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'_'i *1D - loading pits to ascertain if the commitments stated in the PSAR M _- 2323-55-18, Rev. 2 were %.-
.k. and Gibbs & Hill (G&H) specificationThe inspector reviewed Grown & Roots (BE .
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" -* being implemented.
'[ construction procedure 35-1195-CCP-38 " Stainless Steel Liner *
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Erections," and B&R QA procedures _CP-0CP-2.ll., " Inspection of '
s Stainless Steel Pool Liner Systems," and CP-0CI-2.ll-1, " Weld w
Inspection and Fit-Up of Stainless Steel Ciners," to ascertain Addi tional
- 4 g-if the above stated requirements had been implemented. ;
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QA and work procedures in the areas of weld expenda [
surveillance were reviewed to assess control of these activities.
d ified.
_flo items of noncompliance or deviations were i ent
- b. Observation of Work Activities ,s
( 1)
Steel LinD I4" The welding of fillet joints for the attachment of leak chase -
channels and of tacks for the attachment of backing bars for the butt weld seams for stainless steel liners was inspected. [
Weld procedures and welders were found qualified in accordance The with the requirements of the ASME B&PV Code,Section IX. ;.
welding was performed in accordance with _WPk con?n and R9n71 Work and and placed as specified by B&R drawing QB-10553. i-inspection activities were performed as prescribed by the ,
procedures discussed in the previous section. ja b
flo items of noncompliance or deviations were identified. L p
Reactor Coolant System Component Supports ;
(2) L, A limited inspection of the Vertical Columns - C1 as shown r and described on Westinghouse drawings 1457F29 and 1457F27 The inspector i was perfortred in the site storage yard. E reviewed the PSAR and Westinghouse specification G-952628, Rev.1. " Fabrication Requirements For the Reactor Coolant System Component Supports," and determined the vertical column fabrication requirements were ASME B&PV Code,The Section III, Div.1, ilF,1974 edition as a minimum.
inspector was unable to find any documentation in the preliminary data package and certificates of conforman accordance with ASitE III, flF and that volumetric inspection ,.
of the full penetration welds had beenTheperformed licenseeasis prescribed obtaining by ASf E III, t!F, paragraph flF-5212.the cocplete data packa items were fabricated and inspected as prescribed.
This item is considered unresolved.
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I i The floors below grade house the safety injection pumps, RHR pumps and l ;
i coolers, Containment spray pumps and coolers, and the auxiliary I
feedwater pumps. Floors above grade house the eaergency diesel
' generators, electrical switchgear, motor control centers, and CROM
! j i control s. Equipment locations are shown on Figures 1.2-1 j through 1.2-11.
3.8.4.1.2 Auxiliary Building l ;
i j i j t The Auxiliary Building is a multistory, reinforced concrete structure
' with one story below grade and four stories above grade. Floor
' systems, columns, and walls are of reinforced concrete and function to support vertical and horizontal loads in the same manner as those of the Safegua'rds Building. As with the Safeguards Building, space is
[; jl ll . provided,to avoid the contact of structures, and systems are designed l I ! .
to accommodate the differential movements of adjacent buildings. The i
Auxiliary Building houses the Control Room, battery room, compressors, f l l
' veittilating equipment, waste treatment equipment, and other fluid f auxiliary systems. Equipment locations are shown on Figures L.2-1 !
i i through 1.2 11. l
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3.8.4.1.3 Fuel Building j
The Fuel Building is a reinforced concrete structure whose principal
! function is to house the new fuel storage area and the two spent fuel i
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storage pools.
l Both new and spent fuel bundles are stored in stainless steel racks l
which are located in the spent fuel pools which are filled with borated P water. The Span.Lfuel pooly have thick concrete floors and walls and f '
are lined with stainless steel plates for leaktightness.
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SPElfr FURL POOL coQLit!Q_8tfD_CLEh5LT_MIi1E!1_EZEAX_11 EAT PAP AMNPE After 1989 Full Spent Fuel Not Accumulating in Pools ,
Af ter 1986 Refueling Core Unloading Eggl_!!gz_1 Eggl_!!g2_2 2d_fgre in One Pggi J-7/3. Core in One E901 Egol No. 1 ggol No s_2 130 323 0 533* 560 Humber of fuel assemblies 514 stored e 21.7 54.4 0 3.0 58.5 Decay heat produced 26.8 (10 * ' btu /hr) 0 2 1 0 2 0 2 1 0 2 1 2 1 0 2 1 0 1 Number of cooling loops 137 169 - 117 129 - 135 164 -
120 135 - - -
- 105 -
Maximum SFP temperature (F)
- - 6. 8 - - 0.8
- - - - 75.0 - - 0.5
- Temperature rise time (hr) - - 4.8 -
NOTFS:
- 1. Storage capacity of each pool is 560 fuel assemblies.
~'
- 2. D e decay heat produced includes +10 percent uncertainty margin.
- 3. Number of fuel assemblies added to the pools by ye7r is f rom Table 9.1-4.
- 4. Spent fuel pool water volume is 350,000 gal per pool.
- 5. Spent fuel activity level (exclusive of Tritium) is $ 5x10-* Ci/cm3 all other fuel assemblies in
- Assumes that 19 fuel assemblies are stored in 1987 refueling; SFP 81 are from prior to 1987 refuelings.
Assuming both SFP cooling loops are inoperable, the temperature rise time is the time forthe SFP operation.
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,s z, yg FRIDAY MORNING, SEPTEMBER 14,1984 'E E.
01984 FORT WORTH STAR l e, um .'19A 4
Comanche Pea. .k .in.. ..... -TELEGRAMspe :
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used wrong form for y.eart
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h By BR CE MiLLAR sue.Te6. gree wruer . w :t '! ,TItll'er Brandt 'dec!!ned to state BI!Ile Ga 'di, a tidrd. year law ptu-'
who was responsible. But on Thurs- dent representing plant opponenta. U '; -
Quality control inspectors at Co. : day he blamed quality control in- She was referring to the discovery . ;l
'manche Peak nuclear power plant spectors for "a lack of attention to af ter the California plant had been l '*i frilswed the wrong procedure dur. ' detail as to bow.these inspections licensed .that the blue J. C
.Ingatleastfouryearsofinspections :were documented.".'Brandt , was been Areversed.
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ci a storage container designed to ' reassigned in March to his current . "niat's ridicul " replied Dave' '
- h!!d uranium fuel, a plant official tion working. full time prepar Chapman, chief of Texas Ut111(iesi '
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testified nursday. -
- c testimony.for. licensing board quality assurance <;uality:co -
- C. Thomas Brandt,a former high. hearings. ,< . .,. ,, program. .'
l ranking Texas Utilities Co. quality Representatives for plant oppo- ~Chapmais said he was concerned i assurance manager, acknowledged nentscontended that the disclosure I E
that the inspectors used the wrong had potentially far reaching conse. about the breach in procedure'but' '
inspection form while checking quences clouding plant owners' he said subsequentvacuum I andi weldingina keysafetyarea.Hecon. chancesof obtaininga federaloper welds ter tests had confirmed that -theb were safe.
I- #
ceded that the mistake was a viola. ating license. I* s '
tion of a plant procedure but insist. Anthony Roisman, lawyer for the ,'The problem is ed it posed no safety hazards. Dallas. based Citizens Association s "afetysignificance,,that ,
- there is Duringexhaustivequestioningby for Sound Energy,said it was likely There is no reason to believe that I g the U.S. Atomic Safety and Licens. that the inspectors violated the that type of proble ing Board. Brandt said that, begin. r/me procedure while examining parts of the plant.,m existsin other
ning in 1977, inspectors used a less. welding of identical liner plates dstailed iorm while inspecting usedinthespentfuelsand refueling boxes ofinspection documents that Brandt appeared Thursday with j j-welding on the stainless steel liner canals for both Unit I and Unit II. he said would confirm that the bulk '-
plates for the reactor Unit II refuel. "It is potentially as significant as of theinspections were carried out.
ing cavity. ne form omits details any problem found at any other Butsomeof thosedocumentsraised i about the manuf acturer,the welder plant." Roisman said. He is execu. questions among board members. . .
and the weld procedure. tive director of the Washington, Board members questioned the au-However, plant officialscan docu. D.C based Trial Lawyers for Public thenticity of the inspectors
- signa-mtnt that all welds were eithertest. Justice. tures. Some dates and signatures ed independently or that inspec. Rotsman said the lack of inspec. appeared to have beeen written st ,
ti:ns were performed, Brandt ' tlondocumentsinhibitedfederalin. different times,they said. ;
testified. ; spectors from investigating allega- The licensing board is holding' Led by board Chairman Peter tions from plant employees. One hearingsonallegationsthatthereis Bloch, the three member panel NuclearRegulatoryCommissionin a pervasive climate of harassment questioned Brandt extensively dur. spector had ')een told by two work. and intimidation of quality control ing two days of testimony. The ers that there was a trend ofimprop- inspectors at the plant. Hearing are board asked Brandt for proof that er welds on thelinerplates.Without scheduled to continue through Fri-the lnspection was ever conducted, inspectiondata,thereporteouldnot day at the Hyatt Regency Hotel and why plant officials failed to ful- checked, he said. They resume Tuesday at the Rama-ly investigate when the quality con- "It's like Diablo Canyon when da inn Central where they(are trol problem was reported. . they inverted the blueprints,".said scheduled through Sept.2L ,
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3 Malt.* NORTH FULt.S MAtl.* SIX Ft.ACS MALL. ARLINGTON .
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[*. j'Y. NUCLEAR REGULATORY COMMisslON e
lh' S WA SHING T ON, D. C. 20555 5.,%,1' l i '/ [b
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29%5 MEMORANDUM FOR: D. B. Vassallo, Assistant Director for Light Water Reactors Division of Project Management, NRR FROM: G. W. Reinmuth, Assistant birector, Division of Reactor Construction Inspection. IE
SUBJECT:
CLASSIFICATION OF SPENT FUEL POOL LINER PLATES (AITS F12193H1) (AITS F30382H1)
In the enclosed correspondence we are informing all regional offices that fuel poc1 liner plate) are not required to be designed and erected to seismic categ.ory I requirem?nts. _
. If you will concur in this correspondence we believe the transfer of
- 1ead responsibility serial number: IE:RCI:78-04 dated July 17, 1978 and the followup correspondence may be considered closed out.
Please call if you wish to discuss this .scbject further. ,,
<R v -
J .. t .
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),$E . ; ta .v.k -
G. W. Reinmuth ~
Assistant Director Division of Reactor Construction Inspection Office of Inspection and Enforcement l
Enclosure:
Memo, GWReinmutb..to RTCarlson, dated FEB 6 1979 l
cc: J. G. Davis. IE l 3 ', .
l H. D. Thornburg, IE '
N. C. Mosel.ey, IE ,)'Dr e-'Cil o B. H. Grier, RI
_S/
7 Fed M .w9 (f
.J. P. O' Rei11y , RII - p ;q J. !:'
W.G. C. Keppler, Seidle, RIV RII}/
$ /?
R. H. Engelken, RV ,
-CONTACT: W. Laudan, IE '
49-27551
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- pn eyg#*g UNITE 3 STATES
! c NUCLEAR REGULATORY COMMISSION E WASHipeGTOes. D. C. 20G65
' *s.,*****} July 8, 1981 .
Regulatory Guides 1.10, 1.15, 1.18,1.19,1.55, and 1.103 REGULATORYGUIDEDISTRIBJITIONLIST(DIVISION 1)
SUBJECT:
WITHDRAWAL OF SIX DIVISION 1 REGULATORY GUIDES The following regulatory guides were issued as indicated to provide guiduce to licensees and applicants for implementing portions of the Commission's regulations with regard to materials, construction, and testing of concrete containments and other safety-related concrete structures:
1.10 " Mechanical (Cadweld) Splices in Reinforcing Bars of Category 1 Concrete Structures," Revision 1. January 1973, 1.15 " Testing of Reinforcing Bars for Category I Concrete Structures "
Revision 1. December 1972, 1.18 " Structural Acceptance Test for Concrete Primary Reactor Containments,"
Revision 1. December 1972, 1.19 " Nondestructive Examination of Primary Containment Liner Welds,"
Revision 1. August 1972 (Safety Guide 19),
1.55 " Concrete Placement in Category I Structures," June 1973, and 1.103 " Post-tensioned Prestressing Systems for Concrete Reactor Vessels and Containments," Revision 1, October 1976.
The regulatory positions of these guides are now considered to be covered by one or more of the following national standards:
f
-- ACI 359 (ASME Section III, Division 2), " Code for Concrete Reactor Vessels and Containments," endorsed by Regulatory Guide 1.136,
" Materials, Construction, and Testing of Concrete Containments (Articles CC-1000. -2000, and -4000 through -6000 of the Code for Concrete Reactor Vessels and Containments)."
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-- ACI 349, " Code Requirenents for Nuclear Safety-Related Concrete Structures " endorsed by Regulatory Guide 1.142, " Safety-Related -
Concrete Structures for Nuclear Power Plants (Other than Reactor Vessels and Containments)."
l
-- ANSI N45.2.5, " Supplementary Quality Assurance Requirements fo Installation, Inspection, and Testing of Structural Concrete, Structural Steel, Soils, and Foundations During the Construction Phase of Nuclear Power Plants," endorsed by Regulatory Guide 1.94,
" Quality Assurance Requirements for Installation, Inspection, and Testing of Structural Concrete and Structural Steel During the Construction Phase of Nuclear Power Plants."
Therefore, Regulatory Guides 1.10,1.15,1.18,1.19,1.55, and 1.103.are being withdrawn. Withdrawal of these auides is in no way intended to alter any prior or existing licensing consnitments based on their use. ,
Regulatory guides may be withdrawn when they are superseded by the Commission's regulations, when equivalent recommendations have been incorporated in applicable approved codes and standards, or when changes -
j in methods and techniques or in the need for specific guidance have made them obsolete.
f I ,
Robert B. Minogue, Director Office of Nuclear Regulatory Research i
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.. NUCLEAR REGULATORY COMMisslON f...
WASHING TON. D. C. 20555
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. '.~ # H.B. G 1379 MEMORANDUM FOR: R. T. Carlson, Chief, Reactor Construction & Engineering Support Branch, RI FROM: ' . G. W. Reinmuth, Assistant Director, Division of Reactor-Construction Inspection, IE
SUBJECT:
CLASSIFICATION OF SPENT FUEL POOL LIHER PLATES (AITS F12193H1) (AITS F30382H1)
We have been orally informed by the Division of Project Management, NRR that fuel pool liners are not requimd to be designed and erected to -
Seismic Category I requirements. The basis for this position is that .
the primary function of the pool liner is to provide a leak tight' barrier
- and a surface suitable for decontamination, rather than to serve as a critical safety structure. Furthemore the probability of large leaks occurring and being undetected over a period of time such that a potential hazard might be incurred is acceptably low. ,,
We wish to emphasize however, that this decision does not effe'ct'the classification of the fuel pool storage s,tructure, storage racks, supports -
and piping, all of which are required to be., designed and erected to Seismic Category I. requirements.
l l . If you have further questions on this subject please contact W. Laudan (27551) sh.d.33 G. W. Reinmuth Assistant Director Division of Reactor -
Construction Inspection Office of Inspection and Enforcement CONTACT: N. Laudan, IE I !'
49-27551
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HEH,0RANDUM FOR: R. T. Carlson. Chief, Reactor Construction & Engineering Support Branch, RI -
FROM: G. W. Reinmuth. Assistant Director, Division of Reactor Construction Inspeetion, IE -
SUBJECT:
ClJ.551FICATION OF SPENT FUEL P001. LIHER PLATES (AIT5 F12193H1) (AITS F30382H1) '
We have been orally igformed by the Division .of Project Management, NRR that] fuel pool liners; are not requi 4d to be designed and erected to I ismic Category I requirements. The basis for this position is that the primary function of the pool liner is to provide a leak ti@t' barrier
. and a surface suitable for decontamination, rather than to serve as a
- critical safety structure. Furthermore the probability of large leaks occurring and being undetected over a period of time such that a potential hazard might be incurred is acceptably lowi_ ~
We'wish to emphasize however, that this decision does not.effe'et'the classificati.on of the fuel pool storage s.tructure, sto ege racks, supports '
and piping,'all of which are req.uired to be., designed and erected to Seismic Category I requirements.. ,
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. If you have further questions on this subject please conta'ct W. Laudan -
(27551) .
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G. W. Reinmuth
. Assistant Director Division of Reactor Construction Inspection
, Office of Inspection and Enforcement
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*** . DEC 211984 MEMORANDUM FOR: Olan Parr, Chief , J .
Auxiliary Systems Branch Division of Systems Integration , FROM: George Lear, Chief g Structural and Geotechnical Engineering Branch bd Division of Engineering
SUBJECT:
PREPARATION OF A STATEMENT ON THE NRC STAFF'S POSITION ON THE SPENT FUEL POOL LINER FOR COMANCHE PEAK NPP We reply to the request for identification of the structural engineering acceptance criteria on the design of spent fuel liners, based on V. Noonan memorandum, dated December 7, 1984, and discussions between S. Burwell and . J. Holonick with F. Rinaldi of my staff. We understand this information will be used by ycur staff in the preparation of the staff position on spent fuel pool liners for Comanche Peak NPP. The fuel pool is considered a Category I structure. However, the fuel pool liner is not designed as a load supporting member, including the seismic loads resulting from SSE. Although the liner has load carrying capability, no credit for this load carrying capacity is considered in the design of the spent fuel pool. The structural engineering staff requires that the structure providing structural support to the liner system be a Category I structure, and that a leak chase system be provided. These requirements' i are intended to assure that the liner will function to provide a leak tight barrier, a surface suitable for decontamination, and a leak detection system, as required by your staff. , The Division of Reactor Construction Inspection IE, informed all regional offices in early 1979 on the above classification of spent fuel pool liner plates. We are enclosing copies of two IE memos on the subject. If you-have additional questions, contact Frank Rinaldi of my staff.
- _f YJY George Lear, Chief Structural and Geotechnical Engineering Branch Division of Engineering l
l
Enclosure:
As stated cc: See next page. t . .
. ~%. F0lA-85-59 l
. _ _ - - - - - ____ - _ . _ - - _ - , __ h Y _
s.. . I Parr cc: T. Novak ' - V. Noonan J. Knight ~ T. Sullivan
, J. Youngblood S. Burwell G. Ankrum '
l',' Shao - J. Holonick G. Lear P. Kuo F. Rinaldi e 89* i I e l I . I i l i _
~~~
DEC 211984 MEMORANDUM FOR: Olan Parr, Chief Auxiliary Systems Branch Division of Systems Integration
~
FROM: George Lea'r, Chief Structural and Geotechnical Engineering Branch Division of Engineering ,
SUBJECT:
PREPARATION OF A STATEMENT ON THE NRC STAFF'S POSITION ON
.THE SPENT FUEL POOL LINER FOR COMANCHE PEAK NPP We reply to the request for identification of the structural engineering acceptance criteria on the design of spent fuel liners, based on V. Noonan memorandum, dated December 7, 1984, and, discussions between S. Burwell and J. Holonick with F. Rinaldi of my staff. We understand this information will be used by your staff in the preparation of the staff position on spent fuel pool liners for Comanche Peak NPP.,
The fuel pool is considered a Category I structure. However, the fuel pool - liner is not designed as a load supporting member, including the seismic loads resulting from SSE. Although the liner has load carrying capability, no credit for this load carrying capacity is considered in the design of the spent fuel pool. The structural engineering staff requires that the structure providing structural support to the liner system be a Category I structure, and that a leak chase system be provided. These requirements are intended to assure that the liner will function to provide a leak tight barrier, a surface suitable for decontamination, and a leak detection system, as required by your staff. The Division of Reactor Construction Inspection, IE, informed aii regional offices in early 1979 on the above classification of spent fuel pool'11ner plates. We are enclosing copies of two IE memos on the subject. If you
.:l have additional questions, contact Frank Rinaldi of my staff.
George Lear,- Chief Structural and Geotechnical Engineering Branch Division of Engineering
Enclosure:
As stated 1 cc: See next page. l
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