ML20033B944
| ML20033B944 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood  |
| Issue date: | 11/02/1981 |
| From: | SARGENT & LUNDY, INC. |
| To: | SARGENT & LUNDY, INC. |
| Shared Package | |
| ML20033B938 | List: |
| References | |
| NUDOCS 8112020488 | |
| Download: ML20033B944 (11) | |
Text
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CARGENT& LUNDY E N GIN E ERO CHICAGO Proj ect No. 4391/4392-02 4683/4684-02 Commonwealt.h Edison Company Byron /Braidwood - Units 1 & 2 Notes of Meeting Held at Sargent & Lundy Offices on October 20 through 23, 1981 THOSE PRESENT:
E$ L pinski Nuclear Regulatory Commission (NRC)
R.
W. F.
Segersell
)
Commonwealth Edison Company
- A.
K. Singh
)
- F. Y. Aghakhan
)
- M. Amin
)
- A.
Derm enj i an
)
- J. H. Gray
)
- C.
N.
Krishnaswamy )
- T. G. Longlais
)
- R.
R. McCluer
)
Sargent & Lundy
- N.
K. Mehta
)
R.
J. Netzel
)
D.C.
Patel
)
- J.
K.
Patel
)
- S.
Putman
)
- G. Smolak
)
- V.
Singla
)
- V.
V.
Voight
)
O.
Zaben
)
- Pa r t-time 1.
Pur pos e The NRC Structural Engineering Branch perf ormed a Structural design audit of the Byron /Braidwood project.
The purpose of this structural design audit was the following:
a.
To investigate in detail the manner in which the a p-plicant has implemented the structural design criteria committed to in the Saf ety Analysis Report.
Novem ba r 2.
Commonwealth Edison Company November 2, 1981 Byron /Braidwood - Units 1 & 2 Page 2 Notes of Meeting October 26 through 23, 1981 l
b.
To verify that key structural design calculations are i
acce pta ble.
c.
To identify and assess the safety significance of areas that were designed using methods other than those given by the NRC Standard Review Plans and Regulatory Guides.
l l
This audit is considered as an integral part of the licen-sing review process and constitutes the basis for the NRC t
staf f's preparation of the Saf ety Evaluation Report.
2.
Conduct of Audit The attached agenda identifies the Category I str uct ures reviewed during the audit.
In addition, the results of the Seismic Reassessment Program for Category I str uct ures and components were presented to the NRC.
Detailed audit checklists, provided by NRC prior to the auidt, were completed by Sargent & Lundy and used throughout the audit.
The audit of each saf ety related structure began by Sargent & Lundy presenting an overview of the structure including basic description, analysis / design assumptions, modeling techniques and any unique featrues.
The audit sheets were then used to follow through the specific analysis /
design process including the review of key results.
The NRC auditing personnel randomly interjected with questions and requests to review the actual design calculations.
If resolution required additional engineering data to be provided, the specific action item was identified and re-corded in the meeting minutes.
3.
Action Items TL7 attached list of action items was developed during the audit.
This list also summarizes items closed during the audit and identifies the responsibility f or the f ollow-up action items.
Also, attached is a list of documents sub-mitted to the NRC as a result of their requests for additional inf ormation during the audit.
These documents include the design audit forms, Sargent & Lundy calculations and reports, and technical papers.
Commonwealth Edison Company November 2, 1981 Byron /Braidwood - Units 1 & 2 Page 3 Notes of Meeting October 20 through 23, 1981 4.
Conclusion The audit proved to be an ef f ective way of perf orming a licensing review.
The scheduled date for submittal of the Safety Evaluation Report (SER) to the Advisory Acommittee on Reactor Safety is February,1982.
Mr.
R.
Lipinski of NRC stated that if our response to action items is received by December 1, 1981, there stands a good chance of closing these items so that they will not appear as open in the SER.
R.
J. Netzel RJN:kv Copies:
J. Westermeier (2)
A. W. Klienrath (1)
R. Cosaro (1)
G. Sorensen (1)
M. A. Stanish (1)
T.
R.
Sommerfield (1)
R. E. Querio (1)
J.
F. Gudac (1)
C.W.
Fruehe (1)
J. M.
Lavin (1)
V.
I.
Schlosser (1)
G.
P. Wagner (1)
J.
D. Deress (1) i LEA (1) l WAC (1)
RNB (1) l WGH (5)
I DCM (6)
JMM
( 5)
DLL (1)
WCC (1)
s AGENDA 0F NRC AUDIT OF BYRON /BRAIDWD0D PLANTS DATE SUB JECT SPEAKERS / TIME / PLACE Tues.
- 1) Introduction NRC 4
10/20 Purpose 8:30 - 9:00/28E33 8:30 a.m.
End Products Procedures
- 2) Overview of Plant Design 10:00 - 12:00/28E33 a.
General Arrangement R. J. Netzel b.
Seismic Analysis A. K. Singh j
c.
Seignic Reevaluation R. J. Netzel
- 3) Containment 1:00 - 5:00/28E33 a.
Audit of Design S. Putman b.
Ultimate Capacity C. Krishnaswamy I
c.
Interior Structures D. C. Patel/V. K. Singla d.
Action Items NRC-P 8:30 - 5:00/28E33 Wed.
- 1) Auxiliary Bldg.
G. Smolak 10/21
- 2) Essential Service Cooling Towers V. Voight 8:30 a.m.
- 3) Action Items NRC 8:30 - 5:00/29918 Thurs.
- 1) Seisnic Category 1 Tanks F. Aghekhcn 10/22 and Underground Structures A. Dermecj i an 8:30 a.m.
- 2) Crane Supports F. Aghakhan
- 3) River Screen House (Byron)
J. K. Patel
- 4) Action Items NRC j4 l
Friday
- 1) Review of Responses to NRC/S&L 10/23 NRC Questions 9:00 - 1:00/29718 8:30 a.m.
- 2) Schedule
- 3) Adjournment Page 1 of 1 I
a INFORMATION SUBMITTED TO THE NRC FOR THE DESIGN ADEQUACY AUDIT OF OCTOBER 20 THROUGH OCTOBER 23, 1981 PAGES 1.
STRUCTURAL AUDIT FORM OF CONTAINMENT STRUCTURES 1-65 2.
STRUCTURAL AUDIT FORM OF AUXILIARY BUILDING l-84 3.
STRUCTURAL AUDIT FORM OF ESSENTIAL SERVICE COOLING STRUCTURE l-65 4.
STRUCTURAL AUDIT FORM OF REFUELING WATER STORAGE TANKS AND CATEGORY I UNDERGROUND PIPING l-13 5.
STRUCTURAL AUDIT FORM OF FUEL HANDLING BUILDING CRANE l-7 6.
STRUCTURAL AUDIT FORM OF BYRON RIVER SCREEN HOUSE l-61 7.
CABLE TRAY SUPPORT COMPUTER CALCULATIONS 1-13 8.
HVAC HANGER RE-ANALYSIS PROCEDURE l-9 9.
CONTAINMENT STABILITY l-6
- 10. CONTAINMENT LINER REPORT - J. M.
DOYLE & S. L.
CHU 1-7
- 12. CONTAINMENT SKETCHES THROUGH NSSS ENCLOSURES l-4
- 13. ACCIDENTAL EXPLOSION REPORT - S.
T. WU, W.
T.
LI &
B. P. JAIN 1-45
- 14. AUXILIARY BUILDING SHEAR WALL STRESS LEVELS AT ELEVATION 401' l-1
- 15. AUXILIARY BUILDING MAT STABILITY CALCULATIONS 1-15 t
- 16. SHEAR WALL DESIGN PROCEDURE l-14 l
l
- 17. MASONRY WALLS ASPECT RATIO l-4
- 18. MISSILE RESISTANT CONCRETE PANELS 1-38
- 19. AUXILIARY BUILDING SHEAR WALL COMPARISON OF REINFORCING l
STEEL WALL L, Q, 30 1-1 l
l
- 20. ESSENTIAL SERVICE COOLING TOWER CALCULATIONS 1-14
- 21. ANALYSIS OF BURIED ESSENTIAL SERVICE WATER PIPING l-32 l
- 22. SARGENT & LUNDY REPORT 3026 1-28 l
- 23. SEISMIC ANALYSIS OF CRANE BRIDGE GIRDERS & THE CABLE l-12 Page 1 of 1 L
STRUCTURAL DESIGN AUDIT B1 NRC STRUCTURAL ENGINEERING BRANCH OCTOBER 20 THROUGH 23, 1981 LIST OF ACTION ITEMS 1.
Inclusion of additional 5% accidental torsion into the seismic analysis models for the project.
Action:
S&L to assess the impact and provide response to NRC by November 16, 1981.
2.
Response to Question No. 130.19 (Decoupling Criteria).
Action:
S&L discussed the preliminary response with NRC
]
and formal response will be submitted to NRC by November 16, 1981.
3.
Revision to response for Question No. 130.20 (Lumped mass criteria).
Action:
Revision to response was agreed upon between S&L anu NRC.
Formal response will be sent to NRC by November 16, 1981.
I 4.
Additional information in response to Question 130.06 (Seismic reassessment).
Action:
A.
S&L to provide actual stress interaction in reinforced concrete design prior to and i
after the refinements used, for the contain-ment shell and basemat during the reassess-ment by November 16, 1981.
B.
S&L provided sample calculations for cable tray and HVAC supports where ductility ratio exceeded one. (Item closed)
C.
S&L to respond to NRC with the justification l
for the methodology used for cable tray supports (OBE & SSE enveloped spectra used with SSE allowable stress levels) by Noveraber 16, 1981.
5.
Modifications to Byron River Screen House.
Action:
S&L to provide NRC with the extent of modifications required as a result of response to Question 130.09 by December 1, 1981.
Page 1 of 6 l
\\
i STRUCTURAL DESIGN AUDIT El NRC STRUCTURAL ENGINEERING BRANCH OCTOBER 20 THROUGH 23, 1981 LIST OF ACTION ITEMS i
i (cont'd.)
6.
NRC Question No. 130.35 (Transient Loads).
i Action:
Response to this question is acceptable to NRC.
However, S&L will address assymmetric pressure loads on the containment and internal structures l
when responding to Question Nos. 110.14 and l
110.62.
S&L~to respond to these questions by December 1, 1981.
7.
NRC Question No. 130.38 (In-Service Tendon Surveillance).
Action:
S&L to provide justification for the deviation from Regulatory Guide 1.35.
8.
Effect of " jerking" the cable in the Crane Analysis.
Action:
S&L provided a study performed for the Zimmer i
project.
However, S&L to provide summary (as discussed with NRC) concluding that jerki..; of cable has no impact on Byron /Braidwood project.
9.
Containment Stability.
l Action:
S&L provided calculations. (Item closed) l
- 10. Containment Liner Analysis and Design.
i I
Action:
S&L provided liner analysis and design report by J. M.
Doyle and S.
L. Chu. (Item closed)
- 11. NRC Question No. 130.52 (Containment Ultimate Capacity).
1 Action:
NRC to inform S&L of the requirements to answer l
the question, if any.
NRC is also to confirm l
that containment ultimate capacity should not be a SER issue.
- 12. NRC Question No. 130.21 (Deviations from ACI 349).
Action:
S&L to provide response by November 16, 1981.
- 13. Tangential Shear for the Containment.
Action:
S&L to provide impact of ASME Code Case N250 by November 16, 1981, i
Page 2 of 6 i
I
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STRUCTURAL DESIGN AUDIT g
El r
NRC STRUCTURAL ENGINEERING BRANCH OCTOBER 20 THROUGH 23, 1981 LIST OF ACTION ITEMS i
(cont'd.)
- 14. NRC Question No. 130.41 (Conformance to SRP 3.8.2 on Load Combinations).
Action:
S&L provided comparison of criteria between ASME Subsection NE and SRP.
(Item closed)
- 15. NRC Question No. 130.42 (Description of Internal Structures).
Action:
S&L provided additional sketches of the steam generator enclosure wells.
(Item closed)
- 16. NRC Question No. 130.28.
Action:
S&L provided Report SL-3028.
(Item closed)
- 17. Blast Pressure.
Action:
S&L provided SAD Report No. 178.
(Item closed)
- 18. Compliance to Regulatory Guide 1.61.
Action:
S&L provided stress levels for representative i
shear walls.
(Item closed)
- 19. Two inches thick premolded filler joint between Containment and Auxiliary Building.
Action:
S&L to provide physical properties of Ethafoam by November 16, 1981.
{
- 20. Auxiliary Building Stability.
Action:
S&L provided. calculations for the sliding and overturning.
(Item closed) 4
- 21. NRC Question No. 130.49 (Category I E.S.C.W. piping in the Turbine Building Mat).
Action:
S&L to provide NRC with the revised response (Revisions discussed and agreed by NRC) by November 16, 1981.
Revised 03ponse to include the statement that contract quality control records are available at t'
- 22. Shear Wall Design Action:
S&L provided design procedure and example calculations.
(Item closed)
Page 3 of 6 1
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STRUCTURAL DESIGN AUDIT BY.
NRC STRUCTURAL ENGINEERING BRANCH OCTOBER 20 THROUGH 23, 1981 LIST OF ACTION ITEMS (cont'd.)
23.
Masonry Walls Action:
A.
NRC to provide their position in regards to their concerns for unreinforced masonry walls.
B.
S&L to provide a list of interior walls 3
not yet constructed at Byron and Braidwood.
C.
S&L provided the aspect ratios for the masonry walls.
(Item closed) 24.
NRC Question No. 130.25 (Barrier Designs for Missiles).
Action:
S&L provided reference paper and calculations.
(Item closed) 25.
NRC Question No. 130.31 (Shear Walls).
Action:
S&L provided table of actual steel required versus steel provided for the shear walls l
listed in the question.
(Item closed) l 26.
NRC Question No. 130.43 (Description of Category I Structures).
Action:
S&L to provide sketches for River Screen House, Essential Service Cooling Tower, Lake Screen House, Deep Well Enclosure, Safety Valve Room and the additional two sections for the Auxiliary Building.
S&L will provide these sketches by November 16, 1981.
e7.
NRC Question No. 130.53 (Spent Fuel Pool Racks).
Action:
S&L to provide response by November 16, 1981.
28.
Essential Service Cooling Tower.
Action:
S&L provided calculations for sliding of foundation and for the concrete column in the exterior wall.
(Item closed)
Page 4 of 6
. ~. _. _ _ _,... _.. _. _ _ _ _. _ _. _. -. _., _. _. _ -.. _.
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d STRUCTURAL DESIGN AUDIT El NRC STRUCTURAL ENGINEERING BRANCH OCTOBER 20 THROUGH 23, 1981 LIST OF ACTION ITEMS (cont'd.)
29.
Buried Piping Action:
S&L provided design procedure and the calculations.
(Item closed) 30.
Missile Protection for Manhole Cover.
Action:
S&L to provide information for the manhole cover justifying its compliance to missile protection.
S&L will provide the information by November 16, 1981.
l l
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l l
l i
Page 5 of 6
- r. - - -
STRUCTURAL DESIGN AUDIT E
NRC STRUCTURAL ENGINEERING BRANCH OCTOBER 20 THROUGH 23, 1981
SUMMARY
OF ACTION ITEMS Action Item Responsible Scheduled completion Number Engineer Date 4B, 09, 10, 14, 15, 16, 17, 18, 20, 22, 23C, 24, Completed 25, 28, 29 October 23, 1981 01, 02, 03 04A, 07, 08, 13 S. Putman November 16, 1981 04C, 12, 19, 21, 23B, 26, 30 D.
C. Patel November 16, 1981 05, 06 S.
Putman'&
D.
C.
Patel December 1, 1981 27 G.
Kao November 16, 1981 11, 23A NRC As soon as possible.
Page 6 of 6