ML17252A157
| ML17252A157 | |
| Person / Time | |
|---|---|
| Site: | Millstone, Hatch, Monticello, Dresden, Peach Bottom, Browns Ferry, Nine Mile Point, Fermi, Oyster Creek, Hope Creek, Cooper, Pilgrim, Brunswick, Vermont Yankee, Duane Arnold, Quad Cities, FitzPatrick |
| Issue date: | 09/14/1977 |
| From: | Guibert J Office of Nuclear Reactor Regulation |
| To: | |
| References | |
| Download: ML17252A157 (30) | |
Text
{{#Wiki_filter:e .UNITED STATES e NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C.. 20555 SEP 14 1977 DOCKETS NOS.: 50-219, 50-220, 50-237, 50-245, 50-249, 50-254, 50-259, 50-260, 50-263, 50-265, 50-271, 50-277, 50-278, 50-293, 50-296, 50-298, 50-321, 50-324, 50-325, 50-331, 50-333, 50-341, 50-354, 50-355, and 50-366. LICENSEES: Boston Edison Company, Carolina Power & light Company, Commonwealth Edison Company, Detroit Edison Company, Georgia Power Company, Iowa Electric Light & Power Com-pany, Jersey Central Power & Light Company, Nebraska Public Power District, Niagara Mohawk Power Corporation, Northeast Nuclear Energy Company, Northern States Power Company, Philadelphia Electric Company, Power Authority of the State of New York, Public Service Electric and Gas, Tennessee Valley Authority, Vermont Yankee Nuclear Power Corporation FACILITIES: Oyster Creek Nuclear Generating Station, Nine Mile Point Unit No. 1, Pilgrim Unit No. 1, Dresden Units Nos. 2 and 3, Millstone Unit No. 1, Quad Cities Units Nos. l and 2, Monticello, Peach Bottom Units Nos. 2 and 3, Browns Ferry Units Nos. 1, 2 and 3, Vermont Yankee, Hatch Units Nos. 1 and 2, Brunswick Units Nos. l and 2, Duane Arnold Energy Center, Cooper, Fitzpatrick, Enrico Fermi Unit No. 2, and Hope Creek Units Nos. 1 and 2.
SUBJECT:
SUMMARY
OF MEETING HELD ON AUGUST 8, 1977 WITH REPRESENTA-TIVES OF THE MARK I OWNER'S GROUP On August 8, 1977, a meeting was held in Bethesda, Maryland with represen-tatives of the Mark l Owner's Group and the Generic Electric Company (GE). The purpose of the meeting was. to discuss the structural acceptance cri-teria for the Mark I Containment Long Term Program. Enclosure l is a list of the meeting attendees. is a copy of the meeting agenda. Summary The primary purpose of this meeting was to continue the discussions initiated at a previous meeting held on June 17, 1977 related to (1) the assignment of service levels for containment structures and supports subjected to particular postulated load ~ombinations and (2) the assign-ment of basic allowable stress limits to be utilized in the analyses of
'* these structures. Enclosure 3 is a preliminary table of the service levels proposed by the Mark I Owner's Group for the load *combinations under consideration. Enclosure 4 is a summary of the material presented by the Mark I Owner's Group at this meeting. T. Mulford, GE, provided an introduction to the meeting (1) by briefly discussing the areas where the Mark I Owner's Group believes that they are in agreement with the NRC staff, and (2) by identifying the areas .where the Mark I Owner's Group believes it can provide justification. for deviations from a "traditional" interpretation of the Code for ser-vice level assignments. W. Cooper, Teledyne, indicated that the discussions would not include piping, piping supports, or the Brunswick concrete containment, but that these areas would be discussed at a future date. He also indicated that possible increases in allowable stresses on the basis of the dynamic nature of the loadings w6uld not be di~cussed, but that any such increases which can be justified will be presented ~t a future date. W. Cooper discussed the Mark I Owner's propo*sal that SMl allowable stress intensities be utilized for the LTP structural acceptance criteria 1rather than SMc allowable stress intensities. (The SM1 values are 11 to 21 per-cent higher than the SMC values~) The detailed justifications for this proposal are presented in Enclosure 4. With respect to the above-mentioned proposal, the NRC staff stated that it would consider SM1 allowable stress intensities for application in the Mark I LTP only 1f the ASME Code Committee would approve such an approach for application "across-the-board". However, the staff expressed a concern that such a ruling by the Code Committee would most likely re-quire a reinvestigation and subsequent revision of related requirements ! L I for fabrication procedures and preservice and inservice inspections. I W. Cooper presented a table (Chart No. 2 of Enclosure 4) of service level assignments (for certain structural components) and load combina-tions for which the Mark I Owner's believe they are in agreement with the NRC staff's previously stated (June 17, 1977.meeting) positions. The NRC staff stated that the general philosophy behind this table seemed appropriate, but that the staff needs some time to consider the matter further. The staff committed to provide comments to the Owner's Group within two weeks. W. Cooper proceeded to discuss areas where the Mark I Owner's Group believes that justification for deviations from "traditional" interpre-tations of the Code for service level assignments are available. These areas are highlighted in Charts 3, 4 and 5 of Enclosure 4. In general, these proposed deviations would allow local plastic deformation of containment structures which provide a "channeling" function, e.g., the
. vent header between downcomer penetrations, the vent header in the pool swell impingement region. The staff reexpressed its position that , external and internal pressure boundaries, in general, should be treated ! the same since they are both classified as MC by the Code. However, the
- staff also restated its position, as expressed in the June 17, 1977 meeting, that certain deviations allowed,by the Code (e.g., local dynamic loads, jet impingement loads, impulsive loads) would be con-sidered if adequately justified. With respect to deviations based on the dynamic nature of the loadings, the NRC staff requested the Mark I Owner's Group to discuss their programs, if any, designed to mee.t this objective. The NRC staff further expressed its opinion that efforts by the Mark I Owner's Group in this regard would have a higher likelihood of success.
I. The NRC Staff requested information related to the schedule for discu~s*ion on piping, pipe supports, pumps, valves, etc.; the Mark I Owner's Group indicated that such discussions would take place in late August or early September 1977. In conclusion, the NRC staff recommended that the Mark I Owneris Group submit their arguments formally with bases for any deviations from the Code, including a description of any analytical or experimental pro-grams which they were conducting to support these exceptions. i~~ Technical.Assistant Division of Operating Reactors
Enclosures:
As stated
1, ATIENDANCE LIST MARK I CONTAINMENT PROGRAM GE/TRC/NRC WORKING MEETING . E~~losure l ~- STRUCTU~tGe~iE~:A~~~7 CRITERIA NAME K. Herring J. Guibert George O'Connor Randy Broman Larry Steinert Elmer Mangbum Chris Grimes. Sal Mucciacciaro Isa Sihweil C. P. Tan N. W. Edwards B. D. Liaw D. Lynn Whitt R. J. Stuart K. R. Wichman L. C. Shao T. J. Mulford Pei-Ying Chen G. Bagchi F. E. Gregor REPRESENTING 'NRC/DOR/EB NRC/DOR Yankee Atomic Elec:tric Co. Bechtel san Fr~n~isco GE GE NRC/DOR/PSB I Stone & Webster, Cherry Hill, NJ NRC/DSS/SEB NRC/DSS/SEB NUTE CH NRC/DOR/EB CBI NRC/DOR/EB NRC/DOR/EB , NRC/DOR/EB GE NRC/DSS/MEB NRC/DOR/EB DECO ? , 1, ' ~ '\\,
0900 0915 0930 1015 1130 1230 1500 1530 TJM 8/8/77
- e AGBmA MARK I CONTAINMENT PROGRAM STRUCTURAL ACCEPTANCE CRITERIA MEETING WITH NRC AUGUST 8~ 1977 INTRODUCTION BACKGROUND DISCUSSION OF SMlvs. SMC ALLOWABLE STRESS INTENSITIES
. DISCUSSION OF LEVEL ASSIGNMENT AGREEMENTS BETWEEN NRC AND UTILITIES LUNCH MULFORD COOPER COOPER COOPER DISCUSSION OF LEVEL
- . COOPER ASSIGNMENT DISAGREEMENTS BETWEEN NRC AND UTILITIES CLOSURE -
- STEINERT DISCUSSION OF FUTURE ACTIONS ADJOURNMENT
MARK I CONTAINMENT PROGRAM STRUCTURAL ACCEPTANCE CRIT~RIA ACTIVITY 3.1. 3 PLANT UNIQUE ANALYSIS APPLICATION GUIDE, August 8, 1977 P~esentation to NRC Concerning COMPONENT~LOADINGS - SERVICE LEVEL ASSIGNMENTS "~TELEDYNE ENGINEERING SERVICES 303 BEAR HILL ROAD WAL THAM, MASSACHUSETTS 02154 617-890-3350
MARK I CONTAINMENT - STRUCTURAL DESIGN: CRITERIA*~ PURPOSE OF MEETING: TO EXCHANGE THOUGHTS WITH NRC CONCERNING SERVICE CEVEL ASSIGNMENTS FO~ CONiAINMENT STRUCTURES*AN~ S0~PORTS AND THE BASIC . ALLOW~BLE STRESS TO BE USED. . COMMENTS:
- 1.
CHARTS DISCUSSED GO IN SECTION 5 DF PLANT UNIQUE ANALYSIS APPLICATION GUIDE.
- 2.
PIPING AND PIPING SUPPORTS.AND THE BRUNSWICK CONTAINMENT WILL BE DISCUSSED AT A LATER DATE.
- 3.
ONLY *LOAD COMBINATIONS INVOLVING 11 NEW 11 LOADS ARE DISCUSSE.D. LOAD AND LOAD COMBINATION DEFINITION A~E NOT PART OF THE SOC EFFORT.
- 4.
THE CONTAINMENTS WERE ORIGINALLY CONSTRUCTED USING DESIGN PRESSURES AND DESIGN TEMPERATURES WHICH ARE NOT. CHANGE~ ~S A RESULT OF THE NEW LOADS.
- 5.
POSSIBLE INCREASES IN ALLOWABLE STRESSES AS A RESULT OF THE DYNAMIC NATURE OF THE LOADINGS ARE NOT YET INCLUDED. ANY WHICH CAN BE.
- JUSTIFIED WILL BE PRESENTED ~T A LATER DATE.
~TI*~~ a+/-i~ .\\-o d~ bo.-<1 *~ ~ ~ ~~* r~ ~~ ~~ OV'--.
l ~~~K I CONTAINMENT APPROACH TO STRUCTURAL DESIGN CRITERIA
- 1.
PLANT UNIQUE ANALYSIS APPLICATION GUIDE (TES TR-2278(c)) WILL:
- 2.
A. CODE CLASSIFY THE STRUCTURAL ELEMENTS B. REFER TO LOADS AND LOAD COMBINATIONS CONTAINED IN THE LOAD DEFINITION REPORT C. REFERENCE THE CODE AND STANDARD RULES TO BE APPLIED, OR APPROVED ALTERNATIVE CRITERIA D. WHEN NECESSARY, PROVIDE ANALYSIS GUIDANCE I~ GENERAL, THE CODE RULES DEFINED ARE: CLASS MC VESSELS - SUMMER 1977 ADDENDA COMPONENT SUPPORTS - WINTER 1976 ADDENDA
- 3.
'n'i-'.EN COMPLETE APPLICATION OF THESE CRITERIA RESULT IN HARDSHIPS OR UNUSUAL DIFFICULTIES WITHOUT A COMPENSATING INCREASE lN THE LEVEL OF QUALITY AND SAFETY, OTHER STRUCTURAL ACCEPTANCE CRITERIA MAY BE CONSIDERED ON A PLANT SPECIF IC BASIS AFTER NRC APPROVAL.
11 ~ESTORATION OF THE ORIGINAL DESIGN MARGIN
- 1.
DESIGN MARGIN IS A QUALITATIVE ASSESSMENT OF RISK.THAT INCLUDES CONSIDERATION OF THE EXTENT OF KNOWLEDGE OF THE APPLIED LOADINGS, THE EXACTNESS OF THE STRESS ANALYSIS, ANO THE EXTENT TO WHICH THE DESIGN CRITERIA ADDRESS SPECIFIC FAILURE MODES. IT IS.NOT A NUi'IERICAL QUANTITY TO WHICH A SPECIFIC VALUE CAN BE ASSIGNED.
- 2.
EARLY VESSEL DESIGNS FOLLOWED A "DESIGN BY RULE 11 APPROACH CONSIDERING . ONLY A STATIC DESIGN PRESSURE ANO SEISMIC ACCELERATION WITH THE STRESSES EVALUATED BY SIMPLE MEMBRANE ANALYSIS ANO LIMITED TO 28 PERCENT OF THE MINIMUM TENSILE STRENGTH OR, FOR BUtKLING, NOMINALLY 25 PERCENT OF CRITICAL LOAD. 3.. LATER VESSEL DESIGNS SUPPLEMENTED THE ABOVE PROCEDURES WITH MORE DETAILED, BUT STATIC, LOAD AND STRESS EVALUATIONS. SUPPORT DESIGNS FOLLOWED STRUCTURAL STEEL PRACTICES (AISC) WHICH CONSIDERED T~E SAME TYPES OF LOADS AND ANALYSIS AND tIMITED THE STRESSES TO 60 PERCENT OF THE MINIMUM.YIELD STRESSES. TES TR-2278(b) REVIEWS THE HISTORY OF THE CODE RULES IN DETAIL. ..\\2- '"'\\
- \\...;>(~ **
~~ollv~~~~~~ ~~b~,.--~~~
\\U t ~ *~ f ~ l \\Iv~ ~ \\, .f ~ t..)./ BASIC ALLOWABLE STRESS VALUE RECOMMENDATION: THE BASIC ALLOWABLE STRESS VALUE USED BE THOSE NORMALLY USED FOR SECTION III CLASS 2 VESSELS DESIGNED TO SUBARTICLE NC~3200 RATHER THAN THOSE NORMALLY USED FOR CLASS MC VE.SSELS. NUMERICAL EXAMPLE: USING THE VARIOUS GRADES OF SA...;516 AS A TYPICAL VESSEL MATERIAL: GRADE: 60 65 70 VALUE OF: SMC SMl SMC SMl SMC SMl lOOF 16.5 20.0 17.8 21.7 19.3 I 23.3 200F 16.5
- 19. 5 *.
17.8 21.3 19.3 23.1 300F 16.5 18.9 17.8 20.7 19.3 22.5 400F 16.5 18.3 17.8 20.0 19.3
- 21. 7 THE SMl VALUES ARE 11 TO 21 PERCENT HIGHER THAN THE SMC VALUES.
NOTES:
- 1.
SA-36, IF APPLICABLE, DOES NOT HAVE SMl VALUES, SO THE SMC V~LUE WOULD BE USED.
- 2.
FOR LEVEL C SERVICE LIMITS THERE WOULD BE NO EFFECTIVE CHANGE SINCE S IS LARGER THAN 1.2 SMl OR 1.2 SMC FOR THE MATERIALS OF INTEREST.
- 1. ~i WU..
\\~Q.,-Y... l:;_i f'L-V'.rl . ~~ ~ ~ \\,_.~* f\\ t\\ ~.~ I ~U lo.. \\ '1-l\\)_'~ c~~- ~ 8 ~(--~""LOO c~\\.4 ~ \\~ D ~ ~ ~ ... ~&..~ci> f\\.}e~
JUSTIFICATION FOR RECOMMENDED ALLOWABLE$
- 1.
CLASS 2: RULES ARE ACCEPTED FOR COMPONENTS WHICH FUNCTION IN . PARALLEL WITH THE CONTAINMENT SYSTEM, INCLUDING (R.G. 1.26): A. EMERGENCY CORE COOLING SYSTEMS . B. POST-ACCIDENT CONTAINMENT HEAT REMOVAL SYSTEMS C. POST~ACCIDENT FISSION PRODUCT REMOVAL SYSTEMS D. REACTOR SHUTDOWN SYSTEMS E. RESIDUAL HEAT REMOVAL SYSTEMS ~*.~ ~s..t~ ~ ~~ ~
- 2.
MATERIALS: ALL MATERIALS PERMITTED FOR CLASS MC VESSELS ARE PERM ITT ED FOR NC-3200 VESSELS. ( ~~ .\\) '5A - ~<o) 3; DESIGN: NEXT SHEET
- 4.
FABRICATION:
- SINCE 1963, CLASS MC WELD JOINT DESIGNS FOR ALL
. CATEGORIES HAVE BEEN AS RESTRICTIVE AS FOR NC-3200 VESSELS.
- 5.
EXAMINATION: THERE ARE NO SIGNIFICANT DIFFERENCES BETWEEN CLASS MC AND NC-3200 VESSELS FOR MATERIALS LESS THAN 2-1/2 INCHES THICK.
- 6.
- TESTING:
THE TEST PRESSURE FOR CLASS MC VESSELS IS HIGHER THAN
- .-.2 (4'..
THAT REQUIRED FOR NC-3200 VESSELS. ( \\~S~o AY.l
- 12:>10)
- e.
DESIGN JUSTIFICATIO~~ FOR RECOMMENDED ALLOWABLES
- 1.
SUMMER 1977 ADDENDA DESIGN AND ANALYSIS REQUIREMENTS FOR CLASS MC VESSELS ARE THE SAME AS THOSE REQUIRED FOR NC-3200 VESSELS EXCEPT FOR THE BASIC ALLOWABLE STRESS VALUE. THAT IS; A "DESIGN BY ANALYSIS". APPROACH IS USED.
- 2.
"DESIGN BY ANALYSIS" REQUIRES DETAILED LOAD DEFINITION AND STRESS ANALYSIS AND COMPARISON OF THE CALCULATED STRESS INTENSITIES WITH DESIGN CRITIERA RELATED TO IMPORTANT FAILURE MODES, INCLUDING FATIGUE.
- 3.
EXCEPT FOR CLASS MC VESSELS, WHERE CONSIDERATION HAS NOT YET BEEN GIVEN, THE CODE APPLIES A NOMINAL FACTOR OF SAFETY OF THREE ON THE MINIMUM TENSILE STRENGTH WITH THE "DESIGN BY ANALYSIS!' APPROACH AND A NOMINAL FACiOR OF FOUR WITH THE "D~SIGN BY RULE" AP~ROAC~. CONCLUSION AS IS DEMONSTRATED BY THE ACCEPTANCE OF THE "DESIGN BY ANALYSIS" APPROACH AS AN ALTERNATIVE TO THE "DESIGN BY RULE" APPROACH FOR SECTION II I, CLASS 2 AND SECTION VIII VESSELS, BOTH APPROACHES (WHEN COUPLED WITH THEIR RESPECTIVE RULES FOR MATERIALS, FABRICATION, EXAMINATION ANO TESTING) AHE CONSIDERED T.Q RESULT IN EQUIVALENT.DESIGN MARGINS.
IMPLEMENTATION OF THIS RECOMMENDATION Revise Table NE-3221-1 as Shown: Ll L2 LJ L4 I TAllLE NE-3221*1 - SUHHART OF STRESS INTENSITY LIHITS sa~u 1917 ADDEUDA LO/ID I HG LEVEL LEVEL ll SERVICE LEVEL C SERVICE STRESS cor;o1T10N A STRESS llHENSITY INTCNSlTY LIH!T Wll[RE TllE DESl!'ll SEKYICE LIMIT l\\NO LCVEL C STlllJCTURE IS !llTCGnAL STRESS STRESS SERVICE STRESS AttO COllT I HUOUS ANO INTENSITY INTENSITY LIHI T WHERE TllE LEVEL 0 SERVICE STRESS LIMIT LIHIT STRUCTURE IS NOT LIHI T HllEltf TllE !!!!£GAAL NH! CO'!!! !!t"ryJ~ 5Tn11rT11nC' '" 11nT l**V... IV*\\i.. IJ U""I INTEGRAL AflD CONTINUOUS (5) (5) AtlO /IT P/IRTJ/ll SYMBOL PEllETMTION WELDS ( S) pll 1.0 sine 1.0 sml 1.0 sml L2 sml or
- 1.0 Sy PL
- 1. 5 Sn:
1.5 sml 1.5 sml 1.8 sml or
- 1.5 Sy PL + Pb 1.5 smc 1.5 sml 1.5 5ml 1.8 sml or
- 1.5 Sy PL + Pb + Q H/A (1) 3~0 sml 3.0 sml (3) ti/A (.l l PL + Pb + Q +. F H/A (1) s,
- s. 13)
H/A (1) ilOTES:
- 1. II//\\* llo 0V1luatlon requlrad.
- 2. Limits tdentlfled by (6 ) Indicate$ a chotce o~ tho larger or two l1111ts.
J, evaluation.not required for level C Service.
- 4. s,,1s 651 or the general prtinarfmctrbrane allowabla.permltted. ln the application of the rules or Appendix F, S 111j, if applicable; shall be as speclfitd in Table 1-1.0.
- LEVEL D SERVICE STRESS INTENSITY LIHIT llllERE THE STRUCTUR£ IS INTEGRAL & CONT.
(ELASTIC AllAf.YSIS) ( 4) . s, 1.S Sr 1.5 s, H/A (1) NIA (l)
- 5. If SA-36 material is used, Smc values' from Table I-1.10 shall be used.
LEVEL D SERVICE STR£SS lllHNSITY
- LllHT llllCRE TllE STRtiCTURE IS INTEGRAL NiO CO!IT I llUOUS (I :~L~AS T: C A!lllLYSIS)
(4) s, s, s, ff/A (1) H/A (1) -{ -I
- o 10 I
(') N ::r N
- 3
-..J......
- con
~~ - ;o r.i "O 0 ""I c-+ I N N I
STRUCTURAL-ELEMENT ROW External Class MC Torus Shell (Gener al, *Ring Girder, at Supports and Penetrations), External Vent Pipe, 1 Be 1 lows, Drywe 11 (at Vent), Attach-ment Welds, Torus Supports, Sei5"11c Restraints Internal Vent Piee General and 2 Attachment Welds At Penetrations 3 (e.g., Header)
- I.
Pool Swell 4 Impingement Region Vent Header General and 5 Attachment Welds At Penetrations 6 (e.g., Downcomers) Pool Swell .7 Impingement Region Down comers General and 8 Attachment Welds Pool Swell 9 Impingement Region Internal Su~~orts 10 Internal Structures Submerged 11 Non-Submerged 12
EVENT COMBINATIONS Type of Earthquake COMBINATION NUMBER LOADS Normal (D + L + TA + RA) Earthquake SRV Discharge LOCA _Thenna 1 LOCA Reactions LOCA Quasi-Static Pressure LOCA Pool Swell LOCA Condensation Osei llation LOCA Chugging ~ ~- ~$~ ~ ~-~ 6.-e.. ~ -.p,f2 ' ( <;~J) s f:,A-r~1) (5£~/~A I s.<:. v,,) f; ~PONENT -. LOADINGS - SERVICE LEVEL ASSIGNMENTS (h64) SRV SRV SBA IBA SBA IBA SBA IBA
- SBA, IBA, llBA nR4 + EO
+ + + + +
- SRV, SRV, PS co, PS CO, EO EO EQ SRV SRV
[1' [1' CH 0 s 0 s 0 s 0 s 0 s 0 s 0 1 2.. 3 4 5 .6 7 8
- 9 10 11 12 13 14 15 16. 17
- 18.
19 20 N x x x x x x x x x x x x x x x x x x x x EQ x x x x x x x x x* x -X x x x x x x SRV x x x x x x x x x T,. x x x x x x x x x x x x x x x x x R4 x x x x x x x x x x x x x x x x x PA x x x x x x x x x x x x x x x x x PPS x x x Pco x ~ PCH x x x x x x x x x x x x x x ~ ~*I ~' ~~Jw.,.....'1~ 3-~ (~t:..-.a) >-),,...,\\~lo ~ ~~ ~f'-V ~ u....._ b b.._ ~u..D (LO<<)
- ) ~
~~ ~ .t <i-,1-4, (,.....,_,,,_lo "1...:1- <.-4.J-) CH s 21
- ;~
x x* - ;::~ x x (.- x x x
THE FOLLOWING CHARTS CONTAIN THE COMPONENT-LOADINGS - SERVICE LEVEL ASSIGNMENTS, EXCEPT FOR PIPING. ALL CONTAIN THE SAME INFORMATION WITH RESPECT TO EVENT COMBINATIONS, COMBINATION NUMBERS ANO LOADS. THE REMAINDER OF EACH CHART MAY BE OESCRIBEO'AS FOLLOWS: CHART 1 2 /\\ . 3. CONTENT COMPLETE C..~ CONSISTENT WITH PREVIOUS NRC COMMENT MAY DEVIATE FROM PREVIOUS ~J ~ v*vi .-ti NRC COMMENT IV :{loV CO\\'"'~ 4 ~J*'°' ~Pt ) -:~~ ) - '(j > ~l t J*ct"'. I il.'fY.~t-0 ((la. 0,..,..,. (.,l-l ~p*' ~* &cP-oY 6 7 8 DEVIATION BECAUSE OF POOL SWELL CONCERNS DEVIATION BECAUSE OF CHUGGING
- CONCERNS
SUMMARY
CONCERNING POOL SWELL
SUMMARY
CONCERNING CHUGGING
SUMMARY
CONCERNING SRV
COMPONENT
- LOADINGS - SERVICE LEVEL
~NKENTS I I ] EVENT COMBINATIONS 15HV SRV SBA !BA SBA IBA SBA !BA I
- SBA,
!BA, -P~*co~.___ OBA_+ EQ + + + + :
- SRV, SRV, PS-CO, CH -
EQ EQ EQ SRV SRV i EQ EQ Of ~----*-- 0 ! s I 0 I S Type of Earthquake
- s 0
0 s Q I s 0 s 0 s i COMBINATION NUMBER l I 2 I J 4 5 6 7 8 9 10 11 I 12 13 14 15 16 17 18 19 zo 21 LOADS Normal N x x x x x x x x
- l x
x x x x x x x x x x x (O + L + T + R ) . 0 0 Earthquake EQ x x x x x x x x x x x x x x. JI x x x SRV Discharge SRV x x x x x x x x LOCA Thermal TA x x x x x* x x x x x x x x x x x x x LOCA Reactions RA x x x
- x.
x x x x x x x x x x x x x x LOCA Quasi-Static PA x x x x x x x x x x x x x x x x x x Pressure LOCA Pool Swell PPS x x x LOCA Condensation Pco "' '..?.* x
- x.
x Oscillation LOCA Chugging PCH x x x x x x x x x x x x x x x STRUCTUltAL-E~EHENT ROW External Class MC Torus Shel 1 (General, Ring Girder, at Supports and Penetrations), External Vent Pipe, 1 " 8 c A A B c 8 c A A B c B c B I B c B c Bellows, Orywell (at Vent), Attach- ~nt Welds, Torus Supports, Seismic Restraints Internal Vent P12e General and 2 A B c A A B c 8 c A A B c B c B B B c B c Attachment Welds At Penetrations 3 II B c A A B c B c A A B c B c c c c c c c (e.g., Header) Pool Swel 1 4 N,'A N/A N/A N/A N/A N/A N/A N/A N/A N/A k/A N/A N/A N/A N/A D 0 D D D D Impingement Region Vent Header General and s A 8 c A A B. c B c A A B c 8' c B B B c B c Attachment Welds At Penetrat Ions 6 A B c c c c D c 0 c c c 0 c D c c c c 0 0 (e.g., Downcomers) Pool Swell 7 N,'A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A D D 0 0 0 D l111plngement Region Downcomers General and B II B c A A B c B i: A A B c B c c c c c c D Attachment Welds Pool Swell 9 N/A N/A N/A N/A N/A N/A N/A If/A If/A N/A N/A N/A N/A N/A N/A D 0 0 0 0 0 Impingement Region Internal Su2e!!rts 10 II B c A A 8 c B c A A B c B c B B B c B c lnterna 1 Structures Submerged 11 II B c A 'A c 0 c 0 c c 0 E 0 E E E E E . E E Non-Sublnerged 12 N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 0 0 E E E [
COMPONENT _: LOADINGS - SERVICE LEVU ASS-llTS. CONSISTENT WITH PREVIOUS NRC COMM£NTS EVENT COMBINATIONS SRV SRV SBA IBA SBA IBA* SBA + + + + EQ EQ EQ SRV T~ of Earthquake 0 s 0 s 0 s COMSINATIOll NUMaER l 2 3 4 5 6 7 8 g 10 ~ Normal II x x x x x x x
- x x
x (D + L + T0 + R0 ) Earthquake EQ x x x x x x x SRV Discharge SRV x x x x LOCA ThenUl TA x x x x x X: *x LOCA React ions RA X' x x x x x x LOCA Quasi-Static PA x, x x x x x.* x . Pressure LOCA Poo 1 Swel 1 PPS LocA Condensation Pco Osc111at Ion LOcA Chugging PCH x x *x x x x .x STRUCTURAL 0-ElEMENT ROW External Class MC Torus Shell (General, Ring Girder, at Supports and Penetrations), External Vent Pipe, 1 A B c A A B: c* B c A Bellows, Drywe 11 (at Vent), Attach-ment Welds, Torus Supports, Se151111C Restraints Internal Vent Piee General and 2 A B c A A B c 8 c A* Attachment Welds At Penetrations 3 A B c A A B c B c A" (e.g., Header) 'Vent Header Genera 1.a*nd 5 A B c A
- A B
c B c "A Attachment Welds At Penetrations 6 A B :c (e.g., Downcoiners) Oowncomers General and 8 A B c A A B. c B c A Attachment Welds Internal Sue~rts 10 A B c A A B c B c A Internal Structures Sui:-rged 11 A B c A A c D c 0 c Non-Submerged 12 .N/A N/A N/A N/A N/A
- N/A N/A 11/A II/A II/A
~1'-1/W ~;J CL~~J_ cft-h (UM.£_, c~dw/~~ 1¢. ) ,M((P /{,
- . r:/.
IBA
- SBA,
+
- SRV, SRV EQ 0
s 11 12 13 x.
- X x
x x x x x X. x. x x x x x x. x* .X
- ,x x
x A. B. c A B c A B c A B .c A B c A B c c 0 E 111A. II/A N/A
- IBA, DBA D8A + EQ
- SRV, PS CO, PS CO, CH EQ CH 0
s 0 *s o* s 14 15 16 17 18 19 20* 21 i: x x x x x x *x x x x x x X. x ): x x x x x x x x ). x .X X. x x x x x x X. x x x x x x x x x x x x x
- x x
~- ~ ~ (,,i~:(; KB c B B c c A Pr B c ce:z, B c B c B c c c it k B.. c ~ B BJ *s c B c c B c c ~,J\\_ ~ B c "-B ~l B c B c 0 E E E E E E E
- N/A,N/A 0
0 E E E E lJ 9)1
\\ l[VENT. COMBINATIOllS SRV SRV SBA + EQ ..Type of Earthquake* 0 s COMB INATIOft NUMBER 1 2 3 4 I LOADS
- Normal N
x x. x. x (D + L + T0 + R0 ) I Earthquake EQ x x SRV Discharge SRV x x x tOCA Thenlla 1 TA x LOCA Reactions RA x LOCA Quasi-Static PA x Pressure LOCA Poo 1 Swe 11 PPS LOCA Condensation PCO Osc11 latlon. LOCA Chugging PCH x STRUCTURAL-ELEMENT .8Q!! Internal Vent Plee At Penetrations 3 (e.g., Header) Pool Swell 4 Impingement Region Ve.nt *Header At Penetrations 6 ~ c (e.g *.* Downcomers) r--.. Pool Swell. 7 Impingement Region i Downcomers Geheral and 8 Attachment Welds Pool Swell 9 Impingement Region ,.**e COMPONENT -.LOADINGS - SERVICE LEVEL ASSI&MlfTS MAY DEVIATE FROM PREVIOUS NRC CCllMENTS IBA SBA IBA SBA IBA
- SBA, IBA,
+ + + +
- SRV, SRV, EQ EQ SRV SRV EQ EQ 0
s 0 S* 0 s 0 s 5
- 6 7
8 g 10 11 12 13 14 15 x x x x x x x x x x x x x x x x x x x x x x x x x x x x x x x Ji. x x x x x x x x x x X: x x x x x x x X, x x X. x x x x x x x x x x x x x x x x x c c D c o* c c c D c D .OBA PS CO, PS CH 0 16 17 18 x x. x x x x x x x x x x x x x x x x. x vt c ~ c D D D c c c D D D ~~ c D D D I OBA + EQ CO, CH s 0 s 19 20 21 x x x x x* x x x x x x x x x x x x x x x c D D D D D D D D c D D D D
COMPONENT - LOADINGS - SERVICE LEVEL ASSIGNMENTS DEVIATION BECAUSE OF POOL SWELL CONCDIN
- EVENT COMBINATIONS SRV SRY SBA IBA SBA IBA SBA IBA
- SBA, IBA, OBA OBA + EQ
+ + + + +
- SRY, SRY, PS eo;*- ps *- - -*-co, CH EQ EQ EQ SRY SRY EQ EQ CH Type of Earthquake 0. s 0
s 0 s 0 s 0 s 0 s 0 s COMBINATION NUMBER 1 2 l 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 LOADS Normal N x x x x x x x x x x x x x x x x x x x x x
- (o + L + T0 + R0 )
Earthquake EQ x x x x x x x x x x x x x x x x x x ./ SRV Discharge SRV x x x x x x x x x LOCA Therma 1 TA x x x x x x x x x x x x x x x x x x LOCA React ions RA x x x x x x x x x x x x x x x x x x LOCA Quasi-Static PA x x x x x x x x x x x x x x x x x x Pressure LOCA Poo 1 Swe 11 Pp5 x x x LOCA Condensation Pco x x x Osei llation LOCA Chugging PCH x x x x x x x x x x x x x X. x ~* STRUCTURAL-ELEMENT ROW Internal Vent Pl~e At Penetrations l c c c c (e.g.* Head<.!r) Pool Swell 4 D D D D D D Impingement Region Vent Header
- /~y
.;\\ ~ At Penetrations 6 c c (e.g., Downcaners) Pool Swell 7 D D D D D D Impingement Region Downcomers General and 8 c c Attachment Welds Pool Swell 9 0 0 0 0 0 D Impingement Region
EVENT COMBINATIONS SRV SRV SBA + EQ Type of Earthquake 0 s COMBINATION NUMBER 1 2 3 4 LOADS ~...
- Normal N
x x x x (D + L + T + R ) 0 0 Earthquake EQ x x SRV Discharge SRV x x x LOCA Thermal TA x LOCA Re~ctions RA x LOCA Quasi-Static PA x Pressure LOCA Pool Swe 11 . PPS LOCA Condensation Pco Oscillation LOCA Chugging PCH x STRUCTURAL-ELEMENT ROW Vent Header At Penetrations 6 c (e.g., Downcomers) Downcomers General and 8 Attachment Welds COMPONENT - LOADINGS - SERVICE LEVEL ASSIGNMENTS DEVIATIOR BECAUSE Of CHUG6ING COHCERN IBA SBA IBA SBA IBA
- SBA, IBA,
+ + + +
- SRV, SRV, EQ EQ SRV SRV EQ EQ 0
s 0 s 0 s 0 s 6 7 8 9 10 11 12 13 14 x x x x x x x x x x x x x x x x x x x x x x x x x x x x x x x x x x x x x x x x x X. x x x x x x x x x x x x x x. x x x x x x x x c c D c D c c c D c OBA OBA + EQ PS co. PS CO, CH Of s 0 s 0 s 15 16 17 18 19 20 21 x x x x x x x x x x x x x x x x x x x x x *X x x x x x x x x x x x x x x x x x x x.* x x x x x D c D D c c D
COMPONENT - LOADINGS
- SERVICE LEVEL ASSIGNMENTS SUllWIY COHCERNlllG POOL SWELL EVENT COMlllllATIONS SRV SllV SBA IBA S8A IBA SIA IBA SBA0
- IBA, OBA.
OBA * [Q +
- SRV, SllV, PS CD, PS CO, CM EQ IQ EQ SRV SRV
. EQ EQ Of Type of Earthquake 0 s 0 s 0 s 0 s 0 s 0 s 0 s .COMB I NA Tl OH NUMBER 1 2 3 4 5 6 7 8 II 10 11 12 13 14 15 16 17 18. 19 20 21 STRU~TURAl.-ELEHENT fill!!.
- .:~
'Ql!mmr WIT~ MAC 'OMICENT~ ~.Ll!m.~
- Toru1 Sha 11 (General, Ring Girder, at Support*
and Penetrat Ions), 9 8 c Externa*l Vent Pipe, 1 Be 11 ows,. Or ywe 11 (at Vent), Attach* ment Welds, Torus Supports, ~eismlc Restraints Internal Vent Pipe General and z ( ;:!: _____ *~ c ---- Attacl'lnent We Ids ~ At Penetrat Ions 3 c (e.g., Header) I Vent !!!*der b &ener1l and s i; Attaci-nt Welds At Penetrat Ions 6 c (e.g., Downc01111trs) ~~__!'.!. ~ ? Gener* I and 8 c At ttctrnent We 1 d*
- , '1J Internal Sup!>flrh 10
..a c I Internal Structures* ./.~ :~* " Submerged 11 J E E .E Non-Submerged 12 D E E APPL T LEVEL C' lltl£RE llR£ HAS B lnterntl Vent Pipe At Penetrat Ions l ( c c....., -~. (e.g., Header) Vent Header At Penetrations 6 ,......c y (e.g., Downt0111ers) llowcorners (L/~..---"~ General and 8 Attachment Welds APPLY LEVEL D WHERE* llRC HAS 8 DR C. lnt~rn9I ~!nt Plj!! !!!!ill!!!!!!. Downcomers Pool Swell 4,7,9 D 0 D D D D I
-EN~ - LO~DINGS. - sER.mE LEvn 1~~
SUMMARY
CONCERNING CHUGGING EVENT COMBINATIONS SRV SRV SBA IBA SBA IBA SBA IBA
- SBA, IBA, D8A OBA+ EQ
+ + + + +
- SRV, SRV, PS co.
PS co. CH EQ EQ EQ SRY SRV EQ EQ Cll Type of Earthquake 0 s 0 s 0 s 0 s 0 s 0 s 0 s COMBINATION NUMBER l 2 J 4 5 6 7 a g 10 11 12 13 14 15 16 17 18 1g 20 21 STRUCTURAL;ELEMENT ROW CONSISTENT WITH NRC C()ll'ENTS bternal Class MC Torus Shell (General, Ring Girder, at Supports I and Penetrations), External Vent Pipe, l A A B c B c A A B c B c B a c Bellows, Orywell (at Vent), Attach-ment Welds, Torus Supports, Seismic Restraints Internal Vent Plee General and 2 A A B.. C*.. B c Attachment Welds A A a c B c a a c At Penetrations J A (e.g., Header) A B c c'.8 c A A *B c a c c
- .. ::1
- *~ ~
Vent Header ,1.; General and 5 A A 8 c. 8 c A A B c B c B B C* Attecllftent We Ids Downccners General and 8 A A B.c a c A A a c a c Attacllftent Welds Internal Sue1!2rts 10 A A a :C .. a c A A a c a c a a c Internal Structures .* ~ Sublllerged 11 A A c D
- c D
c c D E D E E E E Non-Sublllerged 12 NIA NIA N/A 11/A II/A N/A N/A N/&..,. U/A,.,. U/A n r r APf!L Y LEVg; ' WKUE !!!!C HAS A OR 8 jntgrna l Vent Pi!!!! At Penetrat Ions J c c (e.g., Keader) ,(jj Vent Header i At Penetrat Ions 6 c c c c c c c c c (e.g., Downcoaaers) lloMlccners I. General and 8 c c Attachlllent We Ids APPLY LEVEL D WHERE NRC HAS B OR ~ * \\ Vent Header I:. At Penetrations 6 D D D 0 0 0 (e.g., Oowncomers) Downcomers Gener1l and 8 D Attacllllent Welds ~ Jl 11 *1i j\\,,.. ~*.. ~ ~~ lt } ~.'~ .:If' v; l~{f} y ~~ ~ -- .. ~./;fA. --~ t\\. '
COMPONENT - LOADINGS - SERVICE -LEVEL ASSIGNMENTS SUlfilARY COXCERNING SRV EVENT COMBINATIONS SRV SRV S8A IBA SSA IBA SBA IBA
- SBA,
- JBA, DBA OBA + EQ
+ + +* + +
- SRV, sav.
PS co. PS CO, CH EQ EQ £Q. SRV SRV El~ EQ CH Type of Earthquake 0 s 0 s 0 *' :*s 0 s. 0 s 0 s 0 s ~.. C<MIINATION NUMBER 1 2 3 4 5 6 7 8 9* 10 11 12 13 14 15 16 17 18 19 20 21 STRUCTURAL-ELEMENT ROW i cON51sroo*1nnc Nitc COMIOTS External Class MC I Torus Shell (General, Ring I Girder, at Supports and Penetrations), External Vent Pipe, 1 A B c A A B .C B c Bellows, Drywell (at Vent), Attach-ment.Welds, Torus Supports, Seismic
- Restraints Internal Vent Pi!!!
General and 2 A B c A A. . B.:.C B c Attachllllint Welds At Penetrations 3 A B c A A. B c B c (e.g ** Header) Vent Header General and 5 A B c Attachment Welds A A B c B c At Penetrations 6 A B c (e.g., Downcoaiers) i Downconiers General and 8 A B c A A B c 8 c Attacl'llent Welds Internal Su1!J!2rts 10 A B c A A B c B c Internal Structures Subraerged 11 A B c c c 0 E 0 E Non-Subnlerged I 12 N/A N/A N/A N/A N/A N/A N/A N/A N/A APPLY LEVEL C wHERE NRC HAS A OR B Vent tteader At Penetrations 6 c c c c (e.g., Downcciiaers) APPLY LEVEL D WHERE NRC HAS C Vent Header I At Penetrations 6 .D D J I I I
ADDITIONAL FATIGUE EVALUATION NORMALLY, EVALUATION OF SECONDARY AND FATIGUE STRESSES IN CLASS MC VESSELS IS NOT REQUIRED WHEN LEVEL C SERVICE LIMITS ARE PERMITTED. I CONTAINMENTS, SECONDARY AND FATIGUE STRESS EVALUATION WILL B~ REQUIRED FOR ALL CASES WHERE PREVIOUS NRC COMMENTS WOULD INDICATE A LEVEL A OR B ASSIGNMENT AND LEVEL C HAS BEEN USED, EXCEPT FOR POO( S\\.JELL LOADING. THIS ADDITIONAL REQUIREMENT WILL BE APPLIED TO: ROW. 3 6 8 COLUMNS 17, 20 4-6, 8, 10.. 12, 14 17, 20 ALSO, A NOTE TO THIS EFFECT WILL BE ADDED ON FIGURE NE-3221-1.
PR03ABLE LIMITING STRESS.LEVEL THE NEXT, AND LAST CHART INDICATES A PRESENT ESTIMATE AS TO WHICH OF THE VARIOUS LEVELS WILL.BE LIMITING FOR EACH STRUCTURAL ELEMENT. OF THE 13 LIMITING CONDITIONS IDENTIFIED, NINE APPLY LEVELS CONSISTENT WITH PREVIOUS NRC COMMENTS. THE REMAINING FOUR APPLY LIMITS WHICH MAY BE INCONSISTENT WITH PREVIOUS NRC COMMENTS~ ONE OF THESE POSSIBLE DEVIATIONS IS AT THE OOWNCOMER PENETRATION IN THE VENT HEADER WHEN SUBJECTED TO IBA+ SRV + OBE, WHERE* LEVEL C IS ?ER:~ITIED. THE REMAINING THREE POSSIBLE DEVIATIONS OCCUR AT THE POOL SWELL IMPINGEMENT REGION OF THE VENT HEADER, THE DOWNCOMERS AND THE rnTERNAL VENT, WHERE LEVEL D IS PERMITTED. AT THE PRESENT ONLY THE FIRST OF THESE IS FELT TO BE OF SIGNIFICANCE. THEREFOR~, THE PRESENT JUDGEMENT IS THAT ONLY TWO LIMITING REGIONS WILL HAVE LIMITS WHICH MAY DEVIATE FROM PREVIOUS NRC COMMENTS.
/ EVENT COMBINATIONS ~--** ***-- ~ T~ of Earthqu*ke COMllNATIOll lllJMBER . LOADS No.... 1 (0
- l *To*Ro)
Earthquake EQ SRV Dhcharge SRV LOCA Thenoal TA LOCA React Ions RA LOCA Quast-Static PA Pressure LOCA Pool Swel 1 PPS LOCA Condensat ton Pco Osei llat ion - LOCA Chugg Ing PCH STRUCTURAL-ELEMENT ROW Ext~na 1 C 1 ass MC Torus Sllell (General, R Ing Gtrder, at Supports and Penetrat tons), External Vent Pipe, l Bellows, Drywell (1t Vent), Attach-11et1t We 1 ds, Torus Supports, Seismic Restraints Internal Vent Pl!!* General and 2 Attac-nt Welds At Penetrations 3 (e.g., Header) Pool Swell 4 l1111ingeoient Region Vent Header General and 5 Attaci-nt Welds At Penetrat Ions 6 (e.g., Oowncoaiers) Pool Swell 7 lllP i nget1en t Reg I on Downc.-rs General and 8 Attaci-nt Welds Pool_ s.... 11 9 lllPingement Region lntern1l Suel!!!rts 10 lnternol Structures S.S-rqed 11 lloll*Sublllerged 12 I 5Rv I SRV I I EQ I 0
- s I
I 1 2 ! l x x x x x x x x A 8 c A B c A B c N/A N/A N/A A 8 c A B c N/A H/A H/A A 8 c N/A N/A H/A A B c A B c N/A N/A II/A o*--= Q COl1PONENT
- LOAOING~ - 5(RVIC( L[V£L AIMf.NIS PROBABLY LIMITING SBA! IBA I
I J ___ Dl!A __
- EQ SBA
!BA SBA;IBA1
- SBA,
!BA, DOA I
- . '
- I
- SRV, SRV, PS co,:
PS CO, CH EQ EQ SRV
- SRV EQ EQ CH I
0 s s I l 0 l 0 D. s 0 s s 0 s i I i l l 4 5 6 1 8 9 10 i 11 12 13 14 15
- 16. 17 181 19 20 21 I
I x I x I x x l I x I x x x x x x I I x x x x x x x x x x x x x x x x x x l x l x l I l x x x x x x l l x x l l x l l l x x x i x l l l x l x x l x x I I x l x x x x x x x x x x x I x x l l x x x x I I I l x x x x x x x x x x l A A a c a c A A 8 c 0 c 8 8 0 c 8 c A A 8 c 8 c A A 8 c 8 c B B © c 8 c A A 8 c B c A A 8 c B c c c c © c c N/A N/A N/A N/A I/A N/A N/A II/A N/A N/A N/A fl/A D D D @) D 0 A A 8 c B c A A 8 'f$J' 8 8 CV c B c D ~ D c c c D c D c c c c c c c 0 0 0 [iJ 0 N/A I/A N/A I/A* N/A H/A H/A N/A N/A N/A N/A II/A 0 0 D A A 8 c B c A A E c © c c c c c c 0 II/A N/A I/A N/A N/A N/A N/A N/A N/A N/A "'" N/A 0 D 0 cw 0 0 A A 8 c 8 c A A E-c B c 8 B (f) c B c A A c 0 c 0 c © 0 E 0 E E E E £ £ E I/A N/A N/A I/A N/A N/A NIA I/A N/A N/A © 0 E E E t U~V-l l\\TtO'-'S. R<Dtv'- II \\wo....:.OST fQ..D~t.4-cor-.>c..U-~
I CQMPOll£NT
- LOADINGS
- SERVICE L£Y[L ASSl.l!NM[NTS rvrNT cOll81NATlONS 15Rv I*
SRV SBA tBA SBA j IBA SBA I rBA! sBA, I tBA, .. PoseA1 cu.l*-P*s*J>~-* croQ. CH >--... -.. - *****-----~-+--E-~T---t--+-+-£-T~--t-1 1 _E-;~--t-sa_* v-+.;...si:_v-tl-~t-t.J~-* --.,1--~1-...:.CH--+' -~--+--~~ Type or Earthquake O i S 0 I S J 0 S
- O i S I 0 S
! 0 S 0 S CtlMB I NA T!Oll NUl48£R STRUCTURAL -ELEMENT External Class MC Torus Shell (General, Ring Girder. at Supports .nd* Penetrations), External Yetit Pipe, Bellows, Or.Y"e 11 (at Vent), Attach-eent Welds, Torus SuP!JOrts, Seismic Restraints lnterna 1 Vent Pipe General and Attaci-nt Welds At Penetrations (e.g., Header) Pool Swel 1 lliplngeoent Region General and Attachnlent Welds Pool S....11 llll)lng-nt Region Internal Supports z 4 A 4 8 A A 6 8 I 7 1 a 9 10 11 \\ 12 13114 15 16 I I I I I I : j I i 17 ( 18 19 20 l 21 x x x i x i i.. I -~.. ~ I x x x i x i * *
- I *** **
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- c I c i c l *-
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Distribution:
- NRC PDR
- Local PDR
~ket Files E. G. Case V. Stello J. Reece K. R. Goller T. J. Carter
- D. Eisenhut A. Schwencer D. Ziemann G. Lear R. Reid
- W. Butler D. Davis
- *L. Shao
- OELD
- OI&E (3)
- NRC Participants
- ACRS (16)
W. Paulson P. O'Connor D. Jaffe R. Snaider T. Wambach C. Trammell M. Fletcher P. Riehm L. Kintner
- G. Lainas
- I. Sihweil
- J. Knight
- R. Tedesco
- R. Stuart J. Siegel R. Bevan S. Nowicki D. Verrelli G. Vissing
- with enclosure}}