ML19220C004
| ML19220C004 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 09/30/1975 |
| From: | Silver H Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7904280055 | |
| Download: ML19220C004 (5) | |
Text
{{#Wiki_filter:* UNITEo STATES nut 2AR REGUI.ATORY COMMISSION W A S HIN G TON. O. C. 20 S S S Septe=ber 30, 19 75 C0CKET NO: 50-320 APPLICANT: Metropolitan Edisen Cc=pany FACILITY: Three Mile Island Unit 2 SUBfARf 0F MEETING ON PRE-CPERATICNAL TESTING Representatives of the applicant =et with =e=bers of the NRC staff on Septe=ber 12, 1975 to discuss open ite=s in the DfI-2 review dealing with pre-operational testing. 1. Conformance to Reg Guide 1.79 - 0 413.2, Ite: 10 After considerable discussien regarding the possible approaches to and value of vertex and NPSH testing through the containment strp, where only very limited testing is feasible i.n any event, the applicant stated that either some apprcpriate testing will be done or adequate justifl-cation will be presented for acceptance of analysis only. Hopefully, this will be included in the October 3 amendment. With regard to section C.3.c.(1), verification of core flooding ficw rate, the applicant argued that the design has been proven by testing at Oconee. For test purposes, the DfI-2 RCS cannot be depressuri::ed rapidly since the valve time constant is about 70 seconds, and the accu =ulators should empty in 30 seconds. Possible testing to demonstrate confor=ance with Reg Guide 1.79 was discussed, along with docu=entation regttired if analysis and Oconee tests are used in conjunction with DiI :-ing. The applicant will amend c.e previous response to Q 413.2, Ite: 10, te state that no automatic operation of the core flood tank isolatien valves is required, and that therefors Reg Guid: 1.79 does not apply. 2. Respense Time Testing Docu=entation covering previously discussed factory and prototype testing will be covered in the amend ent se.heduled for October 8, 1975. (In a subsequent conversatien, the applicant informed us that contrary to previous statements, individual testing of RTD's has not been perfor=ed; it was not certain that even prototype testing on the models to be installed had been done.) 85 223 p ou s00ff d
~ 9 O -2 3. Response to G 413.2, Ite: 6 - Lead Croun Assimments The applicant confirmed tnat all AC pcwer not under test will be secured. Some DC necessary for plant operation and sarety will not he discennected. Re applicant recogni:es the intent o f Reg Guide 1.41, to prevent possible cross-connects between divisions, and will = edify TP 600/21 to note this as a test objective. Specific loads w'.11 be identified at a later time. 4 Response to 0 413.2, Item 9c - Turbine Trip Be staff accepted the applicant's statement that the Generator Trip Test will be perfor:ed without direct tripping of the turbine stop valves, so that the turbine protection system will operate in its normal manner to protect the turbine. 5. Reauest for Test Abstracts TP 800/6-Steam Bypass Testing. He applicant noted that NRC concerns about operability are addressed in TP 800/14 and 800/34 TP 300/71-Feed System. The applicant referenced TP 800/12, Unit Load Steady State Te st. .In respense to the staff concerns about safety aspects, the applicant agreed to re-examine the test and respend as necessary by revision to Q 413.7(31 TP 300/8-ICS Tuning. Matters of concern to the staff are covered in TP 800/12, 14, 23, 34 and others. Acceptance criteria is correct response to transients in *hese tests. 6. Resoonse to 0 413.4 - Abne=al Cecurrences The applicant stated that abno=al occmences from such sources as Current Events, EEI, Clearing House, insing Infomation Service, A/3 Su=maries, DfI-1 A/O's, etc., are . d and incorporated into test and cperating procedures. GPU wil c-
- r further formal response, but questions.our require =ents fc
.a femal program. 7. Resocnse to 0 41 ~. 3 - Test Staffing Ihe applicant stated that he will maintain the indicated staff of ten throughout the testing program, supplemented by vendor and A/E personnel acting as advisors and technicians. Y E2]
. 8. Response to 0 413.6-Item 20 - The applicsnt noted that "cperating ccnditions" in the response refers to temperature and pressure, not flow. In any event, they noted that no credit is taken for MSIV action in their accident analysis. Item 34 - The previous response will be modified to describe the test. 9. Response to 0 413.7 The staff requested a general functional description of the planned tests on each co=ponent and system (as listed in the question) required to operate to mitigate the consequences of an accident. The applicant indicated he will respond. 10. Testing to Conform with Reg Guide 1.68 A.1.b. (5) - RCS Code Safety Valves. According to the applicant, valves have been bench tested with hydroset assist by the manufactuer. QA documentation is available. No further tests are planned during pre-op. Storing and handling of the valves in the field is controlled, but some concern was raised about the length of time between testing and operation. A.1.b. (6) - MSIV's. See previous discussion. A.2.c. - Automatic Reactor Power Control System. See previous discussion. A.2. f. - Auxiliary Startup Instru=entation. This will be covered by initial fueling procedures. The applicant will provide appropriate description of these tests. A. 3 - RPS. TP 600/23 will be modified to discuss loss of power considerations. A. 4.b - Main steam RV's. These are tested during the hydrotest in hot functional testing. A.5.0 - Shield cooling. Internal penetrations are air cooled, while reactor building penetratiens are water-coil cooled. These are not described in the FSAR. The applicant will address testing of these systems. A.5. g - Primary Pressure Relief System. See previous discussicn. A.6.c - DC System Tests. The reference in TP 401/3 to an incorrect sectaon in IEEE-450 will be deleted, k@l3 ?>"?s) ar
9 9 A.11 - Reactor Components Handling System. Test for these systems will be covered in initial fueling procedures. The applicant will address this area. B.1.b - RPS Checkout. Pre-critical testing will be covered by Tech Specs. B. I.c - Rod drop time =easurement. Because of the relatively low worth of rods at up to 75% insertion, the applicant was asked to establish acceptance criteria for timing to reach full insertion. B.1. f - Scurce range - 'titors. The applicant noted that calibration and neutron response .cks are covered in 17 301/3D. This was accepted. B.1.h - Hot flow and ' ass of flow tests. The applicant assured us that these tests e.r i-t e ' after #cel loading. 3.1. j - Vibrat t en t th - n R.. i.1) The resp;nse to Q 11.6 identified Oconee as the I. st.." for this p1x,t. D.1. a - Natuza2 01;, "'.at on Tus.s. Oconee 1 is the prototype for this plant. 17 200/6 r A T- '11 :.over confi:=atory tests. D.1.h - Turbine T-ip. See previous discussion. D.1.j - Shutdown from outside the control room. FSAR Section 7.4.1.3 discusses conformance with Criteria 19. Tests will be perfor=ed with the minisus crew size in accordance with the Tech Specs. D.1.r - Process Co=puter.- The applicant noted that for in-core calculations, the ec=puter is checked with simple, hand calculations. / / Y'+ v Harley /1ver,ProjectManager Light W ter Reactors Branch 2-2 Divis n of Reactor Licensing
Enclosure:
List of Attendees ~- awt.s0 ^ rr
LIST.OF ATTENDEES NRC/ MET ED MEETING SEPTEMBER 12, 1975 NRC R. McDer=ott J. Watt H. Canter, IE H. Silver F. Ashe GPU J. Vann T. Cri== ins J. Barron R. Toole M. Nelson f ( a
~ m - - .p,.._.. .^ ~ '. '. ^ ^ x. w September 30, 1975 CCCKET NO: 50-320 APPLICANT: Metropolitan Edison Co=pany FACILITY: 3ree Mile Island L' nit 2 SLM4ARY OF MEETING ON PRE-CPERATICNAL 17! STING Representatives of the applicant met with members of the NRC staff on Septceber 12, 1975 to discuss cpen items in the B!I-2 review dealing with pre-operational testing. 1. Confomance to Ret Guide 1.79 - 0 413.2, Item 10 After considerable discussion regarding the possible anproaches to and value of vortex and NPSH testing through the contcinment st p, where only very limited testing is feasible in any event, the applicant stated that either some appfopriate testing will be done or adequate justifi-cation will be presented for acceptance of analysis only. Hope fully, this will be included in the October 8 amendment. With regard to section C.3.c.(1), verification of core ficoding flew rate, the applicant argued that the design has been proven by testing at Oconee. For test purposes, the TMI-2 RCS cannot be deprassurized rapidly since the valve time constant is about 70 seconds, and the accumulators should e, 'y in 30 seconds. Possible testing to demonstrate confor:tance with Reg Guide 1.79 was discussed, alcng with documentation required if analysis and Ccence tests are used in conj unction with DtI-{ testing. De applicant will amend the previous response to 0 413.2, Item 10, to state that no automatic operation of the core flood tank isolatien valves is required,,and that therefore Reg Guide 1.79 does not apply. 2. Response Time lesting Docu=entation covering previously discussed factory and prototype testing will be covered in the amendnent scheduled for Ceto'cer 8, 1975. (In a subsequent conversation. the apnlicant informed us that contrary to previous statements, individual testing of R'"D's has not ueen pr-for=ed; it was not certain that even prototype testing en the models to be installed had been done.) N"*"8* I... ] O Form AIC-313 ( Rs.. M3) AZCM 0248 2 u. s. eovuse mswt em=vtese opricas i e4.see.ies
. 3. Reseense to 0 413.2, Item 6 - Load Grouc Assienments ne applicant confiised that all AC power not under test will be secured. Some DC necessary for plant operation and safety will not be disconnected. The applicant recogr.izes the intent of Reg Guide 1.41, to prevent possible cross-connects between divisions, and will nodify TP 600/21 to note this as a test objective. Specific loads will be identified at a later time. 4. Response to Q 413.2, Item Oc - Turbine Trip ne staff accepted the applicant's statement that the Generator Trip Test will be performed without direct tripping of the turbine stop valves, so that the turbine protection system will operate in its nor=al manner to protect the turbine. S. Request for Test Abstracts TP 800/6-Steam Bypass Testing. He applicant noted that NRC concerns about operability are addressed in TP 800/14 and 800/34 TP 800/71-Feed System. He applicant referenced TP S00/12, Unit Load Steady State Test. In. response to the staff concern about safetv asrects, the applicant agreed to re-exazrine the test and respond as n3ces'sarr by revision to Q 413.7(3J TP 800/8-ICS Tuning. Matters of concern to the staff are covered in TP 800/12, 14, 23, 34 and others. Acceptance criteria is correct response to transients in these tests. 6. Response to Q 413.4 - Abnamal Occurrences ne applicant stated that abnormal occurrences from such sources as Current Events, EEI, Clearing House, Licensing Information Service, A/O Su=maries, 'DfI-1 A/O's, etc., are reviewed and incorocrated into test and cperating procedures. GPU will consider further for=al response, but questions our requirements for a fonal, program. 7. Resnonsa to 0 413.5 - Test Staffing he applicant stated that he will maintain the indicated staff of ten thmughout the testing program, supplemented by vendor and A/E personnel acting as advisors and technicians. w====- b ?23 38' " Forza AEC-518 (Rev. 9 S 5) AECM 0240 2 u.
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, 3. Response to C 413.6 Item 20 - ne applicant noted that " operating conditions" in the In any event, response refers to temperature and pressure, not flow. they noted that no credit is taken for MSIV action in their accident analysis. Iten 34 - ne previous response will be modified to describe the test. 9. Response to 0 413.7 he staff requested a general functional description of the planned tests on each co=ponent and system (as listeu in the question) required to operate to mitigate the consequences of an accident. D e apolicant indicated he will respond. 10. Testing to Conform with Reg Guide 1.68 A.1.b (S) - RCS Code Safety Valves. According to the applicant, valves have been bench tested with hydroset assist by the manufactuer. QA documentation is available. No further tests are planned during pre-op. Scoring and handling if the valves in the field is centro 11ed, but some concern was raised about the length of time between testing and operation. A.1.b. (61 - MS1V's. See previous discussion. A.2.c. - Automatic Reactor Power Control System. See previous discussi-A.2.f. - Auxiliary Startup Instrumentation. This will be covered by initial fueling procedures. The applicant will provide ap3ropriate description of these tests. A.3 - RPS. TP 600/23 will be =odified to discuss loss of power considerations. A. 4.b - Main s te am RV' *. These are tested during the hydrotest in hot functional testir. A.S.0 - Shield cooling. .nternal penetrations are air cooled, while These are not reactor building penetracions are water-coil cooled. described in the FSAR. The applicant will address testing of these systems. A.5.2 - hiscry Pressure Relief System. See previous discussion. A.6.c - CC System Tests. De reference in TP 401/3 to an incorrect sectaen in IEEE-450 will be deleted. ~ o * *'e s in-9[ I .v.....* ..._ ~. T 2. 4 i anst > ~. ~
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- 4 A.11 - Reactor Components Handling System. Test for these systems will be covered in initial fueling procedures. The applicant vill address this area. B.1.b - RPS Checkout. Pre-critical testing will be. overed by Tech Specs. B.1.c - Rod drop time measurement. Becc.ase of the relatively low wortn of rods at up to 754 insertion, the applicant was asked to estr.blish acceptance criteria for timing to reach full insertien. B. I.f - Scurce range monitors. We applicant noted that calibration and neutron response checks are covered in TP 301/3D. Bis was accepted. B.I.h - Ifot flow and loss of flow tests. We applicant assured us that these tests are scheduled after fuel loading. B.1.j - Vibration testing per R.G.1.20. De response to 0. 11.6 identified Oconee as the prototype for this plant. D.1.a - Natural Circulation Tests. Ocence 1 is the prototype for this plant. TP 200/6 and 200/11 cover confirmatory tests. D.I.h - Turbine Trip. See previous discussion. D.1.j - Shutdown from outside the centrol room. FSAR Section 7.4.1.3 discusses conformance with Criteria 19. Tests will be perfor=ed with the minimun crew si e in accordance with the Tech Specs. D.1.r - Process computer.- The applicant noted that for in-core calculations, the computer is checke d with simple hand cal..culaticns. Harley Silver, Project Manager Light Water Reactors Branch 2-2 Division of Reactor Licensing
Enclosure:
List of Attendees kb 3\\ OrtsC E F 8W #" A "E
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