1 GENERAL INFORMATION (Continued)
(c) Differential Pressure (DP) Differential pressure measurements will be calculated from inlet and disenarge pressure measurements or by direct differential pressure measurement.
(d) Flow rate (O): Pump discharge flow rate shall be measured (e) Vibration (V): Pump vibration will be measured as close as possible to the inboard bearing in a plane approximately perpendicular to the rotating shaft, in a horit.ontal or vertical direction that has the largest deflection for that particular pump. At least one displacement measurement will be taken with one of the instruments referenced in IWP-4520 with exception if a reading is not applicable for a pump. Velocity measurements will also be taken at the IST vibration points l for administrative monitoring.
(5) Allowable Ranoes of Test Ouantities The allowable ranges specified in table IWP-3100-2 will be used for vibration measurements The allowable ranges specified within NUREG 1482 Section 53 will be
- used for discharge pressure, differential pressure. and flow measurements.
[6] Correctis a Action The cperational readiness of a pump shall be determined by comparing Surveillance Procedure test results to the established Acceptable, Alert, and Required Action ranges. Analysis of pump Surveillance Procedure test data shall be completed within four work days (Relief Request RP-8).
(a) If deviation' fall within the Alert range, the frequency of testing shall be doubled until the cause of the deviation is determined and the condition corrected, or an evaluation is performed and new reference values are established.
(b) If deviations fall within the Required Action range, the pump shall immediately be declared inoperative and not returned to service until the cause of the deviation has been determined and the condition corrected, or an evaluation is performed and new reference values are establishea.
(c) Corrective action shall be either replacement, repair, or an analysis to demonstrate that the condition does not impair pump operability and that the pump will still fulfill its function. When an r,alysis is considered necessary, a new set of reference values shall be established after analysis completion.
[7] instrument Accuraev Allowable instrument accuracies are given in table IWP-4110-1. If the accuracies of plant installed instrumentation are not acceptable, temporary M&TE instruments meeting the acceptable accuracies will be used.
- 8. l .1.1 Rev.9 Page 12 of 236
5.1 GENERAL INFORMATION (Continued)
(8) Eremot Safety Related Pumps The Reactor Recirculation Pumps and the Recirculation Jet Pumps are exempt from inservice testing. These pumps do not meet the scope of IWP-1100 in that they are not required to perform a specific function in shutting down the Reactor or mitigating the consequences of an accident, nor are they provided with an emergency power source.
[9] Non-Class (NC) Pumos The Diesel Oil Transfer (DOT) Pumps are tho only Non Class pumps supplied by emergency power which perform a specific function in shutting down the Reactor and mitigating the consequences of an accident. Their Non-Class designation excludes them from the scope requirements of IWP 1100. The DOT Pumps maintain a sufficient operating level in the fuel oil day tank by transferring fuel oil from the fuel oil storage tank to the fuel oil day tank. These pumps are tested in accordance with ASME Boiler and Pressure Vessel Code,Section IV, Subsection IWP requirements and NUREG 1482 Sections 5.1.2 and 5.8 guidelines with the following exceptions:
I (a) IWP-4120, Range - pump testing conforms with the basis of relief and alternate testing for vibration instrument full scale range as specified in Relief Request R P-9.
(b) IWP-4600, Flow Measurement (accuracy) - The basis for exception is that: No installed flow instrumentation exists for either DOT Pump and a portable flow meter is used to obtain flow. The flow meter can only be assigned an accuracy of 15% because of meter calibration, piping configuration, and fluid conditions being monitored. Other methods for measuring flow were rev;ewed, and no other applications were found (without requiring a design modification) which would achieve better accuracy with a high confidence level. Test data obtained by using the calibrated external portable flow meter has demonstrated consistent data with good repeatability. Therefore degradation of the pump hydraulic parameters is easily identifiable from trended data.
An Engineering Evaluation (Reference ERM 90-603, dated 1/14/91) of the DOT Pump design and key failure mechanisms was conducted to determine alert and required action hydraulic criteria. Flow instrument accuracy was considered as part of this review.
[10) Test Frecuency (a) Quarterly - pump testing within a 92 day interval with an allowable extension of no more than 25% using either the Code Test Method or Shutoff Head Test Method, as applicable.
- 8. l .1.1 Rev. 9 Page 13 of 236
5,1 GENERAL INFORMATION (Continued)
(b) Cold Shutdown - pump testing using the Code Test Method which should begin as soon as practicable (within 49 hours5.671296e-4 days <br />0.0136 hours <br />8.101852e-5 weeks <br />1.86445e-5 months <br /> after obtaining Cold Shutdown conditions) during Cold Shutdown and continue until all pumps are tested or the plant is ready to start up, if not previously tested quarterly using the Code Test Method For extended Cold Shutdowns when all pumps will be tested, the 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> limit does not apply.
(c) Refueling Interval - pumps must be tested using the Code Test Method within a two year interval with an allowable extension of no more than 25%.
5.2 PUMP POSTMAINTENANCE TESTING During the inservice life of a pump, work may be required to restore nr maintain the pump 4
performance to within the acceptable ranges. The IST Program requires each pump to be terified as operationally ready after routine servicing. maintenance, repair, or replacement.
The venfication of operational readiness should be achieved by acceptable performance of a
, Surveillance Procedure used to venfy test parameters which ,nay have been affected. The test parameters may be verified by other documented Procedures as long as all test J conditions or parameters are complied with, in accordance with Subsection IWP.
Pump postmaintenance testing guidance is provided using a Step-By-S'ep Determination l
l Retest Flow Path and a Work Scope Guideline. For specialized cases, at the discretion of the ASME Test Engineer, an evaluation may be performed to review a specific maintenance task cgainst the required Code testing. The postmaintenance guidelines may be dev ated from if:
l
- 1) the ASME Boiler and Pressure Vessel Code,Section XI requirements are adnered to arid
- 2) the evaluation is documented on a Pump Record of Corrective Action / Evaluation form (Ref.
PNPS 8.l.1).
Pump Postmaintenance Test Requirement examples are also provided within this section.
The Code Testing (CT) ASME Test Engineer may be consulted for questions or further clarification.
r 8l1.1 Rev 9 Page 14 of 236 i
5.2 PUMP POSTMAINTENANCE TESTING (Continued)
[1) Step-By Step Determination Retest Flow Path STEP 1 Verify whether Pump listed No No IS f Retest for in this Procedure's Pump - --
= Operational T..able (Section. 5 4)
Re_a d_ine. s_ s Yes_
v STEP 2 Work to be performed is identified within - - N o -- _
WS guidelins Ye,s_
t Locate Procedure No. in Pump STEP 3 Table (Section 5.4) of this l Procedure (or other equivalent l documentation) and identify for i retest consideration on Maintenance Request.
STEP 1:
Using this Procedure's Section 5.4, locate the pump and verify whether any test requirements are applicable.
- STEP 2: Verify whether the work to be performed is identified within Work Scope Guidelines listed on next page-STEP 3: .A_Il work identified as "REPA!R", " REPLACEMENT", or " MAINTENANCE" within the work scope guideline requires an IST pump retest Identify the applicable PNPS Procedure No. on the Maintenance Request for retest.
All work identified as " ROUTINE SERVICING" within the work scope guideline requires an IST pump retest QR equivalent documentation.
Identify either the applicable PNPS Procedure number for retest QR equivalent documentation that will verify the test parameter reference value was not affected (such as changing of oil, documented level as visible) on tiie Maintenance Request.
All work identified as "NON PUMP MAINTENANCE / REPLACEMENT" w7 thin the work scope guideline does not require an IST pump retest.
However, the pump's ability to start and run must be verified (i.e., pump is started using control switch and does not exhibit any abnormalities locally).
Other motor performance indicators may also be checked (as a matter of
" good practice") at this time (such as motor amps in normal range) as directed by the Maintenance Request.
81.1.1 Rev.9 Page 15 of 236 1
~ ,
i 5.2 PUMP POSTMAINTENANCE TESTING (Ccntinued) 1 (2]' Work Scooe (WS) Guideline (a) ROUTINE SERVICING - Performance of preventive maintenanco which does not require disassembly of the pump or replacement of parts; such as changing oil, flushing the cooling system, adjusting packing. adding packing rings, or mechanical seal maintenance EXCEPTIONS 1) When routine servicing is periormed on a running pump, venfication that monitored parameters do not change may be substituted in place of the PNPS Procedure as documented on the Maintenance Request. a) adjustment of packing pump observed to continue to run normally (i e., no smoke, packing squealing, etc.) following l -. packing adjustment. 2) When a parameter is venfied within the maintenance instruction during or prior to operation (i.e., verify acceptable oil level), no retest is required.
(b) MAINTENANCE - Performance of preventive or corrective maintenance which ;
requires decoupling the pump from its motor, disassembly of the pump or replacement of consumable items, Motor maintenance is excluded (except for pump motor bearings, which can impact vibration) as a maintenance work scope.
(c) REPAIR - Performance of welding or grinding on a pump to correct a C9fect
(. (does not include pump motor).
(d) REPLACEMENT - Installation of a new pump, pump part, or a modification to the pump (includes replacement of pump motor, which can impact vibration).
(e) NON PUMP MAINTENANCE / REPLACEMENTS - Work that is not performed on the pump but has the potential to impact the pump's ability to start and run. This
- work is considered non IST because it does not have the potential to affect the pump's reference values. This work scope includes, but is not limited to: work performed to the pump motor not listed above, PMs or replacement of ciectrical breakers, and resplicing electrical connections.
- 8. l.1.1 Rev. 9 Page 16 of 236 a
5.2 PUMP POSTMAINTENANCE TESTING (Continued)
. EXAMPLES:
i
- 1. Reactor Puilding Closed Cc-ling Water Pump B (P 2028) requires impeller replacement due to excessive wear according to Maintenance Request.
RBCCW Pump P-2028 No retest STEP 1 No required 'or is listed on Page 26. _
lcperability.
t .
~ e s'_
t Work scope to be performed is identified No STEP 2 within Guidelines -
Replacement, NOTES: 1; Replacement of the pump impeller requires both new hydraulic and ps- mechanical parameters to b established for both shutoff oead and fu'l flow testing. The retest performance i parameters shall be evaluated and
- 1) PNPS 8.5.3.1: Perform , accepted as new reference values.
app licable steps of if plant conditions do not allow conduct STEP 3 Section 7.0, Prerequisites, of FNPS 8.l.11.19, then the reference and Section 8.0, Procedure.' values must be established during the earliest opportunity (Plant Cold
- 2) If plant ccnditions ex;st in Shutdown).
I which the limitations and
- precautions of 2) If the olant is in the Cold Snutdown PNPS 8.l.11.19 can be met, conditiori when maintenance is then all applicable sections completed, then PNPS 8.l.11.19 must be of this Procedure ELug also performed for operability prior to startup, be performed as part of postmaintenance testing.
8.l1.1 Rev. 9 Page 17 of 236 l .
5.2 PUMP POSTMAINTENANCE TESTING (Continued)
- 2. Residual Heat Removal Pump A (P-203A) requires the lubricant reservoir to be filled because level indication is just visible according to Maintenance Request.
lRHR Pump P-203A is STEP 1 [No retest rec;uired l listed on Page 26 No for operability _
4
, Xes_
1 1 Work scope is ider'ified STEP 2 within Guidelines - No Routine Servicing.
Xps 7- NOTE: For pumps, a Maintenance Request
)
t should be used to document PNPS No.: not iequired - " Routine Servicing" retests unless STEP 3 Maintenance hequest the pump is required to be run at its
{ 9ackage utilized to IST reference values prior to document venfication of measunng the affected parameter.
proper oil level,
- 3. Core Spray Pump A (P-215A) requires the pump mechanical seal replacement according to Maintenance Request.
CS Pump P-215A is No retest required STEP 1 N +
listed on Page 26. for operability.
Xep-t t Work scope is identified l STEP 2 within Guidelines - No Maintenance Yes TT NOTE: Maintenance of the pump k mechanical seal PNPS 8.5.1.1: Perform STEP 3 applicable steps of (replacement of parts) i Section 7.0, Prerequisites, requires reconfirming I previous reference values.
and Section 8.0, Procedure.
81.1.1 Rev 9 Page 18 of 236
{
S.2 PUMP POSTMAINTENANCE TESTING (Continued)
- 4. Salt Seivice Water Pump C (P-20BC) requires its electrical breaker to be replaced due to PM program.
STEP 1 SSW Pump P-208C is No retest required' N
lhsted on Page 26. ~* for operability.
Yes I
t Work scope is identified STEP 2 within Guidelir.as - No Non Pump Maintenance /
NOTE: 1) Breaker replacement does not Replacement.
quahfy as a " Replacement" ,
because the breaker is not E considered to be part of the pump.
}
No PNPS Procedde identified.
This work has no potential to ffect pump reference values and Retest check requires the pump does not require retest in to be started using control switch ccordance with ASME code.
and to observe no abnormal l conditions locally. As directed 2) However, th.is work has potential by the Maintenance Request, to impact the pump's abilny to other indicators may also be start and run and so it is classified checked at this time, s "Non-Pump Maintenance /
Replacement"
- 8. l .1.1 Rev. 9 Page 19 of 236 !
l 1
l l 5.3 HYDRAULIC CIRCUITS l
l The following IST hydraulic circuits are used to identify pump test paths and instrumentation.
Individual hydraulic and mechanical reference value test quantities are identified within each pump testing procedure.
M&TE instrumentation may be used in place of installed plant instruments provided that IV'P-4000, Methods of Measurement, requirements are satisfied The effects of flow losses ano elevation differences due to instrument location must be considered.
5.3.1 Salt Service Water (SSW) Pumps
[1] Test Frequency SSW pumps are scheduled for testing: Quarterly using the Code Test Method.
Following maintenance during summer months (July 15th through September 15th), the Shutoff Head Test Method may need to be utilized to verify operability if the Code Test Method cannot be performed due to plant heat load requirements. The method to perform postmaintenance testing utilizing the shutoff head test method is subject to NRC review and approval.
[2] Hydraulic Test Path (a) Shutoff Head Test Method - SSW pumps are shutoff (dead) head tested (Retracted RP-5) by verifying operation at nameplate speed with the associated discharge valve closed. When plant heat loads do not allow a Full Flow Code Test, this method provides an option (subject to NRC review and approval) to '
verify pump operability to perform pump postmaintenance testing.
(b) Code Test Method - Each pump shall be tested by splitting the SSW loops and
[
' establishing single pump operation in the loop utilized for testing. Then, using the RBCCW and/or TBCCW Heat Exchanger Outlet Valves for throttling, establish a flow rate in accordance with current Technical Specifications requirements. Pump discharge pressure shall be recorded, and using suction bay level (RP-4), ihe pump differential pressure (Total Dynamic Head) will be calculated and compared to the established reference values.
[3] Instrumentation (a) Inlet Pressure, Pi(ft): LI-3831 A, LI-38318, or Li-38010, LI-38011 (actual '
measurement from Screenhouse ladder as backup).
j (b) Discharae Pressure (psig): PI-3802, PI-3807, PI-3812, PI-3817, PI-3822, or M&TE gauges at the same location.
(c) Flow rate, O (GPM): F1-6240, F1-6241 (Cold Shutdown testing only), or FE-38002A/ fly-38003A, FE-38002B/ fly-38003B, 8.l.1.1 Rev.9 Page 20 of 236
5.3.2 Reactor Building Closed Cooling Water (RBCCW) Pumps
[1] Test Frequency RBCCW pumps are scheduled for testing quarter!y using the Shutoff Head Test Method. Cold Shutdown using the Code Test Method, and refueling interval using the Code Test Method.
(2) Hydraulic Test Path (a) Shutoff Head Test Method - RBCCW pumps shall be shutoff (dead) head tested (RP-1) by verifying operation at nameplate speed with the associated discharge valve closed.
t (b) Code Test Method - Each pump shall be tested by establishing single pump operation in the loop utilized for testing. Then, using the associated RBCCW l
' Loop RHR Heat Exchanger inlet Valve for throttling, establish a flow rate in accordance with current Technical Specifications requirements. Pump discharge and suction pressures shall be recorded. The differential pressure (Total Dynamic Head) will be calculated and compared to the established value.
[3] Instrumentation (a) Inlet Pressare (psig): PI-4056A, PI-4054A, PI-4057A, PI-4006A, PI-4004A, PI-4007A, or M&TE gauges at the same location.
(b) Discharae Pressure (psig): Pl-4056, PI-4054, PI-4057, PI-4006, PI-4004, PI-4007, or M&TE gauges at the same location.
(c) Flow rate. Q (GPM): FT-6265, FT-6263.
t b
8.1.1.1 Rev. 9 Page 21 of 236
r 5.3.3 Di:s;l O!! Trcnsf;r (DOT) Pumps I
(1) --Test Freqancy DOT pumps are tested on a quarterly frequency.-
[2] Hydraulic Test Path -
Each pump shall be tested by establishing a flow path from the storage tank to the day tank. Then, using the pump discharge isolation valve, throttle to a calculated differential pressure. An external clamp on flow meter (with en approximate accuracy of 5%) will measure the flow rate to assess the pump's operational readiness.
[3] instrumentation (a) inlet Pressure (psig): M&TE test gauges at PI-45002, PI-45003.
(b) Discharoe Pressure (psig): PI-4510, PI-4511.
(c) Flow rate, O (GPM): Portable test equipment installed at midpoint of straight piping.
-5.3.4 Residual Heat Removal (RHR) Pumps
[1] Test Frequency RHR pumps are tested on a quarterly frequency.
[2] Hydraulic Test Path Each pump shall be tested by establishing a flow path with suction from and discharge returning to the Torus (Heat Exchanger Bypass Valve open). Then, using the Loop To Suppression Chamber Spray Cooling Valve for throttling, estabiisn a flow rate in accordance with current Technical Specifications requirements. Pump discharge and suction pressure shall be recorded. The differential pressure will be calcul- d and compared to the established value.
[3] Instrumentation (a) Inlet Pressure (psig): M&TE test gauges at PI-1001-70A, PI-1001-70B, PI-1001-70C, PI-1001-70D.
_(b) Discharoe Pressure (psig): M&TE test gauges at PI-1001-71 A, PI-1001-718, PI-1001-71C, PI-1001-71D.
-(c) Flow rate. Q (GPM): F1-1040-11 A (Loop A), F1-1040-11B (Loop B).
8l.1.1 Rev. 9 Page 22 of 236
5.3.5 Core Spray (CS) Pumps -
[1] Test Frequency CS pumps are tested on a quarterly frequency.
[2] Hydraulic Test Path Each pump shall be tested by establishing a flow path with suction from and discharge returning to the Torus. Then, using the CS Full Flow Test Valve for throttling, establish a flow rate in acccrdance with current Technical Specifications requirements. Pump discharge and suction pressures shall be recorded and the differential pressure will be calculated and compared to the established value.
l
[3] Instrumentation l (a) . Inlet Pressure (osig): M&TE test gauges at PI-40A, PI-408.
(b) Discharoe Pressure (psig): M&TE test gauges at PT-1460A, PT-14608.
(c) Flow rate, O (GPM): Fi-1450-4A, F1-1450-48.
L 5.3.6 - High Pressure Coolant injection (HPCI) Pumps
[1] Test Frequency HPCI pumps (main and booster) are tested on a quarterly frequency when adequate steam pressure is available.
[2] Hydraulic Test Path These pumps (main and booster) shall be tested by establishing a flow path with
. suction from and discharge returning to the CST. Then, using the HPCI Full Flow Test Valve for throttling, establish the speed and flow rate in accordance with current Technical Specifications requirements. Pump discharge and suction pressure shall be recorded The differential pressure will be calculated and compared to the established value.
[3] Instrumentation (a) Inlet Pressure (psig): PI-2340-7 (Booster), M&TE test gauge at PX-2301-80 (Main).
(b) Discharae Pressure (psig): M&TE test gauge at PX-2301-80 (Booster),
PI-2340-2 (Main).
(c) Flow rate, O (GPM): F 1-2340-1. s (d) Speed, N (RPM): SI-2340-1.
81.1.1 Rev. 9 Page 23 of 236
5.3.7 Reactor Core Isolation Cooling (RCIC) Pump
[1] Test Frequency RCIC pump is tested on a quarterly frequency when adequate steam pressure is available.
[2] Hydraulic Test Path The pump shall be tested by establishing a flow path from and returning to the CST.
Then, using the test valve for throtthng, establish the speed and flow rate in accordance with current Technical Specifications requirements. Pumn discharge and suction pressures shall be recorded. The differential pressure will be calculated and cornpared i
to the established value.
[3]- Instrumentation (a) Irelet Pressure (psig): PI-1340-2.
_(b) Discharae Pressure (psig): PI-1340-7.
(c) Flow rate, Q (GPM): F1-1340-1.
(d) Speed. N (RPM): SI-1340-1.
5.3.8 Standby Liquid Control (SLC) Pumps
[1] Test Frequency SLC pumps are tested on a quarterly frequency.
[2] Hydraulic Test Path (a) Test Tank Method - Each pump shall be tested by establishing a suction flow path from the main SLC Sterage Tank and discharge returning to the SLC Test Tank. Then, using the test valve for throttling, establish a discharge pressure at a known reference value. Measure the time elapsed, initial and final test tank levels. Calculate the flov! rate by level change over time and compare to the established value.
(b) Ultrasonic Flow Method - Each pump shall be tested by establishing a suction flow path from the main SLC Storage Tank and discharge returning to the SLC Test Tank. Then, using the test valve for throttling, establish a discharge pressure at a known reference value. Pump flow rate shall be measured and recorded from an iristalled ultrasonic flow meter, then compared to the established reference value.
C
- 8. l.1.1 Rev. 9 Page 24 oi 236
5.3.8 Standly Liquid Control (SLC) Pumps (Continued)
[3] Instrumentation (a) Intet Pressure, Pi: Not applicable (b) Discharoe Pressure Pd (psig) P' 1159 or M&TE test gauge.
-(c) Flow rate. O (inches): Measuring stick (yardstick).
O (GPM): Ultrasonic flow meter 1162.
) 5.4 PUMP PROGRAM TABLE This table identifies the scope of pumps within the IST Program and allows cross-referencing '
specific pump test quantities to their implementing Station Procedure.
The test quantities measured include: Speed (N), Pressure - Discharge Pressure (Pd) or Differential Pressure (DP), Flow Rate (Q), and Vibration (V).
8.1.1.1 Rev.9 Page 25 of 236
~ . . . .
TABLE PUMPS TESTED - ISI CLASS 1. 2. 3. AND fJC PUMPS INSERVICE TEST OUAf4TITIES Ist PalD SPEED PRESS FLOW SYSTEM PUMP # CLASS PalD COORD TEST PROC FREO (fi) JDP of Pd) R AT E (O) VfB (V)
SALT SERVICE P-208A 3 M212 B7 85321 O FJA DP y RP-6 & 9 WATER ;SSW) P-2068 3 M212 B8 85321 O NA' DP y RP4 & 9 P-208C 3 M212 . 87 85321 O fJA DP Y RP4 & 9 P-208D 3 M212 B6 85321 O fJA DP Y RP-6 & 9 P-20BE 3 M212 B5 85321 O f!A DP' Y RP-6 & 9 REACTOR BUILDING P-202A 3 M215 F3- 8531+ 0 fJA DP RP-1 RP-9 CLOSED COOLif4G P-2028 3 M215 F3 8 5 31+ 0 fJA DP R P- 1_ RP.9 WATER (RBCCW) P-202C 3 M215 G3 8 5 31+ O NA DP RP- 1 RP-9 P-202C 3 M215 G5 8531* O fJA DF RP-1 RP-9 P-202E 3 M215 G5 8 5 31+ O NA DP N P.1 R P-9 P-202F 3 M215 F5 8 5 31+ 0 fJA DP R P- 1 RP-9 DIESEL OIL P-141 A fJ/C M223 F6 8911 O NA DP y- y-P-1418 NC M223 E6 8911 O fJA DP y* y*
TRANSFER (DOT)
RESIDUAL HEAT P-203A 2 M241(S2) D6 8 5 2.2 1 O fJA DP y RP-9 REMOVAL (RHR) P-203B 2 M241(S2) D3 85222 O fJA DP Y PP-9 P-203C 2 M241(S2) F6 8 5 2 2.1 O NA DP Y RP-g i P-203D 2 M241(S2) F3 85222 O NA DP 'Y RP-9 P-215A 2 M242 F7 8511 O NA DP y R P-9
'{
CORE SPRAY (CS)
P-215B 2 M242 F9 8511 O NA DP V RP-9 HIGH PRESSURE P-205 2 M244 F9 8541 O Y DP Y R P-9 COOLANT INJECTION MAIN (HPCI) P-205 2 M244 F8 8541 O Y DP Y RP-9 BOOSTFR ~
P-206 2 M246 F8 6551 O Y DP y R p_9 REACTOR CORE iSOL COOLING (RCiC) _. _
STANDBY LIQUID P-20 7 A . 2 M249 ES 831 O NA Pd" RP 3 RP-9 CONTROL (SLC) P-2070 2 M249 FS 841 O fJA Pd" 'P 3 R P-9
+ The RBCCW Pump Shutoff Head Test is performed usmg PtJPS 8 5 31 once per quarter The RBCCW Pump Code Test is pe< formed usmg PTJPS 8111 19 dunng Cold Shutdown and, as a minimum, each refuehng interval Postmamtenance testmg shall be satisfied usmg PNPS 8111 19 by performmg both test methods IF plant cond'hons exist m which comphance with the Procedure's Precautions and Lemstatrovis can be met If pump mamtenance is completed while the plant is m the Cold Shutdown condrtion, then PNPS 8 l 11 19 must be performed poor to plant startup Refer to Step 51[9] for clanfication
- The SLC Pumps are positive displacement type and only require Discharge Pressure (Pd) to be measured Refer to Secteen 5 3 8 for clarification 8 l.1.1 Rev. 9 Page 26 of 236 t . .. .. . . .. .. . . . ._ . - _ . .. . .. .
Gs0 INSERVICE VALVE TESTING 6.1 GENERAL INFORMATION
[1] Applicable Code This inservice Testing Program for ISI Class 1,2,3, and NC valves meets the requirements of Subsection itW of Section XI of the ASME Boiler and Pressure Vessel Code,1966 Edition. Where these requirements are determined to be impractical, specific justifications and requests for relief have been wntten and included as follows:
(a) RELIEF REQUEST - Relief Requests are included in Section 7.4 for impractical test requirements. They are identified as RV-XX and musi be reviewed by and receive NRC approval prior to use.
(b) COLD SHUTDOWN JUSTIFICATION - The reference to a Cold Shutdown Justification in Section 7.2 is for valve test frequency. Cold Shutdown Justifications are identified as CS-XX and comply with the rules of Subsection IWV.
(c) REFUELING OUTAGE JUSTIFICATION: The reference to a Refuel Outage Justification in Section 7.3 is for valve test frequency. The Refueling Outage Justification allows implementation of portions of ASME/ ANSI OM-10 as it pertains to refueling outage frequency testing pursuant to 10CFR50.55a(f)(4)(iv) without requesting formal relief. A Refuel Outage Justification is identified as RJO-XX and is similar in format and purpose to a Cold Shutdown Justification.
This justification provides the mechanism for documenting the bases for performing a specific test on a refueling interval (RI) frequency (usually during a refueling outage), as well as specifying the alternative requirements in accordance with the OM-10 standard.
(d) OPERATIONS AND MAINTENANCE (PART 10) JUSTlFICATION: The ASME/ ANSI Operations and Maintenance (Part 10l [OM-10 or OM(10)) l Justification allows the implementation of portions of ASME/ ANSI OM-10 pursuant to 10CFR50.55a(f)(4)(iv) without requesting formal relief. Portions of editions or addenda may be used provided that all related requirements of the respective editions or addenda are met; therefore, relief is not required for those inservice Tests that are conducted in accordence with OM-10, or portions thereof. Whether all related requirements are met is subject to NRC inspection.
An OM-10 Justification is identified as OM(10)-XX and is similar in format and purpose to a Refuel Outage Justification (except that it is not limited to test frequency requirements). This justification provides the mechan:sm for documenting the bases for performing specific IST valve requirements as well as specifying the alternative requirements in accordance with the OM-10 standard.
- 8. l.1.1 Rev.9 Page 27 of 236
6.1 GENERAL INFORMATION (Continued)
[2] inservice Valve Testina Procram Table The Tab'es contained in Section 6 3 list all ISI Class 1. 2. 3, and NC valves that are tested to meet IST tequirements-The tables are sorted by system and Piping & Instrumentation Diagram (P&lD) number (s) and contain the following information.
(a) VALVE NUMBER Valve identification number (b) P&lD COORQ Coordinate location and sheet number on the PalD.
(c) ISI CLASS: Inservice inspection classification (Class 1,2,3 or NC).
. (d) VALVE -T: Catego y assigned to the valve based on the definitions of
! IkW-2200. Catego;ies A through 0 are defined in the Code. Categories AC and NA are defined by PNPS (1) CATEGORY A - valves for which seat leakage is limited to a specific maxt:. Jm amount in the closed position for fulfillment of their function.
l (2) CATEGORY B valves for which a specific amount of leakage in the closed position is inconsequential for fulfillment of their function.
(3) CATEGORY C - valves which are self actuating in respo..se to some system characteristic, such as pressure (safety and relief valves including vacuum relief valve) or flow direction (check valves).
(4) CATEGORY D valves which are actuated by an energy source capable of only one operation such as rupture disks or explosive 6ctuated valves (5) CATEGORY AC - valves which exhibit both Category A and Category C characteristics.
(6) CATEGORY NA - valves which are not required by IWV to be tested.
(e) VALV7JIF;: Nominal pipe size (in inches)-
(f) VALVE TYPl: Valve Body Design; ANGLE AN PLUG PG BALL BL RELIEF RL BUTTERFLY BF RUPTURE DISC RD CHECK. CK SAFETY SV GATE GA SHEAR SH GLOBE GL STOP CHECK SC NEEDLE ND SPRING CHECK SK 8.l1 1 Rev. 9 Page 28 of 236 i - _ _ _ _ _ -
r 6.1 GENERAL INFORMATION (Continued)
{
(g) ACTUATOR TYPE: Valve Actuator Power; MOTOR OPERATOR MO EXPLOSIVE ACTUATOR EX !
AIR OPERATOR AO MANUAL MA i SOLENOID OPERATOR SO SELF ACTUATED SA HYDRAULIC OPERATOR HO !
(h) blORMAL POSITION: Normal Position During Plant Operation; NORMAL OPEN O LOCKED OPEN LO I NORMAL CLOSED C LOCKED CLOSED LC l (i) TEST REQUIREMENT:- Test (s) that will be performed to fulfill the requirements ,
of Subsection IWV. The test definitions and abbreviations used are identified in t Table 1, inservice Valve Tests.
l (j) TEST FREQUENCY: Frequency at which t_he tests will be performed. The frequency definitions and abbreviations used are identified in Table 2 Test Frequency. ;
(k) PNPS PROCEDURE NO.: The PNPS Surveillance Procedure that satisfies -
each specific test requirement.
(1) TEST DIRECTION: . Direction the valve is exercised to during stroke time measurements or a check valve exercise. The direction for stroke time measurements is that which is required to fulfill its safety-related function according to the Updated FSAR and/or Technical Specifications. The direction '
for check valve exercising is to the position required to fulfill their function.
O - Open C Closed i FF Forward Flow, Normally Closed Valves RF - Reverse Flow, Normally Open Valves (m). RELIEFiJUSTIFICATION: Refer to Section 7.2 for Cold Shutdown Justifications.
These justifications are identified as CS-XX. Refer to Section 7.3 for Refuel Outage Justifications. Thesejustifications are identified as RJO XX. Refer to
. Section 7,4 for Operatiens and Maintenance (Part 10) Justifications. These justifications are identified as OM(10)-XX. Refer to Section 7.5 for Relief Requests. Relief Requests are identified as RV XX.
i
- 8. l.1.1 Rev. 9 Page 29 of 236
6.1 GENERAL INFORMATION (Continued)
(n) NOTES Clarification to the particular column to identify any of the following information:
(1) Special or unique classification (i e Exempt Passive)
(2) Specific information related to that test requirement (3) Alternate test procedure (s)
[3] Exempt Valves Valves exempt accoroing to IWV 1200 and passive valves that do not have a specific maximum leakage requirement are not included in the IST Program Passive valve is a valve that does not perform a mechanical motion dunng the course of accomplishing a system safety function Subarticle IWV 1200," Valves Exempt From Testing", includes:
(a) Valves used only for operating convenien'ce system control, and maintenance.
(b) External control and protection systems responsible for sensing plant conditions and providing signals for valve operation Control valves whose actuators are required to provide a fail safe position have been included in the program in accordance with Generie Letter 89-04 and are fail safe tested only.
Exempt valves with remote position indicators have been included so their position indicators will be checked with the exempt status noted Darnpers are considered exempt (i.e., HVAC System).
[4] hieasurement of Test Quantities (a) STROKE TIME: The preferred stroke time method is the time interval from initiation of the actuating signal to the end of the actuating cycle Alternate stroke timing methods may be utilized and are discussed within PNPS 8.l.1,
" Administration of Inservice Pump and Valve Testing", Step 7.2.10\4) Stroke time value(s) for each power operated valve is specified within the appropriate test procedure.
(b) POSITION INDICATION. Valve disk movement is determined by exercising the valve while observing apcropriate indicators which signal the required change of disk position. Observation of actual valve movement or indirect evidence (such
< as changes in system pressure, flow rate, level, or temperature) which reflect stem or disk position will be used to vei.fy that remote position indicators agree with valve travel direction.
8.l 1 1 Rev. 9 Page 30 of 236
6.1 GENERAL INFORMATION (Continued)
(c) SEAT LEAKAGE: Seat leakage is measured by one of the following methods:
(1) Draining the line. closing the valve. bringing one side to test pressure, and measunng leakage through a downstream telltale connection.
(2) By measuring the feed rate required to maintain pressure between two valves or between two seats of a gate valve provided the total apparent leak rate is charged to the valve or gate valve seat being tested and that the Conditions required by l\W 3423 are satisfied.
(3) By performance of a Pressure Drop (Decay) Test to verify that an entire pressure boundary does not exceed its specified leakage criteria (Reference RV 30).
Exception: Containment isolation valves are seat leak tested in accordance with ASME/ ANSI OM-10. Refer to valve justification OM(10)-01 for basis.
(d) CHECK VALVE EXERCISE: Check valve exercises will be confirmed by observing a direct indicator such as a position indicating device or by observing system changes such as flow rate, system pressure. level, temperature, or other
, positive means.
The following test practices will be utilized:
(1) Full Flow Check Exercise - will be venfied by observation of substantially free flow through the valve. When a required accident condition flow rate exists, it will be verified. If the accident flow rate cannot be confirmed, the valve may be exercised mechanically or placed in the disassembly program (Reference RV-27).
(2) Mechanical Exercisar - the force or torque delivered to the disk by the exerciser must be limited to less than 10% of the equivalent force or torque represented by the minimum emergency condition pressure differential acting on the disk or to 200% of the actual observed force or torque required to perform the exercise on the valve when the valve is new and in good operating condition, whichever is less.
f Vacuum Breaker - for check valves that perform as vacuum breakers. the (3) exerciser force or terque delivered to the disk may be equivalent to the desired functional pressure differential force. Also, the disk movement shall be sufficient to prove that the disk moves freely off the seat. If no functional pressure differential force is specified, only disk movement is required.
(e) CHECK val.VE DISASSEMBl..Y: For certain normally closed check valves, system configuration or limitations inhibits 1) full opening (FC) during flow testing and 2) in some cases also the closed normal position verification (AP).
For valves with these design limitations, the check valve testing hierarchy and disassembly guidance outlined in NRC Generic Letter 89-04 and published
" Minutes of the Public Meetings on Generic Letter 89-04" will be followed. This deviation from the Code (which is approved by the above documents) has been identified within Relief Request RV 27.
81.1.1 Rev.9
{ Page 31 of 236
6.1 GENERAL INFORMATION (Continued)
The check valve disassembly program will be controlled in accordarice with PNPS 8.l.27. These valves with their disassembly groupings are listed by system below:
SYSTEM GROUPff VALVE NUMBERS Residual Heat Removal 1 2B,2D (1001) l Reactor Core 1 24
! Isolation Cooling 2 27 (1301) 3 40.59 l 4 63 Core Spray (1400) 1 13 A.138 High Pressure Coolant 1 39 injection (2301) 2 34.217 i
(f) NO_NlNTRUSIVE TESTING OF CHECK VALVES Nonintrusive test (NIT) methods may be utilized to verify a check valve exercise in the open and/or closed position. If NIT can be employed in lieu of check valve disassembly, then the check valves that receive NIT will not require disassembly. However, if the NIT results are inconclusive for verifying the check valve exercise, then the affected valve must be disassembled using the guidelines within PNPS 8.l.27,
" Inservice Check Valve Disassembly and Exercise Progrem".
For check valves that are periodically verified through NIT techniques as being ,
exercised, a sample plan may be employed. When using NIT techniques in a sample plan, the guidelines within NUREG 1482 Section 4.1.2 must be adhered to. NIT sample testing will be controlled in accordance with PNPS 8.l.37,
" Inservice Check Valve Nonintrusive Testing for Exercise Program"
[5] Allowable Ranoes of Test Quantities (a) STROKE TIME:
(1) For power operated valves, an increase in stroke time of 25% or more from the previous test for valves with stroke times greater than 10 seconds or 50% or more for valves with stroke times less than or equal to 10 seconds is observed, test frequency shall be increased to once each month until corrective action is taken. Valves with stroke times lets than or equal to 2 seconds (Relief Request RV-4) may be classified as fast acting with increased frequency testing not being applicable.
- 8. l.1.1 Rev. 9 Page 32 of 236 1
I G.1 GENERAL INFORMATION (Continued)
(2) In addition to the above requirements limiting stroke values will be implemented based on a valve's reference time (R) which is established from actual field test results Each valve's Required Action stroke time value shall be established as tabulated below and will not exceed either Technical Specifications or Updated FSAR requirements:
Motor Operatored Valtg Formulas Calculated Reference Erratic Values Required Action Value Value (seconds) (seconds) (seconds)
Low (0 8 X R) 5 < R to 515 sec. High (1.2 X R) (1.4 X R)
Round to nearest 1/2 see Round to nearest 1/2 see Low (0.90 X R) 15 < R to L 50 sec. High (1.10 X R) (1.2 X R)
Round to nearest i see Round to nearest 1 see Low (0 95 X R)
R > 50 sec. High (1.05 X R) (1.1 X R)
Round to nearest i sec Round to nearest i sec i
Air. Hydraulic. or Solenoid Operated Valve Formulas 1
Calculated Reference Erratic Values Required Action Value Value (seconds) (seconds) (seconds)
Low (0 5 X R) 1 s R to E 5 sec. High (1.5 X R) (2.0 X R) + (0.5)
Round to nearest 1/10 see Round to nearest 1/10 sec Low (0.5 X R) 5 < R to 510 sec. High (1.5 X R) (2,0 X R)
Round to nearest 1/2 sec Round to nearest 1/2 see Low (0.75 X R)
R > 10 sec. High (1.25 X R) (1.5 X R)
Round to nearest 1 see Round to nearest i see A valve that exceeds its specified limiting stroke time (Required Action Value) shall be declared inoperable immediately and appropriate corrective action taken.
Valves that deviate from their reference stroke time by more than the established Erratic Low or Erratic High Value will be reviewed and monitored for future stroke time deviations.
8_ l.1.1 Rev. 9 Page 33 of 236
6.1 GENERAL INFORMATION (Continued)
(b) F OSITION INDIC ATION During valve opening and closure, the remote position indicators shall accurately reflect valve travel direction (c) SE AT LE AKAGE-(1) Valve leakage rates shall not exceed the value established by Boston Edison Company These leakage values are specified within the implementing test procedures Valves that fall to meet the acceptance criteria shall be declared inoperable immediately and require corrective action.
l (2) For valves 6 inches nominal pipe size and larger (nct to include containment isolation valves), the leakage rate shall not exceed that established by the previous test by an amount that reduces the margin between measured leakage rate and the maximum permissible rate by 50% or greater The test frequency shall be doubled The tests shall be scheduled to coincide with a Cold Shutdown until corrective action is taken If tests show a leakage rate increasing with time and a projection based on three or more tests indicatLs that the leakage rate of the next scheduled test will exceed the maximum permissible leakage rate by greater than 10%, then corrective action will be taken,
[6] Instrument Accuracy instruments used to measure stroke times shall be capable of measurement to the nearest tenth of a second
[7] Corrective Action (a) STROKE TIME Corrective action shall be to repair, replace, or evaluate the operability requirements for the specific valve. When an analysis shows that the condition does not impair valve operability, then a new reference stroke time shall be established.
A completed Attachment 4 of PNPS 8 l 32. combined with either a Corrective Action /E.aluation Form (Attachment 1 of PNPS 8.l.1) or an NWE Surveillance Review Sheet (reference PNPS 13 34 Attachment 9) with ASME Test Engineer signature, satisfies the Corrective Action evaluation requirements for valve operability. If necessary, a valve may be declared operable using the NWE Surveillance Test Review process prior to revision of the affected stroke timing procedure. A revision to the Surveillance Procedure should then be implemented on a priority basis for future operability testing 8111 Rev 9 I Page 34 of 236 l
6.1 GENERAL INFORMATION (Continued)
(b) SEAT LEAKAGE: Corrective action shall be to repair or replace the valve unless an Engineering analysis is performed which demonstrates that the leakage enteria may be increased and the new leakage rate will not impact the valve's ability to fulfillits safety function. The option to evaluate and increase a leakage entena should not be used for Reactor System Pressure isolation Valves (PlVs) without performance of a Safety Evaluation which includes consideration of applicable code requirements.
(c) REllEF VALVES 1
I (1) Relief valves which fall to function properly during testing shall be:
- 1) adjusted,2) repaired, or 3) replaced and retested to show acceptable operation, Procedure credit may be taken for valves that are tested by the vendor / manufacturer provided that similar test methods are used and the documentation venfies that the Surveillance Procedure acceptance enteria have been met.
- (2) For relief valves which fail to meet the set pressure acceptance cateria, the following requirements shall be adhered to
- a. Class i Safety and Relief Valves Any safety / relief valve which exceeds the stamped set presrure by greater than 11%
shall be evaluated for causal effect. Any safety / relief valve 4
which exceeds the stamped set pressure by greater than 13%, the causal effect shall be evaluated for determination of need for additional tests. Any Class I safety / relief valve that exceeds the stamped set pressure by greater than 11% shall be reset, repaired, or replaced and retested before it is returned to service.
- b. Class 2 and 3 Relief Valves: Any valve which exceeds the stamped set pressure by greater than 13%, the causal effect
- shall be evaluated for determination of the need for additional tests. Any relief valve that exceeds the stamped set pressure by greater than 13% shall also be repaired or replaced and retested before it is returned to service.
- 8. l.1.1 Rev. 9 Page 35 of 236
l l
TABLE 1 INSERVICE VALVE TESTS l TEST TEST NAME TE ST DESCRIPTION / DEFINITION LJ Containment Containment isolation Valves (CIVs) will be seat isolation Valves (Air) leak tested using air in accordance with ASME/ ANSI OM 10 paragraphs 4 2.2 2. 4 2 2 3(e), and 4 2.2.3(f). Refer to Valve Justification OM(10)-01 for basis.
LJW Containment Containment isolation Valves (CIVs) will be seat leak Isolation Valves tested with water at a pressure not less than 1.1 Pa and are (Water) not required to be added into the Type C leak test total.
4 These isolation valves are tested to assure the seal water fluid inventory is sufficient to assure the sealing function for at least 30 days. Testing will be conducted in accordance with ASME/ ANSI OM-10 parqagraphs 4.2.2.2, 4.2.2.3(e),
and 4.2.2.3(f). Refer to Valve Justification OM(10) 01 for basis.
i LP Pressure isolation Pressure Isolation Valves (PlVs) are any two valves in l
Valves series within the Reactor coolant pressure boundary which separate the high pressure Reactor coolant from an attached low pressure system and are normally closed.
These valves will be seat leak tested in accordance with ASME Boiler and Pressure Vessel Code,Section XI, lWV-3420 Valve Leak Rate Test. However, Containment isolation Valves which also provide a Reactor coolant system pressure isolation function (LP) shall have the PlV .
test conducted in accordance with OM 10 paragraph 4.2.2.3 (refer to OM(10)-01 for basis). The basis for PlV selection is provided in BECo's response to Generic Letter 87-06.
. LX Miscellaneous Other safety related valves - Miscellaneous isolation isolation Valves Valves will be seat leak tested in accordance with ASME Boiler and Pressure Vessel Code Section XI, or standard pressure drop test techniques (RV 30).
FF Full Stroke Exercise Exercise testing of Category A or B valves through one complete cycle of operation. Also applies to Category C
. safety / relief valves with auxiliary actuating device.
- 1) Normally open: Full stroke exercise the valve closed, then return to open possion 4
- 2) Normally closed: Full stroke exercise the valve open, then return to closed position.
- 8. l.1.1 Rev.9 Page 36 of 236
,. -m - - - - - -- - - - . , . r..,r.w.-- , . - + - .,m-, -
1 TABLE 1 INSERVICE VALVE TESTS (Continued)
IEST TEST NAME TEST DESCRIPTION / DEFINITION ST Stroke Time Stroke time is the measurement of the time required to exercise test a Category A or B valve through an operation.
The direction for stroke time measurements is that which is required to fulfill its safety-related function in accordance with the Updated FSAR and/or Technical Specifications.
PE Partial Stroke Partial stroke exercise testing will be performed on those valves that cannot be full stroke exercised during plant operation and have the capability to be partially exercised.
The full stroke exercise shall be performed during Cold Shutdowns.
FC Check Valve Check valves will be exercised to assure freedom of motion Exercise and prevent sticking / seizure of parts from prolonged immobility.
- 1) Forward Flow Direction (FF)- Normally closed valves: Full stroke open.
- 2) Reverse Flow Direction (RF)- Normally open valves:
Full stroke close.
PC Partial Check Partial (valve checked in same flow direction) exercise is Exercise when a Category C valve cannot be verified in its full flow position as required by an FC test.
RD Rupture Disk Test Nontestable rupture disks were test certified by the manufacturer or the startup testing program and no additional testing shall be required. All rupture disks at PNPS are nontestable and shall be replaced in accordance with ANSI /ASME OM 1 every 5 years (Nonreclosing Pressure Relief Devices).
EX Explosive Test Testing of explosive charges by firing in accordance with ASME Section XI with at least 20% of the charges in a batch fired every 2 years with no charge exceeding 10 years.
- 8. l.1.1 Rev. 9 Page 37 of 236
TABLE 1 ,
INSERVICE VALVE TESTS (Continued)
TEST TEST NAME TEST DESCRIPTIONIDEFINITION RT Relief Setpoint Test Relief and Safety Valve setpoints will be verified in
! accordance with ASME Boiler and Pressure Vessel Code, l Section XI(IWV 3510) ANSI /ASME OM 1-1987; and PNPS Technical Specifications i
FS Fail Safe Test Valves with fail safe actuators (e 9., air operated, spring loaded, solenoid operated and hydraulic operated) will be tested to verify proper fail safe operation upon loss of actuator power.
Pl Position Indication Valves with remote position indicators will be checked to Verification verify that remote valve position indicators accurately reflect valve travel direction-AP Alternate A requirement which will verify a check valve has returned I (Normal) Position to its normal operational pcsition This verification will be Verification implemented when the Check valve performs a safety related or operational function in its normal position.
Check valves reposition themselves following an exercise.
This repositioning is verified by normal operational parameters, special testing, nonintrusive testing, or valve disassembly Test frequency may be as often as every 92 days and will not exceed a refueling interval. Where valves do not receive the "AP" test quarterly, a Cold Shutdown Justification, a Refuel Outage Justification, or a Relief Request, as applicable, for bases or test frequency extension. All Relief Requests will be submitted for review and approval by the NRC The following practices will be utilized for AP verification:
- 1) Performance of a 2-year leak test satisfies an AP requirement for the closed position. Valves whose normal closed position cannot be verified quarterly or during Cold Shutdown without a hardship are referenced within RV 37.
- 2) Check valves requiring disassembly to satisfy the AP requirement may be placed in the Check Valve Disassembly Program (Reference RV 27, Table 1).
Valves will only be disassembled to verify AP if there is no practical method currently available to verify their normal position.
81.1.1 Rev 9 ,
Page 3B of 236 1
TABLE 2 TEST FREOUENCY TEST FREO OPERATIONAL CONDITION FREQUENCY OF TESTING O Power Operation At least once per 92 days.
CS Cold Shutdown See (2) below.
RI Refueling interval See (1) below.
OBJ No operational condition Testing frequencies will be established using limitations the performance based intervals in Option B of 10CFR50 Appendix J. Applies to Containment isolation Valve (CIV) seat leakage tests (LJ and LJW). See (3) below.
2Y No operational condition Every two years. Applies to pos!! ion limitations indication tests (see IWV 3300), seat leakage (excluding CIVs tests)(IWV 3422), and explosively actuated valve tests.
SY No operational condition Every five years. Applies to ASME Class 1 kmitations Safety / Relief Valves (see IWV 3511) and Rupture Disks (IVN-3620).
10Y No operational condition Every ten years. Applies to ASME Class 2 &
limitations 3 Safety / Relief Valves (see IWV-3511) and explosively actuated valve tests (lWV 3610).
(1) Refueling outage conditions are as contained in the definitions of the PNPS Technical Specifications. For Inservice Testing purposes, the refueling interval associated with refuel outage testing may be up to 2 years with an allowable extension of no more than 25%.
(2) Plant Cold Shutdown (as defineci in PNPS Technical Specifications) testing is acceptable when the following conditions are met:
(a) Testing is to commence as soon as practical when the Cold Shutdown condition is achieved, but not later than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after shutdown, and continue until complete or the plant is ready to return to power.
(b) Completion of all testing is not a prerequisite to return to power. Any testing not completed during one Cold Shutdown should be performed during any subsequent Cold Shutdown starting with those tests not previously completed.
(c) Testing need not be performed more often than once every 3 months.
(d) In the case of extended Cold Shutdowns, the testing need not be started within the 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> limitation. However, in extended Cold Shutdowns, all Cold Shutdown Testing must be completed prior to returning to power.
8l.1.1 Rev.9 Page 39 of 236
TABLE 2 TEST FREQUENCY (3) The Containment Isolation Valve seat leakage test frequencies utilize the performance-based intervals in Option B of 10CFR50 Appendix J These seat leakage intervals range from test once per 30 months to 60 months and are established and controlled in accordance with PNPS 8.7.1.31.
(4) PNPS Technical Soecifications Surveillance Interval definitions are to be applied to the following required frequencies for performing inservice testing activities. These required intervals may be extended as allowed by the PNPS Technical Specifications
" Surveillance Frequency" definition.
ASME B&PV CODE TERMINOLOGY REQUIRED FREQUENCIES FOR FOR IST ACTIVITIES PERFORMING IST ACTIVITIEF Weekly At least once per 7 days Monthly At least once per 31 days Quarterly (every 3 months) At least once per 92 days Semiannually (every 6 months) At least once per 184 days Yearly At least once per 366 days Blannual or every 2 years At least once per 732 days 8l.1.1 Rev.9 Page 40 of 236
l G.2 VALVE POSTMAINTENANCE TESTING The IST Program requires each valve to be verified as aperationally ready after routine servicing, maintenance repair. or replacement The verification of operational readiness should be achieved by acceptable performance of a Procedure used to verify test rcquirements which may have been affected The %t requirements may be venfied by other documented procedures as lorig as all test conditions are complied with in accordance with Subsection IWV Valve postmaintenance testing guidance is provided uting a Step By Step Determination Retest Flow Path and a Work Scope (WS) Guideline For specialized cases, at the discretion of the ASME Test Engineer an evaluation may be performed to review a specific maintenance task against the reouired Code testing The postmaintenance guidelines may be deviated f from it.1) the ASME Boiler and Pressure Vessel Code,Section XI requirements aie adhered l
to and 2) the evaluation is documented on a Valve Record of Corrective A: tion / Evaluation form (refer to PNPS 8.11) with appropriate signatures i
l Valve postmaintenance test requirement examples are also provided within this section. The Code Testing ASME Test Engineer may be consulted 'or questions or further clarification.
The As Found (Prework) Testing requirements can be determined through this process As-Found testing is pertinent to Containment isolation Valves (only) and must be identified j prior to start of maintenance for compliance of 10CFR50 Appendir J.
f k
8.111 Rev. 9
{ Page 41 of 236
- 6.2 VALVE POSTMAINTENANCE TESTING (Continued) ,
i j [1) Sten Bv Step Determination Retest Flow Path i CAUTION i
! When a postma:ntenance LJ test requirement is identified a pretest (As Found) test must be I considered prior to commencing work !
i I
d
- Verify whether Valve is No IST Retest for .
listed within Valve Program -- No = Operational l STEP 1 i
. fe_Section 6 3__ Readiness.
6 j Yes_
1 i t j STEP 2 Note test requirement (s)
- for valve 1
_ . . . i
,t Yes.. ,
i i
t .
- For each test requirement verify whether work to be No "
j STEP 3 performed is identified l within WS guideline.
l I _
.Y_e s j Locate Procedure No (s)in Section 6.3 i of this Procedure (or other equivalent l STEP 4 documentation) and identify for retest l ccnsideration on Maintenance Request. l l
i
~
STEP 1:- Using this Procedure's Section 6 3, locate the valve and verify whether it is '
listed within the table.
STEP 2: Note all test requirement (s) identified for the valve.
i
. STEP 3: For each valve test requirement, verify whether the work to be performed is '
identified within the WS guideline.
i 81.1.1 Rev.9 Page 42 of 236 2
. _ - . , _ - . _ _ , _ _ . _ . _ _ . _ ~ . . . _ _ _ _ _ ._._____,..._.,__...~._..___.__..-..m.. .J
6.2 VALVE POSTMAINTENANCE TESTING (Continued)
STEP 4: Identify the applicable PN?G Procedure numbers OR equivalent documentation (that will verity the test requirement is performed in accordance with the Subsection IWV) on the Maintenance Request.
NOTE: When using guidelines to determine Containment Isolation Valve
, ApFound (Prework) test requirements, if a postmaintenance LJ procedure l requires retest for operational readiness, then an As.Found test must be l considered. When the work scope covered in a Maintenance Request is changed, it is important to revenfy this 61.Found testing requirement.
[2] Work Scone Guideline l (a) ROUTINE SERVICING - Performance of planned preventive maintenance l which oces not require disassembly of the valve or replacement of parts (such as adjustment of stem cacking or retorquing of valve assembly bolts).
(b) MAINTENANCE Performance of preventive or corrective maintenance which does require disassembly of the valve or replacement of consumable items.
EXAMPLES: replacement of packing; removal of bonnet, stem assembly, or actuntor; and disconnection of hydraulic or electncallines.
AND SPECIFIED MAINTENANCE Performance of preventive or corrective maintenance which is unique to a test requirement and is identified within the test requirement work scope. The test requirement need only be performed if specifically identified within the work scope.
(c) REPAIR Performance of welding or grinding on a valve to correct a defect l (does not include valve actuator).
(d) REPLACEMENT Installation of a new valve, valve part, or a modification to the valve (does not include valve actuator).
l
\
l I
8.1.1.1 Rev. 9 Page 43 of 236
6.2 VALVE POSTMAINTENANCE TESTING (ConFnued)
Cross-Reference Table (Test Reauirement vs Work Scope)
Test Reauirement Work Scopes PC,FC,AP ROUTINE SERVICING. SPECIFIED MAINTENANCE, REPAIR, or REPLACMENT SPECIFIED MAINTENANCE disassembly of the check valve (i.e . IST Check Valve Disassembly Program).
Exception The ROUTINE SERVICING work task for check valves of applying grease through a grease fitting does Opj require PWT exercising (FC) or alternate position verification (AP).
FE,ST,FS ROUTINE SERVICING, MAINTENANCE, REPAIR, or REPLACEMENT.
Exception- The ROUTINE SERVICING work task for motor operated valves of applying grease through a grease fitting or grease r.ug does ngj require PWT exercising (FE), stroke timing (ST), or position indication verification (PI).
LJ SPECIFIED MAINTENANCE, REPAIR, or REPLACEMENT.
SPECIFIED MAINTENANCE: 1) repacking,2) lowering of motor operated valve torque switch mechanism,
- 3) adjustment of motor-operated valve closing limit switch for valves that close on limit switch,4) disassembly of valve internals,5) removal of valve actuator, or
- 6) adjustment of air or hydraulic valve closing stops.
As Found (Pretest) testing is required for Containment isolation Valves.
Exception: Motor operated valve diagnostic testing may sometimes be used to verify valve seating thrust has not been lowered in lieu of leak testing. Os nsult the Code Test Appendix J or ASME Test Engines, for additional guidance.
81.1.1 Rev. 9 Page 44 of 236
6.2 VALVE POSTMAINTENANCE TESTING (Continued)
Cross-Reference Tabin (Test Reauirement vs Work Scope)
Test Reauirement Work Scenes LP, LX, LJW SPECIFIED MAINTENANCE REPAIR or REPLACEMENT SPECIFIED MAINTENANCE 1) alteration to seating surface,2) lowering of motor operated valve closing torque switch setting. 3) replacer,1ent of motor operated valve torque switch mechanism,4) adjustment of motor operated valve closing limit switch for motor operated valves that close on ;imit switch. or 5) adjustmsiit of air or hydraulic valve closing stops.
Exception: Same as LJ test Pl SPECIFIED MAINTENANCE. REPAIR. or REPLACEMENT.
SPECIFIED MAINTENANCE 1) adjustment or
. disassembly of limit switch mechanism which has potential to impact remote position indication,
- 2) terminating /reterminating wiring for the remote indicator circuitry,3) removal and reconnection of the valve actuator, and/or 4) replacement of control switch and/or air control solenoid Exception: No retest for; 1) replacement of fuses or light bulbs,2) single lead lifting and landing wire removal method, and 3) minor position indicator adjustments that do not have potential to reverse remote position indication, Special Case' RCIC Governor Valve HYD-159 requires Pl test anytime work is performed on valve stroke mechanism or limit switches.
RT SPECIFIED MAINTENANCE, REF AIR, or REPLACEMENT.
l l SPECIFIED MAINTENANCE: adjustment of setpoint, disassembly, or internal gagging.
RD REPAIR or REPLACEMENT.
EX None (Manufacturer's data acceptable).
l
- 8. l.1.1 Rev 9 Page 45 of 236 l
\
6.2 VALVE POSTMAINTENANCE TESTING (Continued)
EXAMPLES: 4
- 1. AO 2031 A requires the valve seating surf ace to be machined (grinding) and lapped according to Maintenance Request and the appropriate procedures to be used for retests-
~
0 503-1 A iNist5d 5n No STEP 1 Page 107. -- Operational
. Readiness _
4
.Y. e s_.
t STEP 2 Note valve test requirements-FE,ST.FS.LJ,Pl l
Xy_
t Work Scope to be performed is STEP 3 identified within Guidelines - No Repair. This requires: FE,ST, FS.LJ.PI NOTE: The Local Leak Rate 1ast Yes J (LJ) may require both
]-
g _
Pre- and Post Leak Rate Proc Nurnbers: Testing STEP 4 FE, ST, FS 8.7.4.4 LJ. 8.71.6 Pl: 8.7.1.6 or 8 l.30 Xes_
_ Y -- . _ . _ . _ . . _ _ _ _ _
Perform applicable Maintenance Request steps of Section 7.0, OR documentation not Prerequisites, and required, retest must be lection 8.p, Procedure perfctmed by Procedure.
8l.1.1 Rev 9 Page 46 of 236
6.2 VALVE POSTMAINTENANCE TESTING (Continued)
- 2. 1001 PSV-44 requires the valve seating surface to be lapped according to Maritenance Requast and the appropriate procecures to be used for retests.
~~
No IST Retest F5i STEP, iOO1-PSV4d is tisieh y -+ Operational en Page 85.
_ Readiness _ _._
i Yas I
t
"*"#*'** '*9"***"
STEP 2 RT.LX ies_.
t '~
Work Scope to be peErmed is STEP 3 identified within Guidelines - No SPECIFIED MAINTENANCE.
This requires: RT,LX 2
les_'
Proc. Numbers:
STEP 4 RT: 8.l26.3 LX: 8.1.26.3 Yes
-_ .E- ..- - --
Perform applicable Maintenance Request steps of Section 7.0, OR documentation not Prerequisites, and required, retest must be Sectio.n 8;0lrocedure performed by Procedure.
8 1.1 1 Rev.9 Page 47 of 236
6.2 VALVE POSTMAINTENANCE TESTING (Continued)
- 3. MO-1400 248 requires the stem packing tc de adiusted to minimize leaking and the retest is to be performed with:n the Maintenance kequest package.
~
STEP 1 tdO-1400 24B is listed No -- Operational on Pace 69.
_.-u---- Readiness.
t Y_e s_.
t I[ote valve test requirements STEP 2 FE,ST.LJ,Pi Yes_
Y
< Work Scope to be performed is STEP 3 identified within Guidelines - No
. ROUTINE SERVICING. This I requires. FE. ST NOTE: Tightening stem packing may 18 require additional valve i
diagnostic testing under the PNPS MOV 89-10 program.
STEP 4 Proc. Numbers.
FE & ST: 8 5.1.3
_Yes_ -
Maintenance Request steps t
could follow procedure requirements to document the Review Procedure OR '
Section 7.0, retests: FE, ST. (Using Prerequisites, and Maintenance Request steps to Section 8 0, Procedure, document retest requirements for retest requirements. is n_ol the recommended method.)
81.1.1 Rev. 9 Page 48 of 236
6.2 VALVE POSTMAINTENANCE TESTING (Continued)
- 4. MO 23013 requires the electric motor to be replaced according to Maintenance Request and the appropriate procedures to be used for retest.
Oo15 ketestioI N --Operational STEP 1 e9 Read iness _
_ _ _ t Y. e s_
t Note valve test requirements.
Work Scope to be performed is identified within Guidelines - No STEP 3 MAINTENANCE This requires FE ST, PI NOTE: Motor replacement is Yes. categorized as MAINTENANCE.
STEP 4 Proc Numbers:
FE & ST: 8.5 4.1 or 8.5 4 4 Pl: 8.5 4.4 _
"s f[aintenance Request steps j-could follow procedure f
requirements to perform the PI
- Perform applicable steps of OR retest (using Maintenance Section 7.0, Prerequisites, and Section 8 0, Procedure, Request steps to document retest requirements is nol the for FE. ST. PI recommended method).
8, l .1.1 Rev. 9 Page 49 of 236
I i
6.2 VALVE POSTMAINTENANCE TESTING (Continued)
- 5. HO 100133A .equires the handwheel to be replaced according to Maintenance 1 Request.
I
- STEP 1 501001 33Us~ hsted No + Operational on Page 83 Readiness 4
Y. . e s_
t Note valve test requirements:
STEP 2 Pl Yes.
t Work Scope to be performed is STEP 3 identified within Guidelines - No MAINTENANCE. This requires < NA NOTE. Handwheel replacement is considered replacement of g valve actuator and falls Proc. Numbers: within WS as MAINTENANCE.
STEP 4 'Not Required MAINTENANCE is not identified within the PI test requirement work scope.
l l 8.1.1.1 Rev 9 l Page 50 of 236
l i
6.3 VALVE PROGRAM TABLE This table identifies the scope of valves within tnu 'ST Program and allows cross-referencing specific valve test requirements to their implementing Station Procedure. The table sequence j is by ascending P&lD numcer (Compressed Air System (31)is asted on P&lDs M220, M227, and M252.)
Newly incorporated component / test requirements will be identified by an asterish (*) next to the implemenung Procedure When using (*) Procedures for postmaintenance testing, the current, approved Procedure should be reviewed for apphcabihty (i e., is the new test
, requirement or component incorporated) i j [1] Valve Test Index System PalD Revision Ea.ge
, Salt Service Water (29) M212 E36 53 Reactor Building Closed Cooling Water (30) M215 E28 55 I Diesel Genera'or Air Start System (47) M219 E10 57 Compressed Air (31) M220 59
- Sh 1 of 2 E34 i
Diesel Oil Transfer (38) M223 E9 60 Containment Atmosphere Control M227 61 (45 & 9) Sh 1 of 2 E35 Sh 2 of 2 E19 Compressed Air (31) M227 69 4
Sh 1 of 2 E35 Nitroger Supply (9) M227 70 Sh 2 of 2 E19 Fuel Pool Cooling and M231 E12 71 Demineralizer System (19)
Radwaste Collection (20) M232 E15 72 Post Accident Sampling & Hydrogen M239 73 And Oxygen Analyzer System (5065) Sh 1 of 3 E10 Sh 2 of 3 E9 l
Residual Heat Removal System (1001) M241 81 i Sh 1 of 3 E45 Sh 2 of 3 E24 l Core Spray System (1400) M242 E22 88 High Pressure Coolant injection M243 91 (2301) Sh 1 E21 M244 Sh 2 E17
- 8. l .1.1 Rev 9
{ Page 51 of 236
. 6.3 VALVE PROGRAM TABLE (Continued)
System PalD Revision f)R21 Reactor Core Cooling System (1301; M245 95 Sh 1 E18 M246 Sh 2 E17 Reactor Water Cleanup System (1201) M247 E26 99 Standby Liquid Control System (1101) M249 E13 100 Control Rod Drive Hydraulic M250 101 System (302) Sh 1 of 2 E28 Sh 2 of 2 E14 Recire Pump Instrumentation _(262) M251 E5 104 Feedwater System (6) M252 E29- 105 Reactor Recirculation System (202) M252 E29 106 Main Steam Isol., ADS, & Safety'_ M252 E29 107 Relief (203)
Nuclear Boiler System (220) M252 E29 110 Compressed Air (31) M252 E29 111 Nuclear Boiler (261) M252 E29 113 Nuclear Boiler Vessel M253 117 Instrumentation (263) Sh 1 of 2 E26 Sh 2 of 2 E17 Diesel Generator Turbo A,ir Assist M259 E4 121 System (47)
Traversing In-core Probe (45) M10-1-5 E2 123 Standby Gas Treatmerit System (48) M294 E15 124 M.Q_T.E The drawing revision level will require changing if:
- 1. The revision affects information within the program table t- .QB
- 2. A formal review of the program is performed against the latest revision.
i i
- 8. l.1.1 Rev. 9 Page 52 of 236 l
m .-
TABLE
!?JSERVICE VALVETESTIttG PROGRAM ISI CLASS 1,2,3 AtJD PJC VALVES PILGRIM FJUCLEAR POVER STATIOf4 P&tD M212 SYSTEM SALT SERVICE WATER (29)
Vat <e P&tD 153 Vatve Vatve Valve Actuator FJorma! Test Test PfFS Proc. Test ReW1 Number Coor Class Cat See Type Type Position Romt Freq tJumber DractKm Jetonatum flotes 3800 G-8 3 8 18 BF MO O FE O 85311 ST O 85311 O Pt 2Y 85311 3801 G-7 3 8 12 BF MO O PE O 85311 FE CS 8I11 14 CS-14 ST CS 8 I 11.14 C CS-14 P1 7Y 8811.14 3905 G-6 3 8 12 BF MO O- PE O 85311 FE CS 881114 CS-14 ST CS 8 I 11.14 C CS-14 P1 2f 851114 3806 G-5 3 8 18 BF MO O FE O 85311 ST Q 85311 O Pt 2Y 85311 3808 C-6 3 B 12 BF MO O FE O 85311 ST O 85311 O/C Pt 2Y 85311 3813 C-6 3 8 12 BF MO O FE O 85311 ST Q 85311 O/C Pt 2Y 85311 3915 D-4 3 8 6 BF AO O FE O 85311 ST O 85311 FS O 85311 C 3925 C-4 3 8 6 BF AO O FE O 85311 ST O 85311 FS O 85311 C 3880A C-7 3 C 12 CK SA O FC O 85321 RF AP CS 85321 Open 38808 C-8 3 C 12 CK SA O FC O 85321 RF AP CS 85321 Open 3880C C-6 3 C 12 CK SA O FC O 85321 RF AP CS 85321 Opan 3880D C-6 3 C 12 CK SA O FC Q 85321 RF AP CS 85321 Open 388GE C-5 3 C 12 CK SA O FC O 85321 RF AP CS B5321 Open 8.1.1.1 Rev. 9 Page 53 of 236
s - ._ _ . - - _ _
TABLE INSERVICE VALVE TESTING PROGRAM '
ISI CLASS 1. 2. 3 AND NC VALVES PILGRIM NUCLEAR POWFR STATION P&fD M212 SYSTEM ' SALT SERVICE WATER (29)
Valve P&tD ISI Valve Valve Vatve Actuator tJormal Test Test PHPS Proc. Test Reisef/
Number Coor Class Cat Scre Type Type Post m Rqmt Freq th h Direction Jtssti6cate tJotes AV-A C-7 3 C 2 CK SA C FC O 85321 FF AP Q 85321 Closed AV-B C-8 3 C 2 CK SA C FC Q 8 5 3 2.1 FF AP O 85321 Closed AV-C C-7 3 C 2 CK SA C FC Q 85321 FF AP Q 85321 Closed AV-D C4 3 C 2 CK SA C FC O 85321 FF AP Q 85321 Closed AV-E C-5 3 C 2 CK SA C FC O 85321 FF AP Q 85321 Closed 8.L1.1 Rev. 9 Page 54 of 236
, _ . _ - . -. -- - . . . . ,_.. ~ - = . - - - - _ - - . . . . ..
TABLE i 4 INSERVICE VALVE TESTING PROGRAM j ISI CLASS 1. 2. 3 AND NC VALVES 4 . PILGRIM NUCLEAR POVER STATION
'- P&lD- M215 ' SYSTEM RE ACTOR PUfLDitJG CLOSED COOLING WATER (30) !
. Valve P&lO ISI Valve Vatn Valve Actuator Normat Test Test Pt4PS Proc. Test Hehett Number Coor Class Cat Sire Type Type Poston Rqmt Freq Number DarMon Jtesttfreatm f40tes l 419 G-3 3 C 8 CK SA. O FC Q 8531 RF taste 2 !
420 G-3 3. C 8 CK SA O FC Q 8531 RF tJote 2 i AP CS B 111 19 Open RV-38 Note 3/3 M 4-53 }
l 421 F-3 3 C 8 CK SA O FC O 8531 RF Note 2 '
~
AP CS 811119 Opan RV 38 Note 3/3 M 4-53 j 422 G-5 3 C 8 CK SA O FC O 8531 RF t40te 2 AP CS 8 t 11 19 Open RV-38 Note 3t3 M 4-53 [
423 G-5 3 C 8 CK SA O FC O 8531 RF taote 2 e AP CS 8I11 19 Open RV-38 Nde 3/3 M 4-53 l 424 F-5 3 C 8 CK SA O FC Q 8531 RF Note 2 AP CS 811119 Open RV-38 Nec 313 M 4-53 I 432 C-6 2 AC 6 CK SA O FC Rt 8715 RF R D 01 AP Q 8131 Open LJ OBJ 8715 07410)01 4 4002 C-4 2 A 6 GA MO O FE CS 881113 iTV-J2 tacte 4 t ST CS 811113 C i RV-32 Note 4 i Pt 2Y 8715 Ns > 8 30 i LJ OBJ 8715 OM(1010 t l 4009A D-6 3 8 8 GA MO O FE CS 811113 9 V-32 t4,te 4 jl ST CS S I 11 13 C RV-32 Note 4 ;
1 Pt 2Y 811113 r 40098 C-4 3 8 8 GA MO O FE CS 8 t 11 13 Rv.32 taote 4 ST CS 811113 C RV-32 Note 4 L PI 2Y 811113 4010A G-7 3 B. 12 GA MO C FE O 8 5 3 to [
ST O 853to O 1
P1 ?V M S 3 to i 4 4010B H-7 3 8 12 GA MO C FE C 8 5 3 to !
ST O 853to O- ;
4 PI 2Y 85310 3 4020 D-1 3 C 0 75 RL SA C RT 10v 8 I26 3 1 4031 D-1 3 C 3 RL SA C RI 10Y 81263 4032 ri-7 3 C 3 RL SA C RT 10Y 8I263 C033 NC C 15 RL SA C RT 10Y 81263* [
4036 H-7 3 C 0 75 RL SA C RT 10Y 81263 L t
WOTE 2. Performance of PNPS 8 I 11.19 also satisfies the FC test requrrement d
'j NOTE 3 If work is performed on these check valves that requires a postmaintenance test (useng PNPS 8 I 11 19) and plant conditions do not allow conduct of FNPS 8 811 19 then an exercise /examinatum using PNPS 3 M 4-53 must be sattsfactonly completed for operability i NOTE 4 Performed during Cold Shutdown, when core flow from recirculation pump operation es not required L
8.l.11 Rev.9; Page 55 of 236 ;
t
- - .. .. . . ~ . - . ~ - . - .. . . . _ - .
TABLE INSERVICE VALVE TESTING PROGRAM ISI CLASS 1. 2. 3 AND NC VALVES P!LGRIM NUCLEAR POWER STATION PalD: M215 __ SYSTEM REACTOR BUILDitJG CLOSED COOtJNG WATER (30)
Valve P&lD ISI Valve Vatve Valve Actuator tJormal Test Test PNPS Proc. Test Reheft -
Number Coor Class Cat Size Type Type- Pasrbon Rqmt Freq tJumber Direction Justification Hofes :
4043A F-2 3 8 1.5 GL AO O FE NA tJA . Pass,ve ST f1A flA PI TJA TJA 40438 F-2 3 B 1.5 GL AO O FE tJA tJA Passeye ST NA NA t
PI f1A tia 4.v iA E-7 3 0 1.5 GL AO O FE TJA NA Passive ST tJA NA PI tJA NA 4044B E-7 3 8 1.5 GL AO O FE NA t4A Passive ST NA fJA Pl NA tJA 4060A C-2 3 8 12 GA MO C FE Q 85310 ST Q 85310 O PI 2Y 85310 4060B D-2 3 8 12 GA MO C FE O 85310 ST Q 85310 0 Pt 2Y 85310 4065 B-2 3 B 6 GA MO O FE O 85310 ST Q 85310 C P1 2Y 85310 4083 E-4 o B 10 BF- MO O FE Q 85310 ST Q 85.310 C Pt 2Y 85310 4084 F-4 3 8 10 BF MO O FE O 85310 ST Q 85310 C PI 2Y 85310 4085A E-2 3 8 8 GA MO O FE CS 811113 RV.34 tJote 3 ST CS 8l11 13 C RV-34 tJote 3 PI 2Y 811113
~4085B D-3 3 8 8 GA MO O FE CS 8 i 11.13 RV-34 tJote 3 ST CS 8811.13 C RV-34 tiotc 3 Pt 2Y 811113 NOTE 3: Performed during Cold Shutdown, when core flow from recirculation pump operation is not required 8.11.1 Rev.9 Page 56 of 236 '
TABLE INSERVICE VALVE TESTING PROGRAM ISI CLASS 1,2,3 AND NC VALVES PILGRIM NUCLEAR POWER STATION 1 PGID: M219 L SYSTEM- DIESEL GENERATOR AfR START SYSTEM (47)
- Valve P&lD ISI- Vatve . Valve Valve Actuator Normal Test Test ' PNPS Proc. Test . Rehef/ -
Number Coor Class Cat - Size Type Type Position ' Rqmt. Freq Number Direction Justifcation ' Notes 101A. G-7 NC AC 0.75 CK SA C FC Q -8.9.1 FF AP Q 891- Closed LX 2Y 8912 RV-30
.101B D-7 NC AC 0.75 CK SA C FC Q 8 9.1 .FF AP Q 8 9.1 Closed -
LX 2Y 8912 RV 101C F-7 NC AC 0 75 CK SA C FC Q 8 9.1 FF AP Q 891 Closed LX 2Y 8912 RV-30 101D B-7 NC AC 0.75 CK SA C FC Q 891 FF AP Q 891 Closed LX 2Y 8912 RV-30 102A F-6 NC A. 0.75 GA MA C FE NA t4A LX 2Y 8 9 1.2 RV-30 102B C4 NC A 0.75 GA MA C FE NA f4A i U 2Y 8912 RV-30 102C E4 NC A 0.75 GA. MA C FE NA f4A LX 2Y 8912 RV-30 102D A4 NC A 0 75 GA MA C FE NA NA LX 2Y B912 RV-30 4582A H4 NC AC 0.75 SV SA C RT 10Y 84263
- LX NA 81263 RT Ver
- fres 45828 D4 NC AC 0 75 . SV SA C RT 10Y 8426.3 LX NA 8 I26 3 RT "enfees 4582C F-6 NC AC 0.75 SV- SA C RT 10Y 8126.3 LX NA 8I26 3 RT Vent.es 4582D C-6 NC AC 0.75 SV SA C RT 10Y 8126.3 LX fIA 8I26 3 RT Venfies 8.1.1.1 Rev. 9 Page 57 of 236
. . -TABLE INSERVICE VALVE TESTING PROGRAM ISI CLASS 1,2. 3 AND NC VALVES .
. PILGRIM NUCLEAR POWER STATION
.P&lO: M219 ,, SYSTEM DIESEL GENERATOR AIR START SYSTEM (47)
Vatve . P&lD ISI Valve Valve - Vatve Actuator Normal Test t est . PNPS Proc. - Test Relet /
Number Coor Class Cat ' Size Type' Type Position Ramt - Freq Number D4rection ' Justification Notes I 4586A H-4 NC .B. 1.5 GA So C FE O. 891 RV-19 l ST O -- NA RV-19
, FS O 891 C RV-19 4580B H-4 NC B 1.5 GA- SO C FE O 891 RV-19 ST NA RV-19 FS O- ~ 891 O C RV-19 4587A E NC B 1.5 GA SO C FE O 891. RV-19 ST Q NA RV-19
=
FS O 891 C RV-19
-4587B E-4 NC .B 1.5 GA SO C FE- O 891 RV-19 ST O NA RV-19 FS O 891 C RV-19 l T4588A E-4 NO B 1.5 GA SO C FE .O 891 R V-19 ST Qi NA RV-19 FS O 891 C' RV-19 4588B D-4 '
NC B 1.5 GA SO- C FE O 891 RV-19 ST' O NA RV-19 FS O 891 C RV-19 4589A B-4 NC B 1.5 - GA SO C FE O 891 RV ST Q NA RV-19 FS O 891 C RV-19
! 4589B B-4 NC B 1.5 GA SO C FE O 891; RV-19 ST O NA RV-19 FS O 891 C RV-19 i
i.
i 1
8.1.11 Rev. 9 '
Page 58 Of 236
TABLE ItJSERVICE VALVE TESTitJG PROGRAM ISI Ct. ASS 1,2,3 AND fJC VALVES PILGRIM F4UCLEAR POWER STATIOf1 P&lD. M220 SHEET 1 of 2 SYSTEM COMPRESSED AIR (31)
Valve P&lD ist Valve Valve Valve Actuator tJormat Test Test PtJPS Proc. Test Relieff Number Coor Class Cat Size Type ~ Type Posrtion Rqmt Freq . tJumber Direction Justification fJotes !
167 D-3 2 AC 3 CK SA O FC Rt 87122 RF PV 02 Also 8 71.5 AP R1 871.10 Ope- RV-02 LJ OBJ 8715 OM(10)-01 i
i l
- 8. .1.1 ' Rev. 9 l Page 59 of 236 l
96
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T S f/ f ic 3 3 Y eit 2- 2-S he u s V V RJ R R n
o d d d d t
i e e e e c s s s s t
s er Fl o Fl o Fl o Fl o F F C
/
C
/
ei TD FC FC FC FC F F O0 OO c
M o A
RSO N r Pr e 11 11 11 11 111 111 GEIT Pm Sb 11 11 11 11 1 1 111 111 OVAL Nu 99 99 99 99 9A 9A 999 999 RAT PV S PN 88 88 88 88 8N 8N 888 888 GCR E t q s A NN ere OQ OQ OQ OO QN A ON OQO OQQ TD W I
TF ESNO LEAP t BT R t s m CP CP CPCP CP CP ETS ETS AE3. A T e aFA FA FAFA FA FA FSF FSF V TR L 2,E L
A1C VSU ESN lao n
i CAMI IL mt i VCR r s C oo C C C C C C C RIG ESL NP SII N P I
r t
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ue tcy pA A A A A A O O AT S S S S S S A A e
v ep layK" K K K K K L L VT C C C C C C B B e
ve 5 5 laiz 5 5 7 7 5 5 VS 2 2 1 1 0 0 1 1 e
vt laa C C C C C C B B VC s
s I a Sl C C C C C C C C _
IC N N N N N N N N Dro 7 4- 5-l ao 7 5 5- 4- 5 PC F D F E G E G E 3
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M r e A v mA A B 8 B 2 D eb
- 1 1 1 5 5 6 6 2 2 l
0 0 0 0 1 1 5 5
& ta u 1 1 1 1 1 1 4 4 P VN
TiBLE ItJSERVICE VALVE TESTitJG PROGRAM .
ISI CLASS 1. 2,3 AND tJC VALVES PILGRIM NUCLEAR POWER STATION P&lD: M227 SHEET 1 of 2 SYSTEM CONTAlfJMEfJT ATMOSPHERE CONTROL P&lD: M227 SHEET 2 of 2 SYSTEM NUMBERS 45 & 9 Valve P&lD ISI Valve Valve Valve Actuator tJorman Test Test PtJPS Proc Test Ret.et/ I' Number Coor Class Cat Stze Type Type Position Rqmi Freq Number Direction Justibcat.on Notes I; 102 C-6 2 A 1 GL MA C FE NA t4A Passtve (Manual)
(45) (SH 1) LJ OBJ 8715 OM(10) 01 1I 103 C-6 2 A. 's GL MA C FE NA NA Passsve (Manual)
(45) (SH 1) LJ OBJ 8715 OM(10) 01 1 104 C-6 2 A 1 GL MA C FE FJA NA Passrve (Manual)
(45) (SH 1) LJ OBJ 8715 OM(10101 Ii 105 C-6 2 A 1 GL MA C FE tJA NA passive (Manual)
(SH 1) LJ OBJ 8715 OM(10) 01 I (45) :
106 E-5 2 A 4 GA MA C FE NA FJA Pass <ve (Manual) !
(45) (SH 1) LJ OBJ 8715 OM(10)-01 1!
X-201A C-7 2 AC 18 CK SA C FC Q 8A1 FF (45) (SH 1) (Testable) AP Q 8A1 Closed Pt 2Y 8 7.1 9 Afso 8130 f LX RI 8A2 RV-03 '
X-2018 C-7 2 AC 18 CK SA C FC O 8A1 FF (45) (SH 1) { Testable) AP O 8A1 Ck> sed Pl 2Y B719 Also 8130 LX R1 8 / '> R V-03 X-201C C-7 2 AC 18 CK SA C FC O 8A1 FF (45) (SH 1) (Testable) AP O 8A1 Closed !
Pt 2Y 8 7.1 9 A!so 8 i 30 [
LX RI 8A2 RV-03 i X-201 D C-7 2 AC 18 CK SA C FC O 8A1 FF (45) (SH 1) (Testable) AP Q 8A1 Closed Pt 2Y 8'719 Also 8130 LX RI 8A2 RV.03 X-201E C-7 2 AC 18 CK SA C FC O 8A1 FF t (45) (SH 1) (Testable) AP O 8A1 Closed
- Pt 2Y 8719 Also 8130 LX Rt 8A2 RV-03 i
t
- 8. l.1.1 Rev. 9 ,
Page 61 of 236 ;
i
TABLE INSERVICE VALVE TESTING PROGRAM ISI CLASS 1,2,3 AND NC VALVES P'tGRIM NUCLEAR POWER STATION PalD: M227 SHEET 1 of 2 SYSTEM. CONTAINMENT ATMOSPHERE CONTROL P&tD: M227 SHEET 2 of 2 SYSTEM NUMBERS 45 & 9 Valve P&tD ISI Valve Valve Valve Actuator Norma! Test Test PNPS Proc. Test Rehet/
Number Coor Class Cat Size Type Type Posstion Rqmt Freq Number Direction Just fecation Notes L201F C-7 2 AC 18 CK. SA C FC Q 8A1 FF (45) (SH.1) (Testable) AP Q 8A1 Closed Pt 2Y 8719 Also 8 I 30 u Rf 8A2 RV-03 X-201G (7 2 AC 18 CK SA C FC Q 8 A.1 FF (45) : 3H 1) (Testable) AP Q 8A1 Closed l
' P! '2Y 8 7.1 9 Also 8130 LX RI 8A2 RV-03 X-201H C-7 2 AC 18 CK GA C FC Q 8A1 FF (45) (SH.1) (Testable) AP Q 8A1 Closed P1 2Y 8719 Also 8 I 30 LX RI BA2 RV03 L201J C-7 2 AC 18 CK SA C FC O 8A1 FF (45) (SH 1) (Testable) AP Q 8A1 Closed Pt 2Y 87.19 Also 8130 LX RI 8A2 RV-03 X-201K- C-7 2 AC 18 CK SA C FC O 8A1 FF (45) (SH 1) (Testable) - AP Q 8A1 Closed Pt 2Y 8719 Afso 8 i 30 LX R1 6A2 RV-03 X-212A A-8 2 AC- 20 CK SA C FC O 8749 FF (45) (SH 1) AP Q 8749 Closed PI 2Y 8715 Also 8 I 30 LJ OBJ 8715 OM(10) 01 X-212B A-7 2 AC 20 CK SA C FC O 8 T4 9 FF (45) (SH1} AP Q 8749 Closed Pt 2( 8 7.1 5 Also 8130 LJ ORf 87i5 OM{10)-O t
- 8. I.1.1 Rev. 9 Page 62 of 235 !
j
1ABLE ItJSERVICE VALVE TESTING PROGRAM 151 CLASS 1. 2,3 AfJD NC VALVES PILGRIM tJUCLEAR POWER STATIOf4 P&lD. M227 SHEET 1 of 2 SYSTEM COPJTAINMENT ATMOSPHERE CONTROL P&lD. M227 SHEET 2 of 2 SYSTEM NUMBERS 45 & 9 Vtiva P&lD ISI Valve Va*ve Valve Actuator Normal Test Test PNPS Proc Test Reimf/ g Number Coor Class Cat Size Type Type Posmon Rqmt Freq Number Direction Justification FJotes 5025 E-8 2 A 8 BF AO C FE f4A FAA (De-Energized m (45) (SH 1) ST NA NA Closed posdson)
FS tJA PJA P1 2Y 8 7 1.5 Also 8130 LJ OBJ B715 OM(10) 01 1 5033A D-7 2 A 1 GL AO C FE o 8742 (9) (SH 2) ST O 8742 C FS O 8742 C Pt 2Y 8715 Also 8130 LJ OBJ 8 7.1 5 OM(10). 01 1 50338 C-6 2 A 4 GA AO C FE O 8742 (9) (SH 2) ST Q 8742 C FS O 8742 C Pt 2Y 8715 Also 8130 LJ OBJ 8715 OM(10) 01 I 5033C D-6 2 A 1 GL AO C FE O 8742 (9) (SH 2) ST O 8742 C FS O 87.42 C Pt 2Y 8715 . Also 8 I 30 LJ OBJ 8715 OM(10) 01 1 5035A E-3 2 A 8 BF AO C FE O 8742 (45) (SH 1) ST -) 8742 C FS O 8742 C PI 2Y 8715 Alsa 8 I 30 LJ OBJ B715 OM(10)-01 l 5035B E-2 2 A 8 BT AO C FE Q 8742 (45) (SH 1) ST O 8742 C FS U 8742 C P1 2Y 8715 Also 8130 LJ OB1 8715 OM(19 01 1 8.1.1.1 Rev. 9 Page 63 of 236
TABLE INSERVICE VALVE TESTING PROGRAM ISI CLASS 1,2. 3 AND NC VALVES PfLGRIM NUCLEAR POVER STATION P&lD: M227 SHEET 1 of 2 SYSTEM CONTAltJMENT ATMOSPHERE CONTROL P&lD: M227 SHEET 2 of 2 SYSTEM NUMBERS 45 & 9 VLive P&lD ISI Valve Valve Valve Actuator Normal Test Test PNPS Proc. Test Rehef/
Number Coor Class Cat Size Type Type Posrtion Rqmt Freq FJumber Direction Just.?scatuar- Notes 5036A C-3 2 A 8 BF AO C FE O 8742 (45) (SH.1) ST O 8742 C FS O 8742 C Pl 2Y 8 7.1 5 Also 81.30 LJ OBJ B 7.1 5 OM(10)-01 50368 C-2 2 A 8 BF AO C FE O 8742 (45) (SH.1) - ST O 8742 C FS O 8742 C Pt 2Y 8 7.1 5 Also 8130 LJ OBJ B715 OM(10)-01 5040A B-8 2 A 20 BF AO C FE O 8749 (45) (SH 1) ST O 8749 O/C FS O 8749 O PI 2Y 8 7 1.5 Also B I 30 LJ OBJ B715 OM(10)-01 50408 B-7 2 A 20 BF AO C FE O 8749 (45) (SH 1) ST Q 8749 O/C FS O 8749 O Pt 2Y 8715 Also 81.30 LJ OBJ 8715 OM(10) 01 5041A C-8 2 A 2 GL AO C FE O 8742 (45) (SH.1) ST O 8742 C FS O 8742 C Pt 2Y 8 7.1 5 Also 8130 LJ OBJ 8715 OM(10)-01 50418 C-8 2 A 2 GL AO C FE O 8742 (45) (SH 1) ST Q 8742 C FS O 8742 C PI 2Y 8 7,1 5 Also 8 I 30 LJ OBJ 8715 OM(10) 01
- 8. l.1.1 Rev. 9 Page 64 of 236
6 INSERVICE VALVE '. uSTitJG PROGRAM ISI CLASS 1,2. 3 AND NC VALVES PILGRIM NUCLEAR POWER STATION P&lD. M227 SHEET 1 of 2 SYSTEM CONTA!fJMENT ATMOSPHERE CONTROL P&lD- M227 SHEET 2 of 2 SYSTEM NtJMBERS 45 & 9 Vdve P&lD ISI Valve Valve Valve Actuator Normal Test Test PNPS Proc Test Reheff Number Coor Class Cat Size Type Type Posmon Rqmt Freq Number Directron Justihcaten Notes ~~
h C O 5042A D-8 2 A 8 BF AO FE B 7.4 2 (SH.1) ST O 8 7.4 2 C (45) O 8 7.4 2 C FS PI 2Y 8 7.1 5 Also 8 f.30 LJ OBJ 8 '71 ' OM(10) 01 @
5042B D4 2 A 8 BF AO C FE O 8742 (45) (SH.1) ST Q 8742 C FS O '8742 C Pt 2Y 8 7.1 5 Also 8130 LJ OBJ 8715 OM(10)-01 ]
5043A E-7 2 A 2 GL AO C FE O .8742 (SH 1) ST O 8742 C.
(43)
FS O 8742 C Pl 2Y 87.15 Also 8 I 30 LJ OBJ 8 715 OM(10F01 {:
5043B E-7 2 A 2 GL AO C FE O 8742 (45) (SH 1) ST O 8742 C FS O 8742 C Pt 2Y 8 7.1 5 Also 8 f 30 LJ OBJ 8715 OM(10)-01 I, 5044A F-7 2 A 8 BF AO C FE O 8742 (45) (SH.1) ST Q 8742 C FS O 8742 C Pl 2Y 8 7.1 5 Also 3 4 30 LJ OBJ 8715 OM(10)-01 F-7 A 8 BF AO C FE O 8742 l!
50448 2 (45) (SH 1) ST Q 8742 C FS O 8742 C P1 2Y 8 7_1 5 Also e 30 LJ OBJ 8 715 OM(10F01 ll 8.1.1.1 Rev.9 Page 65 Of 236
~-. __ _ __
TABLE INSERVICE VALVE TESTING PROGRAM ISI CLASS 1,2. 3 AND NC VALVES PILGRIM NUCLEAR POWER STATION P&lD: M227 SHEET 1 of 2 SYSTEM COfJTAif4MEfJT ATMOSPHERE CONTROL -
P&lD: M227 SHEET 2 of 2 - SYSTEM NtJMBERS 45 & 9 P&lD Valve Valve Valve Actuator fJormal Test Test PNPS Proc. Test Rehef/
Vdve Number Coor ISI Class Cat Seze Type Type Position Rqmt Freq fiumber ' Detection Justification PJotes i1 5081A G-6 2 A 1 GA SO C FE O 8742 ST O 8742 O/C RV-04 (45) (SH 1)
FS O 8742 C P1 2Y 8715 A!so 8 7 4 LJ OBJ 8715 OM(10F01 [
50818 G-6 2 A 1 GA SO C FE O 8 7.4 2 (45) (SH 1) ST O 8742 O/C RV-04 FS O 8742 C Pt 2Y 87.15 Also 8 7 4 LJ OBJ 8 715 OM(10) 01 l 5082A G-6 2 A 1 GA SO C FE O 8742 (45) (SH.1) ST O 8742 O/C RV-04 FS O B742 C Pt 2Y 8715 Also 8 7.4 LJ OBJ 8 715 OM(10)-01 -l 50828 G-6 2 A 1 GA SO C FE O 8742 ST O 8742 O/C RV-04 (45) (SH.1)
FS O 8742 C PI 2Y 8715 Also 8 7 4 LJ OBJ 8715 OM(10) 01 l 5083A G-7 2 A 1 GA SO C FE O 8742 (SH 1) ST O 8742 O/C RV-04 (45) FS O 8742 C
- Pl 2Y 8715 Also 8 7.4 .
LJ OBJ 8715 OM(10) 01 1 5083B G-7 2 A 1 GA SO C FE O 8742 (45) (SH 1) ST Q 8742 O/C RV-04 FS O 8742 C PI 2Y 8715 A13o 8 7 4 LJ OBJ 8715 OM(10) 01 l 8.1.1.1 Rev. 9 Page 66 of 236
.. . . . . = . . . . . . _ _ . - . .
TABLE INSERVICE VALVE TESTING PROGRAM iS1 CLASS 1,2. 3 AND PJC VALVES PILGRIM NUCLEAR POWER STATION PalD: M227 SHEET 1 of 2 SYSTEM. CONTAINMENT ATUOSPHERE CONTROL PalD' M227 SHEET 2 of 2 SYSTEM tJUMBERS 45 & 9 Vrive PalD ist Valve Vatve Valve Actuator (Jormal Test Test PNPS Proc. Test Rehet/
Coor Class Cat Size Type Type Position Rqmt Fraq Numb *r Direction Justificatvan fJotes Number 5084A H.7 2 A 1 GA SO C FE O 8742 ST Q 874.2 O/C RV-04 (45) (SH.1) FS O 8742 C Pl 2Y 8715 Also 8 7 4 LJ OBJ 8715 OM(10) 01 50848 H-7 2 A 1 GA SO C FE O 8742 (SH.1)
ST Q 8742 O/C RV-04 (45) FS O 8 7.4.2 C Pl 2Y 8 7 1.5 Also 8 7 4 LJ OBJ 8 7.15 OM(10) 01 5085A E-7 2 A 1 GA SO C FE O 8742 ST Q 8742 O/C RV-04 (9) (SH 2) O 8742 C FS Pt 2Y 8715 Atso 8 7.4 LJ 03J8715 CM(10) 01 50858 D-7 2 A 1 GA SO C FE O 8742 (9) (SH 2) ST Q 8742 O/C RV-04 FS O 8 7.4 2 C PI 2Y 8 7 1.5 Also 8 7 4 LJ O BJ 8 7.1 5 OM(10)-01 508SA E-7 2 A 1 GA 50 C FE O 8742 (SH 2) ST Q 87A2 O/C RV-04 (9) FS O 8742 C Pi 2Y B 7 1.5 Also 8 7 4 LJ OBJ 8715 CM(10)-01 ,
5086B D-7 2 A 1 GA SO C FE O 8742 ST Q 8742 O/C RV-04 (9) (SH 2)
FS O 8742 C Pt 2Y 8715 Also 8 7.4 LJ OBJ 8715 CM(10) 01
'I 8.1.1.1 Rev.9 Page 67 of 236
TABLE INSERVICE VALVE TESTING PROGRAM ISI CLASS 1,2. 3 AND NC VALVES PILGRIM NUCLEAR POWER STATION PalD. M227 SHEET 1 of 2 SYSTEM CONTAINMENT ATMOSPHERE CONTROL P&tD. M227 SHEET 2 of 2 SYSTEM NUMBERS 45 & 9 Vatve PalD . ISI Vaive Valve Valve Actuator tJormal Test . Test PtJPS Proc Test Reimt/ g Number ~ Coor Class Cat Size Type Type Position Rqmt Freq Number Onection ' Justifmat+on Notes 1 5087A E-8 -2 A 1 GA SO C .FE O 8742 (9) (SH.2) ST O 8742 O/C RV 04 FS O 8742 C Pt 2Y 8715 Also 8 7 4 SO C LJ OBJ 8 715 O 8742 OM(10101 l' 5087B D-8 2 A 1 GA FE (9) (SH 2) ST O 8742 O/C RV-04 FS O 8742 C PI 2Y 8 7.1.5 . Also 8 7 4 LJ OBJ 8715 OM(10} 01 l 5088A E-7 2 A 1 GA SO C FE O 8742 (9) (SH 2) ST Q 8742 O/C RV-04 FS O 8742 C Pt 2Y 87.15 ' Also 8 7 4 LJ OBJ 8 715 OM;10) 01 l 5088B D-7 2 A 1 GA SO C FE O 8742-(9) (SH 2) ST G 6742 O/C RV-04 FS O 87.42 C Pt 2Y 8715 , Also 8 7 4 LJ OBJ 8715 OM(10)-01 . l 0.l.1.1 Rev. 9 Page 68 of 236
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TABLE INSERVICE VALVE TESTING PROGRAM ISI Ct. ASS 1,2,3 AND NC VALVES P!LGRIM NUCLEAR POWER STATION PA D: M227 SHEET 2 of 2 SYSTEM NITROGEN SUPPLY (9)
Valve PalD ISI Valve Valve Valve Actuator tJormal Test Test Pt4PS Proc Test Rehet/
Class Cat Size Type Type Posden Romt Freq tJumber Dnection Justifcaton Notes l Number Coor 340 D-7 2 AC 1 CK SA C FC Q 8A1 FF AP RI 87.15 Closed RJO-10 LJ OBJ 8 715 OM(10}-01 !
341 D-6 2 AC 1 CK SA C FC O 8A1 FF .
AP RI 8 7.1 5 Closed RJO-10 LJ OBJ 8 715 OM(10)41 l 4334 G-6 3 C 15 RL SA C RT 10Y 88263 C RT 10Y 81263 i 4345 B-5 3 C 1 RL SA 5010 G-5 3 C 1.5 R L. SA C RT 10V 81263 8.L1.1 Rev. 9 Page 70 of 236 i
TABLE INSERVICE VALVE TESTING PROGRAM ISI CLASS 1,2,3 AND NC VALVES PILGRIM NUCLEAR POWER STATION Pal & M231 SYSTEM FUEL POOL COOLING (19)
Valve P&lD .ISI Valve Valve Valve Actuator Normal Test Test - PNPS Proc., Test Rehef/ g Number Coor Class Cet Size Type Type Positum Rqmt Freq ' tJumber Derection Justification Notes 235 F-4 3 C 6 CK SA C FC Ri 81291 FF RJO47 AP RI 8 I 29 2 Closed RJOOT 245 E-7 3 C 6 CK SA C FC Rt 81291 FF RJO-07 A' RI 8I29 2 Closed RJO-07 8.1.1.1 Rev. 9 Page 71 of 236
TABLE INSERVICE VALVE TESTING PROGRAM IS1 CLASS 1. 2. 3 AND NC VALVES PILGRIM NUCLEAR POWER STATION P&lD: M232 SYSTEM RADWAGTE COLLECTION (20)
Valve P&lD ISI Valve Valve Valve Actuator Normal Test Test PNPS Proc. Test Relieft Class Cat S7e Type Type Positen Rqmt Freq Number Direction JustMcation Notes !;
Number Coor 7091A G-6 2 A 2 BL AO C FE O 8743.
O 8743
~
ST C FS O 8743 C PI 2Y 8715: Also 8130 LJ OBJ 8715 1, OM(10) 01 7011B G-6 2 A 2 BL AO C FE O 8743 ST O 8 7.4 3 C 4
FS O 8743 C Pt 2Y 8 7.1 5 Also 8 I 30 LJ OBJ 8715 OM(10)--01 Ii 7017A D-6 2 A 2 BL AO C FE O 8743 ST O 8743 C FS O 8743 C Pt 2Y 8 7 1.5 Also 8 I 30 LJ OBJ 8715 OM(10,-01 I, 7017B D-6 2 A 2 BL AO C FE O 8743 ST Q 8 7.4 3 C FS Q 8743 C Pl 2Y 8715 A!so B I 30 LJ OBJ 8715 OM(10) 01 I.
3.1.1.1 Rev. 9 -
Page 72 ef 236
TABLE INSERVICE VALVE TESTING PROGRAM -
1st CLASS 1. 2. 3 AND NC VALVES PILGRIM NUCLEAR POWER STATION P&lD: M239 SHEET 1 of 3 SYSTEM. POST-ACC! DENT SAMPLING & H2&O2 P&lD: M239 SHEET 2 of 3 ANALYZFR SYSTEM (5065)
Valve P&lD ISI Valve Valve Valve Actuator Normal Test Test PNPS Proc Test Relief /
Number Coor Class Cat Size Type Type Position Rqmt Freq Number Directron Justification Notes l 11A. 84 2 A 1 GL SO C FE O 87.41 (SH 1) ST Q 8 7.4 1 O/C RV-04 FS O 8 7.4.1 C Pt 2Y 8 7.1.5 Afsv 8130 .
LJ OBJ 8 7.15 OV(10) 01 8 138 B-3 2 A 1- GL SO O FE O 8.7.4 1 (SH 1) ST O 8 7.4 1 O/C RV-04 FS O 8741 C PI 2Y 8 7.1 5 Also 8130
' LJ OBJ 8 715 OM(10)-01 I 14A B-6 2 A 1 GL SO O FE O 8741 (SH 1) ST Q 8741 O/C RV-04 FS O 8 7.4 1 C Pt 2Y 8715 Also 8130 LJ OBJ 8 715 OM(10)-01 1 15B B-3 2 A 1 GL SO C FE O 87.41 (SH 1) ST O 8 7.4 1 O/C RV-04
'FS O 8741 C Pt 2Y 8715 Also 8 i 30 LJ OBJ 8 715 OM(10)-01 l 18A B-6 2 A 1 GL SO C FE O 8741 (SH 1) ST O 8741 O/C RV-04 FS O 8741 C Pt 2Y O713 Also 8 7 30 LJ OBJ 8715 OM(10)-01 I 208 B4 2 A 1 GL SO O FE O 8741 (SH 1) ST O 8741 O/C RV44 FS O 8741 C P1 2Y 8715 Also 8 f 30 LJ OBJ 8 715 OM(10) 01 I 8.1.1.1 Rev.9 Page 73 of 236
.J
- -. - ~- - % - - - - - - - - _ __
TABLE INSERVICE VALVE TESTING PROGRAM ISI CLASS 1. 2, 3 Ai4D NC VALVES PILGRIM NUCLEAR POWER STATION P&ID: M239 SHEET 1 of 3 SYSTEM. POST-ACCIDENT SAMPL!NG & H 2 & O2 ANALYZER SYSTEM (5065)
PalD. M239 SHEET 2 of 3 Test Reheft P&tD . ISI Valve Vatve ' alve Actuator Normal Test Test Pf 4PS Proc Valve -
Postten Rqmt Freq Number Direction Just!ficat.on Notes l Number Coor Class Cat Size Type Type 2 A GL - SO O FE O 87.41 21A B-6 1 o 874i O/C Rv44 ST (SH.1) FS O 8741 C P1 2Y 8715 Also 8130 LJ OBJ 8 715 OM(10) 01 l B-4 2 A 1- GL SO C FE O 8741 220 ~
ST O 8741 O/C RV44 (SH 1) FS O 8741 C PI 2Y 6715 Also 8130 LJ OBJ 8 715 Ou(10) 01 [
B-6 2 A 1 GL SO O FE O 8741 24A ST O 8 7.4 1 O!C HV44 (SH 1)
' FS O 8741 C Pt 2Y 8715 Also 8 I 30 -
I LJ OBJ B715 OM(10)_o1 B-4 2 A 1 GL SO C FE u 8741 25B ST O 8741 O/C RV-04 (SH 1) FS O 8741 C Pt 2Y 8715 Also 8130 LJ OBJ 8715 OM(10p01 l B4 2 A 1 GL SO C FE O 8741 26A ST Q 8 7 4.1 O/C RV4)4 (SH 1) FS O 8741 C Pl 2Y 8715 Also B i 30 1
LJ OBJ 8 715 OMi 101-01 B-3 2 A 1 GL SO C FE o 8T41 27B ST Q 8741 O/C RV 04 (SH 1) FS O 8741 C-Pt 2Y 8715 Aho 8130 :
1 LJ OBJ 8 715 OM(10) 01 8.1.1.1 Rev. 9 Page 74 Of 236
1 TABLE INSERVICE VALVE TESTING PROGRAM ISI CLASS 1,2. 3 AND NC VALVES PILGRIM NUCLEAR POWER STATION P&lD: M239 SHEET 1 of 3 SYSTEM POST-ACCIDENT SAMPLING & H 2 & O2' P&lD. M239 SHEET 2 of 3 ANALYZER SYSTEM (5065)
Valve P&iD ISI Valve Valve Valve Actuator Normal Test Test PNPS Proc. Test Reiseft Number Coor Class Cat Size Type Type Position Rqmt Freq Number Defection Justifwation Notes 31B C-4 -2 A 1 GL SO C .FE O 8 7.4 1
. (SH.1) ST Q 8741 O/C RV4)4 FS Q 8741 C PI 2Y 8 7.1_5 Also 8 f.30 LJ OBJ 8 715 OM(10Fot -
33A C-6 2 A 1 GL SO O FE O S 7.4.1 (SH.1) S7 O 8741 O/C - RV-04 FS O 8741 C PI 2Y 8 7.1 5 Also 8130 LJ OBJ 8 7.15 OM(10)41 350 C-4 2 A 1 GL. SO C FE O 87.41 (SH 1) ST Q 8741 O/C RV-04 FS O 874.1 C PI 2Y 8715 Aho 8 I 30 LJ OBJ ' 8 715 OM(10)-01 37A C-6 2 A 1 GL SO O FE Q 874.1 (SH 1) ST Q 8 7.4 1 O/C RV-04 FS O 8741 C PI 2Y 8 7.1 5 Also 8 I 30 LJ OBJ 8715 OM(10)-01 63 G-7 1 A 1 GL SO C FE O 8741 (SH 2) ST Q 8741 O/C RV 02 FS Q 8741 C PI 2Y 8715 Also h I 30 -
LJ OBJ 8 715 OM(10) 01 ' 6j 64 G-6 i A .1 GL SC C FE O 8741 >
(SH 2) ST Q 9741 O/C HV-04 FS O 8741 C P! 7Y &715 Also 81 ' '
LJ OBJ 8715 l; Ou(10) 01 "
65 G-6 2 B 1 GA~ SO C FE O 8741 (SH 2) ST Q 8 7.4 1 O RV-04 FS Q 874.1 C I Pt 2Y 8748
> f i
8.l.1.1 Rev. S [
i: age 75 oi236 7
TABLE INSERVICE VALVE TESTING PROGRAM
' ISI CLASS 1,2. 3 AND NC VALVES PILGRIM NUCLEAR POWER STATION P&lD: M239 SHEET 1 of 3 SYSTEM.. POST-ACCIDENT SAMPLtNG & H2 & O 2-P&iD: M239 SHEET 2 of 3 ANALYZER SYSTEM (5065)
Vtive P&lD ist Valve Valve Vaive Actuator Normal Test Test PNPS Proc. Test Rehef/
Number Coor Class Cat Size Type Type Position Rqmt freq Number Directon JustJ cateon~ Notes !
66 G4 2 B 1 GA SO C FE O 8741 (SH 2) ST O 8741 C RV-04 FS O 8741 C Pt 2Y 8748 67 E-6 2 B 1 GA SO C FE O 8 7.4 1 (SH.2) ST O 8 7.4 1 C RV-04 FS O 8741 C PI 2Y 8748 6a E-6 2 B 1 GA SO C FE O 8741 (SH 2) ST Q 8741 C RV-04 FS O 8741 C '
FI 2Y 8748 69 D4 2 B 1 GA SO C FE O 8741 (SM.2) ST O 8741 C RV-04 FS O 8 7 4.1 C PI 2Y 8748 70 D4 2 B 1 GA SO C FE O 8741 ;
(SH 2) ST O 8741 C RV-04
- FS O B741 C I
Pt 2Y 8748 '
71 F-6 2 A 1 GA SO C FE O 8741 (SH 2) ST O 8741 C RV44 FS O 8741 C Pt 2Y 8715 - Also 8130 1J OBJ 8 715 OM(10101 l 72 F4 2 A 1 GA SO C FE O 8741 (SH 2) ST Q 8741 C RV-04 FS O 8741 C Pl 2Y J715 Also 6130 LJ 09J 8715 OMt10) 01 k 8.1.1.1 Rev. 9 Page 76 of 236
<_ _ .. . m. _ . -,. _ __
TABLE INSERVICE VALVE TESTING PROGRAM ISI CLASS 1,2,3 AND NC VALVE 3 PILGRIM NUCLEAR POWER STATION P&lD. M239 SHEET 1 of 3 SYSTEM POST-ACCIDENT SAMPLING & H2&O2 PalD- M239 SHEET 2 of 3 ANALYZER SYST EM (5065)
Vdve P&lD ISI Valve Valve Valve Actuator Normal Test Test PNPS Proc. Test Relief / g, Number Coor Class ' Cat Size Type Type Position Rqmt Treg Number Direction Justrfecatum Notes il 73 C-6 .2 B 1 G-% So C FE O 8741 (SH 2) ST O 8741 C RV-04 FS O 8741 C Pt 2Y E748 74 C-6 2 B 1 GA SO C FE O 8741 -
(SH 2) ST O 8741 C RV44 FS O 8741 C Pt 2Y 8748 75 B-6 2 8 1 GA SO C FE O 8741 (SH 2) ST O 8741 C RV 04 FS O 8741 C Pt 2Y 8748 76 B4 2 B 1 GA SO C FE O -8741 (SH 2p ST Q 8741' C RV-04 FS O 8741 C Pl 2Y 8748 77 E-6 2 A 1 GA SO C FE. O 8741 (SH 2) ST O 87.41 C RV-04 FS O 8741 C Pt 2) 8 7.1 5 Also 8130 LJ 003 8715 OM(10F01 78 E-6 2 A 1 GA SO C FE O 8741 (SH 2) ST Q 8741 C RV-04 FS O 8 7 4.1 C Pt 2Y 8 7 1.5 Also 8 I 30 LJ OBJ 8715 OM(10) ,1 1
1 8.1.1.1 Rev.9 Page 77 of 236 >
t
l TABLE INSERVICE VALVE TESTING PROGRAM ISI CLASS 1. 2. 3 AND NC VALVES PILGRIM NUCLEAR POWER STATION .
Pa!D M239 SHEET 1 of 3 SYSTEM. POST-ACCIDENT SAMPLING & H 2 & O2 P&lD: M239 SHEET 2 of 3 ANALYZER SYSTEM (5065)
Valve PalD ISI Valve Valve Valve Actuater Normal Test Test PNPS Proc. Test Relieft l Class Cat Size Type Type Pos: tion Rqmt Freg Number Direction Justification Netes I Number Coor -
79 D4 2 B 1 GA SO C FE. O 8741 ST O 8 7.4 1 C RV-04 (SH 2) FS O 8741 C Pt 2Y 8748 80 D-6 2 0 1 GA SO C FE O 8741 ST Q 8741 C RV-04 (SH 2) FS O 8741 C Pt 2Y 8748 81 C4 2 B 1 GA SO C FE O 8741 ST O 8741 C RV-04 (SH 2) FS O 8741 C Pi 2Y 8748 C4 2 8 1. GA SO C FE O 8741 82 O 8/41 C RV-04 ST (SH 2) FS O 8741 C Pt 2Y 8748 83 F-6 2 B 1 GA SO C FE O 8741 ST Q 8741 C RV 04 (SH 2) FS O 8741 C PI 2Y 8748 84 F4 2 B i GA SO C FE C 8741 ST O 8741 C RV 04 (SH.2) FS O 8741 C PI 2Y 8748 85 G4 1 A 1 GA SO C FE O 8741 ST O a741 O/C RV04 (SH 2) FS O B741 C Pt 2Y 8715 Also B l 30 LJ OBJ 8715 OM(10)-01 l 86 G4 1 A 1 GA SO C FE O 8741 ST O 8741 O/C RV-04 (SH 2) FS O 8'41 C PI 2Y 8715 Also 81.30 LJ OBJ 8715 OM(10)-01 l 8.1.1.1 Rev. 9 Page 78 of 236 m-
e
~
TABLE INSERVICE VALVE TESTING PROGRAM ISI CLASS 1. 2,3 AND NC VALVES PILGRIM NUCLEAR POWER STATICN PalD.' M239 SHEET 1 of 3 SYSTEM POST-ACCIDENT SiMPLitJG & H2 & O2 P&lD: M239 SHEET 2 of 3 ANALYZER SYSTEM (5065)
Vdve P&lD ISI Vatve Valve Valve Actuator Normal Test Test PNPS Proc Test Relieu [
Number Coor Class Cat Size Type Type Position Rqmt Freq Number Derection Justification Notes 1 87 D-4 2 8 1 GL AO- O FE O 8 7.4 1 (SH.i) ST O 8741 C RV-04 FS O 8741 C PI 2Y 8748 88 D4 2 B 1 GL AO O FE O 8741 (SH.1) ST O 87.41. C RV-04 FS O 8741 C Pl 2Y 8748 -
89 D-7 2 0 1 GL AO O FE O 8741 (SH.1) ST O 8741 C RV-04 FS O 8741 C Pt 2Y 8748 90 D4 2 B 1 GL AO O FE O 8741 (SH 1) ST O 8741 C - RV-04 !
FS O 8741 C Pt 2Y 8748 91 A-5 2 A 1 GA AO O FE O 8741 (SH.1) ST Q 8741 C RV-04 FS O 8741 C Pt 2Y 8715 Also 8130 LJ OBJ 8715 92 A-5 2 A 1 GA AO O FE O 8741 OM(10) 01 l{'
(SH 1) ST O 8741 C RV 04 FS O 8741 C '
PI 2Y S715 Also o l 30 LJ OBJ 8715 OM(10) 01 l 122A C-8 2 B 375 GA SV O FE O ti741 ,
(SH 1) ST O 8741 O RV 04 :
FS O 8741 C PI 2Y 8748 1228 C-1 2 8 375 GA SV C FE O 87.41 ,
(SH 1) ST O 8 7.g 1 O RV-04 FS O 8741 C PS 2Y 8748 _ _
l 8.1.1.1 Rev.9 Page 79 of 236
TABLE I INSERVICE VALVE TESTING PROGRAM ISI CLASS 1,2. J AND NC VALVES l PILGRIM NUCLEAR POWER STATION P&lD: M239 SHEET 1 of 3 SYSTEM' POST ACCIDEf4T SAMPLING & H2 & O2 P83D: M239 SHEET 2 of 3 ANALYZER SYSTEM (5065)
Va!ve Vatve Valve Actuator Normal Test Test PNPS Proc _ Test Relief / g Valve P&lD ISI Justification Notes Coor Class Cat Size Type Type Posrtion Rqmt Freg Numbar Direction Number 123A C-8 2 8 .375 GA SV C FE O 8741 ST Q 8741 O RV-04 (SH 1) FS O 87.41 C Pt 2Y 8748 C-1 2 B .375 GA SV C FE O 8 7.4 1 1239 O RV-04 ST O 8 7.4 1 (SH 1) FS O 874.1 C Pt 2Y 8748 124A C-7 2 B .375 GA SV C FE O 8741 ST O 8 7.4 1 O RV-04 (SH.1) FS O 8 7 4.1 C PI 2Y 8748 1248 C-2 2 B .375 GA SV C FE O 8741 ST O 8741 O RV-04 (SH 1) FS O 874.1 C i
Pt 2Y 8748 8 .375 GA SV C FE O 8 M 3-13 Also 8 M 3-14
% 5117A H4 2 O RV-04 Also 8 M 3-14 ST O 8 M 3-13 (SH 1) FS O 8 M 3-13 C Also 8 M 3-14
.2 8 .375 GA SV C FE O 8 M 3-13 Also 8 M 3-14 51178 H-3 ST O 8 M 3-13 O RV-04 Also 8 M 3-14 (SH 1) FS O 8 M 3-13 C Also 8 M 314 375 GA SV C FE O 8 M 3-13 Also 8 M 2-14 5137A G4 2 B 0 RV-04 Also 8 M 3-14 ST O 8 M 3-13 (SH 1) FS O 8 M 3-13 C Also 8 M 3-14 8 .375 GA SV C FE O 8 M 3-13 Also 8 M 3-14 51378 G-3 2 ST O 8 M 3-13 O RV-04 Also 8 M 3-14 (SH.1) FS O 8 M 3-13 C A!so 8 M 3-14 8.!.1.1 Rev.9 Page 80 of 236
TABLE <
- INSERVICE VALVE TESTING PROGRAM . '
ISI CLASS 1. 2. 3 AND NC VALVES PILGRIM NUCLEAR POWER STATION P&lD: ' M241 SHEET 1 of 2 SYSTEM RESIDUAL HEAT REMOVAL SYSTEM (1001) 7 P&lD: M241 SHEET 2 of 2 '
Velve PalD .. ISI - Valve - Valve Valve Actuator Normal Test Test PNPS Proc. Test Reheft Number - Coor ' Class Cat - Srze = Type : Type Posthon Romt Freg Number Direction Justifcation Notes l" 2A D-6 2- AC .2 CK -SA C PC O 85221 FF -
' (SH 2)
FC~ Rt 8I37 -FF RJO-08 NIT /Dessassemble AP- O 85221 Closeo LJW OBJ 8 712 Of 9(10}41 2B D-3 2 AC .. 2 CK SA C. PC- O 8 5 2 2_1 FF (SH.2) FC " RI 8327- FF RV-27 Dessassemble'
[.
AP O -85221 Closed LJW OBJ B 7.12 OM(10}-01 s 2C G-6 . 2 AC 2 CK. SA C PC O 8 5 2.2 1 FF (SH 2) . FC RI 8837 FF RJO-08 NIT /Dessassemble AP O 8 5 2.2.1 ' Closed LJW OBJ 8712 OM(10)41 2D G-3 2 AC 2 CK SA C PC- O e 5 2 2.1 FF
' (SH 2) '.
FC RI 8127 FF RV-27 - Dessassemble AP . O.85221 Closed LJW OBJ 8 712 OM(10) 01 l 7A 3-5 2 A 18 GA MO O FE O 8 5 2.3 (SH 2) 'ST O 8 5 2.3 O/C PI 2Y 8523 LJW OBJ 8 712 OM(10)-01 l 78 D-4 2 .A 18 GA MO O FE O .8523 ST .O 8523 O/C (SH2) ' Pt 2Y - 8 5 2.3 -
LJW OBJ 8712 OM(10)-01 l-7C F-5 2 A 18 GA MO O FE O 8523 ST. O 8523 O/C (SH 2) 8523 PI 2Y LJW OBJ 8 712 OM(10).01 ' l'.
7D F-4 2 A 18 GA MO O FE O-~8523 ST O 8523 O/C (SH 2)
PI 2Y- 8 5 2.3 :
'L LJN OBJ 8 712 OM(10)-01 8.l.1.1 Rev.- 9
- Page 81 of 236 :
=. ._ -_-
.m. _. _ . _
b TABLE INSERVICE VALVE TESTING PROGRAM -
ISI CLASS 1,2. 3 AND NC VALVES PILGRIM NUCLEAR POWER STATION PalD: M241 SHEET 1 of 2 SYSTEM. RESIDUAL HEAT REMOVAL SYSTEM (1001)
PalD M241 SHEET 2 of 2 Talve P&lD ISI Valve Valve Valve Actuator Normal Test Test PNPS Proc Test Relief /
Number Coor Class Cat Seze Type Type Posrtion Rqmt Freq Number Directron Justification Notes l ;,
16A F-7 2 B 18 GL Mo C FE O 8523 +
(SH 2) ST O 8523 O/C PI 2Y 8523 168 E-2 2 B 18 GL MO C FE O 8523 (SH 2) S1 O 8523 O/C Pt 2Y 8523 18A G-6 2 B 3 GA MO O FE O 8523 (SH 2) ST Q 8523 O/C Pi- 2Y 8523 ;
188 G-3 2 B 3 GA MO O FE O 8523 (SH 2) ST Q P523 O/C Pl 2Y 8523 s 19 B-7 2 8 18 GA MO O FE O 8523 (SH.1) ST Q 8523 C PI 2Y 8523 21 6-3 2 A 4 GA MO C FE O 8523 (SH 1) ST O 8523 C ;
Pt 2Y 85211 Also 8130 +
LX 2Y 85211 22A F-8 2 AC 1 RL SA C RT 10Y 81263 (SH 1) LX NA 8 I "iB 3 RT Verifies 228 F-2 2 AC 1 RL SA C RT 10Y 81263 (SH 1) LX NA 81263 RT Verifms 23A G-6 2 A 10 GA MO C FE O 8523 (SH 1) ST Q 8523 O/C PI 2Y 8715 Also 8130 LJ OBJ__8 715 031031 l 238 G-4 2 A 10 GA MO C FE O 8523 (SH 1) ST O 8523 O/C PI 2Y 8715 Also S I 30 LJ OBJ 8715 OM(10) 01 l 8.l.1.1 Rev.9 Page 82 of 236
TABLE INSERVICE VALVE TESTING PROGRAM ISI CLASS 1,2,3 AND NC VALVES PILGRIM NUCLEAR POWER STATION P&fD. 84241 SHEET 1 of 2 SYSTEM RESIDUAL HEAT REMOVAL SYSTEM (1001)
P&tD M241 SHEET 2 of 2 V4Jve P&lD ISI Valve Valve Valve Actuator fJormal Test Test PNPS Proc. Test Reheft Class Cat Size Type Type Position Rqmt Freq fJumt>ef Direct:on Justificahon Notes l Number Coor 26A G-5 2 A 10 GA MO C FE O 8523 (SH 1) ST O 8523 O/C Pl 2Y 8 7.1 5 Also 8130 LJ OBJ 8715 OM(10) 01 1 268 G-4 2 A 10 GA MO C FE Q 8523 ST Q B 52. 3 O/C (SH 1) 2Y PI 87.15 Also 8 I 30 LJ OBJ 8715 OM(10) 01 l 28A F-6 2 A 18 GL MO O FE O 8523 (SH 1) ST Q 8523 O/C Pt 2Y 8715 Also 8130 LJ OBJ 8715 OM(10) 01 l
_ _ _28B F-4 2 A 18 GL MO O FE O 8523 (SH 1) ST O 8523 O/C P1 2Y 8 7.1 5 Also 8130 LJ OBJ 8715 OM(10) 01 T9A E-6 1 A 18 GA MO C FE CS 8111.3 CS-09 (SH 1) ST CS 81113 O/C CS 09 PI 2Y 8527 Also 8 4 30 LJ OBJ 8715 OM(10) 01 LP 2Y 852/
298 d-4 1 A 18 GA MO C FE CS 81114 CS-09 (SH 1) Si CS 81114 O/C CS-09 PI 2Y 6527 Also 8 4 30 LJ OBJ 8715 OfA(10) 01 LP 2Y 8527 32 B-3 2 A 4 GA MO C FE O ~B523 (SH 1) ST Q 8523 C P1 2Y 85211 Also 8130 LX 2Y 85211 33A E-6 1 f1A 18 GA MA LO NA tJA tJA Exempt (Manuai)
(SH 1) P1 2Y 8527 Also 8 I 30 338 E-4 1 NA 18 GA MA LO fJA f4A tJA Exempt (Manual)
(SH 1) Pt 2Y 8527 Also 8130
- 8. I.1.1 Rev.9 Page 83 of 236
m . .
1 TABLE INSERVICE VALVE TESTING PROGRAM ISI CULSS 1. 2. 3 AND NC VALVES PtLGRIM NUCLEAR POWER STATION P&tD; M241 SHEET 1 of 2 SYSTEM RESOUAL HEAT REMOVAL SYSTEM (1001)
Pa!O M241 SHEET 2 of 2 4
Valve P&lD ISI Vane Vatve Vane Actuator f4orrnal Test Test Pf 4PS Proc. Test Rei.eff Numbar ' Coor Class Cat See Type Type Postten Rymt Fen thumber Dwecten Justifica wm fm 34A F-7 2 A 12 GA MO C FE O 85;'3 (SH 1) ST O 8523 O/C I Pt 2Y 8715 A4o 8 I 30
. LJ OBJ 8 715 0c(10) c1 34A (PSV) F-7 2 AC 2 RL SA C RT 10( 88263 (SH.1) LX NA 31263 RT Ver fies 348 F-3 2 A 12 GA MO C FE O 8523 (SH 1) ST Q 8523, OC PI 2Y 8715' Alse 8130 LJ OBJ 8 715 0 0(10)01
! 34B (PSV) F-3 2 AC 2 RL SA C RT 10t 81263 l
(SH 1) LX NA B I 26 3 RT Ve<Aes 36A E-T 2 B 12 GL MO C FE O 8523 (SH 1) ST Q 8523 OtC P1 2/ 8523 2
36B E-3 2 B 12 GL MO C FE O 8523 (SH 1) ST O 8523 O/C Pt 2Y 8523 37A E-7 2 A 6 GL MO C FE O 8523
, (SH 1) ST O 8523 O/C Pt 2Y 8715 Ago a 30 LJ OBJ 8715 CU(10) O t 378 E-3 2 A 6 CL MO C FE O 8523 I
(SH 1) ST O 8523 OC 4 PI 2Y 8715 Also 8 f 30 j
LJ OBJ 8715 0 0110) 01 l
I
.i I
8.I.1.1 Rev. 9 l Page 84 of 236
. - . ~. . ~ - - . - . . .- . .. . . - _ ~ _ . - _ -. .-. .
TABLE INSERVICE VALVE TESTING PROGRAM ISI CLASS 1. 2. 3 AND NC VALVES P!LGRIM NUCLEAR POWER STATION
- PalD:. M241 SHEET 1 of 2 SYSTEM RESOUAL HEAT REMOVAL SYSTEM (1001)
P&fD M241 SHEET 2 of 2 _.;
Valve P&lD 'St Vatve Vatve Ve:ve Actuator tbrrnal Test Test Fiv S Proc Test Rebef/
Number Coor Class Cat Sea Type Type Posden Rqmt Freq Number Drection JuMdwation Notes I=
43A E-5 2 0 18 GA MO O FE O 8523 ST O 8523 0
(~SH 2)
P3 2Y 6523 438 E4 2 8 18 GA MO O FE O 8'523 (SH 2) ST O 8523 O Pt 2Y 8523 43C G-5 2 8 18 GA MO O FE O 8523
. ST O 8523 O (SH.2) Pt 2Y 8523 43D CA 2 8 18 GA MO O FE O 8523 ST O 8523 O (SH 2) PI 2Y 8523 44 C-5 2 AC 15 RL SA C RT 10Y 84263 LX NA 8126 3 Rt ve,ric (SH 1)
G7 C-5 1 A 20 GA MO C FE CS 8 e 115 CS-02 ST CS 84115 C CS-02 (SH 1) PI 2Y 8528 m3 8 t 33 LJ OBJ B 715 O g10)01 I LP 2Y 8528 50 D-5 1 A 20 GA MO C FE CS 8 t 115 CS-02 ST CS 8 I 11 5 C CS-02 (SH 1) PI 2Y 8528 Also 8 i ?O LJ OBJ 8715 CM(10) 01 l LP 2Y 8528 i
8.l.1.1 Rev. 9 Page 65 of 236
TABLE INSERVICE VALVE TESTING PROGRAM ISI CLASS 1,2. 3 AND NC VALVES PILGRIM NUCLEAR POWER STATION 4 PilD: M241 SHEET 1 of 2 SYSTEM RESIDUAL HEAT REMOVAL SYSTFM (1001)
P'"ID: M241 SHEET 2 of 2 Vatve P&lD ISI Vane Valve Vahre Actuator teormW Test Test Pf4PS Prx . Test Reet/
Numtw Coor Class Cat Stre Type Type Pos.'>on Pqmt Freq Number Directm Just& ate NMes l 67A D4 2' C 12 CK SA C FC Q 85221 FF (SH 2) AP O 85221- Closed 678 D-3 2 C 12 CK SA C FC O 85222 FF (SH 2) AP Q 85222 Clesed 67C F-7 2 C 12 . CK SA C FC Q 85221 FF (SH 2) AP O 85221 Ckned 67D F-3 2 C 12 CK SA C FC O 85222 FF (SH2) _
AP Q 85222 Closed i 68A E4 1 AC 18 CM SA C FC CS 811117 FF Hv41 Sys:em F paw j (SH 1) FC R1 8 I 34 FF RV41 Diagnostre it.7T)
AP 2Y 8527 Closed RV-37 i LP 2Y 8527 68B Ed 1 AC 18 CK SA C FC CS 811117 FF RV41 System F tow (SH.1) FC RI 8134 FF RV41 Diagnoste (f.1T)
AP 2Y 8527 Closed RV 37 LP 2Y 8527 ~~
1 25 F-2 2 AC 2 CK SA C FC Q 8523 FF (SH2) AP 2Y 85213 Closed RV-37 LX 2Y 85213 8.1.1.1 Rev.9 Page 86 of 236
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TABLE INSERVICE VALVE TESTING PROGRAM ISI CLASS 1. 2. 3 AND PJC VALVES P!LGRIM fJUCLEAR POWER STATIOtJ
' P&lD M242 SYSTEM CORE SPRAY SYSTEM (1400)
P&lD IS! Valve Valve Valve Actuator flormal Test Test Pr#$ Proc. Test Rewff Valve tiotes Coor Class Cat Srze Type Type Positen Rqmt Freg flumber Dwectton JusMcam>n Number pass,ve 24 F-8 2 A 12 GA .HO C FE f4A t4A 15 2V 8518 2 A .12 GA HO C FE t4A FAA Passnre 28 H-9 LX 2Y 8518 3A F-7 2 A 48 GA MO O FE O 8513 ST Q 8513 C Pt 2Y 8513 LN/ 0638712 09.tt10FC1 38 F4 2 A 18 GA MO O FE O 8513 ST O 8 5 1.3 C Pt 2Y 8513 LX/ OBJ 8712 00{ t0) 01 4A C-6 2 B 6 GA MO C FE O 8511 ST O 8511 C Pt 2Y 8511 Also 8130 48 C-6 2 0 6 GA MO C FE G 8511 ST O 8511 C Pt 2Y 8511 Atsn 6130 NA 10 GA MA LO f4A FAA f4A E sempt (Vanual) 6A C-3 1 PI 2V 8516 Aly) M t 30 10 GA MA LO F4A FAA FAA E =*mpt (Manual) 68 C-3 1 PJA Pt 2Y 8516 Aho 8130 AC 10 CK SA C FC Rf 8815 FF RV-06 9A D-3 1 AP 2Y 8516 Closed RV-37 LP 2Y 8516 AC 10 CK SA C FC Rt 8115 FF RV 05 90 B-3 1 AP 2Y 8516 Closed RV-37 LP 2Y 8516 13A. E-7 2 C 3 SC SA *LOIC PC O~iift1 FF FC R! 8837 FF RV27 T41T#Desassemble AP Rt a137 Closed RV 27 tert /Desassemble 138 E-9 2 C 3 SC SA *LOIC PC O 8511 FF FC Rt 8137 FF RV-27 NIT / Disassemble AP RI 8I37 Closed RV-27 NtT!Desassemb*e _
- Stop Check Valve Handwheel posrbon - Locked Open normal drse postbon - Closed 8 I.1.1 Rev. 9 Page 88 of 236
TABLE INSERVCE VALVE TESTING PROGRAM ist CLASS 1. 2,3 AND NC VALVES PILGRIM PEJCLEAR POWER STAT!ON P&fD' M242 SYSTEM CORE SPRAY SYSTEM (1400)
Vaive P&tD ist Vahre Vatve Vatve Actuator Normal Test Test PNPS Proc. Test Rebett g Number Coor Class Cat Stre Type Type Posrtion Rqmt Freg Number Dwecten Jushncatxm Notes 24A D-5 2 A 10 GA MO O FE O 85t3 ST Q 8513 O/C Pt 2Y 8 7 1.5 Also 8 ! 30 LJ OBJ 8 715 OM[10101 I 248 B-5 2 A 10 GA MO O FE u 8513 ST O 8513 O/C PI 2Y 8 7.1 5 Aho 8 I 30 LJ OBJ 8 715 OMf1C) 01 I 25A D-4 1 A 10 GA MO C FE CS 811111 CS-03 ST CS 811111 O/C CS-09 Pt 2Y 8516 Arso 8 3 30 LI OBJ 8 715 OM(10F 01 l LP 2Y 8516 25B B.4 1 A 10 GA MO C FE CS 811111 CS4r>
ST CS 881111 O/C CS-09 Pt 2Y 8516 A:so 8 8 30 LJ OBJ 8 715 OM(10) 01 l LP- 2Y 8516 28A E-6 2 AC 2 RL SA C RT 10Y 81263 LX NA 8 f 26 3 R T V-ftes 28D B-7 2 AC 2 RL SA C RT 10Y B B 26 3 LX NA 81263 RT Varfm 31A C-4 1 AC 1 CK SA O FC RI B M 3-2 RF RV-22 AP RI 8 M 3-2 Ops n RV-22 LX RI J M 3-2 RV-72 318 C-4 1 AC 1 CK SA O FC R1 8 M 3-2 RF R v-22 AP R1 8 M 3-2 Open Hv.22 LX RI 8 M 3-2 RV 22 35 E-5 2 AC 6 CK SA C FC O 9511 FF AP R1 8712 Closed RJO to Aho 3 M 4-112 {
8.1.1.1 Rev. 9 Page 89 of 236
TABLE INSERVICE VALVE TESTING PROGRAM ist CLASS 1. 2. 3 AND NC VALVES P!LGRtM NUCLEAR POWER STATION P&tD- M242 .
SYSTEM CORE SPRAY SYSTEM (1400)
Valve P&tD 158 Vatve Valve Vatve Actuator Normat Test Test PNPS Proc Test hem /
Number Coor Class Cat See- Type Type Posthon Rqmt Freq Number Derect:en Justificatwm
. Notes 36A E-7 2 C 10 CA SA C FC Q 8511 FF AP Q 8511 Closed 368 E.9 2 C 10 CK SA C FC O 8511 FF AP Q 8511 Closed 212A D-7 2 AC 2 CK SA C FC O 8 5 1.1 FF AP 2Y 8 5 1.7 Closed RV-37 LX 2Y 8517 B-7 2 AC 2 CK SA C FC Q 8511 FF i 2128 AP 2Y 8517 Closed RV-37 !
LX 2Y 8517 l"
, 214 E-5 2 AC 6 CK SA AC FC O 8511 FF AP R1 8712 Closed R.O 10 ANo 3 M 4112 4
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4 4 8. I.1.1 Rev.9 l Page 90 of 236 l
. _ _ _ - ~ _ . . - - _ . . - . _ .
TABLE INSERVICE VALVE TESTitJG PROGRAM ISI CLASS 1,2. 3 AND NC VALVES PILGRIM NUCLEAR POVER STATION P&ID M243 SHEET 1 SYSTEM H1GH PRESSURE COOLANT INJECTION (2301)
P&lD- M244 SHEET 2 P&tD ISI Vatve Valve Vatve Actuator Normat Test Test PNPS Proc. Tes: Reetj 11atve See Type Type Posrbon Rqmt Freq fJumber Ocectron Just:teatne tu-s !
Number Coor Class Cat 2301-23 E-11 2 B 10 GA HO C FE 0: 8544 ST Q- 8544 0,0 (HO-9) (SH 2)
FS Q 8544 C PI 2Y 8544 2301-24 E-11 2 NA 10 GV HO C Pt 2Y 8544 Esempt - Skd Mounted Contrei Vapwe (HO-2) (SH 2)
Also 8 t 30 3 F-13 2 0 10 GA MO C FE O 8541 Ano 8 5 4 4 (SH 1) ST Q 8541 O A: sob 544 Pt 2Y 8544 4 DJ 1 A 10 GA MO O FE O 8544 (SH 1) ST Q 8544 O/C Pt 2Y 8715 A'so 8 30 LJ OBJ 8715 OM(to) 01 l 5 D4 1 A 10 GA MO O FE O 8544 (SH 1) ST Q 8544 O/C PI 2Y 8715 A;so a 30 LJ OBJ 8 715 CM(10F01 GA MO O FE O 8544 l
6 C-10 2 8 16 (SH 1) ST Q 8544 O/C Pt 2Y 8544 7 H-5 1 AC 14 CK SA C FC CS 8 I 11 7 FF CS04 (SH.1) AP 2Y 81117 Closed CS44 LP 2Y -8548 8 H-5 1 A 14 GA MO C FE CS 811111 CS O's (SH 1) ST CS B t 11 11 O/C CGO')
Pt 2Y e548 Also 8 i 30 g LJ 003 8715 O*.'t 10101 s (P 2 8548 9 H4 2 B 14 GA MO O Pt 2Y 881111 Pan:ve (SH 17 Also 8 8 30 8.1.1.1 Rev. 9 Page 91 of 236
TABLE INSERVICE VALVE TESTING PROGRAM ESI CLASS 1,2,3 AND NC VALVES PILGRIM NUCLEAR POVER STATION P2fD: M243 SHEET 1 SYSTEM HIGH PRESSURE COctArn IPUECTION (2301)
P&lD' M244 SHEET 2 Valve P&lD ISI Vatve Vatve Valve Actuator Normal Test Test F ' #S Proc Test Rehet/
Number Coor Class Cat See Type Type Postten Rqmt Freq Number Dwetton JustificN ??otas l 10 E-6 2 8 10 GL MO C FE O 8544 (SH 1) ST O 8544 C Pi 2Y 8544 14 F-8 2 B 4 GL MO C FE O 8544 (SH.1) ST O 8544 O/C P1 2Y 8544 15 D-7 NC B 10 GA MO C FE O 8544 (SH1) ST O 8544 C Pt 2Y 8544 20 D-10 2 AC 16 CK SA C FC O 8541 FF (SH 1) AP 2Y 85411 Closed RV-37 LX 2Y 85411 23 D-8 2 AC 1 RL SA C RT 10Y 8.! 26 3 (SH 2) LX f4A 88263 RTV-cie 26 E-5 1 .AC 1 SK SA O FC RI 8 M 3-2 RF H v.22 (SH 1) AP R1 8 M 3-2 Open RV.22 LX RI 8 M 3-2 RV.22 29 K-14 2 8 1 GL AO O FE O 8544 (SH.1) ST O 8544 C FS O 8544 C Pt 2Y 8544 33 M-1 2 A 4 GA MO O FE O 8544 (SH.1) ST O 8544 C PI 2Y 8715 Also e 130 LJ OBJ 8 7.15 OM(10F01 I 34 B-8 2 A 4 GA MO O FE O 8544 (SH 1) ST O 8544 C Pt 2Y 8715 Also 8130 LJ ORJ 8715 O W10}C1 l 34 C-6 2 C 2 CK SA C PC O e541 FF (SH 1) FC R1 8I27 FF RV-2 7 Drsassemt>!e AP PI 8712 Closed RJO-10 I 8.I.1.1 Rev. 9 Page 92 of 236
TABLE INSERVICE VALVE TESTING PROGRAM ISI CLASS 1. 2. 3 AND NC VALVES PILGRIM NUCLEAR POWER STATION P&tD- M243 SHEET 1 SYSTEM HIGH PRESSU9E COOLANT INJECTION (2301)
(P&fD: M244 SHEET 2 iSi Vatve Valve Valve Actuator tJormal Test f est Pf4PS Proc Test Ret eft Vatve P&lD Coor Class Cat Size Type Type Posnion Rgmt Freg Namber Drrection Justif.catu m Nrytes Number E-9 2 B 16 GA MO C FE O 8544 35 O/C ST O 8544 (SH 1) Pt 2Y 8544 ~
M-5 2 A 16 GA MO C FE- U 8544 36 ST O 8544 O/C (SH 1) PI 2Y 8544 LJW OBJ 8712 Ot.*t 10) 01 l
M4 2 C 16 CK SA C FC RI 8I27 FF RV 27 Disassemble 39 RV-27 (SH 1)
AP R1 8827 Closed Disawbie 40 K-5 2 AC 4 CK SA C PC O 8541 FF FC RI 8137 FF RJO 09 t;tT.Thsassemble (SH 1) AP RI 8712 RJn 10 Also 3 M 4-112 LJW OBJ 8712 OP.41oj ct AC 20 CK SA C FC O 8541 FF 45 J-4 2 AP R1 8715 Closed RJO-10 t (SH 1) LJ OBJ 8 715 OMt 10) 01 l 53 J-10 3 AC 1 RL SA C RT 10Y 88263 LX PIA 88263 RT Vent:es (SH 2)
L-9 3 B 1 GA AO C FE O 854158544 A:so 8 81127 64 O 8541&8544 O/C CS-19 AJsn 8 8112Y ST (SH 2) FS O 8541&8544 C Also 811127 Pt 2Y 8544 Also S I 30 16 RD SA C RD SY 81265 N%Testadie OQ K-11 2 D Rs, %ce (SH 1) taon Testable K-12 NC D 16 RD SA C RD SV B 126 5 69 R+pt.v e -
(SH i n AC 20 SC SA **LO/C FC O 8541 FF 74 J-3 2 RJO-10 AP H1 a715 C:esed l (SH 1) LJ Oiti 8715 Cd410001 C 4 CK SA C FC O 8541 FF 75 K-8 2 AP NA NA Closed (SH 2) FF 76 L-8 2 C 2 CK SA C PC O 8541 FC R1 85410* FF RJO-04 (SH 2) AP Q 8131 Closed
- Stop Check Vafve. Handwheel positum - Locked Open. normal drse posdion - Closed 8 I 1.1 Rev. 9 Page 93 of 236
TABLE INSERVICE VALVE TESTING PROGRAM ISI CLASS 1,2. 3 fMD NC VALVES PILGRIM NUCLEAR POWER STATION SYSTEM HIGH PRESSURE COOLANT INJECTION (2301)
P&lD: M243 SHEET 1 PalD M244 SHEET 2 Test PNPS Proc. Test Retiet/
Vane Vane Vahre Actuator Nor tal Test Vane P&lD IS!
Stre Type Type Postbon Rqmt Freq Number Directw>n Jus %cahon Nm l Number Coor Class Cat K-4 2 AC 2 CK 'SA C PC O 6541 iF 217 FC RI 8827 FF RV-27 D.sassemble (SH 1) AP RI 8712 Closed RJO 10 LJW OBJ 8 712 Outto) of AC CK SA C FC RI 65413 FF RJO{r$
218 J-3 2 1 AP RI 8715 Closed RJO-10 (SH 1) LJ OBJ 8715 OM(10)-01 AC 1 SK SA O FC RI 8 M 3-2 RF RV-22 220 F-5 1 RI 8 M 3-2 Open RV-22 AP (SH 1) LX RI 8 M 3-2 RV_72 C 3 CK SA C FC RI 85414* FF RJO-W 232 M-1 2 Closed RJO-06 AP R$ 85414*
(SH 1) RI 85414* FF RJO-06 M-1 2 C 3 CK SA C FC 233 AP RI 85414* Closed RJO46 (SH 1) O 8544 2 A GL SO C FE 9068A J-2 1 O 8544 C ST (SH.1) FS O 8544 C Pt 2Y 8544 LJ OBJ 8715 OM(10) et I J-2 2 A 1 GL SO C FE O 8544 D688 ST Q 8544 C (SH 1) FS. O 8544 C PI 2Y 8544 I LJ OB_J_8 715 Ovi10101 -
K-10 2 0 1 GL AO C FE O e544 9312 ST O 8544 C (SH 1) FS O 8544 C Pt 2f 8544 9313 K-10 2 8 1 GL AO C FE O 8544 ST O 8544 C (SH 1) FS O 8544 C Pt 2Y 8544 8 11.1 Rev. 9 Page 94 of 236 l
u _ . .. ..
. ._m.. _ . - ._ . _ . _ . ~ _ . . - - _ - . . _ _ _ - . _ _ _ . m _.m..-_-__ _ .- _ _ _ . . . - -
7 _._- - _
4 F
f TABLE i INSERVICE VALVE TESTING PROGRAM ist CtASS 1. 2. 3 AND NC VALVES PILGRIM NUCLEAR POWER STATION P&lD: M245 SHEET 1 SYSTEM REACTOR CORE COOLING SYSTEM (1301) i P&iD M246 SHEET 2 l Malve P&tD 151 Vatve Valve Vahre Actuator tJormat Test Test PfFS Proc. Test Resett Number Coor Class Cat - See Type Type Poution Rqmt Fm Numeer Derecton Jmtd.cate mtes 1 E-12 2 B 2 GA SO O FE O 8551 ,
(SH 2) ST O 8551 C RV (4 FS O 8551 C Closed i Pt 2Y 8551 Also 8130 ;
3 E-11 2 0 2 GV HO O PI 2Y 8551 Exempt - Sud i
. (HYD-159) (SH 2) Mounted Control !
Vane A!so 8 I 30 ,
9 E-10 2 D 8 RD SA C RD 5( 88265 t4on-Testatne l 3 (SH 2) Reptare (
10 D-10 f4C D 8 RD SA C RD 5Y 8826 5 N:m imm l (Sri 2) F ,ptace ,
i 92 L-7 3 B 1 GL AO C FE O 8554 :
1 (SH 2) ST Q 8554 C [
FS O 8554 C !
Pt 2Y 8554 j 15A B4 1 AC 1 SK SA O FC PI 8M32 RF 14V-22 l (SH 1) AP RI 8M32 Open RV 22 !
LX RI 8 M 3-2 RV-22 158 B-6 1 AC 1 SK SA O FC HI 8 M 3-2 RF H V-22 !
(SH 1) AP R1 8 M 3-2 Open RV-22 LX R1 8 M 3-2 RV-22 16 C-6 1 A 3 GA MO O FE O 8554 (SH.1) ST O 8554 OC Pt 2Y 8715 Arso a a 3c LJ ORf 8715 Of410)01 17 C7 1 A 3. GA MO O FE O 8554 (SH 1) ST O 8554 Orc -
Pt 2) 671i Also 8130 [
LJ 00.3 6715 OM(to) et i
i t
8l.1.1 Rev. 9 Page 95 of 236 l
TABLE INSERVICE VALVE TESTING PROGRAM ISI CLASS 1. 2. 3 AND NC VALVES i l P!LGRIM NUCLEAR POWER STATION i- P&iD. M245 SHEET 1 SYSTEM REACTOR COGE COOLING SYSTEM (t301)
Pard M246 SHEET 2 Valve P&tO ISI Vatve Vale . Valve Actuator Normal Test Test PNPS Proc Test Rehet! Ii Numbet Coor Class Cat Stre Type Type Posdron Rqmt Frea Numte Ortectm Justacate ~
Nots {l 22 D-11 2 8 6 GA MO O FE O 8554 (SH 1) ST Q 8554 O/C Pt 2Y 8554 23 D-11 2 AG 6 CK SA C FC Q 8>$1 FF (SM 1) AP 2Y 85510 Closed RV-37 LX 2Y 855to
! 24 K-11 3 C 1 CK S C PC O 8551 FF i (SH 2) FC Rt 8t27 FF 'iv.27 Disassectie AP Rt 8127 Closed RV-2 7 Desassetne 4
25 L-8 2 A 6- GA MO C FE O 8554 (SH 1) ST Q 8554 OC M 2Y 8554 l LMd OBJ 8712 CU(1U) o t 26 D-10 2 8 6 GA MO C FE O 8554
1 (SH 1) AP Rt 8827 Closed RV-27 Drsassemt>3e 31 C-8 2 AC 2 RL SA C RT 10Y 88263 (SH 2) LX NA 88263 R T V. nties 34 K.13 2 B 1 GL AO C FE o 8554 (SH 1)
ST Q 8554 C FS Q 8554 C Pt 2Y 8554 CO J-9 2 C ~2 CK SA C PC Q 8551 FF (SH 1) FC Rt 8r27 FF RV.27 Dwsemth
, AP Rt M712 RJo .10 l 41' J-6 2 C 8 CK SA C FC O M551 FF (SH 1) AP Rt 8712 Rxj. t r*
42 J4 3 AC 1 HL SA C RI toy 812t> 3 (SH 2) LX NA 8 i26 3 RT Verr'ws 47 H-8 2 AC 2 CK SA C PC Q 8551 FF (SH 1) FC RI 8137 FF RM) NIT /DesassemtAe AP RI 87?2 Closed RJO 10 LMf OBJ 8 712 OUf 10)-01
. 48 E-8 2 B 4 GA MO O Pt 2Y 881111 Passive 4
(SH 1) Also 8 I 30 1
8.1.1.1 Rev. 9 Page 96 of 236 i
TABLE INSERVsCE VALVE TESTING PROGRAM ISI CLASS 1. 2. 3 AND NC VALVES PILGRIM NUCLEAR POWER STATION P23D: M245 SHEET 1 SYSTEM REACTOR CORE COOLING SYSTEM (1301)
P&lD M246 SHEET 2 Test Hebett P&lD IS1 Va;ve Vatve Vatve Actuator teormat Test Test Pf 4PS Prx Vatve Rqmt Freq Numtm Dwecten Just&aten Notes l Ntwnber Coor Class Cat Srze Type Type Pos+on E-7 A 4 GA MO C FE CS 881111 C M'9 49 1 ST CS 8 I It 11 O/C C&O9 (SH 1) Pt 2Y 855/ Also 81 30 LJ OBJ 8 715 O*.'( 10F01 f LP 2Y 8557 AC 4 CK SA C FC CS 88119 FF GS O4 50 E-7 1 AP 8 f 119 Closed CS44 2Y (SH 1) LP 2Y 8557 2 .B 4 GL MO C FE O 8554 53 D-8 C ST O 8554 (SH 1) Pt 2Y 8554 AC 2 CK SA C PC O B551 FF 59 J-7 2 Dmssemt9e FC Rt 8827 FF RV-27 (SH 1) AP k. 8712 Closed RJO-10 LAV OBJ 8 712 OU110F01 l H-8 2 8 2 GL MO C FE O 8554
~60 ST O 8554 GC (SH 1) Pt 2Y 8554 FE O 8551 f.go e s s a 61 E-13 2 B 3 GA MO C ST O 8551 O/C Aso8554 (SH 2) Pt 2Y 8554 J-7 2 0 2 GL MO C FE O 8554 62 ST O 8554 Ott (SH 2) M 2Y 8554 C 2 CK SA C PC O 8551 FF 63 K4 2 RI 8127 rF RV-27 LesemNe FC (SH 2) AP RI 812T Clow1 RV 27 h semNe AC 8 SC SA 1 0/C FC O 6551 FF 64 J4 2 RJO 10 AP Rt 8712 Chaed )
(SH.1) L.AV C@J B712 O*.410) O t s
- Stop Check Vafve. Handwheel posmon - Locked Open, normat disc pos: tion - Closed 8 I1.1 Rev. 9 Page 97 cf 236
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I TABLE INSERVICE VALVE TESTING PROGRtM RSI CtASS 1. 2. 3 AND NC VALVES PILGRIM NUCLEAR PONER STATION PalD- M245 SHEET 1 SYSTEM. F:EACTOR CORE 000L17#, SYSTEM (1301)
P&fD' M246 SHEET 2 l Vaive P&tD 4S1 Vatve Valve Valve Actuator Normat Test Test Pt4PS Prot Test R ese-f1 i Number C xt Class Cat See Type Type Posbon Rqmt Freg Number Dire JusScatwm P des 70 J-12 3 AC 1.5 RL SA C RT 10Y 88263 (SH 2) LX NA 81263 RT Vedies 9067 H4 2 C 1 SK SA C FC CS 8111.10 FF CS-11
- (SH 1) AP Q 8551 C1esed i
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i' l TABLE INSERVICE VALVE TESTING PROGRAM iSI CLASS 1. 2. 3 AND NC VALVES 7 i PILGRIM NUCLEAR POWER STATION :
P2tD. M247 SYSTEM REACTOR WATER C. EAMJP SYSTEM (1201) !
Valve P&lD (St Valve Vahre Vahre Actuator Normal Test Test PNPS Proc. Test Rei NW Coor Class Cat S!ze Type Type Positen Rqmt Freq Number Dwecte Just,-fcate fues 2 C-2 1 A 6 GA MO O FE O 8652 ST Q 8652 C l Pt 2Y 8715 Arso s 3 30 i LJ OBJ 8 715 Ov(10 pot l 5 C-3 1 A 6 GA MO O FE O 8652 k
- ST O .652 C
' Pt 2Y 8715 A13e 3 3 30 LJ OBJ 8715 Of.'{ 10) 01 80 B-9 1 A 4 GL MO O FE O 8652 t ST O 8652 C ,
Pt 2Y 8715 Also 8130 sJ OBJ 8 715 OuttCpot ,
C 4 CK SA O FC RI 8421 RF RV-21 i 81 BA 1 AP O 8131 Opee l 85 C-2 1 B 6 GA MO O FE O 8652 !
ST O 8652 C i'
Pt 2Y 8652 360 C-3 1 AC 1 SK SA O FC. RI 8M32 RF RV.22 i AP RI 8 M 3-2 Open RV-72 [
LX R1 8 M 3-2 RV-22 r
~d1 3 D-3 1 AC 1 SK SA O FC Rt 8 M 3-2 RF HV-22 [
AP RI 8 M 3-2 Open RV-22 ?
LX RI 8 M 3-2 RVC i f t
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- Page 99 of 236 <
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TABLE INSERVICE VALVE TESTING PROGPAM ISI CLASS 1,2. 3 AND NC VALVES PILGRIM NUCLEAR P3NER STATION P;ID M249 SYSTEM STANDBY LtOU:D COf4 TROL SYSTEM (1101)
Valve P&lD ISI Valve Valve Valve Actuator Normal Test Test PNFS Proc Test RWff g Number Coor Class Cat See Type Type Pos4 ton Ramt Freq tJumber Dwedum Jushfecaton Nctes j 1 J-2 _ 1 NA 1.5 GA MA LO NA FM f1A E=W (Manual)
Pt 2Y 87121 15 J-2 1 AC 15 CK SA C FC R8 846 FF Rv.08 AP 2Y 'J422 C bed RV-37 LX 2Y 8422 16 H-1 1 AC 15 CK SA C . FC RI 846 FF RV-OS AP Rt 8 7 1 2.1 Closed RJO-10 Also 8 7. t 5 LJ OBJ 8 715 O*Jt 10)-01 l 43A E-4 2 AC 15 CK SA C FC Q 841 FF AP 2Y 8 4 2.1 Closed RV-37 LX 2Y 8421 438 F-4 2 AC 1.5 CK SA C FC O 841 FF AP 2Y 8 4 2.1 Closed RV-3 7 LX 2Y 8821 1105A D-4 2 C 1 RL SA C RT 10Y 812ti 3 1105B H-4 2 C 1 RL SA C RT 10Y 81263 1106-A E-2 2 0 15 SH Ex C EX :Ov 846 1106-B E-2 2 0 1.5 SH Ex C EX 10Y 846 8.I.1.1 Rev. 9 Page 100 of 236
1 TABLE INSERVICE VALVE TESTING PROGRAM ISI CIASS 1,2,3 AND NC VALVES ,
PILGR*M NUCLEAR POWER STATION !
P&lD: M250 SHEET 1 of 2 SYSTEM. CONTROL ROD DRIVE HYDRAUllC SYSTEM (302) l PCtD- M250 SHEET 2 of 2 Valve P&lD ISI Valve Vahre Vatve Actuator Normal Test Test PNPS Proc. Test RAtt -
Number Coor Class Cat Stre Type Type Pm Ramt Freg Numt>er DwMe J e hhca h Notes 2A J4 1 AC 2. 5 SC SA O/LO FC O 8131 RF
, (SH 1) AP O 8131 Opm !
LX 2Y '8331 28 K4 1 AC 25 SC SA O/LO FC O 8431 RF (SH1) AP O 8 I31 open IX 2Y 9331 21A G-3 2 A 1 PG AO O FE O 833 (SH 2) ST O e33 o ST Rt 8 M 1-31 C RV-25 FS O 633 C Pt 2Y B33 '
LX 2Y 8332 218 G-7 2 A 1 PG AO O FE O 833 (SH 2) ST O 833 O ST RI 8 M 1-31 C RV-26 FS O 833 C Pt 2V 833 !
LX 2Y 8332 22A D-4 2 A 2 PG AO O FE O 8 3.3 (SH 2) ST O 833 O ST Rt 8 M 1-31 C RV-26 4
FS O 833 C Pt 2Y 833 LX 2Y 6332 ,
22B D-7 2 A 2 PG AO O FE O 833 (SH 2) ST O 833 O ST Ri 8 M 1-31 C RV45 l FS O 833 C L I
M 2Y 833 l LX 2y 8332 ,
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8.l.1.1 Rev. 9 !
Page 101 Of 236 (
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TABLE INSERVICE VALVE TESTING PROGRAM 151 CLASS 1,2. 3 AND NC VALVES PtLGRtM NUCLEAR POWER STATION POID: M250 SHEET 1 of 2 SYSTEM CONTROL ROD DRIVE HYDRAUltC SYSTE'4 (302)
R3tD- M250 SHEET 2 of 2 Vatve . P&tD ISI Vatve Vahre Valve Actuator Normal Test Test Pi4PS Prot Test Reheft g Number Coor Class Cat Stre Type Type Position Rgrri Freq FAsmber Dorada Justk a m Notes 33A G-3 2 A 1 PG AO O FE O 633 ST Q 833 O ,,
(SH.2) ST RI 8 M 1-31 C RV-26 i FS O 833 C !
PI 2Y 833 LX 2Y 8332 238 G-7 2 A 1 PG AO O FE O 833 (SH 2) ST O 833 0 ,
ST R1 8 M 1-31 C RV-2s !
FS O 833 C Pt 2Y 833 LX 2Y 8332 24A D-4 2 A 2 PG AO O FE Q 833 i' (SH.2) ST Q 83L O- '
ST RI 8 M 1-31 C RY-26 I FS O 833 C. j Pt 2Y 833 LX 2Y 8332 24B D-7 2 A 2 PG AO O FE O 833 ,
(SH 2) ST Q T33 O l ST R1 8 M 1-31 C RV.26 FS O 833 C l Pt 2V 833 '
LX 2Y 8332 ,
114 A-18 2 C 05 CK SA C FC RI 99 FF Hv 4r+ 1 a (HCU) (SH 1) AP FM f4A Rvw !
i 115 C-19 2 C 05 CK SA C FC R1 99 .FF (HCU) (SH 1) AP HI 8t25 Closed $4v og i 120 B-18 2 B 05 r4D 50 C FE O e32 HVT7 3 (HCU) (SH.1) ST Q NA Rv-17 4 FS O 832 C Rv-17 1
~121 B-18 2 B 05 ND SG C FE O 632 RV-17 !
(HCU) (SH.1) ST Q FM RV-17 FS O 832 C RV-17 i !
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Page 102 Of 236 l
TAEKE INSERVICE VALVE TESTING PROGRAM ISI CLASS 1. 2. 3 AND NC VALVES PILGRIM NUCLEAR POWER STATION l PGJD: M250 SHEET 1 of 2 SYSTEM CONTROL ROO ORfVE HYDRAULIC SYSTEM (302) )
POJD M250 SHEET 2 of 2 Vatve P&lD IS1 Valve Vatve Vahre Actuator Nms i Test Test PNPS Proc Test Hehett Number Coor Class Cat Stre Type Tne Pose m Rqmt Freq Number Dawton Jush5 cation Neds 122 B-17 2 B Ob ND SO C FE O 832 H v.17 ST Q f1A RV-17 (HCU) (SH.1) O FS 832 C RV-17 123 B-17 2 B 05 t4D SO C FE O 832 RV-t 7 ST Q NA RV.17 (HCU) (SH 1) FS Q 832 C RV-17 126 B-17 2 8 1 PG AO C FE Ri 99 Rv4r3 ST RI P4A R /-09 (HCU) (SH.1) FS R1 99 O RV c9 PI 2Y 99 127 A-17 2 0 05 PG AO C FE R$ 99 RV-09 ST Rt FIA RV 09 (HCU) (SH_11 FS Rt 99 O RV-09 PI 2Y 99 138 C-16 2 C- 05 CK SA O FC Q 832 RF RV-10 (SH 1) AP Q 8831 Open (HCU) 151 k-4 1 AC 25 CK SA O FC RI S331 RF RV-42 (SH 1) AP Q 8 I 31 Open LX 2Y 8331 8.11.1 Rev. 9 Page 103 of 236 i
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TABLE INSERVICE VALVE TESTING PROGRAM ISI CLAFS 1,2. 3 AND NC VALVES PILGRIM NUCLEAR POWER STATION P&lD: M251 SYSTEM RECTRC PUUPINSTRUMENTATION(2152) valve P&lO ISI varve Vatre Vatve Actuator teoru al Test Test PNPS Pror- Test Ruet/
Number C -r Class Cat Stre Type Type Poset,en Romt FrM thmtiar Due Just:feca*we tL>tes 25A D-1 2 AC 1 SK SA O FC Rt 8 M 3-2 RF RV 22 AP RI 8 M 3-2 Open RV.22 LX Rf 8 M 3-2 RV 22 l 258 O-1 2 AC 1 SK SA O FC RI 8 M 3-2 RF RV 22 AP RI 8 M 3-2 Open RV-22 LX RI 6 M 3-2 RV 22 26A D-1 2 AC 1 SK SA O FC RI 8 M 3-2 RF RV 22 An . e u 3-2 Open RV-22 ie RI 8M32 RV.22 268 D-1 2 AC 1 SK SA O FC Rt 8 M 3-2 RF RV-22 l AP R1 8 M 3-2 Open Hv-22
- LX RI 8 M 3-2 RV 72 I F013A C-2 2 AC 0 75 CK SA O FC RI 871z1 RF RJO-03 Atso 8 715 AP Q d*31 Open LJ OBJ 4 715 Out 10)-01 F0138 C-2 2 AC 0 75 CK SA O FC R4 87121 RF RJOO3 At o 8 715 AP. O 8 I 31 Open LJ OBJ 8715 Ocito)Ot F015A C-1 NC C 0 75 RL SA C_ RT 10Y 8i26 3 F0150 C-1 tA C 0 75 RL SA C RT 10Y 81263
~
l F017A C-1 2 AC 0 75 CK SA O FC Rt 87.12.1 RF RJO 03 Kiso 8 715 AP O 8131 Open LJ NJ 8715 Ot.q tcy ot F0178 C-1 2 AC 0 75 CK SA O~ FC RI 67121 RF kBTn A%g735 AP G R I 31 Op-n LJ OfjJ B715 opg.ot l
l l 8.1.1.1 Rev. 9 l Page 104 of 236
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TABLE INCERVICE VALVE TESTING PROGRAM 133 CLASS 1. 2. 3 APO NC VALVES PILG'fM NUCLEAR POWER STATION
- j. PalD: M252 SYSTEM FEEDWATER SYSTEM (S)
~ Valve P&lD ISI Vatve Valve Valve Actuator Normal Test Test Pf4PS Proc. Test Retief!
Number Coor Class Cat See Type Type Positw>n Rg nt Freq Number Direction Jus' ficat*on hot s 58A E-4 .1 AC 18 CK SA O FC RI 8 7.1 5 RF RJO-02 AP Q 93 Open Note 5 LJ OBJ 8715 OU(10F01 58B F-4 1 AC 18 CK SA O FC RI 8715 RF RJCM12 AP O 93 Open Note 5 LJ OBJ 8715 Of.ttiopat 62A E-3 1 AC 18 CK SA O FC RI 8 7.1 5 RF RJO42 AP O 93 Open Note 5 LJ OBJ 8 715 OP.t{ t 0)-0 t 628 F-3 1 AC 18 CK SA O FC Ri 8 7.1.5 RF RJO42
' AP Q 93 Open No's 5 LJ OBJ 8715 OM(10}41 Note 5: Performed at least quarterfy when the Reactor is 2 90% rated power i
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TABLE INSERYlCE VALVE TESTING PROGRAM
! ISI CLASS 1,2. 3 AND NC VALVES PILGRIM NUCLEAR POWER STATICN l POJD: M252 SYSTEM REmCTOR RECTRCULATION SYSTEM (202)
Valve P&lD ISI Valve Vahre Valve Actuator teormal Test Test Pt4PS Proc. Test - Retieu Number Coor Class Cat See Type Type Posrtion Rqmt Freg Number DirectMm Jushhcat e Notes !
4A L-5 1 NA 28 GA MO O NA NA t4A Passive Pt 2Y 89111 48 M-6 1 NA 28 GA MO O NA f4A f4A Passrve Pt 2Y 88112 5A L-8 i B 28 GA MO O FE CS 85111 Rv-33 t4ote 3 ST CS 8!I 11 1 C RV-33 Note 3 Pt 2Y 88111 SB M-6 1 B 28 GA MO O FE CS B 1112 RV-33 f40te 3 ST CS 8 I 11 2 C RV.33 Note 3 Pt 2Y 81112 NOTE 3. Performed duieng Cold Shutdown when core flow from rectreufation pump operabon is not reezered I
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TABLE INSERVICE VALVE TESTING PROGRAM ISI CLASS 1. 2,3 AND NC VALVES PILGRIM NUCLEAR POWER STATION P&lD: M252. SYSTEM MAIN STEAM ISOL , ADS.. &
SAFETY RELfEF (203) i Valve P&lD ist VaM Vane Vane Actuator Normat Test Test PNPS Proc T est R et.et/
Number 'Coor Class Cat See Type Type Posthon Rgmt Fem Number Dweeton Justibcaten hetes !
1A C-9 1 A 20 GL AO O FE CS 8744 CSi7 ST CS 8744 C CS-17 FS CS 8744 C CS-17 Pt 2Y 8 7.1 6 Also 8 I 30 i LJ OBJ 8 716 OMAO)-01 l!
10 E-9 1 A 20 GL AO O FE CS 8 7.4 4 CS-17 '
ST CS 8744 C CS-17 FS CS 8744 C CS-17 P1 2Y 8716 Abo 8130 l LJ OBJ B 716-OM{1o) 01 ll' 1C F-7 1 A 20 GL AO O FE CS 8744 CS-17 ST CS 8744 C CS-17 i FS CS 8744 C CS-1/
I P1 2Y 8716 Also 8 a 30 LJ OBJ 8716 OM{10)41 CS 17 lt!
, 1D F-7 1 A 20 GL AO O FE CS 8744 ST CS 8744 C CS-17 {
FS CS 8744 C CS-17 Pt 2Y 8716 Also 8 8 30 LJ OBJ 8716 09410).01 ll!
2A C-11 1 A 20 GL AO O FE CS 8744 CS-17 ST CS 8744 C CS-17 '
FS CS 8744 C CS-17 Pt 2Y 8716 Al,o 8130 i LJ OBJ 8 716 0M{16401 lI i
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Page 107 of 236 l l
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TABLE
- INSET 4VICE VALVE TESTING PROGRAM ISI CLASS 1. 2. 3 AND NC VALVES PfLGR!M NUCLEAR POVER STATION P&lO
- M-252 SYSTEM MAIN STEAAt ISOL . ADS. &
SAF ETY REttEF (203) tfatve P&lD 158 Vaive Valve Valve Actuator teormat Test Test Pt4PS Proc. Test Hetien g Number Coor Class Cat Site Type Type Posit e Rqmt Frea f4 umber Directm Juv.fcation f40tes 1 2B E-3 1 A 20 GL AO O FE CS 8744 C517 ST CS 8744 C CS 17 FS CS 8744 C C St7 Pt 2Y 8716 Also 6130 LJ OBJ 8716 OMEO) 01 ll 2C F-7 1 A 20 Gu EO O FE CS 8744 CS-17 ST CS 8744 C CS-t 7 FS CS 8744 C CS-17
+ Pt 2Y 8 7.1 6 Also at t 30 LJ OBJ 8716 OM[10) 01 l 2D F-7 1 A 20 GL AO O FE CS B744 CS-17 ST CS 8 7.4 4 C CS-17 FS CS 8744 C CS-17 Pt 2Y 8 7.1 6 Also 8 I 30 LJ OBJ 8716 OM(to t01 l, 3A C-7 1 C 6 RUSV AO/SA C FE 5* 8562 Pt 2Y 8562 RT SY B l 26 2 RV 40 l LX NA 8 I 26 2 RV-40 RT Vetire 38 F-7 1 C 6 RUSV AOISA C FE SV 8562 M 2Y 8562 RT SY 81162 RVan LX NA 81262 RV40 RT vesitn 4
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l 8I1.1 Rev. 9 i Page 108 of 236
- 1 TABLE INSERVICE VALVE TESTING PROGRAM ISI CLASS 1. 2. 3 AND NC VALVES PILGRIM NUCLEAR POWER STATION P&lD~ M252 SYSTEM. MAIN STEAM ! SOL . ADS. &
SAFETY RELTEF (203)
Valve P&lD ISI Vahre Valve Valve Actuator Normal Test Test Pt4PS Proc. Test He4.eu Number Coor Class Cat See Type Type Posrten Rqmt Freq Number Derection Justrfrat.nn ? Mas 3C F-7 1 C 6 RL/SV AO/SA C FE SY e562 P1 2Y 8562 RT SY 81262 RV40 LX FAA 81262 RV40 RT Venfies 3D E-9 1 C 6 RUSV AO/SA C FE SY 8562 '
Pt 2Y 8562 RT SY 8 I26 2 RV40 LX NA 88252 RVJO RT Venf> s 4A E-8 1 C 6 SV SA C RT SY 81261 LX t.A 812S 1 R T Venfe 4B E-7 1 C 6 SV SA C RT 5V 81291 LX f4A 88261 p y y nf,,,
8.1.1.1 Rev. 9 Page 109 of 236
TABLE INSERVICE VALVE TESTING PROGRAL ISI CLASS 1. 2. 3 AND NC VALVES PfLGRIM NUCLEAR PCP.*ER STATION P&tD. M252 SYSTEM NUCLEAR BOILER SYSTEM (220)
Valve P&lO ISI Vane Vahre Vatve Actu5 tor Normal Test Test PNPS Proc. Test Releeft Number Coor Class Cat See Type Type Posdxm Rqmt Freq Num M Deedron Jushicatum tpA.s 1 C-9 1 A 3 GA MO C FE CS 874.3 ST CS 8743 C Pt 2Y 8715 Also 8 I 30 LJ OBJ 8715 O'J110)-01 2 C-11 1 A 3 GA MO C FE CS 8743 ST CS 8743 C Pt 2Y 8715 psso 3 t.30 LJ OBJ B 715 O*J(10) 01 44 K4 1 A 1 GA AO C FE CS 8743 ST CS 8743 C l FS CS 8743 C l Pt 7Y 8715 Atso 8 : 30 LJ OBJ 8 715 Ou(10)ot (6 K-3 1 A 1 GL AO C FE CS 8743 ST CS 8743 C FS CS 8743 C PI 2Y 8715 Alsa 8 8 30 LJ OBJ 8715 OM(103 01 3 46 BA 1 B 1 Gt AO C FE CS 8811.11 Cs03 ST CS 811111 C CSM FS CS 811111 C CS,06 I Pt 7f 811111 47 B 1 B 1 GL AO C FE CS 881111 C5 06 ST CS 811111 C CS Or FS CS 811111 C CS-06 Pt {V _8111 11 l 8.1.1.1 Rev. 9 Page 110 of 236
1 TABLE
' INSERVICE VALVE TESTING PROGRAM IS1 CLASS 1,2. 3 AND NC VALVES PILGRIM NUCLEAR POWER STATION P;.lD: M252 SYSTEM COMPRESSED AIR (31)
~
Valve P&lO ISl Valve Vatve Valve Actuator Normal Test Test Pt4PS Proc. Test Rettet/
Number Coor Class Cat See Type Type Position Rqmt Freq f4 umber Owecte Justr5 cat:on Nets 84A B-9 NC C 1 CK SA C FC CS 8744 FF RV-18 f40te 6 AP RI 87114 Closed RV-18 l
84B E-10 f4C C 1 CK SA C FC CS 8744 FF RV-18 Note 6 AP RI 87114 Closed RV-18 84C E-11 NC C 1 CK SA C FC CS 8744 FF RV-18 f4cte 6 AP R1 07114 Closed RV-19 84D E-11 NC C 1 CK SA C FC CS 8744 FF PV-18 Note 6 AP RI S7114 Closed kV-18
, 85A 8-11 NC C 1 CK SA C FC CS 8744 FF R V-10 f4ote 6 AP R1 8711# Closed RV-19
, 858 E-10 NC C 1 CK SA C FC CS 87d4 FF R T18 recte 6 AP RI 87114 Closed RV-18 '
i 85C E-11 NC C 1 CK SA C FC CS 8744 FF HV-13 f4ote 6 l
AP RI 87114 Closed RV-18 i 65D E-11 NC C 1 CK SA C FC CS 8744 FF R V-18 t4ote 6 AP RI 87114 Closed RV-18 372A C-7 3 AC 1 CK SA FC CS 8 i t115 FF RV-36 f40te 4 AP 2Y 8 7.1.10* C hed RV-37
[- LX 2Y B 7110 P V-30 3720 E-10 3 AC 1 CK SA v FC CS 811115 FF RV-36 Nye4 4
AD 2Y 871.10* Closed RV-37 LT 2Y 87110 RV-30 372C E-11 3 AC 1 CK SA C FC CS 811115 FF RV-36 teote 4 j AP 2Y 87.110'. Closed RV-37 j LX 2Y 87110 RV-30
) 372D E-11 3 AC 1 CK SA C FC CS 811115 FF RV-36 taute 4 g AP 2Y 87110* Closed R V-37 LX 2Y 871.10 RV-30 NOTE 4. Exercise valves during Cold Shutdown when the Drywell is de-<nnted NOTE 6. Exercise open MSIVs during Cold Shutdown which verifies check valve exercise.
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8.I.1.1 Rev. 9 Page 111 of 236
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TABLE INSERVICE VALVE TESTING PROGRAM ISI CLASS 1,2. 3 AND NC VALVES '
PILGRIM NUCLEAR POWER STATION P&lD. M252 SYSTEM. COMPRESSED AIR (21)
Valve P&lD ISI Valve Valve Valve Actuator Normal Test Test PNPS Proc Test Retmf/ g Number Coor Class Cat Size Type Type _ Position Rqmt Freq thember Direction Justificahon Nees 1 373A B-7 3 A 3/4 GL MA C FE NA tJA Passive (Manual)
LX 2Y 87110 RV-30 3738 E9 3 A 3/4 GL MA C FE NA tJA Passsve (Manual)
LX 2Y 87,110 RV-30 373C F-7 3 A 3/4 GL MA C FE tJA tJA Passive (Manual)
LX 2Y 87110 RV-30 373D F-8 3 A 3/4 GL MA FE t4A NA Passrve (Manual)
LX 7Y 87110 RV-30 9085A B-9 3 C 1 'iV SA ,-g RT 10Y 81263 9085B B-9 3 C 1 SV SA
d"; 10Y 81263 9085C B-9 3 C 1 SV SA C iff 10Y 81263 9085D B-9 3 C 1 SV SA C DI 10Y 8 I26 3 9085E B-12 3 C 1 SV SA C RT 10Y 81263 .
9085F B-12 3 C 1 SV SA C RT 10Y 81263 .L 9085G B-12 3 C 1 SV SA C RT 10Y 81263 9085H B-12 3 C 1 SV SA C RT 10Y 8 I 26 3
.t 8.1.11 Rev. 9 Page 112 of 236
TAOLc_
INSERVICE VNJF YtWING PROGRAM '
ISICLASS ,2. 3 A 8 NC VALVES PILGRIM NLA U7 NNER STATION P&lD: M252 SYSTEM NUCLEAR BOTLER(261)
Valve P&lD .ISI Valve Valve Valve Actuator . Normal Test Test PNPS Proc, . Test Rehet/
Number ; Coor Class Cat Size Type Type ' Positeon Rqmt Freq Number Defecison Justificatum ' Notes 1-17A - D-11 1 AC 1- SK SA. O FC Rt 8 M 3-2 RF RV-22 .
AP RI 8 M 3-2 Open RV-22 LX Ri 8 M 3-2 RV-22 -i 1-17B E-11 1 AC. 1' SK SA O FC RI 8 M 3-2 RF RV-22 i AP. RI 8 M 3-2 Open RV-22 i LX RI 8 M 3-2 !
RV-22 1-17C D-11 1 AC 1 SK SA O FC R1 8 M 3-2 . RF RV-22 :
AP - RI 8 M 3 Open - RV-22 LX RI 8 M 3-2 RV-72 .; 17D E-11 1 AC 1 -SK SA O FC RI 8 M 3-2 RF RV-22 -[
AP . RI 8 M 3-2 Open RV-22 i LX RI 8 M 3-2 RV-22 i T-TM D-11 1 AC 1 SK SA O FC Ri 8 M 3-2 RF RV.22 ,
AP Ri 8 M 3-2 Open RV '!
LX RI 8 M 3-2 RV-22 !
1-18B E-11 1 AC 1 SK SA O FC RI 8 M 3-2 RF RV-22 i AP RI B M 3-2 Open RV-22 ~)
LX RI 8 M 3-2 kV-22 {
1-18C D-11 1 :AC 1 SK SA O. FC Rt 8 M.3-2 RF RV-22 [
AP RI 8 M 3-2 Open RV-22 -I u RI 8 M 3-2 RV-22 1-18D E-11 1 AC 1 SK SA O FC Rt 8 M 3-2 RF RV 22 AP RI. 8 M 3-2 Open RV-22 !
LX Rl 8 M 3-2 RV-22 19A K-11 1 AC 1 SK. SA O FC R1 8 M 3-2 RF RV-22 AP RI 8 M 3-2 Open- RV-22 .!
LX Rt 8 M 3-2 RV 22 !'
19B J-11 1 AC- 1 SK SA O FC RI 8 hl 3-2 RF RV-}2 ~~
AP RI 8 M 3-2 Open RV-22 LX RI 8 M 3-2 RV-22 i 20A K-11 1 AC 1 SK SA O FC R1 8 M.3-2 RF RV-22 AP R1- 8 M 3-2 Open RV-22 i u RI 8 M 3-2 RV-22 !
20B J-11 1 AC 1 SK SA O .FC R1 8 M 3-2 RF RV-22 I AP RI 8 M 3-2 Open RV-22 i LX RI 8 M 3-2 RV-22 _
8.l.1.1 Rev 9 Page 113 of 236 t
. . _ _ _ . _ _ m
TABLE' INSERVICE VALVE TESTING PROGRAM ISI CLASS 1,2. 3 AND NC VALVES PILGRIM NUCLEAR POWER Si ATION POlD: M252. SYSTEM. NUCLEAR BOILER (261)
Valve P&lD iSI Valve Valve - Valve Actuator Normal Test . Test PNPS Proc. Test Reheft Number Coor Class Cat Size ' Type Type Position Rorrt Freq Number Direction Justificatron Notes 21A K-11 1 .AC 1 SK SA- O FC RI 8 M 3-2 RF RV.22 AP Ri 8 M 3-2 Open RV-22 LX RI 8 M 3-2 RV-22 21B L-11 1 AC 1 SK SA O FC RI 8 M 3-2 RF R V-22 AP R1 8 M 3-2 Open- RV-22 LX R1 8 M 3-2 RV-22 22A K-11 1 AC .1 SK SA O FC RI a M 3-2 RF RV-22 .
AP R1 8 M 3-2 Open RV-22 LX Rl 8 M 3-2 RV-22 ~
228 L-11 1 AC 1 SK SA O FC Rt 8 M 3-2 RF RV AP RI 8 M 3-2 Open RV-22 '
LX RI 8 M 3-2 RV-22 67A E-3 1 AC 1 SK SA O FC RI 8 M.3-2 RF R V-22 AP RI 8 M 3-2 Open RV-22 LX RI 8 M 3-2 RV-22 67B E-3 1 AC 1 SK SA O FC R1 8 M 3-2 RF RV-22 AP Rt . . 8 M 3-2 Open RV-22 LX RI 8 M 3-2 RV-22 67C E-3 1 AC 1 SK SA O FC Ri. 8 M 3-2 RF R V-22 AP RI 8 M 3-2 Open RV-22 LX RI 8 M 3-2 RV-22 67D E-3 1 AC 1 SK SA -O FC R1 8 M 3-2 RF RV-22 AP- RI 8 M 3-2 Open RV-22 LX RI 8 M 3-2 RV-22 67E D-3 1 AC 1 SK SA O FC RI 8 M 3-2 RF RV-22 AP .RI ' 8 M 3-2 ' Open RV-22 LX RI BM32 RV.?? ~'
67F D-3 1 AC 1 SK SA O FC- Rt S M 3-2 RF RV-22 AP RI 8 M 3-2 Open RV LX HI B M 3-2 RV-22 67G D-3 1 AC 1 SK SA O FC R1 8 M 3-2 RF RV-22 AP RI 8 M 3-2 Open RV-22
-LX RI- 8 M 3-2 RV-22 67H D-3 1 AC 1 SK- SA .O FC R1 8 M 3-2 RF RV-22 AP RI 8 M 3-2 Open RV-22 LX RI 8 M 3-2 RV-22 8.l.1 1 ReV. 9
. Page 114 of 236
TABLE INSERVICE VALVE TESTING PROGRAM ISI CLASS 1. 2. 3 AND NC VALVES I
P!LGRIM NUCLEAR POWER STATION P2lD: M252 SYSTEM NUCLEAR BOfLER (261)
- ' Valve P&lO ISI Valve Vatve Valve Actuator Normal Test Test PtJFS Proc. Test Rehef/ I Number Coor Class Cat Stre Type Type Posrtion Rqmt. Freq Number Direction Justification Notes j l
89A L-3 1 AC 1 SK SA O FC R1 8 M 3-2 RF RV-22 AP RI 8 M 3-2 Open RV-22 i LX RI 8 M 3-2 RV-22
! AP nl 8 M 3-2 Open RV-22 l LX Rt 8 M 3-2 RV-22
, 110A M-3 1 AC 1 SK SA O FC Rt 8 M 3-2 RF RV-22 i AP RI 8 M 3-2 Open RV-22 L LX RI B M 3-2 RV-72 110B J-11 1 AC 1 SK SA O FC RI 8 M 3-2 RF RV-22 AP RI 8 M 3-2 Open RV-22 .
U( RI 8 M 3-2 RV-22 b 81.11 Rev.9 Page 115 of 236
TABLE i INSERVICE VALVE TESTING PROGRAM '
ISI CLASS 1,2. 3 AND NC VALVES PILGRIM NUCLEAR POWER STATION P&lD: M252 SYSTEM NUCLEAR BOfLER (261)
Valve PalD ISI Valve Valve Valve Actuator Normal Test Test PNPS Proc. Test Relief /
Number Coor Class Cat Size Type Type Position Rqmt. Freq tJumber Diraction Justification Notes 96A L-10 NC C 1 CK SA C FC CS 81.1112 FF RV-35 Note 4 AP CS 861112 Closed RV 35 968 L-10 NC C 1 CK SA C FC CS 8611.12 FF R435 Note 4 AP CS 811112 Closed RV-35 96C L-10 NC C 1 CK SA C FC CS 8 1.11.12 FF RV 35 tJote 4 AP CS 811112 Closed RV-35 97A B-8 NC C 10 CK SA C FC CS 8111.12 FF RV-35 Note 4 AP CS 811112 Closed RV-35 978 F-8 NC C 10 CK SA C FC CS 8111.12 FF RV-35 tJote 4 AP CS 8 I 11 12 Closed RV-35 97C F-8 NC C 10 CK SA C FC CS 881112 FF RV 35 Note 4 AP CS 8111 12 Closed RV-35 97D E-9 NC C 10 CK SA C FC CS 8111.12 FF RV-35 tJute 4 AP CS 811112 Closed RV-35 98A D-7 NC C 10 CK SA C FC CS 8411.12 FF RV-35 Note 4 AP CS 811112 Closed RV 35 988 F-9 IJC C 10 CK SA C FC CS 8111,12 FF RV-35 Note 4 AP CS 881112 Closed HV-35 98C F-9 NC C 10 CK SA C FC CS 811112 FF RV-35 tJote 4 AP CS 811112 Closed RV-35 98D E-10 NC C 10 CK SA C FC CS 8111.12 FF RV-35 Note 4 AP CS 8111 42 Closed RV-35 NOTE 4: Exercise valves during Cold shutdown when the Drywellis de-4nerted 8.1.11 Rev. 9 Page 116 of 236 l t
TABLE :
INSERVICE VALVE TESTING PROGRAM ist CLASS 1,2,3 AND NC VALVES PILGRIM NUCLEAR POWER STATION D&lD: M253 SHEET 1 of 2 SYSTEM NUCLEAR BOfLER VESSEL PalD M253 SHEET 2 of 2 INSTRUMENTATION (263)
Vilve P&lD iSI Valve Valve Valve Actuator Normal Test Test PNPS Proc Test Relieu Number Coor Class Cat Size Type Type Position Rqmt Freq Number Direction Justification Notec j;I C2205A-1 NC AC 0.375 CK SA O FC R1 8333* RF RV43 '
(tNBRD) (SH 2) AP O 8 I 31 Open LX R8 8333*
C2205A-1 NC AC 0.375 CK SA O FC RI 8333* RF RV43 (OUTBRD) (SH.2) AP Q 8131 Open LX RI 8333*
C2206A-1 NC AC 0 315 CK SA O FC RI 8333* RF RV43 (lNBRD) (SH 2) AP Q 8 i 31 Open LX RI 8333*
C2206A-1 NC AC 0375 CK SA O FC Rt 8333* RF RV43 (OUTBRD) (SH.2) AP O 8 I 31 Open LX RI 8333*
215A F-6 1 AC 1 SK SA O FC R1 6 M 3-2 RF RV-22 (SH 1) AP RI 8 M 3-2 Open RV-22 LX RI 8 M 3-2 RV-22 2158 F-3 1 AC 1 SK SA O FC Rt 8 M 3-2 RF RV-22 (SH.1) AP Rt 8 M 3-2 Open RV-22 LX Rt 8 M 3-2 RV-22' 217A E-6 1 AC 1 SK SA O FC P1 8 M 3-2 RF RV-22 (SH.1) AP RI 8 M 3-2 Open RV-22 LX RI 8 M 3-2 RV-22 217B E-3 1 AC 1 SK SA O FC Rt 8 M 3-2 RF RV-22 (SH.1) AP RI 8 M 3-2 Open RV-22 LX RI 8 M 3-2 RV-22 713A E-6 1 AC 1 SK SA O FC RI 8 M 3-2 RF RV-22 (SH 1) AP RI 8 M 3-2 Open RV-22 I Rt 8 M 3-2 LX RV-22 219B E-3 1 AC 1 SK SA O FC Hi 8 M 3-2 RF RV-22 pH 1) AP Rt 8 M 3-2 Open RV-22 '
LX R1 8 M 3-2 RV-22 ~~
220A E-6 1 AC 1 SK SA O FC RI 8 M 3-2 RF RV-22 !
(SH 2) AP RI 8 M 3-2 Open RV-22 LX RI 8 M 3-2 RV-22 220B D4 1 AC 1 SK SA O FC RI 8 M 3-2 RF RV-22 (SH 2) AP RI 8 M 3-2 Open RV-22 LX RI 8 M 3-2 RV-22 8.l.1.1 Rev. 9 Page 117 of 236
TABLE INSERVICE VALVE TESTING PROGRAM ISI CLASS 1,2,3 AND NC VALVES PILGRIM NUCLEAR POWER STATION P&lD: M253 SHEET 1 of 2 SYSTEM NUCLEAR BOILER VESSEL PAID: M253 SHEET 2 of 2 INSTRUMENTATION (263)
'ViTve P&lD ISI Valve Valve Vatve Actuator Normal Test Test PNPS Proc. Test Rehet/ g Number Coor Class Cat Size Type Type Posthon Rqmt Freq Number Detection Justificatron Notes I 223A E-6 1 AC 1 SK SA O FC RI B M 3-2 RF RV-22 AP Rl 8 M 3-2 Open RV-22 (SH.2) Rt LX 8 M 3-2 RV 22 '
2238 E-6 1 AC 1 SK SA O FC RI 8 M 3-2 RF RV-22 (SH 2) AP RI 8 M 3-2 Open RV-22 LX RI 8 M 3-2 RV-22 225 C-7 1 AC 1 SK SA O FC Rt 8 M 3-2 RF RV-22 ,
AP Rt 8 M 3-2 Open RV-22 (SH 2)
LX RI 8 M 3-2 RV-22 227 C-7 1 AC 1 SK SA O FC R1 8 M 3-2 RF RV-22 (SH.2) AP RI 8 M 3-2 Open RV-22 LX R1 8 M 3-2 RV-22 231A B-7 1 AC 1 SK SA O FC RI 8 M 3-2 RF RV-22 (SH 2) AP R1 8 M 3-2 Open RV-22 LX RI 8 M 3-2 RV-22 2318 B-7 1 AC 1 SK SA O FC Rt 8 M 3-2 RF RV-22 (SH 2) AP R3 8 M 3-2 Open RV-22 LX Rl 8 M 3-2 RV-22 233 D-4 1 AC 1 SK SA O FC Rt 8 M 3-2 RF RV-22 (SH 2) AP RI 8 M 3-2 Open RV-22 LX RI 8 M 3-2 RV-22 237 E-6 1 AC 1 SK SA O FC R1 8 M 3-2 RF RV-22 (SH 1) AP Rt 8M32 Open RV22 LX R1 8 M 3--2 RV-22 242A D4 1 AC 1 SK SA O FC RI BlA 3-2 RF R V-22 (SH 1) AP RI 8M32 Open RV-22 LX RI 8 M 3-2 RV-22 242B D-3 1 AC 1 SK SA O FC R1 8 M 3-2 RF RV-22 (SH 1) AP RI 8 M 3-2 Open RV 22 LX RI 8 M 3-2 RV-22 2-125A F-6 1 AC 1 SK SA O FC RI 8 M 3-2 RF RV-22 (SH 1) AP R1 8 M 3-2 Open RV-22 LX R1 8 M 3-2 RV-22 2-125B F-3 1 AC 1 SK SA O FC Rl 8 M 3-2 RF Rv-22 (SH 1) AP R1 8 M 3-2 Open RV-22 LX RI 8 f 13-2 RV-22
- 8. I.1.1 Rev.9 Page 118 of 236
. -- . . _ - . . . . - . - . ~ . - .- - - ---. - - - - . . . ~~- - - - - - - . - - - - -
- - . . . - . ~ . . , . . .
i
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t
! TABLE INSERVICE VALVE TESTING PROGRAM iSt CLASS 1. 2. 3 AND NC VALVES
' Pit _ GRIM NUCLEAR POWER STATION f i PalD: M253 SHEET 1 of 2 SYSTEM. NUCLEAR BOILER VESSEL l P&lD; M253 SHEET 2 of 2 INSTRUMENTATION (263) ;
Vitve . PalD ISI ~ Valve Valve Valve Actuator Normal Test Test PNPS Proc. Test Rehet/ i Number Coor Class Cat Size Type' Type Position Ramt Freq Number Direction Justification Notes 1 51 B-7 1 AC 1 SK SA O FC RI 8 M 3-2. RF RV-22 ;
, (SH 2) AP RI 8 M 3-2 Open RV-22 l l LX RI 8 M 3-2 RV-22 i l 53 B-7 1 AC 1 SK SA O FC RI 8 M 3-2 RF RV-22 ;
(SH.2) AP RI 8 M 3-2 Open RV-22 i LX RI. 8 M 3-2 RV-22 !
-O 55 B-7 1 AC 1 SK SA FC R1 8 M 3-2 RF RV-22 (SH.2) AP RI 8 M 3-2 Open RV-22 3 LX R1 8 M 3-2 RV-22 )
57 B7 1 AC ' 1 SK SA O FC RI 8 M 3-2 RF RV-22 j (SH 2) AP RI 8 M 3-2 Open RV-22 t LX RI 8M32 RV-22 t
- 59 B-7 1 AC 1 SK SA O FC R 8 M 3-2 RF RV-22 l (SH 2) AP . RI 8 M 3-2 Open RV-22 LX R1 8 M 3-2 RV-22 61 B-7 1 AC 1 SK SA O FC RI 8 M 3-2 RF RV-22 (SH.2) AP R1 8 M 3-2 Open . RV-22 3 LX RI 8 M 3-2 RV-22 !
38 B-7 1 AC 1 SK SA O FC RI 8 M 3-2 RF RV-22 .
(SH.2) AP RI' 8 M 3-2 'Open RV-?? !
j LX RI 8 M 3-2 RV-22 -
1 45 B-7 1 AC 1 SK SA O FC Rl 8 M 3-2 FsF RV-22 ,,
(SH 2) AP RI 8 M.3-2 ' Open RV-22 l LX RI 8 M 3-2 RV-22 ,
' 44 A-7 1 AC 1 SK SA O FC Rt- 8 Lt 3-2 RF RV-22 (SH 2) AP R1 8 M 3-2 Open RV 22 }
LX RI- 8 M 3-2 RV-22 3 69 A-7 1 AC 1 SK SA O FC: Rt 8 M 3-2 RF RV-22 !
(SM 2) AP Rt 8 M 3-2' Open RV-22 .
LX Rt 8 M 3-2 RV-22 l 71 A-7 1 AC 1 SK SA O FC RI 8 M 3-2 RF RV-22 i
(SH 2) AP R1 8 M 3-2 Open RV-22 LX RI 8 M 3-2 RV-22 :
I 73 A-7 1 AC 1 SK SA O FC R1 8 M 3-2 RF RV-22 !
AP RI 8 M 3-2 Open . RV-22 i (SH 2)
- LX R1 8 M 3-2 RV-22 I I
t i
F t
9 8.l.1.1 Rev.9':
Page 119 of 236'll t
T, c3LE INSERVICE VALVE ISTING PROGRAM ISI CLASS 1,2. 3 AND NC VALVES PILGRIM NUCLEAR POWER STATION P&lD: M253 SHEET 1 of 2 SYSTEM. NUCLEAR BolLER VESSEL P&lD: M253 SHEET 2 of 2 INSTRUME rJTATION (263)
Valve PalD ISI Vane Valve Valve Actuator Normal Test Test PNPS Proc. Test Rehet/
Number Coor Class Cat Size Type Type Position Rqmt Freq Number Directron Justdication FJotes l 75 A-7 1 AC 1 SK SA O FC RI 8 M 3-2 RF RV-22 (SH 2) AP RI 8 M 3-2 Open RV-22 LX RI 8 M 3-2 RV.22 77 A-7 1 AC 1 SK SA O FC Rt 8 M 3-2 RF RV-22 AP RI 8 M 3-2 Open RV-22 (SH.2)
LX RI 8 M 3-2 RV-22 79 E-4 1 AC 1 SK SA O FC Rt 8 M 3-2 RF RV-22 AP RI 8 M 3-2 Open RV-22 (SH 2)
LX RI 8 M 3-2 RV.22 81 E-4 1 AC 1 SK SA O FC RI 8M32 RF RV-22 (SH 2) AP RI 8 M 3-2 Open R V.22 LX RI 8 M 3-2 RV 22 83 E-6 1 AC 1 SK SA O FC RI 8 M 3-2 RF RV-22 AP RI 8 M 3-2 Open RV-22 (SH 1)
LX RI 8 M 3-2 RV 22 90 E-4 1 AC 1 SK SA O FC RI 8 M 3-2 RF R V-22 (SH 2) AP RI 8 M 3-2 Open RV-22 LX Rl 8 M 3-2 RV-22 92 D-4 1 AC 1 SK SA O FC RI 8 M 3-2 RF RV-22 (SH.2) AP R1 8 M 3-2 Open RV-22 LX Rt 8 M 3-2 RV 22 8.l.1.1 Rev. 9 Page 120 of 236
TABLE INSERVICE VALVE TESTING PROGRAM ISI CLASS 1. 2, 3 AND NC VALVES PILGRIM NUCLEAR POWER STATION P&lD: M259 SYSTEM. DfESEL GENERATOR TURBO AIR ASSIST SYSTEM (47) -
Valve P&lO ISI Valve Valve Valve Actuator Normal Test Test PNPS Proc. Test Reheft Number Coor Class Cat Size Type Type Position Ramt. Freq Number Dnection Justification Notes l 201A G-7 NC AC 0 75 CK SA C FC Q 8 9.1 FF AP Q 891 Closed LX 2Y 8912 RV-30 2018 C-7 NC AC 0 75 CK SA C FC Q 891 FF AP O 891 Closed LX 2Y 8912 RV-30 201C E-7 NC AC 0 75 CK SA C FC Q 891 FF AP Q 891 Closed LX 2Y 8912 RV-30 203A F-7 NC AC 0 75 GA MA C FE NA NA LX 2Y 8912 RV-30 203B B-7 NC AC 0.75 GA MA C FE NA NA LX 2Y 8 9 1.2 RV-30 203C E-6 NC AC 0 /5 GA MA C FE NA NA LX 2Y 8 9 1.2 RV-30 301A C-4 NC AC 0 75 CK SA C FC O 891 FF AP Q 891 Closed LX 2Y 8912 RV-30 3018 G-4 NC AC 0 75 CK SA C FC Q 891 FF AP Q' 891 Closed LX 2Y 8912 RV-30 301C E-4 NC AC D 75 CK SA C FC O 8 9.1 FF AP Q 891 Closed LX 2Y 8912 RV-30 303A C-3 NC AC 0 75 GA MA C FE tJA NA
' LX 2Y _ 8 91.2 RV-30 3038 F-3 NC AC 0 75 GA MA C FE f4A NA LX 2Y 8912 RV-30 303C E-3 NC AC 0 75 GA MA C FE NA NA LX 2V 8912 RV-30 8.1.1.1 Rev. 9 Page 121 of 236
-. .- s . . ._ _ . . . _
TABLE INSERVICE VALVE TESTING PROGRAM ISI CLASS 1. 2. 3 AND NC VALVES PILGRIM NUCLEAR POWER STATION P&lD: M259 SYSTEM. DIESEL GEf4ERATOR TURBO AIR ASSIST SYSTEM (47)
Vcjve P&tD ISI Varee Valve Valve Actuator Normal Test Test PNPS Proc. Test Rehef/
Number Coor Class Cat Size Type Type Posrtion Ramt Freq Number Dnection Justification fJotes '
4563A G-7 NC AC 0 75 SV SA RT 10Y 81263 C LX NA 8126 3 RT Venfies 75 3B D-7 NC AC 0 75 SV SA RI 10Y 81263 C LX tJA 81263 RT Venfias r 4563C D-7 NC AC 0 75 SV SA RT 10( 81263 C LX tJA 81263 RT Venfies 4563D G4 NC AC 0 75 SV SA RT 10( 8 i 26 3 C LX NA 81263 RT venfies 4565A E-7 tJC AC 0.75 SV SA RT 10Y B 126 3 C LX NA 81263 RT Venfies 4565B E-4 NC AC 0 75 SV SA RT 10Y 8126 3 C LX NA 81263 RT Verifies 4569A E-6 NC B 1.5 GA SO FE O 891 C RV-19 ST Q tJA RV-19 FS Q 891 C RV-19 4569B E-2 NC B 1.5 GA SO FE O 891 C RV 19 ST Q NA RV-13 FS O 891 C RV-19 4570A F4 tJC B 1.5 GA SO FE O 891 C RV-19 ST Q NA RV-19 FS Q 891 C RV-19 45100 E-2 NC B 15 GA SO FE O 891 C RV-19 ST Q NA RV-19 FS O 891 C RV-19
- 8. l.1.1 Rev. 9 Page 122 of 236 i
. .- ~ - . . . -- . ..
TABLE' INSERVICE VALVE TESTING PROGRAM ISI CLASS 1,2,3 AND NC VALVES P!LGRlM NUCLEAR POWER STATION r I
PalD: M1Q-1-5 (VENDOR DRAWING) SYSTEM TRAVERSING !N-CORE PROBE (45) .
Valve PalO ISI Valve Valve Valve Actuator . Normal Test Test PNPS Proc. Test Reheft Number Coor Class Cat Size Type Type Position Rqmt Freq tJumber Onection Just&at#on ' tJotes l:
300A 2 A 0 25 BL SO C FE O 87.43 (Bill A) ST O 8743 C RV-04 FS Q 8743 C Pt 2Y 8715 Also 8.1.30 W OBJ 8 7.1 5 OM(10F01 g:'
3000 2 A 0 25 OL SO C FE O 8743 (Ball B) ST O 8743 C RV-04 FS O 8743 C Pl 2Y 8 7.1.5 Also B t 30 W OBJ 8 71.5 300C 2 A 0 25 OL SO C FE O 8743 CM(10) 01 l! '
(Biti C) ST- O 8743 C RV-04 FS O 8743 C Pt 2Y 8715 Also 8130 W OBJ 87.15 OM(10)-01 l:
3000 2 A 0 25 BL SO C FE O 8743 (Bill D) ST O 8 7.4 3 C RV-04 FS O 8743 C Pt 2Y 8 7.1.5 A#so B I 30 U OBJ 8 7.1 5 OM(101-01 l
N2Check . 2 AC 0 25 CK SA O F C. RI 8 7 1.5 RF R V-05 s AP 2Y 87411 Opan RV-05 LJ OBJ 8 715 OM(10F01 l 301A (Shear A) 2 D 0 25 SH EX O EX 10Y 3 M 2-5 6 3 301B (ShearB) 2 D 0 25 SH EX O EX 10Y 3 M 2-5 6 8 301C (Shear C) 2 D 0 25 SH EX O EX 10Y 3 M 2-5 6 8 3010 (Sherr D) 2 D 0 25 SH EX O EX 10Y 3 M 2-5 6 8
- 8. '.1.1 Rev.9 Page 123 of 236 ,
TABLE '
INSERVICE VALVE TESTI'tG PPOGRAM ISI CLASS 1,2. 3 AND NC VALVES PILGRIM NUCLEAR POWER STATION P&lD: M294 SYSTEM: STMJD8Y GAS TREATMENT SYSTEM (48)-
Vatve PalD ISI Valve Valve Valve Actuator Normal Test Test PtJPS Proc les! Rehet/
Number Coor Class Cat Size Type Type Posdion Ramt Freq Number Directen Justification Notas- l N99 F-6 2 B 20 BF AO C FE O 872.10
- ST Q 8 7.2.10 O/C FS O 87.210 O Pt 2Y 8 7.2.10 872.10 N106 D-6 2 B 20 BF AO C FE O ST O 8 7.2.10 O/C FS O 872.10 0 Pt 2Y 87.210 N108 F-2 2 B 20 BF AO C FE Q 87210 ST O 872.10 O/C FS Q 87210 0 Pl 2Y 87210 N112 D-2 2 B 20 BF AO C FE O 87.210 ST 'O 87210 O/C FS Q 872.10 0 PI 2Y 872.10 8180 E-2 2 D 8 RD SA C RD SY 81265 tJon-Testable Replace I
L 8.I.1.1 Rev.9 ,
Page 124 of 236 t
7.0 PROGRAM COLD SHUTDOWN JUSTIFICATIONS. REFUEL OUTAGE JUSTIFICATIONS, AND RELIEF REQUESTS .
7.1 PUMP TESTING PROGRAM RELIEF REQUESTS Pump Relief Requests (RP) are provided for conditions in which compliance to ASME Code,Section XI test requirements cannot practically be satisfied Each Relief Request identifies:
pump (s) involved. test requirement (s) of noncompliance, t; asis for relief, and alternate testing.
l
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- 8. l.1.1 Rev. 9 Page 125 of 236
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b
[1] Relief Reouest RP-1 PUMPS: P 202A, P-202B, P-202C, P 202D, P-202E P-202F SYSTEM. Reactor Building Closed Cooling Water (RBCCW)
CLASS: 3 FUNCTION: Emergency Equipment Cochng TEST REQUIPEMFNTS: Table IWP-3100-1, inservice Test Quantities: Measure pump flow rate.
BASIS FOR RELIEF: Reactor Building Closed Coohng Water System instrumentation is not configured to measure individual pump flow rate during plant operation. Redesign of the system would be necessary to install flow instrumentation or to utilize portable flow instrumentation.
Piping configuration does not permit installation of flow onfices on the pump discharge piping that would be consistent with good instrument practices. Adequate distance downstream of elbows is not available on the individual pump discharge prior to where 4
discharge piping joins a common header.
The Reactor Building Closed Cookng Water System is part of the ultimate heat sink for containment cooling functions and Reactor Vessel shutdown cooling. Test loops do not exist for individual
- pump flow tests; therefore, disturbance of the system normal configuration during operation and some Cold bhutdown conditions will have a negative impact on the plant's ability to safely operate or maintain the plant in the Cold Shutdown condition.
Since the RBCCW cooling demands are reduced in a Cold Shutdown condition, the RBCCW cooling loads can be split to minimize a loop's loads on the approach to Cold Shutdown so each of the three pumps in a loop may be tested on an alternating basis during each Colt Shutdown. A Cold Shutdown Test frequency implies that pump testing using the Code Test Method should begin as soon as practicable (within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after obtaining Cold Shutdown conditions) and continue until all pumps are tested or plant is ready to startup, it not previously tested quarterly using the Code Test Method. When all pumps are to be tested in a loop (i.e , during extended Cold Shutdowns), the 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> limit does not apply.
- ALTERNATE TESTING: Measure pump shutoff head quarterly. Measure each loop's individual pump flow rate on an alternating basis during Cold Shutdown not to exceed a refueling interval.
APPROVED BY SER (TAC 110 M85069)
- 8. l.1.1 Rev.9 Page 126 of 236
[2] Relief Reauest RP.2 RETRACTED 8l.1.1 Rev.9 Page 127 of 236
[3); Relief Reauest RP PUMPS: P 207A, P-207B SYSTEM: Standby Liquid Control CLASS: 2 FUNCTION: Provides a met %u of shutting down the Reactor without use of the control rods-TEST REQUIREMENTS: IWP 3500(a), Duration of Tests - each pump shall be run at least 5 minutes under conditions as stable as the system permits.
IWP-4600, Flow Measurement - flow rate shall be measured using a rate or quantity meter installed in the pump test circuit.
BASIS FOR RELIEF: The Standby Liquid Control (SLC) Pumps are required to supply the necessary flow tate at a given system pressure. The inlet !
pressure (no installed test equipment) will be equivalent to the !
static head provided by the test tank. Sst tank levelis established within the inservice test procedures. ' 0 system resistance is set to specified discharge pressure refere v value. Then the test tank level change is measured to deteuit 3: pump flow rate.
The SLC pumps are tested by pumping into a test tank. The test
- -tank capacity does not allow operation of the pump for much longer-
- - than 3 minutes.-
i The present Surveillance Procedure has produced consistent test
- j. results and provides good repeatability, Pump flow rate.
- calculations meet the accuracy requirements of Table IWP-4110-1 for measured values.
i ~ ALTERNATE TESTING: The pump shall be run for a minumum duration of 3 minutes and an-accurate measurement of the test tank level before and after the 3 minute run shall be used to verify test parameters.
B
, CONFORMS TO SER (TAC NO. 74785) ANOMALY #2 CONFORMS TO SER (TAC NO. M85069)- ANOMALY #6 APPROVED BY SER e
i i.
8.l.1:1 Rev. 9
[ Page 128 of 236 t
4
[4] Relief Reauest RP_4 RETRACTED 4
4 t
4 9
d J
s 8.1.1.1 Rev.9 Page 129 of 236
! [5] Relief Recuest RP-5 RETRACTED E
T 4
)
4
- 8. l .1.1 Rev.9 Page 130 of 236
[6] Relief Reauest RP-6 PUMPS: P-208A, P 2088; P-208C, P 208D P 208E SYSTEM. Salt Service Water f, LASS: 3 FUNCTION: Emergency Equipment Cooling TEST REQUIREMENT: IWP-4510, Vibration Amplitude BASIS FOR RELIEF: i he pump casing is physically located underwater and is therefore inaccessible.
ALTERNATE TESTING: Measure vibration on the upper mttor bearing housing in three orthogonal directions, one of which is the axial direction.
CONFORMS WITH SER (TAC NO. M85069) d 8.1.1.1 Rev.9 Page 131 of 236
[7] Relief Reouest RP 7 RETRACTED IDFNTIFIED AS SER (TAC NO. 74785) ANOMAllES #4 & #5 8.1.1.1 Rev.9 Page 132 of 236
[8] Relief Reouest RP-8 PUMPS: P-202A P-202F P 205 Main P-208A P-215A P 2028 P-203A P 205 Booster P-2088 P-215B P-202C P-203B P-206 P-208C P-202D P-203C P 207A P-20BD
, P-202E P-203D P-207B P-20SE SYSTEMS: As Appicable CLASSES: 2. 3 ERNCTION: As Apphcable TEST REQUIREf.iENT: IWP 3220, Time Allowed for Analysis of Tests - all test data shall
, be analyzed within 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> after completion of a test.
BASIS FOR RELIEF Test acceptance criteria are contained within the test procedures and the determination of equipment operability is made immediately by on-shift personnel Therefore, on-shift personnel shall declare the pump inoperable and the appropriate Technical Specifications action time must be staned The analysis of results for degradation requinng increased testing or Engineering evaluation wi;l then occur when the appropriate personnel are available for reviewing the inservice pump test data. The appropriate personnel are not always readily available for this
- review effort.
ALTERNATE TESTING: Test data will be reviewed within four work days (96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br />) following the test, excluding weekends (Saturday and Sunday) and holidays.
APPROVED BY SER (TAC NO. M85069) 3 1
- 8. l .1.1 Rev.9 Page 133 of 236
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[9] Relief Reauest RP-9 PUMPS: P-202A P-202F P 205 Main P-208A P 215A P-202B P-203A P-20.5 Booster P-2088 P-2158 P-202C P-203B P-206 P 2080 P 202D P 203C P-207A P-208D P-202E P 203D P-2078 P-208E SYSTEMS: As Applicable CLASSES: 2, 3 FUNCTIONS: As Apphcable i'
TEST REQUIREMENT: IWP-4120, Range - the full scale range of each instrument shall be three times the reference values or less.
BASIS FOR RELIEF The analog instrumentation (IRD) used to measure vibration amplitude has a range selector with multip!es of 3 and 1 (i.e., full scale ranges of 0.1,0.3,1,3,10, and 30). The IWP-4120 range j requirement translates into requinng all measurements to be in the upper 66% of the meter scale When measuring reference values 4 that fall between 0 030 to 0.033 0 30 to 0 33, and 3.0 to 3.3, this requirement cannot be met For tnese specific cases, the upper 70% of full scale must be used The Code deviation described above occurs infrequently and is so minute, the effects are i insignificant when compared to the many variables encountered during vibration data collection. Measuring reference values using
- the upper 70% of the meter full scale does not impact vibration measuring consistency for monitanng pump degradation.
ALTERNATE TESTING. Pump vibration reference values will be measured within the upper 70% of the vibration meter's full scale l APPROVED BY SER (TAC NO. 74785)
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- 8. I.1.1 Rev.9 Page 134 of 236
1 (10] Relief Reauest RP-10 RETRACTED i-8.1.1.1 Rev.9 Page 135 of 236
7.2 VALVE TESTING PROGRAM COLD SHUTDOWN JUSTIFICATIONS Valve Cold Shutdown Justifications (CS) are provided for conditions where compliance to ASME Code,Section XI, Subsection IWV test requirements are satisfied, but conditions exist that necessitate a test frequency of " Cold Shutdown"in lieu of " quarterly" Each Cold Shutdown Justification identifies valve (s) involved, compliance test requirement (s), basis for justification and an alternate testing frequency of Cold Shutdown l
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- 8. l.1.1 Rev. 9 Page 136 of 236
, [1] COLD SHUTDOWN JUSTIFICATION CS-01 RETRACTED IN ACCORDANCE WITH SER (TAC NO. 74785) ANOMALY #17 t
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![2] COLD SHUTDOWN JUSTIFICATION CS-O2 ,
SY3TEMf. Residual Heat Removal System (1001) ,..
VidNES 47,50
- QATEGORY:
A~
I CLA'SS:
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} - FUNCTION: The 47 and 50 valves are the RHR shutdown cooling suction path primary i coniainment and pressure isolation valves.
l TEST REQUIREMENTS ^ IWV 3411; Test frequency - exercise at least once every
~ three months.
l IWV 3413; Power operated valves - full stroke time.-
l ' BASIS FO_R The valves are interlocked to prevent opening when Reactor-JUSTIFICATION: pressure is greater than 70 psig Each pressure isolation motor l -
operated valve maintains one of the two high pressure barriers L during plant operation To exercise these valves during plant
- operation would involve a loss of one pressure isolation barrier
- between the high pressure Reactor coolant system and low pressure RHR system.
ALTERNATE TESTING: Exercise valves during Cold Shutdown.
REVIEWED BY.SER (TAC NO. 74785) ACCEPTABLE l .
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, [3] COLD SHUTDOWN JUSTlFICATION CS-03 RETRACTED d
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8.1.1.1 Rev. 9 Page 139 of 236
[4] COLD SHUTDOWN JUSTIFICATION CS 04 SYSTEMS: High Pressure Coolant injection System (2301)
Reactor Core Isolation Cooling System (1301) vat VES: 2301-7,1301 50 CATEGORY. AC CLASS: 1 FUNCTION These valves are the HPCI and RCIC injection pressure isolation check valves.
1MIREQUIREMfNI IWV 3521; Test frequency - exercise at least once every three months, quarterly.
FASIS FOR Testing these valves during normal operation would require.
JUSTIFICATION 1) injecting cold water into the Reactor Vessel using the HPCI (or RCIC) System which would result in both a reactivity excursion and thermal shock to the feedwater nozzle and piping and 2) loss of one pressure isolation barrier betweer the high pressure Reactor coolant system and low pressure HPCI (or RCIC) System, These valves are manually stroke testaDie Since a maximum allowable torque on the mechanical test lever of 120 ft Ib for valve 23017 and 75 ft Ib for valve 130150 are specified by the ma nufacturer to prevent damage, the valves can be tested by manual stroking open and then closed only if the plant is not in an abnormal Cold Shutdown valve lineup (no differential pressure across these valves). During a normal Cold cautdown, the feedwater heador is isolated ALTERNATE TESTING' Perform manually exercise and closed normal position verification (AP) dunng Cold Shutdown.
CONFORMS WITH SER (TAC NO. 74785) ANOMALY #19 REVIEW 5D BY SER ACCEPTABLE Bl.1.1 Rev. 9 Page 140 of 236 i
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[5] COLD SHUTDOWN JUSTlFICATION CS-05 RETRACTED IN ACCORDANCE WITH SER (TAC NO,74785) . ANO'.iALY #17 4
- 8. l.1.1 Rev. 9 Page 141 of 236
[6] COLD SHUTDOWN JUSTIFICATION CS 06 SYSTEM. Nuclear Boiler Main Steam Vent. Drain & Sampling System (220)
VALVES: 46,47 CATEGORY B CLASS: 1 .
FUNCTIOtj These valves are used to vent the Reactor Vessel head and Main E13am Line "A" during startup.
F TEST REQUIREMENTS: IWV 3411; Test Frequency exercises at least once every three months.
IWV 3413; Power operated valves full stroke time.
IWV 3415: Fail safe at least once every three months.
BASIS FOR Exercising one of these valves during normal operation leaves JUSTiclCATION- the other valve as the only barrier between the Reactor Vessel and the Drywell sump Any leakage through the closed valve could potentially pressuri;:e the Drywell which is an unnecessary risk for the sole purpose of testing a valve. Finally, operating procedures prohibit operation of these valves during power operation.
ALTERNATE TESTING: Exercise valves dur;ng Cold Shutdown.
REVIEWED BY SER (TAC NO 74785) ACCEPTABLE 8,l.1.1 Rev. 9 Page 142 of 236 s
[7] COLD SHUTDOWN JUSTIFICATION CS-07 RETRACTED
[8] COLD SHUTDOWN JUSTIFICATION CS-08 RETRACTED IN ACCORDANCE WITH SER (TAC NO. 74785) ANOMALY #17
- 8. i .1.1 Rev. 9 Page 143 of 236
[9] COLD SHUTDOWN JUSTIFICATION CS 09 SYSTEMS: Residual Heat Removal System (1001)
Core Spray System (1400)
High Pressure Coolant Injection System (2301)
Reactor Core isolation Cooling System (1301)
VALVES' 100129A.100129B,1400 25A.1400 258,2301-6,1301-49 QATEGORY: A CLASS: 1 FUNCTION: These valves provide pressure isolation from the high pressure Reactor coolant system.
TEST REQUIREMEN'S- lWV 3411; Test Frequency Exercise at least once every three months.
> IWV-3413; Power operated valves - full stroke time.
BASIS FOR These pressure isolation motor operated valves maintain one of JUSTIFICATION: the two high to low pressure barriers during plant operation. The other pressure isolation barrier is a check valve. To exercise these valves during plant operation results in a loss of one isolation barrier. Exercising these motor operated valves quarterly with the Reactor Vessel at pressure significantly increases the occurrence probabilities of an intersystem loss of coolant accident.
ALTERNATE TESTING: Exercise valves during Cold Shutdown.
REVIEWED BY SER (TAC NO. 74785) ACCEPTABLE 8.1.1.1 Rev. 9 Page 144 of 236
[10) COLD SHUTDOWN JUSTIFICATIO'N CS 10 i RETRACTED
- 8. l .1.1 Rev.9 Page 145 of 236
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[11) COLD SHUTDOWN JUSTIFICATION CS 11 SYSTEM: Reactor Core Isolation Cooling System (1301)
VALVE: 9067 CATEGORY- C CLASS: 2 FUNCTION: This valve provides a vent path to reheve a vacuum created within the RCIC exhaust hne after turbine operation.
TEST REQUIREMENT: IWV 3521; Test Frequency exercise at least once every three months.
BASIS FOR The RCIC turbine line exhaust vacuum breaker check valve shall JUSTIFICATION: be forward flow exercised. This normally closed check valve is verified in the open direction by performing a test that ensures unrestricted flow. Performanca of this test at power would require isolation of the RCIC turbine for safety reasons. This will make RCIC inoperable during preparation testing, and restoration of this system. Exercising is to be performed during Cold Shutdown.
ALTERNATE TESTING: Exercise valve during Cold Shutdown.
REVIEWED BY SER (TAC NO. 74785) ACCEPTABLE 8.i.1.1 Rev.9 Page 146 of 236
[12] -
COLD SHUTDOWN JUSTlFICATION CS 12 RETRACTED IN ACCORDANCE WITH SER (TAC NO. 74785) ANOMALY #17
[13) COLD SHUTDOWN JUSTIFICATION CS 13 RETRACTED IN ACCORDANCE WITH SER (TAC NO. 74785) ANOMALY #17
- 8. l.1.1 Rev. 9 Page 147 of 236
l [14) COLD SHUTDOWN JUSTIFICATION CS-14 l
L SYSTEM: Salt Service Water Sysicm (29) ,
l VALVES: -3801,3805 CATEGORY: B CLASS: 3 FUNCTION: These valves control cooling water flow from the Turbine Building Closed Cooling Water (TBCCW) heat exchanger and, therefore, the amount of cooling available for TBCCW equipment. The safety function of these valves is to close on LOCA signal in order to direct maximum cooling water flow to the RBCCW heat exchanger.
TEST REQUIREMENTS: IWV-3411; Test Frequency - exercise at least once every three months.
lWV 3413: Power operated valves - full stroke time.
BASIS FOR Since critical power generation equipment such as the turbine
' JUSTIFICATION: lube oil coolers, Reactor feed pump coolers, and generator L hydrogen and stator coolers are serv ced by TBCCW, a complete stroke closure of the valves would cause a disruption of cooling in
! the system. This cooling disruption could lead to power generation
! equipment damage and possible plant Scram from generator- ,
protective functions.
ALTERNATE TESTING: Partial stroking of valves quarterly. Exercise valves during Cold-Shutdown.
I l REVIEWED BY SER (TAC NO,74785) ACCEPTABLE l
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[15) COLD SHUTDOWN JUSTlFICATION CS 15 RETRACTED
[16) COLD SHUTDOWN JUSTIFICATION CS 16 RETRACTED l
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[17) COLD SHUTDOWN JUSTIFICATION CS 17 SYSTEM: Main Steam VALVES: AO 203-1 A through 1D and AO 203 2A through 2D CATEGORY A
. CLASS: 1 FUNCTION: These main steam isolation valves are used to isolate the main steam line penetrations.
TEST REQUIREMENT: IWV 3411: Test Frequency - exercise at least once every three months.
IWV-3413; Power Operated Valves - full stroke time.
IMV-3415; Fail Safe - at least once every three months.
BASIS FOR Full stroke exercising requires a reduction in power to JUSTIFICATION: approximately 60% due to the loss of steam flow from one main steam line to the turbine. This reduction in power to perform exercising quarterly is costly and a burden to the utility. Recent industry information indicates that closing these valves with high steam flow in the line may be a large contributing factor to 4
observed seat degradation. The valves are designed for and receive a partiei stroke exercise quarterly to verify proper position indication, limit switch actuation, and partial fail safe with full stee'a flow during plant operation. Partial stroke exercising is accomplished by bleeding down the accumulator air supply to the operator. Therefore, conformance to the quarterly requirements is impractical for the facility.
ALTERNATE TESTING: Partial stroking of valves quarterly. Exercise valves during Cold Shutdown.
i UNREVIEWED BY SER (TAC NO,74785)
REVIEWED BY SER (TAC NO. M88198) ACCEPTABLE
- 8. l.1.1 Rev. 9 Page 150 of 236
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_ [18] COLD SHUTDOWN JUSTIFICATION CS 18 SYSTEMn Compressed Air (31)
VALVES: 31-CK 15A,31 CK 158 CATEGORY: C CLASS: NC FUNCTION: These check valves open allow makeup air to supply the suppression chamber to Reactor Building vacuum breaker air accumulator system.
TEST REQUIREMENT: IWV 3521; Test Frequency exercise at least once every three months.-
l BASIS FOR-- These check valves normally remain closed during plant JUSTIFICATION: operation. They open during recharging of the torus vacuum breaker air accumulators. The accumulator system is monitored on a shift by shift basis to verify both leak tightness of the accumulator system and operability of containment isolation valves (i.e.,45-AO 5040A and 45-AO 50408). To perform a closed normal position verification following a forward flow exercise requires opening an upstraam manual accumulator isolation valve and venting off the upstream side of each check valve. This testing challenges the leak tightness of the atisociated accumulator system and operability of the containment isolation valves.
Therefore closed normal position verification will be performed during shutdown when primary containment and accumulator
- system integrity are no longer required.--
ALTERNATE TESTING: Perform closed normal position venfication (AP) during Cold Shutdown.
REQUIRED BY SER (TAC NO. 74785) _ ANOMALY #19 8.l.1.1 Rev.9 Page 151 of 236
[19) COLD SHUTDOWN JUSTIFICATION CS -19 SYSTEM: High Pressure Coolant injection l
! VALVE- AO 2301-64 CATEGORY C l CLASS' 2 l
FUNCTION: This valve opens to create a flow path that enables condensate from the HPCI Gland Seal Condenser (GSC) to be pumped to Clean Radwaste when the HPCI System is in standby mode This valve isolates while HPCIis in operation to prevent the HPCI GSC pump discharge piping from communicating with Clean Radwaste.
TEST REQUIREMENT: IWV 3413; Power Operated Valves - full stroke time BASIS FOR This air operated valve opens to create a flow path that enables JUSTIFICATION' condensate from the HPCI Gland Seal Condenser (GSC) to be pumped to Clean Radwaste when the HPCI System is in standby mode. This valve isolates while HPCI is in operation to prevent the HPCI GSC pump discharge piping from communicating with Clean Radwaste.
This normally closed valve cannot be stroked when either of the following isolating conditions is present: 1) isolation signal when the HPCI System is initiated either manually or through an automatic signal or 2) isolating condition wh_ en HPCI GSC level is below the HPCI GSC pump low level permissive setpoint. If either of the above conditions occurs, then this valve will not respond to hand switch operation.
On some occasions immedis.tely following a HPCI pump run, there is sufficient level in the GSC to permit valve stoke testing.
However, if the GSC pump begins to pump down within 2 to 3 minutes before the HPCI pump is tnpped or while the HPCI System is being secured following pump trip, then the GSC low level permissive will not be clear and the valve cannot be stroked using the control switch. In this case, valve stroking may not be possible for extended periods of time. Restarting HPCI to obtain another chance for valve stroking would place undue wear and tear on the HPCI turbine / pump system and would be burdenstme.
(Continued)
- 8. l.1.1 Rev.9 Page 152 of 236 M
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[19] COLD SHUTDOWN JUSTlFICATION CS 19(Continued) l l
l A review of plant on line computer data for the GSC system shows that when the HPCI Systen,is in the standby mode a low level permissive may not clear for weess or months to allow stroking the AO 2301-64 valve This is due to zero or very low steam leakage past the HPCI steam admission valve (a new design valve was installed during RFO #10 which has greatly diminished steam leakage).
Testing this valve on a quarterly basis would cause an undue hardship. To conduct a full stoke exercise (FE) and stroke time (ST) consistently on a quarterly basis, one of the following measures will need to be implemented: 1) water must be manually introduced into the HPCI GSC shell side by installing a temporary hose that supplies water from either the HPCI pump suction (using CST static head pressure) or the plant demineralized water system or 2) the low GSC water level permissive that prevents stoking this valve using the control switch must be defeated by installing an electrical jumper.
Stoking the AO 230164 valve on a sinet quarterly frequency during power operation will require periodic conduct of one of the above listed special provisions and renders the HPCI System inoperable for an extended period of time (several hours). To create the conditions that will allow stoke testing quarterly is burdensome and creates an undue hardship without a compensating increase in the level of quality and safety, ALTERNATE TESTING : Attempt to perform stroke timing for this valve immediately following each quarterly IST HPCI pump test. For those cases when this valve does not stroke following the HPCI quarterly pump test, valve stroke timing will be attempted again during the next scheduled HPCI pump run(s). If valve stroke timing exceeds the quarterly .equency, then conduct valve stroking on a Cold Shutdown frequency.
8l.1.1 Rev. 9 Page 153 of 236
7.3 VALVE TESTING PROGRAM REFUEL OUTAGE JUSTIFICATIONS Valve Refuel Outage Justifications (RJO) are provided for conditions in which compliance to ACME Code,Section XI, Subsection IVN test requirements cannot practically be satisfied These justifications allow for the implementation of portions of OM 10 as it pertains to refueling outage frequency testing pursuant to 10CFR50 55alf M4)(iv). without requesting formal rehef Each Refuel Outage Justification identifies vaheis) involved test requirement (s) of noncomplian:e casis for justification a ternate testing. and frequency of refuel interval 81.1.1 Rev. 9 Page 154 of 236
[1] REFUEL OUTAGE JUSTIFICATION RJO-01 l (previously relief request RV 01)
SYSTEM- Reactor Building Closed Cochng Water System (30)
VALVE: 432 CATEGORY: AC CLASS: 2 FUNCTION: This valve provides isolation to Drywell components by RBCCW. The
! components would require isolation for Primary Containment enteria and
! maintenance.
TEST REOUIREMENT: IkW 3521; Test frequency exercise at least once every three months, quarterly.
BAEFOR This check valve is the outboard Pnmary Containment isolation
, JUSTlFICATION: valve for a system considered in service during plant operation.
The forward flow exercise of this valve is verified quarterly.
I Performance of a check valve closure test during plant operation would result in tho isolation of "A" and "B" loop Drywell coolers and "A" and "B" loop recirculation pump seal water and motor lube oil coolers. Isolation of those coolers associated with the recirculation pumps will lead to the accelerated degradation or failure of recirculation pump seals and may damage recirculation pump motors due to overheating. Additionally, isolation of the Drywell coolers during operation would impact the equipment environmental qualification requirements due to Drywell heatup, Decay heat removalis a key safety function as defined by PNPS dunng Cold Shutdown. Due to this concern, PNPS procedures often require that at least one recirculation pump remains in operation during Cold Shutdown to compensate for a potential loss of decay heat removal. The required isolation to test valve 30 CK-432 would isolate cooling to be"1 recirculation subsystems causing the same failure concerns adoressed above. Additionally, isolation of Drywell coolers during Cold Shutdown will expose the Drywell to repeated unnecessary heatup with potential to adversely affect component operating hfe and habitability requirements.
Permanent plant installed, nonintrusive test equipment does not exist for this valve. Other methods using portable equipment (e.g ,
acoustic, ultrasonic, magnetic, and radiography) which can be used to venfy a reverse flow exercise on this valve require valve closure for extended periods and, as previously stated, are not practical for luarterly or Cold Shutdown testing.
(Continued)
- 8. l .1.1 Rev. 9 Page 155 of 236
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[1] REFUEL OUTAGE JUSTIFICATION RJO-01 (Continued)
Seat leak testing (normally performed during a refuel outage) in l &ccordance with 10CFR50 Appendix J ensures valve exercising in the closed direction and avoids recirculation pump degradation and unnecessary Drpell heatup Dunng refueling intervals when Appendix J leak testing will not be conducted. ae reverse flow exercise will be performed using other methods. The alternate
, methods will either utill:e: 1) leak testing using water to verify I
valve closure or 2) specialized testing that manipulates system flow and uses portable noninstrusive test equipment to document valve closure.
is acceptable for implementation in This alternate accordance with ONtestinh10 pursuant to 10CFR50.55a(f)(4)(iv)ifl the related requirements of OM-10 are implemented. The related requirements for exercising during refueling outage are paragraphs 4.3.2.2(e) and (h).
ALTERNATE TESTING: Verify reverse flow exercise (FC) of this check valve during each l refueling interval in accordance with the provisions of OM 10 paragraphs 4.3.2.2(e) and (h)-
CONFORMS TO SER (TAC NO. M85069)
- 8. l.1.1 Rev. 9 Page 156 of 236
[2] PEFUEL OUTAGE JUSTIFICATION RJO 02 (previously relief request RV 12)
SYSTEM: Nuclear Boiler Feedwater System (6)
VALVES: 6 CK 58A,6 CK 588,6 CK-62A,6 CK-62B l CATEGORY- AC CLASS: 2 l FUNCTlQ3 These valves serve as feedwater iniet check valves.
TEST REOUIREMENT: IWV 3421; Test Frequency exercise at least once every three months.
BASIS FOR These check valves are the inboara and outboard Primary JUSTIFICATION. Containment isolation valves for a system considered in-service during plant operation. Verification of the closure of these check '
valves during plant operation would require isolation of all feedwater flow to the vessel (the feedwater trains are crosstied).
Such an evolution creates an adverse operating conditon which would cause automatic plant shutdown due to loss of feedwater flow.
Performing a reverse flow exercise during Cold Shutdowns would create prolonged periods of system testing and unreasonable increases in radiation exposure. Permanent plant-installed, nonintrusive test equipment does not exist for verifying disc position of these valves. Other methods using portable test equipment (e.g., acoustic, ultrasonic, magnetic, and radiography) which may be used in performing a reverse flow exercise test for these check valves during a plant Cold Shutdown have been reviewed and determined not to be practical. Portable methods require special test equipment to be installed and benchmarked prior to gathering final test data. This benchmarking also necessitates repeated feedwater system startup and shutdown operations which require excessive system manipulation during plant Cold Shutdown conditions. These alternate testing methods either require extended system testing to perform and/or cannot consistently provide accurate reliable results when utilized within the time constraints necessary for Cold Shutdown testing.
Therefore, the only' practical method available to verify check vals a closure is during the performance of leak testing. Verifying a reverse flow exercise more frequently than that used for seat leak testing would create a hardship without a compensating increase in the level of a safety. Leak testing (in accordance with 10CFR50, Appendix J) ensures valve exercising in the closed direction.
(Continued)
- 8. l.1.1 Rev.9 Page 157 of 236 A
[2] REFUEL OUTAGE JUSTIFICATION RJO 02 (Continued)
This alternate testing is acceptable for implementation in accordance with OM 10 pursuant to 10CFR50.55a(f)(4)(iv)if the related requirements of OM 10 are implemented. The related requirements for exercising during refueling outage are paragraphs 4 3.2 2(e) and (h). Use of this OM 10 alternate test requirement is discussed and approved wthin NUREG 1482, Section 4.1.4.
ALTERNATE TESTING- Verify reverse flow exercise (FC) of these check valves each refueling interval (RI) in accordance with the provisions of OM 10 paragraphs 4.3 2 2(e) and (h).
CONFORMS TO SER (TAC NO, M85069)
- 8. l.1.1 Rev. 9 Page 158 of 236 i
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[3] REFUEL OUTAGE JUSTIFICATION RJO-03 I (previously relief request RV 13)
SYSTEM: Recirculation Pump Seal Water System (262)
VALVES: 262 F013A,262 F0138,262 F017A,262 F017B i CATECORY. AC CLASS: 2 FUNCTION: These valves serve as the recirculation pump seal water inboard and outboard containment isolation check valves TEST REQUIREMENT: l\W 3521(Test Frequency exercise at least once every three months.
BASIS FQ_R These check valves are the Primary Cortainment isolation valves JUSTIFICATION: for a system considered in service during plant operation. The open function of ;hese valves is non safety related. Testing these valves to the frequency establisheo by IWV 3521 would cause an undue hardship.
Verification of check valve closure during plant operation would require isolation of the recirculation seal purge lines. Opt ation of the recirculation pumps without seal purge has been shown to lead to accelerated degradation of pump seals. Additionally, leak testing to verify valve closure would require opening a connection on the seal purge line outside of the Drywell. This may introduce air into the seal purge system regt ,ng venting to avoid rapid degradation of recirculation pump seals. Venting of the seal purge line following testing would require Drywell access, which is only accessible during Cold Shutdown.
The required isolation to test these check valves during plant Cold Shutdowns would result in the isolation of the recircu!ation seal purge lines causing the same failure concerns addressed above.
Decay heat removal is a key t.afety function as defined by PNOS during Cold Shutdown. Due to this concern, PNPS Procedures often require that at least one recirculation pump remains in operation during Cold Shutdown to compensate for a potentialloss of decay heat removal. Permanent plant installed, nonintrusive test equipment does t ct exist for verifying disc position of this valve. Other methods using portable equipment (e 9., acoustic, ultrasonic, magnetic, and radiography) which may be used in testing those check valves associated with the secured recirculation pump have been reviewed for use in performing a reverse flow exercise (FC) test and have oeen determined to be not practical. Portable methods require special test equipment to be installed and benchmarked prior to gathering final test data.
These alternate testing methods either require extended system outages to perform and/or cannot consistently provide accurate reliable results when utilized within the time constraints necessary for Cold Shutdown testing.
(Continued)
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[3] R 'UEL OUTAGE JUSTIFICATION RJO 03 (Continued)
I
< Primary Containment leak testing or closure verification using a
- water leak test method each refuehng interval constitutes the most prudent method for exercising. The localleak rate tests require system draining and/or venting with entrance into the plant Drywell.
Therefore, verifying a reverse flow exercise more frequently than i that used for seat leak testing would create a hardship without in compensating increase in the level of safety. Leak testing ensures valve exercising in the closed direction.
This alternate testing is acceptable for implementation in accord 6nce with OM 10 pursuant to 10CFRSO.55a(f)(4)(iv)if the related requirements of OM 10 are implemented. The related requirements for exercising during refueling outage are paragraphs e 4.3.2.2(e) and (h). Use of this OM 10 alternate test requirement is also discussed and approved within NUREG 1482, Section 4.1.4.
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ALTERNATE TESTING: Verify reverse flow exercise (FC) of these check valves during leak testing each refueling interval in accordance with the provisions of OM-10 paragraphs 4.3.2.2(e) and (h).
CONFORMS TO SER (TAC NO. M85069)
- 8. l .1.1 Rev. 9 Page 160 of 236
[4] REFUEL OUTAGE JUSTIFICATION RJO-04 SYSTEM: High Pressure Coolant injection VALVE: 76 CATEGORY: C CLASS: 2-
- FUNCTION: This valve is the HPCI GSC Pump Discharge Check Valve which provides the flow path for condensate from the Gland Seal Condenser (GSC) to be pumped back into the HPCI Booster Pump suction. .This valve closes when the condensate pump is not operating to prevent CST water from -
flowing back through the discharge of the GSC condensate pump into the GSC shell side.
TEST REQUIREMENT: IWV 3521; Test Frequency - exercise at least once every three months, quarterly.
BASIS FOR This valve is the HPCI GSC Pump Discharge Check Valve which JUSTlFICATION: provides the flow path for condensate from the Gland Seal Condenser (GSC) to be pumped back into the HPCI Booster Pump suction. This normally closed valve must be forward fiow exercised by performing a specialized test which benchmarks the pump down
- rate of the HPCI GSC. The closed normal position verification (AP) of this valve is verified once per quarter.
Testing this valve to the frequency established by IWV-3521 would' cause an undue hardship. To conduct the forward flow exercise a -
temporary hydraulle circuit is established by installing a test hose from the HPCI pump suction (using CST static head pressure) to the HPCI GSC shell side. A temporary sight glass to observe GSC -
levelis created by attaching a second clear hose and runnnig it vertically along side the GSC. Then, by starting the GSC pump and observing the GSC pump-down performance, the GM pump discharge check valve forward flow exercise is verified.
(Continued) 8.l.1.1 Rev 9 Page 161 of 236
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[4] REFUEL OUTAGE JUSTIFICATION RJO-04 (Continued)
I OM-10 permits deferral of full stroke exercising until refueling i outages when this testing is not practical during power operation or Cold Shutdowns. Performing a forward flow exercise during power operations is impractical because it is intrusive and renders the HPCI System inoperable for an extended period of time To verify this valve open using flow it is necessary to take the HPCI System out of service, set up a special hydraulic test loop and test equipment, peiform performance testing, remove test equipment, and restore the system to operable status. Even during Cold Shutdowns, to create the system conditions aned anduct testing for this check valve exercise, the HPCI System muut be made inoperable for an extended period of time such that it could delay returning the plant to power (approximately 8 to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />).
Permanent plant installed nonintrusive test equipment does not exist for this valve. Other methods using portable equipment (e.g.,
acoustic, ultrasonic, magnetic, and radiography) which could be used in verifying a forward flow exercise would still require a temporary hydraulic circuit to be established and the GSC pump to be run for sufficient time while test equipment % benchmarked and data is collected.
All methods for conducting a forward flow erercise either require extended system outages to perform and/or cannot consistently provide accurate reliable results w"en utilized within the time constraints necessary for Cold Shutdown testing.
This alternate testing is acceptable in accordance with OM 10 pursuant to 10CFR50.55a(f)(4)(iv)if the related requirements of OM-10 are implemented. The related requirements for check valve exercising during a refueling outage are paragraphs 4,3.2.2(e) and (h).
Al. TERN ATE TESTING: Perform forward flow exercise (FC) of this check valve once each refueling intervalin accordance with the provisions of OM-10 paragraphs 4.3 2.2(e) and (h).
- 8. l.1.1 Rev. 9 Page 162 of 236
[5] REFUEL OUTAGE JUSTlFICATION RJO-05 SYS FEM- High Pressure Coolant injection VALVE: 218 CATEGORY. C CLASS- 2 FUNCTION: This is the HPCI exhaust drain pot containment isolation check valve which provides the flow path that allows condensate that collects between the HPCI inboard and outboard exhaust line check valves to drain into the HPCI exhaust line drain pot. This valve provides a containment isolation barrier in the closed position.
TEST REQUIREMENT: IWV-3521; Test Frequency exercise at least once every three months, quarterly.
BASIS FOR This normally closed valve must be forward flow exercised by JUSTIFICATION: performing a specialized test. The closed normal position verification (AP) of this valve is venfied once per refueling interval during Appendix J leak rate testing Testing this valve to the frequency established by IWV-3521 would cause an undue hardship. Performing this test at power would require isolation of the HPCl turbine for safety reasons. This will require HPCI to be inoperable during preparation, testing, and restoration of this system.
To conduct the forward flow exercise a temporary hydraulic supply is established by installing a test hose from the plant domineralized water system to the HPCI exhaust line. Then the highest flow rate achievable through the 3/4" test hose is established to flood up the leg of piping upstream from this check valve. The introduced water then flows through the CK-2301218 and into the HPCI exhaust line drain pot, raising the level in the drain pot and causing the high level alarm to annunciate. The rate of flow is then calculated based on the time lapsed between introducing the water flow into the exhaust line and receiving the drain pot high level alarm.
Due to the nature of the piping configuration, occasionally the drain
. rate into the drain pot becomes impaired due to air binding, preventing this test from providing the desired observed result. For l these cases, the HPCI exhaust line piping and the drain pot must l
be manually vented and drained, and then the test terun to achieve l a satisfactory exercise.
(Continued)
- 8. l.1.1 Rev. 9 l Page 163 of 236
~ _ _ _ _ _ . . _ _ _ - _ . . . .__._ _ _. __. __ _ _ _ _ _ _ __
[5] REFUEL OUTAGE JUSTIFICATION RJO 05 (Continued) l OM 10 permits deferral cf full stroke exercising until refueling outages when this testing is not practical during power operation or Cold Shutdowns. Performing a forward flow exercise during power operatione or Cold Shutdowns is impractical because it is intrusive and renders the HPCI System incperable for an extended period of time. To verify this valve open using flow it is necessary to take the HPCI System out of service. set up a special hydraulic test supply, install system vent and drain hoses, perform forward flow j testing, drain down the remaining water from the HPCI exhaust line, remove test equipment, and restore the system to operable status. Even during Cold Shutdowns, to create the system conditions and conduct testing for this check valve exercise, the HPCI System must be made inoperable for an extended period of tima such that it could delay returning the plant to power (approximately 8 to 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br />).
Permanent plant installed nonintrusive test equipment does not exist for this valve. Other methods using portable equipment (e g., accustic, ultrasonic, magnetic. and radiography) which could be used in verifying a forward flow exercise would still require a temporary test circuit to establish the conditions for conducting a forward flow exercise. Also, because this is a steam line drain line, it is difficult to ensure the drain piping is maintained completely free of air voids during testing, which will render some methods unreliable.
All methods mentioned above for conducting a forward flow exercise either require extended system outages to perform and/or cannot consistently provide accurate reliable results when utilized within the time constraints necessary for Cold Shutdown testing.
This alternate testing is acceptable in accordance with OM 10 pursuant to 10CFR50.55a(f)(4)(iv)if the related requirements of OM-10 are implemented. The related requirements for check valve exercising during a refueling outage are paragraphs 4.3.2.2(e) and (h).
A_LTERNATE TESTING - Perform forward flow exercise (FC) of this check valve once each refueling interval in accordance with the provisions of OM-10 paragraphs 4.3.2.2(e) and (h).
- 8. l.1.1 Rev.9 Page 164 of 236
I L )
[6] REFUEL OUTAGE JUSTlFICATION RJO 06 SYSTEM: High Pressure Coolant Injection !
VALVES' 232,233 l CATEGORY: C CLASS- 2 l FUNCTION' These valves provide a vent path to relieve the vacuum which is created - }
l within the HPCI exhaust line after turbine operation. These valves close .
l to prevent HPCI exhaust steam from bypassing the exhaust steam line !
l submerged pipe header (which provides suppression for the exhaust ,
steam). ,
i ;
l TEST REQUIREMENT- l\W-3521; Test Frequency exercise at least once everyt .
l three months, quarterly.
BASIS FOR - This normally closed valve must be forward flow exercised (FC) by l JUSTIFICATION: performing a specialized test. The closed normal position venfication (AP) of this valve is also performed concurrent with this test by pederming an air leakage test.
Testing inhlve to the frequency established by IWV 3521 would !
cause an vndue hardship.~ Performing this test at power would require isolation of the HPCI turbine for safety reasons. This will require HPCI to be inoperable dunng preparation, testing, and restoration of this system.
To conduct the forward flow exercise, an air test flow instrument with a pressure gauge is connectad to the vacuum breaker system using a test hose, and a system vent path is established. Then the desired air flow rate is achieved through these check valves while the test cart air makeup pressure is monitored. The test is satisfactory when a specified rate of flow is established without exceeding a maximum backpressure. To perform the closed normal position verification (AP) of this valve, a leak rate monitor with an installed pressure gauge is connected to the vacuum. .
breaker system using a test hose, and a system vent path is '
established. Two separate air leak rate tests are conducted to-ensure that each valve returns to its closed position. These tests are satisfactory when a specified leakage rate which is indicative of
~
full valve closure is achieved.
(Continued) i 1
- 8. l.1.1 Rev.9 Page 165 of 236 t
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(6) REFUEL OUTAGE JUSTIFICATION RJO-06 (Continued)
OM 10 permits deferral of full stroke exercising until refueling outages when this testing is not practical during power operation or Cold Shutdowns. Performing a forward flow exercise during power operations or Cold Shutdowns is impractical because it is intrusive and renders the HPCI System inoperable for an extended period of time To verify this valve open using flo'v, it is necessary to take the HPCI System out of service, set up special test equipment, establish a vent path, and pederm forward flow testing Then the 5 system must be realigned. leak rate test equipment is instal!ed, two leak rate tests are conducted to verify valve closure, test equ pment removed, and the system restored to operable status, i Even during Cold Shutdowns, to create the system conditions and conduct testing for this check valve exercise, the HPCI System must be made inoperable for an extended period of time such that it could delay returning the plant to power.
Permanent plant installed nonintrusive test equipment does not exist for this valve Other methods using portable equipment (e.g., acoustic, ultrasonic, magnetic, and radiography) which could be used in verifying a forward flow exercise would still require a temporary test circuit to establish the conditions for conducting a forward flow exercise. Also, because this is a vacuum relief line (and contains air), ultrasonic methods for verifying valve movement will not work.
All methods mentioned above for conducting a forward flow exercise either require extended systern outages to perform and/or cannot consistently provide accurate reliable results when utilized 4 within the time constraints necessary for Cold Shutdown testing.
This alternate testing is acceptable in accordance with OM 10 pursuant to 10CFR50.55a(f)(4)(iv)if the related requirements of OM-10 are implemented The related requirements for check valve exercising during a refueling outage are paragraphs 4.3.2.2(e) and (h).
ALTERNATE TESTING: Perform the forward flow exercise (FC) and closed normal position verification (AP) of these check valves once each refueling interval in accordance with the provisions of OM-10 paragraphs 4.3.2.2(e) and (h).
- 8. l.1.1 Rev. 9 Page 166 of 236
[7] REFUEL OUTAGE JUSTIFICATION RJO 07 1
l SYSTEM: Fuel Pool Cooling System I VALVES- 235,245 i
CATEGORY: C CLASS: 3 FUNCTION: These safety related valves maintain the reactor cavity basin pressure boundary during refueling operations in the event that the non seismic (non safety related) upstream piping in the Fuel Pool Cooling System ruptures.
TEST REQUIREMENT- l\W 3521; Test Frequency exercise at least once every three months, quarterly.
BASIS FOR These valves maintain the reactor cavity basin pressure boundary JUSTIFICATION when it is filled to support refueling operations. In the event that the non- seismic upstream piping in the Fuel Pool Cooling System ruptures, these check valves must close to prevent siphoning dowr.
the reactor cavity to the cavity spargers (below this level the siphon will be broken).
These normally closed valves must be forward flow exercised (FC) by performing a flow test to the reactor cavity basin. The reactor cavity basin is normally only filled during refueling operations (while in a refueling outage). The closed normal position verification (AP) of each valve is verified by performing a gross leakage test while the reactor cavity sparger line is water filled.
Testing these valves to the frequency established by IWV 3521 would cause an undue hardship. Satisfying these test requirements quarterly, during cold shutdowns or non-refueling outages requires flowing large quantities of water into the reactor cavity. During all modes of plant operation and cold shutdowns, the reactor cavity remains drained with massive shielding blocks installed.
To conduct the forward flow exercise requires establishing a flow path to the reactor cavity basin. These check valves are in the injection flow path to the reactor cavity (and dryer / separator pool if the fuel pool gate is removed) through the reactor cavity spargers. This injection may be conducted using either the fuel pool cooling system or the augmented fuel pool cooling feature of the RHR system. When flowing water through the reactor cavity spargers (and dryer / separator pool), the inlet reactor well sparger block valves are manually cycled to direct flow through each sparger check valve.
(Continued)
- 8. l.1.1 Rev.9 Page 167 cf 236
4-
[7] REFUEL OUTAGE JUSTIFICATION RJO-07 (Continued)-
4
!- To establish the conditions to perform the closed normal position l verification (AP) for these check valves, the reactor cavity must be filled to a level above the reactor cavity spargers. Then utilizing the static head of water from the reactor cavity, a leakage check using the telltale method (collection point upstream of each check valve)is conducted to verify valve closure. These tests are satisfactory when a leakage rate indicative of valve closure is achieved.
OM 10 permits deferral of full stroke exercising until refueling outages -
when this testing is not practical during power operation or cold shutdowns. Forward flow exercising is not practical because it requires directing large amounis of water to (and filling) the reactor
- cavity. The closure venfication requires the reactor cavity to be filled to create the static head (as a driving force) needed to conduct a seat leakage test.
Other methods for verifying a check valve exercise using nonintrusive test equipment (e g., acoustic, ultrasonic, magnetic, and radiography)-
are impractical to because no flow path is available to conduct testing through the reactor cavity spargers except during refuel outages.
This alternate testing is acceptable in accordance with OM-10 pursuant to 10CFR50.55a(f)(4)(iv) if the related requirements of OM-10 are implemented. The related requirements for check valve exercising during a refueling outage are paragraphs 4.3.2.2(e) and (h).
ALTERNATE TESTING: Perform the forward flow exercise (FC) and closed normal position verification (AP) of these check valves once each refueling interval in accordance with the provisions of OM-10 paragraphs 4.3.2.2(e) and (h).
8.l.1.1 Rev. 9 Page 168 of 236
[8] REFUEL OUTAGE JUS'ilFICATION RJO-08 S.YSTEM, Low Pressure Coolant injection
- VALVES; 2A,2C CATEGORY: C CLASS: 2 FUNCTION: These are the LPCI Minimum Flow Check Valves. They open to provide a minimum flow path to prevent pump overheating and damage during low flow conditions. These valves close to pr3 vent backflow through a secured pump when the other pump in the loop is running. The closed position also performs a containment water seat barrier functico.
TEST REQUIREMENT: IWV 3521; Test Frequency - exercise at least once every three months, quarterly.
l BASIS FOR These normally closed valves must be forward flow exercised by 3 1USTIFICATION. performing a specialized nonintrusive test (NIT). These valves are normally closed, which prevents backflow through a secured pump when the other pump in the loop is running. The exercise position is open which provides a minimum flow path to prevent pump overheating and damage during low flow conditions. Quarterly testing of these valves includes a partial forward flow exercise (PC) and closed normal position verification (AP) whir" is conducted !
during pump testing. The Appendix J water sealleak rate testing of these valves is performed on a periodic basic in accordance with the Appendix J testing matrix.
Testing these valves to the frequency established by IWV 3521 would cause an undue hardship. To conduct a forward flow exercise requires installing an ultrasonic flow meter onto the LPCI minimium flow piping. ' hen the respective pump is run while system flow is throttleo io maximize pump flow through the minimium flow path. Due to their size and configuration, these minimium flow lines typically experience high flow turbulence that can impair test conduct. This turbulence impacts ultrasonic signal strength and can create gross distortions to the ultrasonic flow readout. Sometimes, mor? San one test must be run to verify a satisfactory forward flow exercise.
(Continued) 8.1.1.1 Rev.9 Page 169 of 236
[8] REFUEL OUTAGE JUSTIFICATION RJO-08 (Continued)
OM-10 permits deferral of full-stroke exercising until refueling outages when this testing is not practical during power operation or Cold Shutdowns. Performing a forward flow exercise during power operations or Cold Shutdowns is impractical because it requires operating the system over an extended period o' time to ensure accurate and repeatable results. To verify this valve open using flow, it is necessary to install ultrasonic flow testing sensors, perform setup programming, vent the LPCI System prior to l surveillance conduct, establish system conditions to obtain a l satisfactory ultrasonic zeroing benchmark, run the LPCI System and manipulate minimum flow rates for the forward flow exercise, review the results for acceptance (and rerun the testing process as necessary to obtain satisfactory results), return the LPCI System to normal, remove ultrasonic test sensors and equipment, and perform independent system verifications for operability. Even during Cold Shutdowns, to perform preparations, create the system conditions, conduct testing. and perform restorations for this check valve exercise will tie up the LPCI System for an extended period of time such that it could delay returning the plant to power.
l Permanent plant installed nonintrusive test equipment does not exist for this system. The alternative method of using portable ultrasonic test equipment which is used to verify a forward flow exercise requires a lengthy period for setup, test conduct, acceptance, and restoration. All other methods considered for conducting a forward flow exercise either require extended system outages to perforrn and/or cannot consistently provide accurate reliable results when utilized within the time constraints necessary for Cold Shutdown testing.
This alternate testing is acceptable in accordance with OM-10 pursuant to 10CFR50.55a(f)(4)(iv)if the related requirements of-OM-10 are implemented. The related requirements for check valve exercising during a refueling outage are paragraphs 4.3.2.2(e) and (h).
ALTERNATE TESTING: Perform forward flow exercise (FC) of these check valves once each refueling interval in accordance with the provisions of OM-10 paragraphs 4.3.2.2(e) and (h).
For check valves that are periodically verified through NIT techniques as being exercised, a sample plan may be employed.
When using NIT techniques in a sample plan, the guidelines within NUREG 1482 Section 4.1.2 muct be adhered to.
- 8. l.1.1 Rev.9 Page 170 of 236 i
[9] hdFUEL OUTAGE JUSTIFICATION RJO-09 SYSTEM' Reactor Core Isolation Cooling System, High Pressure Coolant injection System VALVES: CK 1301-47. CK-2301-40 CATEGORY. C CLASS: 2 FUNCTION: These are the Minimum Flow Check Valves for the Reactor Core Isolation Cooling (RCIC) System and the High Pressure Coolant injection (HPCI)
System. They open to provide a minimum flow path to prevent pump overheating and damage during low flow conditions. These valves close when each system is in standby to prevent backflow via the minimum flow line (from the interconnecting LPCI System) through the secured pump. The closed position for both valves also performs a containment water seal barrier function.
TEST REOUIREMENT: IWV-3521; l est Frequency - exercise at least once every three months, quarterly.
BASIS FOR These normally ciosed valves must be forward finw exercised by JUSTlFICATION: performing a specialized test. These valves are normally closed, which prevents backflow through a secured pump from the interconnecting LPCI System Torus return piping header. The exercise position is open which provides a minimum flow path to ,
prevent pump overheating and damage during low flow conditions.
Quarterly testing of these valves includes a partial forward flow exercise (PC). The closed normal position verification (AP) is performed once each refueling interval. The Appendix J water seal leak rate testing of each valve is performed on a periodic basis in
( accordance with the Appendix J testing matrix.
Testing these valves to the frequency established by IWV-3521 would cause an undue hardship.
(Continued)
- 8. l.1.1 Rev. 9 Page 171 of 236
~ __._
[9] REFUEL OUTAGE JUSTIFICATION RJO-09 (Continued)
OM-10 permits ceferral of full-stroke exercising until refueling outages when this testing is not practical during power operation or Cold Shutdowns. Performing a forward flow exercise dunng power operations or Cold Shutdowns is impractical because it requires manipulating the system (to establish test flow conditions) over an extended period of time to ensure accurate and repeatable results.
Permanent plant installed nonintrusive test equipment does not exist for either of these systems. The alternative method of using portable diagnostic test equipment which is used to verify a forward
- flow exercise requires a lengthy penod for setup, test conduct, l acceptance, and restoration. All other methods considered for l conducting a forward flow exercise either require Extended system outages to perform and/or cannot consistently provide accurate reliable results when utilized within the time constraints necessary for Cold Shutdown testing.
(
This alternate testing is acceptable in accordance with OM-10 pursuant to 10CFR50.55a(f)(4)Ov)if the related requirements of OM 10 are implemented. The related requirements for check valve exercising during a refueling outage are paragraphs 4.3.2.2(e) and (h).
ALTERNAl E TESTING: Perform open partial stroke exercise (PC) for each valve quarterly during pump testing. Perform forward flow exercise (FC) of these check valves once each refueling interval in accordance with the provisions of OM-10 paragraphs 4.3 2.2(e) and (h).
- 8. l.1.1 Rev.9 Page 172 of 236
[10) REFUEL OUTAGE JUSTIFICATION RJO-10 SYSTEM: As Applicable VALVES: Check valves requiring closed alternate position verification (AP) as listed within this relief.
CATEGORY: AC CLASS: 1,2,3 FUNCTION: These valves are required to return to their normally closed position to perform their function or minimize seat leakage for containment isolation purposes.
TEST REOUIREMENT: IWV-3521; Test Frequency - exercise at least once every three
, months.
I-BASIS FOR REllEF: These check valves are required to return to their r.ormal closed position to perform their function and/or limit seat leakage for Primary Containment iolation. Obtaining a satisfactory seat leakage test (normally performed during a refuel outage) ensures that each valve's obturator has returned to the normal closed position. Attempting to venfy their closed position by "other positive means" or by performing seat leakage tests on a quarterly or Cold Shutdown basis is not practical and would place undue hardship on the plant.
Permanent plant-installed nonintrusive test equipment does not exist fo,r verifying disc position for any of these listed valves. Other methods using portable equipment (e g., acoustic, ultrasonic, magnetic, and radiography) which may be used in performing a closure verification on a quarterly or Cold Shutdown frequency -
have been reviewed and determined to be not practical. Portable methods require special test equipment to be installed and benchmarked prior to gathering final test data. These alternate testing methods either require extended system outages to perform and/or cannot consistently provide accurate reliable results when utilized within the time constraints necessary for quarterly or Cold Shutdown testing.
(Continued) 8.1.1.1 Rev.9 Page 173 of 236
- . [10] REFUEL OUTAGE JUSTIFICATION RJO-10 (Continued)
Seat ieak testing (normally performed during a refuel outage) in accordance with 10CFR50 Appendix J will be used to verify the .
I normal closed position of these valves. During refueling intervals when Appendix J leak testing will not be conducted, the c!osure verification will be performed using other methods. The alternate rnNhods will either utilize.1) leak testing using water or air to venfy valve closure or 2) specialized testing that manipulates system flow and uses portable nonintrusive test equipment to document valve closure. These valves are tabulated as part of this justification with a brief explanation of the unique hardship or impracticality of testing.
This alternate testing is acceptable for implementation in accordance with OM-10 pursuant to 10CFR50.55a(f)(4)(iv)if the related requirements of OM-10 are implemented. The related
- requirements for exercising during refueling outage are paragraphs 4.3.2.2(e) and (h).
ALTERNATE TESTING: Perform the closed normal position verification (AP) for these check valves during each refueling interval in accordance with the provisions of OM-10 paragraphs 4 3.2.2(e) and (h).
REQUIRED BY SER (TAC NO. 74785)- ANOMALY #19 CONFORMS TO SEP. (TAC NO 85069)- ANOMALY #5 (Continued) 8.1.1.1 Rev.9 Page 174 of 236
[10) REFUEL OUTAGE JUSTIFICATION RJO-10 (Continued)
I Valve No (s) Description 9-CK 340 These valves are the inboard containment isolation valves (Type C tested) 9-C K-341 for the Drywell and Torus Nitrogen Makeup System. This makeup system is part of the Primary Containment Atmosphere Control System and ensures a source of nitrogen to maintain the inerted condition of containment These valves are exercised periodically in the open direction. The most practicai method of closed normal position verification (AP)is during an Appendix J seat leakage test or simplified closure test which also measures seat leakage. These tests require isolating the line to inis penetration (which would make Containment Atmospheric Dilution System components unavailable) and installing test equipment. Therefore, testing to verify normal closed position more frequently than once each refueling interval results in a hardship and unusual difficulty without a compensating increase in the level of quality and safety due to an increase in personnel radiation exposure, loss of system availability, and manpower constraints.
31-CK-434 This is an inboard containment isolation valve (Type C tested) in the nitrogen line which supplies a remote air operated exerciser for exercising the Torus to Reactor Building Vacuum Breakers. This check valve is exercised open quarterly during vacuum breaker testing The only practical method of normal closed position verification (AP)is during an Appendix J seat leakage or simplified closure test which also measures seat leakage. These tests require climbing tc the top of the Torus to allow valve lineup and test equipment installation. This location is a high radiation area and difficult to access. Testing to verify normal closed position more frequently than once each refueling interval results in a hardship and unusual difficulty without a compensating increase in the level of safety because of the increase in personnel radiation exposure and the safety risks associated with working on top of the Torus.
CK-1101-16 This valve is part of the Reactor Coolant pressure boundary for the Standby Liquid (reactivity) Control (SLC) System This check valve performs a containment isolation function and forms the Code Class break between Class 1 and Class 2 SLC piping A seat leakage test or a closure test using seat leak methods is the most practical method for verifying the normally closed position. Because conducting a forward flow exercise requires initiating the SLC System and injecting into the Reactor Vessel (refer to RV-08), nonintrusive methods to verify closure can only be conducted infrequently (once each refuel outage).
Therefore, verifying the closed normal position venfication (AP) more frequently than once per refueling interval would create a hardship without a compensating increase in the level of safety.
(Continued)
- 8. l.1.1 Rev. 9 Page 175 of 236
[10] REFUEL OUTAGE JUSTIFICATION RJO-10 (Continued)
Vaive Nois) Descriotion CK-2301-45 These valves are containment isolation valves (Type C tested) between CK-2301-74 the HPCI turbine exhaust header and the suppression pool (Torus).
CK 2301-218 The most practical method available to verify each valve's closed normal position ' $P)is to perform an Appendix J seat leakage test or closure ;
venfication using leak test methods. This testing requires erection of scaffolding, isolation of the penetration, and installation of test equipment.
Venfying the closed position more frequently than once each refueling interval would be a hardship without any compensating increase in the level of safety due to increased personnel radiation exposure and prolonged periods of safety system inoperability.
10-CK-515 These valves are water-tested containment isolation valves for the Core CK-1301-47 and Suppression Pool Cooling and Reactor Vessel Level Makeup systems.
CK-1301-59 These valves require testing to assure that the seal-water (Torus) fluid CK-1301-64 inventory is sufficient to maintain the sealing function for at least 30 days, CK-2301-40 The most practical method available to verify each valve's closed normal CK-2301-217 position (AP)is to perform an Appendix J seat leakage test or closure CK-1301-40' verification using water leak test methods Testing requires isolating CK-1301-41
- the penetration, in some cases the erection of scaffolding, and installation CK-1400 " of test equipment. Testing often requires personnel to enter high radiation CK-1400 ; areas Verifying the closed position more frequently than once each CK-2301-34* refueling interval would be a hardship without any compensating increase in the level of safety due to increased personnel radiation exposure and prolonged periods of safety system inoperability. The asterisk
- valves are not required to be designated category "AC", but their "AP" test is normally performed (using leak test methods) in conjunction with the other valve seat leakage tests.
8.1.1.1 Rev.9 Page 176 of 236
7.4 VALVE TESTING PROGRAM OPERATIONS AND MAINTENANCE (PART 10)
JUSTIFICATIONS Valve Operations and Maintenance (Part 10) Justifications [OM-10 or OM(10)) are provided for conditions in which compliance to ASME Code,Section XI. Subsection l\W test requirements cannot practically be satisfied. These justifications allow for the implementation of portions of ASME/ ANSI OM 10 pursuant to 10CFR50 55a(f)(4)(tv) without requesting formal l relief. Each OM-10 Justification identifies: valve (s) involved, test requirement (s) of l noncompliance, basis for justification, alternate testing, and test frequency.
l I
- 8. l.1.1 Rev.9 Page 177 of 236
[1] VALVE JUSTIFICATION OM(10)-01
- i. - SYSTEM: As Applicable L
VALVES' Containment isolation Valves -
CATEGORY.i A and AC ~
CLAS_S_: 1 and 2 FUNCTION: These valves provi the Pnmary Containment isolation barriers to minimize the consequences of an accident.
TEST REQUIREMENT: IWV-3422; Test Frequency - tests shall be conducted at least once every two years.
= BASIS FOR The NRC issued License Amendment No.167 for the Pilgrim JUSTIFICATION: Nuclear. Power Station on October 4,1996. The amendment allows BECo to implement Option B of Appendix J and to establish-a performance-based leakage rate test interval for the containment isolation valves subject to leakage testing. This Operations and -
Maintenance (Part 10) Justification reviews and resolves the test frequency inconsistencies that exist between the 1986 ASME B&PV Code,Section XI and the adopted Option B of 10CFR50 Appendix J. '
The 1986 Edition of Section XI of the ASME B&PV Code includes requirements for valve leak rate testing in paragraph IWV-3420.
These rules are applicable to all Category A valves. Position 10 of
-GL 89-10 indicated that all containment isolation valves included in the Appendix J program should be included in the IST Program as Category A (for power operated) valves or Category AC (for check) valves, as applicable. In Position 10 the NRC stated that the valve leakage requirements of Appendix J were considered equivalent to the requirements of IWV-3421 through IWV-3425, but that licensees must comply with the analysis of leakage rates and corrective action requirements of IWV-3426 and 3427(a).
The requirements of IWV-3421 through IWV-3425 apply to scope, ;
frequency,. differential test pressure seat ..'akage measurement, and test medium. Paragraph IVN-3422 requires a test frequency of at least once every two years. The leak rate testing of valves in )
Appendix J at the time GL 89-04 was issued required tests to be performed during each reactor shutdown for refueling, but in no case at intervals greater than two years. The performance-based interval in the new Option B of Appendix J is not equivalent to the frequency required by IWV-3422.
(Continued)
- 8. l.1.1 Rev.9 Page.178 of 236
[1] VALVE JUSTIFICATION OM(10)-01 (Continued)
Paragraph 4.2.212 of OM-10 specifies the reouirements for containment isolation valves as follows:
Category A valves, which are containment isolation valves, shall be tested in accordance with federal regulation -
10CFR50 Appendix J. Containment isolation valves which also provide a reactor coolant system pressure isolation function shall additionally be tested in accordance with paragraph 4.2.2.3.- ,
Paragraph 4.2.2.3 of OM-10 gives the requirements for leak rate testing for valves other than containment isolation valves, including frequency, differential test pressure, test medium, analysis of
. leakage rates, and corrective action. The frequency requirements for containment isolation valves would be specified by Appendix J.
Paragraph (b)(2)(vii of Section 50.55a modified the requiremants of OM-10 for lST of) containment isolation valves. Specificaliy, paragraph (b)(2)(vii) requires that, when using OM-10 for IS T,-
leakage rates for Category A containment isolation valves t'iat do not provide a reactor coolant system pressure isolation fun.: tion must be analyzed in accordance with paragraph 4.2.2.3(e) of OM-10 and corrective actions for these valves must be made in accordance with paragraph 4.2.2 3(f) of OM-10.~ Therefore, conducting IST in accordance with OM-10 does not preclude the -
use of Option B of Aapendix J for establishing a '
performance-based eakage monitoring schedule for leak testing containment isolation valves.
Use of portions of OM-10 is allowed pusuant to the provisions in 10CFR50.55a(f)(4)(iv) provided that all related requirements are
-met. The related portions of OM-10 for leak rate testing of containment isolation valves are paragraphs 4.2.2.2,4.2.2.3(e),
and 4.2.2.3(f). Approval for use of portions of editions or addenda has been granted as acceptable within the Safety Evaluation Report (with attached TER) by the Office of Nuclear Reactor Regulation related to the Inservice Test Program and Requests for
- Relief, Pilgrim Nuclear Power Station Docket No. 50-293, dated 6/23/93 (TAC No. M85069).
3 ALTERNATE TESTING: Perform seat leakage testing (test requirements LJ and LJW) of containment isolation valves in accordance with the provisions of OM-10 paragraphs 4.2.2.2,4.2.2.3(e), and 4.2.2.3(f). Containment
' isolation valves which also provide a Reactor coolant system pressure isolation function (test requirement LP) shall additionally ae tested in accordance with OM-10 paragraph 4.2.2.3.
Use of OM-10 Alternate Testing Requirements approved in NRC Safety Evaluation Report dated 6/23/93 (TAC No. M85069).
- 8. l.1.1 Rev.9 Page 179 of 236 i
7.5 VALVE TESTING PROGRAM RELIEF REQUESTS Valve Relief Requests (RV) are provioed for conditions in which compliance to ASME Code,Section XI, Subsection itW test requirements cannot practically be satisfied. Each Relief Request identifies: valve (s) involved test requirements (s) of noncompliance, basis for relief, Ond alternate testing c
8,l.1.1 Rev.9 Page 180 of 236
[1] RELIEF- REQUEST RV-01 a RETRACTED 8.1.1.1 Rev. 9 Page 181 of 236
[2]. RELIEF REQUEST RV-02 SYSTEM: Compressed Air System (31).
, VALVE 167 CATEGORY: AC CLA3S: 2 FUNCTION: ~ This valve is the nitrogen / instrument air to Drywell inboard isolation valve for Primary Containment isolation.
TEST REQUIREMENT: IWV-3521; Test frequency - exercise at least once every three months, quarterly.
BASIS FOR REllEF: This check valve is the Primary Containment isolation valve for a system considered inservice during plant operation. The no_rmally open check valve requires a reverse flow exercise. Leak testing (in accordance with 10CFR50 Appendix J) ensures valve exercising in the closed direction.
The open normal position venfication (AP) can only be performed by entering the containment (Drywell) environment, isolating components supplied by Drywell instiument air, and allowing unrestricted instrument air to escape through a test connect' n, Drywell components which will be isolated include: Inboarc MSIVs and Main Steam Relief Valve Accumulators, Equipment and Floor Drain Sump instrumentation, and Drywell air-operated valves (i.e.,
Rx Head Vent, Rx Sampling, and Rx Seal Drain). To conduct testing for the open normal position (AP) verification other than during a refueling interval would result in a hardship without any
- compensating increase in the level of safety due to excessive Drywell component isolation and an increase in personnel radiation exposure.
- ALTERNATE TESTING: Perform reverse flow exercise (FC) and open normal position l verification (AP) during each refueling interval.
CONFORMS WITH SER (TAC NO. 74785)- ANOMALY #19 PREAPPROVED BY SER, PER GL 89-04 8.l.1.1 Rev,9 Page 182 of 236 Y
[3] RELIEF REQUEST RV-03 SYSTEM: Containment Atmosphere Control System (15)
VALVES: X-201 A X 201E X-201J X 201B X 201F X-201 K X-201C X-201 G X-201D X-201 H CATEGORY: AC CLASS: 2 FUNCTION: These valves are the pressure Suppression Chamber to Drywell vacuum breaker valves which equalize the pressure between the two volumes when the Suppression Chamber pressure exceeds '..., Drywell pressure.
TEST REQUIREMENTS: IWV 3420, Valve i.eak Rate Test.
ANSI /ASME OM-1-1987; Section 1.3.4.3, Primary Containment Vacuum Relief Valves (Set Pressure).
BASIS FOR RELIEF: A specific maximum leakage per valve is not applicable to the vacuum breaker valve testing A gross leakage (go/no go) pressure decay test is performed on the pressure Suppression Chamber atmosphere in accordance with PNPS Technical Specifications on a quarterly basis The IWV-3420 valve leak rate test requirements shall be verified by a pressure decay test which identifies a specific leakage rate from the Drywell to the pressure Suppression Chamber atmosphere in accordance with the PNPS Technical Specifications on a refueling interval basis.
ANSI /ASME OM-1 requires operability testing of Primary Containment vacuum relief valves at a six month frequency. This testing standard states, 'The valves shall be actuated to verify open and close capability, set pressure and performance of any pressure and position sensing accessories" These vacuum relief valves have restricted access which prevents normal set pressure verification during power operation. These valves are located within a hazardous environment (N2 inerted) and require removal of a bolted primary containment (Torus) manway hatch and installation of temporary lighting for set pressure verification.
These valves are exercised quarteri They also receive Technical Specifications required manual manipulation with position switch calibration and functional testing, which is performed locally every refueling interval. Set pressure verification is accomplished using a test gauge (i.e., push-type) on the valve disk in conjunction with the Technical Specifications required testing.
(Continued)
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(3) RELIEF REQUEST RV-03 (Continued)
ALTERNATE TESTING: Valve leak rate test req airements shall be demonstrated in accordance with PNPS Technical Specifications.
Valve set pressure operability test shall be performed in conjunction with the Technical Specifications required testing once every refueling interval 1%W 3420: GRANTED PER SER (TAC No. M85069)
OM 1: GRANTED PER SER (TAC No. M88198) 8.1.1.1 Rev 9 Page 184 of 236
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[4] RELIEF REQUEST RV-04 SYSTEMS: All Applicable
~ VALVES: All Applicable CATEGORIES: A,B CLASSES: All Applicable FUNCTION: Not Applicable TEST REQUIREMENT: ItW.3417(a) Corrective Action Df. SIS FOR RELIEF: Valves designed to be rapid acting have extremely short stroke times, Since these valves stroke fast it is difficult to time them accurately and any deviation in trended time could be due to reaction time of the individual performing the testing rather than any change in the valve's performance. Because of the rapid action of these valves, a 2 second acceptance limit will be used and stroke times will not be recorded and trr nded, Valves i exceeding the 2 second limit will be declared inoperable.
ALTERNATE TESTING: Verify that all valves classified as rapid acting have stroke times of less than 2 seconds. No stroke time recording or trending will be performed.
PREAPPROVED PER GL 89 04, REFERENCE SER (TAC NO. 74785) 8.1.1.1 Rev.9 Page 185 of 236
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-[5]- RELIEF REQUEST RV-05 SYSTEM: . Traversing in-core Probe System-(45)
VALVE:: "N2Purge Supply Check -
CATEGORY: AC i
l CLASS: 2' FUNCTION:- This valve serves as the outboard Primary Containment isolation valve for the TIP purge system.
TEST REQUIREMENT: IWV-3521; Test frequency exercise at least once every three months, quarterly, BASIS FOR RELIEF: This check valve is the Primary Containment isolation valve for a system considered inservice during plant operotion. This normally partially open check valve requires a reverse flow exercise. Leak testing (in accordance with 10CFR50 Appendix J) ensures valve exercising in the closed direction.
The open normal position verification (AP) of the valve cannot practically be performed dunng normal operation or Cold Shutdown. Open position verification can only be obtained during purging evolutions or by special testing using'a vent path. System purging is normally only conducted fo; lowing TIP System maintenance or Appendix J leak testing and requires access into the Drywell. Normal position verification testing requires access into the Drywel! and disassembly of a flanged connection to obtcin the needed vent path. Therefore, to verify open position during plant operation or Cold Shutdown creates undue hardship resulting from Drywell environmental safety concerns and increased personnel radiation exposure.
ALTERNATE TESTING: Perform exercise and open normal position verification (AP) at least once every 2 years.
CONFORMS WITH SER (TAC NO,74785)- ANOMALY #19 PREAPPROVED BY SER, PER GL 89 04
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-[6]' RELIEF REQUEST RV-06 GYSTEM: Core Spray System (ir0) iVALVESi .9A,9B CATEGORY: - AC CLASS: 1 FUNCTION: These valves are the Core Spray injection Pressure isolation Check Valves.
TEST REQUIREMENT: IWV-3521; Test frequency - exercise at least once every three months, quarterly.
~ BASIS FOR RELIEF: Testing these valves during normal operation would require injecting cold water into the Reactor Vessel using the Core Spray System. This would result in both a reactivity excursion and thermal shock to the Reactor Vessel and spray sparger. Testing these valves during Cold Shutdown could cause a thermal shock to the Reactor Vessel when the vessel metal temperature is greater.
than 212 F.
The suppression pool is the Core Spray System's water source.
Injection of suppression pool water into the Reactor Vessel during Cold Shutdown results in exceeding the EPRI Water Chamistry Guidelines which PNPS has adopted to preclude the initiation and propagation of intergranular stress corrosion cracking in Reactor coolant stainless steel components. The chemistry of the suppression pool water (typical conductivity of 4 to 5 pmho/cm) does not meet the chemical requirements of the Reactor coolant (typical conductivity of 0,15 to 0.3 prnho/cm). Restart of the Reactor is not permitted until the Reactor coolant water ch9mistry is within the EPRI Guidelines.
In addition, the amount of water that is injected into the vessel
-during the test of only one of the Core Spray injection check valve results in significant vessel level increase and may cause a vessel isolation. This would extend the length of a shutdown since the only means of water removal from the Reactor is via the Reactor Water Cleanup System line to the condenser.
The forward flow exercise of the injection check valves will require Reactor Vessen level control out of the normal parameter and a bleed and feed of the core spray system to improve water quality prior to testing.
ALTERNATE TESTING: Exercise valves each refueling interval.
PREAPPROVED PER GL 89-04, REFERENCE SER (TAC NO,74785)
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[7) RELIEF REQUEST RV-07 RETRACTED 8.l.1.1 Rev.9 Page 188 of 236
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-[8] REllEF REQUEST RV-08 i
- SYSTEMi Standby Liquid Control System (1101)
VALVESi 15,16
- - CATEGORY
- AC-l CLASS: 1
[ FUNCTION: - These valves are the SLC injection check valves.
l TEST REQUIREMENT: IWV-3521; Test frequency - exercise at least once every three months, quarterly.
BASIS FOR REllEF: To verify forward flow during normal operation or Cold Shutdown would require firing a squib valve and injecting water into the -
. Reactor Vessel using the SLC pumps. Injecting water during l operation could result in adverse plant conditions such as changes l in reactivity, power transient, thermal shock indue.ed cracking, and j possible plant trip, injecting water during a Cold Shutdown can
- result in cyclical thermal shock-induced cracking as cold water j- enters the Reactor Vessel which is at an elevated temperature due to decay heat.-
1 i injection of the SLC System during Cold Shutdowns using
- demineralized water requires a lengthy flushing operation to remove boron from the system. Even after extensive flushing, boron remains present in system dead legs. Some of this boron
- _ propagates into the Reactor Vessel during injection and is difficult
- to remove from the system. The presence of boron in Reactor water impedes the plants ability to achieve criticality for plant startup.
Verify forward flow operability during refueling while performing the
- Standby Liquid Control System injection test, which requires
- pumping demineralized water into the Reactor Vessel after firing at least one squib valve.
ALTERNATE TESTING: Exercise valves each refueling interval.
PREAPPROVED PER GL 89 04, REFERENCE SER (TAC NO 74785)-
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[9] RELIEF REQUEST RV-09 .
SYSTEM: Control Rod Drive Hydraulic System (302)
. VALVES: 114,115,126,127 (typical of 145 each)
CATEGORIES: B, C CLASS: 2 FUNCTION: These valves are the CRD Discharge Header Check (114), Accumulator Supply Check (115), Scram Inlet (126) and Outlet Valves (127).
TEST REQUIREMENTS: IWV-3411; Test frequency - exercise at least once every three months.
IWV-3413; Power operated valves - full stroke time.
IWV-3415; Fail safe - at least once every three months.
lWV-3521; Test frequency - exercise at least once every three months.
BASIS FOR RELIEF: These valves (with the exception of the 115) operate coincidentally to rapidly insert control rods and will be tested by Scram timing control rod drives in accordance with Technical Specifications Section 4.3. This requires testing of at least 10% of the drives every 120 days. Additionally 100% of the drives are tested during each shutdown that is greater than 120 days in duration.
The Scram inlet and Outlet Valves are power operated valves that full-stroke in milliseconds and are not equipped with indication for individual positions. Therefore, measuring their full-stroke time as required by the Code is impractical. Verifying that each associated control rod meets the control rod Scram insertion time limits is an acceptable alternate method for detecting valve degradation.
The Accumulator Supply Check Valves (115) will be verified as forward flow exercised by observing that their respective CRD accumulator fault lights clear following restoration from Scram time testing. In addition, this valve is verified closed by securing the CRD pumps and verifying an absence of annunciator indication or significant local pressure degradation from the HCU Scram Accumulators each refueling interval.
(Continued)
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[9] RELIEF REQUEST RV-09 (Continued)
ALTERNATE TESTING: Scram functional timing in accordance with plant Technical Specifications will be used to verify individual valve fail-safe and exercise testing for valves 114,126, and 127. The Accumulator Supply Check Valves (115) will be 1) venfied as forward flow exercised during restoration from Scram time testing and 2) have closed normal position verification ( AP) performed each refueling interval.
CONFORMS TO SER (TAC NO. 74785) ANOMAllES #11 & #12 PREAPPROVED BY SER PER GL 89 04
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[10]l REllEF REQUEST RV.-10
. SYSTEM: Control Rod Drive Hydraulic System (302)
. VALVES: 138 (typical of 145)
CATEGORY: C-CLASS: 2 FUNCTION: These valves are the CRD cooling water check valves. l TEST REQUIREMENT: IWV-3521; Test Frequency-exercise at least once every three months.
BASIS FOR REllEF: Failure of these valves to reverse flow exercise would be identified by applying 1) a notch out signal which would result in a CRD double-notch or 2) a notch-in signal which would result in a CRD non notch. Each partially or fully withdrawn operable control rod shall be exercised one notch at least once each week in ,
accordance with the Technical Specifications.
ALTERNATE TESTING: Exercise by meet;ng the surveillance requirements in PNPS Technical Specifications.
PREAPPROVED PER GL 89-04, REFERENCE SER (TAC NO. 74785) i i
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- [11] RELIEF REQUEST RV-11 RETRACTED 4
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(12) RELIEF REQUEST RV-12 RETRACTED 8.1.1.1 Rev.9 Page 194 of 236
[13) RELIEF REQUEST RV-13 RETRACTED
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[14] RELIEF REQUEST RV 14 l
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[15} RELIEF REObEST RV-15 RETRACTED i
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I (16] RELIEF REQUEST RV 16 RETRACTED
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[17) RELIEF REQUEST RV 17 SYSTEM: Contrm Rod Dri,e Hydraulic System (302)
VALVES: 120, u1,122,123 (Typical of 145)
CATEGORY: B CLASS- 2 FUNCTION- Direct Control Rod Drive (CRD) for the insertion and withdrawal of control rods.
TEST REQUIREMEN1 s IVN 3411; Test Frequency exercise at least once every three months.
IVN 3413; Power operated valves Full stph: tirne.
IWV 3415; Fail safe at least once every three months.
BASIS FOR REllEP The insertion and withdrawal of control rods is accomplished via positioning of these valves. The CRD Units are integrally constructed components. Notching of control rods causes rapid position changes to these valves The recording of stroke time (e g., less than a tenth of a second) would only be indication of electrical circuitry delay and human response errors. Proper insertion / withdrawal by notching shall verify valve operability, ALTERNATE TESTING: Verify control rod movement by notching weekly.
APPROVED BY SER (TAC NO. 74785) l l
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[18) REllEF REQUEST RV 18 SYSTEM: Nuclear Boiler Compressed Air (31) val.VES: 84A,848,84C,84D,85A,858,85C,BSD CATEGORY- C CLASSi NC l FUNCTION: These valves open to allow normal opening of the MSIVs and recharging of the $
TEST REQUIREMENT: IWV-3522(b); Normal Close Valves exercise procedure. ;
BASIS FOR REllEF: These check valves are required to supply nitrogen / instrument air ;
to recharge air accumulators during each Main Steam isolation Valve (MSIV) full stroke cycle. The air volume of these accumulators is required for satisfactory MSIV close stroking but is not sufficient to open an MSIV. Failure of a check valve to adequately open (forward flow exercise) would 1) impede accumulator recharging and 2) impair the normal opening function of its MSlV.
The MSIVs are stroke timed in the open direction when exercised in accordance with IWV 3411. The associated MSIV opening time will be observed and compared to an established limit to ensure that each accumulator check valve has opened sufficiently to pass the required flow for recharging the accumulator. Monitonng the associated MSIV opening time is an acceptable alternate method for detecting degradation of these check valves.
The closed normal position verification (AP) of these valves requires depressurization of the MSIV accumulator supply air and a bleod down of the accumulator pressure. These accumulators are required for normal operation of the MSIVs and depressurization will require access to the Drywell and Steam Tunnel for prolonged periods of time, imposing additional ALARA >
concerns. Testing for normal position verification other than during
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a refueling interval results in hardship without a compensating .
increase in the level of safety due to prolonged periods of component inoperability and increase radiation exposure. ,
ALTERNATE TESTING: Verify forward flow exercise of each check valve by monitoring the open stroke time of their respective MSIV. Also, verification of these valves closed normal position (AP) will be performed during each refueling interval.
CONFORMS WITH SER (TAC NO. 74785) ANOMA1.lES #13 & #19 -l 8.1.1.1 Rev. 9 Page 200 of 236
[19] RELIEF REQUEST RV-19 SYSTEMS: Diesel Generator Air Start System (47)
Diesel Generator Turbo Air System (47)
VALVES: 4586A. 45868, 4587A. 45878, 4588A, 45888, 4589A, 45898, 4569A,45698,4570A.4570B CATEGORY: B CLASS: NC FUNCTION- These air start solenoid valves provide starting air to the emergency diesel generator.
TEST REQUIREMENTS: IWV-3411: Test Fregt.ency . exercise at least once every three months.
lWV 3413; Power operated valves - full stroke time.
lWV 3415; Fail safe - at least once every three months.
BASIS FOR REllEF: Valve design does not allow for any valve position indication venfication. During the Diesel Generator Alternate Air Bank Start monthly surveillance, failure of a valvo to perform its open function will result in an increase in the starting time. Also, failure of the valve to close will cause starting air to not secure.
6_LTERNATE TESTING: Valves shall be verified operable during monthly diesel generator Technical Specifications surveillance testing. The starting time will be monitored and trended to determine valve operability.
PREAPPROVED PER GL 89 04, REFERENCE SER (TAC NO. 74785) 8.l.1.1 Rev.9 Page 201 of 236
[20] RELIEF REQUEST RV 20 RETRACTED
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[21] RELIEF REQUEST RV 21 SYSTEM; Reactor Water Cleanup System (1201)
VALVE: 81 CATEGORY- C CLASS: 1 FUNCTION: This valve provides the path for RWCU return flow to the Reactor Vessel.
TEST REQUIREMENT: IWV 3521; Test Frequency exercise at least once every three months.
BASIS FOR REllEF- The Reactor Water Cleanup return check valve shall be reverse flow exercised. This normally open check valve is verified in the closed direction by isolating the RWCU return header, pressurizing the feedwater header, and venting the piping on the upstream side of this check valve to verify restricted flow. Controlled pressurization of the feedwater header to perform this test occurs during hydrodynamic leakage testing of the RCIC Pressure Isolation Valves each refueling interval.
l During Cold Shutdown conditions, this system is required to be l
operable in order to control Reactor water level and primary system chemistry. Pressurization of the Feedwater Header for Hydrodynamic Leak Testing requires extensive valve alignment to the Feodwater System and renders both the Feedwater and RWCU Systems inoperable for an extended period of time.
ALTERNATE TESTING: Exercise valve during hydrodynamic leak testing each refueling interval.
APPROVED DY SER (TAC NO. 74785) l l
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[22] RELIEF REQUEST RV 22 SYSTEMS: Core Spray System (1400)
High Pressure Coolant injection System (2301)
Reactor Core Isolation Cooling System (1301)
Reactor Water Cleanup System 1201)
Recirculation Pump Instrumentat(ion (262)
Nuclear Boiler Instrumentation (261)
Nuclear Boiler Instrumentation (263)
VALVES: All Applicable CATEGORY: AC CLASS: 1,2 :
FUNCTIO $ These excess flow check valves provide Primary Containment isolation in case i of an instrument line break. ,
TEST REQUIREMENT: IWV-3521; Test Frequency - exercise at least once every
, three months.
, IWV 3422; Frequency - test shall be ccnducted at least once every r 2 years.
BASIS FOR REllEF: These excess flow check valves are the Primary Containment isolation valves for systems considered inservice during plant operation. These normally open instrument isolation check valves require a reverse flow exercise. Leak testing (in accordance with ASME Code) performs valve exercising in the closed direction t each refueling interval. Following the leak test a normal open position verification is performed to each valve.
The leak rate testing of excess flow check valves requires the Reactor coolant pressure boundary (Class 1) to be at a pressure of at least 600 psig. Testing requires valving out instruments which '
have a high arobability of causing a safety system function initiation anc/or isolation. Therefore, the plant should be shutdown -
for testing, During plant shutdowns, the Reactor coolant pressure boundary is not pressurized except when performing the .
l once per-refueling outage ASME Boiler and Pressure Vessel I Code,Section XI System Leakage Pressure Test. The excess flow check valve leak testing is conducted during this system leakage nressure test.
l ALTERNATE TESTING: Perform exercise, leakage test and open normal position ;
- verification (AP) to these valves during each refueling interval. !
l CONFORMS WITH SER (TAC NO. 74785) ANOMALY #19 APPROVED BY SER I
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[23] RELIEF REQUEST RV-23 SYSTEM: Diesel Oil Transfer System (38)
VALVES: 116A.116B CATEGORY: C CLASS: NC FUNCTION: These valves provide the supply path for diesel fuel oil for running the Emergency Site Diesel Generators.
TEST REQUIREMENT: IWV 3522; Check Valve Full Flow Exercising - exercise at least once overy three months.
BASIS FOR REllEF: These check valves, located within the day tank, are required to supply fuel oil to each emergency diesel generator. Failure of a check valve to open (forward flow exercise) would deprive the diesel of fuel. Inadequate supply of fuel oil would cause the diesel load handling capabilities to be impaired during surveillance testing, Therefore, proper operation of each emergency diesel generator during full load testing verifies the check valve forward flow exercise.
ALTERNATE TESTING: Emergency diesel operability testing will verify check valve forward flow exercise, APPROVED BY SER (TAC NO. 74785) l l
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[24) RELIEF REQUEST RV 24 RETRACTED l
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[25) RELIEF REQUEST RV 25 RETRACTED i
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[26] RELIEF REQUEST RV.26 SYSTEM- Control Rod Drive Hydraulic System (302)
VALVES: 21A,218,22A,228,23A.23B,24A,24B CATEGORY: A CLASS: 2 FUNCTION: These valves close to isolate Reactor. coolant flow past the Control Rod Drive seals during a Scram condition. They open to drain the Scram Discharge Volume Tank and allow a Scram condition to be reset.
TEST REQUIREMENT: -lWV 3413; Power operated valves + full stroke time (closed) i BASIS FOR REllEF: These air operated valves are stroked closed quarterly using a separate testing air vent (bleed) circuit. Stroke times using the test -
circuit can only verify the valve's closed exercise since the closing stroke times are very erratic. Timing of the valve's closing stroke using the test circuit quarterly provides meaningless data for tracking valve performance. The only method available to close stroke time these valves is by initiating a Reector Scram. Trending these valves in the closed direction by Scramming the Reactor quarterly is impractical. Valve open stroke times are measured and trended quarterly to monitor for valve degradation.
Once per refueling outage, in accordance with Technical Specifications, a full Reactor Scram is initiated which utilizes the normal vent circuit for these valves. Since the Technical Specifications surveillance requirement is being satisfied, then the test frequency assures that the necessary quality of systems and components is maintained, that facility operation will be within the safety limits, and that the limiting condition for operation will be met. Therefore, the proposed alternate testing provides an-acceptable level of quality and safety.
ALTERNATE TESTING:' Measure close stroke times by inserting a full Reactor Scram in accordance with Technical Specifications not to exceed a refueling interval.
CONFORMS WITH SER (TAC NO. 74785) ANOMALY #10
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[27] RELIEF REQUEST RV 27 SYSTEM: As Applicable VALVES: 100120,10012D.130124.1301 7.1301-40,130159,1301-63, 1400 13A,1400 13 B, 2301 34, 2301 -39, 2301 217 CATEGORIES: AC and C CLASS: 1,2, 3, and NC FUNCTION: All check valves whose ability to fully open cannot be verified without disassembly.
TEST REQUIREMENT. lWV 3521; Test Frequency Exercise at least once every three months.
BASIS FOR RELIEF: These check valves are normally closed and must open to perform their function. System design inhibits the verUication of full open position during flow testing due to system configuration or limitations. These valves will be placed in a check valve disassembly program complying with the guidelines of Generic Letter 89 04. These check valves are identified in two tables that provide the justification for disassembly with the associated retests.
The two tables are: Table 1 - Disassembly to satisfy both the Exercise and Normal Position Verification and leible 2 -
Disassembly to satisfy the Exercise. Other check valves which require a disassembly to verify operability may be incorporated into this program as long as the alternate testing guidelines are followed.
ALTERNATE TESTING: A sample disassembly and inspection plan which selects one valve in each group to be disassembled every refueling outage will be utilized. Sample groups may consist of more than four valves; however, all valves within each group must be disassembled within I
a maximum of six years.
The sample disassembly and inspection program involves grouping similar valves and testing one valve in each group during each i refueling interval. The sampling technique requires that each valve l in the group be the same design (manufacturer, size, model l number, and materials of construction) and have the same service conditions including valve orientation. During each disassembly, the licensee will verify that the disassembled valve is capable of full stroking (through manual exercise) and that the internals of the valve are structura!!y sound (no loose or corroded parts).
(Continued)
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[27] RELIEF REQUEST RV 27 (Continued)
ALTERNATE TESTING- (Continued)
A different valve for ea:h group is required to be disassembled, inspected and manually full stroke exercised at each successive refueling interval until the entire grctp has been tested If the d sesserrbled valve is not capab'e of being full-stroke exercised or tnere is binding or failure of valve :n'ernals the remaining valves in that group must also be disassembled, inspected, and manually fuH stroke exercised during the same interval Once this is completed. the sequence of disassembly will be repeated unless extension of the interval can be juef i ed CONFORMS WITH SER (TAC NO. 74785) ANOMALIES #6 & #19 PREAPPROVED BY SER, PER GL 89 04
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TABLE 1 DISASSEMBLY TO SATISFY BOTH THE EXERCISE AND NORMAL POSITION VERIFICATION Valve No (s) Justification and Retest (If Apphcable)
CK 130127 These check valves are the suppression (Torus) water supply valves for CK 230139 the RCIC and the HPCI Systems. The function of these alternate suction paths is to provide automatic availabihty of Ttrus water upon either high suppression pool water level or low condensata storage tank (CST) level. Use of the Torus water suction path is not permitten within plant Operating Procedures and only with special controls during abnormal conditions unoer Emergency Operating Procedures. During normal operation, each check valve remains isolated by both upstream and downstream automatic actuated motor operated isolation valves Therefore. a partial or full exercise and closed normal position verification (AP) cannot be performed using system operating parameters and will be satisfied using the Check Valve Disassembly Program.
CK 1301-63 These check valves are the RCIC Vacuum Tank Condensate Pump CK 1301-24 discharge valves. Their function is to allow the condensate pump to reduce fluid level while preventing the backflow of condensate storage tank (CST) water into the vacuum tank when the RCIC System in its standby mode. Both valves are partial exercised during the quarterly RCIC pump test by monitoring appropriate syrtem parameters. The full exercise and closed normal position verification (AP) cannot be performed using system parameters or relevant test methods and will be satisfied using the Check Valve Disassembly Program.
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TABLE 2 DISASSEMBLY TO SATISFY THE VALVE Full EXERCISE Valve No (s) Just feation and Retest (If Arrhcable)
CK 1001-2B These are the "B" Loop LPCI Minimum Flow Check Valves Their normal CK 1001-2D operat4cnal position is closed which prevents backflow through a secured pump when the other pump in the loop is runn;ng The exercise position is cpen which provides a minimum flow path to prevent pump overheating and damage during low flow conditions Testing cf these valves includes a partial exercise and normal position verification (AP) dunng each quarterly pump test.
Since there is no quantitative method of verifying each valve's opening (full flow exercise) and due to turbulent minimum flow conditions, they have been incorporated into the Check Valve Disassembly Program.
CK 1301-40 These check valves are the RCIC Vacuum Pump Discharge Check CK-130159 Valves to the Torus. Their normal operational position is closed preventing Torus water backflow due to pressurization during an accident, The exercise position is open which provides a flow path for pumping noncondensable gases from the vacuum tank to the Torus Test:ng of these valves includes a partial exercise during each quarterly pump test and closed normal position verification (AP) during valve seat leakage test Since there is no quantitative method of verifying the valve's opening (full flow exercise), they have been incorporated into the Check Valve Disassembly Program.
CK-140013A These are the Core Spray Pump Minimum Flow Stop Check Valves. Their CK-1400138 normal operational position is closed which prevents backflow through respective secured pump. The exercise position is open which provides a minimum flow path to prevent pump overheating and damage during stadup.
Testing of these valves includes a partial exercise during each quarterly pump test. There is no quantitative method for verifying the opening of these valves (full flow exercise) using system flow due to turbulent minimum flow conditions. Since the full flow exercise (FC) and closed normal position verification (AP) cannot be performed us:ng system parameters or relevant test methods, they will be verified by using nonintrusive testing (NIT) techniques However, if these NIT methods provide inconclusive results, then the above requirements will be satisfied using the Check Valve Disassembly Program.
8l.1.1 Rev. 9 Page 212 of 236
TABLE 2 DISASSEMBLY TO SATISFY THE VALVE FULL EXERCISE Valve No (O Justification and Rotest (If Applicable)
CK 230134 These check valves are the HPCI Turbine Exhaust Drain Line Valves.
CK 2301217 They allow turbine enhaust drain pot condensate to be directed via steam traps to the Torus ana prevent Torus water backflow during Torus accident pressurization when HPCI is no lenger being used Testing of these valves includes a partial exercise during the HPCI quarierly pump test, and closed normal position verification (AP) during the valve seat leakage test. Since there is no quantitative method for verifying each valve's opening '_ full flow exercise), they have been incorporated into the Check Valve Disassembly Program.
8.1.1.1 Rev. 9 Page 213 of 236
[28) RELIEF REQUEST RV 28 RETRACTED I
8.1.1.1 Rev.9 Page 214 cf 236
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[28) RELIEF REQUEAT RV 28 RETRACTED
- 8. l.1.1 Rev.9 Page 214 of 236
[29) RELIEF REQUEST RV 29 RETRACTED 8.I.1.1 Rev. 9 Page 215 of 236
[30) RELIEF REQUEST RV-30 SYSTEMS: As Applicable VALVES As Applicable CATEGORIES A.AC CLASSES As Applicable FUNCTION Valves which are included within a pressure boundary that has a syst,.n integrity leakage criteria to ensure satisfactory performance of the system safety function. These system pressure boundaries are inclusive of numerous componentshtems (i.e., valves, piping. fittings, accumulators, and appurtenances) and, therefore, the entire boundary must comply with a specific leakage limit.
TEST REQUIREMENTS. lWV 3424; Seat Leakage Measurement IWV 342G; Analysis of Leakago Rates IWV 3427; Corrective Action BASIS FOR REllEF: Seat Leak Testing of valves categorized as "A" or "AC" normally involves a determination of specific leakage for each valve. Where a valve becomes an integral part of a pressure boundary, it no longer singularly maintains the specified leakage limit. Each component within the pressure boundary must be considered when trying to satisfy the Acceptance Cnteria since the valves cannot be tested independently. No one component or multiple components is allowed to leak in excess of the specified leakage limit which is less than or equal to that which would be assigned to the smallest valve as specified by the owner. The method commonly used to venfy leak tightness of a pressure boundary is a Pressure Drop (Decay) Test. The American Society for Nondestructive Testing (ASNT) provides testing guidance (
Reference:
ASNT Non Destructive Testing Handbook. Volume 1, Leak Testing) in which the results are equivalent and sometimes superior to Section XI, IWV 3420. This testing will be conducted at least once every 2 years.
This relief does not apply to Containment Isolation Valves, Pressure isolation Valves, or other valves that have a component specific leakage limit ALTERNATE TESTING: Perform Pressure Drop (Decay) Tests in lieu of IWV 3424, ikW-3425, and IkW 3427 utilizing a pressure boundary specified leakage limit.
CONFORMS WITH SER(TAC NO. 74785) ANOMALY #9 APPROVED BY SER
- 8. l.1.1 Rev. 9 Page 216 of 236
[31) REllEF REQUEST RV 31 RETRACTED
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8l.1.1 Rev.9 Page 217 of 236
[32) RELIEF REQUEST RV 32 SYSTEM: Reactor Building Closed Cooling Water System (30)
VALVFJ 4009A,4009B,4002 CATEGORIES' A.B QLASSES: 2. 3 FUNCTION. These valves provide isolation to Drywell components cooled by RBCCW.
The components would require isolation for Primary Containment critoria and maintenance.
TEST REQUIREMENTS- l\W-3411; Test frequency - exercise at least once every three months.
ItW 3413; Power operated valves full stroke time.
BASIS FOR REllEF The testing of these valves requires isolation of the following components; Drywell Area Coolers, Reactor Recirculation Pump Seal Coolers, Reactor Recirculation Pump Lube Oil Coolers.
Additionally, for testing the 4009A and 40098 the Reactor Water Cleanup (RWCU) non regenerative heat exchan er, B Fuel Pool Cooling Heat Exchanger. RWCU Pump Cooling stem Coolers, Control Rod Drive (CRD) Pump Area Cooling, an CRD Pump Thrust Bearing Coolers must also be isolated The listed components supply numerous plant systems required for safe plant operation. The recirculation pumps and Drywell coolers may be required to support the alant during Cold Shutdown conditions to 3revent water stratific&v iin the vicinity of Reactor Vessellower lead and overheating of Drywell components.
Exercising these valves quarterly during power operation is impractical because the resulting flow interruption could cause equipmerit damage. It also is impractical to exercise these valves during Cold Shutdown when Drywell cooling loads are high or when a Reactor recirculation pump is operating. Stopping of Reactor recirculation pumps during each Cold Shutdown to allow exercising these valves could result in extending the Cold Shutdown which would be costly and burdensome to the plant.
Therefore compliance to the Code test frequency is impractical.
The proposed alternate testing provides a reasonable alternative.
ALTERNATE TESTINQ: Exercise valves during Cold Shutdown when recirculation pumps and Drywell coolers are not required but not to exceed a refueling interval.
APPROVED BY SER (TAC NO. 74785)- ANOMALY #17
- 8. l.1.1 Rev. 9 Page 218 of 236
[33) RELIEF REQUEST RV 33 SYSTEM: Nuclear Boiler - Reactor Recirculation System (202)
VALVES: 5A, 5B CATEGORY. B CLASS- 1 FUNCTION: These valves are the Reactor recirculation pump discharge valves and function to close upon LOCA signals. (This is the remaining function of LPCI Loop Selection Logic)
TEST REQUIREMENTS: IVN 3411, Test Frequency exercise at least once every three months.
IWV-3412; Power operated valves full stroke time.
BASIS FOR REllEF- Closure of these valves during normal operation will result in loss of forced circulation to the Reactor, a condition prohibited by PNPS License.
Closure of these valves during Cold Shutdown necessitates securing operation of the Reactor recirculation pumps. This is detrimental because even though tne moderator temperature is less than 212'F, the recirculating system is usually kept in operation during Cold Shutdown to provide Reactor coolant mixing to prevent Reactor Vessel temperature stratification. The Reactor Vessel temperature profile takes on an increasing temperature gradient between the bottom vessel head and the shutdown core when mixing (forced circulation) is stopped. Additionally, the water in the idle recirculation loops cools down. This stratification can have the following adverse effects: Reactor Vessel temperatures become greater between the vessel bottom and top resulting in unnecessary thermal cycling, startup of the shutdown recirculation pump can cause a cold water intrusion affecting Reactor Vessel metal temperatures. Deliberate stopping and starting of the recirculation pumps 1) creates unnecessary cycling wear on major equipment important to plant reliability and 2) could result in extending the shutdown, both of which would be costly and burdensome to the plant. Therefore compliance to the Code test frequency is impractical. The alternate testing provides a reasonable alternative.
At. TERNATE TESTING: Exercise valves during Cold Shutdown when a respet.tive Reactor recirculation pump is not required. but not to exceed a refueling interval.
APPROVED BY SER (TAC NO,74785) ANOMALY #17
- 8. l .1.1 Rev.9 Page 219 of 236
[34] RELIEF REQUEST RV-34 SYSTEM. Reactor Building Closed Cooling Water (30)
VALVES' 4085A,4085B CATEGORY: B CLASS: 3 FUNCTION Valves 4085A and 4085B are the non safety related component isolation valves for RBCCW Loop A.
TEST REOUIREMENTS: IWV 3411; Test Frequency exercise at least once every three months.
IkW-3413; Power operated valves full stroke time.
BASIS FOR REllEF. Valves 4085A and 4085B are the non safety related component isolation valves for RBCCW Loop A Components cooled by this RBCCW branch include the Reactor recirculation pump motor-generator set fluid couphng oil and bearing coolers.
Siroke testing quarterly during power operation could result in loss of cooling to the recirculation pump motor-generator set fluid couphng oil and bearing coolers witn consequent loss of forced circulation to the Reactor, requinng plant shutdown.
Stroke testing at Cold Shutdown could result in loss of the recirculation pump operation due to interruption of cooling to the recirculation pump motor-generator set fluid coupling oil and bearing coolers. This is detnmental because even though the moderator temperature is less than 212*F, the recirculation system is kept in operation during Cold Shutdown to provide mixing of the Reactor coolant to prevent Reactor Vessel temperature stratification.
The Reactor Vessel temperature profile takes on an increasing temperature gradient between the bottom vessel head and the core when mixing (forced circulation) is stopped. Additionally, the water in the idle recirculation loops cools down. This stratification can have the following adverse effect: Reactor Vessel metal temperature differences become greater between Reactor Vessel bottom and top resulting in unwanted thermal cycling. Start up of the shutdown recirculation pumps causes a cold water intrusion which affects Reactor Vessel metal temperatures and causes thermal cycling of the Reactor Vessel.
ALTERNATE TESTING: Exercise valves during Cold Shutdown when Reactor recirculation pumps are not required but not to exceed a refueling interval.
APPROVED BY SER (TAC NO. 74785)- ANOMALY #17
- 8. l.1.1 Rev.9 Page 220 of 236
[35) RELIEF REQUEST RV-35 SYSTEM: Nuclear Boiler SRV Vacuum Relief (261)
VALVES: 96A,968,96C.97A.978,97C,97D,98A.9BB.9BC,98D CATEGORY, C CLASS NC FUNCTION: Vacuum breakers ensure that pressure is equahred for the main steam safety relief discharge lines.
TEST REQUIREMENT: l\W-3521; Test Frequency - exercise at least once every three months, quarterly, BASIS FOR REllEF: The SRV suppression pool discharge vacuum breakers provide a means for reheving the vacuum developed in the discharge lines caused by condensing steam. The vacuum breakers are located in the Drywell (Primary Containment) and are normally closed.
During power operation, the inerted Drywell environment is unsuitable for manned entry due to atmosphere and high temperature. The forward flow exercising and verification of normal closed position of these valves can only be performed manually. This method of exercising during power operation would have adverse safety and ALARA concerns. Forward flow exercising and closed normal position verification (AP) will be performed during Cold Sht idown when the Drywell is deinerted.
ALTERNATE TESTING. Perform exercise and closed normal position verification (AP) of these valves during Cold Shutdown (when Drywell is deinerted) not to exceed a refueling interval.
APPROVED BY SER(TAC NO,74785) ANOMAllES #17 & #19
- 8. l.1.1 Rev. 9 Page 221 of 236
[36) RELIEF REQUEST RV-36 SYSTEM: Nuclear Boiler Compress 3d Air (31)
VALVES: 372A,372B,372C,372D CATEGORY: AC CLASS: NC FUNCTION' These valves provide isolation and allow recharging of the 80S air accumulators.
TEST REQUIREMENT: IWV-3521; Test Frequency exercise at least once every three months, quarterly.
BASIS FOR RELIEF- These check valves with their associated air accumulators are located in the Drywell (Primary Containment) and are not accessible during normal plant operations. Check valve forward flow exercising will be accomplished by bleeding air through the air accumulators Therefore, exercising of these check valves will be performed during Cold Shutdown when the Drywell is deinerted.
ALTERNATE TESTINC: Exercise valves during Cold Shutdown (when Drywellis deineried) not to exceed a refueling interval APPROVED BY SER (TAC NO 74785) 8.1.1.1 Rev.9 Page 222 of 236
[37) RELIEF REQUEST RV-37 SYSTEM: As Applicable VALVES: - Check valves requiring seat leakage measurement for closed alternate position l verification (AP) as listed within this relief-CATEGORY: AC CLASS: 1,2,3 -
FUNCTION: These valves.are required to return to their normally closed position to minimize seat leakage.
TEST REQUIREMENT: lWV-3521; Test Frequency - exercise at least once every three months.
BASIS FOR REllEF: These check valves are required to return to their normal closed position to perform a safety function and limit sea 11eakage to a i specific amount. Conducting a satisfactory seat leakage measurement assures the valve's obturator has returned to the normal closed position. Permanent plant-installed nonintrusive test equipment does not exist for verifying disc position for any of these listed valves. Other methods using portable equipment (e 9.,
acoustic, ultrasonic, magnetic, and rac;ography) which may be used in performing a closure verification on a quarterly or Cold Shutdown frequency have been reviewed and determined to be not practical. - Portable methods require special test equipment to be installed and benchmarked prior to gathering final test data. These alternate testing methods either require extended system outages to perform and/or cannot consistently provide accurate reliable ,
results when utilized within the time constraints necessary for quarterly or Cold Shddown testing.
Therefore, attempting to ve-ify the closed position by other positive
^ means or by performance '.af seat leakage tests on a quarterly or Cold Shutdown basis is not practical and would place undue hardship on the olant: These valvos are tabulated as part of this relief with a briet explanation of the unique hardship or impracticality of testing.
- ALTERNATE TESTING: The closed normal position verification (AP) for the identified valves will be saiisfied by the valve seat leakage test or closure test using leak test methods which will be performed at least once every two years.
REQUIRED BY SER (TAC NO. 74785)- ANOMALY #19 (Continued)
- 8. l.1.1 Rev.9 Page 223 cf 236
[37) RELIEF REQUEST RV-37 (Continued)
Valve No (s) Description CK-1001-68A/B These valves are part of the Reactor coolmt pressure boundary for the CK-1400-9A/B Core and Suppression Pool Coohng and Reactor Vessel Level Makeup systems. Ec :h valve performs a pressure isolation function between ,
the Reactor coolant pressure boundary and the associated low pressure l system. A seat leakage test is the only practical method for verifying the normally closed position. Testing these valves requires entry into the Drywell (e g , Drywell must be de inerted) for system isolation, installation of test equipment, and sometimes partial drain-down of the system.
Therefore, venfying the closed normal position (AP) more frequently than the interval used for seat leakage testing would create a hardship without a compensating increase in the level of safety, due to an increase in personnel radiation exposure and prolonged periods of safety system inoperability.
CK 1101-15 This valve is part of the Reactor coolant pressure boundary for the Standby Liquid (reactivi:y) Control (SLC) System. This check valve maintains the Reactor coolant pressure boundary for this high pressure system. A seat leakage test is the only practical method for verifying the normally closed position Since there is no test connection upstream from this valve to enable pressunzation, the closed position can only be practically verified by performing a leakage test during the Class 1 Reactor Pressure Vessel System Leakage Test. This system leakage test is only conducted near the end of each refueling outage. Because this valve is located inside the Drywell and conducting an exercise requires initiating the SLC System and injecting into the Reactor Vessel (refer to RV-08),
nonintrusive test methods are not practical.
Therefore, verifying the closed noimal position verification (AP) more frequently than the interval used for leakage testing would create a hardship without a compensating increase in the level of safety.
CK-1001362B These valves are the seismic boundary isolation between the Core Spray l CK-1001-363A or LPCI suppression pool cooling systems and their keepfill supplies.
CK-1400-212A Loss of keepfill for maintenance or testing creates a potential for air CK-1400-212B intrusion which would jeopardize the affected cooling system's operability.
The only reasonable method to verify the valves' closed normal position venfication (AP)is by performing a seat leakage test. Leak testing of these valves requires isolation of the keepfill supply and entry into a radiation area to install test equipment and conduct testing. Therefore, verifying the closed position more frequently than the interval used for the seat leak testing would be a hardship without a compensating increase in the level of safety due to increased personnel radiation exposure and pcolonging the duration of a safety system's inoperability.
(Continued)
- 8. l.1.1 Rev. 9 Page 224 of 236
[37) RELIEF REQUEST RV-37 (Continued)
Valve No (s) Description CK-1101-43A/B These valves are the Standby Liquid Control (SLC) pumps discharge check valves cnd prevent possible backflow through the idle parallel SLC train. The only practical method for venfying their cirsed normal position (AP)is during a seat leakage test. This test i ng requres isolation of both SLC trains and removal of a pump discharge relief valve to establish a vent path. Therefore, venfying the closed position more frequently than that used for seat leakage testing creates a hardship without a compensating increase in the level of safety due to prolonged periods of safety system inoperability.
31-CK-372A These normally closed valves are the nitrogea/ air supply checks to the 31-CK-372B ADS accumulators. The check valves close to maintain the accumulators 39-CK-372C leak tight integrity upon loss of the rTogen/ air supply. Verifying leak tight 31-CK-372D integrity (which includes seat leakage of this supply check) is accomplished by performance of a pressure decay test. Each test requires entry into the Drywell for isolation of the accumulator (Drywell must be de inerted), installation of a pressure gauge, and venting off the Drywell nitrogen / air supply. All of these activities take place in a high radiation area. Drywell isolation causes a loss of air to instrumentation (e.g.,
equipment and floor drain sumo bubblers) and air-operated valves (e.g.,
inboard MSIVs, Reactor heac 9nts, etc.) Therefore, verifying the closed position more frequently than tnat used for seat leakage testing creates a hardship without a compensating increase in the level of safety due to extended Drywell air and ADS System inoperability, an increase in personnel radiation exposure, and entry into a hazardous environment.
CK-1301-23 These valves are condensate storage tank (CST) water supply check CK-2301-20 valves for Reactor Core Isolation Cooling (RCIC) and High Pressure Coolant injection (HPCI) Systems. The function of these normally closed check valves is to 1) open to supply the normal suction path for each system and 2) close to prevent backflow during system automatic swap to an alternate (Torus water) suction path This closing prevents suppression pool water from being directed to the CST when the Torus is pressurized during severe accident conditions. The only prrctical method available to verify each valve's closed normal position (AP) is during seat leakage testing. This testing requires isolating both suction paths and installing test equipment, which rer.ders the systems inoperable for an extended period of time. Therefore verifying the closed normal position (AP) more frequently than that used for seat leakage testing would be a hardship without any compensating increase in the level of ssfety due to prolonged periods of safety system inoperability.
8.1.1.1 Rev.9 Page 225 of 236 4
[38) RELIEF REQUEST RV 38 SYSTEM: Reactor Building Closed Cochng Water VALVES: 30-CK-419 through 30-CK-424 CATEGORY: C CLASS: 3 FUNCTION: These normally open check valves are the pump discharge check valves which when open allow proper coolant flow and when closed prevent diversion of flow and reverse pump rotation.
TEST REQUIREMENT: IWV-3521; Test Frequency - exercise at least once every three months.
BASIS FOR RELIEF: During plant operation these normally open check valves are exercised closed during quarterly pump testing. Because of each system's large cooling loads and lack of installed instrumentation, individual pump flow rates cannot be obtained. This deviation is identified by pump Relief Request RP-01 with an alternate testing entena of measunng flow rate dunng a Cold Shutdown, if practical, but on a not to exceed a refueling interval basis. Therefore, verifying these check valves full open quarterly or during each plant Cold Shutdown is impractical and would place an undue hardship on the facility.
AL1 ERNATE TESTING: Perform open normal position venfication (AP) in conjunction with the respective pump's flow rate measurement test.
REQUIRED BY SER (TAC NO. 74785) ANOMALY #19 8.1.1.1 Rev.9 Page 226 of 236 1
[39) F ELIEF REQUEST RV-39 SYSTEM: All Applicable VALVES: All Applicable CATEGORY: All Applicable CLASS: All Apphcable FUNCTION: As Applicable -
TEST REQUIREMENT: ASME Section XI (IWV-3417(b) and liW 3523) states that if the condition is not or cannot be corrected within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the valve shall be declared inoperative. When corrective action is required as a result of tests made dunng Cold Shutdown, the condition shall be corrected before startup.
BASIS FOR RELIEF- The PNPS Technical Specifications Limiting Conditions for Operation and ASME Section XI provide the controls by which valves and systems are declared inoperable. Technical Specifications control which systems are required to be operable for entry into each operational mode When a component is declared inoperable, the affected system's operability is determined and reviewed against apphcable operational modes.
IWV-3417(b) and IWV-3523 do not consider the system requirements for entry into each operational mode; therefore, strict compliance would result in a hardship without a compensating increase in the level of quality or safety.
The PNPS ASME Section XI Testing Program and PNPS Technical Specifications rer,uire a valve to be declared inoperable immediately wNn corrective action is required as the result of testing. The allowance for a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> grace period prior to declaring a component inoperable is not allowed within the PNPS IST Program.
PNPS Procedures and controls require the impact of degraded or failed components be reviewed for their effect on plant safety. For issues with potential outstanding question (s), plant support engineers of various disciplines are contacted and a detailed review is conducted as appropriate.
The evaluation process for degraded and/or inoperable components considers potential impact on total plant safety which encompasses a 10CFR50.59 applicablility check. For the infrequent cases, where there is potential for an unanalyzed test or unreviewed safety question, a 50.59 Safety Evaluation is performed.
(Continued)
- 8. l.1.1 Rev.9 Page 227 of 236
[39) RELIEF REQUEST RV 39 (Continued) 1 ALTERNATE TESTING Plant entry into operational modes. such as plant startup, shall be governed by PNPS Technical Specifications and not by ASME Section XI. IVN-3417(b) and IVN-3523 PNPS Procedures and controls will review the impact of degraded or failed components for their effect on plant safety The evaluation process will consider total plant safety which encompasses a 10CFR50.59 apphcability check. A 50.59 Safety Evaluation will be performed when tnere is a potential for an '
unanalyzed test or unreviewed safety question.
UNREVIEWED BY SER (TAC NO. 74785)
REVIEWED BY SER (TAC NO M85069)
- 8. l.1.1 Rev.9 Page 228 of 236
[40) RELIEF REQUEST RV-40 SYSTEM: Nuclear Boiler - Main Steam isol., ADS, and Safety Relief System (203)
VALVES: 3A,38,3C,3D CATEGORY: C CLASS: 1 FUNCTION The functions of the Reactor Safety Relief Valves (SRVs) are: 1) open upon receipt of an auto depressurization signal to blow down the Reactor,2) act as a primary system relief valve which can be manually actuated from the Control Room, and 3) act automatically to relieve Reactor pressure at setpoint.
TEST REQUIREMENT: ANSI /ASME OM-1-1987, Section 3.3, Periodic Testing BASIS FOR RELIEF- The IST Program complies with ANSI /ASME OM 1-1987, Requirements For Inservice Performance Testing Of Nuclear Plant Pressure Relief Devices. During refueling outages PNPS currently removes the SRV pilot assembly and transports it to a certified valve testing facility for performance of the following recommended tests: setpoint (lift pressure), reseat (reclosure pressure), and pilot stage seat tightness. A main valve body slave is used to test each pilot. ANSI /ASME OM-1 states, "No maintenance, adjustment, disassembly, or other activity which could affec' as found set pressure or seat tightness data is permitted prior to testing." Since main body seat leakage is monitored continuously during normal plant operation, its seat tightness as-found determination is satisfied prior to the pilot assembly removal.
ANSI /ASME OM-1 also states, " Tests prior to maintenance or set pressure adjustment, or both, shall be performed in the following sequence." of which strict adherence to the sequence cannot be satisfied by testing the pilot assembly only. PNPS current test practices ensure that applicable tests specified within ANSl/ASME OM-1 Section 3.3.1.1, Main Steam Pressure Relief Valves With Auxiliary Actuating Devices, are performed and the entire valve operability is verified prior to resumption of electric power generation. Common ;ndustry practice is to test the Target Rock safety / relief valve SRV pilot assembhes as separate units.
Therefore, removal of the entire valve assembly for testing would create hardships by 1) increased safety risks and radiation exposure during the removal and installation process,2) cost increase and schedule delays for decontamination, and
- 3) increased shipping expenses. These hardships are not warranted since there is no compensating increase in the level of quality and safety because the test as-found data is not affected and all applicable tests are performed.
(Continued)
- 8. l.1.1 Rev.9 Page 229 of 236
[40] RELIEF REQUEST RV-40 (Continued)
ALTERNATE TESTING: SRV pilot assemches will be tested using a slave main valve body to comply with ANSI /ASME OM-1. Periodic Testing requirements.
UNREVIEWED BY SER (TAC NO. 74785)
REVIEWED BY SER (TAC NO. M85069) s
- 8. l.1.1 Rev. 9 Page 230 of 236
[41) RELIEF REQUEST RV-41 SYSTEM. Residual Heat Removal System (1001)
VALVES: 68A,68B CATEGORY: AC CLASS: 1 FUNCTION. These valves are the Low Pressure Coolant injection (LPCI) pressure isolation check valves which provide a flow path for shutdown cooling.
TEST REQUIREMENT: ItW 3521; Test frequency - exercise at least once every three months, quarterly BASIS FOR REllEF: These check valves are the pressure isolation valves for the Low Pressure Coolant injection (LPCI) System and remain closed during normal plant operation. Each valve is an integral part of its respective RHR shutdown cooling loop flow path. One loop of RHR shutdown cooling is necessary for decay heat removal during a Cold Shutdown.
PNPS practice is to select an RHR snutdown cooling loop on a staggered basis each shutdown and remain exclusively in the selected loop for shutdown duration, unless changing plant conditions or maintenance activities necessitate shifting to the other loop. Swapping from one RHR loop to another creates a
" higher risk evolution" because of 1) excessive manpower loading,
- 2) deviations from normal system configurations, 3) complexity of this task (i.e., high susceptibility to events causing the loss of ' ey safety functions), and 4) large dose accumulations.
This inethod of devoting one loop to shutdown cooling for the shutdown duration is supported by the conclusions of NUMARC 91-06, Guidelines For industry Actions to Assess Shutdown Management. This document references numerous NRC IENs and IEBs in which a loss of " key safety functions" (i.e.,
decay heat removal capability and inventory control) has cecurred during " higher risk evolutions" Because of task complexity, shifting RHR shutdown cooling loops for.the purpose of exercising these injection check valves creates a high risk evolution and should be avoided.
(Continued)
- 8. l.1.1 Rev.9 Page 231 of 236 1
, [41] RELIEF REQUEST RV-41 (Continued) i i
BASIS FOR REllEF: (Continued)
For the case of mid-cycle and refueling outages, plant conditions / activities usually require swapping from one RHR loop to tne otner. For these extenced outages. both LPCI injection check valves will be exercised Exercising an injection check valve at the maximum required accident flow rate is only obtainable by operating three RHR pumps Normal p! ant limitations do not allow the operation of more than two RHR pumps within a loop A full flow exercise can be verified by performing diagnostic testing while two pumps pass flow through a shutdown cooling loop This special testing requires entry into Primary Containment (Drywell) and operation of test equipment in a high radiation area Verifying LPCI flow during two pump or < ration will fui, flow exercise the injection check valves. Performing sample diagnostic nonintrusive monitoring of these valves on a refueling interval basis using the guidelines within NUREG 1482 Section 4.1.2 will ensure operational adequacy and satisfy the maximum required accident flow verification.
ALTERNATE TESTING: Exercise valves on a staggered basis during shutdown cooling operation, not to exceed a refueling interval. Perform sample diagnostic nonintrusive testing each refueling interval adhering to the guidelines within NUREG 1482 Section 4.1.2 and verify that the RHR Cold Shutdown flow rate (two pumps running) fully opens these valves.
UNREVIEWED BY SER (TAC. No. 74785)- ANOMALY #16 REVIEWED BY SER (TAC NO. M85069)
- 8. l.1.1 Rev.9 Page 232 of 236 l
[42] RELIEF REQUEST RV-42 SYSTEM: Control Rod Drive (CRD) System VALVES: 151 CATEGORY: AC CLASS: 1 FUNCTION: This valve allows the flow of high pressure water to the CRD mechanisms for cooling and positioning control rods (during both normal and Scram conditions). This valve also closes to isolate a potentialleakage pathway for primary coolant to leak past both the Primary and Secondary Containment boundaries via the CRDH System following a design bases accident LOCA.
TEST REQUIREMENT: IWV-3521; Test frequency - exercise at least once every three months, quarterly BASIS FOR REllEF- This is the control rod drive hydraulic (CRDH) Supply Header Check Valve for a system required to be in service during plant operation. This normally open check valve was newly installed during RFO 9 (May 1993) and requires a reverse flow exercise (FC). The open normal position ver fication (AP)is performed on a quarterly basis.
The most practical method for performing a reverse flow exercise during seat leakage testing, which requires CRDH flow to the CRD mechanisms and Reactor coolant recirculation pump seals to be secured. Isolating the CRDH flow during power operation interrupts the flew for maintaining and controlling control rod positions. Pressure would decay from the isolated system causing control rods to drift from their positions, requiring immediate plant shutdown.
Interrupting CRD flow during Cold Shutdowns to allow valve closure terminates seal purging functions to the CRD mechanisms and Reactor coo ant recirculation pump seals, which can negatively affect seal performance. Particularly for the CRD mechanisms, flow interruptions of seal purging tends to impact smooth performance on some CRDMs (causing sticking) which could delay plant startup and is not recommended industry practice k except during extended maintenance / refuel outages.
Therefore, verifying a reverse flow exercise more frequently than that used for seat leakage testing would create a hardship without a compensating increase in the level of safety due to increased equipment performance problems, which are created by removing and returning the system from service to allow valve closure for testing.
(Continued) 8.1.1.1 Rev. 9 Page 233 of 236
[42] RELIEF REQUEST RV-42 (Continued)
ALTERNATE TESTINA Exercise valve closed at least once every two years during seat leakage testing APPROVED BY SER (TAC. No, M88198) 8.1.1.1 Rev.9 ;
Page 234 of 236
t
[43) RELIEF REQUEST RV-43 SYSTEM: - Nuclear BoilerVesset instrumentation (263)
--VALVES: - CK-C2205A 1 (Irboard), CK-C2205A 1 (Outboard),
CK-C2206A 1 (Inboard). CK-C2206A-1 (Outboard) :
CATEGORY: AC' CLASS: NC !
FUNCTION: These valves open to allow CRD charging water ;o be supplied to each of the two Emergency Core Cooling System (ECCS) water level reference legs.
These valves also close to ensure stable operation of the Reactor water level instrumentation, upon loss of the CRD C_harging Water System, by preventing reverse flow from the instrument racks from migrating back into the CRD System.
TEST REQUIREMENT: IWV-3521; Test frequency - exercise at least once every three months, quarterly BASIS FOR RELIEF: These are the supply check valves for the Reactor water level reference leg purge system which is required to be in service during plant operation. These newly installed check valves require a reverse flow exercise (FC). The open normal verification (AP) is performed on a quarterly basis. The most practical way to perform a reverse flow exercise is to conduct a seat leakage test which requires isolating CRD flow to the water level reference legs.
Conducting a leak test also requires breaching the system boundary and installation of test equipment for system pressurization and vent path. Isolating and breaching the Reactor water level purge system during power operation or plant Cold Shutdowns can negatively impact this system's function by terminating water purge and creating a condition that allows the potential for air to be introduced into these reference legs.
Other methods (e.g., acoustics, ultrasonics, magnetics, and radiography) have been reviewed for performing a reverse flow exercise (FC) to these valves during Cold Shutdowns; however, they have been determined not practical. These alternate methods
' either rec,uire extended system outage time for testing and/or cannot con istently provide reliable test results due to the small size of these valves (0.375 inch with Swagelok fittings).
Therefore, verifying a reverse flow exercise more frequently than that used for seat leakage testing would create a hardship without a compensating increase in the level of safety. This is due to the conditions that impair the Reactor water level reference leg purge system's ability to perform its intended function which are created by removing and returning the system from service and breaching the system to allow valve closure verification for testing.
(Continued)
- 8. l .1.1 Rev.9 Page 235 of 236
[43] RELIEF REQUEST RV-43 (Continued)
ALTERNATE TESTING- Reverse flow exercise (FC) valves closed at least once every two years during seat leakage testing.
EVALUATED BY SER (TAC No. M88198) 8.l.1.1 Rev. 9 Page 236 of 236
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