ML20076C429

Forwards Changes to Inservice Testing Programs for Pumps & Valves,In Response to NRC Comments During 910507 Telcon

ML20076C429
Person / Time
Site:	Braidwood
Issue date:	07/15/1991
From:	Checca A COMMONWEALTH EDISON CO.
To:	Murley T NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
References
NUDOCS 9107220102
Download: ML20076C429 (163)

Text

{{#Wiki_filter:- ~ k. Ctmm ns::alth Eulsen -f / E 1400 opus Place 1 -r I #7 Cawnsta Grove,libnois 60515 s f-July 15,1991-Dr. Thomas E. Murley, Director - Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Coramission Washington, D.C. 20555 Attn: Document Control Desk

Subject:

Braidwood Station Units 1 and 2 Inservice Testing (IST) Programs for Pumps and Valves NBO_RocketNoL50-456-.and 50-45Z

Reference:

(a) Se atember 15,1988, L.N. Olshan letter to H.E. Bliss (b) December 21,1988 R. Chrzanowski letter to T.E. Murley (c) August 31,1987 S.C. Hunsader letter to T.E. Murley g Ja* uary@31,1989 S.C. Huntader letter (d) to T.ii riay (e) May 23,1991 T.K. Schuster letter n to T.E. Murley

Dear Dr. Murley:

The Braidwood Station (IST) Programs for Pumps (Revision 5) and Valves (Revision 5) are enclosed with this letter and include changes based on the comments presented in the teleconference held on May 7,1991. These revisions include changes presented in reference (e) for Byron Station as they apply to Braidwood Station. Attachment A to this letter presents the differences or changes made between Revision 4 which had been submitted previously in reference (d) for Braidwood Station and Revision 5 as providad here. For ease of your review Revision 5 has been reformated to match the curren*. Byron revisions. Attachments B and C are the actual pump and valve programs, respactively. CD v-l 91072201o2 9107j/36 -O e DR ADOCK 05000 o CO PDR k ',\\) ' l "4 ZNLD/968/3 p

F Dr. Thomas E. Murley July 15,1991 Eumpfragram As noted in previous submittals, the IST Pump Program for Braidwood consists of a tabular listing of those pumps which are identified in the Byron /Braidwood UFSAR as Active, and that have an emergency power source; plus a series of Notes and Relief Requests. Active pumps are defined as those pumps called on to perform a safety functions as well as to accomplish and maintain a safe reactor shutdown. The only exception are the diesel drive auxiliary feedwater pumps (1/2AF01PB) which are included in the program although they are not supplied by an emergency power source. ' alYe_Erogram l The IST Valve Prog,am for Braidwood consists of a tabular listing of ASME Section Class I, ll, and lil valves which have been assigned a specific Code catagory, plus a series of notes and relief requests. Please address any questions you mcy have regarding this matter to this Very truly yours, &n k 14W Allen R. Checca Nuclear Licensing Administrator cc: R.M. Pulsifer Resident inspector-Braidwood W. Shafer-Region lil I ZNLD/968/4 l

ATTACHMENT A

SUMMARY

OF CHANGES ZNLD/968/5

Summary of Changes to Revision 5 of the Inservice Testing Program Plan for Pumps and Valves Section 3.0 - Tahle_.nfJ:nntenta The format of the Braidwood Inservice Testing (IST) program for pumps has been changed to coincide with the Byron Station program. 1. Added a program refere. ice section. 2. Changed note numbers to match Byron's. 3. Added a technical approach and position section. 4. Changed relief request numbers to match Byroa's. 5. PR-02a is being submitted to exempt bearing temperature measurements from all pumps in the program. Section 3.1 - P.rDgram_Rescription 1. Expanded this section to incorporate Byron's additional information. Section 3.2 - P.ID9 tam _BeleteAces 1. Added this section to list various references used to develop the IST program, including NRC SERs. Section 3.3 - Eump_ Tables A. P. ump _ Table DnscLhtion 1. Added a "T" character identifier to the " Code" field (for tracking purposes only). 2. Added a statement to the " Test Interval" description concerning testing when a pump is not required to be operable. 3. Added a " Remarks" field description. B. PMmp TAhlen 1. Added the AB pumps to the program for tracking purposes only. Pump Technical Approach and Position, PA-01 provides the explanation why these pumps will be tracked by the IST program. 2. Deleted the DO pumps from PR-03 because the permanently installed flow instruments will be used. 3. Changed PR-03 (rev. 4) to PR-05 (rev. 5) to match Byron's program. 4. Changed Note 2 to Note 3. 5. Changed Note 1 to Note 2. 6. Added type of driver to " pump name" column for the AF pumps. 7. Changed PR-04 to PR-06 to match Byron's program. 8. Changed PR-03 to PR-05 to match Byron's program. 9. Added " Pump" to the WO pump description, 217(070891) ZD79G

m Summary of Changes to Revision 5 of the Inservice Testing-Program Plan for Pumps and Valves [Section 3.4 - Pump..Netas 1. This section was changed to reflect Byron's program numbering. Those notes which are not applicable to Braidwood's program are specifically identified.. Note 5 - these pumps do not exist at Braidwood. Note 6 - pertains to Byron's modified unit two SX booster pump only. Note 7 - Braidvood elected to track the AB pumps per the IST program versus a separate program.

Section 3.5 - Eump le_chnicALAppInaches_and_Eositions 1.

Added this section to implement standard IST program format and practices as outlined in the Ceco. " Conduct of ISI/IST Manual." 2. Added to. describe how the AB pumps will be tested and tracked. Section 3.6 - Enmp_E211ef Requests j 1. An approval status section/ step (9) vas add ed to all relief requests to track both revision and approval for eas s of review. - l 2. PR the total number of pumps was change 3. 3. PR changed to PR-5 to match Byron's pr(aram. j 4. PR changed to PR-6 to match Byron's program. 5. PR does not apply; these pumps do not exist at Braidwood. 6. PR-02a - submitting this relief request to incorporate all pumps in the program. This is an industry wide change (from measuring teir.perature yearly to measuring vibration in velocity) and is ' acceptable to the NRC and ASME-interested parties. Needs NRC approval. 4 k 2 '217(070891) ZD79G

g7z Summary of Changes to Revision 5 of the Insorvice Testing Program Plan for Punpa and Valves Section 4.0 - Table _._of_Cuntanta The format of the Braidwood Inservice Testing (IST) program for valves has been changed to coincide with the Byron Station program. 1. Added a program reference section. 2.- Changed note numbers to match Byron's. 3.- Added a technical approach and position section. 4. Changed relief request numbers to match Byron's. Section 4.1 - PIngram_pancriplign 1. Expanded this section to incorporate Byron's additional information. Specifically: a. Added status and requirements of the NRC approval on relief requests. b. Added paragraph describing scope of valve program. c. Added description of positions on stroke timing and check valve testing per Generic Letter 89-04, d. Added required action range response when~ data falls outside acceptable limits. e. Added description of when new stroke time reference values are required. Section 4.2 - PI_qgram RefeERDefe 1. Added this section to list various references used in program development or that are pertinent to the program, including NRC SERs. Section 4.3 - Valve Tabing A. Y.AlVA_IAhle Descriplign 1. Added a "T" character identifier to the " Code" field (for trocking purposes only). 2. Added_ field descriptions and columns for " Notes" and " Technical Approaches and Positions." 3._. Added a " Remarks" field description. 4. Changed ut description to CT/Bt to indicate the direction a_ check valve will be tested. Ct - for open direction and Bt - for closed directitn. 5. Deleted the " maximum stroke time" and " system" fields. B. Valve Tab'as 1. Added the AB pump discharge check valves to the program for tracking purposes only. Valve Technical Approach and Position, VA-5 provides the explanation why these valves will be tracked by the IST program. L. Added new " Technical Approaches and Positions" and " Notes" columns. 3. Addtd VA-2 to all fai1~ safe tested (Ft) valves. 4. Added VA-3 to all check valves nnd VA-1 to all power operated valves. 3 217(070891) ZD79G

[' Summary of Changes'to Revision 5 of ' the Inservice -Testing Program : Plan for Pumps and Valves B. Enlyg_Tahlag (continued) i i }5. '1/2AF001A/B ~ added Bt at RR per VR-19. 6. 1/2AF014A-H - added Bt at CS and Notes-12 and 30. 7. 1/2CC9437A - deleted passive from remarks and added an FT test. ) 8, 1/2CC9463A/B - added Ct/Bt at CS,-Xt at OP and Note 32. 9. OCC9464 - added Ct/Bt at CS, Xt at OP and Note 32. 10. 1/2CC9486 - added Bt at RR per VR-8. 11. 1/2CC9518 - added Bt at RR per VR-8 and Note 24, deleted passive from remarks. 12. 1/2CS008A/B - added Bt at RR per VR-4. 13, 1/2CV112B/C - added Note 28. 14. 1/2CV8113 - added Ct/Bt at RR -per VR-9 and Note 29, deleted passive from remarks. 1/2CV8100 and 1/2CV8112 f requency changed to RR. 15, 1/2CV8442 - added Note 29, 16. 1/2CV8480A/B - added Bt at OP and Note 31. 17. '1/2CV84 81A/B - tidded Bt at RR per-VR-15. 18. 1/2CV8546 - changed Ct at CS to Ct at RR per VR-15 und added Note 26. 19. 1/2D0003A-D - added Bt at OP. 20. 1/2FP010 - corrected valve type to globe (GL). 21.- 1/2FWO34A-D - renumbered Note 18 to 21. 22, 1/2IA091 - added Bt at RR per VR-10, deleted passive from remarks. 23. 1/2PR002G/H -'added Ft at RR per VR-23, deleted passive from remarks. 24. 1/2PR032 - added Bt at RR per VR-24, deleted passive from remarks. 25. 1/2PS228A/B'- changed from globe to gate type valves. '26, 1/2PS229A/B - chanJed from globe to gate type valves. 27. 1/2PS230A/B - charged from 1" globe to 0.5" gate type valves per Mod M20-1-88-060. 28. 1/2PS231A/B - added Bt at RR per VR-25 and changed Note 21 to Note 22, 29. 1/2RE1003 - deleted VR-12. 30. 1/2RE9157 - deleted VR-12. l 31. 1/2RE9159A/B - deleted VR-12.

32. -1/2R179160A/B - deleted VR-12.

33, 1/2RHB705A/B - added Ct/Bt at RR per RV-15 and Notes 24 and 35. 34. 1/2RH8730A/B - added Bt at CS per Note 8.- -35. 1/2RY455A - changed St at OP to St at RR per Note 36. 36, 1/2RY456 - changed St at OP to St at RR per Note 36. l 37. 1/2RY8025 - deleted passive from remarks. l 38. 1/2RY8046 - added Bt at RR per VR-26, deleted passive from remarks. 39, 1/2RY8047 - added Bt at RR per VR-26, deleted passive from remarks. 40. 1/2SD002A-H - deleted VR-1 and added Note 34. i 41, 1/2SD005A-D - deleted-VR-1 and added Note 34. L 42, 1/2SI8815 - added Bt at RR per VR-15; changed Ct at CS to.Ct at RR per VR-15. 43. 1/2SI8818A-D - added-Bt at RR per VR-15 and Note 23. 44, 1/2SI8819A-D - added Bt at RR per VR-15 and Note 23. 45. 1/2SI8841A/B - added Bt at RR per VR-15; changed Ct at CS to Ct at RR per VR-15. 4 217(070891) ZD79G

Summary of Changes to Revision 5 +- of the Inservice Testing Program Plan for pumps and Valves B. Valyn_ Inkles. (,ontinued) -l 46. 1/2SI8900A-D'- added Bt at RR per VR-15; changed Ct at CS to Ct at RR per VR-15. 47, 1/2SI8905A D -'added Bt at RR per VR-15. .48. 1/2 SIB 919A/B - added Bt at OP. 49. 1/2 SIB 922A/B - added Bt at RR per VR-3. 50. 1/2SI8926 - added Note 25. 51. 1/2 SIB 948A/B~.added Bt at RR per VR-5, deleted Ct at CS per VR-5; added Note 23 to the-1/2 SIB 948A/B valves. 52. 1/2SI8949A-D - added Bt at RR per VR-15. 53. 1/2SI8956A/B - added Dt at RR per VR-5, deleted Ct at CS per VR-5. 54, 1/2SI8958A/B - added Note 27.

55. '1/2 SIB 964 - deleted passive from remarks.

56. 1/2SI8968 - added Bt. at RR per VR-18, deleted passive from remarks. 57. 1/2SX002A/B - added Bt at OP. 58, 1/2SX016A/B - deleted passive from remarks. 59. 1/2SX016A/B - deleted passive from remarks. 60. 1/2SX147A/B - added control valves to program per Byron's latest submittal. 61. 1/2VQ001A/B --deleted passive from remarks. 62. 1/2VQ002A/B - deleted passive from remarks. 63. 1/2VQ004A/B - deleted passive from remarks. 64. 1/2VQ005A/B/C - deleted passive from remarks.

65..1/2WOOO7A/D - added Bt at RR per VR-27, deleted passive from remarks.

Section 4.4 - Yalyt.l{stten 1.- This section was changed to reflect Byron's program numbering. Those notes which are not applicable to Braidwood's program are specifically identified. I 2. Changed Note 18 to 21, 3. Changed Note 21 to 22. 4. Added Notes 23 through 36. Section 4.5 - Yalve TechninaL AppInaches and_fas1Linns l .1. Added this_ section to implement standard IST program format and l practices aus outlined in the CECO. " Conduct of ISI/IST Manual." 2. Added VA-1 through 4 to coincide with Byron's program. 3. Added V A-5 _to-describe how the AB pump discharge check valves will be tested and tracked. 5 217(070891) ZD79G

Summary of Changos to Revision 5 of the Inservice Testing program Plan for Pumps and Valves Section 4.6 - Enhe__Rel.itLReg.uts.ta 1. An approval status.section/ step (9) was added to al. 5elief requests to track both revision and approval for ease of review. 2. VR Revised to document GL 89-04, Attachment 1, Item 10 concerning trending of CIVs sized six inches or greater. ASME Section XI IWV-3427(a) will not be utilized. Also, valves 1/2SD002A-H and 1/2SD005A-D were removed per Tecnnical Specification Amendment 126. This relief request is in accordance with GL 89-04 requirements, and is pre-approved. 3. VR Provided additional information f or the disassembly and inspection sample plan per GL 89-04. This revision incorporates the latest Byron discussions with NRK. This relief request is in accordance with GL 89-04 requirements, and is pre-approved. VR Added back flow test code (Bt) to section 4. 4. VR Provided additional information for the disassembly and inspection sample plan per GL 89-04. This revision incorporates the latest Byron discussions with NRR. This relief request is in accordance with GL 89-04 requirements, and is pre-approved. 5. VR Added additional-information regarding acoustic testing of these valves and provided justification for performing the Ct test during refueling only. The refueling frequency needs NRC review and app-oval. 6. VR-8 Added valves 1/2CC9518 and 1/2CC9534 with supporting information. These additions need NRC review and approval. 7. VR Added valves 1/2CV8113 with supporting information. These additions need NRC review and approval. 8. VR Added valves 1/2IA091 with supporting information. These additions need NRC review and approval. 9. VR Removed the RE system valves from this relief per system engineers request. NRC approval is not required. 10. VR Added valves 1/2RH8705A, B and 1/2 SIB 818A-D with supporting justification. In addition, the Ct testing of all these valves is requested to be done on a refueling basis only; additional justification has been provided. These additions need NRC review and approval. 11. VR Additional information and justification was added to incorporate Byron's SER ltems. 12. VR This relief differs from Byron's program in that each valve has been separated into various other requests for relief. VR-18, VR-23 through VR-27 resulted from this break up. Each of these relief requests need NRC review and approval. VR-18 was never submitted for Braidwood's program due to delays in receiving the program SER from the NRC. 13. VR This is a new relief request for the 1/2AF001A, B valves. This relief incorporates the latest Byron /NRR comments. This relief request is in accordance with GL 89-04 requirements, and.is pre-approved. 14. VR-20 through VR not used at Braidwood Station. 6 217(070891) ZD79G

7. ATTACHMENT B INSERVICE TESTING PROGRAM PLAN FOR PUMPS l t I i l I ZNLD/968/6

~ l l SE:CTICM 3.0 INSERVICE TESTING PROGRAM PLAN FOR I W S BRAIDWOOD STATICM UNITS 1 AND 2 217(061891) ZD79G/7

INSERVICE TESTING PROGRAM PLAN POR PUMPS BRAIDWOOD STATION UNITS 1 AND 2 Revision 5 TABLE OF CONTF.NTS 3.0 Inservice Testing Program Plan for Pumps 3.1 Program Description 3.2 Program References 3.3 Pump Tables 3.4 Pump Notes Note 1 -Deleted-Note 2 Pumps Lubricated by Pumped Pluid Note 3 Pump Idle Suction Pressure Note 4 Deleted - Not Used at Braidwood - Byron OHLY Note 5 Not Used at Braidwood - Byron ONLY Note 6 Not Used at Braidwood - Byron ONLY Note 7 Not Used at Braidwood - Byron ONLY 3.5 Pump Technical Approaches and Fusitions PA-01 Performance Testing of the Boric Acid (AB) Transfer Pumps 3.6 Pump Relief Requests PR-01 Pump Vibration PR-02 Pump Bearing Temperatures PR-02a Pump Bearing Temperatures PR-03 -Deleted-Not used at Braidwood - Byrtn ONLY PR-04 -Deleted-Not used at Braidwood - Byron G'LY PR-05 Use of Ultrasonic Plowmeters PR-06 Diesel Oil Transfer Pump Differential Pressure PR-07 Not used at Braidwood - Byron ONLY 3.0 - Page 1 of 1 217(070891) ZD79G/8

fNSERVICE TESTING PROGRAM PLAN FOR PUMPS BRAIDWOOD STATION UNITS 1 AND 2 Revision 5 SECTIN 3.1 PROGRAM DESCRIPTICN 217(070891) ZD79G/9

INSERVICE TESTING PROGRAM PLAN FOR PUMPS BRAIDWOOD STATION UNITS 1 AND 2 Revision 5 PROGRAM DESCRIPTION The Pump Inservice Testing -(IST) Program Plan for Braidwood Nuclear Power Station Units 1 and 2, is implemented in accordance with the requirements of Subsection IWP of Section XI of the ASME Boiler and Pressure Vessel Code, 1983 Edition, through the Summer of 1983 Addenda. Where these requirements are determined to be impractical, specific relief is requested. Additional pump relief requests may be necessary and these will be identified during subsequent inservice tests. The pumps subject to IST testing are those pumps which are identified in accordance with the scope of ASME Section XI, subsection IWP-1100: "IWP-1100 SCOPE... This Subsection provides the rules and requirements for inservice testing of Class 1, 2, and 3 centrifugal and displacement type pumps that are installed in light-water cooled nuclear power plants, that are required to bring and maintain the plant in cold shutdown condition or mitigates the consequences of an accident, and that are provided with an emergency power source. The results of these terts are to be used in assessing operational readiness of the pumps durino their service life." The only exceptions are the diesel driven auxiliary feedwater pumps (IAF0lPB and 2AF0lPB), which are not supplied by an emergency power source. The diesel oil transfer pumps (1/2 DOO1PA, 1/2DOO1PD, 1/2000lPC and 1/2DOOlPD) are classified non-ASME Clasu G. Pump reference values shall be determined from the results of a pre-service test, which may be run during pre-operational testing, or from the results of the first inservice test run during power operation. Reference values shall be at points of operation readily duplicated during subsequent inservice testing. Additional reference values may be necessary and these will be taken in accordance with IWP-3111 and 3112: 1. After a pump has been replaced, 2. When a reference value or set of values may have been affected by repair or routine servicing of a pump, or 3. If it is necessary or desirable for some other reason than 1 or 2 above. Per NRC Generic Letter 89-04, Attachment 1, Position 28, whenever pump data is determined to be within the Required Action Range, the pump is inoperable, and the Technical Specification LCO Action statement time starts. In the event a pump must be declared inoperable as a result of inservice testing, limitations on plant operation will be as stated in the Technical Specifications. Section XI of the ASME Boiler and Pressure Vessel Code shall not be construed to supersede the requirements of any Technical Specification. 3.A - Page 1 of 1 217(070891) ZD79G/10

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INSERVICETESTINGPROGRAMPLANh0EPUMPS BRAIDWOOD STATION UNITS 1 AND 2 Revision 5 SECTION 3.2 PROGRAM REFERENCES l 217(070891) ZD79G/11

F 7 INSERVICE TESTINt' PROGRAM PLAN POR PUMPS BRAIDWOOD STATION UNITS 1 AND 2 Revision 5 PROGRAM REFERENCES 1. Title 10, Code of Federal Regulations, Part 50, Domestic Licensing of Production and Utilization Jacilities, particularly Section 50.55a, Codes and Standards; 2. ASME Boiler and Pressure Vessel Code, Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components, 1983 Edition, Summer 1983 Addenda. 3. ASME/ ANSI OM-1987, Operation and Maintenance of Nuclear Power Plants, including 1989 Addenda, Part 6, inservice Testing of Pumps in Light Water Reactor Power Plants. 4. U.S. Nuclear Regulatory Commission, Generic Letter 89-04, Guidance on Developing Acceptable Inservice Testing Programs. 5. Braidwood Station UFSAR, Section 3.9.6.1, inservice Testing of Pumps. 6. Braidwood Station Technical Specification, 4.0.5, ASME XI Program Requirements. 7. Braidwood Station Technical Staff Procedure, BwvP 200-1, ISI Requirements for Pumps, 8. NRC Safety Evaluation Reports (SER's): 3.2 - Page 1 of 1 217(070891) ZD79G/12

INSERVICE TESTING PROGRAM plaid FOR PUMPS BRAIDWOOD STATION UNITS 1 AND 2 Revision 5 SECTION 3.3 PUMP TABLES t l l l 217(070891) ZD79G/13

~ INSERVICE TESTING FROGRAM PLAN FOR PUMPS BRAIPAOOD STATION UNITS 1 AND 2 Revision 5 PUMP TABLE DESCRIPTICH The tollowing information is included in the summary tables: The first four columns include the unique Braidwood Station Equipment Piece N umbe r,. the Pump N ame, the Code Class (1, 2, 3, N for non-Code, and T for tracking purposes only), and the system P & ID for the pump listed. Spec.d e Speed will be measured by a tachometer for variable speed drives. Inlf.t_EIS1EuLe t Inlet pressure will be measured via permanently installed geuges or other means, provided the equipment accuracy meets the requiremente of IMP-4150. This is to be measured both before pump startup and during the test. D11(ALentinl_f12112ta Differential pressures will be measured using calibrated differential pressure gauges or by recording the difference between calibrated inlet and outlet pressure gauges. Elow_ Rate: Flow rates will be measured using permanently installed instrumentation or other means, provided that equipment accuracy meets the requirements of IWP-41SO. Also, refer to relief request PR-05. Yibration: Vibration measurement shall be made ur,ing portable or hand held instruments at locations marked on the pumps, relief request PR-01. dealing _IempcI.atute Beering temperature is not measured per PK-02. Iest_JAteIyal: An inservice test shall be run on each pump nominally every 3 months during normal plant operation, in accordance with IWP-3400, except during periods when the pump is not required to be operable. LubrJratign_ Ley _c1: subrication level will be observed through sight glasses for the pumps listed in the program, when provided. Remarks: Any applicable note (s) are referenced here. Rey 1Eign_11gm.ltgr : The current revision of the program is listed. IADje A c: The table pages are numbered sequentially and show the total number of pages. 3.3 - Page 1 of 1 217(070891) l z079G/14

. INSERVICE TESTING. PROGRAM PLAN CLASS 1, 2,. 3 and AUGMENTED PUMPS BRAIDWOOD NUCLEAR POWER STATION UNITS 0, 1, 2 Revision 5 i C TEST PARAMETERS. I A-LUBRI-S SYSTEM INLET DIFF FLOH BEARING. TEST CATION: PUMP NUMBER PUMP NAME S P & ID SPEED PRES PRES RATE VIBRATION TEMP INTERVAL LEVEL REMARKS' OAB03P Boric Acid T M-65 No No PA-1 PA-1 PA-1 PA-1 Quarterly, Yes l Transfer Pump 1AB03P Boric Acid T M-65 No No PA-1 PA-1 PA-1 PA-1 Quarterly Yes Transfer Pump i ZAB03P Boric Acid T H-65 No No PA-1 PA-1 PA-1 PA-1 Quarterly Yes Transfer Pump 1AF0lPA Auxiliary Feedwater 3 M-37.. .No Yes Yes Yes PR-1 Yes Quarterly. Yes' 2 Pump (Motor) ^ lAF01PB Auxiliary Feedwater 3 H-37 Yes Yes Yes Yes PR-1 Yes Quarterly Yes Pump (Diesel) 2AF0lPA Auxiliary Feedwater 3 M-122 No Yes Yes Yes-PR-1 Yes Quarterly Yes Pump (Motor) i 2AF0lPB Auxiliary Feedwater 3 M-122 Yes Yes Yes Yes PR-1 Yes Quarterly Yes ~ Pump (Diesel) t OCC01P Component Cooling 3 H-66 No Yes Yes PR-5 PR-1 PR-2 Quarterly Yes Note 3 l Pump ICC0lPA Component Cooling 3 M-66 No Yes Yes PR-5 PR-1 PR-2 Quarterly Yes Note 3-Pump { ICC01PB Component Cooling 3 M-66 No Yes Yes PR-5 PR-1 PR-2 Quarterly- .Yes Note 3 Pump 2CC0lPA Component Cooling 3 M-66 No Yes Yes PR-5 PR-1 PR-2 Quarterly. Yes Note 3 Pump i 3.3 PUMP TABLES - Page 1 of-4 217(070891) ZD79G/1 1

INSERVICE TESTING PROGRAM PLAN; ' CLASS 1, 2, 3 and AUGMENTED-PUMPS BRAIDWOOD NUCLEAR POWER STATION UNITS 0, 1, 2 Revision 5 C TEST PARAMETERS. A LUBRI-5 SYSTEM INLET DIFF FLOH BEARING TEST CATION EUMP NUMBER PUMP NAME S P & ID _ SPEED PRES PRES RATE VIBRATION TEMP INTERVAL LEVEL RE?tARKS 2CC0lPB Component Cooling 3 M-66 No Yes Yes: PR-5 PR-1 PR-2 Quarterly Yes Note'3 Pump 1CS0lPA Containment Spray 2 M-46 No 'Yes-Yes. Yes PR-1 PR-2 Quarterly No Note 2 Pump 1CS01PB Containment Spray-2 M-46 No Yes Yes Yes PR-1. PR-2 Quarterly-No Note.2 Pump 2CS01PA Containment Spray 2 M-129 No Yes Yes Yes PR-1 PR-2 Quarterly No Note'2 Pump 2CS01PB Containment Spray 2 H-129 No Yes-Yes Yes PR-1 PR-2 Quarterly No Note 2-Pump 1CV01PA Centrifugal Charging 2 M-64 No Yes Yes ' Yes PR-1 Yes Quarterly Yes Pump ICV 0lPB Centrifugal Charging 2 M-64 No Yes Yes Yes PR-1 Yes Quarterly Yes Pump 2CV0lPA Centrifugal Charging 2 M-138 No Yes Yes Yes rR-1 Yes Quarterly Yes Pump 2CV0lPS Centrifugal Charging 2 M-138 No Yes Yes Yes PR-1 Yes Quarterly-Yes Pump 1D001PA Diesel Oil Transfer 3 M-50 No Yes PR-6 PR-5 PR-1 PR-2 Quarterly No Note'2 Pucp 3.3 PUMP TABLES - Page 2 of 4

217(070891)

ZD79G/2

i INSERVICE TESTING PROGRAM PLAN i 'CLASSL1, 2, 3 and AUGMENTED PUMPS BRAIDH000 NUCLEAR POWER STATION-UNITS.0, 1, 2 Revision 5 l C TEST PARAMETERS L A LUBRI-S . SYSTEM INLET DIFF FLOW BEARING . TEST - CATION' PUMP NUMBER PUtiP NAME S P & ID SPEED PRES PRES RATE VIBRATION TEMP INTERVAL ~ LEVEL REMARKS 1D00lPB Diesel 011 Transfer 3. M-50 No Yes PR-6 PR-5 PR-1 PR-2 Quarterly No Note 2 Pump 1D001PC Diesel 011 Transfer 3 M-50 No Yes PR-6 PR-5 PR-1 PR-2 Quarterly No Note 2' Pump 1D001PD Diesel 011 Transfer 3 M-50 No Yes PR-6 PR-5 PR-1 PR-2 Quarterly No Note 2 Pump-l 2000lPA Diesel Oil Transfer 3 M-130 No Yes PR-6 PR-5 PR-1 PR-2 Quarterly-No Note 2. Pump 2000lPB Diesel Oil Transfer 3 M-130 No Yes PR-6 PR-5 PR-1 PR-2 Quarterly. No' Note 2 Pumo 2000lPC Diesel Oil Tran[.r 3 M-130 No Yes PR-6 PR-5 PR-1 PR-2 Quarterly No Note 2 Pump 2D00lPD Diesel Oil Transfer 3 M-130 No Yes PR-6 PR-5 PR-1 PR-2 Quarterly No Note 2 Pump 1RH01PA Residual Heat 2 M-62 No Yes Yes Yes-PR-1 PR-2 Quarterly No Note 2 i Removal Pump 1RH01PB Residual Heat 2 M-62 No Yes Yes Yes PR-1. PR-2 Quarterly No Note 2 Removal Pump 2RH0lPA Residual Heat 2 M-137 No Yes Yes Y.. s PR-1 PR-2 Quarterly No Note 2-Removal Pump 4 2RH0lPB Residual Heat 2 M-137 No Yes Yes Yes PR-1 PR-2 Quarterly No. Note 2 Removal Pump 3.3 PUMP TABLES - Page 3,of 4 217(070891) ZD79G/3 i-a.,

INSERVICE TESTING PROGRAM PLAN CLASS 1, 2, 3 and AUGMENTED PUMPS BRAIDWOOD NUCLEAR PCHER STATION UNITS 0, 1, 2 Revision 5 C T,Ji 'ARAMETERS A LUBRI : 5 SYSTEM INLET DIFF F >H BEARING TEST CATION PUMP NUMBER PUMP NAME S P & ID SPEED PRES PRES RATE VIBRATION TEMP INTERVAL LEVEL REMARKS ISI0lPA Safety Injection 2 M-61 No Yes Yes Yes PR-1 Yes Quarterly Yes Pump ISIO1PB Safety Injection 2 H-61 No Yes Yes Yes PR-1 Yes Quarterly Yes Pump 2SIO1PA Safety Injection 2 H-136 No Yes Yes Yes PR-1 Yes Quarterly Yes j Pump 2SI0lPB Safety Injection 2 M-136 No Yes Yes Yes PR-1 Yes Quarterly Yes Pump ISX0lPA Essential Service 3 M-42 No Yes Yes PR-5 PR-1 Yes Quarterly Yes Note 3 Water Pump ISX0lPB Essential Service 3 H-42 No Yes Yes PR-5 PR-1 Yes Quarterly Yes Note 3 Hater Pump 2SX01PA Essential Service 3 M-42 No Yes Yes PR-5 PR-1 Yes Quarterly Yes NoteL3 Hater Pump 2SX01PB Essential Service .3 M-42 No Yes Yes PR-5 PR-1 Yes Quarterly Yes-Note 3 Water Pump OH00lPA Control Room 3 H-l l 8 No Yes Yes Yes PR-1 PR-2 Quarterly Yes Note 3 Chilled Water Pump OWOOlPB Control Room 3 M-118 No Yes Yes Yes PR-1 PR-2 Quarterly Yes Note 3 Chilled Water Pump 3.3 PUMP TABLES - Page 4 of 4 217(070891) ZD79G/4 . a

M-1 INSERVICE TESTING PROGRAM PLAE4'FOR PUMPS BRAIDWOOD STATIC 25 UNITS 1 AMD 2 Revision 5 SECTICM 3.4 PUMP NCTTES 217(070891) ZD79G/1

.l INSERVICE TESTZWG PROGRAM PLAN FOR PUMPS BRAIDWOOD STATION UNITS 1 AND 2 Revisio 5 PUMP NOTES HQTE 1 -Deleted-HQIE_2 The Diesel Oil Transfer (1DOO1PA-D and 2DOO1PA-D), Residual Heat Removal (1RH01PA/B and 2RH01PA/B) and Containment Spray (ICS01PA/B and 2CS01PA/B), pumps cannot be measured for lubrication level. These pumps are lubricated by the fluid pumped and hence have no indication for lubrication level. NOTE _3 The Component Cooling Water pumps (OCC01P, ICC01PA/B and 2CC01PA/S), Essential Service Water Pumps (ISX01PA/B and 2SX01PA/B), and the Control Room Chilled Water Pumps (OWOO1PA/B) are in systems which are in continuous operation. The idle it.let pressure for these pumps cannot be obtained without interrupting normal system operation and causing system transients. The idle inlet pressure will be recorded only if the pwnp to be tested is not in operation at the start of the test. Proper pump operation is assured by continuous pump operation as well as quarterly monitoring of the remaining ISI pump parameters. NQIE A -Deleted-HQII._5 Not Used at Braidwood - Byron ONLY NQIE_6 Not Used at Braidwood - Byron ONLY l HQIT.L.1 Not Used at Braidwood - Byron NLY I l i 3.4 - Page 1 of 1 1 217(070891) ZD79G/21 l l

W,-, INSERVICE TESTING PROGRAM PLAN FOR PUMPS BRAIDWOOD STATION UNITS 1 AND 2 Revision 5 SECTION 3.5 IVHP TEC11NICAI, APPROACIIES AND POSITIONS l 217(070891) ZD79G/22

Rovision 5 IST Technical Approach and Posjtion No. PA-01 l A.- Compnnent Identification: j 1. -Description: Performance Testing of the Boric Acid ( AB) Transfer Pumps 2. Component Numbers: 0AB03P, 1/2AB03P 3.

References:

(a) Engineering Correspondence (CliRON 9161733) dated January 17, 1991 4. Code Class: 3/T (Tracking purposes ONLY)) B. Requirements: The ASME Section XI Code requires safety related pumps performing a specific function in shutting down the reactor or in mitigating the consequene.es of an accident, and that are provided with an emergency power supply be included in the inservice testing program (IST). However, the.AB pumps do not have an " emergency" power supply, so consequently, they are not required to be included in the program. Braidwood was licensed as a " hot shutdown" plant. This means it was only required to be capable of hot shutdown using r.on-safety related systems or repair to postulated damaged equipment. For this reason the electrical support for.the emergency boration function is Safety Category II. Also, tdue RWST (Refuellug Water Storage Tank) is a seismic Category I structure - as described in the UFSAR Table 3.2-1 and is designed to withstand design basis accidents, including tornados. The RWST is required for ECCS (Emergency Core Cooling Systems) operation. The AB pumps are tested per the Technical Specification requirement that requires-an 18 month flow verification of.30 gpm to the RCS. Also, the AB pumps are monitored per the station's vibration monitoring program requirements. C, fosition: The AB purc "all outside the scope of one ASME Section XI and the IST program. However, because of.tlut operating significance of these pumps, and based on correspondence and discussions witli NRR and CECO Engineering, Braidwood Station has decided to list the AB pumps in the program for' tracking purposes only. They will be tested in a like fashion to the ASME Section XI program. The hydraulle limits used will be similar to those specified in ASME/ ANSI OMa-1988, Part!6.- Meaning that the differential pressure limits will be plus or minus 10 percent of its reference value (flow rate will be a set value). There will be no alert limits placed on differential pressure. The AB pumps will_ be trended-to monitor for degradation or_ abnormal / erratic operation. Also,-the vibration l _ readings and limits will be similar to those in ASME/ ANSI OMa-1988, Part 6. { 3.5 - Page 1 of 1 217(070801) ZD79G/23

Revision 5 SECTICM 3.6 ITMP RELTEF REQUESTS i i i-l 217(070891) ZD79G/24

~_ RGvision 5 RELIELEEQUES*L110dR-41 .l 1 '1. EUMP NUMBER: All pumps in the program plan. -2. RUMDER_Of_ ITEMS: 47 pumps. '3.- ASME_CODI_ELASSt-2&3 4. ASNE CODE d ICTION_XI REQQ1REMENTS: In refereace to Table IWP-3100-2, " Allowable Ranges or Test Quantities", pump vibration is to be measured in and compared to $1ues given in mils displacement. 5. BASIS _EDR_RELIIE: The measurement'of pump vibration is required so that developing problems can be detected and repairs initiated prior to a punp becoming inoperable. Measurement of vibration only in displacement quantities does not take into account frequency which is also an important factor-in determining the severity of_the vibration. 6. ALIKERAIE_ TESTING: 0 l The ASME Code minimum standards require measurement of the vibration i amplitude in mils (displacement). Braidwood S2ation proposes an alternate program of measuring vibration velocity (inches per second) which is more' comprehensive than that required by Section XI. This technique is an industry-accepted method which is much more meaningful and sensitive to small changes that are indicative of developing mechanical problems. These velocity measurements detect.not only high amplitude vibration, that indicate a major mechanical problem such as misalignment or unbalance, but also the equally harmful low amplitude, high frequency vibration due to bearing wear that esually goes undetected by simple displacement measurements.- The allowable ranges of vibration and their associated action levels will be patterned after the requirements established in ANSI /ASME OMa-1988, Part 6. These ranges will be used in whole to assess equipment operational readiness for all-components. t j The acceptable performance range for.all components will be 1 2.5-times the 2 reference value, not to exceed.325 inches per secord. The alert range,,a t which time the testing frwquency would be doubled, will be > 2. 5 to 6 titnes the reference value, not to excewd.70 inches per second. Any vibrating velocity greater than 6 times the reference value or greater-than.70 ' inches-per second will require corrective actions to be performed on the j affected component. I.- i. Vibration measurements for all pumps will be obtained and recorded in l* velocity, inches per second,-and will be broadband unfiltered peak i measurements. The monitored locations for vibration analysis'will be marked so as to permit subsequent duplication in both location and plane. 3.6 - Page 1 of 10 -217(070891) ZD79G/25 . - - ~

Rovlsion 5 RELIELEEQUESTJia_EIL-01 The frequency response range of the vibration transducers and their readout system shall be cwpable of f requency responses f rnm one-third mlnlmum pump shaft rotational speed to at least one thousand herts; The Vertical Line Shatt pumps in the program will have vibration measurements taken on the upper motor bearing housing in three orthogonal directions, one of which is-the axial direction'. i 7. JilET1f.1CATL0ti t Measurements of vlbration in mils displacement are not sensitive to small changes that are indicative of developing snechanical problems. Therefore, the nroposed alternate method of measuring vibration amplitude la inches /second provides added assurance of the continued operability of the pumps.. Also, there are no positive displacement pumps or centrifugal pumps which rotate at less than.600 RPM in Braldwood's IST program. i 8. ArrLICADLE_.7110LEIR10D1 Thls relief-la requestted once per quarter during the first inspection interval. 9. AEERQYA L ETATUS.L a. Rellet granted per NRC Generle Letter 89-04. s i 1 i s 1 i 3.6 - Page 2 of.10 i i 217(070891) ZD790/26 _a___,._________.-_____.....____._..-,-,._.u__..-....._.....-.

Revision $ RELIEL RE0 VEST _130.. PIE 02 i. TVMENUMDEE: OCC01P, ICC01PA, ICC01PH, 2CC01PA, 2CC01PH, ICS01PA, ICS01PH, 2 CliO 1 P A, 2 CS01Pil, IDU01PA, 1D001Pli, 1D001PC, ID001PD, 2D001PA, 2D0010H, 2D001PC, 2D001PD, 1 Ril01 P A, 1R1101 Pit, 2NH01PA, 2 k H01 Pil, OWOO1PA, OWOO1PH 2. HUMDER.QE_ ITEMS! 23 pumps 3. ASME CVDE_ CLASS: 2 &3 4 ASM E COPE, _.S ECT 10!L X LECOU I E EMENTS : Per IWP-3100, Innervice Test, Ptocedute pump bearing temperatures are required to be mear.us ed to detect any change in the mechanical characteristics of a bearing. 1WP-3500(b) requires three successive readings t aken at ten minute intervals thnt do not vary more than 3%. 5. DASIS_ E01 RELIEE: These pump hearings are not provided wit.h permanent temperature a. detectors on thermal wells. Therefore, gathering data on bearing temperature is impractical, b. The only tempesature measurements possible are from the bearing housing. To detect high bearing temperature at the bearing housing would requite that the bearings in qu3stion be seriously degraded. Measurement of housing temperature on t.hese pumps does not provide c. positive infotmation on beating condition or degradation. Por example, the bearings on the Diesel 011 Transf er Ptunps (1DOO1PA-D and 2DOO1PA-D) are cooled by the pumped fluid. Therefore, any heat generated by degraded bearings is carried away by the cooling fluid and would not be dir ect ly measur ed at the bearing housing. f>. AL'/EPRATLlEST1HG No direct alternate test is proposed for bearing temperatures.

However, mear.urement of hydraulle patameters and vibration readings do provide a more positive method of monitoring pump condition and bearing degradation.

7. JUSTJLICAT10H: Dy measuring pump hydraulle parameters and vibration velocity, (as described in PR-01), pump operahility and the

t. r ', nd i h i of mechanical degradation in assured.

Also, since these parameters (i.e., hydtnulic parameters and vibration) are measured quarterly, the pump mechanical condition will be more accutately determined than would be possible by measuring bearing temperature on a yearly

e. sis.

8. APPLICADLE TIME _ PERIOD: This relief in sequested once per year, during the first inspection interval. 9. APPEDVAL.SThTUS: Pelief gi ant ed per NRC Generic Lett er 89-04. r. 3.6 - Page 3 of 10 217(070891) ZD79G/27

... _. _ _.. _ ~ ._m._._ Revision 5 RELIELREQUESLNQ4_PR-D20 1. l'UMPJiUNDER: All psunpa in the program plan. 2. HUlillE1LDE_lTCMS: 42 pumps 1 3. ASMLCODLCLASS: 2 f. 3 ) 4. ASME.IORC 4.J ECIlotlXLE CQUIRDiCN TS : Per IWP-3100, inservice Test Procedure pump bearing temperatures are required to be measured to detect any change in the mechanical characteristics of a bearing. INP-3500(b) requires three successive readings taken at ten minute intervals that do not-vary acre than 3%. 5. DASIS_IQR_RELIEft-n. The CC, CS, DO, RH, SX and WO pump bee.' ags are not provided with 'l permanent temperature detector s or therrnal wells. Therefore, .j gathering data on bearing temperature'is impractical. The only temperature measurements possible are from the bearing housing. i Measurement of housing temperature on these pumps does not provide ~ positive information on bearing condition or degradation. b. Even those casos where bearing temperature monitoring equipment.ls available, bearing temperature ineasurements will not provide 4 significant additional information regarding bearing condition other than that already obtained by measuring-vibration. Measurement of' vibration provides more concise and cotsistent Information with respect to pump and bearing condition. The usage of vibration ineasurements can provide information as to a change in the balance of rotating parts, misalignrnent of bearings, *rorn bearings, changes in internal hydraulle forces and general ptunp integrity prior to the condition degrading to the point where the component is jeopardized. Bearing temperature does not always predict such problems.- 3 c. An increase in bearing temperature most often does not occur until the bearing has deteriorated to a point where additional pump damage may occur. -Bearing temperatures are also affected by the temperature of i the medium being ptunped. thus the hydraull: and vibration readings are re?re consis tent. Also, the Code specifictily exempts temperature measurement for pump bearings in the main flow path (i.e., the diesel oli transfer pumps). 3.6 - Page 4 of 10 217(070891) ZD79G/28 _-___.._.___._..__;.__u.

Revision B \\ RELIELEEQUESI_NQJR-32 a 6.- ALTEFJiATLIESIING t l Quarterly measurement of hydraulle parameters and vibration readings + i provide a more positive method of monitoring pump condition and bearing degradation. l 7. MSIIE1CAIlotit Dy measuring pump hydraulle parameters and vibration velocity, (as described in PR-01), pump operability and the trending of mechanical l d degradation is assured. Also, since these parameters (t.e., hydraulle parameters and vibration) are measured quarterly, the pump mechanical condition will be more accurately determined than would be possible by measuring bearing temperature on a yearly basis. l 1 8. APlLICADLE TIME PERIQD: This rellof is requested once per year, during the first inspection interval. 9. AEEROYALSIAWS i This relief As a proposed change to the approved PR-02 and is HQT approved _for use. f'ormal written approval from the NRC la required + pilur to use. Expedited review and approval is requested. I ( 7 3.6 - Page B of 10 i 217(070891) ZD79G/29 ,..., _ _.., -, _... ~.. _,..., _ _. _,,...... _., _., _ _. _... _ _. _. _...... _ _.. -.... - _, _,. _ -..,..,, ~,. _, _,...

AdTG!CI)M1%. Hevision 5 RELIEEEE7 JEST _NO._l'R10, -Deleted-

3. 6 - l' age 6 of 10 217(070891)

ZD79G/30

Revision 5 RELIEE EEQUESLHQ,_EE:.QA -Deleted-i j t t L l! i t i I .t 6 i 3.6 - Page 7 of 10 l l 217(070891) ZD790/31 i ~

Revision 5 RELLEE_EEQ'lEST_HQ uPRr05 1. PUMP NUMI;ER: OCC01P, ICC01PA, ICC01PD, 2CC01PA, 2CC01PD, ISX01PA, ISX01PD, 2SX01PA, 2SX01PB 2. NUMD;R_UE_ ITEMS : 9 Pumps 3. ASME_CODL_ CLASS: 2&3 l 4. ASME_CODEuSECTIPH XL FIINIEEMENTS Per IWP-4120, the full scale range of each inst,rument shall be three times the neference value or less. 5. DASIS_ EOR _ RELIEF The full scale range of ultrasonic flowmeters, used to collect Section XI flow data, exceed three times the reference value. 6. ALTEPJ! ATE _IESTING: Ultrasonic flowmeters. with digital readouts and totalizer features will be utilized to obtain Section XI flow data. 7. JUET.IE1CliTION : Ultrasonic flowmeters provide en accurate means of measuring flowrate. They utilize a digital displey whose accuracy is independent of the full scale range. The ul t.r a s on i c flowmeter is well within the requirements of IWP-4110 and IWP-4120, which refer to an 11strument accuracy of + 2 % of full scale for an instrwnent with a tange of three times the refetence value or less. The follcwing examples will illustrate this point. The component cooling pumps (OCC01P, 1/2CC01PA, and 1/2CC01PD) have a reference value of approximately 4500 gpm. Using the Code requirements, an instrument with a full scale range of 13,500 gpm (3 x 4500 gpm), the acceptable instrument accuracy is 270 gpm (.02 x 13500 gpm). Using the ultrasonic f.awmeter, with an accuracy of.t 4% of the indicated reading, provides an instrument accuracy of a 180 gpm.(.04 x 4500 gpm). Use of an ultrasonic flovmeter, with totalizer and integrator feature, instead of other instruments allowed by IWP-4110 and IWP-4120, will provide more precise and accurate flow measurements. 8. APPLICADLE_2IME_ PERIOD ;'. 3c This relief JG requested $3ce per quarter, during the first inspection interval. 9. API $t0VA LSTATUS: a. Relief grant ed per NRC Generic Letter 89-04. 3.6 - Page 8 of 10 217(070891) ZD79G/32 t I t I

Itevision 5 FELILLEE0 VEST _NQu PRr00 1. 1: UMP _ HUMDER: 1D001PA, IDOO1Pil, 1DOO1PC, 1DOO 11'D, 2DOO1PA, 2 DOO 1 P!J, 2DODIPC, 2DOO1PD, 2. UUMDELLOLITEMS: B pumps 3. AEME_f0DE_ CLASS 3 4. A SME_ COD E, _ S E CT I O!L T. L RERVI B EMEN T S Per 1HI'-3100, differential pressure shall be measured on all pumps that are tested. 5. DASID_TQllELLIEE These pumps are positive displacement Diesel Oil Transfer Pumps. The pump differential pressure is not a factor affecting pump performance, but rather dependent only on the Anlet pressure to the pump. As the pump discharge pressure is constant, and the inlet pressure varies with tank level, the differential pressure is not a valid,, Lr ational par amet er. 6. ALTERHATE TISTIRQt Pump discharge pressure for positive displacement pumpn is a valid operational parameter. This will be used to evaluate the Diesel Oil Transfer Pumps performance. 7. JUSTIr1 CAT 10H Using pump discharge pressure in lieu of pump differential pressure will provide meaningful pump performance data for evaluation of operational readiness of the Diesel Oil Transfer Pumps. 8. APPLIC ABLE__ TIME _ PERIOD 8 This relief is request M once per quarter during the first inspection interval. 9. Aff1M AL_ STATUS: a. Ite11ef granted per N14C Generic Letter 09-04. 3.6 - Page 9 of 10 217(070891) ZD79G/33

1 Revision L ELLIEt'_ REQ' JEST _140 I'R-07 110 t tised at Braldwood - Ilyron OtiLY 3 6 - Page 10 of 10 217(070891) ZD79G/34

l ATTACHMENT C l lNSERVICE TESTING PROGRAM PLAN FOR VALVES l ZNLD/968/7

l Revision 5 SECTICN 4.0 INSEftVICE TESTING l'HOGitAM l'I.AN l'OR VAINES IIR A11MKXX) STATI(N LINITS 1 AND 2 217(070891) ZD79G/35

Revision 5 TAHLE OF CtMTENTS 4.0 Inservice Testing Program Plan for Valves 4.1 Program Description 4.2 Program References 4.3 Valve Tables 4.4 Valve Notes Note 1 Main Steam Isolation Valves Note 2 CV Emergency Boration System riowpath Valves Note 3 Main Feedwater Isolation Valves Note 4 CV System Letdown and Make-up Isolation Valver Note 5 RHR Pump Suction Isolation Valves Note 6 Intersystem LOCA Valves Note 7 Reactor Vessel Head Vent Valves Note 8 CV, RHR Pump Discharge Check Valves Note 9 RHR ECCS Check Valves Note 10 Main Feedwater Waterhammer Prevention Valves Pote 11 VQ Purgo Supply and Exhaust Isolation Valves Note 12 AF Suction and Steun Generator Check Valves Note 13 CV High Head Injection Isolation Valves Note 14 SVAG Valves Note 15 -Deleted-Note 16 Main reedwater Regulating Valves Note 17 Main Feedwater Regulating Bypass Valves Note 18 -Deleted- (Incorporated into Hote 21) Not e 19 -Deleted- (Incorporated into Note 14) Note 20 Position Indication Testing cf Solenoid Valves Note 21 Main reedwater Tempering Flow Isolatio" Valves Note 22 Hydrog*n Monitoring System Check Valves Note 23 Event % Check Valves Note 24 Pressure Relief Check Valves Note 25 SI Pump Suction Check valve (1/2818926) Note 26 CV Pump Suction Check Valve (1/2CV8546) Note 27 RH Pmnp Suction Check Valves (1/251895BA/B) Note 28 VCT Outlet Check Valve (1/2CV844C) Note 29 Emergency Boration Check Valve (1/2C"8442) Note 30 AT Check Valve Leak Checks (1/2AF014A-H) Note 31 CV/SI Mini-Flow Recirculation Line Check Valve Full Flow Testing (1/2CV8480A/B and 1/2SI8919A/B) Note 32 CC Pump Discharge Check Valves (1/2CC9463A, 1/2CC9463B, OCC9464) Note 33 Not Used at Braldwood - Byron ONLY Note 34 SD Containment Isolation Valves (1/2SD002A-H, 1/2SD005A-D) Note 35 RH Containment Isolation Valves (1/2RH8705A/B) Note 36 PZR PORVs 1(2)RY455A/4S6 Test Frequency (GL 90-06) 4.0 - Page 1 of 2 217(070891) ZD79G/36 i t

Revision $ TAHLE OF CONTINTS 4,5 Valve Technical Approactes and Positions VA-01 Method of Stroke Timing Valves VA-02 Method of Fall Safe Testlng Valves VA-03 Method of Exercisin'g Check Valves VA-04 Determining Limiting Values of Tull-Stroke Times for Power Operated Valve 6 VA-05 Testing of the Boric Acid Transf er Punips Discharge Check Valves 4.6 Valve Relief Requests VR-1 Appendix J Type C Tested Valves VR-2 Containment Spray NaOll Additive Check Valves VR-3 Safety Injection ECCS Check Valves VR-4 Containment Spray Discharge and Ring Header Check Valves VR-5 Accumulator Discharge Check Valve Testing During Refueling VR-6 51 Pump Suction Check Valve VR-7 -Deleted-VR-R Component Cooling RC Pump Thermal Barrier Volves VR-9 RC Pump Seal Injection CV Check Valves VR-30 Instrument Air Containment Isolation Valves VR-11 -Deleted-VR-12 Valves Str oking Normally in 2 Seconds or Less VR-13 Diesel Generator Ste.iting Air Solenoid Valveo VR-14 -Deleted-VR-IS Snfety Injection ECCS Check Valve Testing During Refueling VR-16 Containment Sump Outlet Isolation Valve Testing During Refueling VR-17 Motor Driven Auxiliary Teedwater Pump LO Cooler Solenoid Valve Stroke Testing VR-18 SI Check Valve Back Flow (Ht) Testing During Refueling VR-19 Auxiliary Feedwater Pump Suction Check Valve Disassembly and Inspection per NRC Generic Letter 89-04 VR-20 Hot Used at Braidwood Station - Byron ONLY VR-21 Not used at Draidwood Station - Byron ONLY VR-22 Not Used at Braidwood Station - Byron ONLY VR-23 PR Check Valve Back Flow (Dt) Testing During Refueling VR-24 PR Check Valve Back flow (BL) Testing During Refueling VR-25 PS Check Valve Beck Flow (BL) Testing During Refueling VR-26 RY Check Valve Back Flow (BL) Testing During Refueling VR-27 WO Check Valve Back Flow (Bt) Testing During Refueling 4.0 - Page 2 of 2 217(070891) ZD79G/37

Rovision 5 J SECTION 4.1 PROGRAM DESCRIPTIOf 217(070891) ZD79G/38

Revision 5 PROGRAM DESCRIVfIm The Inservice Testing (IST) Program for Class 1, 2, & 3 valves meets the requirements of Subsection IWV of the ASMC Section XI Code, 1983 Edition, through the Summer of 1983 Addenda. Where code requirements are determined to be impractical, specific requests for relief are written, referenced, and included with the tables. Additional valve relief requests may be necessary and these will be Identified and submitted during subsequent progran revisions. Per NRC Generic Letter 89-04, the status of relief requests as stated in the SER is unchanged. Any modifications to Braidwood's Station relief requests approved in the SER which are covered by one of the eleven positions discussed in NRC Generic Letter 89-04, Attachment 1, must he per fortned in accordance with the guidellnes given in the Generic Letter. Pre-approval is granted for all relief requests submitted which are consistent with the eleven positions given. New relief requests dealing with a position nqi covered by HRC Generic Letter 89-04, Attachment 1, must receive NRC appreval prior to implementation. The table lists all code Class 1, 2, &3 valves which have been assigned a specific code category as directed by Subsection IWV of Section XI. The table is organired according to operating system and listed in valve number order using P&lD references to f urther categorire. The valves subject to ISI testing are those valves which are identified in accordance with the scope of ASME Section XI, Subsection IWV-1100 "This Subsection provides the rules and requirements for inservice testing to assess operational readiness of certain Class 1, 2, and 3 valves (and their actuating and position indicating systems) in light-water cooled nuclear power p'. ants, which are required to perform a specific function in shutting down a reacter to the cold shutdown condition or in mitigating the consequences of an accident." Exceptions to this scope are these valves which are exempt, but added to the progrmn based on NRC mandates. These valves are identified in the progren notes and relief requests. After installation and prior to service, all valves identifled in this program were tested as required by Subsection IWV-3100 of Section EI of the ASME Code. These tests were c3nducted under conditions similar to those to be experienced during subsequent inservice tests. When a valve or its control system has been replaced or undergone maintenance that could affect its performance, it will be retested prior to its return to service, to demonstrate that all perf ormance parameters are within acceptable limit s. i l 4.1 - Page 1 o t' 2 l 217(070891) ZD79G/39 i

Revision 5 As required by HRC Generic Letter 89-04, Attachment 1, Position 5, the limiting value of full-stroke time will be based on the valve reference or average stroke time of the valve when It is known to be in good condition and operating properly. This limiting value is based on a reasonable deviation from this reference stroke time based on valve sir.e, valve type, actuator type, system design, dual unit / dual train design, etc. The deviation should not be so restrictive that it results in a valve being declared inoperable due to reasonable stroke time variations. However, the devlatlon used to establish the limit should be such that corrective action would be taken for a valve that may not perform its intended function. New or additional reference values may be required Af 1) A valve has been replaced, 2) When a reference value or set of values may have been affected by repals or routine servicing of a valve, or 3) If it is necessary or desirable for some reason other than 1) or

2) above.

HRC Generic Letter 89-04, Attachment 1, Positions 1-3 discuss full stroke, j alternatives to full stroke, and backflow testing of check valves, respectively. A valid full stroke test is one in which verification of i maximum required accident condition flow through the valve is obtained. The minimum acceptable flow va4ue for a specific valve is determined from Technical Specifications, UFSAR, manufacturers data, engineering calculations, etc. An alternative to full stroke testing includes, but is not limited to, a sample disassembly and Inspection program of valves grouped by similarity of design (manufacturer, size, model number, materials of construction, etc.) and service conditions (including valve orientation). This sample disassembly and inspection program will be performed during refueling outages. A backflow test. verlfles that the disc travels to the seat promptly on cessation or reversal of flow, for check valves which perform a safety function in the closed direction. For category A/C check valves (valves that have a crecified leak rate limit and are self-actuated in response to a system characteristic), the backflow test is satisfied by performing the Jenk-rate test. ] Per NRC Generic Letter 89-04, Attachment 1, losition IB, whenever valve data is determined to be within the Required Action Range, the valve is inoperable, and the Technical Specification LCO Action Statement time starts. In the event a valve must be declared inoperable as a result of inservice testing, limitations on plant operations will be as stated in the Technical Specifications. I Section XI of the ASME Boller and Pressure Vessel Code shall not be construed to supersede the requirementr of the Technical Specifications. 4.1 - Page 2 of 2 I i l l 217(070891) ZD79G/40 i u.

Hovision 5 SECTICM 4.2 l'R(X; RAM REFERDfCE!1 i 217(070891) ZD79G/41

'I Rovlsion 5 PROGRAM REFERENCES 1. Title 10, Codo of Federal Regulations, Part 50, Domestic Licensing of Production and Utilization Facilities, particularly Section 50.55a, Codes and Standards. 2. ASME Doller and Pressure Vescel Code, Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components, 1983 Edition, Summer 1983 Addenda. 3. ASME/ ANSI OM-1987, Operation and Maintenance of Nuclear Power Plants, includlug 1988 Addenda, Part 10, Inservice Testing of Valven in Light Water Reactor Power Plants. 4. U. S. Nuclear Regulatory Commission, Generic Letter 89-04, Guidance on Developing Acceptable Inservice Testing Programs. 5. Draldwood Station UPSAR, Section 3.9.6.2, Inservice Testlug of Valves. 6. Breldwood Station Technical Specification 4.0.5, ASME XI Program Req ui r eme r.t s. 7. Draldwood Station Technical Staff Procedures, DVP 200-2, 200-3, & 200-4, IST Requirements for Valves. 8. NRC Safety Evaluation Report:s (SER's): 4.2 - Page 1 of 1 217(070891) ZD79G/42

Revision 5 ) SECTILM 4.3 VAINE TABLES l l ) l ) I i i i 217(070891) ZD79G/43 r

Itevision 5 TAnLE Dr:r.CHIPTI(M The following information Ja included in the valve summa: y t ables: A. REYlSIM{n The revision corresponds to the current revision of the program. D. l' AGE : The pages are numbered sequentially and show the total number of tables. C. VALYE R HilEB The valve number references the unique Braldwood Station equipment piece number (EPN). This specific valve number identifles the unit and system. D. 1%JD: The P&lD column references the specific P&lD number which the valves are located on. The Unit 2 P&ID number is given directly underneath the Unit 1 P&ID number. E. CLASS: This column refers to the ASME Code Class assigned to the specific valve (1, 2, 3, N for non-Code, and T for tracking purposes only). F. VALVI_ CATEGORY: The valve category identifies the valve category defined in subarticle IWV-2200 of ASME Section XI. G. VALVE _ SIZE The valve size lists the nominal pipe size of each valve in inches. l l l l 4.3 - Page 1 of 5 217(0701591) 7.D79G/44

Hevision 5 TAllt.E DESCRIPTICH 11. VALVE _ TYPE: The valve type categorites the valve as to its valve design. The following abbreviations will be used t.o identify specific valve types Gate GA Globe GL Butterfly BTF Check CK Safety Valve SV Relief Valve HV Power Operated !.ellef Valve PORV Diaphragm Seated D Plug P Angle Idi 1. ACL_TYr.E The actuator type identifJos the valve actuator. The following abbreviations will be used to designate speelfic types of valve actuators: Motor Operated M.O. Air Operated A.O. Hydraulic Operated H.O. Self Actuated S.A. Manual M Solenoid Operated S.O. J. IlQEMAL_f.QSITIQli llormal position identifies the normal operating position of a specific valve. O for open and C for closed. K. STROKE _DIRECIIQi The stroke direction identifies the direction the valve actuator moves a specific valve stem to place the valve disc in a position to perform its designed safety function. O for open, and C for closed. This identifles the dl,rection the valve stem will move when tested. Note Exercising of a power operated valve will involve stroking the valve to both its open and closed position. The valve will only be timed, however, in the direction designated to perform its safety function. Therefore. the program plan specifies only the direction in which valves must be stroked to be timed. 4.3 - Page 2 of 5 217(070891) ZD790/45

R3violon 5 TAltl.r. Df;SCitIPTI(N h. TEST E Til0D The test method column identifies specific tests whlch will be performed on specific valves to fulfill the requirements of Subsection IWV of ASME Section XI. The tests and abbtevlations used are as followst 1. (Dt) Check Valve 13ack I'l ow Te s t The check valve disc will be exercised to the closed position required to fulfill its safety function by verifying that the disc travels to the seat promptly on cessation or reversal of flow, except fot those valves that can only be back flow tested by rneans of a sent leakage test. 2. ICtLCbecLValvelulL Stro k e_ Te nt The check valve disc will be exercised to the open position required to fulfill its safety functlon by verifying thn. maximum required accident flow through the valve or alternatives to full flow testing, per HRC Generic hetter 89-04, Attachment 1, Positions 1 end 2. 3. IEtLTall Snic Test Valves with fall safe actuators will be tested to verify the valve operator moves the valve stem to the required fall safe position upon loss of actunting power, in accordance with IWV-3415.. IN This wil ibe or pmplished during the normal uttoking of the valve. on s /4,) king a valve to its fall safe position, the solenoid.,3perat]r is de-eneagired causing air to be vented which In turn a Alows ' he spring to move the valve to its fall safe position. This condition simulates loss of actuating power (Electric and/or Alt) and hence satisfles the fall safe test requirements of IWV-3415. 4. LILLPositiculndication_ Check Valves which are identified to require a Position Indication Test will be inspected in accordance with IWV-3300 of ASME Section XI. 5. ILtLSenticok egtL Tes t The seat leakage tests will meet the requirements of INV-3420 for Category A valves. On these valves, seat leakage is limited to a specific maximum amount. In the closed position for fulfillment of their safety funct ion. i l 4.3 - Page 3 of 5 217(070891) ZD79G/46

Revision 5 TAHl.E DESCRIPTI(M 6. 1RLLSaf ety._Yalve Se troinLCheck Safety valve setpoint n will be verlfled in accordance with IWV-3510 of ASME Section XI. 7. ISLL11ull HLtrike _TesL Valve exercialng tests of Category A and B valves will be per f ortned in accor dance with 1NV-3410. The test will include full stroke testing to verify operability in the direction required to fulfill the required safety function. 8. IKLLlattial-littche lest if only limited operation is practical during plant operation, the valves shall be part-stroke (Xt) exercised during plant operation and full-stroke exercised during cold shutdowns, In accordance with IWV-3412 or IWV-3522. M. iEST_ MODE: Denotes the frequency and plant condltlon necessary to perform a given test. The following abbreviations are used HQ tital_ Ope tallon_.J 0P1 Testa designated "0P" will be perfoirned once every 3 mont hs, except in those modes in which the valve is not required to be operable. Semiannual IS) Tests with this designation will be conducted once every 6 months, except in those modes in which the valve is not required to be operable. ColtL Shutdown _lCS) Valves that cannot be operated during plant operation shall be full stroke exercised during cold shutdowns. Valve testing will commence within 48 hours after shutdown, with completion of cold shutdown valve testing not being a preregulsite to plant startup. Valve tests which are not completed during a cold shutdown, shall be completed during subsequent cold shutdowns to meet the Code Specified Testing frequency, for planned shutdowns, where ample time is available, and testing all the valves identitled for cold shutdown test frequency in the IST Program will be accomplished, exceptions t.o the 48 houro may be taken. In case of frequent cold shutdowns, valve testing need not be performed more often than once during any three-month period. i - Re ac Lo r_Ref ueling _(RR) Tests with this designation will be conducted during teactor refueling outages only. 4.3 - Page 4 of 5 217(070891) ZD79G/47

Revision 5 TARI.E DESCitIPTION H. ECLIIf_EIQUEST: Relief requests reference a specific request for relief from code requirements. All relief requests are included in Section 4.6. O. 11 RIES: Notes provide a short explanation concerning a particular IST valve. All notes are included in Section 4.4. P. TIflPdlCAL_AffERAtllE S_Al!D_fDSIT10l!S Technical approaches and positions provide detailed discussions on a particular IST topic. All technical approaches and positions are included in Section 4.5. O. EDiARKS: Remarks reference other information useful in determining valve testing requirements or methods. i l l a l 4.3 - Page 5 of 5 217(070891) ZD79G/48

.[:I; + ihi,ii h: l;*! ( ti m SK RAM E R H .) C5A 5 5 E0V TP( 34 fo S 1 E T O e N ga P SE T L rS B EE) A IUR T LQV EE( E RR V L AV 3 TE 4 SD' P P EO O O TM D TO SH t t ET C C TE M ET KC OE 0 0 RR TI SD N LO AI MT RI C C OS NOP .E TP A. A. CY AT 5 5 EVE LP K K AY C C VT E ) VE. 0 0 LZN AII 2 2 VS( Y R EO VG C C LE AT VA S C E V LA N S N V O S A I A T T L DT L P E A C T T M N S AE R M R A A G G E 5 5 O U W D R A O I 5 5 P P 6 6 d P G nR M M N aA.E 2 I T L S 3 C & E .U N, 3 7 ) T 2 1 5. R 7 8 1 E O EE 4 4 9 C ,O , n VB 8 8 8 9 I 1 O 0 o LM B B 0 4 V W AU A A 7 / i E S I T i / ( G RS D S s VN 0 2 0 9 S A A I v 1 7 7 N L E N e 1 D I C B U R. 2 Z t = lj-:. 1I 1 1 l; I 4 e i!!!i! 11 !'i !i 1 5; i '1Il !.j; 1; 4

INSERVICE TESTING PROGRAM PLAN i a CLASS 1, 2, 3, and AUGMENTED VALVES f

. BRAIDM)DD NUCLEAR POWER STATIO;t UNITS 0, 1, & 2' i

. Revision 5 4

VALVE VALVE VALVE VALVE ACT. NORMAL STROKE TEST TEST RELIEF TECH. NUMBER P&ID CLASS CATEGORY SIZE TYPE TYPE POSITION DIRECT. METH00 NOCE REQUEST NOTES POS. REMARKS 1-(IN.1 (VU) (VA) 1/ZAf001A N37 3 C 6.0 CK S.A. C 0 Xt/Ct OP/CS 12 3 l i t M-122 C 8t RR VR-19 1 1/2Af001B M-37 3 C - 6.0 CK S.A. C 0 Xt/Ct OP/CS 12 3 l N122 'C Bt RR VR-19 3 j-1/2Af003A N37 3 C 6.0 CK S.A. C 0 Xt/Ct OP/CS 12 3 - N122 f 1 1/ZAF0038 N37 3 C 6.0 CK S.A. C 0 Xt/Ct OP/CS 12 3 l l N122 1/2Af006A N37 3 6 6.0 GA M.0. C 0 St OP 1 l N122 It RR 1/2Af0068 N37 3 B 6.0 GA M.D. C 0 St OP 1 M-122 It RR j 1/2AF013A N37 2 B . 4.0 GL M.0. O C St Op 1 N122 It RR {. 1/2Af013S N37 2 B 4.0 GL M.O. O C St OP 1 ? I N122 It RR 2 1/2Af013C N37 2 B 4.0 GL M.0. O C St 09 1 ) } M-122 It RR i 1/2AF0130 5 37 2 B 4.0 GL M.D. O C St OF 1 1 f e N122 It RR l } 1/24.f 013E N37 2 B 4.0 GL M.D. O C St OP 1 j N122 It RR 1/2Af013F N37 2 B 4.0 . GL M.0. O C St OP 1 r l N122 It RR j 1/2Af013G' M-37 2 B 4.0 GL M.O. O C St op 1 4122 It RR 1/2Af013H N37 2 8 4.0 GL M.0. O C .St OF 1 6 4 N122 'It RR [ 1/2Af014A N37 2 C 4.0 ~CK S.A. C 0 Ct CS 12 3 N!22 C' Et CS

12. 30 3

1 1/2AF0148-N37 2 C 4.0 CK S.A. C 0 Ct CS 12 3 i N122 C Bt C5

12. 30 3

i j 4.3 VALVE TABLES - Page 2 of 43 { 217(070891) k . ZD79G/50 j - ~

1. l INSERVICE TESTIM PROC 4AM PLAN CLASS.1. 2, 3. and AUGMENTED VALVES-BRAIDWOOD PM. LEAR FOWER STATION UNITS 0, 1. & 2 [ l Revision S {. j VALVE VALVE VALVE VALVE ACT. NORMAL STROKE TEST TEST RELIEF TECH. i TYPE l POSITION DIRECT. METHOD N00E CEOUEST . NOTES POS. REMARKS NthBER P&lD CLASS CATEGORY SIZE TYPE IIM.} (VR) (VA) [ j' 1/ZAF014C N37 2 C 4.0 CK S.A. C 0 Ct CS 12 3 [ N122 C Bt CS

12. 30 3

1/2AF0140 N37 2 C 4.0 CK S.A. C 0 Ct CS 12 3 f i i N122 C 'Et CS

12. 30

'3 [ 1/ZAF014E N37 2 C 4.0 CK S.A. C 0 Ct CS 12 3 [ N122 C Bt CS

12. 30 3

1/2AF014F N37 - 2 C 4.0 CK S.A. C 0 Ct CS 12 3 N122 C Bt CS

12. 30 3

[ '1/ZAF014G N37 2' C 4.0 CK S.A. C 0 Ct CS 12 3 t 4 d l I N122 C Bt CS

12. 30 3

[ 1/2AF014H N37 2-C 4.0 CK S.A. C 0 Ct C5-12 3 Y i N122 C Bt CS 12 '30 3 i 1/2AF017A N37 3 8 6.0 GA M.0. C 0 St OP I _i.'AF017B N37 3 8 . 6.0 GA M.O. C 0 St OP 1 L N122 It RR l: T N122 It RR t j 1/2Af t. ?9A N37 3 C 6.0 CK S.A. C 0 Ct CS 12 3 r i l N122 [ 1 1/2AF029B NS7 3 C 6.0 CK S.A. C 0 Ct CS 12 3 l 5 N122 [ t t i k 1 r 1 't I i I t r 4.3 VALVE T MLES - Page 3 of 43 ( t i 1 j' ) i 217(070891) r l ZD79G/51 L ?

INSERVICE TESTD4G PROGRAM PLAN 4

' CLASS 1, 2. 3. and AUGMENTED VALVES l BRAIDWOOD NUCLEAR POWER STATID ! ' UNITS 0. 1, & 2 i 1

. Revision 5 l'

~ .f VALVE VALVE VALVE VALVE ACT. NORMAL STROKE TE; ' TEST RELIEF TECH. I NUMBER .P&ID CLASS. CATEGORY SIZE TYPE TYPE POSITION DIRECT. NETA NODE REQUEST NOTES POS. REMARK $ s j fin.1 (VR1 iVAl .I i 1/2CC685 M-66-1A 2-A 4.0 GA M.O. O C St CS VR-8 1 0 It RR N139-1 Lt RR VR-1 f I 1/2CC9412A M-66-2 3 B' 12.0 GA M.O. .C 0 St OP 1 [ N139-2 It RR [ l' 1/2CC94128 N66-2 '3 8 12.0 GA M.0. C 0 St OP 1 l M-139-2 It RR i i 1/2CC9413A N66-1A '2 A 6.0 GA M.O. O C St CS M-8 1 W139-1 It RR l Lt RR VR-1 1/2CC9414 M-66-1A

2 A

6.0 GA M.O. O C St CS VR-8 1 i N139-1 It RR Lt RR VR-1 l 1/2CC9416 M-66-IA 2 A 6.0 GA E 9. O C St CS VR-8 1 l 5139-1 It RR Lt RR VR-1 ( I 1/2CC9437A N66-1A 2 B' 3.0 GL A.O. C C St/Ft 07 1,2 i l W139-1 It RR f 1/2CC94373 N66-1A 2 8 3.0 GL A.O. 0 l C St/Ft OP 1,2 i a N139-1 It RR J f j-1/2CC9438 566-1A 2 A 4.0 GA M.D. O C Lt RR VR-1 } N139-1 It RR j i St CS VR-8 _j ( 1ACC9463A N66-38 3 C 12.0 CK $.A. C 0 Ct/Bt CS 32 ~; ,d3 C Xt OP 4 e 1/2CC94638 M-66-3B 3 C 12.0 CK S.A. C 0 Ct/Bt CS 32 3 ) C Xt OP , l 3 l( 3 OCC9464 N66-38 3 C 12.0 CK S.A. C 0 Ct/8t CS r l h C Xt OP l 3 1 f i 1/2CC9473A N66-38 3 B 16.0 GA M.O. C 0 St OP L._. i It RR i 4.3 VALVE TABLIS. f.; e,of 43 [ l I j 4 4 i '217(070891) { ZD79G/52 1 1 m ~ -m

l.

[ L ,, $fi' lk i:I r + 1I

.i

!?i!if .),11II?jtl , i! .I 35 ;!: SKR' AP" E-R H .) CSA 1 3 3 3 3 3 3 EOV TP( 34 l fo S E 5 T 4 4 O 2 2 e N ga P SE T L FS B EE) 8 8 8 A IUR T LQV 8 1 8 1 8 E EE( l RR V R R R R R R L V V V V V V AV 3 TE 4 SD P R R R R R R R EO O R R R R R R R TM D t t t TO B B B SH t t / t / t / t ET S I t C t C t C TE L L L M ET KC OE 0 C 0 C 0 C 0 RR TI SD N LO AI MT RI C O C C OS NOP' .E 0 A. A. A. TP CY' AT M S S S EVE LP A K K K AY G C C C VT E ) 5 5 VE. 0 0 7 7 LZN AII 6 6 0 0 VS( 1 Y R EO VG C C C LE B A A A AT VA S C EV L A N S N VO .S A I A 3 2 2 2 L DT L F E A C T T MNS A E R MR GG E 8 A 1 A 1 A 1 O UW D 3 1 1 1 R A O" I 9 9 9 P P 6 6 3 6 3 6 3 d F 6 6 1 6 1 6 1 G nR N aA M M M M M M M I E2 T L S 3 C & E U B T ,N 3 6 8 4 ) 2 1 5 R 7 d 1 3 1 E '.O EE 4 4 5 5 9 C . n VB 9 9 9 9 83 C I 1 O0 o LM C C C C 0 5 V W i AU C C C C 7 / 0 G R S DS s. VN 2 2 2 2 ( 9 E S I Ti / / / / 7 7 S AAI v 1 1 1 1 1 D N L R N e I C E UR. 2Z 1 j 4 i4!,l-I i: ]ri,

i INSERVICE TESTING FROGRAM PLN4 CLASS 1, 2, 3, and AUGMENTED VALVES BRAIDWOCO NUCLEAR POWER STATION UNITS 0, 1, & 2 Revision 5 VALVE VALVE VALVE VALVE ACT. NORMAL STROKE TEST TEST RELIEF TECH. RUMBER P&ID CLASS CATEGORY SIZE TYPE TYPE POSITION DIRECT. METHOD MODE REQUEST NOTES POS. REMARKS (IN.1 i (VR) (VA1 1/2CS001A M-61-4 2 B 14.0 GA M.0. O C St OP 1 M-136-4 It RR 1/2CS001B M-61-4 2 B 14.0 GA M.0. O C St OP 1 It RR _M-136-4 1/2CS003A M-46-1A 2 C 10.0 CK S.A. C 0 Xt/Ct OP/RR VR 4 3 M-129-1A 1/2C50038 M-46-1A 2 C 10.0 CK S.A. C 0 Xt/Ct OP/RR VR-4 3 M-122 1A 1/2CS007A M-46-IC 2 A 10.0 GA M.0. C 0 Lt RR VR-I H-129-1C St GP 1 It RR 1/2CS0078 M-46-1C 2 A 10.0 GA M.0. C 0 Lt RR VR-! M-129-1C St OP 1 It RR 1/2C5008A K-46-1C 2 AC 10.0 CK S.A. C 0 Ct/St RR VR-4 3 M-129-1C C Lt RR VR-1 3 1/2CS006B K-46-1C 2 AC 10.0 CK S.A. C 0 ) Ct/Bt RR VR-4 3 H-129-1C C Lt RR VR-1 3 1/2C5009A M-61-4 2 8 16.0 GA M.0. C 0 St CP 1 M-136-4 It RR 1/2CS009B M-61-4 2 B 16.0 GA M.0. C 0 St OP 1 M-136-4 It RR 3 1/2CS011A M-46-;A 2 C 6.0 CK S.A. C 0 Ct OP M-129-1A 1/2CS0118 K-45-1A 2 C 6.0 CK S.A. C 0 Ct OP 3 K-129-1A 1/2C5019A U 46-1B 2 B 3.0 GA M.0. C 0 St OP 1 M-129-1B It RR 1/ZCS0198 M-46-1B 2 8 3.0 GA M.0. C 0 St OP 1 M-129-1B [t RR 1/2C5020A H-46-1B 2 C 3.0 CK S.A. C 0 Ct RR VR-2 3 M-129-1A 1/2CS020B M-46-18 2 C 3.0 CK S.A. C 0 Ct RR VR-2 3 M-129-1A 4.3 VALVE TABLES - Page 6 of 43 217(070891) ZD79G/St ww-~ < \\

INSERVICE TESTING PROGRAM PLAN CLASS 1. 2, 3. and AUGMENTED VALVES

BRAIDWOOD HUCLEAR F0WER STATION LMITS 0.1, & 2 Revision 5 VALVE VALVE VALVE VALVE ACT.

NORMAL STROKE TECT TEST RELIEF TECH. NUMBER P&ID CLASS CATEGORY SIZE TYPE TYPE POSITION DIRECT. METHOD MODE REQUEST NOTES' FOS. RENARKS (IN.1 (VR1 (VA) 1/2CV1128 M-64-4A 2 B 4.0 GA M.0. O C

. S t CS

4. 28 1

N138-48 It RR 1/2CV112C M-64-4A 2 B 4.0 GA M.0. O C St CS 4, 28 i W138 48 It RR 1/ZCV112D M-64-4B 2 8 8.0 GA M.0. C 0 St CS 2 1 f S138-4A It RR 1/2CV112E M-64-4B 2 B 8.0 GA M.0. C 0 St CS 2 1 N138 4A It RR 1/2CVS100 M-64-2 2 A 2.0 GL M.0. O C St RR VR-9 N138-2 It RR 1 Lt RR VR-1 1/2CV8104 N64-48 2 8 3.0 GL M.O. C 0 St CS 2 1 7 M-138-4A It .J 1/2CV8105 M-64-3B 2 B 3.0 GA M.0. O C St CS 4 1 f M-138-38 It RR 1/2CV8106 W64-3B B 3.0 GA M.D. O C St CS 4 1 m I N138-3B It RR 1/2CVS110 M-64-3A 2 8 2.0 GL M.O. O C St OP 1 W138-3 It RR i 1/2CV8111 M-64-3A 2 B 2.0 GL M.0. O C St OP 1 M-133-3A It RR 1/2CV8112 M-64-2 2 A 2.0 GL M.0. O C St RR VR-9 1 N138-2 It RR Lt RR VR-1 1/2CV8113 N64-2 2 AC .75 CK S.A. C C Lt/Bt RR VR-1, 9 3 M-138-2 0 Ct RR VR-9 24 3 1/2CV8114 N64-3A 2 B 2.0 GL S.0. O C St OP 1 M-138-3 It RR 20 1/2CV8116 M-64-3A 2 B 2.0 GL-5.0. O C St OP 1 [ M-138-3A It RR 20 [ 4.3 VALVE TABLES - Page 7 of 43 [ i i 217(070891) [ ZD79G/55 { I ~!

INSERVICE' TESTING PROGRAN PLAN 'Cl. ASS 1, 2. 3, and AUGMENTED VALVES-BRAIDWOOD NOCLEAR POWER STATIO UNITS 0..1. t.2 Revision 5 .5 VALVE VALVE VALVE VALVE ACT. NORMAL STROKE TEST TEST' , RELIEF TECH. f' NUMBER P&ID CLAC CATEGORY . SIZE. TYPE-TYPE POSITION DIRECT. METHOD MODE REQUEST NOTES P05. RENARKS fIK.) (VR) 'fVA)" 1/2CV815Z W64-5 2 A 3.0 GL. .A.O. O C St CS 4 1 ( 5138-5A It RR t Ft C5 4 2 i Lt RR VR-1 l 1/2CV8160 564-5 2 A 3.0 GL A.D. O C St CS 4 1 ( l-N138-5A It RR Ft CS 4 2 t RR VR-1 1/2CVS442 M-64-48 2 C 2.0 CK S.A. C 0 _. Ct CS 2, 29 1 N138-4A i 1/2CV8480A N64-3A 2 C 2.0 c. S.A. C 0 Ct OP 31 3 { M-138-3A C Bt OP 3 i 1/2CV8480B M-64-3A 2 C 2.0 CK S.A. C 0 Ct OP 31 3-W138-3A C Bt OP 3 1/2CV8481A M-64-3A 2 C 4.0 CK S.A. C 0 CtrXt RR/0P VR-15 3 N138-3A C Bt RR VR-15 3 1/2CV8481B S64-3A 2 C 4.0 CK S.A. C 0 Ct/Xt RR/OP VR-15 3. l H-138-3A C Jt RR VR-15 3 1/2CV8546 M-64-48 Z C 8.0 CK S.A. C 0 Ct RR VR-15

2. 26 3

N133-4A I 1/ZCV8804A N64-48 2 B 8.0 GA H.O. C 0 St CS 2 1 N138-4A 'It RR i i r 4.3 VALVE TABLES - Page 8 of 43 i 4 } I ~. 217(070891) l ZD79G/56 I l. r,~ v ~

INSERVICE TESTING PROGRAM PLN1 CLASS 1, 2, 3. and AUGMENTED VALVES BRAIDWOOO NUCLEAR POWER STATION UNIT S 0, 1, & 2 Revision 5 VALVE VALVE VALVE VALVE ACT. NOEMAL STROKE TEST TEST RELIEF TECH. NUMBER P&ID CLASS CATEGORY SIZE TYPE 'iYPE POSITIO'i DIRECT. f4ETH00 MCOE EEQUEST NOTES FOS. REM, ARKS ( VR ) (VA) (IN.) 1/2DG5182A M-54 4 NONE B 3.0 GA S.0. C 0 St OD VR 13 1/2DG5182B N152-20 NONE B 3.0 GA S.O. C 0 St OF VR-13 1/2DG5183A NSW NONE B 3.0 GA S.0. C 0 St OP VR-13 T/2DG51838 M-54-4 NONE B 3.0 GA S.0. C 0 St OP VR-13 1/ZDG5164A M-152-20 NONE C 3.0 CK S.A. C 0 Ct OP VR-13 3 1/20G51848 M-152-20 NONE C 3.0 CK S.A. C 0 Ct OP VR-13 3 1/2DG51SSA N152-20 NONE C 3.0 CK S. A7 C 0 Ct CP VR-13 3 1/2DG5185B M-152-20 NONE C 3.0 CK S.A. C 0 Ct OP VR-13 3 l l l l l 4.3 VALVE TABLES - Page 9 of 43 217(070891) 2D79G/57 L

S KRAM E 1. H. .) CSA3 33 3 3 3 3 3 TPE f EO 34 o 0 S 1 E T e O g N a P SEL T B FS A EE1 T IUR LQV E EE( V RR LAV 3 4 TE SD P P P P P P P P EO O O O O O QO O TM i D TO SH t t t t t t t t ET C BC B C BC B TEM ET KC OE 0 C 0 C 0 C 0 C RR TI SD N LO AI MT RI C C C C OS NOP .E TP A. A. A. A. CY AT S S S S EVE LP K K K K AY C C C C VT E )5 VE 5 5 5 LZN AII 1 1 1 1 VS( Y R EO VG LE C C C C AT VA S C EVLA N S N V O S A I A 3 3 3 3 L DT L P E A C T T M N S l A E R M R A B A A l O U W D 18 1 A 1 B G G E 1 1 1 1 R A O I 0 - 0 - 0 Q P P 0 30 30 3 0 3 d P 5 1 5 1 5 1 5 1 G n R N aA M MM HM M M M I E 2 T ,L S 3 C & E U, 5 R 3 3 3 3 T . N A B C D ) 1 2 1 9 O EE 0 0 0 0 E , O 0 io LM 0 0 0 0 0 5 8 8 I 1 O , n VB 0 0 0 0 C 7 / V W AU 0 0 0 0 E S I T i VN 2 2 2 2 0 G R S D S s ( 9 / / / / 7 7 S A A I v 1 1 1 1 1 D N L R N e I C C U R 2 Z l lllll I

h( I:[ I t h. l' i >;; i?! rFk ih!f iI il e e e e S v v v v K i i i i R s s s s .A s s s s .N a a a a E P P P P R H .) CSA EOV TP( 34 fo l S i E T O e N ga P SE T L FS B IUR 1 1 1 A EE) 1 T LQV R R R R EE( V V V V E RR V LAV 3 TE 4 SD R R R R EO R R R R TM D TO SH t t t t ET L L L L TE M l ET KC' OE' C C C C RR TI SD N LO AI MT RI C C C C OS NOP .E TP CY M M M M AT EVE LP P P P P AY VT E 1 VE 0 0 0 0 LZN AII 4 4 3 3 VS( Y' R EO VG LE A A A A AT VA S C EVL : A N S 4 V O S sA I A 2 2 2 2 L DT L P E A C T T M NS A E R P R GGE A A B C B C OU W D 1 1 1 1 1 1 R AO I P P 3 3 3 33 3 d P 6 6 6 6 6 6 G nR N M M M M M DaAE 2 T ,L S 3 C & ,U ) E N T 2 1 5 R 9 0 1 2 1 E D EE 0 1 1 9 , n VB 0 0 0 0 8 9 C ,O O0 o LM C C C C 0 5 I 1 i AU f f f f 7 / V W S A AI i VN 2 2 2 2 ( G R S D S s 0 E S I T / / / / 9 v 1 1 1 1 7 7 D N L R N e 1 I C B U R 2 Z

t' r IIr tI:!!IFLr! 1 !i !\\!:I Ii r k t i f t f SA FAM E R H .l CSA1 2 EOV TP( 34 fo .S' 2 E 1 TO e N ga P SE T L FS B EE) A I0R T L0V EE( E RR VLAV 3 TE 4 SD P R P EO O E O TM' D TO SH t t T ET S I F TE-M ET KC OE C RR TI SD N LO AI MT RI O OS NOP .E iP O. CY AT A EVE L LP G AY VT E ) VE. 0 ZN %II 4 VS( l Y R EO VG L LE AT VA S C EVLA N S 4 V O S N I A 2 . L DT L P E A C T T . M NS . A E R Ht GG J 1 O 1 W 1 D I 2 R A . P P 5 d P G nR M N a A I E 2 T ,L S 3 C & E ,UN ) T 2 1 5 R 0 1 9 E O EE 1 C ,O n VB 0 8 0 I 1 O 0, o LM P 0 6 AU f 7 / V W i R S D S s VN 2 0 G E S I T i / ( 9 S AA I v 1 7 7 N L R N e 1 D I C B UR 2 Z ll l 4 1 4

INSERVICE TESTING PROGRAM PLAN CLASS 1, 2. 3, and AUGMENTED VALVES BRAIDWOOD NUCLEAR POWER STATION UNITS 0, 1, & 2 Revision 5 ~ TECH. VALVE VALVE VALVE VALVE ACT. NORMAL STROKE TEST TEST RELIEF NUMBER P&ID CLASS CATEGORY SIZE TYPE TYPE POSITION DIRECT. METH00 MODE REQUEST NOTES P05 REMARKS (VR) (VA) _Ilft. ) 1/2FWOO9A M-36-1C 2 8 16.0 GA H.O. O C St/Xt CS/0P 3 1 It RR M-121-1B 1/EF WOOAB M-36-1A 2 B 16.0 GA H.O. O C St/Xt CS/0P 3 1 It RJ 1/2FWOO9C M-36-ID 2 B 16.0 GA H.O. O C St/Xt CS/0P 3 1 M-121-!D_ It RR M-121-1A_ 1/2FWOO90 M-36-18 2 B 16.0 GA H.O. O C St/Xt CS/0" 3 1 1 It RR 1/2FWO34A M-36-IC NONE B 2.0 GL A.0 0 C Ft RR 21 2 l M-121-1C_ M-1ElzlE_ 1/2F WO348 M-36-1A NONE B 2.0 GL A.O. O C Ft RR 21 2 1/2FWO34C M-36-10 NONE B 2.0 GL A.O. O C Ft RR 21 2 M-121:12_. M-121-1A 1/2FWO340 M-36-18 NONE B 2.0 GL A.O. O C Ft RR 21 2 i M-lll-lC_ 1/2FWO35A M-36-lC 2 8 3.0 GL A.O. O C St OP 1 It RR H-121-18 Ft OP 2 1 1/2FWO358 M-36-1A 2 B 3.0 GL A.O. O C St OP It RR M-121-1D Ft OP 2 1 ( 1/2FWO35C M-36-1D 2 8 3.0 GL A.O. O C St OP It RR M 121-1A Ft OP 2 1/2FWO35D M-36-1B 2 8 3.0 GL A.O. O C St OP 1 It RR M-121-1C Ft OP 2 1/2F WO39A M-36-1C 2 B 6.0 GA A.O. O C St OP 10 1 It RR M-121-1B Ft C1_ 10 2 4.3 VA.VE TABLES - Page 13 of 43 217(070891) ZD79G/61 (

INSERVICE TESTING PROGRAM PLAN CLASS 1, 2, 3, and AUGNENTED VALVES j BRAIDWOOD NUCLEAR POWER STATION j-UNITS 0, 1, & 2 . Revision 5 NUMBER P&ID CLASS CATEGORY SIZE-TYPE TYPE POSITION DIRECT. METHOD MODE REQUEST TECH. f VALVE VALVE . VALVE VALVE ACT. NORMAL STROKE TEST TEST RELIEF NOTES P05. REMARKS (IN.1 (VR) (VA) 1/2FWO398 M-36-1A-2 'B 6.0. GA A.O. O C St CS - 10 : 1. 5121-1D It RR Ft CS' 10 2 l 1/2Fu039C W36-10 2 B 6.0 GA A.O. 0 C St CS 10 .1 ^ W121-1A It RR Ft CS 10 2 l 1/2FWO390 M-36-1B 2 8 6.0 GA A.O. .O C St CS 10 1' M-121-1C It RR Ft CS 10 2' 1/2FWO43A M-36-1C 2 8 3.0 GL A.O. C C St OP 1 M-121-1B It RR-Ft OP 2 '1/2FWO43B M-36-1A 2 B 3.0 GL A.O. C 'C St OP 1 M-121-1D It RR. 1 Ft OP 2 1/2FWO43C M-36-1D 2 B 3.0 GL A.O. C C St OP 1 N121-1A It RR Ft OP 2 1/2FWO43D M-36-1B 2-B 3.0 GL A.O. C C St OP 1-5121-IC-It RR Ft OP ~2 s 1/2FW510 M-36-1C NONE B 16.0 AN A.O. O C Ft RR 16 2 [ I M-121-1 { 1/2FW510A M-36-1C NONE B 4.0 GA A.0 C C Ft RR 17 2' M-121-1 [ 1/2FW520 M-36-1A NONE B 16.0 AN A.O. O C Ft RR 16 2 M-121-1 f 1/2FWS20A %36-1A P:0NE B 4.0 GA A.O. C C Ft RR 17 2 L M-121-1 ' j. 1/2FW530 M-36-1D NONE B 16.0 AN A.O. O C Ft RR 16 2 i M-121-1A k 4.3 VALVE TABLES - Page 14 of 43 t 7 -{' 217(070891) ZD79G/62 I i

1l l l l! a J o S KR ' -A' M ER' M .) CSA2 2 2 EOV TP( 34 I fo S 5 E 7 6 7 1 T 1 1 1 O e N ga P S E T L FS B EE) A IUR T LQV EE( E RR V LAV 3 TE 4 SD R R R EO R R R TM D TO w SH t t t ET F F F TE w M ET KC OE C C C RR TI ?D .N' LO AI MT RI C O C OS NOP .E TP 0 O. D. CY AT A A A E' VE LP A N A AY G A G VT E ) VE .0 0 0 LZN ail 4 6 4 VSf 1 - Y R E'O~ VG LE B B B AT VA S .C E V LA t S E E E N V O S N N N A I A O O O L DT L N N N P E A - C T T NNS A E R M R A C C GGE 0 1 B 1 8 1 OU W D 1 1 1 R A O I 1 1 1 P P 6 2 6 2 6 2 G n R. P 3 1 3 13 1 d N aA M M M M H M E 2 I T L S 3 C & E U A A ) T ,N 2 1 5 R C 0 0 1 E O EE 3 4 4 9 C ,O , n VB 5 5 5 8 3 O 0 o LM W W W 0 6 I 1 V W AU F F F 7 / i E S I T i - VN 2 2 2 0G R S D S s / / / ( 9 S A A I v 1 1 1 7 7 N LR N e 1 D I C B UR - 2 Z ll1 l i l j ,I 1 4i

i,

i4;li.

y i lL [! \\i t i Y S KRAM E R H .) CSA 1 2 1 2 3 EOV TP( 34 f.o S 6 E 1 T O e .N ga P SE T 0 L FS 0 0 0 0 1 B EE) 1 1 1 1 1 1 A IUR T LQV R R R R R R 1 EE( V V V V V V E RR k V V LAV 3 TE 4 SD R R R R R R R R R EO R R R R R R R R R TM D t TO B SH t t t t t t t t / ET L S f I L S f I t TE L M ET KC OE C C C RR TI SD N LO AI MT RI 0 O C OS NOP .E A. 0 O. TP CY AT A A S E - VE LP L L K AY G G C VT E ) 5 VE .0 0 7 LZN AII3 3 0 VS( Y R EO VG C LE A A A AT VA S C EV LA N S N V O S A I A 2 2 2 L DT L P E A C T T MNS A E R M R G GE 0 5 0 5 0 5 O U W D 1 1 R A O I 1 1 1 1 P P 5 5 5 5 5 5 d P 5 5 5 5 5 5 G nR N aA M M M M M M I E 2 T ,L S 3 C & .U E N T ) 2 1 5 R 5 6 1 1 E ,D , n VB 0 0 0 8 4 EE 6 6 9 9 O C O0 o LM A A A 0 6 I I V W AU 1 I I 7 / i R S D S s VN 2 2 2 0 G E S I T i / / / 9 ( S A A I v 1 1 1 7 i N L R N e D 1 I C B U R 2Z m m m

INSERVICE TESTING FROGRAM PL/J4 CLASS 1, 2, 3, and AUGMENTED VALVES BRAIDWOOD NUCLEAR PCMER STATION UNITS 0, 1, & 2 Revision 5 ACT. NORMAL STROKE 7tST TEST RELIEF TECH. TYPE l POSITION VALVE VALVE VALVE VALVE DIRECT. METH00 MODE REQUEST NOTES P05 REMARKS NUMBER P&ID CLASS CATEGORY SIZE TYPE (VR1 (VA) (IN11 1/2MS001A M-35-2 2 8 30.25 GA H.O. O C St/Xt CS/0P 1 1 It RR M-120-ZA 1/2MS0018 M-35-1 2 8 32.75 GA H.O. O C St/Xt CS/0P 1 1 It RR _M-120-1 1/2MS001C M-35-2 2 8 32.75 GA H.O. O C St/Xt CS/0P 1 1 It RR M-120-2B 1/2M5001D M-35-1 2 ___. 8 30.25 GA H.O. O C St/Xt CS/0P 1 1 It RR M-120-1 1/2MS013A M-35-2 2 C 6.0 x SV S.A C 0 Rt RR M-12Q:Z.A 10.0 1/2MS013B M-35-1 2 C 6.0 x SV 5.A. C 0 Rt RR l Mrj ZQ:1 10.0 1/ZMS013C M-35-2 2 C 6.0 x SV 5.A. C 0 Rt RR (_ _MM ZD-2B 10,0 1/2MS0130 M-35-1 2 C 6.0 x SV 5.A. C 0 Rt RR I M-12Q 1 _10.0 1/2M5014A M-35-2 2 C 6.0 x SV 5.A C 0 Rt RR M 120-2A 10.0 1/2MS0148 M-35-1 2 C 6.0 x SV S.A. C 0 Rt RR _f-12Q-1 10.0 1/2MS014C M-35-2 2 C 6.0 x SV 5.A. C 0 Rt RR M-120-2B 10.0 l 1/2MS0140 M-35-1 2 C 6.0 x SV S.A. C 0 Rt RR M-120-1 10.0 1/ZM5015A M-35-2 2 C 6.0 x SV 5.A. C 0 Rt PR M-12Q ZA 10.0 1/2M5015B M-35-1 2 C 6.0 x SV 5.A. C 0 Rt RR 1/2M5015C ._M-120-1 10.0 M-35-2 2 C 6.0 x SV 5.A. C 0 Rt RR M-12Q-2B ljl. 0 1/2M50150 M-35-1_ 2 C 6.0 x SV 5.A. 0 0 Rt RR M-120-1 10.0 4.3 VALVE TABLES - Page 17 of 43 217(070891) 2D79G/65

f ilfllI Jlll lll(l'j jlllll!jl l jIl S KRAM E R M.i C5A 1 2 1 2 i 2 1 2 1 2 E0V 3 TP( 4 \\ f o S 8 1 E T O e N g a P S E T L FS B EE1 2 1 2 2 A 2 1 1 1 T IUR LQV EEi R R R R E RR V V V V VLAV 3 4 4 Tk S R R R R R R R R P R P P R PP R P P R P P R P 0_ O R O E0 P R R R R R R R O R O O R OO R O O R TM D TO SH t t t t t t t t t t t t t t t t t t t t t t t ET R 4 R R R R R R S I F S I F S I F S I F S I F TE M ET KC OE 0 0 0 0 0 0 0 0 C C C C C RR TI SD N LO AI MT RI 0 0 0 0 0 0 0 0 _C C C C C OS NOP .E TP A. A. A. A. A. A. A. O. 0 0 0 D. A. CY AT S 5 S 5 5 S S S H M ff M A EVE V V V V LP V V V V V V V V R R R R A AY S S S S S S S S O O O O G VT P P P P E ) x x x x x = x x x x x x VE . 0 0 b 0 0 0 0 0 0 0 0 0

0. 0 0,0 0

LZN AII 0. 0 0. 0. 0 0. Q. 0 0 0 0 0 0 0, 4 V S L_6 1_6 1_6 1 6 6 1 b 1 6 1 6 6 6 6 6 6 6 6 1 Y R EO VG LE C C C C C C C C B B B B B AT VA S C E VLA N S N V O S A I A 2 2 2 2 2 2 2 2 2 2 2 2 2 L D T L P E A C T T "A N S E R MR A 8 A B A B A CG E 2 2 l 2 1 Z 1 2 1 2 1 2 1 2 1 2 O U W D 2 1 2 1 2 1 - 2 1 2 R A 0 I O - 0-0 - 0 0 - Q - Q-0 0 0 0 0 P F 5 Z5 25 25 25 25 25 E5 2 5 2 5 2 5 2 5 2 d P 3 1 3 1 3 13 1 3 1 3 1 3 1 3 1 3 1 G nR 1 3 1 3 1_3 N M M M iM W M S M W M 5 M S N aA M M M M M M M M M t ,E2 I L TS 3 C & T . U, R 6 1 6 1 0 0 0 0 0 0 0 0 1 8 6 E N A 8 C 0 A B C 0 A S C 0 A ) 2 E D 1 5 6 1 6 7 7 7 7 8 1 1 1 0 9 C , O, n VB 0 0 0 0 1 1 1 1 1 8 8 8 1 1 EE 1 I 1 O0 o LM S S S 5 S S S S S S S 5 S 0 6 V W AU M M H M M M N M M M M M M 7 / R S O S is VN 2 2 2 Z Z 2 2 2 2 2 Z 2 2 0 G E S I T i / / / / / 9 S A A I v 1 1 1 1 1 / / / / / / / / ( 7 1 1 1 1 1 1 1 1 7 N L R N e 1 D I C B U R 2 Z l lllll l\\ll Jl llll llIlil l 11 j. l l

l Il 4 I I i ) I i' l SK RAM E R H .) 2 CSA 1 2 1 2 1 EOV TP( 34 fo S 9 E 1 TO e N ga P S E T L FS B EE) A IUR T LQV EE( E RR VLAV 3 TE 4 SD P R P P R P P R P EO O R O O R O O R O TM D TO SH t t t t t t t t t ET S I F S I F S I F TE'M ET KC OE C C C RR TI SD N LO AI MT RI C C C OS NOP' .E TP O. O. O. CY AT A A A E' VE LP A A A VT ' G G G AY E ) VE. 0 0 0 LZN AII 4 4 4 VS( Y R EO VG LE 8 8 8 AT VA S C EV LAVO S N -S A I A 2 2 2 L DT L P E A -C T T M NS AE R MR B G GE 1 2 1 O UW D 1 2 1 R A O I 0 0 0 P P 5 2 5 2 5 2 d P 3 1 3 1 3 1 N M H M % M G nR N aA,E 2 I T L S 3 C & E U T ,N B C D ) 2 1 5 R 1 1 1 1 E D EE 0 0 0 9 C ,O , o LM 5 5 S 0 6 n VD 1 1 1 9 7 I 1 O 0 V W i AU M M M 7 / R S D S s VN 2 2 2 0 G S A A I v 1/ / / E S I T i ( 9 1 1 7 7 N L S N e 1 D I CB UR 2 Z 1 ji 1l

INSERVICE TESTING PROGRAM PLAN' CLASS 1. 2, 3 and AUGMENTED VALVES - BRAIDWCOD NUCLEAR F0WER STATIC:4 . UNITS 0, 1, & 2 Revision 5 VALVE VALVE VALVE VALVE ACT. NORMAL STROKE TEST TEST RELIEF TECH. NUMBER P&ID CLASS. CATEGORY SIZE TYPE TYPE POSITION DIRECT. METHOD MODE REQUEST NOTES' POS. REMARKS ( IN_1 (VR) (VA) 1/20G057A N47-2 2 A 3.0 BTF M.0. C C .Lt RR VR-1 W150-2 St OP 1 It RR 1/20G079 N47-2 2 A 3.0 BTF M.0. C C Lt RR VR-1 M-150-2 St OP 1 It RR 1/20G080 M-47-2 2 A 3.0 BTF M.0. C C Lt. RR VR-1 M-150-2 St OP 1 It RR 1/20G081 M-47-2 2 A 3.0 BTF M.0. ~C C Lt RR VR-1 %15t-2 St OP 1 4 It RR 1/20G082 547-2 2 A 3.0 .BTF M.0. C C Lt RR VR-1 M-150-2 St OP 1 It RR 1/20G083 N 47-2. 2 A 3.0 BTF M.0. C C Lt RR VR-1 M-150-2 St OP 1 It RR 1/20G084 M-47-2 2 A 3.0 BTF M.O. C C Lt RR VR-1 N150-2 St OP 1 It RR 1/20G085 N47 'd 2 A 3.0 BTF M.0. C C Lt RR VR-1 M-150-2 St OP 1 It RR 4.3 VALVE TABLES - Page 20 of 43 217(070891) ZD79G/68 L

~ INSERVICE TESTING PROGRAM PL#4-CLASS,1, 2, 3,~and AUGMENTED VALVES t ~ SRAIDWOOO NUCLEAR POWER STATION UNITS 0, 1,'& 2 Revision S VALVE uALVE VALVE VALVE ACT. ~ POSITION DIRECT. METHOD MODE REQUEST NOTES 'POS. REMARKS NORMAL-STROKE TEST TEST RELIEF TECH. NUNBER P&ID CLASS CATEGORY SIZE TYPE TYPE (IN.1 (VR1' (VA1 1/2PR001A-M-78-10 2 A 1.0 GL A.O. O C Lt RR VR-1 ? M-151-1 ft OP 2 St OP 1 '- I It RR 1/2PR001B M-78-10 2 A '1.0 .GL A.O. O C Lt RR VR-1 M-151-1 Ft OP 2 St OP 1 It .RR I 1/2PR002E N78-6 2' A 2.0 GL. H C C Lt RR VR-1 Passive I 1/2PR002F N78-6 2 A 2.0 GL M C C Lt RR VR-1 Passive 1/2PR002G M-78-6 2 AC 2.0 CK S.A. C C Lt/Bt RR VR-1, 23 3 i h 1/2PR002H M-78-6 2 AC 2.0 CK S.A. C C Lt/Bt RR VR-1, 23 3 t l 1/2PR032 5 78-10 2 AC 1.0 CK S.A C C Lt/Bt RR VR-1, 24 3 1 M-151-1 i 1/2PR033A %78-6 2 A 2.0 GL M C C Lt RR VR-1 Passive i 1/2PR033B M-78.-6 2 A 2.0 GL M C C Lt RR VR-1 Passive i 1/2PR033C N78-6 2 A 2.0 GL M C .C Lt RR VR-1 Passive 1/2PR0320 578-6 2 A 2.0 SL M C C Lt RR VR-1 Passive I I 1/ZPR066 578-10 2 A 1.0 GL A.0 0 C Lt RR VR-1 i i S1SI-1 -Ft OP 2 [ It RR St OP.. . _. _aaott) - rage ta or_ sa e 9.a vatvt ._ 1 t i 217(070891) ZD79G/69 {

INSERVICE TESTING PROGRAN PLAN CLASS 1, 2, 3, and AUGMENTED VALVES BRAIDWOOD NUCLEAR P0wER STATION UNITS 0, 1, & 2 Revision 5 VALVE VALVE VALVE VALVE ACT. NORMAL STROKE TEST TEST RELIEF TECH. NUMBER Pf.!D CLASS CATEGORY SIZE T'/PE TYPE POSITION DIRECT. METHOD MODE RE00EST NOTE $ P05. REMARKS i (yR) (VA) IIN.) Lt RR VR-1 1/2PS228A N-68-7 2 A 0.50 GA S.0. O C St OP VR-12 1 ft OP 2 M-140-6 It RR 20 Lt RR VR-1 1/2PS2288 H-68-7 2 A 0.50 GA S.O. O C St OP VR-12 1 ft OP 2 M-140-6 It RR 20 Lt RR VR 1 1/2PS229A M-68-7 2 A 0.50 GA S.0. O C St OP VR-12 1 Ft OP 2 l M-140-It RR 20 Lt RR VR-1 1/2PS2298 M-68-7 2 A 0.50 GA S.0. O C St OP VR-12 1 Ft OP 2 M-140-6 It RP 20 Lt RR VR-1 1/2PS230A M-68-7 2 A 0.50 GA S.O. C C St OP VR-12 1 ft OP 2 M-140-6 It RR 2Q Lt RR VR-1 1/2PS2309 S68-7 2 A 0.50 GA S.O. C C St OP VR-12 1 ft OP 2 5140-6 It RR 20 1/2PS231A M-68-7 2 A 0.75 CK S.A. C C Lt/Bt RR VR-1, 25 3 0 Ct OP 22 3 J-140-6 1/2PS231B M-68-7 2 A 0.75 CK S.A. C C Lt/Bt RR VR-1. 25 3 0 Ct OP 22 3 M-140-6 1 St OP 1/2PS9354A N68-1B 2 A 0.375 GL A.O. C C Lt RR VR-1 It RR M-140-1 2 Ft OP. _ _VALVL iAOLL) - VagE 4.4 OT e 4.J 217(070891) ZD79G/70 i c g

INSERVICE TESTING PROGRAN PLAN CLASS 1

2. 3. and AUC+1NTED VALVES -

BRAIDWOOD NUCLEAR POWER STATION UNITS 0. 1, &'2 Revision 5 VALVE VALVE VALVE VALVE ACT. NORMAL STROKE TEST TEST RELIEF TECH. NUMBER P&ID CLASS. ' CATEGORY SIZE TYPE. TYPE POSITION DIRECT. METHOD MODE RE7;EST NOTES P05. REMARKS. FIN.) (VR1 (VA) 1/2PS93548 St OP 1. S68-1d 2 A 0.375 ' GL A.O. C C Lt ER VW-1 W140-1 It RR Ft OP 2 1/2PS9355A St OP 1 568-1B 2 A 0.375 GL A.O. C C Lt RR VR-1 S140-1 It RR Ft OP 2 1/2PS93558 St OP 1 N68-1B 2 A 0.375 GL A.O. C C Lt RR VR-1 N140-1 It RR Ft OD 2 1/2PS9356A St OP 1 N68-1A 2 A 0.375 GL A.O. C C Lt RR VF-1 N14C-1 It RR Ft OP 2 1/2PS9356B St OP 1 468-1A 2 A 0.375 GL A.O. C C Lt RR VR-1 5140-1 It RR Ft OP 2 1/2PS9357A St OP 1 N68-18 2 A 0.375 GL A.O. C C Lt RR VR-1 N140-1 It RR Ft OP 2 1/2PS9357B St OP 1 N68-1B 2 A 0.375 GL A.O. C C Lt lRR VR-1 N140-1 It RR-l 1 Ft OP 2 4.3 VALVE TABLES - Page 23 of 43 217(070891) ZD79G/71

,i i - I t(+!l i I l; i I; ,1 SKR' AM E R H .1 2 1 2 CSA 2 1 2 1 1 EOV TP( 34 fo S 4 E 7 7 0 7 7 0 7 7 07 7 0 2 T 2 2 2 2 O e N ga P SE T L FS 2 2 2 2 BA EE1 1 IUR 1 1 1 T. LQVR R R R EEf V V V V E RR VLAV 3 TE 4 SD S S R S S RS S R S S R EO C C R C C RC C R C C R TM D TO SH t t t t t t t t t t t S' F I ET S F I S F I S F I TEM ET KC OE 0 C 0 C 0 C 0 C RR TI SD - N LO AI MT RI C C C C OS NOP' .E TP 0 0 0 0 CY' AT S 5 5 5 EVE LP L L L L AY G G G G VT E 1 VE 0 0 0 0 LZN AII1 1 1 1 VS( Y R EO VG LE B B B B AT VA S C EV LA N S N VO S A I A 1 i 1 1 L DT L P E A C T T N NS AE R 1 R B B B B G GE 8 1 B 1 8 1 B 1 1 O U W D 1 1 1 R A O I 5 5 5 5 P P 0 3 0 3 0 3 0 3 d P 6 1 6 1 6 1 6 1 G nR N aA M M M M M M M M I E 2 T ,L S 3 C & E U A 8 C 0 ) T , N 2 1 5 R 4 4 4 4 1 E D EE 1 1 1 1 9 O, n VB 0 0 0 0 8 2 C , O 0 o LM C C C C 0 7 I 1 V W AU R R R R 7 / i R S D S s VN 2 Z 2 2 0 G E S I T i _/ 9 N L R N e _1 1/ / / ( S A A I v 1 1 7 7 D 1 C B UR 2 Z I f !r i t I.

.f e (((l I,[ l SK RAM E R H .) Z 1 2 1 2 1 2 1 2 1 2 CSA 1 2 1 EOV TP( u fo S a E' i TO e N gar 5 u T FS o EE) 1 1 1 1 1 1 1 r, IUR i LQV R R R R R R R EE( V V V V V V V L RR v L s. v s. TE 4 S0 P R R P P R P R P R P R P R R P P R P R P R P R P R P R E0 O R R O O R OR O R OR OR R O OR OR O R O R OR O R TN D TO SH t t t t t t t t t t t t t t t t t t t t 't t t t t t t t ET S L I F S I F L S I F L S L I F S I F L S I F L S I F L TE'M ET KC OE C C C C C C C RR TI SD N LO AI 1T J I C O O C O O O WS POP ,E TP O. O. O. O. O. O. O. CY' AT ' A A A A A A A EVE LP 0 D D D D D D AY VT E .) 5 5 VE. 0 0 7 7 0 0 0 LZN AII 3 1 0 0 1 1 3 VSI Y R EO VG LE A A A A A A A AT VA , S C .EV L A N S N V O - S A I A 2 2 2 2 2 2 2 L DT L P E A .C T T M N S A E R MR G G 1 1 1 1 1 1 1 OUW l 1 1 D 1 1 1 1 1 1 R A O I 1 1 1 1 1 P P. 0 4 0 4 0 4 G 4 0 4 0 4 0 4 d P 7 1 7 1 7 1 7 1 7 1 7 1 7 1 NW M N NM MW 5M 5H NM G nR N aA I E 2 T ,L S 3 C& E U A B A 8 3 7 9 9 0 0 0 ) T ,N 2 1 5 R 0 5 5 5 6 6 7 1 E D EE 0 1 1 1 1 1 1 9 C ,O , n VB 1 9 9 9 9 9 9 8 3 I 1 O0 o LM E E E E E E E 0 7 V W i AU R R R R R R R 7 / R S D S s VN 2 2 2 2 2 2 2 0 G E S I T i / / / / / / / ( 9 S AAI v 1 1 1 1 1 1 1 7 7 D N L R N e 1 I C B UR 2 Z

L 3j l i

I.

!:[> [ !i ~ SKRAM E-R - t'.) O5A 1 2 1 2 E0V TP( 34 fo S 6 E 2 TO e N' ga P SE T L FS B EE) 1 1 A IUR T e LQVR R EE( V V E RR VLAV 3 TE 4 SD R P R P R P R P EO" R O TM' ' R O R O R O 0 T0 SH t t t t t t t t ET' L 5 I F L S I F TE M ET KC OE C C RR TI SD N LO AI MT RI' O O OS NOP E' TP O. O. CY AT A A EVE LP P P AY VT E ) VE 0 0 LZN AII 2 2 /S( Y R EO VG LE A A AT VA S C E' V' LA N S A I - S N V O A 2 2 L DT L P E A C T T MNS A E R H R G G E B A O U W D 6 6 R A O I 8 8 P P - P 4 4 d G nR N aA M M ,E 2 I T L S 3 C& E U T ,N ) 2 1 5 R 6 7 1 E D EE 2 2 9 n VB 0 0 S4 C ,O , o LM f F 0 7 .O 0 I 1 W i AU R R 7 / VR 5 D S s VN 2 2 0 G E 5 I T i / / ( 9 S A A I v 1 1 7 7 N L R N e 1 D I C B UR 2Z i 4

~ INSERVICE TESTING PROGRAM PLAN CLASS 1, 2, 3, and AUGMENTED VALVES BRAIDWOOO NUCLEAR POWER STATION - UNITS 0, 1, & 2 Revision 5 VALVE VALVE VALVE VALVE ACT. NORMAL. STROKE TEST TEST RELIEF TECH. NUMBER P&ID Ci. ASS CATEGORY SIZE TYPE TYPE POSITION DIRECT. METHOD MODE REQUEST NOTES POS. REMARKS (IN.1 ( VR1 (VA) 1/2RH3701A M-62. 1 A 12.0 GA M.0. C 0 St-CS 5 1 S 137 It RR Lt RR 6 1/2RH8701B M-62 1 A 12.0 GA M.0. C 0 St .CS 5-1 f M-137 It RR 4 Lt RR 6 1/2RH8702A M-62 1 A 12.0 GA M.D. C 0 St CS 5 1 1 M-137 It RR -[ Lt RR 6 ~ 1/2RH8702B M-62 1 A 12.0 GA M.O. C 0 St CS 5 i M-137 It RR l Lt RR 6 i 1/2RH8705A M-62 2 AC 0.75 CK S.A. C C Lt/8t RR VR-15 6 3 'l M-137 0 0 Ct RR VR-15 24.35 ? 4 1/2RH8705B M-62 2 AC 0.75 CK S.A. C C Lt/Bt RR VR-15 6 J s M-137 0 0 Ct RR VR-15 24.35 3 l 1/2RH8708A M-62 2 C 3.0 x RV 5.A C 0 Rt RR M-137 4.0 t 1/2RH87086 M-62 2 C 3.0 x RV S.A. C 0 Rt RR M-137 4.0 ? 1/2RH8730A M-62 2 C 8.0 CK S.A. C 0 Ct/Xt CS/0P 8 3 l M-137 C Bt CS 3 i 1/2RH87308 M-62 2 C 8.0 CK S.A. C 0 Ct/Xt CS/0P 8 3 ( f M-137 C Bt CS 3 4.3 VALVE TABLES - Page 27 of 43- [ t i 217(070891) -{ ZD79G/75 t v w

1 INSERVICE TESTING PROGRAM PLN4 : , : CLASS'.1, 2, 3, and AUGMENTED VALVES, BRAIDWOOD NUCLEAR POWER STATION UNITS 0, 1, & 2 Revision 5 VALVE VALVE VALVE VALVE ACT. NORMAL STROKE TEST TEST RELIEF TECH. i NUMBER P&lD CLASS CATEGORY SIZE TYPE TYPE POSITION DIRECT. METHOD MODE REQUEST ' NOTES POS. REMARKS : (IN 1 (VR) (VA) 1/2RY455A N60-5 1 B 3.0 PORV_ A.O. C 0 St CS 36 1 'g N135-5 It RR Ft CS 2 i 1/2RY456 M-60-5 1 B 3.0 PORV A.O. C 0 St CS 36 1 e M-135-5 It RR Ft CS 2 1/2RY8000A N60-5 1 B 3.0 GA M.0. O C St OP 1 M-135-5 It RR '[ 1/2RYB0008 M-60-5 1 8 3.0 ' GA M.0. O C St OP 1 N135-5 It RR 1/2RY8010A M-60-5 1 C 6.0 SV S.A C 0 Rt RR l i N135-5 It RR 1/2HY80108 M-60-5 1 C 6.0 SV S.A. C 0 .Rt RR + M-135-5 It RR 'l 1/2RY8010C M-60-5 i C 6.0 SV S.A. C 0 Rt RR i M-135-5 It RR 6 1/2RY3025 M-60-6 St OP 1 N135-6 2 A 0.375 GL A.O. C C Lt RR VR-1 ~ It RR Ft OP 2 1/2RY8026 N60-6 2 A 0.375 GL A.O. O C Lt RR VR-1 M-135-6 St OP 1 I It RR Ft OP 2 1/2RY8028 M-60-6 2 A 3.0 D A.O. O C Lt RR VR-1 M-135-6 St OP 1 i It RR Ft OP I 1/2RY8033 M-60-6 2 A 0.75 D A.O. O C Lt RR VR-1 N135-6 St OP VR-12 1 It' RR Ft OP 2 l 4.3 VALVE TABLES - Page 28 of 43 I 217(070891) ZD79G/76 ?

i SKRAM E R H .) CSA 3 3 3 3 EOV TP( 34 fo S 9 E 2 TO e N ga P 9 S E T 6 6 L FS 2 2 B EE) A I0R T L0V 1 1 EE( E RR R R V V V LAV 3 TE 4 SD R R EO R R TM D TO-t t SH B 8 ET / / TE' t t M' L L ET KC OE C C RR TI SD N LO AI MT RI C C OS NOP .E A. A. TP CY AT S S E-VE LP K K AY C C VT VE. 5 E ) 0 7 LZN AII 3 0 VS( Y R EO VG C C LE A A AT VA S' C E V L N V O - S A N S A I A 2 2 L DT L P E A C t T T N S

1. E R M R GGE 6

6 O U W D 6 - 6 R A O I 5 5 P P 0 3 0 3 d P 6 1 6 1 G nR N aA M M M M I E 2 T , L S 3 C & E U T , N, 5 R 4 4 6 7 ) 2 1 1 E D EE 0 0 9 I 1 O0, n VB B 8 8 7 C C o LM Y Y 0 7 AU R R 7 / V W i R S D S s VH 2 2 0 G E S I T i / / ( 9 S A A I v 1 1 7 7 NLR N e 1 D I CB UR 2 Z 4 i t-j

i' 4

[ SK R AM E -- R H'.) CSA 1 2 1 2 EOV TPf 34 fo S-0 E 3 TO e N ga P SE T L FS B EE) 1 1 A IUR T LQV R R EE( V V E RR VLAV 3 TE 4 SD R P R P R P R P EO R O R O R O R O TM D TO SH t t t t t t t t ET L S I F L S I F TE M ET KC OE C C RR TI SD ~ N LO AI MT RI 0 O OS NOP E 0 O. TP CY AT A A E VE LP A A AY G G VT E 1_ VE 5 5 LZN AII 1 1 VS( Y R EO VG LE A A AT VA S C EV ,. L S A O N V S A I A 2 2 L DT L P E A C T T MNS A E R M R G G E G U W D 2 2 R A O I P P 4 4 d P 5 5 G nR N aA H H ,E 2 I L TS 3 C & E ,U , 5 R 2 3 1 N ) T 2 1 E D EE 3 3 9 C ,O , n VB 0 0 8 8 I 1 O0 o LM A A 0 7 V W AU S S 7 / i R S DS s VN 2 2 0 G E S I T i / / ( 9 S AA I v 1 1 7 7 N L R N e 1 D I C B UR 2 Z

' INSERVICE TESTING FROGRAM PLN4 C1. ASS 1. 2. 3 and AUGMENTED VALVES BRAIDWOCD NUCLEAR POWER STATION -UNITS 0,'1. & 2 Revision 5 /ALVE VALVE. VALVE VALVE ACT. NORMAL-STROKE' TEST-TEST RELIEF-- ' NLtBER P&ID CLASS ' CATEGORY-SIZE' TYPE TYPE' POSITION DIRECT. METHOD MODE REQUEST TECH.. i NOTES POS. REMARKS (IN.) (VR) (VA) 1/2SD002A M-48-5A/B 2 A - 2.0 GL A.0 0 C .Lt RR - 34 St OP 1 It RR Ft OP 2 1/2500028 M-48-5A/B 2 A 2.0 GL A.O. O C Lt RR 34' St OP 1 It RR Ft OP 2 1/2SD002C M 48-5A/B 2 A 2.0 GL A.0 0 C Lt RR 34-St OP 1. It RR Ft OP 2 1/250002D M-48-5A/B 2 A 2.0 GL A.O. O C Lt RR 34 St OP 1 It 'RR Ft OP 2 1/2SD002E M-48-5A/B 2 A 2.0 GL A.0 0 C Lt RR 34 St OP 1 It RR Ft OP 2' 1/25D002F M-48-5A/B 2 A 2.0 GL A.O. O C Lt RR 34-St OP 1 It RR Ft OP 2 1/2SD002G M~t8-5A/B 2 A 2.0 GL A.0 0 C. Lt RR 34 St OP 1 It RR Ft OP 2 1/2SD00ZM M-48-5A/B 2-A 2.0 GL A.O. O C Lt RR 34 St OP 1 It RR Ft OP. _ ar,otta - rage an or sa -

• .a vatvt 2

217(070891) 2D79C/79 .~<

l. f[t m S' KRA M ER' H .) CSA 1 21 21 21 2 EOV TP( 34 fo S 2 E 3 T 4 4 4 4 O 3 3 3 3 e N ga P SE T L F ** B T L) A IUR T LQV EE( E RR' V L AV 3 TE 4 SD P R R P P R R P P R R P P R R P EO O R R O O R R O O R R O O R R O TM D TO SH t t t t t t t t t t t t t t t t ET S L I F S L I F S L I F S L I F TE M ET KC OE C C C C RR TI SD . N LO AI MT RI 0 O 0 O OS NO'P .E 0 O. 0 O. TP CY' AT A A A A = EVE LP L L L L AY G G G G VT E )5 5 5 5 .7 7 7 7 VE LZN3 3 3 3 AII VS(0 0 0 0 Y R EO VG LE A A A A AT VA S C EV LA N S N V O S A I A 2 Z 2 2 L DT L P E A C T T MN S A E B B B B R M R' / / / / GGE A A A A O U W' D 5 5 5 5 R A O I P P 8 8 8 8 c P 4 4 4 4 G nR N aA M N M M .E 2 I L TS 3 C & E U A 8 C D ) T ,N 2 1 5 R 5 5 5 5 1 E O EE 0 0 0 0 9 a1,O , n VB 0 0 0 0 5 0 O 0 o LM D 0 D 0 0 8 W i AU S 5 S 5 7 / - S D S s VN 2 2 2 2 0 G

S I T i

/ / / / ( 79 AA I v 1 1 1 1 7 . L R N e 1 D 1 C B U R 2 Z <t

[t f l 5K W LR H .) C5A 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 E0V TP( 34 fo S 3 E 3 T 3 3 4 4 4 4 4 4 O 1 1 1 1 1 1 1 1 e N ca P SE T L FS B EE) 6 6 A IUR 1 1 T LQV EE( R R E RR V V VLAV 3 TE 4 SD 5 R 5 R 5 R 5 R P R 5 R P R P R 5 R 5 R R RR R P R P R 5 RP R EO C R C RC R C RO R C R O R O R C R C R R R R RO R O RC R O R_ TN D TO SH t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t ET 5 I S I S IS I S I S I S IS I S IS I S IS I 5 IS I S IS I TEM ET KC OE 0 0 O 0 0 0 0 0 C C 0 0 C C C C RR TI SD 1 N LO AI MT RI C C C C 0 C C O O C C O O O O OS NOP .E TP 0 0 0 0 C. O. G. D. D. 0 D. O. O. 0 9 D. CY AT M M M M M M M M M M M M M M M M EVE LP A A A A A A A A A A A A A A L L AY G G G G G G G G G G G G G G G G VT E ) VE 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 5 LZN AII 4 4 4 4 8 8 6 6 8 8 4 4 2 2 2 1 YS( 2 1 1 l Y R EO VG LE B B B B 8 B B B B B B B 8 B 8 B AT VA C E VLA N 5 N V O S A I A 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 L DT L P E A C T T M NS AE R R GE 2 2 3 3 A 1 A 1 A 1 A 1 4 4 4 4 4 4 B 1 A 1 GO L W D 2 - 2 - 3 - 3 1 1 1 - 4 - 4 - 4 - 4 - 4 - 4 1 1 R A O I 6 6 6 6 6 6 6 1 6 6 6 6 - 6 6 6 6 6 P P 1 31 31 3 1 3 1 3 1 3 1 3 1 3 1 3 1 3 1 3 1 3 1 31 3 1 31 3 1 6 1 6 1 6 1 6 1 6 1 6 1 d P 6 1 6 1 6 6 1 6 1 6 16 1 6 6 1 6 1 1 G nR N aA N N M-WN N N N N N N N N N N N N N N N N N 5 N N N N N N M 5 N I E2 T. L S3 C a E U A B A B 8 A B A 8 A 8 A 3 1 1 2 2 4 6 7 7 9 9 1 1 2 2 2 1 S R 0 0 0 0 0 0 0 0 0 0 1 1 1 1 3 4 ) T . N 1 1 1 E D EE 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 9 C .O ,n VB 8 8 B 8 8 8 8 8 B F 8 8 B 8 8 '8 81 O0 o LN 1 1 I I I 1 1 I I 1 1 1 I 1 1 0 8 I 1 V W AU 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 7 / i R SDS s VN 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 0 G E S I T i / / / / / / / / / / / / / / / / ( 9 S AAI v 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 7 7 N L R N e 1 D I C B UR 2Z i1 j!' l!l ltl! liiil llil .i .jili <',i !1 lji4{1iiii 1 jl! =

t INSERVICE TESTING PROGRAM PLAN - [ CIA 55 1, 2, 3, and AUGMENTED VAL 7ES I BRAIDWOOD NUCLEAR POWER STATION UNITS 0, 1. & 2 Revision 5 t, l + VALVE VALVE VALVE VALVE ACT. t#JRMAL STROKE TEST TEST RELIEF TECH. NUMBER P&ID CLASS CATEGORY' SIZE TYPE TYPE POSITION DIRECT. N MODE REQUEST NOTES POS. RE1W K5 t (IN.) (VR) (VA! [ 1/25I8815 N61-2 1 AC 3.0 CK 5.A. C 0 Ct RR VR-15 3 N136-2 C Lt/Bt RR VR-15 6 3 1/25I881SA N61-4 1 AC 6.0 CK 5.A. C 0 Ct C5 9 3 l h N136 4 C Lt/Bt RR VR-15 6_ 23 3 1/25I8818B M-61-4 1 AC 6.0 CK 5.A. C 0 Ct C5 9 3 i 5136-4 C it/Bt RR VR-15

6. 23 3

e 1/25I8818C . N61-4 1 AC 6.0 CK 5.A. C 0 Ct C5 9 3 l i i N136-4 C Lt/Bt RR VR-It A 23 3 f j t/25188'A N61-4 1 AC - 6.0 CK 5.A. C 0 Ct C5 9 3 I i i N136-4 C Lt/Bt 9R VR-15

6. 23 3

{ 1/2518819A N61-3 1 AC 2.0 CK 5.A. C C Lt/Bt RR VE-15 6, 23 3 N136-3 0 Ct RR VR-15 3 [ 1/25I88198 M-61-3 1 AC 20 CK 5.A. C C Lt/Bt RR VR-15

6. 23 3

? [ i N136-3 0 Ct GR VR-15 3 { i 1/2518819C N61-3 1 AC 2.0 CK 5.A. C C Lt/Bt ER VR-15

6. 23 3

i N136-3 0 Ct RR W-15 3 1/251890 N61-3 1 AC 2.0 CK 5.A. C -C Lt/St RR VR-15

6. 23 3

) i I N136-3 0 (t RR VR-15 3 1/25I8821A N61-3 2 B 4.0 GA M.0. O _C 5t 07 1 t N136-3 It RR 1/25188218 N61-3 2 B 4.0 GA M.D. O C 5t OP 1 E I N136-3 It RR j 1/2516835 N61-3 2 B 4.0 GA M.0. O C St C5 14 1 i 3 i f i N136-3 It RR I 1/2518840 M-61-3 2 B 12.0 GA M.D. C 0 St C5 14 1 i I t N136-3 It RR ) 1/25IS841A N61-3 1 AC 8.0 CK 5.A. C C Lt/Bt RR VE-15 6 3 [ i ? N136-3 0 Ct RR W-15 3 L i 1/25I88418 N61-3 1 AC 8.0 CK 5.A. C C Lt/Bt RR VR-15 6 3 N136-3 0 Ct RR VR-15 3 [ 4.3 VALVE TABLES - Pa9e 34 of 43 ( L e 1 I

217(070891) i 1

2D79G/82 l i

l a ^ INSERVICE TESTING PROGRAM PLAN I CLASS 1, 2, 3. and AUGMENTED VALWS ' l - BRAIDWOOD NUCLEAR PoetER STATION l UNITS 0, 1, & 2 . Revision 5 -VALVE VALVE. VALVE VALVE ACT. NORMAL STROKE TEST TEST RELIEF TECH. l 4 NUMBER P&ID CLASS CATEGORY SIZE TYPE TYPE POSITION DIRECT. METHOD MODE RE7 JEST NOTES POS. REMARKS (VR1 (VA) (IN_1 1/2518871 2 A 0.75 GL A.0 C C St OP 1 Lt RR VR-1 1 N61-6 It RR M-125-6 Ft OF 2 1/2518880 2 A 1.0 GL A.O. C C St OP 1 N61-6 Lt ER IR-1 It RR N136-6 Ft OF 2 1/2518848 2 A 0.75 GL A.0 C C St OP 1 Lt RR VR-1 M-61-3 It RR N136-3 Ft OP 2 1/ZSI8900A N61-2 1 AC 1.5 CK S.A. C 0 Ct ER VR-15 3 1/25189006 N61-2 1 AC 1.5 CK S.A. C 0 Ct RR VR-15 6 3 C Lt/Bt RR VR-15 N136-2 3 C Lt/Bt RR VR-15 6 3 N136-2 1/2"IB900C N61-2 1 AC 1.5 CK S.A. C 0 Ct RR VR-15 3 C Lt/Bt RR VR-15 6 3 N736-2 1/25189000 N61-2 1 AC 1.5 CK S.A. C 0 Ct ER VR-15 3 C Lt/Bt RR VR-15 E 3 Nf36-2 1/2SI8905A N61-3 1 AC 2.0 CK S.A. C 0 Ct RR VR-15 3 C Lt/Bt RR VR-15 6 3 Nf36-3 1/25189058 N61-3 1 AC 2.0 CK S.A. C e Ct RR VR-15 3 C Lt/Bt RR VR-15 6 3 W136-3 1/2SI8905C N61-3 1 AC 2.0 CK S.A. C 0 Ct RR VR-15 3 C Lt/Bt RR VR-15 6 3 N136-3 1/2SI8905D N61-? 1 AC 2.0 CK S.A. C 0 Ct RR VR-15 3 C Lt/St RR VR-15 6 3 M-136-3 1/2SI8919A N61-1A 2 C 1.5 CK 5.A. C 0 Ct 09 3 C Bt OP 31 3 N136-1 1/25I8919B N61-1A 2 C 1.5 CK S.A. 0 0 Ct OP 3 C Bt OF 31 3 N136-1 4.3 VALVE TABLES - Page 35 of 43 l 217'070891) ZD79G/S3

INSERVICE TESTING PROGRAM FLAR CLASS 1, 2, 3. and AUGMENTED VALVES BRAIDWOOD NUCLEAR POWR STATIO:4 UNITS 0, 1, & 2 . Revision 5 VALVE VALVE VALVE VALVE ACT. NORMAL STROKE TEST TEST RELIEF TECM. l f i NUMBER P&ID CLASS CATEGORY ' SIZE TYPE TYPE POSITION DIRECT. TTHX) NODE RECCEST NOTES F05. REFAKS I-1IM.) fW1 (VA) i 1/2518920 N61-1A 2 8 1.5 GL M.O. O C St OP 1 l I i N136-1 It RR i 1/2SI8922A N61-1 A - 2 C 4.0 CK S.A. C 0 . Ct RR VR-3 3 i 1 i i N136-1 C Bt RR 'VR-3 3 i 1/2518922B N61-1A 2 C 4.0 CK S.A. C 0 Ct RR VR-3 3 i N136-1 C Bt RR VR-? 3 j 1/25I8924 N61-1A 2 B 6.0 GA M.0. O C St OP 1 1 i N136 1 It K2- [ 1/25I8926 M-61-1A 2 C 8.0 CK S.A. C 0 CUXt RE/GP VR-6 25 3 i ( N1351 3 [ 1/2SI8948A N61-5 1 AC 10.0 CK S.A. C C LUBt RR VR-5

6. 23 3

l-N136-5 0 Ct RR VR t i L 1/25I89488 N61-5 1 AC 10.0 CK S.A. C C Lt/Bt RR W-5

6. 23 3

I N136-5 0 Ct RR VR-5 3 l. 1/2 SIB 948C N61-6 1 AC 10.0 CK S.A. C C Lt/Bt RR VR-5 6 3 ( e N136-6 0 Ct RR V7-5 3 l 1/2518448D 561-6 i AC 10.0 CK S.A. C C Lt/Bt RR W-5 t 3 i l } N136-6 0 Ct RR VR-5 3 l j 1/2 SIB 949A N61-3 1 AC 6.0 CK S.A. C C Lt/Bt RR VR 15 6 3 L i 1 N136-3 0 Ct RR VR-15 3 t i 1/2518949B N61-3 1 AC 6.0 CK S.A. C C Lt/Bt RE VR-15 6 3 i-j M-136-3 0 Ct RR VR-15 3 7 1/2SI8949C N61-3 1 AC 6.0 CK S.A. C C Lt/St RR VR-15 6 3 i i I .{ N136-3 0 Ct RR VR-15 3 j 1/25189490 N61-3 1 AC 6.0 CK S.A. C C Lt/Bt RR VR 6 3 9 l N136-3 0 Ct RR VW-15 3 [ 1/2 SIB 956A 561-5 1 AC 10.0 CK 5.A. C C Lt/Bt PR VR-5 6 3 r l N136-5 0 Ct RR VR-5 3 [ i _.1/25189568 N61-5 1 AC 10.0 CK S.A. C C LUBt RR VR-5 6 3 l j s N136-5 0 Ct RR VR-5 3 l 1/ZS18956C N61-6 i AC 10.0 CK S.A. C C LUBt ER VR-5 6 3 i N135-3 0 Ct RR VR-5 3 4.3 VALYE TA8LES - Faga 36 of 43 I l 217(070891) ? { 2D79G/S4 t t

GS

• /

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INSERVICE TESTING PROGRM PLAN 1 CLASS 1,-2,.3, and ALF> TENTED VALVES m BRAIDWOOD NUCLEAR POWER STATIG2 !, (NITS 0,1, & 2 }.' Revision 5 VALVE VALVE VALVE VALVE r.CT. NOR?tAL STROKE TEST TEST RELIEF TECH. 8 e NUMBER F&ID CLASS CATEGORY SIZE TYPE-TYPE POSITION DIRECT. PETHOD MODE REQUEST. NOTES FOS. REMARKS (IN.1 (VR) (VA) 1/2V0001A N105-1

2 A

48.0 BTF H.O. C C Lt S VR-1 11 I N106-1 St 'CS 11 1 It RR 1/2V00018 N105-1 2 A 48.0 BTF. H.O. C C tt S VR-1 II l N106-1 St CS 11 1 l It RR j 1/2VQ002A N105-1 2 A 48.0 BTF H.O. C C Lt S VR-1 11 l~ N106-1 5t CS 11' 1 It RR 1/2VQOO2B N105-i 2-A 48.0 BiF H.O. C C Lt S VR-l' 11 f. 5106-1 St CS 11 '1 l It RR 1/2VQ003 N105 2 A 8.0 BTF A.O. C C Lt OP VR-1 11 { N106-1 St OP 1 t It RR i 1/2V0004A N105-1 2 A 8.0 BTF A.O. C C Lt OF VR-1 11 l N106-1 St OP 1 b { It RR i 1/2V00048 N105-1 2 A B.0 BTF A.O. C C Lt OP VR-1 11 N106-1 St . OP 1 I It RP l 1/2VQ005A N105-1 2 A B.O BTT A.O. C C Lt OP VR-1 11 [ N106-1 St 'OP 1 f It RR 1/2VQ0058 N105-1 2 A 8.0 BTF A.O. C C Lt OP VR-1 11 f N106-1 St OP 1 I l It RR i l 1/2V0005C N105-1 2 A 8.0 BTT A.D. C C Lt OP VR-1 11 ( N106-1 5t OP 1 .[ } It RR 1 i 4 1 i 4.3 VALVE TABLES - Page 40 of 43 [ l ( i l [ 4 I I 217(070891) l

'ZD79G/88 1

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}l ~ -IMSERVICE TESTING PROGRAM PLAN 1 CLASS.1, 2. 3, and AdQENTED VALVES BRAIDWOCD KUCLEAR DOWER STATION ' ' UNITS 0, 1, & 2 ! -Pevision 5 5 b VALVE VALVE VALVE VALVE ACT. NORMAL STROKE TEST TEST RELIEF TECH. { f NUteER P&ID CLASS CATEGORY SIZE TYPE TYPE POSITION DIRECT. METHOD MODE REQUEST NOTES P05. REMARKS fIM.1 fVR1 iVA1 1/2WOOO6A St OP 1 i N118-5 2. A 10.0 GA M.0. O C Lt RR VR-1 N118-7 It RR [ l 1/2W90068 St OP 1 I t [ M-118-5 2 A 10.0 GA - M.D. O C Lt RR VR-1 r M-11B-7 It RR i 1/ZWOOO7A N118-5 2 AC 10.0 CK S.A. C C it/Bt RR VR-1, 27 3 . i i N118-7 1/ZWOOO7B N118-5 2 AC 10.0 CK S.A. C C Lt/Bt RR VR-1, 27 3 L l N11 %7 i j 1/2 WOO 20A St OP 1 I t N118-5 2 A 10.0 GA M.D. O C Lt RR VR-1 j f Nii8-7 It RR t 1/2 WOO 20B St OP 1 i i M-118-5 2 A 10.0 GA M.0. O C Lt RR VR-1 j i f W118-7 It RR [ 4 1/ZW0056A St OP 1 i j f N118-5 2 A 10.0 GA M.G. O C Lt RR VR-1 N118-7 It RR I ( 8 1/2W00568 St OP 1 f M-118-5 2 A 10.0 GA M.0. O C Lt RR VR-1 i i f g N11b7 It RR { 1 i l l t 2 i i l 4.3 VALVE TABLES - Page 43 of 43 i 217(070891) i I ZD79G/91 f i. g ...w,.c-m,. w, q m 3 ~ ..v.s.-- ., +. -,, -, ,,--m,-

Revision f 1 SECTI(M 4.4 l VAINE N(TrES 1 9 127(070891) ZD70G/92 .. ~ -

~ _ _ - -. . - - _ ~. Rovlsion 5 VAUVE HUTES NOTE 1 Closure of the Main Stenm isolation valves IMS001A-D or 2MS001A-D during unit operation would result in reactor trip and safety injection actuation. To av< ~ this transient, theco valves will be partially stroked every three mc.ith s. Tull stroke testing will be done during Modes 4, 5, or 6 as plant conditions allow, per IWV-3412. NOTE.1 The tasting of any emergency boration flowpath valves during unit operation is not practical. Stroke testing the Doric Acid injection isolat.lon valve 1CV8104/2CV8104 and check valve ICV 8442/2CV8442, the Ril to CV ptunp suction Isointion valve 1CV8804A/2CV8604A, or the RWST to CV pump suction isolation i valves ICV 112D,E/2CV112D,E, could result in bosation of the RCS, resulting in i a ecoldown transient. Aligning the system in this configuration even for a short duration is, therefore, unacceptable. These vs1ves will be stroke tested during cold shutdown, in accordance with INV-3412. NOTE._3 These valves are the Main reodwater isolation valves: 1FWOO9A-D/2rWOO9A-D, and cannot be fully stroked during operation as feedwater would be terminated causing a reactor trip. They will, however, be partially stroke tested during operation as well as full stroke tested during cold shutdown, per the requirements of INV-3412. NOTE _4 Closure of these letdown and makeup valves ICV 112D,C/2CV1128,C, ICV 8105/ 2CV8105, ICV 8106/2CV8106, ICV 8152/2CV8152, and ICV 8160/2CV8160 during normal unit operation would cause a loss of charging flow which would result in a reactor coolant inventory transient, and possibly, a subsequent reactor trip. These valves will be full stroke / fall safe exercised during cold shutdown as required by INV-3412. HQTE_5 The 1RilB701A/B, 1 R118702 A/ B, 2 Ril8701 A/B, and 2Ril8702A/B valves are t he isolation boundary between the Hesidual llent Removal Pumps and the Reactor Coolant System. Opening one of these valves during unit operation will leave only one valve Acolating RIIR from the high RCS pressure. This would place the plant in an undesirable conditlon. Therefore, these valves will be full stroke tested during cold shutdown, per INV-3522. 4.4 Page 1 of 7 127(070891) ZD79G/93

Revision 5 ~ HDTE._6 The-following valves have been identified as intersystem'LOCA valves. They form a piessure boundary between the RCS and other essential rnmponents in order to protect these components f rom dmnage. These valves will be leak tested in accordance with the Draldwood Technical Specifications. Performance of the leak test on these valves also satisfies the back-flow test required for. check valves by NRC Generic Letter 89-04. Intersystem LOCA Valves 1Ril8701A/B 1Ril8702A/B 2Ril8701A/D 2 Rl!871*. A/ B 1Ril8705A/B 1518815 2Ril870$A/D 2518845 1M18818A-D 1818905A-D 2S18818A-D 2S18905A-D ISIR819A-D IS18948A-D 251BB19A-D 2S18948A-D 1818841A/B 1818949A-D 2S18841A/Il 2S18949A-D t 1518900A-D 1510956A-D 2518900A-0 PS18C56A-D i HOTE_1 The Reactor Pressure Vessel Vent Valves 1RC014A-D and 2RC014A-D cannot be stroked during unit operation, as they provide a pressure boundary betwoon the Reactor Coolant system and containment atmosphere. ft.llure of one of these vs1ves in the open position would result in leaving only one valve as the high pressure bot.ndary. These velves will be full stroke / fall safe exercised when the RCS pressure is at a minimum during cold shutdown, per IWV-3412. IfRTE_0 i 4 The Residual 11 eat Removal Pump discharge check valves 1Ril8730A/B and 2RII8730A/it cannot be full stroke exercised during unit operation due to the i high RCS pressure. These check valves will be partial stroke t6sted, however, on n quarterly basis and full stroke exercised durlul cold shutdown. This is in accordance with IWV-3522. NOTE _S i Due to the RCS pressure, the_ check valves listed below cannot be full stroke exercised during unit operation: ISIB818A-D 2S18818A-D RilR Cold Leg injaction IS18958A/B 2S18958A/B RWST to R11R Pump Suction i These valves will be full stroke exercised during cold shutdown,-In accordance with IWV-3522. l i 4.4 Page 2 of 7 127(070891) ZD79G/94

nevision 5 NOTE _10 The IrWO39A-D and 2rWO39A-D valves cannot be stroke tested during unft operatien as closure of theri valves would result in termination of the waterhanner prevention feedt ater flew. Thls would result in undesirable affects on the Stemn Generators. These valves will be full stroke / fall safe tested during cold shutdown, per IWV-3412. HQIE_Il The Primary Containment Purge Supply and Exhaust Valves 1VQ001 A/B, IV0002A/B, 2VQ001A/B, and 2VQOO2A/D cannot be stroke timed during unit operation, These 18-inch valves are the only isolation points between the containment atmosphere and the environment. Stroking thest valves at any time other than mode 5 or 6 would be a violation of the Draldwood Technical Specifications. These valves will be full scroke tested during cold shutdown, in accordance with INV-3412. These valves will be leak tested semlannually, in accordance with Draidwood Station Technical Speelfications. The primary Containment Mini-rurge and Exhaust Valves IVOOO4 A/It, IVQ005A/B/C, 2VQ004A/B, and 2V0005A//D/C, and the Post LOCA Purge Exhaust Valves IV0003/ 2V0003 will be leak tested every 3 months, in accardance with Braldwood Station Technical Specifications. HQ7E_12 The Aux 111ary reedwater check valves 1Ar001A/B, IAr003A/D, IAr014A-H, 1Ar029A/0, 2Ar001A/D, 2 7.r00 3 A/ B, 2Ar014A-H, and 2Ar029A/D cannot be full stroke tested durIng unit operation, as this would induce potentially damaging thermal stresies in the upper feedwater nostle piping. The 1Ar001A/D, t 1Ar003A/D, 2Af001A/D, and 2Ar003A/D valves will be partially stroke tested during operation, and all valves full stroke tested during cold shutdown. This will be performed per Tech Spec 4.7.1.2.2 and is in accordance with I IWV-3522. i HQTE_13 l The High Head Injection Isolation Valvec 1516801A/B and 2SI8001A/B cannot bo l E stroke tested during unit operation. These valves isolate the CV system from the RCS. Opening them during operation would enable charging flow to pass directly into the RCS, bypassing the regenerative heat exchanger. The temperature difference of the charging flow and the RCS could result in L damaging thermal stresses to the cold leg nozzles as well as cause a recctivity change which would, in turn, cause a plant transient. These valves will be full stroke tested during ccid shutdown in accordance with INV-3412. l 4.4 Page 3 of 7 127(070891) ZD79G/95

Revision 5 4 HQTE 14 -The safety injection system SVA0 (Spurious Valve Actuation Group) valves 1518802A/D, 15I8806, IS18009A/B, 1818813, 1818835, 1518840, 2SI8002A/a, 2 SIB 806, 2 SIB 809A/D, 2818813, 2S15835, and 2$18840 cannot be stroke tested during unit operation. These valves are re quit ed by the Technical l Specifications to be de-energized,ln thelt proper positions during unit operation. Stroking them would be a violation of the Technical Specifications 1 as well aa defeating the de-energized SVAG valve principle. These valves will be stroke testod during cold shutdown when they are not required to be de-energized. This As In accordance with IWV-3412. t HQTE_l$ 1 -DELETED-1 NOTE _10 4 These feedwater valves are exempt from all ASME Section XI testing requirementa per IWV-1100 and INV-1200. They are included in the program for operability tracking purposes only. The closure of the Maln reedwater -hegulating Valves irW510, IrW520, IrW530, IrW540, 2rW510, 2rW520, 2rW530, and 2rW540 during unit operation would cause a loss of feedwater to the steam generators, resulting in a plant transient with a possible reactor trap as a result. These valves will be fall safe (ft) tested pursuant to the Braldwood Station Techuldal Specifications. N,QTE_17 These feedwater valves are exempt from all ASME Section XI testing requirements per INV-1100 and IWV-1200. They are Included in the program for operability tracking purposes only. The closure of the Main reedwater Regulating Bypass-Valves 1FW510A, IrW520A, IFW530A, IFW540A, 2rW510A, 2rW520A, 2rW530A, and 2FW540A:during unit operation would require the Main reedwater. Regulating Valves to correct for bypassed flow and could result in a plant transleut with a possible reactor trip as a result. These valves will be fall i safe (Ft) tested pursuant to the Braldwood Station Technical Specifications. HQTE_10 L -DELETED- ] (Incorporated into NOTE 21) HQTE_19 -DELETED-(Incorporated Anto NOTE 14) l 4 l r c il 4.4 Page 4 of 7 i 127(070891) ZD79G/96

-.- - - - - - _ - - -. -.- ~ _.,. Revision 5 HQIL2.0 .The remote position indicator for these valves cannot be observed directly due to the encapsulated design of the solenoid valve body. During the indication test, ludirect evidence of the necessary valve disk movement shall be used, in I accordance with IWV-3412 (b). The talves affected are listed below ICV 8114 .1PS230A/B 2PS228A/B 1CV8116 1RC014A-D 2PS229A/B 1PS228A/B 2CV8114 2PS230A/B 1PS229A/D 2CV8116 2RC014A-D HRIL2.1 The Main Faedwater Tempering Flow Isolation Valves-1/2FWO34A-D are exempt from all ASME Section XI tenting requirements per IWV-1100 and IWV-1200. They are included in the program for operability tracking purpost.s only, and will be fall safe (ft) tested pursuant to the Draldwood Station Technical l Specifications. 1 HQIE_22 Per NRC request, the post-accident hydrogen mcnitoring system check valves 1/2PS231A and 1/2PS231B will be stroke exercised open on a quarterly frequency to verify operability. NOTE 21 1/2SI8818A-D,_1/2SI8819A-D, and 1/2SI8948A/B are Event V check valves, which are defined as two check valves in series at a low pressure /RCS Interface whose failure may result in a LOCA that bypasses containment. They are individually leak-tested in accordance with NRC' generic letter 89-04, position 14b. HOIE_24 1/2CC9518r 1/2CC9534, 1/2CV8113, and 1RH8705A/B are check valves designed to relieve pressure between two contalmnent isolation valves. The full flow limiting value is zero, since the safety function of these valves in the open direction is to relieve pressure only. HQIE_25 Check valve 1/2 SIB 926 prevents flow from the Safety Injection (SI) pump suction line to the Fefueling Water Storage Tank (RWST). The SI pumps are normally lined up in the INJECTION HODE to take suction from the RWST. This check valve would stop reverse flow when the SI pumps are transf erred to HOT / COLD LEG RECIRCULATION MODE to prevent contnmination of the RWST. Ilowever, the=1/2S18806 M.O.V. is in series with this check valve and would be cloned to prevent reverse flow as directed by the emergency procedures. Therefure, no backflow test (Bt) is required for 1/2518926. 1 4.4 Pape 5 of 7 l 127(070891) .ZD79G/97 ~

I l Revision 5 l NOTE _26 Check valve 1/2CVB510 prevents flow from the Chemical and Volume Control (CV) pump suction line to the Refueling Water Storage Tank (RWST). The CV pumps are normally lined up in the INJECTION MODE to tnke suction from the RHST. ~ This check valve would stop reverse flow when the CV pumps are transferred to llOT/ COLD LEG INJECTION MODE to prevent contamination of the RWST. Ilowev e r, the 1/2CV112D and 1/2CV112E M.O.V.'s are in series with this check valve and would be closed to prevent reverse I]ow as directed by the emergency procedures. Therefore, no back flow test (BL) is required for 1/2CV8546. NRIE_Z2 l -Check valves 1/2 SIB 958A/B prevent flow from the Residual Heat (Ril) Removal pump suction line to the Ref ueling Water Storage Tank (RWST). The RH pumps are-normally lined up in the INJECTION MODE to take suction from the RWST. These check valves 'would stop reverse flow when the Ril. pumps are transferred to HOT / COLD LEG RECIRCULATION MODE to prevent contamination of the RWST. Ilowever, the 1/2S18812A/B M.O.V.'s are in series with these check valves and would be closed to prevent reverse flow as directed by the emergency procedures. In addition, the RH suction valves 1/2 SIB 812A/B, 1/2Ril8701A/B or 1/ 2 RH 8702 A /11, and 1/2S18811A/B are electrically interlocked to prevent the backflow to-the RWST when the Ril system la in a RECIRCULATION MODE. Thus, no back flow testing of 1/2SID958A/B is required. NQIE_20 HRC Generic Letter 89-04, Attachment 1, Position 3 lists the CVCS Volume Control Tank (VCT) outlet check valve as an example of ASME Code Class check valves that perform a safety f unction in the closed direction that are frequently not back flow tested. At Braidwood Station, check valve 1/2CV8440 prevents flow from the Chemical and Volume Control (CV) pump suction to the 'VCT. The VCT is normally aligned to the CV pumps during normal plant operation. During e Safety Injection signal, the VCT is automatically isolated by closure of the 1/2CV1128 and 1/2CV112C M.O.V.'s, which are in series with the-1/2CV8440 check valve. Closure of either M.O.V. will prevent reterse flow to the VCT. Thus, no back flow testing of 1/2CV8440 is required. NRIE_19 Check valve 1/2CV8442 prevents flow from the Chemical and Volume Control (CV) pump - suction header to the boric acid transfer pump. This line is normally isolated by the 1/2CV8104 emergency boration valve. This valve would only be opened during.an emergency with the boric acid trcaster pump running. This check valve is unnecessary with the current system operation, and thus, no back flow testing of 1/2CV8442 is required. 4.4 Page 6 of 7 -127(070891) ZD79G/98 ,---.-._.-_.-_.__,__-_--,_a

i Revision 5 1 I i HQTE_3D check valves 1/2AF014A-H are verified to be closed each shift by the Operating Papartment, by verifying that the temperature at 1/2AF005A-H is 1 130* F. If i -the tempereture is > 130' F at any 1/2AF005 valve, then an abnormal operating l procedure is entered to isolate and cool down the affected lines. This j shif tly n.onit> ring of 1/2AF014A-H in the closed position adequately monitors the status of these valves. No additiontd monitoring / trending by the IST Group la required. i lLOTE_.11 Check valves 1/2CV8480A/B and 1/2 SIB 919A/B are the Centrifugal Charging pwnp and Saf ety Injection Pump mini-flow recirculation lane valves wh3ch open to allow recirculation flow during IST Surveillances. Acceptable full-stroke will be verified whenever the recorded mini-recirculation flowrote is within the " acceptable" or " alert" ranges given in the IST Pump Surveillance. liQTL_32 Check valves 1/2CC9463A/B and OCC9464 are the Component Cooling Water Pump discharge' check valves. The full design accident flow through any one pump cannot--be obtained during normal operation without-causing low flow alarms in adjacent loops and possible equipment damage due to low cooling water flowrates to the Reactor Coolant Pump (RCP) seals. These valves will be full-stroke exercised during cold shutdowns when plant conditions allow all four RCP's off. HQTE ll

• Used at Byron Station ONLY*

NOTE 34 - Per Braidwood Technical Specifications Amendment, valves 1/2SD002A-H, 1/2SD005A-D.have been removed from.the last of valves to be tested under 10CFR50 Appendix J and will now be tested per ASME Code Section XI, IWV-3420. N.QTIL15 The 1/2RH8705A/B check valves will be operability tested by verifying that there is depressurization in line 1/2RH26AA-3/4 and 1/2RH26AB-3/4 when they are opened. This is a test method which was approved by the NRC in Byron's SER dated 9/14/90. NOTE 36 In response to GL 90-06, "PORV and Block Valve Reliability and Additional LTOP for LWRs," the 1(2)RY455A and 1(2)RY456 valves will be restricted from stroke testing in Mode 1. Technical Specifications will provide direction for any further operability testing required. (Reference NTS Item - 456-130-90-4.4-0100) 4.4 Page 7 of 7 127(070891) ZD79G/99

Revision 5 SECTION 4.5 VALVE TECilHICAL APPROACIIES AND POSITICMS 127(070891) ZD79G/100

__._.m. Revision 5 IST Techulcal Approach and Position No. VA-01 A. Component _ldentificat19st 1.

== Description:== Method of Stroke Timing Valves - Timing using control board position Indication lights (Ut). 2,_ Component Numbers: See IST Valve Tables. 3. Referencest ASME Code, Section XI, Subsection IWV, paragraph INV-3413(a). 4. Code Class: 1, 2, and 3. B. -Et2nirnment Use of the control board open and closed lights to determlne the stroke time of power-operated valves has recently become an lasue for discussion in the industry.- Paragraph 1RV-3413 of ASME XI defines " full-stroke time" as "that time interval from Initlation of the actuating signal to the end of'the actuatlng cycle. It is common industry practice to measure stroke time _ ao the time _ Interval between placing the operator switch on the control board in the "close" or "open" position and indication that the valve is open or_ closed on the control board (switch to light). C. Essiticus It is recognlsed that the way in which the limit switch that operates the remote position Indicator lights is set may result in " closed" or "open" Indication before the valve obturator has actually completed its travel. This is not conaldered to be a problem, as'the purpose of the test is to determine if degradation of the valve operator system is occurring, which la determined by observing changes in stroke time relative to the reference stroke time. Stroke time measurements should be rounded to the nearest tenth-(0.1) of a second, except that stroke times less than one half (0.5) second may be rounded to 0.5 second, if appropriate. Standard roundlug techniques are to be used when rounding stop watch readings during valve stroke time testing (e.g.,'10.45 rounds to 10.5 and 10.44 rounds to 10.4). Rounding to the nearestLaocond for stroke times of 10 seconds or less, or 10% of the speelfled limiting stroke time for stroke times longer than 10 seconds, as allowed by ASME Section XI subparagraph IWV-3413(b), will not be used. l 4.5 - Page 1 of 9 l-127(070891) ZD79G/101 l;

l Revision 5 \\ \\ l IST Technical Approach and position No. VA-02 I i A. Camponent,.1dentillsation: 1. Descriptions Method of pall Safe Testing Valves. 2. Component Numbers: See IST Valve Tables (pt). 3. References ASME Code, Section XI, Subsection IWV, paragraph IWV-3415. i 4. Code Class: 1, 2, and 3, B. Enquitaments paragraph INV-3415 of ASME XI states that "When practical, valves with fall-safe actuators shall be tested by observing the operation of_the valves upon loss of actuator power." Most valves with fall-safe positions j have actuators that use.the fall-safe mechanism to stroke the valve to the fall-safe position during normal operation. For example, an alt-operated valve that falls closed may.use air to open the valve against spring pressure. When the actuator is placed in the closed positlon, air is vented from the diaphragm and the spring moves the obturator to the closed . position. i C. Entitinni In the cases where normal valve operator action moves the valve to the closed position by de-energizing the operator electrically, by venting air or both (e.g., an electric solenold in the air system of a valve operator r.ioves to the vent position on loss of power), no additional fall-safe testing is required. Valves with fall-safe actuators that do not operate as part of normal actuator operation must be tested by other means. This may be accomplished for motor-operated valves by opening the circuit breaker supplying operator power _and observing that_the valve moves to its fall-safe positlon. Lifting leads is'not required unless it is the only method of de-energising the actuator. Using a valve remote poeltion indicator as verification of proper fail-safe operation is acceptable, provided the Indicator is periodically verified to be operating properly as required by ASME Code, Section XI, Subsection IWV, paragraph IWV-3300. E i 4.5 - page 2 of 9 t l 127(070891). ZD79G/102 . ~. _. -. _ -. _. _..... ~.,. _ -.. _ _. _. _ _ _ _, _.. _ _ - ~

Revlolon $ 1 IST Technical Approach and Position No. VA-03 A. CojnponcD LldenL111CAtlDDI 1. Descriptiont Method of Tull Stroke (Ct) and Dack Flow (DL) Exercising of Check Valves. 2. Component Numberst See IST Valve Tests (CL and Bt). 3.- _ References (a) NRC Generic Letter 89-04, Guldance on Developing Acceptable Inservice Testing Programs, Attac)unent 1, positions 1, 2, and 31 (b) ASME Code, Section XI, Subsection IWV, paragraph IWV-3$22) (c) SMAD Report M-1078-91, "S! Accumulator Check Valve Acoustle Test." 4. Code Class 1, 2, and 3. B.- Enquil.emcatl l l r _ Paragraph IWV-3$22 of At ticle XI states " check valves shall be exercised to the position required to fulfill their function unless such operation is not practical during plant operation. If only-11mited operation is practiem1, during plant operation the check valve shall be part-stroke ~ exercised during plant operation and full-stroke exercised during cold shutdowns." for check valves with no external posi*-ton Indication devices, the determination of when they are in full open position has proven difficult to determine. The verification of when a valve la the full open position affects the determination of which valves are only i part-stroked and thus require additional full-stroke testing during cold shutdown or refueling. j C. Positions - Valid full-stroke exe cising to the full-open or full-closed position may be accomplished by observing an exteruni position indicator which in considered to be a positive means of determining obturator poultion. Where external position indicators are not provided, manual stroking of the valve is acceptable. Where a mechanical exerciser is used, the torque required to move the obturator must be recorded and meet the acceptance standards of subparagraph IWV-3522(b). Per the requirements of HRC i Generic. Letter 89-04, Attacluont 1, Positlon 1, the other acceptable method of full-stroke exercising a check valve to the open position is to verify.thatLthe valva pa'snes the maximtun r equired accident condition flow. Any fJow less than this is considered as a part-stroke exercise. Flow through the valve must be determined by positive ineens such as permanently installed flow instruments, temporary flow lustrtunents, or by measuring the_ pressure drop across the velve or other in-line component. Measuring total flow t hrough mu?

• iple pat allel lines does not provide verification of flow through individual valves.

4.5 - Page 3 of 9 y 127(070891) ZD79G/103- -~ . ~. m.-. . ~..,. _ -.. _. _., _ _... _ _ _. _, _ _.... _. -.__, _-._.-

Revision $ IST Technical Approach and position No. VA-03 C. position, continued-One exception to the " maximum required accident flow" requirement is the methodology used to verify full-strcke exercising of the Safety Injection (SI) Accumulator Back-up Check Valves, 1/2818956A-D. Because of the high maximum design flow rate of these valves, a maximum design accident flow rate test is physically impossible to perform. For these valves, an Engineering calculation has been performed to determine the minimum flow rate for full disc 11ft. An acceptable full-stroke exercise of these valves will be performed each refueling outage by measuring the pressuriser level increase over time, converting these parameters to a flow rate through the valve, and verifylng this value is greater than or equal to the engineering calculated minimum flow rate for full dlse lift. per reference e above, these valves were also verlfled to full-stroke open t by using a " time of arrival" acoustic emission technique on the unit one valves that was performed in conjunction with the injection test described 1 in VR-05. This method la superior to sample disassembly and inspection of -one valve per outage which would require unusual system line-ups, freeze seals, radiation exposure, and possible plant transients. Other alternatives to measuring full design accident flow or disassembly and inspection of check valves to satisfy full stroke requirements is allowed as long as the requirements of HRC Generic Letter 89-04,, positions 1, 2, and 3 are utilized OR specific relief requests are approved by the-NRC. i Stroklng a valve to the full closed position for valves without a manual exerciser or position Indicator must be verifled using indirect means. t These include, but are not limited to,-(1) observing pressure indications on both sides of the valve to determine if the differential pressure expected with the valve shut is obtained, or (2) opening a drain l connection on the upstream side of the valve to detect leakage rates in excess of that expected with the valve shut. { i-Valves that cannot be full-stroke tested or whero full-stroking cannot be = ver1 fled, shall be disassembled, inspected, and manually exercised. Valves that require disassembly for full-stroke testing during cold shutdowns or refueling still require quarterly part-str oke testing, where possible. Testing of check valves by disassembly shall comply with the followingt a. During valve testing by disassembly, the valve internals shall be visually inspected for worn or corroded parts, and the valve disk shall be manually exercised. b. Due to the scope of this testing, the personnel hazards involved, and system operating restrictions, valve disassembly and inspection may be performed during reactor refueling outages. Since this frequency differs from the Code required frequency, this deviation must be specifically noted in the IST program. I I 4.5 - Page 4 of 9 l 127(070891) -ZD79G/104 ,a.__._ . J

Revision $ IST Technical Approach and position No. VA-03 c. Where it is burdensome to disassemble and inspect al,1 applicable valves each refueling ad. age, a sample disassembly and inspection plan for groups of identical valves in similar applications may be employed. The NRC Ceneric 1.etter 89-04 guidelines for this plan are explained below: The sample disassembly and inopection program involves grouping similar valves and testing one valvo in each group during nach refueling outage. The sampling technique requires that eacn valvo in the group be the same denign (manuf acturer,' size, model number, and materials of construction) and have the smne setylce conditions including valve orientation. Additionally, at each disassembly the licensee must verify that the disasoembled valve la capable of full-stroking and that the internals of the valve are structurally sound (no loose or corroded parts). Also, if the disassembly is to verify the full-stroke capability of the valve, the disk should be manually exercised. A different valve of each group la required to be disassembled, inspected, and manually full-stroke exercised at each successiva refueling outage, until the entite group has been testc6. If the disassembled valve is not capable of being full-stroke exercised or there is binding or failure of valve luternals, the remaining valves in that group must also be disassembled, inspected, and manually full-stroke exercised during the sNne outage. Once thic is' completed, the sequence of - 1 disassembly must be repeated unless extension of the interval can be juetified. Extending the valve sample disassembly and inspection interval from t disassembly of one valve in the group every refueling outage or expanding the group size-would increase the time between testing of any particular valve in the group. Wath four valves in a group and an 18-month reactor cycle, each valve would be disassembled and inspected cysry six years. If the fuel cycle la increased to 24 months, each valve in a four-valve snmple group would be disassembled and inspected only once every eight years. Extension of the valve disassembly / inspection interval from that allowed by the Code (quarterly or cold shutdown frequency) to longer than once every 6 years is a substantial change which may not he justified by the valve failure rate data for all valve groupings. When. disassembly / inspection data for a valve group show a greater than 25% failure rate, the station should deternine whether the group sise l should be decreased or whether more valves from the group should be disassembled during every refueling outage. Extensions of the group size will be done on a case by case basin. 4.5 - pago 5 of 9 127(070891) L ZD790/105 Am ur 1-S 4eme-m-=e**- p--.r e,e r'-w-. .e--ne <wn.-w rme-.,eew. ew, _.,-ie,g-w -pp.y-r 4,.9 y .y.- +,& e' .gy._,.,yy gmpyg-,.g-ww-.wmvuqym-eggig.y._.-4.,-y,g..pg.,r-m ,py,y,*y + y

Revision 5 i IST Technical Approach and Position No. VA-04 j A. Componentident1Ilcations i 1.

== Description:== Determining Limiting Values of rull-Stroke Times for Power Operated Valves. 2. Component Ntunbers: See IST Valve Tables (5t). 3. Referencost a. ASME Code, Section XI, Subsection INV, Sub Article IWV-3413. b. HRC Generic Letter 89-04, Attachment A, Position S. c. ANSI /ASME OM-1987 through OMb-1989 Addenda, Part 10, Section 4.2 4. Code Class 1, 2, and 3. 8. Ecuuirements The IST program originally nasigned a limiting value of full-stroke time based on the most conserva+1ve value from plant' Technical Snecifications (TS) or Updated Final Safety Analy11s Report (UFSAR). For ives not having a speelfled value of full-stroke, a limiting value was assigned based on manufacturers design input, engineering input, or initial valve pre-oferational testing. This methodology is contrary to NRC Generic Lotter 89-04. According to NRC Generic Lett.er 89-04 the limiting value of fell-stroke ~ should be based on an average reference stroke time of a valve when 1t is known to be operating properly. The limiting value should be a reasonable deviation from this reference stroke time based on the valve size, valve type, and actuator type. The deviation should not be so restrictive that it results_An a valve being declared inoperable due to reasonable _ stroke time variations. However,' the deviation used to establish the limit should be such.that. corrective action would be taken for a valve that may not' perform its intended function. When the calculated lim' ting value for a full-stroke is greater than a TS or safety analysis limit, the TS or -safety analysis limit should be used as the limiting value of full-stroke time. Based-on this, a review of each valve operating history was performed and an average / reference value of full-stroke determined. In addition, valves were grouped together by system, train, unit, valve type, and actuator type to provide for e more chorough review in determining i what would be a " reasonable" deviatlos. trom the average / reference full-stroke value. ~ The 1983 Edition through Summer 1983 Addenda of ASME Section XI does not. provide guidance for determining values of full-stroke. J 4.5 - Page 6 of 9 127(070891)- ZD79G/106- _..,. - _. _,. _.. _. _. -., _ _.. _ _ _ _ _ ~, _.. _., _, _ _ _..,.. _ _.., -

.._m Revision 5 IST Technical Approach and Position No. VA-04 C. LanLLinDs The following criteria will be used as general guidance to establish REQUIRED ACTION ranges for power-operated valvest HQV ' gISQVigZi[OV ' s / AOV ' s - Le s a t h an _ gLeguaLio 10.1REQada I REQUIRED ACTION VALUE Greater than-(2.0)(Tref), if (2)(Tref) is less than 5 seconds, 5 seconds may be used as the limiting value of full-stroke. HQVISISOV's/HOV's - GrtatgLthan30_GECRDdEI REQUIRED ACTION VALUEt Greater than (1.75)(Tref), but not to erceed Tech Spec. or UFSAR limiting value. ADV's - Qtegig Lthan 10 sRInDdBI REQUIRED ACTION VALUEt Greater than (2.0)(Tref), but not to exceed. Tech Spec, or UFSAR limiting value. Additional Notest 1. T is the reference or average stroke value in seconds of an ref individual valve or valve grouping established when the valve is known to be operating acceptably. -2. Standar6 rounding techr.lques are to be used when rounding off stopwatch readings during valve stroke timing (e.g. 10.45 rounds to 10.5, and 10.44 is rounded to 10.4 seconds). Round off all measurea stroke time to the nearest tenth of a second. 3.. When reference stroke valves or average stroke valves are affected by other parameters or conditions, then these parameters or conditions L must,be analyzed and the above factors adjusted. 4. If the above calculated values exceed a Technical Specification or TSAR value, then the TS or TSAR value must be used for the limiting value of full-stroke. a' I l' l 4.5 - Page 7 of 9 127(070891) ZD790/107 ,. _.. _. -, ~ _ _.. _, - _ _ - _,. _ _ _ _ - -.. -__.. _,_ __ _. _..-_, _ _ -_ _ __.. _. _. _ _

Revision 5 IST Technical Approach and Position No. VA-04 Additional Hotest (continued) 5. Fast. acting valves (valves which normally stroke in less tha.n 2 seconds consistently) are included in Relief Request VR-12. These ve.1ves are !!QT assigned ALERT RANGES and are llOT trended. 6. Ths hbove critoria is a guide and cannot cover all valves. The EEQUIRE ACTIOtt VALUES are selected based on comparisor. between tho RFTERE!1Cr VALUE, LIMITING VALUE given in Technical Specifications /UTSAR, operating history, and calculated values using the above criteria. Val'es which serve the v same function on dual trains (i.e., ICC9473A 7. and ICC94738) and duni units (i.e. 1CC9473A and 2CC9473A) are assigned the same REQUIRED ACTION VALUE based on human factors considerations, unless valve or system design differences exist between the trains / units. 7 4,5 - Page 8 of 9 127(070891) ZD79G/108

Revision 5 IST Technical Approach and Position No. VA-05 A. Cmponer.Lldentitintion: 1.

== Description:== Testing of the Boric Acid Transfer Pumps Discharge Check Valves 2. Component Number s t 0AB8473, 1/2AB8487 3. Referencess (a) Engineering Correspondence (CHRON I 161733) dated January 17, 1991 4. Code : lass: 3/T (Tracking 7urposes ONL'J) B. Requirements These check valves are tested per the Technical Specification requirement that requires an 18 month flow verification of 30 gpm to the RCS. Because the AD pumps were added to the program, the discharge check valves will also be added for tracking purposes only. C. Ens 11JDat The boric acid.ransfer pumps "t* Sd to the IST program per pump technical posir on PA-01. Sin 9 t-vias done, it was decided to put the discharge check valves in th-eg o " as well for tracking purposer only. Tnese valves are required to <s m imte of 30 gpm in order to meet the Technical Spec 2iication requir.1.=: t se quarterly pump test will verify greater than 30 gpm, which is 10.i t h ntly more frequent than the current Technical Specification freque.x; 'ack flow is prevented from the chemical and volume control system (CV) by check valve 1(2)CV8442 and motor operated valve 1(2)CV8104 in the emergency boration flow path. Also, the system uses only a single purp in series which precludes short circuiting of flow through the parallel pump's discharge check valve, so no back flow test will be performed. ) 4.5 - Page 9 of 9 127(070891) ZD79G/109

Revision 5 s SECTION 4.6 VMXE RELIEF REQUESE / 127(070891) ZD79G/110

Rsvision 5 RELIELEEQtlESLYR:1 1. Valve NumbgIn-1 All Type C tested primary containment isolation valves in this program are listed as Category As VALVE 1 YALYE_1 YALYE_1 1) ICC685 41) IFR033B 81) 1S18964 2) ICC9413A 42) 1PR033C 82) 1S18968 3) 1CC9414 43) 1PR033D 83) 1VQ001A 4) ICC9c16-44) IPR 066 84) 1VQ001B 5) 1CC9438 45) 1PS228A 85) 1VQo02A i 6) 1CC9486 46) IPS228B 86) 1VQOO2B 7) 1CC9518-47) 1PS229A 87) 1VQ003 8) 1CC9534 48) IPS229B 88) 1VQ004A 9) ICS007A 49) IPS230A 89) IVQOO4B 10) 1CS007B 50) 1PS230B 90) 1VQ005A 11) 1CS008A 51) 1PS231A 91) IVQ005B 112) ICS008B 52) IPS231B 92) IVQ005C 13) ICV 8100 53) 1PS9354A 93) IVQOl6 14) ICV 8112 54) 1PS9354B 94) 1VQO17 15) ICV 8113 .55) 1PS9355A 95) IVQO18 16) ICV 8152 56) 1PS9355B 96) 1VQo19 17) ICV 8160 57) 1PS9356A 97) IWM190 18) 1FC009 58) IPS9356B 98) INM191 39) 1FC010 59) 1PS9357A 99) IWOOO6A 20) 1FC011 60) -1PS9357B 100) IWOOO6B 21) IFC012 61) 1RE1003 101) 1WOOO7A 22)~ IIA 065 62) 1RE9157 102) IWOOO7B 23) IIA 066 63) 1RE9159A 103) IWOO20A 24) IIA 091 64) 1RE9159B 104) IWOO208 25) 10G057A 65) 1RE9160A 105) IWOO56A 26) 10G079 66) 1RE91600 106) IWOOS6B 27) 10G080 67) 1RE9170 28) 10G081 68) 1RF026 29) 10G082 69) 1RF027 30) 10G083 70) 1RYB025 31) 10G084 71) 1RYB026 32) .10G085 72)- 1RY8028 33) IPR 001A 73) 1RY8033 34) 1PR001B 74) 1RY8046 35) 1PR002E 75) 1RY8047 36) 1PR002F 76) 1SA032 37) 1PR002G 77) ISA033 38) 1PR002H 78) ISIB871 39) 1PR032 79) ISI8880 40) IPR 033A 80) ISI8888 4.6 - Page 1 of 49 127(070891) ZD79G/111

Revision 5-FILIELEEQUEST_VR:1 YAlrejiwnbers - (continued) - YALYL.1 ' YALVI_t YALYL.l. 107) 2CC685 147) 2PR033B 187) 2SI8964 108) 2CC9413A 148) 2PR033C 188) 2 SIB 968 109) 2CC9414 149) 2PR033D 189) 2V0001A 110) 2CC9416 150) 2PR066 190) 2VQ001B 111) 2CC9438 151) 2PS228A 191). 2VQ002A 112)- '2CC9486 152) 2PS228B 192) 2VQOO2B 113) 2CC9518 153) 2PS229A 193) 2VQ003 114) 2CC9534 154) 2PS229B 194) 2VQOO4A 115) 2CS007A 155). 2PS230A 195)- 2V0004B 116) 2CS0078-156) 2PS230B 196) 2VQ005A i 117)- 2CS008A-157) 2PS231A-197) 2V0005B-118) 2CS008B 158) 2PS231B 198) 2VQ005C 119) 2CV8100 159) 2PS9354A 199) 2V0016 120) 2CV8112 160) 2PS9354B 200) 2VC017 121) 2CV8113 161) 2PS9355A 201) 2V0018 122) 2CV8152 162) 2PS9355B 202) 2VQ019 123) 2CV8160 163) 2PS9356A 203) 2NM190 124) 2FC009 164) 2PS9356B 204) 2WM191 -125) 2FC010 165) 2PS9357A 205) 2WOOO6A 126) .2FC011 166). 2PS9357B 206) 2WOOO6B 127) 2FC012- -167)- 2RE1003 207) 2WOOO7A 128) 21A065 168) 2RE9157 208) 2WOOO7B 129) 2IA066 169) 2RE9159A 209) 2 WOO 20A 130) ?IA091' 170) 2RE9159B 210) 2 WOO 20B 131) 200057A 171) 2RE9160A 211) 2 WOOS 6A 132) 200079 172) 2RE9160B 212) 2 WOO 56B 133) '20G080 173) 2RE9170 134) 2OG081 174) 2RF026 135) 20G082 175) 2RF027 136)- 20G083 176) 2RY8025 l 137) 20G084 177) 2RY8026 l 138) 20G085 178) 2RY8028 l 139) 2PR001A 179) 2RY8033 140) 2PR001B 180) 2RY8046 141) 2PR002E 181) 2RY8047 142) 2PR002F 182) 2SA032 143) 2PR002G 183) 2SA033 144) 2PR002H-184) 2SI8871 145) 2PR032 185) 2SI8880 146) 2PR033A 186) 2SI8886 4.6 - Page 2 of 49 127(070891) ZD79G/112

Revision 5 RELIEE_EEQUESI_YR 1 2 Ilumher.of._1tems: .212 3. ASRLC9de_Categnty A 4. ASMILC9de&_Se ctirnlLRe quir eme n ts : Seat Leakage Measurement per IWV-3420 and Corrective Action per IWV-3427(b). 5. Ragia_1gI_Rellel: Primary contalmnent isolation valves will be seat leak tested in accordance with 10 CFR 50, Appendix J. For these valves, Section XI testing requirements are essentially equivalent to those of Appendix J. ~ 6', 'Alternette_ Inst.ing : PrimLry containment isolation valves shall be seat leak rate tested in accordonce with the' requirements of 10 CFR 50, Appendix J. The results of such leak rate measurements shall be analyzed and corrected, as necessary, in'accordance with the guidance set forth in ASME Code Section XI. Subsect3on IWV, paragraphs IWV-3426 and IWV-3427(a). The trending requirements of INV-3427(b) will nat be utilized. 7.- JM511firatiDRt No additional information concerning valve leakage would be gained by performing separate tests to both Section XI and Appendix J. Therefore, overall plant safety is not affected. As specified per NRC Generic Letter 89-04, Attachment 1, position 10, the usefulness of IWV-3427(b) does not justify the burden of complying with this requirement. 8. APRlicable Time Period: This relief is requested once per two years during the first inspection ( interval. 9. 'AppInYal_Etatusi -a, Relief granted per NRC Generic tetter 89-04 b. Deleted SD valves per Technical Specification knendment 526. l 4.6 - Page 3 of 49 l 127(070891) zD79G/113

Pevision 5 RELIELEEQUESLYR._2

• 1.

' Y.aly.c 11umbat ICS020A 2CS020A ICS020B 2CS020B-2.~ llumber of-ItemE 4-3. ASML. Code _Categnty: C 4. ASMLCado. Eecli.oJLKLRequirements: ~ Exercise' check valves to the position required to fulfill their function (open=Ct; closed =Bt), unless such operation is not practical during plant operation,_per IWV-3522. .5. -Haals for Relief: The check valves in_the spray additive system cannot be stroked without introducing NaOH into the CS system. 6. AltnInnte_Ingling: The A and D train valves are of the same design (manufacturer, size, model number, and materials of construction) and have the same service conditions, including orientation, therefore they form a sample disassembly group. Group 1-Group 2 1CS020A-2CS020A-ICS020B 2CS020B 1. One valve from each group, on a per unit basis, will be examined each refueling outage. If the disassembled valve.is not capable of being full ' stroked exercised or there is binding or failure of internals, the remaining valve on the affected unit will be inspected. l 7 Jus tif.irati.QD: Full flow testing of these valves cannot be accomplished without posing a serious threat to the safety of equipment and personnel. It is impractical to either full or partial stroke exercise these valves since -flow through them would result in the introduction of NaOH into the CS system. Full flow testing would require a special test hook-up and necessitate flushing the rystem. l l-4.6 - Page 4 of 49 127(070891) ZD79G/114

RQvision 5L RELLLE.Et0GESI_YE:2 7. J.ustification s (continued) The alternate test-f 7-quency is justifiable in that maintenance history and previous inspections of.these valves at both Byron and Braidwood stations has shown no evidence of degradation or physical impairments. This is to be expected since these valvenfsee very limited operation. Industry experience,L as documented in NPRDS, showed no history of problems with these valves, A company wide check valve evaluation addressing the "EPHI Application Guidelines for Check Valves in Nuclear Power Plants" revealed that the location, orientation and application of these' valves are not conducive to the type of wear or degradation correlated with SOER 86-03 type problems. Iloweve r, they still require.some level of monitoring to detect hidden problems. Tlie alternate test method'Is suf ficient to ensure operability of these volves~and is consistent with Generic letter 89-04. 8. Applisahla lime _Perindt This relief is requested once per quarter during the first inspection interval. 9. ApgrRYAl_Si dua a. Relief granted per' Generic Letter 89-04, l-4.6 - Page 5 of 49 127(070891) ZD79G/115

-.._-_ _.._ _ _.__- _._.~... _ _._._.~...._-_ Revision 5-ELIELMOVESIJUL-l

1. -- YalYtJlumbat :

IS18922A/B 2518922A/B 2. IlumbmI_ n L Il eins: 4 3. ASME_ Code _Categnty: C 4.. ASME_ Code. Snc.Linall_ Requirements: Exercise for operability (Ct/Bt) of check valves every 3 months, per IWV-3521. 5. Haals_ lor._RelleI: These check valves.cannot be full flow tested during operation as the shut-off head of the Safety injection pumps is lower than'the. reactor coolant system pressure. Performance of this test with the RCS depressurized, but intact, could lead to inedvertent over-pressurization of the system. The alternate method of protecting against over-pressurization by partially draining the RCS to provide a surge volume is not considered a safe practice due to concerns of maintaining adequate water level above the reactor core. 6. Alternative Testing: These valves will-be full-stroke tested during refueling outages as a minimum, but no more frequently than once per quarter. 7. dustificatinn This alternative will adequately maintain the system in a state of operational readiness, while not sacrificing the safety of the plant, by testing the valves as often as safely possible. 8. Applinable Time Perind: This relief is requested once per quarter during the first inspection interval. 9. Approval ~ Status: a. Relief granted per NRC Genoric Letter 89-04. 4.6 - Page 6 of 49 127(070891) ZD79G/116

Revision 5 i EELLEE._REW EEI.JPei li Valve Numbert ICS008A/B 2CS008A/D 1CS003A/B 2CS003A/B 2. liumber of.I?,fmat 8 3. ASME Code _Categg y* AC and C 4. AS_ME CodeL Sectinn XI Requ1Ifmg.RLSI Exercise check valves to the position required to fulfill their function (open=Ct; closed =Bt), unless such operation is not practi:a1 during plant operation, per IWV-3522. 5.' Basis for Relief: These valves cannot be full flow tested as a matter of course during unit operation or cold shutdown as water from the CS pumps would be discharged through the CS ring headers causing undesirable effects on system components inside containment. Additionelly, the full flow testing of these check valves during periods of cold shutdown, using the CS pumps, would 1111 the reactor ref ueling cavity with contaminated water from the ress&Ilug water storege tank. The filling of the cavity, via temporarily installed large bore piping, would require the removal of the reactor vessel head so as to preclude equipment damage from borated water. The erection of temporary piping from the CS line to the reactor cavity would take an estimated nine to twelve shifts, or longer compared to one to two shifts for valve inspection. This estimate does not take into account the time required to drain and remove the' piping from containment. Currently, full flow recirculation flow paths do not exist from the discharge of the CS pumps through these check valves to the refueling water storage tank. The addition of such flow paths would require extensive plant modifications to existing plant designs, including penetration of containment integrity. Partial stroking of the 1/2CS008A, B valves using air does not provide adequate assurance of valve operability and may be detrimental for the following reasons .A. There is no correlation between air flow and angle of disc movement. B. Venting and draining the appropriate piping quarterly may cause deposition of boric acid residue which could in turn promote binding of the check valve internals. 4.6 - Page 7 of 49 127(070891) ZD79G/117

Revision 5 RELIEE_ REQUEST _YR-A 6. Alicrnateletting The A and B train valves are of the same design (manufacturer, size, model number,iand materials of construction) and have the same service conditions, including orientation, therefore they form a sample disassembly group. Group 1 Group 2 1CS003A 2CS003A ICS003E 2CS003B Group 1 Grot *p 2 1CS008A 2CS008A ICS008B 2CS008B One valve from each group, on a per unit basis, will be examined each refueling outage. If-the disassembled valve is not capable of being full stroked exercised or there is binding or failure of interns 1s, the remaining valve on the affected unit will be inspected. In addition to the above, the 1/2CS003A, B valves will be partial stroke tested during the quarterly pump surveillance. 7. Justification: The 1/2CS003A, B and.1/2CS008A, D valves are removed from the system and visually examined per the strict detailed inspection requirements of the Station Check Valve Program. This inspection adequately verifies that the valves are maintained in a state of operational readiness. The valves are verified to be functional by performing a-thorough visual inspection of the internals and by performing a manual-full-stroke-exercios of each disc. Previous inspections of these particular valves-at both Byron and Braidwood Stations has repeatedly shown'them to be in good condition. The_ wafer type design of the valve body for these valves _makes their removal a simple process, with little chance of damage to their internals. .Also, there is no disassembly of internal parts required; all wear surfaces are accessible by visual examination. After inspection and stroke testing, the valve is reinstalled into the line and post maintenance testing is performed. The 1/2CS008A, B valves receive a containment leakage tect, and the 1/2CS003A, B valves are partial flow tested..These tests verify proper installation of the check.alves, and the valve inspection procedure requires post-inspection visual examination of the check valve to ensure that the pin is oriented properly and that the flow direction is correct. l 4.6 - Page 8 of 49 127(070891) ZD79G/118 l.

. ~. ~. ...-- ~.... - -. _.. -.. Revision 5 EELIIF REQUEST VR-4 !7. J.ugtification s (continued) LThe' alternate test frequency is justifiable in that maintenance history and previous inspections of these valves at both Dyron and Braidwood stations has shown no evidence of degradation or physical. impairments. . Industry experience, as documented'in NPRDS, ahowed no history of problems with these valves; A company wide check valve evaluation addressing the "EPRI Application Guidelines for Check Valves in Nuclear Power Plants" revealed that the location, crientation and application of these valves are not conducive to the type of wear or degradation correlated with SOER 86-03 type problems. However, they still require some level of monitoring to detect hidden problems. The alternate 7 est method is sufficient to ensure operability of these t valves and is consistent with Generic Letter 89-04. 8. Applicable _ Time Period: This relief is requested once per quarter during the first inspection interval. 9. - AEptqYal_S_ tat.us a. Relief granted per NRC Generic Letter 89-04. l 4.6 - Page 9 of 49 i 127(070891) -ZD79G/119 l

/ Rsvision 5 EELIEF REOUEST VR-5 (1. Valve Numbat: 1SI8956A-D 2SI8956A-D ISI8948A-D 2SI8948A.D -2. Rumber of Items: 16 3. ASME Code Category: AC 4. ' ASME_Cnda. Section XI RequiIemeALE: Check valves that cannot be exercised during plant operation shall be specifically_ identified by the owner and shall be full stroke exercised during cold shutdowns per IWV-3521 and IWV-3522. 5. Ilna.iLI2r Re11el The accumulator check valves cannot be tested during unit operation due to the pressure dif ferential between the _ accumulators (650 psig) and the reactor coolant system (2235 psig). Full stroke exercising of these valves could occur only with a rapid depressurization of the reactor coolant system. 6. ' A11gInnte Testing: Braidwood Station Technical Specifications require leak testing to be performed on these valves if the unit is in cold shutdown for greater than 72 hours and if-such leak rate testing has not been performed within the past nine months. Therefore, Braidwood Station will back flow (Bt) test these check valves on the same schedule. Successful completion of the seat leakage test will provide positive verification of closure (Bt). The accumulators will be discharged into the reactor vessel during refueling outages to~ perform a full stroke exercise (Ct) of these valves. An Engineering calculation has been performed to determine the minimum flow rate for full disc lift. An acceptable full-stroke exercise of these valves will be performed each refueling outage by measuring the pressurizer level-increase over time, converting these parameters to a flow rate through the valve, and verifying this value is greater.than or equal to the engineering calculated minimum flow rato for full disc-lift. Positive verification of valve full stroke will be adequately demonstrated using this method. 7. Justifications Back flow testing these check valves on the same schedule as their required Technical Specification leak rate testing will adequately maintain the system in a state of operational readiness without causing unnecessary personnel radiation exposure. 4.6 - Page 10 of 49 127(070891) ZD790/120

Revision 5 EELIEF REQUIST_YE_5 7. Justificatigms (continued) It is impractical to full stroke these valves during cold shutdowns, routine or forced, due to time and system constraints, increased radiation exposure, and costs involved. The roactor coolant system (RCS) must be_at approximately 40 pci with all 4, reactor coolant pumps (RCPs) off and accumulator-pressure at 100 psi over RCS pressure. Installing special test equipment to record pressurizer level increase could interfere with the requited Technical Specification leakage test, required prior to entering Mode 2. The amount of nitrogen required to test these valves alone is approximately $2500. Also, at this point in core life, boron concentration in the RCS is relatively low compared to the 2000 ppm concentration in the accumulators. This injection test uses an estimated 8 to 10 thousand gallons of-water, which will increase the RCS boron concentration, resulting in substantial delays with startup of the reactor. To dilute the RCS boron concentration, the feed and bleed process will greatly increase the amount of high grade water rejected from the site and may_even increase the amount of radioactive effluents discharged to the environment. Additionally, the unit one valves were acoustically tested during the above described injection test on 2/1/91. Using a " time of arrival" technique,'the ISI8956A-D valves were positively proved to full stroke to the open position as flow developed through each valve.- This test is documented in System Material Analysis Department (SMAD) Report M-1078-91. The SI8948 valves have also been shown to full-stroke at a much lower flow _ rate during the RH system injection test. This alternate test method is superior to sample disassembly and inspection of one valve per outage which would require unusual system line-ups, freeze seals, radiation exposure, and possible plant transients. 8. Applicable __TJme peripAL -This relief is requested once per quarter during the first inspection interval. 9. Approval Stat.ust a. Relief granted per NRC Generic Letter 89-04. b. Requested refueling frequency for the CT exercise test of these valves and incorporated the necessary information and justification. Information regarding acoustic test results was also included per revision S submittal. l l_ 4.6 - Page 11 cf 49 127(070891) ZD79G/121

1 -Rovision 5 ) llELIEF REQUIS*Lyl-b

1.. Yaly1Jiumbat t.

18I0926 2 SIB 926 2. liumhgr of-Itemat. 2-3. AM4Mosla_Categnty C 4.- ASM2 Code, Section XI Reggi;1menta t Exercise for operability (Ct) of check valves every 1 months, per IWV-3521. 5. DAsis for Relieft-Full stroke exercising of the Safety-Injection pump suct a check valves, ISI8926 and 2518926 cannot be demonstrated durit.g unit operation as the reactor coolant system pressure prevents the pumps from reaching full flow injection conditions. Performance of this test with the reactor coolant system intact could lead to an inadvertent over-pressurization of the system. The alternate method of protecting agailct over-pressurizar bn by partial draining of the reactor coolant system to provide a surge volume is not considered a safe practice due to concerns of mal".taining adequate water level above the reactor core. 6. Alternate Te1 Ling: The 1S18926 and 2 SIB 926 valves will be partial stroke tested during periodic inservice tests with the SI pumps in the recirculation mode. Full stroke exercising for the val' es will be done during refueling outages as a minimum,-but no more frequently than once per quarter. 7. J.ustification l-This alternative will adequately maintain the system in a state of operational readiness, while not sacrificing the safety of the plant, by testing the valves as.often as safely possible. 8. Applicable Time PeI,indi This relief is-requested once per quarter during the firrt inspection interval.

9. ' Approval Statua

.a. Relief granted per NRC Generic Letter 89-04. i.. d l 4.6 - Page 12 of 49 127(070891) ZD79G/122 L c r

_... _. = _. _ _... _. Revision 5 EELI.ELRfGESLVM i -DELETED-Deleted relief-request VR-7. Incorporated valves formerly covered by VR-7 Into VR-12 and VR-17. 2- ? 4.6 - Page 13 of 49 127(070891) ZD79G/123 l

. _.. _ ~ m. . _.. _ _m ..._ ~ _ _ _ __ 4 Revision 5-RELIEF 3WESLYR-1 l '. YAlyn_humhnt: ICC683 FC685 1CC9413A ..;94')A ICC9414

• CO a
• ICC9416 tet ICC9438

C, 8 1CC9486 2risso0 1CC9516 2C09518 1CC9534 2CC9534-

2.. thnhnL.nLLtum-16 3.

ASMLCode_ Cats a A, B, and C 4. ASME__Cade, Se ctinn_XLReg.uir ements : Exercise for operability: full stroke testing (St) of Category A & B v51ves! full stroke end back rinw tant ing (Ct/Bt) of Category C valves every 3 months per IW-3411 and IW-3421, respectively. 5. Danis _. Ion.RalinI: Component cooling (CC) water flow to the reactor coolant pumps is required at all times while the pumps are in operation and for an extended period of. time while in cold shutdown. Failure of one of these valves in a closed position Juring an exercise test would result in a loss of tooling flow to the RCPs'and eventual pump damage and/or trip. The RCPn also provide the necessary driving head to the prescurizer spray valves for pressure control in the RCS, while a steam bubblo exists in the pressurizer, during both power operation and reactor shutdown. 'The closure test for the 1/2CC9518 (flow to RCP thermal barrier) and 1/2CC9534 (flow to RCP motor barrier oil cooler) valves can only be verified by performing a local leakage. rate test (LLRT). The opening test is performed-in conjunction with the fill and vent of the piping following the leak test. Performing thih LLRT requires placing the system in an inopereble status, isolating that portion of piping, end connecting an external pressure supply. 6. Altninate Testing These valves will be exercised on a refueling frequency when all four RCPs are no longer. required to support plant conditions and can be removed from service. Check valves 1/2CC9486 (total CC flow to the RCPs) will be back flow tested (Dt) cle, sed. on-the same. frequency as their seat leakage test. The 1/2CC9518 and 1/2CC9534 check valves will be exercised (Ct/Bt) each refueling outage in conjunction with the associated seat leakage test. This frequency is at least once per two years, to be performed during reactor refueling outages. i 4.6 - Page 14 of 49 127(070801) . ZD79G/124-

Revision 5 RELIEF _REQUESLXR-B 7. JustificAtioDI This alternate testing will adequately maintain these portions of the CC system in a state of operational readiness, while not impacting the Safety of the plant or causing-unnecessary personnel radiation exposure or possible damage to the RCPs. The 1/2CC9518 and 1/2CC9534 check valves function only when both of the associated containment isolation valves (CIVs) are closed during an accident condition involving adverse containment conditions. Each valve opens in a manner _that will bypass the upstream isolation valve to relieve excess pressure. Back flow testing these check valves and the 1/2CC9486 check valves on the same schedule as their leak rate test will adequately maintain this portion of the CC system in a state of operational readiness without causing unnecessary personnel radiation exposure or possible damage to the RCps. During forced outages, limited manpower and resources are a"allable to perform the necessary prerequisites involved with an LLRT. Performing an LLRT to prove valve closure would only draw manpower away 5-om the task at hand, and could hamper attempts to rebtart the unit. An I ' ? requires personnel involvement from operations (valve manipulat 3sns,ud out of services), radiation protection (radiation surveys an/ moni.oring), instrument maintenance (installation of test equipmer.t), and technical staff (LLRT rig operation and test supervision) that results in increased man-rem, which conflicts with station ALARA goals and practices. For these reasons, performing an LLRT to verify valve closure is considered to be impractical during cold shutdown. In addition, performance of leakage testing on a two year (refueling) frequency is adequate to demonstrate structural integrity of valve seating capability per both Append.*x-J and ASME Section XI requirements. 8. APPil.CAhle_ lime Period: This relief is requested once per quarter during the first inspection interval. 9. APatoral_ Status a. Relief granted per NRC Generic Letter 89-04. b. Requesting additional relief for valves 1/2CC9518 and 1/2CC9534 per revision 5 submittal. 4.6 - Page 15 of 49 127(070891) ZD79G/125

4 Revision 5 RELIEF _REQUESI NE:2 1. YJtlyr_thunheit ICV 8100 2CV8100 1CV8112 2CV8112 -ICV 8113 '2r18113 2. Hymber_of Items: 6 3. ASliE__Cade_Cate.goIy : A and AC 4. ASliE_Cnde, Sestinn_KLRequirements - Exercise for operability: full stroke testing (SL) of Category A & B valves; full stroke and back flow testing (Ct/Bt) of Category C valvps every 3 months per IWV-3411 and;INV-3421, respectively. 5. Has.is_foI_EnlicI These valves cannot be tested during unit operation as seal water flow from the CV system is required continuously while the reactor coolant pumps are in operation. Failure of one of these valves in the closed-position during-an exercise test would result in seal water return flow being' diverted to the PRT by lifting a relief valve upstream of the isolation valves. The RCPs also provide the driving head to the pressurizer spray valves for pressure control in the RCS, while a steam bubble exists in the pressurizer, during both power operation and reactor shutdown. The closure test for the 1/2CV8113 (seal return pressure relief check valves) can only be verified by performing a local leakage rate test (LLRT). Performing this test requires placing the system in an inoperable status, isolating that portion of piping, and connecting an external-pressure supply. The opening test requires isolating both the inboard motor and manual isolation valves and running a centrifugal charging pump on mini-flow recirculation to supply pressure for opening the valve. The inboard manual vent is opened to verify that the check valve is capable of j' relieving pressure. 6. AlicInnteJ elting: The 1/2CV8100 and 1/2CV8112 valves will be exercised on a refueling frequency when all four RCPs are no longer required to support plant operations and can be taken out of service. The 1/2CV8113 check valves will be exercised (Ct/Bt) each refueling outage in conjunction with their associated leakage rate test. This frequency is L at least once per two years, to be performed during a reactor refueling-outage. 4.6 - Page 16 of 49 127(070891) -ZD79G/126

m Revision 5 EELIEF REQUEST VR-9 7. dualifiration This alternate testing will adequately maintain this portion of the CV system in a state of operational readiness, while not impacting the safety of the-plant or causing unnecessary personnel radiation exposure or possible damage to the RCPs. The 1/2CV8113 check valves function only when both of the associated containment isolation valves (CIVs) are closed during an accident condition involving adverse containment conditions. Each valve opens in a manner that will bypass the upstream isolation valve to relieve excess pressure. Back flow testing these check valves on the same schedule as their leak rate test will adequately maintain this portion of the CV system in a state of operational readiness without causing unnecessary personnel radiation exposure or possible damage to the RCps. During forced outages, limited manpower and resources are available to perform the necessary prerequisites involved tiith an LLRT. Performing an LLRT to prove valve closure would only draw manpower away from the task at hand, and could hamper attempts to restart the unit. An LLRT requires personnel invo.1vement from_ operations (valve manipulations and out of services), radiation protection (radiation surveys and monitoring), instrument maintenance (installation of test equipment), and technical staff (LLRT rig operation and test supervision) that results in increased man-rem, which conflicts with station ALARA goals and practices. For these reasons, performing an LLRT to verify valve closure is considered to be impractical during cold shutdown. In addition, performance of leakage testing on a two year (refueling) frequency is adequate to demonstrate structural integrity of valve seating capability per both Appendix J and ASME Section XI requirements. 8. Applicable Time Perigd: This relief is requested once per quarter during cue first inspection interval. 9. -Approval Status: Relief granted per NRC, Generic Letter 89-04. a. I b. Requesting additional relief for the 1/2CV8113 check valves per revision 5 submittal. l l 4.6 - Page 17 of 49 -127(070891) ZD79G/127

Rsvision 5 RELIELJtEQUESLVR 10 1. Valva _lhunbe r t lIA066 2IA066 IIA 065 2IA065 IIA 091 2IA091 2. ZhunbcL_QLLLPRts : 6 3. AStiLC2de_.CategoIy : A and AC 4. ASME_ fade 2 Seeti01LKLEE9uilfmeALE i Exercise for operability (St and Ft) of Category A and B valves and (Bt) of Category C valves every 3 months per IW-3411 and IW-3521. 5. Batis_foL_Eelief: Stroke testing of these valves during plant operation or cold shutdown would, by decign, isolate the air cperated instruments and valves inside the containment building. 6. AltcInn.tn._TfA Ling These valves will be exercised during refueling outages. The back flow (Bt) test for the 1/2IA091 check valves will be done in conjunction with their seat leakage test. This testing period will be each refueling outage as a minimum, but no more frequently than once per quarter. 7. lus_Lificatipn The full stroke exercising of the instrument air containment isolation valves during unit power operations or cold shutdowns, introduces the possibility of causing major operating perturbations and/or personnel safety concerns should these valves fail to re-open during testing activities. The failure of these valves in the closed position, as a result of testing activities during plant operation or cold shutdown, would subsequently isolate the air operated instruments and valves inside the containment building thus resulting in one or more of the following scenarios: A. Loss of Pressurizer Pressure Control The pressurizer spray valves 1/2RY455B & C and the pressurizer aux 111ary spray valve 1/2CV8145 would fail closed and not be available for pressurizer pressure control. 4.6 - Page 18 of 49 127(070891) ZD79G/128

Revision 5 ELIELEEGIESLYR:10 B. Loss of Chemical Volume Control System Letdown Flow (both normal and excess) and Charging Flow t The loss of instrument air would_cause a disruption in the unit letdown flow paths resulting in pressurizer level increases. Such valves as the letdown orifice containment outlet header isolation-valve 1/2CV8160, the letdown line isolation valves 1/2CV459 and 1/2CV460, the letdown orifice outlet isolation valves 1/2CV8149 A, B & C, tho ex ess letdown heat exchanger inlet isolation valves 1/2CV8153A & B, and the regen heat exchanger letdown. inlet isolation valves 1/2CV8389A & B would go to their fail closed positions. Additionally, the ability to normally make up reactor coolant inventory and adjust the reactor chemical shim (i.e. normal boration/ dilution) would also be lost as the regenerative heat exchanger inlet isolation valves 1/2CV8324A & B would fall to their respective closed positions. C. Lc e of Component Cooling to Containment Penetretions - -The_ loss of instrument air' supply would cause the penetratici. cooling supply flow control valve 1/2CC053 to go to its fail closed position. The loss of penetration cooling would result in elevated temperatures being-imposed on the penetrations being supported by the component cooling system. 4 D. Loss of Personnel Breathing Air - The11oss of instrument air supply to the service air downstream isolation valve 1/2SA033 would cause this valve to go to its fail closed position. This loss of service air in the containment building would eliminate the normal source of supplied breathing air needed to support numerous maintenance and component inspection activities in a contaminated radiological environment. 8. APPL 1CAhlm_ Time Period: This relief is requested once per quarter during the first inspection -interval. 9. Approval Statuat a. Revised (to address NRC concerns) in Byron's response to SER 12/16/88 (Byron Station Letter 88-1321). b. Requesting additional relief for check. valves 1/2IA091 regarding back flow testing. l 4.6 - Page 19 of 49 l' 127(070891) ZD79G/129

1 Revision 5 i ElldEF REOUEST Vk-11 -DELETED-Deleted relief request VR 1.. per EG&G Idaho (Technical Reviewers) recommendation to Byron. This was a request for extension of position -indication tests from every two years to every three years. i 1 J 4.6 - Page 20 of 49 127(070891) ZD79G/130

Revision 5 RELIEF _ REQUEST VR_-12 f 1. yftlyt_llumhet: Valves that normally stroke in 2 seconds or lesst YALVI t. VALYE_I 1MS018A-D 2M5018A-D 1PS228A, B -2PS228A, B 1PS229A, B 2PS229A,-B 1PS230A, B 2PS230A, B 1RC014A-D 2RC014A-D 1RY8033-2RY8033 2. IlumbeI_nLitents: 30 3. ASME._Cnde_Categnty

• A&B 4.

ASME_.csule2_Enctinn_.XLEeguirements : Verification, by trending rif power operated valve times, that an increase in stroke time of 50% or more, from the previous test,.does not occur, per IWV-3417(a). 5. Ratig_1pr Relicit-Minor timing inaccuracies, with small stroke times can lead to substantial increases (percent wise) in stroke times. For example, a valve with a stroke time of 1-second in an initial test, and 1.6 seconds in the -subsequent test, has experienced an apparent 60% increase in stroke time. If the accuracy requirements of IWV-3413(b) are utilized, it could be argued that stroke times between 1 and 2 seconds could constitute as much as a 100% increase in stroke time when, in fact, only a 0.2 second increase l occurred. For instance, if the initial time was 1.4 seconds, (measured to the nearest second is 1.0 second) and II the next time is then 1.6 seconds, (measured to the nearest second is 2.0 seconds) the percent increase is 100%. =6. AlleInata_Tas11DS

• Fast acting valves _can be defined as.those valves that normally stroke in 2-seconds or less.

No trending of stroke time will be required, and upon exceeding 2 seconds, corrective action shall be taken immediately.In accordance with INV-3417(b). 4.6 - Page 21 of 49 127(070891) ZD79G/731

Revision 5 RELIELREQUESLYR-12 7. JuGLlikcnL19Bt For'short stroke times, the trending requirements are too stringent for the accuracles specified in the Code. The alternative specified will - adequately maintain the system in a state of operational readiness, while not imposing undue hardships or sacrificing the safety of the plant.

8.. Applicable Time Perip43 This relief is requested once per quarter, during the first inspection interval.

9, ApIIDIAl_ELALMRt a. Revised (to address NRC concerns) in Byron's response to SER 12/16/88 (Byron Station Letter 88-1321), b. Re31af granted per NRC Generic Letter 89-04, t l l t l-l l l 4.6 - Page 22 of 49 127(070891) l ZD79G/132 i

Revision 5-RELIILREQUESLYR:11 1. Yalyt.R a hnf_s: 1DG5182A,B-2DG5182A,B 1DG5183A,B 2DG5183A,B 1DG5184A,B 2DG5184A,B 2DG5185A,B 2DG5185A,B ~2. Hubetal.11 ems :- .16 3. ASME_ Code _ Category:- B&C 4. ASMLCodcJinclinalLRequirementa These valves

• e not within the scope of ASME Code, Section XI, Subsection IWV requiret However, the requirements for' stroke timing and trendinglof the valves associated with the Diesel Air Start System are-being mandated by the NRC as an augmented testing requirement pursuant to 10CTR50.55 (a) (g).

Therefore, valves associated with the Diesel Air Start System shall be exercised to-the position required to fulfill their function during plant operation per INV-3412 and IWV-3522. Additionally, the stroke testing of power operated valves shall be measured to the nearest setond and such stroke times trended to document continued valve operational readiness per IWV-3413:(b) and IWV-3417. 5. Basis _LoLEellel The monthly Diesel-Generator testing program, outlined in Braidwood i Station's Technical Specifications and implemented by station operating procedures, exceeds the intent of the quarterly valve testing program -which would be required by ASME Code, Section XI. Additionally, the stroke timing of solenoid operated valves associated with the Diesel Air Start 9y item is impractical due to the f ast actuation of these valves. 6. Alternate _Tes11ng s -The performance of Braidwood 6chtlon's Diesel Generator operability monthly _ surveillance will verify 3he operational readiness of the valves associated with the Diesel Air Start System. This. surveillance testing will require the recording of the air pressures contained in-both trains A & B of the Diesel Generator Air Start Receiver Tanks both before and immediately after Piesal Generator start. By the_ comparison of'these valves between trains, the satisfactory operation of the power operated and self-actuated check valves associated with the Diesel Air Start System can be adequately demonstrated. 4.6 - Page 23 of 49 =127(070891) ZD79G/133

.. =. _ Revision 5 i RELIIL.REQUISI_YA:13 7. dLtatificatinn: Proper valve operation will be demonstrated on a monthly basis by the ~ verification of Diesel Generator air start capability.. Such verification will' compare the air pressures contained in the receiver tanks both before and'after the Diesel Generator start, thus verifying the operability of the air start control valves. The proposed testing methodology at the increased frequency satisfies the intent of the Section XI requirements without posing undue hardships or difficulties. 8. Applicable Time Perind: This relief is requested once per quarter during the first inspection interval. 9. App _Inval Status a.. Relief granted NRC Generic Letter 89-04. l l 4.6 - Page 24 of 49 127(070891) ZD79G/134

- ~ -..... -.. Rsvision 5 RELIEF _ REQUESI_YR=14 -DELETED-- Deleted relief _ request VR-14. This was a request for exemption for position indicating tests for solenoid operated valves. Alternate t.'st.ing. allowed by the ASME Code will be used instead. 1 l^ 1 I l. i: 4.6 - Page 25 of 49 127(070891) ZD79G/135

Revision 5 i EEL 1EE_BEQUEET VR-15 l 1. Yah.e_ Numhem ICVB481A, B 2CV8481A, B 1CV8546 2CV8546 3RH8705A, B 2RH8705A, B 1518815 2SI8815 ISI8818A-D 2 SIB 818A-D ISIB819A-D 2SI8819A-D 1SI8841A,B 2SI8841A,B ISIB900A-D 2SI8900A-D ISIB905A-D 2SI8905A-D ISI8949A-D 2SI8949A-D 2. Hwnler o f Vahns : 56 3. ASME__CQfle_Cale_gQ.Iy : AC 4. ASME. Code,_Siction XL_Ee_quhretnLs: Check valves that cannot be exercised during plant operation shall be specifically identified by the owner and shall be exercised to the position (s) required to fulfill their function (Ctropen; Bt= closed) during cold shutdowns per IWV-3522. 5. BAgis_fon.Re1ief The closure test for the 1/2RH8705A, B (RHR suction isolation pressure relief) check valves can only be verified by performing a local leakage rate test (LLRT). The opening test is performed in conjunction with the Illl and vent of the piping following the leak test. Performing this LLRT requires placing the system in an inoperable condition, isolating that portion of piping, and connecting an external pressure supply. Technical Specifications specifically exempt the RHR suction isolations from LLRT following flow through the valves. The full stroke exercising of check valves not stroked quarterly is required to be performed during cold shutdowns. However, the stroking of check valves 1(2)SI8815, 1(2)SI8900A-D, 1(2) SIB 949A-D, and 1(2) SIB 841A-B, associated with Emergency Core Cooling System, during cold shutdowns will induce thermal stresses on their respective reactor vessel nozzles as the Reactor Coolant System (maintained approximately 180*F) is injected with water from the Refueling Water Storage Tank (maintained approximately 65'F. This also applies to the stroking of check valves 1(2)CV8546 and 1(2)CV8481A,d because the full stroke of these check valves causes stroking of 1(2) SIB 815 and 1(2)SI8900A-D located in the full flow path. Additionally, Braidwood Station Technical Specifications require all Safety Injection Pumps and all but one Charging Pump to be inoperable during Modes 4, 5, and 6, except when the reactor vessel head is removed (the reactor head is removed only during refueling). This requirement minimizes the possibility of low temperature over pressurization (UTOP) of the Reactor Coolant System. Therefore, check valves 1(2) SIB 819A-D, 1(2)SI8905A-D, and 1(2)SI8949A-D, cannot be ful) stroke exercised during both routine and forced Mode 5 cold shutdowns, as required by IWV-3522, 4.6 - Page 26 of 49 127(070891) ZD79G/136

t<evision 5 IG1Er EEWESLVIEIL 5. Linnis_ Ion Eellet s (continued) In addition to the st roke test. exercise used to verif y operat ional tendiness of these check valves, t he act of such r.tr oking nus.e t he necessity fo Technical Specification required leak rate testing of these valves prios to unit etiticality. This testing, in conjunction with the st r oke exer cising of t hese check volves, adds approslmately one week to the durat ion of any outage and addit ional radiat ion caposure to worker s who inust connect flowmeters and dif tet ent ial pr essut e gauges directly to pl es containing radioactive f l u i d a.. i 6. A1.ttrinate TcGting: The 1/ 2 I<llB7 0 $ A, 11 check valves elll be exercised (Ct/HL) tested each refueling outogo in conjunction with their associated leakage rate tast. This frequency is at least once per in months, to be petformed during a teactor ref ueling out, age. The back flow test of these check valves can only be individually verified by performing a local leak rat e t est. Dialdwood Station's Technical Specification 3/4.4.6.2 requires toutine leak rate testing to be performed on these Fenctor Coolant System Pressure Houndary luolation (P1V) chock valves: 1. At least once per 10 months; 2. Prior to ent ering Mode 2 whenever the plant has been in cold shutdown for greater than 72 hout s or more if leakage test ing has not been performed within the previous nine months; 3. Prior in r-tArning the valve to service f ollowls.g maint enance tepair, or - -placement work on the valvol 4. Within 24 houts following valve actuation due to automatic or manual operntloa or Llow through tPo valve, except for the 1/ 2 hilB',01 A, B and 1/ NilB702 A, 11 Based on t his,5chnical Specification that ensures the structural Integrity of the'e valves, Draidwood will back flow (Dt) test. t hese check frequency. valves on the sat e The full stroke fCt) of these choca volves will be performed at each refueling outage. 7. Justification: The 1/ 2 ftil8705 A, B check valves function only when both of the associated containment isolation valves (ClVs) are closed during an accident condition involving adverse cont ainment conditions. Each valve opens in a inanner that will bypass the upstream isolation valve to telleve excess pressure. Exercising (Ct/Ht) testing these check valves on a retueling frequency will adequat<.ly maintain this por tion of t he 1111 system in a state of operational readiness without causing unnecentary perronnel radiation exposure or delays in st ar tup of t he r eactor. 4.6 - Page 27 of 49 l 127(070891) ZD790/137

Revision 5 RELIELPEWEST_Ylh15 7 Justificaticus (continued) St roke exercising (CL) of check valves l)SIBbl9A-D, 1(2)S18949A-D, and 1(2)S10905A-D can only be safely performed in Mode 6 with the Reactor Ve::sel head removed. Also, these valves cannot be !ull stroked without exceeding Technical Speelfication 3/4.5.3 requirements, which requires that all safety injection pumps be demonstrated inoperable when RCS temperatute is less than 350' F. Stroke exercising check valves 1(2)SID819A-D, 1(2)S18905A-D and 1(2)S18949A-D at least once per Reactor Ref ueling rnode of operation, will Insure compliance with Dialdwood St ation Technical Specifications and minimize the potsibility of low temperature over-pressutization of the Reactor Coolant System. It is impractical to full stroke test the 1(2)CVB481A, D, 1(2)CVB546, and 1(2)S18t15, 1(2)S18900A-D, and 1(2)S18841A, B cheek valves as it will: 1) Induce unnecessary thermal stresses to the reactor vessel nozzles, 2) Cause the necessity to perform the Technical Specification required LLRT, and 3) Inject lange quant.itles of 2000 ppm borated water into the RCS. Injecting high concentrations of borated water into the RCS would significantly impact the t ime s eguired t o restar t the teactor at t his tirne in core life, (greate than 9 months per Technical Specificat.lon 3/4.4.6.2) when boron concentration is maintained at a much lower value. To dilute the RCS boron concentsatiot., the feed and bleed piocess will greatly increase the amount of high grade water rejected from the site and could even increase the amount of radioactive elfluents dischanged to the envi t onune nt. During forced outeges, limited manpower and rescutees n!e available to pe r i o rin the necessary piernquisites involved with an LLRT. Performing an LLRT to prove valve closute would only draw manpower away from the task at hand, and could hamper attempts t o restar t t.he unit. An LLRT requires personnel involvement irom operations (valve manipulations and out of services), radiation protection (radiation surveys and monitoring), instrument maintenance (installation of test equipment), and technical statf (LLRT rig operation and test supervision) that results in increased man-rem, which conflicts with st ation ALARA goals and practices. For these reasons, performing an LLRT to verify valve closure is considered to be impractical during cold shutdown. In addition, petformance of leakage testing on a two year (tefueling) frequency Is adequate to demonstrate structural integrity of valve seating l capability per both Appendla J and ASMC Section XI requirements. B. Applic ahin_ Time _retiod : This relief la requested once per quatter during the first inspection interval. 4.6. Page 28 of 49 127'" ') h 7t' i

Revision 5 litLIEr_ ECWESLVR-15 9. AITi ova t..S t atuu t a. Revised (to addrer.n HRC conceins) in 14yr on's s erponse to SrH 12/16/90 (Dys on St ation Lett er 08-1321). b. Relief gianted per NRC Genesle Letter 89-04. c. Itequested addit ional t ellef for valves 1/2kl1070$A, D and refueling frequency for full stroke testing those check valves per revision 5 submittal. 4.6 - Page 29 of 49 127(070091) ZD79G/139

Revision 5 i RELIEr REQUEG'LYR.10 1. Valya_llumbe nt IS18811A, B 2518811A, n 2. 16abef_uLlalve n s 4 3. ASlilLIode_ Category B 4. ASli!Lfode.,_Sentic.nll_Requhements : Valves that cannot be exercised during plant operation shall be specifically identified by the owner and shall be full stroke exercised durlng cold shutdowns per IWV-3412. j 5. Bes.1a_IOLRelici The (ull stroke exercising of valves not stroked quarterly is required to-be performod dtring cold shutdowns. However, t he stroking of the Containment Sump out15c Isolation Valves, 1/2 SIB 811A,H regulres the suction of the Residual Heat Removal Pumps to be drained, thus rendering i one train of-the system inoperable. ~ For Cold Shutdown operations with the Reactor Coolant Loops filled and one train of Residual Heat Removal declared inoperable, _Draldwood Station's Technical Specifications require two steem generators with a secondary side narrow' range water level greater.than 41% (Unit 1) and greater (nan 18% (Unit 2). -However, if the cold shutdown was necessitsted by a problem requiring draining of the secondaty side of the Steam Cenerat(rs (i.e. [ tube leaks), Braidwood Station's Technical Specification 3.4.7.4.1 would preclude the testing of the containment sump outlet isslatior. valves until -such time as-the affected steam generators had been refille.d. For Cold Shutdown operations with the Reactor Coolant Loop 6 not Illied (i.e. drained down to support Reactor Vessel Incore Seal Talle, Loop Stop Valve, _ Reactor Coolant Pump _and Seal Maintenance or primary leakage), Braldwood Station's Technical Specification 3.4.1.4.2 would preclude the testing of the Containment Sump Outlet Isolation Valves as it mandates that "two residual heet removal (RHR) Loops shall be operable and at least one RHR Loop shall be in operation. 6. Alternate _Testingt Draidwood Station w411 full stroke exercise the Containment Sump Outlet Isolation Valves, 1-'2 SI 8 811 A, B during refueling outages vice cold shutdown. 4.6 - Page 30 of 49 127(070891) ZD79G/140

Revision 5 RELIEt_REQVEST_YR-16 j_ 7. Jualification: The full stroke testing _of the 1/2S18811A, B valvest in conjunction with system dralning, filling and venting of each train, accounts for an additional six days (3 days per train) of scheduling requirements and Increased radiation dose to operators and radiological control personnel. Processing of thousands of gallons of contaminated water, and subsequent required 11guld effluent discharges would also result from the draining,_ i refilling and venting of the RHR system. This time duration required to ] perfoam the surveillance testing of the Containment Swnp Outlet Isolation Valves during Cold SFutdown activities, could, as a result, cause a i violation of the action requirements for Braldwood Station's Technical Specifications 3.4.1.4,1 and 3.4.1.4.2. The violations would orrtr since these action statements require (as noted in their respective 'cet ite sections) the return of the inoperable residual heat removal It*p to service within 2 hours, li such loop was removed for surveillanc, reglang l provided the-other RHR Loop 1s operable and in operation. In addition, HRC Generic Lotter_88-17, Loss of Decay Heat Removal, highlights the consequences of a loss of RH dusing reduced Reactor Coolant System inventory (below three feet below the reactor vessel f'enge). If the operating RH pump is lost due to alr entrainment, and the other train is inoperable for the stroke test, then the " operable" train must be vented to restore decay heat removal. Under worst conditions, bolling in the core would occur in approximately 10 minutes, the core would be uncovered in approximately 30 minutes, and f uel damage would occur in approximately 1 hour. Given the apparent disparity between the Technical Specification time requirements for an inoperable RHR Loop return to service (2 hours) and the time required to perform surveillance stroke testing of the Containment-Sump Outlet Isolation valves (1 days) during Cold Shutdown, the proposed _ alternate testing frequency _of sefueling_ outage periodicity will adequately maintain the system in a state of operatJonal readiness, while not imposing undue hardships or sacrificing the safety of the plant. 1 8. Appl)RAbin Time PgI1ndt c This relief la requested once per quarter, during the first inspection interval. 9. Apprsynl_ Status a. Revised (to address NRC concerns) in Byron's response to SER 12/16/90. i 4.6 - Page 31 of 49 127(070891) ZD790/141

Revision b EELIEr_lEWESTJK:17 1. Yalve_theber s : ISx101A 2SX101A 2. IhnbetoIJelves 2 3. ASMLCude_. Category d 4. A SM E_Co de,_S es t i o nlLtcquir ement s : Stroke time and trend the stroke tin <e for power operated valves per IWV-3413 and IWV-3417. 5. Danis _for_ Relief Valves 1/2SX101A are the essential service water outlet isolation valves for the motor driven auxiliary feedwater (AT) pump lube oil coolers. These valves are cornpletely encapsulated per design (valve stem not s visible) and do not have any limit switches that can be used to trigger a change in valve stem position. TheJe valves are energised by a 'b" contact in the motor breaker closing causing the valve to close. On pun.p start, the "b" contact opens de-energising the coil causing the valve to open. These valves change position instantaneously (l.e. rapid acting) and are basically a go-no-go type, in regards to stroking. There is no practical way to accurately stroke these valves without a system modifAcation. 6. Alternate _7enLing Valves 1/2SX101A can be verified to open during each quarterly ASME surveillance of the motor driven auxillary feedwater pumpr. by observing that temperature downstream the valve chant;os when the pump star ts. This is a poultive verification of flow through the valve, which is ludicative of the valve opening. Observing that proper lube oil temperatures are maintained will also prove that the valve opens. In addition, these valves are stroked monthly during the AF pump surveillances required by Draldwood Technical Specifications. 7. dus.t.if1Intion s These valves will be stroke exercised to their required safety position each quarter during the applicable motor driven auxiliary feedwater pump ASME surveillance. Also, these velves are tested monthly for proper valve operation per Technical Specification requirements. This testing will adequately maintain the system in a state of operational readiness, while not sacrificing the safety of the plant. 8. Applicable _Ilme_l'eriodt This tellef is requested once per quarter during the first inspection intetval. 9. ApptnV A LStatus t a. Relief is being resubmitted per SER Appendix C response. 4.6 - Page 32 of 49 127(070891) ZD79G/142

y Revision 5 j RELIELEEWE!iLVlt.10 1 1. Yalyn_liumbers: 1/2818968 2. Ihnber_cLYalves 2 3. ASMC_ Code _ Category: AC 4. ASHLCodeuSectionlLhguirement: Exercise check valves to the position required to fulfill their function (Ut)= closed),' unless such oper ation la not practical during plant operation, per INV-3522. i 5. Basis _for_Relieft l These valves can only be verified closed by performing a local seat leakage test (LLRT). performing this LLRT requltes placing the system in an inoperable status (removed from service) for an extended period of time due to the need to isolate portions of the system, and connecting leak rate test equipment. The 1/2818968 valves are located insido containment in the nitrogen supply line to the RCS (SI) accumulators. This LLRT could lead to eventual problems with maintaining accumulator pressure, should any system leakage exist. 6. Alternatt_ Testing l These valves will be back-flow tested each refueling outage in conjunction with their associated leakage rate test. 7. Justificatisnt To perfo~m an LLRT on a quarterly basis would require that the nitrogen supply system be removed from service and placed in an inoperable condition, which could Impact accumulator operability. A one hour Technical Specification time clock is associated with low accumulator pressure that would require reactor shutdown. Also, quarterly testing would reo,uire a containment entry during power operation that would conflict with. station ALARA goals and practices in reducing man-rem and is .not prudent from a personnel safety standpoint. Two individuals must always enter containment together, whenever containment integrlty is required for personnel safety considerations. During forced outages, limited manpower and resources are available to perform the necessary prerequisites invv4ved with an LLRT. Performance of an LLRT to prove valve closure would only draw manpower away from the task at hand, and could hamper attempts to restart the unit. Also, if the nitrogen system is depressurleed to perfc*r the LLRT, this could cause the secumulators to depressurize (if valve leakage were to occur) creating I another activity to be performed (acewnulator nitrogen fill) prior to unit startup.. For these reasons,. performing an LLRT is considered to be impractlcal during cold shutdown. 4.6 - Page 33 of 49 127(070891) ZD79G/143-

Revision 5 RELIEr REWESLYRdB 7. Justificatiunt (continued) In addition, performance of leakage testing on a two year (refueling) frequency is adequate to demonstrate structural integrity of valve seating capobility pet both Appendix J and ASME Section XI requirements. Iloweve r, when a valve ialls to meet its leakage criterla and repairs are required which make the internals accesalble for inspection, a detailed visual luspection will be performed. The disassembled valve disc is verifled to be capable of being full stroked and is checked for binding or failure of valve internals. Only trained check valve inspectors are utillred for this examination. The results of this inspection are reviewed and evaluated by the station's Check Valve Coordinator f or any further action required. This alternate test method is sufficient to insure the operability of these volves. B. Applitchle_ Time _Pn is41 This relief 1s requested once per quarter during the first inspection interval. 9. Apprsynl_ Status a. Reller is requested per revision 5 submittal. 4.6 - Page 34 of 49 127(070891) ZD79G/144

Revision 5 RELlELREWCSLVE:19 1. YAlYn_Humbara: 1AF001A 2AF001A 1AF001B 2Ar001B 2. Number of Valyggs 4 3. ASME_ Code Cattegnry: C 4. ASMLC04L_S.cstisn_XLEcquLtement Exercise check valves to the position required to fulfill their function (open = CL; closed = BL), unless such operation is not practical during plant operation, per INV-3522. 5. Ilasis_for_ Enlimit i Per program note 12, these valves are full-stroke tested during cold shutdown in-accordance with Technical Specification 4.7.1.2.2 which ensures the operability of the Aux 111ery Feedwater flow path te each steam generator by verifying flow to each steam generator-following each cold shutdown of 30 days' prior to entering Mode 2. Testing at this frequency is sufficient to ensure operability of this system and forms the basis of this Technical Specification. Iloweve r, the closure capability of these valves cannot be verified adequately.by performing a back pressure test due to the multiple boundary isolation points. This configuration makes it impossible to assign any observed leakage to any individual valve or component using standard mass make-up or pressure decay techniques. 6. AltnInntn_ Tatting The A and B train valves are of the same design (manufacturer, size, model number, and materials of construction) and have the same service conditions, including orientation, therefore they form a sample disassembly group. Group 1 Group 2 1AF001A 2AF001A 1AF001B 2AF001B One valve from each group, on a per unit basis, will be examined each refueling outage. If the disassembled valve is not capable of being full-stroked exercised or there is binding or failure of internals, the remaining valve on the affected unit will be inspected. 4.6 - Page 35 of 49 l 127(070891) ZD79G/145

Revision 5 EEL 1Er.lECUE!iLYH 19 I 7. JustificnLion Performing a pressure test to verify closure is impractical due to the system configuration. To perform this test it would be necessary to attach a pump or some other type of pressure source to a test connection and pressurize the line containing the valve, llowever, this line also contains many potential leakage paths (valves, pump seals, and instruments). It is impossible to assign a leakage value to any specifle path using available methods of seat leakage testing. The alternate test frequency is justirlable in that removal of those valves requires that the system be taken out of service for an extended period of time. Due to Safety System Performance, Probable Risk Assessment (PRA), and availability concerns involving the Aux 111ery feedwater system those valves cannot be removed on a quarterly frequency without impacting plant safety. Maintenance history and previous inspections of these valves at both Byron and Braidwood stations has shown no evidence of degradation or physical impairments. Industry experience, an documented in NPRDS, showed no history of problems with these valves. A company wide check valve evaluation addressing the "EPRI Application Guidelines for Check Valves in Nuclear Power Plants" revealed that the location, orientation and application of these valves are not conducive to the type of wear or degradation correlated with SOER 86-03 type problems, llow eve r, they still require some level of monitoring to detect hidden problems. The alternate test method is sufficient to ensure operability of these valves and is consistent with Generic letter 89-04. 8. Appligable _ Time _EeI.10di This relief is requested once per quarter during the first inspection interval. 9. Apptcyn1_ Status: a. Relief granted per NRC Generic Letter 89-04. 4.6 - Page 36 of 49 127(070891) ZD79G/14e

l Revision 5 RELIErJIQUES1_VR:20 i I allot used at Braidwood - Dyron OtiLY* 4.6 - Page 37 of 49 l 127(070891) ZD79G/147

..._.m._ -._.._.__m .._-_.~_m. Revision 5 s RELIEE_REQUIELYR-21 i Withdrawn from Dyron's program per SER dated 09/14/90

• Not used at Braidwood - Dyron ONLY*

1 i l t i i 4.6 - Page 38 of 49 127(070891) ZD79G/148-wwe-w-g -gy,#.--w-Wes,w~+,. -py.,

Ritvisioin 5 RELIEEEERUEST_VE 22 I

• Not ur,ed at liraldwood - Dyr on ONLY*

4.6 - l' age 39 of 49 127(070891) ZD790/149

Revision 5 RELIEE_REQUESI_YR 23 J I 1. YAlyn_liumberg: 1/2PR0020, 1/2PR002il 1 3 2. Ihunkgr of Valves 1 4 3. ASMLCodelategory: AC 4. AEME_ Coded o ttiost.XLRequi f.eme nt s Exercise check valves to the position required to fulfill their function (Dt)sclosed), unless such operatlon is not practical during plant operation, per IWV-3522. 5. liasirtierJtellei These valves can only be verlfled closed by performing a focel seat leakage test (LLRT). Performing this LLRT requires placing the system in an inoperable status (removed from service) for an extended parlod of time -due'to the need to isolate portions of the system, and connecting leak rate test equipment. The 1/2PR002G, H valves are located luside containment - An-the return line of the air particulate and lodine samplers (1/2PR51J or 1/2PR$2J). [ 6. Alternate._Insilmg These valves will be back flow tested each refueling outage in conjunction with their associated leakage rate test. 7 JySLillcnLigns To perform an LLRT on a quarterly basis would require that the associated sample panel (s) be removed f rom service and placed in an inoperable condition. Alao, quarterly testing would require a containment entry during power at 8.on that would conflict with station ALARA goals and practicen in rg man-rem and is not prudent from a personnel safety standpoint. '.. as a large neutron strewn at these particular valves and hatch ;ocet3rne and two 2ndividuals must always enter containment together, wher.ever contaltunent integrity is rer.uired for personnel safety considerations. During forced outages, limited manpower and resources are available to -perform the necessary prerequisites involved with an I.LRT. Performance of an LLRT to prove valve closure would only draw manpower away from the task at hand, and could hamper attempts to restart the unit. For these reasons, performing an LLRT is-considered to be impractical during cold shutdown. In addition, parformance of leakage testing on a two year (refueling) frequency is adequate to dwmonstrate structural integrity of valve seating capability per both Appendix J and ASHC Section XI requirements. 4.6 - Page 40 of 49 127(070891) ZD79G/150 ~ -. -.. - - - -. - - -.:--.

Itevision b EELIELREWESLVR:23 7. Just.111CDtion s (continued) llowever, when a valve falls to meet its leakage criteria and repairs are required which make the internals accessible for inspection, a detailed visual inspection will be performed. The disassembled valve disc is verified to be capable of being full stroked and is checked for binding or failure of velve internals. Only trained check valve inspectors are utilized for this examination. The results of this inspection are reviewed end evaluated by the station's Check Valve Coordinator for any further action required. This alternate tast method is sufficient to insure the opesability of these valves. D. Applicable. lime _l'eriod: This relief is requested once per quarter during the first inspection Interval. 9. AppI9YA.LSLQLVG a. i<e l l e f is requested per revision 5 submittal. 4.6 - Page 41 of 49 127(070091) ZD79G/151

Revision $ ItEL11TJE0JESLVli.-24 1. Yalvel mbers: 1/2PR032 2. Ilmber_oLVn1YeS 8 2 3. ASMC__Cnde_ Category: AC 1

4. ' ASMC _ Code,_Erstion_XI_Regttir eme nt s Exercise check valves to the position required to fulfill their function I

(!!t ) = c l o sed ), unless such operation is not practical during plant operation, per INV-3522. I i 5. batis__f or_Eclief s These valves can only be verlfled closed by performing a local seat leakage test (LLRT). Performing this LLRT requires placing the nystem in an inopetable status (temoved from setylco) for an extended period of time due to the need to isolate portions of the system, and connecting Icak rate test equipment. This would make the process radiation monitor (PRM) e (1/2PR11J panel) Anoperable requiring entry into a 72 hour Technical Speelfication time clock.- The 1/2PR032 valves ate located inside containment in the return line of the process radiation monitor. 6. A11rinate_Testingt Tliese valves will be back flow tested each refueling outago in conjunction with their associated leakage rate test. 7. Justifications To perform an LLRT on a quarterly basis would require that the associated PRM be removed from service and placed in an inoperable condition. Also, quarterly testing would require a containment en try during power operation that would conflict with station ALARA goals and practices in reducing man-tem and is not prudent from a personnel safety standpoint. Two andividuals must always enter containment together, whenever containment . integrity is-tequired for personnel safety considerations. During forced outnges, limited manpower and' resources are available to pertosm the necessary preregulaltes involved with an LLRT. Performance of an LLRT to prove valve closure would only draw manpower away from the task at hand, and could hamper attempts to restart the unit. For these reasons,-performing an LLRT la considered to be impractical during cold shutdown. In addition, performance of leakage testing on a two year (refueling) frequency is adequate to demonstrate structurcl integrity of valve seating . capability per both Appendix J end AP4E Saction XI requirements. l 4.6 - Page 42 of 49 l 127(070801) ZD790/152

. - - _ ~. - - - - -.. - Rovision 5 EELIELJtEWESLYR-14 7. JustificatioJ (continued) llowever, when a valve falls to meet its leakage criteria and repairs are required which make the internals accessible for inspection, a detailed visual inspection will be performed. The disassembled valve disc is verified to be capable of being full stroked and is checked for binding or failure of valve Internals. Only trained check valve inspectors are utilized for this examination. The results of this inspection are reviewed and evaluated by the station's Check Valve Coordinator for any further action required. This alternate test method 84 sufficient to insure the operability of these valves. 8. App.11cahic Jime l e.tiod: This relief la requested once per quarter during the first inspection interval. 9. ApproyaLStaills t a. Relief is requested per revision 5 submittal. l 4.6 - Page 43 of 49 -127(070891) ZD79G/153 i

Ravlsion 5 REldELEE0DESI_YRJ$ i 1. YalymJiumhetsi ' 1/2PS231A, 1/2PS231B 2. Number _si_Yalvent 4 3. ASME_.Cs.dclategory: AC 4. ASH E_Co de2_Hentio n_Kl_Re quirement Exercise check valves to the position required to fulfill their function (Bt)= closed), unless.such operation is not practical during plant operation, per INV-3522.. 5. Datin lor Relief 'These valves can only be verified closed by performing a local seat leakage test-(LLRT). Performing this LLRT requires placing the systtm in an inoperable status (removed from service) for an extended period of time due to the ne6d to isolate portions of the system, and connecting leak -rate test equipment. This would make the hydrogen monitor inoperable. The 1/2PR231A, D-valves are located inside containment in the return line of the hydrogen monitors. 6. AlternatiLInsting These valves will be back flow tested each refueling outage in conjunction with their associated leakage rate test. 7. Justificatio.D To perform an LLRT on a quarterly basis would require that the associated hydrogen monitor-be removed from service and placed in an inoperable condition. This is in conflict with Technical Specification 3/4.6.3.2, which requires the hydrogen monitors to be in the standby mode to meet the requirements' set forth in NUREG 0737, Item II.F.1.6 in Modes 1 and 2. Also,. quarterly testing would require a containment entry and climbing in

the penetration areas during power operation and would conflict with station ALARA goals and practices in. reducing man-rem and is'not prudent from a personnel safety standpoint. Two individuals must always enter containment together, whenever containment integrity is required for

-personnel safety considerations. F -During forced outages, 11mited manpower and-resources are available to perform the necessary prerequisites involved with an LLRT. Performance of an LLRT to prove. valve closure would only draw manpower away from the task at hand, and could' hamper attempts to restart the unit. For these reasons, performing an LLRT-is considered to be impractical during cold shutdown. 4.6 - Page 44 of 49 127(070891) ZD79G/154

Rovision b RELIELIGOVESTJR-25 4 7. Justificittlons (continued) i In addition, performance of leakage testing on a two year (refueling) l frequency is adequate to demonstrate structural Integrity of valve seating capebility per both Appendix J and ASMf: Section XI requirements. Ilowever, when a valve falls to meet its leakage critetla and repairs are required which make the internals accessible for inspection, a detailed visual inspection will be performed. The disassembled valve disc is verified to be capable of being full stroked and is checked for bipSing or failure of valve internals. Only trained check valve inspectors are utilized for this examination. The resulte of this inspection are reviewed and evaluated by the station's Chsck Valve Coordinat.or for any further action required. This alternate test method is sufficient to insure the operability of these valves. 8. Appli. cable _ Time _Eeriod: This tellef is reqvssted once per quart.et during the first inspection interval. 9. AppIMALS.tatus I a. Reller is requested per revision 5 submittal. (- l I l 4.6 - Page 45 of 49 127(070891) ZD790/155 -..---.-..a.

Revision 5 RELIELREQUESLVR-20 1. ValytJ{nmbets: 1/2RY8046, 1/2RYB047 2. Hwtbe t_of_Yalve s : 4 3. MMLCde._ Category : AC 4. MMLCdn_Sention3LRequirement s Exercise check valves to the position required to fulfill their function (BL)= closed), unless.such operation is not practical during plant operation, per INV-3522. 5. Basia_ Lot _Rellet s These valves can only be verified c osed by performing a local seat leakage test (LLRT). Performing this LLRT requires placing the system in an inoperable status (removed from service) for an extended period of time due to the need to isolate portions of the system, and connecting leak rate test equipment. The 1/2RY8046 valve is located inside containment in the' primary water (PW) line to the Pressure Relief Tank (PRT) and the Reactor Coolant Pump (RCP) number three seal standpipes. The 1/2RY8047 valve is also inside containment in the nitrogen supply line to the PRT. This will directly impact the PRTs ability to condense any steam discharged frem the pressurizer (PZR) safety valves in order to maintain acceptable pressure inside the tank. 6. Alternate Teating: These valves will be back flow tested each refueling outage in conjunction with their associated leakage rate test. 7 JMSLLLLC&LL9nt To perform an LLRT on a quarterly basis would require that both the nitrogen and PW systems be removed from service and placed in an inoperable condition and would directly impact the operability of the PRT. The nitrogen is'used for purging and venting of hydrogen which comes from the reactor coolant, while the primary water is used to control pressure in the PRT in. case of an over-pressure condition in the RCS -(safety valve or PORV lifting). Also, quarterly testing would require a containment entry during power operation that would conflict with station ALARA-goals and practices in reducing man-rem and is not prudent from a personnel safety standpoint. Two individuals must always enter containment together, whenever containment integrity is required for personnel safety considerations. During forced outages,-Ilmited manpower and resources are available to perform the necessary prerequisites involved with an LLRT. Performance of an LLRT to prove valve closure would only draw manpower away from the task at hand, and could hamper attempts to restart the unit. For these re asons, performing an LLRT is considered to be impractical during cold shutdown. 4.6 - Page 46 of 49 127(070891) j, ZD79G/156 L

Revision 5 14LIELREWEST_YR:20 i 7. Als1111cALipn (continued) In addition, performance of leakage testing on a two year (refueling) frequency is adequate to demonstrate structural Integrity of valve seating capability per both Appendix J and ASME Section XI requirements. Itowever, when a valve falls to meet its leakage criteria and repairs are required which make the internals accessible for inspection, a detailed visual inspectlen will be performed. The disassembled valve disc is verlfled to be capable of being full stroked and is checked for binding or failure of valve internals. Only trained check valve inspectors are utilized for this examination. The results of this inspection are reviewed and evaluated by the station's Check Valve Coordinator for any further action required. This alternate test method is sufficient to insure the operability of these valves. 8. Applicable _limethLlod This relief la requested once per quartet during the first inspection Interval. 9. AppIR_YAl_Slatus t Relief is requested per revision 5 submittal. a. 4.6 - Page 47 of 49 127(070891) ZD79G/157

1 Revision 5 EELIEE_fl00ECLY1t-21 1. Valyt.Jhunbers: 1/2WOOO7A, 1/2WOOO7D

2. - Humber_st.Ynive s :

4 3. AStiLC9de_. Category s. AC i 4. A SH LCs den.S estin1LXLRe quir eme nt : Exercise check valves to the position required to fulfill their function (Bt)= closed), unless such operation is not practical during plant operation, per IMV-3522. 5. Dasis_inr_Relleit These valves.can only be verified closed by performing a local seat leakage test (LLRT). Performing this LLRT requires placing the system in an inoperable status (removed from servfto) for an extended period of time due to the need to isolate portions of he system, and connecting leak rate test eq'alpment. This particular LLRT test procedure requires approximately 3 days per valve to complete. It usually takes two days to drain the system and another day to Illi and vent the isolated portions of piping. The 1/2WOOO7A, B valves are located inside containment in the supply lines to the RCrc chilled water coils. 7 6. AlternateJerdingt These valves will be back flow tested each refueling outage in conjunction with their associated leakage rate test. 7. ~ JusklLksnLlen To perform an LLRT on a quarterly basis would require that the containmen~- chilled water (WO) system be removed from service and placed in an inoperable condition for an extended period of-time. It is impractical to perform this test during power operation because the WO system is needed during the-summer months to keep containment temperatures below 120 *r. This.la based on the environmental qualification of components inside containment.- Also, quarterly testing would involve containment entries during power operation that would conflict with station ALARA goals and l practices in reducing man-rem and is not prudent from a personnel safety standpoint. Two individuals must always enter containment together, whenever containment lutegrity is requited for personnel safety considerations. During forced outages, limited manpower and resources are available to perform the necessary prerequisites involved with an LLRT. Performance of an_LLRT to prove valve closure would only draw manpower away from the task at hand, and could hamper attempts to restart the unit. For these reasons, performing an LLRT la considered to be impractical during cold shutdown. 4.6 - page 48 of 49 127(070891) - ZD790/158 +--,--e. - - - ~-n,. -. + -w.w--- ,n- ,..-,e,,y--w. ,nn-,-,,w.. , r ..=ne--,

povision 5 RELI.ErJEQt!ESI_YL21 7. aluRL111cittlons (continued) In addition, performance of leakage testing on a two year (refueling) frequency is adequate to demonstrate structural integrity of valve seating capability por both Appendix J and ASME Section XI requirements. llowever, when a valve f alls to meet its leakage criteria and repairs are required which make tho internals accessible for inspection, a detailed i visual inspection will be performed. The disassembled valve disc is verlfled to be capable of being full stroked and is checked for binding or failure of valve internals. Only trained check valve inspectors are utilized for this examination. The resu?ts of this inspection are reviewed and evaluated by the station's Check Valve Coordinator for any further action required. This alternate test method la sufficient te insure the operability of these valves. 8. Arnl.icable_Ilme_ Period e This tellet is requested once per quarter during the first inspection interval. 9. Approval 3 tutus + f<ellef is requested per revision 5 submittal. a. t 4.6 - page 49 of 49 127(070891) 'ZD79G/159 . c a.... ... -... _ _ _ _ _. ~ _. _., _ _.., _, ,-_..__.._....;._-._.__-_-._.}}