ML19220C335
| ML19220C335 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 02/17/1976 |
| From: | Silver H Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7904300436 | |
| Download: ML19220C335 (5) | |
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UNITED STATES NUCLEAR REGULATORY CO T.t?.11ssiC N W ASHINCTCN. C.
C.
20$55 Feb rua ry 17, 1975 COCX2T NOS:
50-320 APPLICANT:
Metropolitan Edison Ccmpany FACILITY :
Three Mile Island
SUMMARY
OF MEETINu CN CPEN ITEMS CN TMI-2 Representatives of the applicant and his contractors met with members of the NRC staff en February 6,1976 to discuss various ocen items in the review. A summary of the discussion en each item follows:
Shield & Penetration Ccolina The applicant verified his ccmmitment to test the ccoling functicn of the Penetration Cooling System by cenitoring apprccriate temceratures during Hot Functional Testing. NRC agreed to accept the rescense in Q 41.20 (4) on p. 52-3d7, and the acplicant agreed to modify the title of paragraph (4) to describe more accurately the actual system.
Rod Orco Time Testing NRC again stated that the applicant should either provide acceotance criteria for full centrol red i.1sertion times or alternatively, oravide justification for not establishing such acceotance criterien.
The applicant noted that historically S&W plants have tested red drco times to 75% insertion and cuestioned the justification for our recuest.
Further discussion did not resolve this issue, and the aaplicant requested a formal questien if cur pcsition remained unchanged.
Conformance with R.G.1.21 The acplica.c noted that itemi:ation in the FSAR of scecific CC loads which will not be disconnected during testing would make any necessary changes in this list difficult. They proposed identifying specific loads in the test procedure, and stated that connected 1 cads will be kept to the minimum censistent with plant safety and test recuirements.
These would include certain fire service loads, and scme alarm, test monitoring, and ccmmunicaticns circuits only as recuired for safety anc test purposes. NRC agreed to accept this statement of intent, ct acled with scecific listing in the test orccedure of connectec leads, as s a ti s r,yi ng thi s i tem.
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~ Containment Sumo Tescing cer R.G.1.79 Considerable discussion teck place regarding possible test setucs, limita-tiens, and temcorary modifications required to perform eaningful tests.
The acplicant indicated he felt that mcdel testing is an acequate and feasible acpecach, rather than testing through the clant sumo and systems,
and intends to submit a proposed program within a few weeks cefining such tes ts. NRC noted that full justification for this aporoach must be presented, and that our concerns of adequate NPSH, line cleanline::, and vortexing, must be addressed.
Core Flood Flow barif4 cation The applicant noted their intent to reference tests o.: the Cccnee plant as the basis for conforming with R.G.1.79 cn TMI-2, since sicw valva ccening times en tnis plant preclude Teaningful direct testing.
75'I - 2 will submit as part of the FSAR justification for this accreacn, describing the Cconee tests and the analysis of the TMI-2 ficws.
This analysis uses methods similar to these used on Oconee, and is based on as-built system parame ters. The submittal will clude correlation of Cconee test results with calculated values.
LPI Crossconnect Points made by the applicant include:
1.
SAW-lCC64 indicates one hour is available to manually cperate the crcssconnect valves.
2.
LP recirculation ficw to the core is not required for care cooling af ter switchover fran injection mode.
3.
Any required " plumbing" changes (check valves, cavitating ventaris,
etc.) will take approximately 2 years to imolement.
The NRC sta## noted:
4 BAW-lCC64 has not yet been ac:ected by the staff, and in any event y
acclies to plants of icwer pcwer level than E4I-2 5.
Manual valve operation is no longer accepted in accicent situations.
The acclicant agreed to determine correct references and to veri #y t:e time available to ccerate the valves.
NRC will review these inouts and confirm cur position as a oropriate.
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-% [ Subsequent references by the applicant raised additicnal cuestiens.
It was also later determined that the valves in questions are locally controlled electric motor driven, but can be manually operated.
Soth the applicant and the staff are continuing their review of this item.]
Switchover feca Inf ection Mcde to Recirculatien Mode The applicant noted he would modify the response to 0 22.5 to show soecific times, BWST capacities, and ficws for all ocerations, to assure capability to accomplish the switchover mr.aually.
The possibility of vortexing in the SWST as the level accroaches che outlet no::le, the need to prevent tnis,
tnd possible water level assurotions were discussed.
The applicant indi-cated details of the operating procedure for the swit nover will be provided as appropriate.
Structural Effects of Subcomcartment Transients It was agreed that a presentation would be made by the applicant at a future meeting, later scheduled for February 19, 1976.
Diversity in CHR HP-LP Isolation The applicant stated the FSAR will be revisea to shcw the diversity to be provided.
Containment Peak ?ressure NRC confirmed that leak testing of the containment at the peak pressure calculated in the response to Q 3.4 is recuired.
SWST Drawdcwn Test The applicant stated that the respcnse to Q 310.2 will be revised to describe this test. A general descriptacn of the procedure was disc" sed.
Pre-service Primary System Hydrotest The applicant requested guidance on methods of calculating the recuired test temperature and on performing the test.
The acplicable provisions of the regulati:ns and ASME Code were discussed.
Technical Succar: Staff Qualifications (Q 212.1)
NRC noted that an udequate resconse would include nuccer of : ecole anc total excerienca and ecucation in each area at the present time.
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ECCS Final Accectance Criteria The applicant stated that the response to Q 21.34 is intended to cover their ccamitment to cceply, and that topical rescrt 3AN-10103 Rev.1 specifically covers TMI-2.
The wording of Q 21.3a will be revised for clarification, and Section 5.3 of the FSAR will be revised to refer to the topical report.
[3AW-10103 has been accepted by the staff with scme open items.]
A meeting was planned to discuss further open items, including structural response of subccmpartment walls and steam line break analysis.
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Hrie[
NI, Pro r
Lig$t ' ater Reactors Branch #2 Divss'en of Project Management
Enclosure:
List of Attendees W
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ENCLOSURE
'!M - MET ED MEETING FEERUARY 6, 1976 NrtC Harley Silver Jim Watt Oave Shun Bi l Milstead Frank Ashe
'darren Hazelten Bob McDermott GPUSC Dick Heward Max Nelsen Ed Wallace Lou Lanese B&W Bill Gray Lee Pletke S&R Tony Zallnick F.
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/1 vav
4 MEETING
SUMMARY
Applicant and cc D. Eisenhut Docket File #
L. Shao NRC CPR R. Baer Local POR A. Schwencer TIC B. Grimes LWR #2 File H. Centon NRR Reading V. Moore B. Rusche G. Knighton E. Case B. Youngblood R. Boyd W. Regan R. Heineman R. Vollmer D. $kovholt D. Bunch P. Collins J. Collins C. Heltemes W. Kreger R. Houston M. Ernst R. Denise R. Ballard T. Speis M. Spangler R. Clark W. Gammill R. DeYoung J. Stepp J. Stolz L. Hulman K.
Kniel M. Willians C. Parr LPM W. Butler EPM D. Vassallo ELD R. Maccary ACRS (16)
J. Knight IE (7)
- 5. Pawlicki Participants I. Sibweil S. Varga D. Ross M. Sc vice P. Check T. Novak Z. Rosztoczy R. Tedesco V. Benaroya G. Lainas T. Ippoli to V. Stello K. Goller R. Purple D. Ziemann G. Leaa R. Reid
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