ML20210A627
| ML20210A627 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 02/02/1987 |
| From: | Alexion T Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| GL-83-28, NUDOCS 8702060508 | |
| Download: ML20210A627 (6) | |
Text
4 Docket Nos.
50-327 2 FEB 1987 and 50-328 LICENSEE:
Tennessee Valley Authority FACILITIES:
Sequoyah Nuclear Plant
SUBJECT:
SUMMARY
OF PEETING TO DISCUSS OUTSTANDING ENGINEERING ISSUES On January 21, 1987, representatives of NRC and TVA met to discuss outstanding engineering issues regarding Sequoyah. lists the attendees. includes handouts provided by TVA at the meeting.
The review status of many issues were discussed. The issues included ampacity, superheat, cable pulling, instrun,ent sensing lines, bypass inoperable status indication system, Reg. Guide 1.97, Generic letter 83-28, concrete, design control, electrical calculations, Appendix J exemption, containment spray pump time, design baseline verification program, hydrogen, Diece-parts and con-tainment fan flooding.
As a result of this meeting, the need for timely follow-up meetings / discussions were identified regarding cable pulling, superbeat, ampacity, piece-parts and hydrogen.
Thomas W. Alexion, Project Manager PllP, Project Directorate #4 Division of PWR Licensing-A cc: See next page iJ PWR#
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PDR ADOCK 05000327 P
ENCLOSURE 1 TVA/NRC MEETING - January 21, 1987 OUTSTANDING ENGINEERING ITEMS NAME ORGANIZATION TT Alexion NRC/FWRf4 C.E. Rossi NRC/PWR-A J.E. Knight NRC/EICSB F. Rosa NRC/EICSB J. Holonich NRC/PWR#4 R. Wessman NRC/TVAPS L. Kelly NRC/TVAPS B.K. Singh NRC/PWR#4 G. Hubbard NRC/IE T.J. Kenyon NRC/PWR#4 E. Imbro NRC/IE D. Humenansky NRC/0CM T. A. Ippolito TVA Licensing W.S. Raughley TVA Electrical Branch Chief M. Burzynski TVA Licensing M. Harding TVA Licensing C. Fox TVA ONP B.J. Youngblood NRC/PWRr4 R. Ballard NRC/PAEB S. Hou NPC/PAEB F. Rinaldi NRR/PAEB l
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- .', i DCIDSURE 2 CABLE AMPACITY Problem Identification INPO finding, March 1984' Bellefonte Electrical Evaluation Team Finding, January 1985 NSRS Report, March 1986 Electrical Engineering Branch Problem Identification Report, PIRGEN8605, August 1986 Employee Concerns Realuation Program Element 240.00, November 1986 Problem Description TVA Ampacity Standards did not consider the following which adversely affect the cable rating:
The* cable diameter and number of
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Purchased cable constructions.
The revised conductors proportionately raises / lowers ampacities.
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standard addresses 280 cable types used at TVA while the original l
addressed 30.
The assumed conduit spacing used in the calculation B.
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to derate to reflect the as huilt.
Original ampacities were based on 3" trays while' 4" trays. wore use Ampacity is inversely proportional to the increased depth' of fill
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which results from use of the deeper cable tray.
Engineering did not derate for fire retardant cable coatings, tray Due to the above D.
covers and bottcms and Appendix R fire wrap. inadequacie accomodate these doratings.
Problem Solution Developed and applied the revised ampacity standard using SWEC f
technical expertise, industry standards and TVA specific testing (R 1.
Bechtel has reviewed the standard as part of ECIG and commented that it was acceptable while guestioning if we hadWhe DS-E12.6.3).
sufficient conservatism in one area.
Lundy standards our results are equivalent.
f Completed a sampling program to bound and minimize the problem 2
SQEP-47).
456 deficiencies Documented actual deficiencies on SCR SQNEEB86178.
3.
identified for unit I and 2.
Dispositioned 327 deficiencies on a case-by-case basis by remo De-energized 18 conservatism and using as built information.
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non-safety related cables.
Resized 111 for unit 1 and 2.
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l 01/20/1987 17:57 c*** PANAFAX UF-400 "2" 06607346 P.02 f
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Y A.
Safety Evaluation of Ice Condenser and Hydrogen Mitigation System
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Changes 1
TVA will perf orm an evaluation of all changes (ECNs/FCRs,,FCNs, TACFe, 1.DCRs and DFCRs) since UL on the saf ety-related portiontto'f the hydrogen mitigation system and ice condenser system to address NRCs h
concerns on contain:nent integrity. 'The evaluation vill comply with the 4
objectives of the DBVP program as follows:
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To verify the adequacy of the plant modifications made since OL to systems, or portions of systems, required to mitigate design basis N
events and to provide for saf e shutdown of the plant.
To provide confidence that the modifications are supported by l
W engineering analysis and documenta. tion.
To provide confidence that the modifications are made in conf ormance
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with licensing commitments.
These objectives are being met by TVAs review that will entail the f ollowing steps :
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Identifying'all changes (ECNs, FCRs, FCNs, TACTS, LDCRs, and DFCRs) involving systems *43 and 61 (hydrogen mitigation dnd ice' condenser Q$
systems, respectively).
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Identif y all changes that can aff ect the saf ety-related fdnetions s
of these systems.
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3.
Evaluate these changes (item'2 above) against the design source documents (FSAR. design criteria. technical specifications, or i
other codes and standards, as required) to determine whether any of the changes vill reduce these systems ability to perform its
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designated safety function or will violate licensing commitments.
4.
Where necessary, USQDs and UDIEs will be completed or revised in accordance with TVA procedures.
5.
Any deficiencies encountered from the review that require corrective action will be documented and processed in accordance with TVA procedures.
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6.
A final report will be issued to su=marize and document the results of this review.
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Mr. S.A. White
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Tennessee Valley Authority Sequoyah Nuclear Plant cc:
Tennessee Departrent of Public Regional Administrator, Region II Health U.S.-Nuclear Pegulatory Commission, ATTN: Director, Bureau of 101 Marietta Street, N.V., Suite 2900 Environmental Health Services Atlanta, Georgia 30323 Cerdell Hull Building Nashville, Tennessee 37219 J. A. Kirkebo ATTN:
D.L. Williams Mr. Michael H. Mobley, Director Tennessee Valley Authority Divisicr cf Radiological Health 400 West Summit Hill Drive, W12 A12 T.E.P.R.A. Building Knoxville, Tennessee 37902 150 9th Avenue North Mashville, Tennessee 37203 Fr. Bob faas Westinghouse Electric Corp.
County Judge P.O. Box 355 Hamilton County Courthouse Pittsburgh, Pennsylvania 15230 Chattanooga, Tennessee 37402 R. L. Gridley Tennessee Valley Authority SN 157B Lookout Place Chattanooga, Tennessee 37402-2E01 M. R. Harding Tennessee Valley Authority Sequoyah Nuclear Plant P.O. Boy 2000 Soddy Daisy, Tennessee 37379 Pesident Inspector /Sequoyah NPS c/o U.S. Nuclear Regulatory Commission 2600 Igou Ferry Road Soddy Daisy, Tennessee 37379 H.L. Abercrombie Tennessee Valley Authority Sequoyah Nuclear Plant P.O. Box 2000 Soddy Daisy, Tennessee 37379 T-- L_._
4 MEETING
SUMMARY
DISTRIBUTION
[NijiE"#3 NRC Participants
' ' " ^ ' '
NRC PDR T. Alexion L PDR C. Rossi NSIC J. Knight PRC System F. Posa.
PWR#4 Reading File J. Holonich M. Duncan R. Wessman OGC-Bethesda L. Kelly J. Partlow B.K. SingF E.-Jordan G. Hubbard l
B. Grimes T. Kenyon ACRS (10)
E. Imbro TVA0P (3) S. Richardson AR 5029 D. Humanensky HDenton B.J. Youngblood JTaylor R. Ballard LSpessard S. Hou GZech, RII F. Rinaldi JHolonich KHooks BHayes NGrace KBarr SAConnelly DMuller TNovak CUpright MReinhart JThompson bcc:
Licensee & Service List
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