ML19220C289
| ML19220C289 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 12/08/1977 |
| From: | Silver H Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| TASK-TF, TASK-TMR NUDOCS 7904300143 | |
| Download: ML19220C289 (7) | |
Text
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- g UNITED STATES 7
NUCLEAR REGULATORY COMMISs!ON f,h1 j
W ASHINGTON. D. C. 2CS55 s..
t December 8, 1977 00CKET N0: 50-320 APPLICANT: Metropolitan Edison Company FACILITY:
Three Mile Island Unit 2
SUBJECT:
SUMMARY
OF MEETING ON OPEN ITEMS Representatives of the applicant and Burns & Roe met with members of the staff on November 9,1977, to discuss various open items in our review, as follows.
Final Steam Line BreaF Fix The applicant presented 1 revised implementation schedule (attached) for the ultimate fix for +.he postulated steam line break, and noted that although nearby dates have slipped, the schedule still calls for implementation during the first refueling. As described by the applicant, the final system will include two redundant safety grade feed isolation valves in each feedwater line, one inside and one outside the containment, replacing the existing check valves. The emergency feed system, turbine stop val Ws, and MSIVs remain unchanged. The cxisting feed control statim will remain in use for nomal operation, but the feed latch sigrals will be removed from the stop and control valve, and will be applied to the new isolation valves.
The existing steam line break analysis will remain essentially unchanged, but the eGc1ng feed. ne break analysis will be changed scmewhat to account for valve closure time.
A sketch schematic was presented (attached) showing the revisions, but it was indicated that minor changes may be made. The applicant stated that femal documentation of this proposal would be rade shortly.
It.>.erim Operation - Steam Line Break __
Cne copy of analyses covering the unmitigated steam line break first cycle operation was presented but not discussed at length.
(These analyses have since been submitted femally.) long tem cooling is not covered by these analyses but will be submitted shortly.
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- Boron Flow Sensors The applicant stated he will install ultrasonic flow indicators rather than thermal instruments as previously intended. He noted these are identical to those approved for the Crystal River plant.
Sensors and cables would be permanently mounted with readout instruments either pe-manently mounted or portable to be installed after an accident.
Docketed information is required.
Electrical Site Visit Items The memorandum of 9-21-77 from F. Ashe to F. Rosa,
Subject:
Site Visit Report for Three Mile Island Unit Number 2, was discussed.
It was agreed that modifications required by these items must be installed prior to attaining 1% power. References below are to Enclosure 2 in that memo. The applicant will submit information on the docket for these items.
3.
Safety Features Actuation Cabinet Room - With regard to separation of the 4.16kV bus duct from SFAS equipment, the applicant stated that a fire barrier will be installed.
4.
Switchyard Installation - Mr. Rosa indicated that the arrangement 07 the transmission towers within the switchyard was acceptable.
5.
Auxiliary Buildino - The applicant noted that the substation rooms have flood doors and floor drains, and the exchanger area has an open stairway.
6.
Electrical Penetrations - The applicant stated that the safety penetrations in question were qualified without the existing enclosures.
We stated that the enclosures would has? to be qualified for the appropriate environment. The applicant will respond to this requirement.
8.
Undercround Cable Installation - The applicant stated that physical separation is provided in the duct banks, but the situation in manholes is unknown. This will be addressed.
9.
Flow Sensors (Boron)
See previous discussion on this subject.
O
. Reactor Buildina Sorav Pumo_
Recent results of the applicant's investigation indicated one of the two pumps has an acceptable NPSH and can operate indefinitely. The other is estimated to operate acceptably for 5-7 days and would be warranted for 2-3 days. The suction specific speed is apprcximately 17,000 -
NRC staff felt a maximum of 12,000 would be acceptable. Sump boiling was agreed to be a generic concern and not required to be addressed specifically for this plant, but pump self-venting characteristics should be.
The applicant's investigation is continuing.
Preco Testing - Pump NPSH IIeasured pressure drops on the suction side of the LPI pumps was approxi-mately 20% less than calculated. The applicant will cover this and valve operability in a future amendment.
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Silver, Project 'hnager HarleyjWaterReactorsBranch4 Lig 6,t -
Division of Project Management
Enclosures:
As stated l
ATTENDEES - Tf1I--2 OPE.i ITEMS MEETING 11/9/77 Harley Silver, NRC Scott Dam, Burns & Roe S. A. Morrison, Burns & Roe F. Eltawila, NRC R. Schlosser, Burns & Roe L. Diaz, Burns & Roe F. Rosa, NRC-J. J. Watt, NRC Lou Lanese, GPUSC Mike' Morele, GPUSC P.. T. English, Burns' & Roe e
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.a ACTICN PLAN FCR IMPLEMENTATICN OF STAFF CRITERIA Star:--
'Jork Cc=olete Evaluation of ?ctential Soluticcs 1.
Design scoping of nodificatica 3/77 2.
Analyze un=itigated staan line break 3.
Cther supporting analysis Oesizn Selection 3,.
7 1.
Conpare des,gn approaches 12,,.,
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2.
Evaluate inplica:1cas of analyses resul:s 11/77 NRC Staff Evaluation of Concep:
12/15/77 11/77 Secping Design Calcula: ions a/73 11/77 Ini:iate Procurenen: of Long Lead Time Itecs i/73 Cbtain Sids 3/7S e/73 Cceple:e Detailed Design Calculations 9/73 3/73 3id Evaluations e/7S 1,73 Place Ceder for Long Lead Tine Cc=ponents 3/73 Finali:ation of Oesign Prefabrication 9/73 9/73 Sub=1: final resign to NRC for review and 10/73 approval in inf or:stica succi::a1
'0/79 Installa:1ca during Refueling Cu: age Revise FSAR
!-o necchs after conpletion of installa: ion 4 i /'.
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