ML20009E271
| ML20009E271 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood  |
| Issue date: | 07/21/1981 |
| From: | Snell J Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8107270368 | |
| Download: ML20009E271 (9) | |
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3 Ny Docket Hos.: ySTN;50-454,aSTN 50-455 and STH 50-456, STN 50-457 d " g-d (0
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e APPLICANT: Cormonwealth Edison Conoany c,;
a FACILITY:
Byron and Braidwood Stations j
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SUBJECT:
SufflARY OF MEB REVIEW 11EETING OF TiiE BYR0tuBRAIDH00D FSAR l
A ceeting was held itay 11-13, 1981 in the Westinghouse offices in Bethesda,11D
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with representatives from Cor.nonwealth Edison Company, Sargent & Lundy, and Westinghouse. The purpose of the meeting was tozresolve the open items in 1
the Mechanical Engineering branch reviewlof the Dryon/Braidwood FSAR[which were identified in a draf t Safety Evaluation Report /(transmitted to the applicant by a letter dated April 9,1981). A list of attendees at tne t
cceting is given in Enclosure 1.
The agenda of the meeting is included i
as Enclosure 2.
i The applicant and its eepresentatives proposed a resolution for each issue l
listed in the meeting agenda. The following items were resolved by discussion ~
l and clarification and require no further action by the applicant:
i N2, h8, N10, Ull, h13, N14, H20, H27, U2, B3, B8, 69, B12, B13 mid
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The following items were discussed and a resolution was reacned by the applicant presenting additional information. The items will be closed upon proper docu-mentation in a future auendment to the FSAR:
N1, N3, h5, N6, N7, H9, H12, N16, H18 N19, N21 H22. H24, H26, B4, 85, D7, B10, Bil, B14, B16, and 817 t
The remainder of the items listed in the agenda were not resolved and require the applicant to do further analysis and study. A description of the.open items with the status and method of resolution is as follows:
N4 - The applicant must justify the use of SATAN-IV computer code for loop p'. ping analyses by comparing it with liULTIFLEX, which is i
a code approved by HRC. This comparison should also include the modeling scheme used in SATAN-IV.
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B1 - Byron and Braidwood Stations were designed and constructed based on an SSE of 0.2g with deconvolution of the design spectrum from the ground surface to the bedrock - till interface.
The staff's j
i position is that deconvolution is not appropriate for byron /Braidwood I
1 1
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-2 and that the applicant must reassess the adequacy of the seis'aic nargins in response to SEB's Question 1?0.06. The applicant will address Concerns expressed by HEu in that respense.
i-86 - The computer code PIPSYS used by Sargent & Lunay for integrated 1
piping analysis must be benchmarked in accordance with the fiP.C d'
position as given in i;UREG-1677.
N17 - The staf f disagreed with Westinghouse's position concerning stress 4
criteria for functional capability of Class 2 and 3 austenitic steel bends and elbows. Westinghouse has formed a task force to resolve this issue, with resolution expected in within approximately 2 months.
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l N15, N23, N25, 618 -
These items 'nvolve asymetric loads on reactor internals, NSS5 coroponents supports, and reactor coolant system piping and components.
For each of these items, the unresolvea issue is the need for an assessment of the asycznetric pressure loads. The applicant comitted to provice such an analysis in an amendn.ent to the FSAR in response to Questions 110.14 and 110.62.
C1 - The applicant plans to submit the preservice testing program for pumps and valves in early 1982 and the inservice testing program for punps and *alves in September 1982. This item will be closed upon submittal of the testing progra.as and acceptance by NRC.
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M< I James Snell, Project Manager Licensing Branch No.1 Division of Licensing
Enclosures:
As stated d
cc: See next page i
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Hr'.'J. 3. Abei Dirc:ter ci Muclear Licensing Conmonweastn Edison Company Post Office Box 767 Chicaao. Illinois 60690 ccs:
Mr. William Kortier Mr. Edward R. Crass Atomic Power Distribution Nuclear Safcguards and Licensing Division-Westinghouse Electric Corporation Sargent & Lundy Engineers P. O. Box 353 55 East Monroe Street Pittsburgh, Pennsylvania 15230 Chicago, Illinois 60603 Paul M. Murphy, Esq.
Nuclear Regulatory Commission, Region III=
Isham, Lincoln & Beale Office of Inspection and Enforcement One First National Plaza 799 Roosevelt Road 42nd Floor Glen Ellyn, Illinois 60137 Chicago, Illinois 60603 Myron Cherry, Esq.
Mrs. Phillip B. Johnson Cherry, Flynn and Kanter 1907 Stratford Lane 1 IBM Plaza, Suite 4501 Rockford, Illinois 61107 Chicago, II:inois 60611 Professor Axel Meyer Department of Physics Northern Illinois University DeKalb, Illinois 60115 C. Allen Bock, Esq.
P. O. Box 342 Urbanan, Illinois 61801 Thomas J. Gordon, Esq.
Waaler, Evans & Gordon 2503 S. Neil Champaign, Illinois 61820 Ms. Bridget Little Rorem Appleseed Coordinator 117_ North Linden Street Essex, Illinois 60935 Kenneth F. Levin, Esq.
Beatty, Levin, HG11and, Basofin & Sarsany 11 South LaSalle Street Suite 2200 Chicago, Illinois 60603 i
1 ENCLOSURE 1 Meeting Attendees May 11-13,1981
}l tC Sargent & Lundy J
B. Bosnak W. Cliff E. Heminger E. Crass L. k'hite K. Adlon K. Kiper A. Deguermendjian R. Netzel
- 0. Zaben Argonne S. Putman He Ahmed Westinghouse Commonwealth Edison J. Connor M. Oper J. Westermeier R. Kelly T. Tramm B. Maurer L. Bowen M. Beaumont M. Wright y,-
ENCLOSURE 2 Meeting Agenda MEB Raview of Byron FSAR May 11-13, 1981 i
MEB SER Review Meeting Agenda It' ens Monday Afternoon SER Reference Item Page l
Paragraph Description
Response
N1 1
3.6.2 (3)
Justify break locations from Bob Kelly WCAP-8082A Brad Maurer N2 2
3.6.2 (4)
Justify use of WCAP-8082A with Bob Kelly loop isolation valves Brad Maur:r N3 2
3.6.2 (5)
Describe Westinghouse / BOP Bob Kelly interface for component supports Brad Maurer N4 2
3.6.2 (6)
Justify use of SATAN-IV Bob Kelly Brad Maurer B1 5
3.7.3 (6)
Demonstrate adequacy of seismic J. T. Westermier margins (Deconvolution)
B2/N5 5
3.7.3 (7)
Provide natural frequencies for B2-R. J. Netzel Seismic Cat. I structures NS-Bob Kelly Brad Maurer B3/N6 5
3.7.3 (8)
Provide discussion of modeling B3-A. A. Deguermendjian for pipe supports and snubbers N6-Bob Kelly Brad Maurer B4/N7 6
3.7.3 (9)
Identify equipment for which B4-K. L. Adlon the natural period is not known N7-Bob Kelly Brad Maurer N8 6
3.7.3 (10)
Response to Q110.33 part (4) is Bob Kelly not satisfactory Brad Maurer B5 6
3.7.3 (11)
Identify buried structures and A. A.
Deguermendjian describe seismic analysis
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MEB SER Review Meeting Agenda Items Tuesday Morning i
SER Reference Itcm Fage Paragraph Description
Response
B6/N10 7
3.9.1 (2)
Provide basis for selection of B6-A. A.
Deguermendjian number of masses in seismic N10-Bob Kelly model of piping and components Brad Maurer N11 7
3.9.1 (3)
Specify use of simplified elas-Bob Kelly tic-plastic methods / provide Brad Maurer tabt lar summary of stress ranges N12 8
3.9.1 (4&5)
Justify use of ASME Section III Bob Kelly Appendix F for general compo Brad Maurer nents/Specify deformation / dis-placement limits N13 8
3.9.1 (6)
Justify 4% critical damping for Bob Kelly
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reactor coolant loop and Brad Maurer supports B7 10 3.9.2.1 Document preservice examination L. A. Bowen and pre-operational testing program for all snubbers B8/N14 11 3.9.2.2 Dynamic Qualification of B8-K. L. Adlon mechanical equipment N14-Bob Kelly Brad Maurer Bil/N17 13 3.9.3.1 (1)
Address functional capability Bll-A. A.
Deguermendjian of equipment when service B N17-Bob Kelly limits are exceeded (Question Brad Maurer 110.40)
N19 14 3.9.3.1 (4)
Revise response to Q110.61 Mae Wright regarding tube plugging limit B12/N20 15 3.9.3.2 Pump and valve operability B12-K. L. Adlon r.ssurance N20-Bob Kelly Brad Maurer
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s MEB SER Review Meeting Agenda Items Tuesday Af ternoon SER Feference Itcm Page Paragraph Description
Response
N9 6
3.7.3 (12)
Resolve concerns regarding Mark Beaumont damping valves used for reactor internals seismic analysis B9/N15 12 3.9.2.3 (2)
Impact of revised seismic input B9-R. J. Netzel on safe shutdown evaluation N15-Mark Beaumont B10/N16 13 3.9.3.1 (1)
Provide discussion of load com-B10-R. J. Netzel bination methods and max loads, N16-Mark Beaumont stresses, deformations N18 14 3.9.3.1 (2)
Address reactor internals as Mark Beaumont requested in Q110.15 and 0110.41 N24 18 3.9.4 (2)
List load combinations and Mark Beaumont stress limits for pressure boun-dary items /Specify design crit-eria and load combinations for non-pressure boundary items N25 20 3.9.5 (4)
Address asymetric loading on Mark Beaumont reactor vessel intervals N26 20 3.9.5 (5)
Clarify manner of compliance Mark Beaumont with ASME code N27 20 3.9.5 (6)
Clarify use of unitradicted Mark Beaumont material properties for fatigue evaluation of reactor intervals
r MEB SER Review Meeting Agenda Items Wednesday Morning SER Refereppe Item Page Pa agraph Description
Response
B13/N21 15 3.9.3.3 (2)
For safety and relief valves Bob Kelly discharging to closed system, Brad Maurer include effects of water slugs B14 16 3.9.3.3 (3)
For safety valves that discharg?
A. A.
Deguermendjian to an open system, justify use of DLF less than 2.0 B15/N22 15 3.9.3.3 (4)
Identify safety and relief valves B15-A. A.
Deguermendjian locations, mounting arrangements, N22-Bob Kelly opening sequence, and load com-Brad Maure r bination and stress limits t
B16 17 3.9:3.4 (2)
Justify use of stress limits R. J. Netzel i
50% greater than normal allowables B17 17 3.9.3.4 (3)
Identify ccmponent supports R. J. Netzel which are s'bjected to tempera-u tures greater than ambient B18/N23 17 3.9.3.4 (4)
Respond to Q110.14 and 110.62:
B18-R. J. Netzel asymetric loads on component N23-Bob Kelly supports Brad Maprer C1 22 3.9.6 (4)
Submit program for preservice L. A. Bowen and inservice testing of pumps and valves
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MEETING StM4ARY DI"n!E'~ f 0N eDockerUFile!
G. Lear-NRC P""
- 4. Johnston 8.ocal FDR S. Pawlicki TIC /...nC/ Tera V. Benaroya N. Hughes
- 2. Rosztoczy' LBil P. ::fing W. Haass H. Dentnn D. Muller E. Case R. Ballard D. Eisenhut W. Regan R. Purole D. Ross B. J. Youngblood P. Check A. Schwencer Chief, Power Systems Branch F. Miraglia
- 0. Parr J. Miller F. Rosa G. Lainas W. Butler R. Voiines W. Kreger J.
P. Knignt R. Houston R. Bosnak Chief, Radiological Assessment Branch:
F. Schauer L. Rubenstein R. E. Jeci.30a T. Speis Project Manager K. Kiper/J. Snell M. Srinivasan Attorney. OELD J. Stolz M. Rushbrook S. Hanauer OIE (3)
W. Gammill ACRS (16)
T, Murley R. Tedesco F. Schroeder D. Skovholt M. Ernst NRC
Participants:
R. Baer C. Berlinger B. Bosnak, E. Hemminger K. Kniel L. White, K. Kiper G. Knighton A. Thadani D. Tondi J, Kramer D Vassallo P, Collins D. Ziemann bec: Applicant & Service List t
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