ML20125B698: Difference between revisions
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| number = ML20125B698 | | number = ML20125B698 | ||
| issue date = 12/10/1979 | | issue date = 12/10/1979 | ||
| title = Submits Info Requested by NRC | | title = Submits Info Requested by NRC Re Inservice Insp & Inservice Testing Program.Resolves & Documents Licensee Open Items | ||
| author name = Mattimoe J | | author name = Mattimoe J | ||
| author affiliation = SACRAMENTO MUNICIPAL UTILITY DISTRICT | | author affiliation = SACRAMENTO MUNICIPAL UTILITY DISTRICT | ||
| Line 11: | Line 11: | ||
| contact person = | | contact person = | ||
| document report number = NUDOCS 7912270246 | | document report number = NUDOCS 7912270246 | ||
| title reference date = 10-17-1979 | |||
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC | | document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC | ||
| page count = 48 | | page count = 48 | ||
Latest revision as of 22:25, 22 September 2022
| ML20125B698 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 12/10/1979 |
| From: | Mattimoe J SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | Reid R Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7912270246 | |
| Download: ML20125B698 (48) | |
Text
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e~~suun SACRAMENTO MUNICIPAL UTILITY DISTRICT O 6201 S S 95813, (916) 452 3211 i December 10, 1979 Mr. Robe r t W. Reid, Chief Operating Reactors Branch d4 Division o f Ope rating Reactors C. S. Nuclear Regulatorv Commission Washington D. C. 20555 Re: Rancho Seco Nuclear Generating Station ISI/IST Program. Reid le t t e r to Mat t imoe ,
, , . . . i Cated L .ll L ! i I c,* e
Dear 'tr. Reid:
' r the . uert . : cur le t t e r o f .'etaber 17, 20'?. picase
- nd .ncic e .cr a1 Jacumentation of cur m iraion- eith stat an Oct uer ' and .. 9 rtya r a in g mec; f ica t :an - to our 15!,IFT Program. Questica numbera correspond to : .:o se subnitted to us en Septercer 21, 1979, b" Mr. Dan :;arner and included as Enclosure _.
The actual ee 4 7 "ot : :a"e been ncluded as Enclosure 3. Licensee open items have been resolved and are documented in this letter. If mu : ave anc questions. -lease feel free to con-tact '! r . 2i11 ^ar: :t 0: -" "taft at 22n c e. eco. Re spc.c t f ull:. submitted,
/ se %=.%-(
/J . A . Ma t t imoe ,
Assistant General Manager and Chief Engineer l JJ'!: b ks Enclosures 90005061 i D C D\ e\ 7912270 d b O
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3 ., -
, c VALVE TESTING PROGRAM A. MAKE UP/HIGH PRESSURE INJECTION
- 1. Question: Does any normal makeup flow exist through valves SIM036 (M521/G5) and SIM037 (M521/G2)?
Discussion: Normal RCS makeup flow of approximately 60 gpm exists through these valves during normal power operation. SIM036 and SIM037 are partial stroke exercised (closed - then open) quarterly during full stroke exercising of SFV23604, Pressuriser Level Control Iso (M521/F6). No verification of stroking of SI:1036 or SIM037 is made due to inaccessibility of the valves during power oper-ation. These valves cannot be full stroke exercised open (the safety features position) during power operation because the only available flow path to utilize for testing is cennected to the RCS. Design flow of 500 gpm cannot be achieved by the centrifugal type Make Up/High Pressure Injection Pumps when pumping into the RCS during pcwer ope rat io n. These valves cannot be full stroke exercised dur;na Colc Shutdoun because power to the Make Up/High Pressure In-jection Pumps and Safety Features Valves must re.Tain racked out to provide low temperature over pressure pro-tection. These valves will be full stroke exercised during Refuel-ina Outages. SIM049, SIM050, SIM047, SIM041, SIM040 and HV23dO1 (M5 l/J2/J2/J5/F2/F5,J5, respectively) cannot be full ) stroke exercised during power operation because the only ) available flow path to utilize for testing is connected to the RCS. Design flow of 500 gpm cannot be achieved by the centrifugal type Make Up/High Pressure Injection l Pumps when pumping into the RCS during power operation. l l These valves cannot be full stroke exercised during Cold Shutdown because power to the >bke Up/High Pressure In-jection Pumps and Safet:. Features Valves must be racked out to n rovide low temperature over pressure nrotection. These valves will be full stroke exercised during Refuel-ing Outages. Request for Relief Number PV1 will be revised to reflect the above comments and resubmitted. l 1 90005062 l On. ,g
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- 2. Question: 'n'ha t is the safety related function of valves SFV22005 (M521/B2), SFV22006 (M521/C2) and SFV22025 (M521/B1)?
Discussion: The valves listed above close on safety features actua-tion to provide RCS isolation. SFV22005 and SFV22006 will be full stroke exercised quarterly (no program change or relief required). SFV22023 (M521/B5), SFV22009 (M321/B6) and SFV22025 (M321/31) cannot be full stroke exercised quarterly because our ability to maintain pressuricer level con-trol would be compromised if any of the valves failed to reopen after being stroked closed during power oper-ation. These valves will be full stroke exercised at Cold Shut-down. A new request for relief will be submitted for these valves and the Valve Testing Program changed accordingly.
- 3. Ccmment: All valves list ed in the program as Categorv B/E should be recategoriced c.
D i s c u s -iion : Sives currr: liste d u Category 3/1 in the 'a l v e Testing Frr_ s, stil ccatc ori . E enca ,t ar-
- >therwiu '
n; in .hi- letta Question: Are SIM07: (M521/IV), SIM079 (M321/G9) and SIMOS1 (M321/F9) safat: related? Discussion: The valves listed are located in recirculation lines and are necessar" - ' mn for rat ricn of :De 'an c High Pru wure Inj at.cn Pumss. Tc.e s e calves are not oafety related as tecirculation is not neces 4a rv during igh pressure injectien. (Note the SFV234 5 (M5.'l/D7) and SFV2366 (M521/ET) clase on safet; features actua-tion. SIM073, SIM079, and SIMCS1 will be removed from the Valve Testing Program.
- 5. Question: How are check valves SIM045 (M521/JS), SIM058 (M521/Gd) and SIM002 (M521/HS) full stroke tested quarterly' Discussion: These valvee are not full strake te s ted qua r terl:. :ecaust during power operation, the oni) available flow path to utilice for testing is connected to the RCS. Design flow of 500 gpm cannot be achiaved by the centrifugal Make Up/
High Pressure Injection Pumps when pumping into the RCS during power operation. These valves cannot be full stroke exercised during Cold Shutdown because power to the Make Up/High Pressure In-jection Pumps and Safety Features Valves must be racked out to provide low temperature over pressure protection. These valves will be partial stroke exercised quarterly and full stroke exercised at refueling cutages. A Re-quest for Relief to this effect will be submitted. 90005063
- 6. Question: Why will the consequences listed in Relief Request PV4 occur?
Discussion: These valves, listed in PV4, are required to be open during power operation for normal operation of the Seal Return System. Reactor Coolant Pump operation with no seal return may cause an imbalance of stage pressures and subsequently loss of stage flow. This would result in degradation of seall..s capability. I Relief Request PV4 will be rewritten and submitted to reflect the statements outlined above.
- 7. Question: What is the flow path utilized to full stroke exercise SIM052 (M521/F10), BWSO44 (M321/Gil), BWS019 (M521/Il0) and SIM043 (M521/Jll)?
Discussion: The flow path utilized for testing these valves is through the MU/HPI Pumps to the RCS or Make Up Tank. Exercising these valves during power operation would cause highly con-centrated Boric acid to be injected into the RCS through the Pressurizer Level Control Valve and RCP seals. This would cause unwanted changes in RCS Baron concentration and could result in power transientis. These valves cannot be full stroke exercised during Cold Shutdown because power to the Make 'Jp/High Pressure in-jection Fumps and Safet' Features Valves must remain racked out to provide cold over pressure protection. These valves will be full stroke exercised during refuel-ing outages. PV5 will be revised to reflect the preceed-ing comments and resubmitted.
- 3. Question: Is PLSO44 (M521/G12) safety rela ed?
Discussion: PLSO44 is not safety related. It is used for backflow / l pressure prevention and as a maintenance valve. This ] valve will be removec from the program. '
- 3. DECAY HEAT / CORE FLOOD l
- 1. Cc= ment: IF DHS015 (M522/D7) is Category A/C/E, a leak test must be perfo rmed.
Discussion: An Appendix J Leakage Test is perfermed on this v 1ve.
- 2. Question: How are valves RC5001 (M522/D7), RCS002 (M322/D9), CFS001 (M522/D7) and CFS002 (M322/D9) full stroke exercised?
Discussion: These valves are incorrectly listed in the Valve Testing Program Tabulation as Category A/C. They should be Cate-gory C only. In addition, these valves are listed as being full stroke exercised during each Cold Shutdown. The valves are partial stroked only at Cold Shutdown and Refueling. l 900050A4 l 3 i
B.2 Discussion (Continued) Consideration of verification of disc movement will be made during Refueling Outages by the method shown in Enclosure 1. It should be noted that this was a " License Open Item" following the ISI/IST review meeting.
- 3. Question: Can Valve HV26011 (M322/E10) be exercised during power operation without over pressuricing the low pressure Decay Heat System?
Discussion: Isolation between the Decay Heat System and the RCS (SIM050, M521/J2), the Pressuricer (DHS059, M522/E10) and the High Pressure Injection Pumps (HV23302 and SFV23810, M321/J4 and J5) currently exists. However, since there is the possibility that leakage by or fail-ure of the valves listed above can occur, HV260ll will be full stroke exercised only during Cold Shutdowns and Refueling Outages.
- 4. question: Are valves HV26106 (M522 / F13) and HV20105 (M322/F13) tested in the direction required by Appendix J7 Discussion: ies. Blank flanges eith zalves are placed in the Emergenc- samn and the valves are tested in :ne
" correct" direction. No change is requirec in the program originally submitted.
- 5. Question: How are check valves DHS003 (M522/J9), DHS004 (M522/Il0),
DHS007 (M522/HS) and DHS005 (M522/H9) full stroke tested q ua rt e rly ? Discus s ion : The valves listed are Decay Heat Pump Suction (DHSn03 and DHS004) and Discharge (DHS007 and DHS005) Check Valves. The Decay Heat ?umas are full flow tested quarterly by SP 203.0;A ("A" Leop) and SP 203.053 ("3" Loop), Quarterly Decay Heat Removal Pump P-261A(3) Surveillance and Inservice Test. DHS007 and DHS000 are full stroke exercised during the pump tests and no change is required in the program originally submitted. DHS003 and DHS004 will be tested as outlined in 3.6 below.
- 6. Question: How are Check Valves BW5003 (M522/G4) and BWS004 (M522/G4) full stroke exercised?
Discussion: 3WS003, SWS004, DH3003, and DHS004 are not full stroke exercised quarterly. : the accident condition, these valves must pass a tr'ai af 4500 gpm (3000 gpm to Decay Heat and 1500 gpm :: xeactor Building Spray). This flow cannot be achieved during power operation. The valves cannot be fully stroked during Cold Shutdown, because the Borated Water Storage Tank is isolated and because 4 90005065
B.6 Discussion (Continued) Decay Heat Suction Valves from the Reactor Vessel are open and must remain open to provide decay heat removal. Therefore, a Request for Relief will be submitted to allow partial stroke testing quarterly with full stroke testing at refueling. It should be noted that this was a " License Open Item" following the ISI/IST Review.
- 7. Question: What are the saf ety f unctions of DHS057 (M522/I8) and DHS058 (M522/I8)?
Discussion: DHS057 and DHS058 provide backflow prevention f rom the Decay Heat System to the Spent Fuel Cooling System. They are contained in lines which cross tie the Decay Heat System with the Spent Fuel Cooling System for the purpose of providing spent fuel cooling with the Decay Heat System should the Spent Fuel Cooling System be inoperable. The valves must open to provide this func-tion. Therefore, OHS 057 and DHS058 will be full stroke tested quarterly. It should be noted that this con-trasts alth the meeting notes *nich stated that these valves will be removed from the IST Program. S. Question: What is the safety related function of HV20003 (M322/D13)? Discussion: HV20003 provides a means of recirculation of Reactor Coolant following a RCS cold leg break to prevent Baron precipitation during long term cooling. Exercising HV20003 eithout closing DHS461 (M322/E13), which is inaccessible during power operation, would introduce voids to Decay Heat Pump suction piping. These voids would cause water hammering and pump cavitation which could result in significant pipe, pipe support, and pump damage. This clarification will be added to Re-lief Request PV10. No changes to the Valve Testing Requirements Table are necessary.
- 9. Question: What are the safety functions of DHS 038 (>622/E9) and DHS039 (M522/E7)?
Discussion: These valves provide containment isolation. Accordingly, a Seat Leakage Test (SLIJ) will be performed on the valves during Local Leak Rate Testing recoired by SP 205.02, Local Component Leak Rate Su /eillance Test-ing, for Penetrations 27 (DHS039) and 23 (DHS038). It should be noted that this conflicts with the meeting notes. 5 900050A6
B. 9 Discussion (Continued) Further, to maintain consistency in the program, the philosophy of categorizing any valve which provides a containment isolation function as an "A" valve will be introduced with SLTJ Tests specified per SP 205.01, Reactor Building Integrated Leakage Rate Test, and SP 2C5.02, Local Component Leak Rate Surveillance Testing. A generic Relief Request will be submitted per staff's suggestion.
- 10. Question: What are the safety related functions of the valves listed below? Should they be categorized A/E?
CFS003 (M522/C3) CFS004 (M322/C3) CFS005 (M522/A4) CFS006 (M322/A4) CFS009 (M522/B4) CFS010 (M322/34) CFS0ll (M522/B4) CFS012 (M522/B4) Discussion: All valves listed provide a containment isolation function and will be recategorized A/E with SLT T Testing specified as outlined in Item B.9 above. A Request for Relief from tarterly exercising these manual passive valves 'elll be submitted.
- 11. Question: What are the safety related functions of HV26513 (M522/D6) and HV26514 (M522/D10)?
Discussion: HV26513 and HV26514 are normally open valves whose power is racked out. Operating Procedure B.2, Plant Heatup and Startup, verifies the valves open and the power racked cut. Positian indication is displayed in the Control , Room continuously. These valves are not safety related and need not be included in the IST Program. No program change is required. , 1 C SPENT FUEL COOLING
- 1. Question: Do SFC500 (M523/D7) and SFC501 (M523/D7) perform a con-tainment isolation function?
Discussion: No. These valves will not be included in the IST Program. No program change is required. D. CCNTAINMENT BUILDING SPRAY
- 1. Request: Provide more detailed information on how CBS009 (M324/D7) and CBS010 (M524/DS) are full stroke exercised.
Discussion: CBS009 and CBS010 cannot be full stroke tested. No stroking can be performed quarterly because entry to areas inaccessible during power operation in the Con-tainment Building would be required. Precautiens , l 90005067 s
D.1 Discussion (Continued) required to be taken to preclude spraying down the Containment Building are too involved to be performed during a normal Cold Shutdown. These valves will be partial stroke exerc ised during Ref ueling. PV11 will be rewritten with the clarifications from above.
- 2. Question: What alternate tests have been considered for satisfying the exercising requirements for the valves listed below?
CB5021 (M324/H6) CBS022 (M524/H9) CBS027 (M524/H6) CBSO23 (M524/H9) HV29015 (M324/H6) HV29016 (M324/H9) Discussion: This item was left as a " Licensee Open Item" following the meeting. Full stroke testing these valves is not possible due to introduction of NaOH solution to the Decay Heat System. Consideration is being given to partial draining the Reactor Building Spray Additive Tanks through the listed valves and CSSO43 (M324/Hn) and C35044 (M324/H9) and monitoring level instrumentation for flew verification.
- 3. Question: What is the safety related function of CSS 031 (M321/I9) and CBS032 (M524/I9)?
Discussion: These valves provide isolation between redundant lines which provide Na0H to Decay Heat Pump suction for pest accident pH adjustment and as such are saf ety related valves and will be added to the IST Program. In addition, the valves listed below vill be added to the Program. CBS029 (M524/H7) C35033 (M524/Il0) CBS035 (M322/Il0) C35030 (M324/H9) CBS034 (M524/H10) CBS036 (M522/JS) Relief will be requested for stroking CBS035 and CB5036.
- 4. Comment: CBS504 (M524/G12) and CSS 503 (M524/G5) will require relief from quarterly stroking as they are Categorv C Check Valves.
Discussion: PV13 sill be rewritten to request relief ac outlined above. E. MAIN STEAM / FEEDWATER/ AUXILIARY FEEDWATER
- 1. Question: Should PV20564 (M530/J7) and Pv20566 (M330/I7) be categor-ized "B" rathe r than "C"?
Discussion: Yes. Valve Testing Requirement will be changed. No relief is required. 7 90005068
I
- 2. Question: Why are PV20562A, B and C (M530/J8 and 19) categorized B/C rather than B?
D13cussion: The valves listed above were incorrectly shown as Category B/C. Valve Testing Requirements will be changed to show them as Category B only. No program relief is required.
- 3. Question: Why can't TV1, 2, 3 and 4 (M330/D5 and F5) be " tripped" for timing during Cold Shutdown?
Discussion: TV1, 2, 3 and 4 will be full stroke exercised (slowly) quarterly. A Trip Test will be performed during Startup following Cold Shutdowns. Timing will be performed dur-ing the Trip Test only. A maximum time acceptance criteria will be determined. PV14 will be rewritten to incorporate the above comments.
- 4. Request: Review the safety related function of the valves listed below to determine if they should be included in the IST Program.
MSS 007 (M530/H7) MS5003 (M530/17) MSS 009 (M530/G7) MSS 010 (M330/J7) MSS 013 Ci331/H7) MS3014 Ci330/d7) M33015 (M330/J7) MSS 016 (M530/I7) MSS 017 (M530/J10) Discussion: All valves listed are maintenance valves whose position is verified in Operating Procedure B.2, Plant Heatup and Startup. prior to power operation. These valves .d ll no t be included in the IST Program. ::o program change is necessary.
- 5. Question: Is F.iS120 (:1532/B4) locked in the open position?
Discussion: Yes. FWS119 (M532/G4) is also locked open. Soth will be categorized as "E" valves and tested accordingly.
- 6. Request: Provide a more technical basis fcr PV16 and PV17. Discuss more fully the adverse effects of exercising the valves listed during power operation.
Discussion: Full stroke exercising the valves listed would secure feedwater flow to each steam generator, which would cause a reactor trip. The valves will be full stroke tested during Cold Shutdowns. PV16 and PV17 will be rewritten to reflect the above co=ments. No change in testing re-quirements is necessary.
- 7. Question: What is the safety related functien of FW5050 (M532/J7)?
i Discussion: FWSOSO has no safety function. HV20611 (M532/J6) satisfies Criteria 37 of 10CFR50 for Containment Isolation. FW5060 will be removed from the program. It should be noted that this resolution differs from that of the IST Program Review, s 90005069
E.7 Discussion (Continued) 1 In addition, FWS101 (M532/F6) and FWS102 (MS32/F7) will ' be added to the IST Program as Category A/E valves. SLTJ Tests per Sp 205.01, Reactor Building Integrated Leakage Test, will be specified. Relief from exercising these manual passive valves will be requested.
- 8. Question: How are FWSO47 (M533/F4) and FWSO48 (>$33/G4) full stroke tested quarterly?
Discussion: These valves were incorrectly listed in the Valve Testing Requirements as being stroked quarterly. These valves will be full stroke exercised on a Cold Shutdown frequency and will be added to Relief Request PV15. F. MAIN CONDENSATE AND MAKEUP
- 1. Question: How are MCM059 (M536/I2) and MCM060 (M536/I2) full stroke exercised quarterly
Discussion: These valves are part stroke exercised during quarterly testing of Auxiliary Feedwater Pumps P313 and ?319 in a low flow recirculation mode. They will be full stroke tested during Cold Shutdown when full flow OTSG Injection Tests are conducted. G. AC7ILIARY 3 TEAM
- 1. Request: Review the safety related function of ASC048 (M337/H13) and ASC049 (M537/H13) to dete rmine if they should be categorized A/E and A/C respectively.
Di sc us s ion : ASC048 will be categorized A/F and relief requested from e::ercising since it is a manual passive locked closed valve. ASC049 will be categorized A/C/E and relief requested from exercising since it is a manual passive locked closed stop check valve. Both valves will have an SLTJ type test speci-fled per Sp 205.01, Reactor Building Integrated Leakage Rate Test. H. COMPONENT COOLING WATER
- 1. Comment: Containment Building Isolation Valves must be categorized A or A/C as applicable.
Discussion: The valves listed below will be categorized as shown below. Catecory A: 1 SFVa6014 (M543/F10) SFV46203 (M543/F10) SFV46204 (M543/F10) SFV46906 (M543/Cl3) SFV46907 (M543/B13) SFV46903 (M543/C13) Categon/ A/C: CCWO3o (M543/E10) CCW194 (>$43/313) I 90005070 l 9 l !
H.1 Discussion (Continued) SLTJ tests will be specified per SP205.01, Reactor Building Integrated Leakage Rate Test. PV18 requests relief from quarterly exercising and contains sufficient support inf o rma t ion. I. NUCLEAR SERVICE RAW WATER / NUCLEAR SERVICE COOLING WATER
- 1. Question: Should valves NRW001 (M544/I9), NRWOO3 (M544/G10) and NSWO86 (M545/G7) be categorized E rather than B7 Discussion: NRW001 and NRWOO3 will be categorized E.
NSWO86 will be categorized E and maintained in the program.
- 2. Question: What are the safety functions of NRWO41 (M544/C4) and NRWO42 (M544/C9)?
Discussion: NRWO41 and NRWO42 provide the capability to conserve water in the spray ponds by alternately running in the spray and by-pass modes. This f unction would be required in the event the ability to make up to the spray ponds has been lost. These valces will be added to the IST Program as Category 3 valves. No reliet for testing requirements is necessarv. J. HEATING AND VENTILATION
- 1. Question: Would failure of the valves listed below in a nonconserva-tive position during power operation place the plant in an unsafe condition?
SFV53504 (M551/E10) SFV53503 (M551/ Ell) SFV53605 (M551/F10) SEV53604 (M551/Fil) Discussion: Failure of a single valve on a penetration will not place the plant in an unsafe condition because the redundant penetration isolation valve will provide containment in-tegrity. When this is considered in light of the fact that these valves are normally closed and would therefore , be passive components during an accident condition, the ! staff suggestion that relief be recuested from quarterly exercise and timing seems reasonable. However, we have the ability to purge during power opera- ) tion. To accomplish this, both valves on each penetration l must be open. During an accident condition , the valves I would be required to stroke closed to provide containment l integrity and therefore are active components. For purposes of testing, these valves will be considered active components and contrary to staf f's suggestion, no i relief from exercise / timing requirements will be requested. 1 l 2. Question: Are HGS 013 (M551/Il2) and HGS 012 (M551/Il2) safety related? 90005071
l l i Discussion: These valves provide isolation of the Containment Building from the ILRT Test Cart and, as such, are manual, passive, normally l closed containment isolation. valves. Therefore, they will be cate-I gorized A/E with relief requested from leakage testing and stroking requirements.
- 3. Question: Should the valves listed below be included in the IST Program?
HGS 004 (M551/Gil) , HGS 005 (M551/Gil) l HGS 010 (M551/Fil) ) HGS 0ll (M551/Fil) l Discussion: Operating Procedure A.56, Hydrogen Purge System, stipulates I that manual valves HGS 005 and HGS 010 be normally open during ) post accident hydrogen purging as protection against drawing a vacuum on the Containment Building (in which case check m1ves HGS 004 and HGS 0ll would open) . A.56 also allows
'wration of the Hydrogen Purge System with HGS 005 and iiuS010 closed during periods when accurate monitoring of ex-haust radiation level is desired (with monitoring of contain-ment pressure to assure a vacuum is not drawn). Therefore, these valves are not functionally safety related and will not be strokec. MGS005 and HGS 010 will be categorized as A valves and a Request for Relief will be submitted for stroking requirements. SLTJ Tests will be specified per ;
S?205.J1, Reactor Ouilding Intcgrated Leakage Rate Test. 1 l K. R\DWASTE SYSTEM j I
- 1. Question: Are leak tests performed on SFV60003 (M560/I2) or SEV66303 (M561/31)? ;
Discussion: These valves are leakage tested in accordance with require- I ments of SP205.02, I , cal Component Leak Rate Surveillance Test. Valve testing requirements will be amended. L. CHEMICAL ADDITION AND SAMPLING
- 1. Question: Is SFV20092 listed in the IST Program actually SFV70002 (M570/C3) as shown on PSID M570?
Discussion: Yes. The Valve Testing Requirements Table will be corrected. 2 Question: Are the valves below safety related and as such should they be included in the IST Program? 3WS038 (M570/J6) BWS039 (M370/I6) BWS035 (M570/I8) l BWS036 (M570/J9) l 90005072 300RORB.M 11
Discussion: All valves listed above, except BWSO40 and 3WS054, are normally closed maintenance valves and as such will not be included in the IST Program. VWSO40 and BWivj4 are safety related and will be included in the IST Program. In addition, BWSO41 (M570/J5) and BWS045 (M322/G12) will be added. Relief will be requested from suroking BWS045. M. SERVICE AIR
- 1. Question: Should SAS052 (M590/E13) and SAS054 (M590/E13) be categorized A/E and leak tested?
Discussion: These valves will be categorized A/E with an SLTJ type test specified per SP 205.01, Reactor Building Integrated Leakage Test. Relief will be requested from exercising these manual, passive, locked closed valves. N. NITROGEN GAS
- 1. Comment: NGS011 (M591/G12) must be e:<ercised quarterly or relief must be requested.
Discussion: Relief f rom stroking this normally closed passive check valve will be requested.
- 2. Question: Should SG3017 (M591/Hil) be categcriced A/E and tested accordingly' Discussion: NG5017 will be categorized A/E and relief will be requested f rom stroking this manual, passive valve. A SLTJ test per SP 205.01, Reactor Building Integrated Leakage Test will be specified.
- 3. Question: Should NGSold (M591/Il2) be included in the IST Program?
Discussion: SGS013 will be categorized A/C and included in the IST Program. Relief will be requested f rom stroking this nor-mally closed passive check valve and an SLTJ leakage test will be specified per SP 205.01, Reactor Building Integrated Leakage Test. P. DEMINERALIZED WATER
- 1. Question: Should DMWO24 (M593/C10) be categorized A/E and tested accordingly?
Discussion: DMWO24 will be categorized A/E. Relief will be requested from stroking this manual, passive, locked closed valve. A SLTJ 1eakage test per SP 203.01, Reactor Building Inte-grated Leakage Test, will be specified.
- 2. Question: Should DMWO25 (>693/C10) be categorized A/C and tested accordingly?
Discussion: DMWO25 will be added to the IST Program as a Category A/C Valve. Relief f rom stroking will be requested for this passive, normally closed check valve and a SLTJ leakage test per SP 205.01, Reactor Building Integrated Leakage Test, will be specified. 90005073
t Q. MISCELLANEOUS
- 1. Question: Should any components of the Emergency Diesel Generator Air Starting or Fuel Transfer Systems be included in the IST Program?
Discussion: No. The Emergency Diesel Generators and associated sub-systems are tested monthly per Technical Specification requirements. These components will not be included in the IST Program, therefore, no program change is required.
- 2. Question: Is SFC019 (M523/H6) safety related?
Discussion: No. Alternative cooling and makeup sources to the Spent Fuel Pool are available from the Decay Heat System and Borated Water Storage Tank. No program change is required.
- 3. A definition of when and how much valve testing is to be done at Cold Shutdown will be provided per staff's suggestion.
4 A Request for Relief from IWV3410(g) will be submitted per staff's suggestion. i 90005074 1 l l l l l 13
PLMP TESTING PROGRAM
- 1. Question: Can the pumps listed in PV20 be tested in a fixed resistance system?
Discussion: All pumps listed are tested in fixed resistance systems. PV20 will be withdrawn as no relief is required.
- 2. Question: PV17 does not apply to the Auxiliary Feedwater Pump.
Should this Relief Request be PVl9? Discussion: Yes. PVl9 is the correct request; however, it is unnecessary and will be withdrawn.
- 3. Question: Is inlet pressure for the Nuclear Service Raw Water Pumps (P472A and 3, 3044/E3 and E7) measured?
Discussion: Yes, inlet pressure is measured and recorded.
- 4. Question: Can the Auxiliary Feedwater Pumps be tested in a fixed resistance system and PV22 withdrawn?
Discussion: Yes, the pumps will be tested in a fixed resistance system and PV22 will be withdrawn.
- 3. Request: Provide more detailed information regarding measurement of flow rate for the Nuclear Service Raw Water Pumps.
Discussion: A more detailed explanation of the alternate method for measurement of Nuclear Ser/ ice Raw Water Pumps will be provided in the Alternate Test section of Relief Request PV2 3.
- 6. Comment: ASME Section XI states that pumps must be tested monthly.
Discussion: Relief Request PV24 has been submitted to allow quarterly testing. This is an open item for NRC.
- 7. Comment: Eductors are utilized to draw NaOH into Reactor Building spray.
Discussion: The question of whether to test thesc eductors as pumps per Section XI was raised by staff and left as an open item for NRC resolution. 90005075 14
NONDESTRUCTIVE EXAMINATION PROGRAM A. CLASS I COMPONENTS
- 1. Question: Why aren't the reactor inlet, outlet, and sa:
nozzle to safe end welds listed in the examit as dissimilar metal welds? Discussion: Reactor inlet and outlet nozzle to pipe weld steel to carbon steel welds and are, therefo in the dissimilar metal weld category. Reac jection dissimilar metal welds are included section of the program under Section B4.1. change is necessary.
- 2. Question: Why are Reactor Vessel Closure Nuts given a ation?
Discussion: The 1971 Edition of Section ;;I with Addenda Summer 1973 was utilized during the first 40-That edition specifies a volumetric and visu. examination for nuts under Item 1.S. No pro necessary.
- 3. Request: Explain more fully the reason for no examina in Relief Request NDEl.
Discussion: NDElwill be rewritten to state that all acce of the weld will be examined during the firs Should any recordable indications he notea, examined manually during the second period, percent of the seld will be examined f rom th during the third period.
- 4. Request: Provide radiation levels and the estimated p in NDE4 and NDE5.
Discussion: Radiation levels, examination times and man for various areas (estimated from OD contact ings) are listed below. Component Rad tvl(R/hr) Exam Time, Reactor Vessel 13 o Reactor Head 13 3 Core Flood Nozzles 10 3 Stm. Gen. Head 15 1 Pressurizer 15 0.5 NDE4 and NDE5 will be resubmitted with the a: included.
- 5. Question: Is a surface examination of the pump ID poss a volumetric examination?
15 90005076
1 Discussion: No. Radiation levels are estimated to be on the order of 15 R/hr or greater. The exan!7ation would take at, least four hours and would, therefore, result in at least 60 Man Rem of exposure. No program change is necessary. B. CLASS 11 COMPONENTS l 1. Question: What systems were exempted from volumetric examination pursuant to IWC1220 (b) and (c) of Section XI? Discussion: Containment Building Spray and Core Flood Discharge were excluded as allowed in IWCl220 (b) and (c) respectively. It js understood that for these systems, the normal exam-ination requirements of Section XI will be required as augmented exams by the Saf ety Evaluation Report (SER) C. PRESSURE TESTS
- 1. Request: Provide more information with regard to Relief Requests NDE10, NDE11 and NDE12.
Discussion: Tests are to be performed at pressures lower than those required because it is not possible to provide isolation. NDE10 - All Class 2 and 3 piping within pump isolation valves for those pumps listed in the IST Program will be visually examined during normal creration. NDEll - RCP Seal Injection piping will be visually examined during normal system operation. NDE12 - Auxiliary Feedwater Pump and Turbine Driver seal and bearing cooling piping will be visually exam-ined during normal system operation. Inspection schedules sill be is noted in NDE10, NDE11 and NDE12. No program change is necessary. D. MISCELLANEOCS It was noted by staff that a Relief Request should be submitted for the 20% DAC criteria of Section XI. In subsequent telephone conversations, staff has noted that this is unnecessary and no request will be submitted as noted in the meeting notes. 90005077 16 1 1 l
ENCLOSURE 1: RCS001, RCS002, CFS001 and CFS002 DISC MOVEMENT VERIFICATION Note: This procedure is to be completed during Refueling Outages when the Reactor Coolant System is at its normal operating pressure. Install a pressure gage on CFS508 (CESS 16) and read pressure. as Pressure is ?ressure is ' RCS 600 psig. ,ressure (2135 psig) e RCS001 (RCbUUJ) CFSO91 UtF5002) is closed is closed Close HV26513 Close HV26313 (HV26516) (HV26 511. ) Install Pressure Cage Depressurize Piping on CFS51,3 (CFS517) through CFS308 (CFS516) Pressurice Piping through
/ \
Depressurization Depressurization CFS508 (CFS516) and observe Successful Not Successful pressure on CFS513 (CFS517) I I RCS001 (RCS002) RCS001 (RCS002) N is closed is open Pressure Remains Pressure 600 psig - 600 psi; . Repair i Retest CFS001 (CFS002) 'CFS001 (CFS002) : is closed is open Repair & Retest 90005078 17 l
1 L . . RMCHO S000 .'l'JCL E.M CE.'IPt'I.'G STA72P.' Wi!T ?
"- ENCLOSURE 2 ENCLOSt,2 2 (ME7GICE I/C4C~IOt PFCGRAq *
$ 0;T03?R 13, IN9 TO FEBRUAKf 18,1933 FERIOD: .
R@liEST FGR AD3:T CML lHFG?PATIC-lI l 1. CLAE i C'J".r0 TITS
's . Cca:trr.k; Item 31.6 catecary B-f, My aren't We reacb:e inlet, autlet and safety fcfenion non',a. 0-rde end wid; listed in the e:cmation progrc=!
l E. Why are closura riur; listed as receivir.g a visul inspectica in 4 J Additi0n 70 VOltittfiC and Surfa:C eX2Cin2tiCA when Iaule Ihl=26C) i 1
. TCquirt$ S /DIVmstric ar.d surfaC2 BE77;inatica khtn the DutS " 7 15 2 - , .
s r TS;:"M J. .- 1
- 0. Rdief Rgtest NUE 1: The proposed alternate examf ution N.qdees:
4 -
" bring the firs; cce-third intem), .111 3ccat:ibic m'M of the wald f
- !a. .
will te ext.rined frc.m the top cr flanpe surface by utili:ing a fu!T f , 350" steep of the vesset circumference. In addit'on, c'uring ::u /Inal ene thrid ir.tcrui, ICCI of the dd v:li !:e enr.ined froa tM vens! ID " [ h Sir.:e reu nate th:t 55 cf tne fiang: :o-v;:.er nW course is accusnie
- }, from the = ting surfa
- a, ny aren't the nacir, Miens c:cducted as milewe i
\
l 1st Ce.sthird hvied - 255 weld (Dam frog e.fng surfecc)
! 2nd Oce-thin! Pericd - 75% veld (ban fcca i:uting surfaca - total j wild 50Q s
3rd Cna-third .%ried - 5G7, welc (Exam frc.r. f.0. ) . I If inspecticas.ccuid be c=r.leted ir. this r. inner no rquest fcr edief
; rould N r.tcenary.
1; i , 4. Ralief Reonest KOC 4 4 5* Pielse, spnify k.Mt radiatica levek yfli f
- M n.d iidiude in relicf muest the atticutsd personnel expstre.
- 5. ReHei Rec.ust 217: Is a surface ew.iudco frc. I.O. of pp p:nbie '
blice of w.k-drie en inatien ice the puu casing walds? a n. mt n mms . I
$ i. Firm, identify ucw systems or partiens of systa-.s that were except I
i, ' fecm c.mination ;urteant to !KrM20 (t,) md (c). 4 J- .i .. I 1 a s 9 *g'3~ A D- * * ]M . L . = 90005079
I
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. l J
t II!. E'J? TESTS h L'.it.cf P.e:;uest: liDE ID, il 2nd 12: Tts staff rect;nizeS that ' ' there are n:n-isolable junctions cong ASME Code Gass 1, 2 and 3
' C m nent.t. The alternate leaksg tens for the reitef requests f listtd above should be concutted at the icwer te:t pres.sure as recuired
. by Code. Please litt the ccq: rents and jun:.tle.cs r0ferred to in l '
Relief Ret;uests 10 - 12 and their high/ low design ;fessures, d
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l 90005080 l
)DDR ORGNAL e
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- 5. M H is l'n0j as s :staq:ry A/.E n1vo aM th:refore ras h 1 ca','.
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i 11 Revise e.t v fe t.- raia tc ?.!c:1.n of 9,e fCowi .g va'a ves to de:cr= irs e g e. s.. .:... ,y s. . , . .:~ . . .. . .,.. u y.1 , r i. ., : a e' : :. . e .* a ?C .*. # e,.ra e afe. ,iu.=.a f., s ;. e'.t.'.'..*,, 4? . . f 'f.t g ?'\1
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*90005082 :
P00R ORIGINAL W '
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0:.:rtet::ent i:si stten Sr.ctiun? i i D. Rue'. - t :11dir; S.nr.w . ,
.1. Pmide rcre etziied inerr2 tion :r. a:w car.cn v.: c33 lc era rd! '
sttr'<e exer .i su. ' j
- 2. 's?at altar e.te tests havt un can-Mared fer sc:icfying t% ))
exercisin; ruuircen.ns ter tr.: fciinir; <ahnt? () 1
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.i. W: is the san:y niaud function of valves 05:031 ,:t 22 ^22 ?
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- f. Y. sin C rde .:ts a~d p.wv1 i I. Men are uhu HCCU ina ,Wv50 full stnd.c e:Orcisd cuc.-tcriy7 I
h, f.Ulili3.'V 3 Da:L's T .
- 3. Ecden thz- nfe:y reia:2c f: cticn of valves .GCN-3 aM A5CM9 to cebr ir.a W tr.ey sacAo ta categcrize: NE anc .V rn;t:.:ively. ,
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- 2. Review tr.e safcty relaMJ func'.icn of vehes F.73Gik ?.M H5.3'A2 to j detemine if tr.ey sd:uld be reca:egori:ec A/E. ;
4, . i. Reyfew the safety r:1a:ad functica of the fol1 cide; vaives ts ! ! cetemine if they sbuld ts ir.cised in tfre ni .orepr::. I
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- 1. hhe E311. :s: b2 fait strate e.v.er:f red ;;ar::r?y er re !cf :at 9 to rei.esten.
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3. Review the tafe*y reisted fun: tion af v:ive P.O.0012 to catc.aine if it shcu1d be in:1uu' in t:*- iD' ?:-: g:- .
- p. v., .i e . . > 3 5 s. . e > . '
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- ENCLOSURE 3 * .
IST f*EETIfiG WITP,,M. go,,jgG - /0 g y y g j/ The team related the position relative to the ASME Code requirements It IW-3520(a), (b), (b)(1) and (b)(2) (1974 Edition) for check valves. was cade clear that check valves are expected to be full stroked or if only limited operation is possible (and it has been demonstrated by the licensee and agreed to by the staff) during ;cwer operation, the check valve shall be partial strcked. Si,nce disk pcsition is not always observable, fluid flow d test are acceptable @(4 demonstratt . hat a valve has been exercised to' the l l position re:;uired to fulfill its functionJand it is censidered full stroking when the flew used is at least that which is identified in the plant's safety , analyses for the valve in cuestion. Any less flow used will be considered as a partial stroke unless it can be demonstrated that the lasser flow will still
~ '
place the valve disk in the same position (or in a more conservative position) as the flow in the plant's safety analysis. The licensee agreed with this understanding. The Code states that, in the case of cold shutd wns, valve testing need not be performed more often than once every three months for Category A and B valves and once every,nine renths for Category C valves. It is our position th.:t the
- code is incon*istent and that Category C valves should be tested on the same schedule n Category A and B valves, The licensee has agraed to modify his note on co* d shutdown to read, "In the case of fregent cold shutdowns , valve testing will not be perfereed more often than once every three (3) conths for ;
l Category A, 0 and C valves." 90005086 P00R OR G NL . I - - - - . - - - _ _ - . - - - - - _ _ - - - _ - - - - - -- v
y - .. The team noted that the licensee's T. 'S. cay be in conflict with the NRC staff
" Guidelines for Excluding Exercising (cycling) Test cf Certain Valves During Plant Operation." The licensee has agreed to review their T. 5. and to consider the need to prepose T. S. Changes which would have the effect of Orecluding such testing. Further, the team noted that these guidelines pointed out that
. all valves, which when cycled, could subject a system to ::res'sure in excess of .
?
their design pressures should not be tested during power cperation. It is
. 1
. assumed for the purpcse of a cycling test that one or more of the upstream (or downstream which ever is applicable) check valves has failed unless positive methods are avai.lable for de ermining the pressure or lack thereof on the high pressure side of the valved tc be cycled. The licensee agreed to carefully review the application of these guidelines to their plant and im;lement these guidelines where pcssibic. Any conflict will be identified by the licensee to
. NRC.
The. team ncted that NRC differentiates for valve and pump testing pur:oses be-tween the cold shutdcwn mode and refueling acde. That is for testing purpcses the refueling mode is not treated as just another planned cold shutdcwn. The team discussed the position for valve testing at cold shutdewn condition. 5 It was made clear that the intent is that valve testing c0=ence as scon as t l possible into the cold shutdcwn but no later than 48 hcurs after the shutd:wn. . And that vaive testing continue until ec. plete or plant startup to return to . a
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90005087 l l 3, . u . .
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, power. Any testing not completed at one cold shutdown should be performed ,
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- during subsequent cold shutdowns before the next refueling.
All valves l
. 1' identified to be tested at cold shutdown are expected to be tested at refueling. t The licensee understands this pcsition and agreed to consider applying it in !
. defining the licensee IST program.
) !
The team noted that although we are only reviewing at this time Code Class 1, l I 2 and 3 safety related valves (those that mitigate the consequences of an . accident and/or safely shutdown the reactor and to maintain the reactor in a shutdown condition), the team in this workir.g sessi:n made it clear we are not taking the position that the other C:de Class 1, 2 and 3 valves are not imoortant and therefore, sbcuid no be tested. We noted fer example that it is possible
..that I&E may identify valves other than those safety related valves discussed The licensee in our working session that should be included in the IST program.
. sta'ted they underst:cd. The team res ested that if by testing a r.cn-safety related valve it is necessary to isolate a safety syste , the licer.see shculd identify these instances. The licensee agreed to this action.
The folicwing valves were identified as examples of valves that perform pressure isolation: 2C5 do // CF G CC/ ncr sn, ces cs: o s s c i.r, par oa ' Nm3 N / .,w, 90005088 sist -on i 5/a- w? f/s " p?'? , $lA ~ d V / pp . pyV, $//P ~ CII0
.7 a
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h - 4 The fo11cwing signatures indicate that the parties reviewed the minutes taken
' ~
in the course of this meeting and understand that they reflect the contents of the meeting. .
/N' 8 28 agrees to provide a revised IST submittal by
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6ffhr . N,RC: . AL6p Date: d
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