FVY-87-109, Forwards Info on Regional Insp Re Mark I Containment Mods (USI A-7) Conducted on 871005-09
| ML20236S707 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee  |
| Issue date: | 11/23/1987 |
| From: | Capstick R VERMONT YANKEE NUCLEAR POWER CORP. |
| To: | Varela A NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| REF-GTECI-A-07, REF-GTECI-CO, TASK-A-07, TASK-A-7, TASK-OR FVY-87-109, NUDOCS 8711300047 | |
| Download: ML20236S707 (97) | |
Text
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u LVERMONT YANKEE NUCLEAR ' POWER , CORPORATION 1 j
j RD 5, Box 169. Ferry Road, Brattleboro, VT 05301 FVY 87-109
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ENGINEERING OFFICE {
' # 1671 WORCESTER ROAD a
November 23, 1987 FR AMINGHAM, MASSACHUSETTS 01701
- TELEPHONE 617-8?2 8100 United States Nuclear Regulatory Commission
' Document Control Desk Washington, DC 20555 Attention: USNRC - Region I Division of Reactor Safety Mr. A. A. Varela 631 Park Avenue King of Prussia, PA 19406
References:
(a) License No. DPR-28 (Docket No. 50-271)
(b) Letter, USNRC to VYNPC, NVY 87-130, dated August 19,'1987 (c) Letter, USNRC to VYNPC, NVY 87-157, dated September 30, 1987
Subject:
Regional Inspection Related to Mark 1 Containment Modifications, (USI A-7) Conducted October 5-9,.1987
Dear Sir:
Pursuant to your recent request, enclosed please find one copy of the i information presented on October 5, 1987 pertaining to the subject i inspection. Should you have any questions, or require additional information concerning this matter, please contact this office.
Very truly yours, VERMONT YANKEE NUCLEAR POWER CORPORATION d'
R. W. C pstick Licensing Engineer RWC/25.272 Enclosure kf
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8711300047 371123 PDR G
ADOCK 05000271 PDR
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MARK I CONTAINMENT PROGRAM FOR VERMONT YAhTEE 9
, e NRC AUDIT WEEK OF OCTOBER 5 s -
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I ORGANIZATION CHART (Present Day) i l
S. R. MILLER PROJECT MANAGER j 1
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ADMIN. ASSISTANT ADMIN. ASSISTANT SECRETARY tm
(_) J. K. THAYER PROJECT ENGINEER PROJECT ENGINEER ENGINEERING LICENSING SCIENCES ENGINEERING MANAGER ENGINEER l
l R. P. OLIVER I&C LEAD ELECTRICAL SYSTEMS LEAD ECHANICAL LEAD INGINEER LEAD ENGINEER ENGINEER ENGINEER
________________ ________________ ____________ ____________ l ENGINEERS ENGINEERS ENGINEERS ENGINEERS I RESPONSIBLE FOR I STRUCTURAL /
MECHANICAL ENGINEERING 1
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PLANT HISTORY
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o Vermont Yankee Nuclear Power Station is a 514 megawatt boiling water reactor supplied by General Electric o License to start'constructi6n: November 1968 o License to operate: November 1972 o Architect / Engineer: Ebasco Services, New York .
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- o. Responsibility for Mark I Containment
- Des'ign of primary containment:
General Electric Company
- Construction of primary containment:
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Chicago Bridge and Iron
- Design of torus attached piping:
Ebasco
- Design and construction of torus attached piping supports:
ITT Grinnell 5830R/18.101
O CHRONOLOGY OF MARK I PROGRAM FOR VERMONT YANKEE c . .. ..
1975 o General Electric (GE) identifies additional DBA loads for Mark I containments.
- 1. Air clearing
- 2. Dynamic effects of steam condensation i
o GE completes generic analysis and reports results to NRC and Mark I utilities.
Conclusions O 1. Containment function is maintained
- 2. Specific containment components need plant-unique evaluation o Sixteen Mark I utilities formed an owner's group to pool resources to develop a systematic approach to the Mark I evaluation.
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- o. Two-phase approach established to re' solve containment:. integrity questions.
4 1 ~. : Short-Term Program'(STP) -- --
4 Plant-unique ~ evaluations Established.a safety factor of.2.0 for containm'ent functional integrity
- 2. Long-Term Program Restore original design safety margins
, To Vermont Yankee Resolution (STP)
- Column reinforcement and tiedown, EDCR 76-1 Torus /drywell pumpback system, PDCR 76-9 These modifications satisfied STP requirements l0: 5875R/26.109
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O 1976 -
Establishment.of long-term program Ensure that the containment structure has the original licensed ' design safety margins.
1977-1981 o GE - owner's group developed new load definitions through:
Full scale testing at FSTF (C0 Load)
In plant SRV testing at Monticello NPS 1/4 scale plant-unique testing 9 -
Analytically developed load definitions o Code acceptance criteria document established.
o GE issues Load Definition Report (LDR)
L o NRC issues NUREG-0661 which endorses LDR as governing load definition document.
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s 1980' VERMONT YANKEE REFUELING OUTAGE A_)
l o Major Modifications Installed, EDCR 80-11 Saddles Tee Quenchers and. Supports Downcomer Ties RHR Return Elbows SRVDL 10-Inch Vacuum Breakers Minor Internal Modifications Vent. Header Deflectors 1983 REFUELING OUTAGE o Completed Modifications
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.Catua1k Additional 10-Inch SRV Vacuum Breakers Upgraded Temperature Monitoring System Attached Piping Support Modifications o Submitted Plant-Unique Analysis Report to NRC 1984 o NRC completes post-implementation audit review of Vermont Yankee PUAR and concludes that modifications have restored the original design safety margin.
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SUMMARY
TO YANKEE RESPONSE TO MARK I CONTAINMENT PROGRAM-l l
g o Short-TermLProgram-i :f I
Criteria ------- -------- > - NUREG- 0 4 0 8 Resolution'--------------------> EDCR'VY'76-liand PDCR 76-9 sNRC Acceptance ----------------> Docket No. 50-271, dated January 13, 1981.
- o. Long-Term Program Criteria ----------------------> GE NED0-21888 NUREG-0661 Resolution --------------------> EDCR 79-9
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EDCR 79-57 EDCR 80-11
. EDCR 80 c EDCR 82-24
.EDCR'82-35 EDCR 82-37
'EDCR 83-23 NRC Acceptance ----------------> Docket No. 50-271, dated July 2, 1984
< Two' reports - one titled " Plant-Unique Analysis Report of the Torus Suppression Chamber"-(Technical Report TR-5319-1, L' '
- Revision 2) and the other " Plant. Unique Analysis Report of the Torus Attached Piping" (Technical Report TR-5319-2) - detail the Mark I Containment Program for Vermont Yankee Nuclear Power
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MARK I PROGRAM c'~'s RESPONSIBILITIES
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GENERAL ELECTRIC COMPANY
- 1. Mark I Program Manager j
- 2. Develop new hydrodynamic load definitions (LDR/PULD) 3.- Generic Licensing NUTECH l
Mark I program monitor for load development work under i contract to Mark I owner's group.
TELEDYNE ENGINEERING SERVICES
- 1. Utilized load definition documents and plant-unique
(]) test data to analyze torus internal &nd external structures. ]
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- 2. Designed modifications. ;
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YNSD ENGINEERING
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- 1. Coordinate consultant activities.
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- 2. Member of Mark I Owner's Group.
- 3. Preparation of detailed design change packages (EDCRs) for all modifications related to Mark I Program.
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- 4. Provided on-site engineering support during l
/T modification work. I U
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N- MARK'I'LSTRUCTURAL ANALYSIS
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Analysis Calculations YAEC CYGNA' Modification EDCRs Analyze, Design Drawings- o Design Information Design / Modify SRV Line Supports .o. QA. Requirements Large' Bore Piping' Analysis' o Safety. Evaluations TAP Supports
- { Calculations / Support Loads o Installation Specs I
Review and Approval I
Lof Vendor Documents On-Site QA/QC Plant-. *---!
Specific Licensing U
i CB&I AND MERCURY COMPANY f Installation Procedures Welding i NDE 1
Installation Drawings l QC i
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. CRITERIA-4 NUREGiO661 Sec. 3.10'-
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i YNSD' TELEDYNE 1
EDCR 82-37 . - - - - - - - Hydrodynamic Loads on Instruments
.and Supports ,
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HISTORY OF THE MARK I CONTAINMENT PROGRAM AT VERMONT YANKEE Background Information To understand the need for re-evaluating the Mark I containments, it is essential to review the developm'nt e history for establishing the original design technical bases.
Testing was initially performed on a pressure suppression concept for the Humboldt Bay power plant. Additional tests were also performed for the Bodega Bay power plant concept. The purpose of these initial tests was to demonstrate the viability of the pressure suppression concept for containment design, and the tests were instrumented to obtain quantitative information for establishing design pressures. The tests were designed to simulate the Loss-of-Coolant Accident (LOCA) with various equivalent pipe breaks up to
'approximately twice the cross-section area for a Design Basis Accident (DBA).
The Mark I containment design, which is discussed in various plant Safety Analysis Reports (SAR), is based on the experimental technology obtained from O these tests.-
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General Electric tested the Mark III containment concept in its Pressure Suppression Test Facility (PSTF). These tests were initiated for the Mark III concept because of the geometrical configuration difference over the previous containment concepts principally in the utilization of horizontal vents.
(Steam had been ejected vertically downward; whereas, the Mark'III design l ejects steam horizontally.) More sophisticated instrumentation became l available for the Mark III tests as well as elaborate computerized methods for l
data reduction techniques. It was from the PSTF testing that the short-term dynamic effects of drywell air being forced into the pool in the initial stage of the LOCA event were first identified.
Also, recent experience at operating plants shows the dynamic effects of l Safety / Relief (S/R) valve discharge to the suppression pools were
! substantial. Although the S/R valve discharge and LOCA events are not i directly related, both events are characterized by an initial short-period p injection of air into the suppression pool.
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! During the early period *of a postulated LOCA in a pressure suppression containment, there is an initial short duration dynamic loading when the drywell air (noncondensibles) is compressed and ejected into the suppression pool water. .This air injection results in a pool swell of short duration in which a slug of water rises and impacts the underside of the Vent Header Piping System and other structurai components within the suppression chamber of the Mark I containment.
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I In addition to the PSTF test data, other LOCA-related dynamic information was obtained from tests performed by a foreign company. During the later stages of a postulated LOCA event, steam flow ejected from the downcomer into the suppression pool diminishes. At low steam flow rates, steam bubbles tend to alternatively form and collapse at the bottom of the downcomer opening immersed in the suppression' pool. The collapse of the bubble causes the water to slap the side of downcomer inducing a lateral impulse'to the tip of the downcomer. These impulses are random in magnitude'and direction, and terminate as flow continues to diminish. These impulses are referred to as lateral loads in the remainder of the report. Since the lateral loads occur at the later stages of a postulated LOCA event, whereas, the drywell air discharge into the suppression pool occurs during initial LOCA stages, the loads do not occur concurrently. Also, the characterizations of the loads are quite different. The drywell air discharge is characterized by a single impulsive event, while the lateral loads are characterized by approximate 250-cycle loading random magnitudes and directions.
Using information extrapolated from the PSTF tests and.available representative data from foreign test programs, General Electric began an evaluation of the potential impact on a typical Mark I containment (called
" Reference Mark I Containment"). In performing the above analysis, subjective judgment was used for selecting the loads and structural components which were considered most significant for evaluating containment function during a LOCA I event. The emphasis of the above effort was to provide an expeditious evaluation of containment capability to meet its functional requirements during a LOCA event. The purpose of this study was to assure that the health and safety of the public is maintained while a more in-depth analysis was p
J performed during continued plant operation.
5830R/18.101
I The results of_this study reported to the NRC in an oral presentation'on 1
/~N April 10, 1975, did conclude the containment function would be maintained l N-]' using realistic assumptions relative to pool swell effects and lateral j downcomer effects. In addition, specific containment components were f identified for more detailed evaluation.
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J In the interim, all the utilities with auclear plants incorporating Mark I containments met with General Electric in San Jose on April 23-24, 1975, to discuss the work for the referenced Mark I plant. (Each utility had received NRC letters, dated approximately April 17, 1975, requesting additional .
information on containment capability relative to LOCA-related suppression phenomena.)
l As a consequence of the April meeting, the utilities decided to form an owners' group which would enable them to pool their talents, ideas, and experience to develop a strong, technically sound, and systematic approach to the Mark I evaluation. The purpose of this ad hoc organization is to be responsive to the NRC in the shortest time possible recognizing that much of the evaluation would be similar for all the plants.
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s By letters submitted to the NRC during the week of May. 5,1975, a two-phase
_ approach for the re-evaluation of Mark I containments was committed.
The two phases are called, " Mark I Short-Term Program" (STP) and " Mark I
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l Long-Term Program" (LTP) scheduled for completion in September 1975 and at the end of 1976, respectively.
The Mark I Short-Term Program's purpose is to provide an in-depth evaluation
'of structural response under the probable loads induced by a postulated DBA to i confirm the earlier judgement made for the reference. Mark I plant that all Mark I containments are capable of withstanding the most probable LOCA-induced loads considering the latest pool dynamic load information and still remain functional even though some of these-loads were not explicitly included in the original design basis. Thus, a more extensive in-depth analysis can be performed during continued plant operation without risk to the health and r"' safety of the public.
5830R/18.101
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The Mark I Long-Term Program _ includes the development of design basis loads as 7
x a consequence of the latest pool dynamic information and to assess whether the j
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'~)_ Mark I containments are capable of sustaining these loads within specific j structural criteria. Also, S/R loads will be addressed in the long-range program.
One of the.LOCA-related hydrodynamic loads induced by a postulated design !
basis accident is torus uplift,. This load is a result of the air compression in the upper half of the torus due to the pool swell, a phenomenon associated with downcomer clearing and air bubble formation.
Results obtained during the STP indicated that Vermont Yankee's torus had.an excessive uplift problem. This information was verbally communicated to NRC, and Vermont Yankee Nuclear Power Station was voluntarily shut down to ensure that the health and safety of the public was not endangered.
. The subsequent presentation to NRC in Bethesda for resuming operation of Vermont Yankee included a structural modification commitment. This
'T modification prevents torus uplift during a DBA by anchoring the torus support (J columns to the concrete mat.
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Criteria ~(NUREG-0408).
i Until. implementation.of the,long-term program, the-. licensee must. provide'- ]
a margin'of' safety..of'at lealit.twol(2.0)'in the containment design to ll i.m. . . ' assure containment function in the' event of..a design basis L
Loss-of1C oolant!L Accident (LOCA). The licensee must also be able to' .,
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L maint'ain'1.7. psi A.between th'e torus.and drywell'. . .
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Resolution' .;
'EDCR 76 Torus column reinforcement and~tiedown. _
'PDCR 76-9: -Torus /Drywell Pumpback' System..
NRCAcceptance'-(DocketNo.50-271',cdatedJanuary'13,1981)l V .. . .,
[ NRC determined Vermont Yankee's response to the STP provided a margin of' ;q h J e, . safety of at'least two (2.0) and provided an adequate basis for' continued.
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plant operation until the' completion of the long-term program. .
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o Long-Term Program Criteria (NUREG-0661) 4 (p.e neo p - u age) f After modifications made in the LTP, the licensee must ensure the containment structure has th'e original licensed design safety margins.
Resolution -
Many engineering design changes were impicmented for the resolution of the LTP. The following is a list of each EDCR together with a brief description.
EDCR 77-22 (Torus Support Modification) ;
Gussets were to be welded between the torus and columns, plus rerouting three NNS lines to allow for gusset installation. During the welding of the gusset pads to the torus shell, cracking of the shell occurred and was noted, and the EDCR was cancelled.
EDCR 79-57 (Wide-Range Torus Water Level and Containment Pressure)
Instrumentaticin was added to monitor wide-range torus water and containment pressure.
EDCR 78-02 (SRV Tee Quenchers) .
The SRV ram heads were to be replaced with tee quenchers. EDCR was never issued. Modification became part of EDCR 80-11.
l EDCR 78-17 (Torus Repair) i
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Repaired crack damage to torus which occurred during EDCR 77-22. i I
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EDCR 79-1 (Torus Support Modification) l
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Resume work intended in EDCR 77-22. More problems with welding, EDCR was cancelled.
1 EDCR 79-6-(Vent Header Impa'c't Device and'Downcomer Tie Straps)
EDCR was never issued for construction. Modification became part of EDCR 80-11.
EDCR 79-9 (Torus Monorail Installation)
Installation of' monorail inside torus to assist in the completion of the long-term program.
1 EDCR 79-10 (Torus Ring Girder Drain Enlargement)
EDCR was never issued for construction; became part of EDCR 80-11.
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EDCR 79-11 (RER Elbow Addition)
EDCR was never issued for construction; became part of EDCR 80-11.
EDOR 80-11 (Torus Modifications - 1980)
EDCR added torus saddles, replaced ramsheads with tee quenchers, added vent header deflectors and supports, added downcomer ties, rerouted RER return line in torus, replaced two-inch SRVDL with ten-inch vacuum ,
breakersr. replaced existing wetwell/drywell vacuum breakers, reinforcement of four-inch spray header support, and modifications to j
! submerged piping.
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EDCR.a'dded a' Containment Inerting' System to, among.other things, maintain. ){
.drywell. pressure, 1.7 psi above torus pressure for normal power' operation and provide the ability to re-establish the 1.7 psi drywell to torus %P d
' I within one hour should the '6P be lost'for any reason.
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< !y EDCR 82-24 (Modification of Vermont. Yankee NPS Torus) t fm j)
Modifications'to torus internals for the LTP.
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Modifications to torus-attache'd pipe supports due to new loads from the.
LTP.
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EDCR 82-37'(Torus Instrumentation) ,
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- lRemountvabioustorus'nstrumentationduetoEDCR82-24.
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EDCR 83-23 (Additional Torus-Attached Piping Support Modification (Design) ,
- Modifications'to the torus-attached pipe support not covered in ii EDCR 82-35. - },
NRC Acceptance (Docket No. 50-271,' dated July 2, 1984).. -
NRC, completed a post-implementation audit review of the Vermont Yankee ,
Nuclear Power Station Plant Unique Analysis Report for the Mark I L
Containment,Lon5-Term Program. The NRC concluded that the modifications d.ade by Vermont Yankee have, restored the original design safety margin ',
and the issue was complete.
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SUNARY TO YANKEE RESPONSE TO i
5 MARK I CONTAINMENT PROGRAM
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- eCriteria ---- ---- - - - - > NUREG-0408 Res olution ------------- O---------> EDCR VY 76-1 and PDCR 76-9 i
NRC Acceptance -------e --- > Docket No. 50-471,
- ". . dated, January )3, 1981
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--> NUREG-0661 4 chE nups-1.tS88 t
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' Resolution'j, - - - - - - - - -
t> EDCR 79-9 EDCR 79-57
' EDCR 80-11 <
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EDCR B0-56 p' ,
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EDCR 82-24 IDCR 82-35
' EDCR 82-37 ,
- f. EDCR 83-23 j ,
.i j, ---- > Docket No. 50 271, NRC] Acceptance
'~' dated July 2, 1984 bb Two reports - one titled " Plant-Unique Analysis Report of the To'rus t }
p.gi Suppression Chamber",(Technica1 ,
Aelprt TR--5319-1, Revision 2) and the other <
" Plant Unique ena'ysi's tuport of the'Iorus >,
Attached Piping" (Technical Report 1 '1" ! t i TR-5319-2) - detail the Matt I Contaih:rient Program for Vermont Yankee Nuclear , ,
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PARTIES. INVOLVED IN MARK I CONTAINMENT RESOLUTION FOR VERMONT YANKEE
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b- o Short-Term Program (EDCR VY 76-1 ar.d PDCR 76-9) y
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owner.
VermontYhukeeNuclearPower, Corporation Engineers Yankee Atomic' Electric Company ;
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Engineering Consultant -
-L Teledyne Materials Research I
Construction ,
Mercury Company ,
o Long-Term Program (EDCRs 79-9. 79-57, 80-11, 80-56, 82-24, 82-35, 82-37, ' )
'- and 83-23)
.O.wn e r Vermont Ydnkee Nuclear Power Corporation pm.
V 3Nineers Yankee Atomic slectric Company P Responsibilities
- 1. Co'erdinate censultant activities,
- 2. Mem'ier of Mark I Ovners' Group,
- 3. Preparett:!od' of Detailed Design Change Packages (EDCRs) for all 9
modifications related to the Mark I, Program, and l 1
L 4 ,, Provide on-site engineering, support during installation activities.
Engineering Consultants 1;., General Electric Comeany Responsibilities 1
- a. Mark I Program Manager,
- b. 'Dewlop new hydrodynamic load definitions (LDR and PULD), and p
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- c. Generic licensing.
i 5830R/18.101.
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- 2. NUTECH ,
Responsibilities a.. Mark lI. Program monitor for' load development work under contract
'to Mark I Owners' Group.
3.' Teledyne Materials Research/Teledyne Engineering Services Responsibilities-
- a. Utilized load' definition documents and plant-unique test data to analyze torus internal and external structures, and
.bE Designed modifications, all but large bore torus-attached pipe supports.
4..'Cygna Energy Services
' Responsibilities
- a. Provide analysis, modification / design for large bore torus-attached pipe supports, and L b. Provide field engineering support during installation of large bore torus-attached pipe supports.
Construction -
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- a. Chicago Bridge and Iron
' Responsibilities
- 1. -Downcomer Ties
- 2. Vent Header Deflector
- 3. SRV' Quenchers and Supports
-4 Torus Support Reinforcement
- 5. RER Return Line Elbow
- 6. One Inch 0 Vent Drain Line RCIC Turbine Exhaust j 7.
- 8. Spray Header Support i-B. Mercury Company l Responsibilities
- 1. Vent Header and Downc'omer Stiffening *
- 2. Torus Monorail
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.3... Catwalk Grating and Handrail
- 4. Temperature Monitoring System
- 5. Containment Inerting System
- 6. SRV Discharge Line Vacuum Breaker
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e C. Vermont Yankee Maintenance Staff
!]. Responsibilities Wetwell/Drywell Vacuum Breaker Disc Modification 1.
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Responsibilities r (/T w
- 1. Wetwell/Drywell Vacuum Breaker Dise Modification i'
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MARK I STRUCTURAL ANALYSIS
-s
~j GE LDR _ _ _ ._.
PULD
_l I
I e I 1
TES t Structural _
Analysis Calculations YAEC CYGNA Modification EDCRs Analyze, Design Drawings o Design Information Design / Modify SRV Line Supports o' QA Requirements Large Bore ,,
Piping Analysis o Safety Evaluations TAP Supports Calculations / Support Loads o Installation Specs Review and Approval I I
of Vendor Documents On-Site QA/QO Plant- +__d Specific Licensing N ,]
- U CBEI AND MERCURY COMPAhT Installation Procedures .
k'elding KDE Installation Drawings QC D
e 4
W 73
'J
'- 5830R/18.101
L' f '. ;
TEMPERATURE MONITORING SYSTEM
.m '
i
- 1. - FRITERIA l
NUREG-0661 ,,
Sec. 3.10 NUREG-0783 1TSD TELEDITE EDCR 82-37 *--- --
Hydrodynamic Loads on Instruments and Supports !
MERCURY COMPANY
/~T kJ Installation Qc I
i'
'd 5830R/18.101
l 1.0 ORGANIZED. COORDINATED, AND DIRECTED i
f) v Issue How was the overall engineering effort for response to USI A-7 organized, coordinated, and directed?
Response .,,
The overall engineering effort to resolve USI A-7 was organized, coordinated, and directed by NSD of YAEC.- The organizational flow charts are provided in attached presentation package.
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V 5830R/18.101 i
I
1 2.0 0//QC INVOLVEMENT
?
(l q)
. Issue How as QA/QC involved in the overall effort to address USI A-77
Response
The YAEC Quality Assurance }rogram provides for three levels of control:
Level 1 - This level includes independent inspections and tests performed during routine and nonroutine activities by appropriately trained personnel. As determined by the Quality Control Task Force, independent inspections of normal plant activities are provided by the Vermont Yankee plant through their peer inspection program.
Level 2 - This. level includes surveillance and monitoring activities )
^
' that are performed by the YAEC QA Department. Such activities include observation of tests and inspections, !
significant activities, vendor performance, and review of !
records and procedures. Surveillance verify, on a sample basis, that day-to-day activities are effectively and adequately controlled.
Level 3 - This icvel includes a comprehensive audit and evaluation program by the YAEC Quality Assurance Department to assure that the QA Program is functioning as it should and doing the (q
./ job it should. This level includes measures performed to verify that activities required by the Operational Quality '
Assurance Manual (YOQAP-1-A) are established, implemented,
' ~
and satisfy regulatory requirements.
OUALITY AUDIT AND ENGINEERING GROUP j t
i The Quality Audit and Engineering Group (QA&EG) is responsibic for providing technical expertise in specific areas of the Operational Quality Assurance Program. These areas include overall responsibility for the In-Plant Audit Program, YNSD Operational Quality Assurance Program Manual Internal Audit Program, Trend Analysis, training of YNSD Quality Assurance personnel, procedure reviews, and QA record retention.
)
PROCUREMENT GROUP The Quality, Design, and Procurement Group (QD&PG) is responsible for maintaining and implementing a system for the control of purchased material, equipment, and services. This system includes maintenance of the YAEC ;
Approved Vendors List for operating plants, which is supported by implementation of a vendor audit program, and review of procurement documents, which is supported by a vendor surveillance program.
1 j
{ A I U 5830R/18.101
-- J
, m L
LThe QD&P GroupLis' responsible'for. reviewing plant and' engineering design change requests, specifications, procedures, and drawings-to assure that appropriate' quality standards are included or referenced;therein.
i TOPERATIONS OUALITY' GROUP' The. Operations Quality Group (0QG) is. responsible for providing Vermont
. Yankee'with on-site expertise in the. areas of mechanical, electrical, .
. instrumentation, Land NDE Quality Assurance.
y OQG is' responsible'for the performance'of surveillance of essentially
' all activities addressed by the QA' Program._LOQG performs reviews of specified~
-documents for inclusion of QA' requirements and reviewsfand approves plant QA procedures.:.0QG interfaces with QD&PG.for activities' performed at the plant and audits or surveillance ; of.' local- vendors. ' OQG-interfaces with-QA&EG through the performance of reaudits and'closecut of items on the Plant Audit and Discrepancy Status Report.
I 6
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.b 5830R/18.101 n----- a .1------- - - --w-- . - - . - - . - - - - - ----_--_--------_------_-__--a__----_--.--_-_
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3.0 AE/ CONSULTANT FIRMS
,n I88"'
(f 7,-[
L- -What AE/ consultant firms (if.any) were used to develop responses and/or' ;
. perform analyses.and design modifications? What was the extent of their l involvement (scope of work)?
s
Response
o Short-Term Program Engineering Consultant - Teledyne Responsibilities Analysis and design of torus column reinforcements and tiedown.
o Long-Term Program Engineering Consultants
- 1. General Electric Company Responsibilities
- a. Mark I Program Manager T Develop new hydrodynamic load definitions (LDR and PULD)
-437 ) b.
- c. Generic licensing
- 2. NUTECE Responsibilities
- n. Mark I Program monitor for load development work.under contract to Mark I Ovners' Group
- 3. Teledyne Materials Research/Teledyne Engineering Services i Responsibilities
- a. Utilized load definition documents and plant-unique test data to analyze torus internal and external structures
- b. Designed modifications, all but large bore torus-attached pipe supports s
l' Nb*' 5830R/18.101
1
- 4. Cygna Energy Services .
-s f Responsibilities
(;Jy l
- a. Provide analysis, modification / design for large bore j torus-attached pipe supports
- b. Provide field engineering support during installation of large (
bore torus-attached pipe supports i
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O m e-,a I
f' N 5830R/18.101
]
4.0 PERSONNEL QUALIFICATIONS l,, ) Issue 1 What personnel qualifications and/or special training was provided (or required) for licensee and/or consultant personnel involved in work performed
- for USI A-77 11
Response
No specific personnel qualifications and/or special training was provided (or required) for licensee and/or tonsultant personnel involved..
although a number of procedures and work instructions were developed and adhered to for the USI A-7 effort.
A list of procedures, work instructions, and engineering guidelines, as well as who they were used by, is shown below. All are available for review upon request.
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Q. <
.e iYAEC; : ;YAEC Engineering Manual g e
- TES. - Project QA' Program Project No.' 2252/5319 A-F'
- Procedure for preparing SRV loads for analysis.
GeneralLcontrol procedure EP-1-003.
- EngineeringProcedure$P-2-042,"AnalysisofSmallBorePiping Attached to the Torus Shell'for VYNS"
- Engineering Procedure EP-2-020. " Calculation of Pipe Wall Stress'at Shear: Lugs" E - Engineering Procedure EP-2-021,'" Baseplate and' Anchor Bolt' Analysis"
- . Engineering Procedure EP-2-027, " Calculation of Pipe Wall Stress at Stanchions and Trunnions" CYCNA'- Work instruction for pipe support analysis.WI-82005-3
- Work instruction for pipe support analysis by hand calculations' WI-82005-4' Work instruction for pipe support analysis using'GTSTRUDL WI-82005-5.
- Work instruction for base plate' analysis using "EPLATE.'.' WI-82005-6.
k -
- Work instruction for. field change requests WI-82005-77
. . Work; instruction for walkdown verification of TAP pipe supports WI-82005-9.
- Design criteria for pipe support analysis DC-82005-2.
\1 0
6 5830R/18.101 7
1.
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5.0 OA OVERSIGHT / AUDITS I~T Issue
\..)
Frovide' documentation of QA oversight / audits of all contract organizations involved'in USI A-7 actions.
Response ,,
Material for Question No. 5 are QA oversights of all contract organizations involved in USI A-7 actions. .
Mercury Company Roll / Blip 88/14 Vendor Evaluation Report 75-1 (VER 75-1), April 3, 1975 Surveillance Report 76-8, February 19, 1976 81/1186 GE - Installation and Service Engineering (I&SE)
VER 79-7, January 26, 1979 149/438-Teledyne Engineering Services (TES)
. VER 79-29, September 5, 1979 273/391 VER 79-29-1, November 30, 1979 273/404 VER 83-38, January 12, 1984 896/166
~
VER S3-38-1, March 23, 1984
- 896/187 7'N .
418/1228
- (_) Surveillance Report.(SR) 83-25, February 16, 1983 460/507 SR 83-25-14 June 21, 1983 ER 83-25-2, July 15, ?983 ~
460/516
..^
SR 83-64 September 16, 1983 460/569 SR S3-64-1, January 5, 1984 877/737 ER 84-54, August 3, 1984 877/1043 Cygna Energy Services VER 83-04, February 24, 1983 663/37 VER 83-39,1 January 27, 1984 896/192 VER 83-39-1, May 7, 1984 896/214 VER 83-39-2, September 10, 1984 896/217 SR 83-61, September 8, 1983 460/545 SR 83-61-1, October 31, 1983 ,
460/555 Teledyne Materials Research (TMR)
Surveillance Report 76-9, February 23, 1976 81/1189 Chicago Eridee and Iron (CB4I)
Surveillance Report 80-95, August 14, 1980 248/410 Surveillance Report 80-95-1, August 14, 1980 248/410 Surveillance Report 80-95-2, September 9, 1980 248/410
,~~
-}' 5830R/18.101
Quality Assurance Inspection (Surveillance) 1 I
/~'E EDCR 76-01 (NUREG-0408) Surveillance 76-4
~
EDCR 79-09 (NUREG-0661) None !
EDCR 80-11 80 l l
83-24 :
EDCR 82-24 None ,
EDCR 82-35. ,,
83-14 l
. EDCR 82-37 83-46 EDCR 83-23 None EDCR 80-56 st-zo BL-05 Internal and In-Plant Audits Internal Audit No. 35 (Mechanical Services Group) included review of EDCR 82-37.
' In-Plant' Audit VY-85-07 included review of EDCR 80-56.
Nuclear Safety and Review Committee
~
. EDCR 83-23, Meeting 83-11-S 83-13-R NOTE All the above'are available for review upon request.
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5830R/18.101 ;
}
l 1
1 6.0 CYGNA/TELEDYNE 7_
Issue Q_)
Clarify whether Cygna was subcontracted to Teledyne Engineering Services j (TES) or was contracted directly by Yankee Atomic. i l
1 Response , ,
Cygna was contracted directly by Yankee Atomic. >
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5830R/18.101
I>
7.0 ENGINEERING PROCEDURES MANUAL
- v[ )_ . Issue-i Provide a copy of the engineering procedures manual in effect at the time the'USI A-7 modifications were designed and installed. This information
- should be available during the' inspection.
o
Response
See attached engineering procedures.
O- .
O l
I 5830R/18.101
--- ---_j
8.0 TORUS STRUCTURE AND SYSTEM MODIFICATION INFORMATION !
(~T y1 Issue Complete documentation pertaining to the following torus structure and '
system modifications is required.
8.1 Torus Column Reinforcement and Tiedown-8.2 Mitered Joint Saddle 8.3 Vent Reader Deflector ,
I 8.4 Drywell/Wetwell Differential Pressure Control System 8.5 SRV Tee-Quencher and Supports 8.6 Fool Temperature Monitoring. System ,
8.7 Saddle Anchor Bolts c I
As a minimum, the following information should be included in these ;
information packages:
- a. Installation Specifications
- b. Structural Adequacy, Calculations .
T' -
e A- c. Contract and Procurement Documents
- d. Design / Construction Drawings
- e. As-Built Drawings
- f. Procedures Governing:
l .
Installa. ion Work Welding Nondestructive Examination Inspection -
- g. Personnel certification and qualifications for:
I Welding Nondestructive Examination Quality Control l
k' 5830R/18.101 l
l U-_- _-- -
- h. Material certification for:
f, ') - Structural Steel s -
Piping _
Coating ti
- 1. Documentation of QC' inspection of fabrication / installation activities J. Nonconformance reports generated during the modification activity (if applicable)
- k. References to all Technical Specification (TS) sections affected by each particular modification
' Response-
~
See attached Sections 8.1 through 8.7.
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\- 5830R/18.101 l
1 t
- _ . _ _ _ _ _ _ . _ _ _ s
.i.
8.1; Torus Column Reinforcement-and Tie-Down
~ ., .
-! ;a. . Installation Specifications
- 1. lEDCRi76-1:
- b. Structural Adequacy Calculations'
.. - o
- 1. See"TES Calculation 5319F-240
- c. Contract and-Procurement Documents
- 1. .See Microfilm Roll 2342 - Blip 1466
- d. : Design / Construction Drawings 1.. Teledyne Drawings:
C-4056, Revision 2
'D-4429, Revision 3 C-4049,' Revision 1 C-4087, Revision 0 C-4086, Revision 0 B'4057~
- ,' Revision 1
, B-4051, Revision 1 ,
C-4050, Revision 0 B-4053 Revision 0 _.
~
.B-4048,' Revision 0.
{ ' ri 1 , e.- As-Built-Drawings .
. 'I
-1. Vermont Yankee drawings: , :]
}
1 5920-6042 Revision 0 L 5920-6043, Revision 1 5920-6044,- Revision 0. e 5920-6045, Revision 0 5920-6046, Revision 0 . 5920-6047, Revision 0 ,
)
5920-6048, Revision 0 jJ 5920-6049, sheet 1, Revision 0 .
-5920'-6049, Sheet 2, Revision 0 1
- 5920-6049 . Sheet 3, Revision 0 f'.
. Procedures Governing: -
~
- 1. Installation Work See Microfilm Roll 2342 - Blip 1111 ,
- 2. Welding See Microfilm Roll 2342 - Blips 1229, 1303
.5830R/18.101
- 3. Nondestructive Examination a,
("'N See Microfilm Roll 2342 - Blip 1252
\~/- ,
- 4. Inspection See Microfilm Roll 2342 - Blip 1214 g; Personnel Certification'and Qualifications For:
jl . Welding See Microfilm Roll 2342 - Blip 1492
- 2. Nondestructive Examination I See Microfilm Roll 2342 - Blips 1286 and 1476
- 3. Quality control See Microfilm Roll 2342 - Blip 1976
- h. Material Certifications For:
- 1. Structural Steel
' See Microfilm Roll 2342 - Blip 1352 /^)
( ,/ 2. Piping -.. - w.e
.See. Microfilm Roll 2342 - Blip 1352
- 3. Coating !
See Microfilm Roll 2342 - Blip 1352
- i. Documentation of QC Inspection of Fabrication / Installation Activities
- 1. See Microfilm Rolls 2341 and 2342
- j. Nonconformance Reports Generated During the Modification Activity
- 1. See Microfilm Roll 2342 - Blip 1508
- k. Technical Specification Changes ,
I
- 1. No Technical Specification changes as a result of EDCR 76-1.
}
,A
\-) 5830R/18.101
8.2 MITRED Joint Saddle Installation Specifications 0' i a.
- 1. EDCR 80-11
- b. Structural Adequacy Calculations
- 1. See TES Calculations 5319-23, 5319F-230, and 5319F-231.
- c. Contract and Procurement Documents
- 1. See Microfilm Rolls 1964 - Blip 1310; 1974 - Blips 1460, 2325; 1975 - Blips 110, 416, 495; and 1976 - Blip 620
- d. Design / Construction. Drawings
- 1. Teledyne Drawings:
-E-5169 Sheet 1, Revision 1 E-5169, Sheet 2, Revision 1 A-5183, Revision 0
- 2. CB&I Drawings:
70, Revision 3 71, Revision 4 (' 72, Revision 3
' 73, Revision 4 74, Revision 7 75, Revision 2 ,,
76, Revision 3 77, Revision 2 78, Revision 0 80, Revision 2 81, Revision 7 ' - 82, Revision 2 83, Revision 2 84, Revision 1
- e. As-Built Drawings l
- 1. Vermont Yankee Drawings: .
5920-263, Revision 2 5920-9131, Revision 0 5920-9132, Revision 0 5920-9133, Revision 0 5920-9134 Revision 0 5920-9135, Revision 0 5920-9136 Revision 0 5920-9137 Revision 0 5920-9138, Revision 0 l . %/ (3 5830R/18.101 1
5920-9139, Revision 0 5920-9140, Revision 0 5920-9141, Revision 0 (V~') 5920-9142 Revision 0 5920-9143, Revision 0 5920-9144, Revision 0
- f. procedures Governing: g
- 1. Installation Work See Microfilm Rolls 1974 - Blip 1424; 1975 - Blips 93, 148,'370, 2007; and 1976 - Blip 440
- 2. Welding See Microfilm Rolls 1974 - Blips 481, 1108; 1975 - Blips 2205, 2404; 1976 - Blip 2027; and 1964 - Blip 957.
- 3. Nondestructive Examination l See Microfilm Rolls 1974 - Blips 664, 1287; 1975 - Blip 2007; 1976 - Blips 254, 2323; and 1964 - Blip 909.
- 4. Inspection See Microfilm Rolls 1975 - Blips 157, 196, 2007; and 1976 -
j] Blips 926, 964. V
- g. Tersonnel Certification and Qualifications
~ '
l '.' Welding See Microfilm Rolls 1975 - Blips 185, 977; 1976 - Blip 2119; and 1964 - Blip 596.
- 2. Nondestructive Examination See Microfilm Rolls 1975 - Blip 180; 1976 - Blips 26, 259, 709, 2237; and 1964 - Blip 749.
-3 . Quality Control l
See Microfilm Rolls 1975 - Blips 199, 225; and 1964'- Blip 513.
- h. MateriakCertificationsFor:
- 1. Structural Steel See Microfilm Rolls 1975 - Blips 165, 1053; 1976 - Blip 571; and 1964 - Blip 1310.
f~h xI 5830R/18.101 l
-( !
l
- 2. Piping >
\;
_ {: See Microfilm Rolls 1975 --Blips 165, 1083; 1976 - Blip 571'; ar.d , ')
,r)i i
(- 1964 - Blip 1310. ; l
- 3. Coating See Microfilm Rolls 1975 - Blips 165, 1083; 1976 - Blip 571; ,
1977 - Blip 42; and'1964'- Blip 1310 j q , i. Documentation of OC Inspection of Fabrication / Installation Activities \ i I
- 1. See Microfilm Rolls 1974, 1975, 1976, and 1977.
- j. Nonconformance Reports Ge'nerated During the Modification Activity ; I
- 1. See Microfilm Rolls 1974 - Blip 376; 1975 - Blip 831; and 1976 -)
Blips 434, 2015. . .
~
- k. Technical Specification Changes ,
- A.r : >
- 1. No Technical Specification changes as a result of EDCR 80-11.- b
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) Structural Adecuacy Calculations .
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- 1. See TES Calculation'A 2252-1, 5319F-210, and 5319F-211._ f
)&o # c. Contract and Procurement Documents \
2
/ ,
- 1. See Microfilm R 11s 1964 - Blip 1310; 1974 - L ps 15.50., 2325; ,
1975. - Blips hJ, 416, 495;/ and 1976 - Elip 62!... ' >
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- d. Desien/ Construed.J - on Drawings ,
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- 1.' Teledpra, Drawings: ,
's 1 ,,
D-4%f,7.evition.2 D-4930, Revision 2 - g=
+
D-5168p Revision 2 , C-5268,0.evision 1 * , B-5271g Rtvisi.on 0 i
# ,D-52Q', Mvision0 "
a D-5299, Revision 0 j D E-530P, Revision 1 , C-5303, Revision 0 1 ; (] L ' C-5304, Revision 0 3: ( l d ,r 2.'(ChiDrawings: / '
~
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's L i f/7,3evision 4 ,
d, I 51,' E.itision 4 3 1
/g, 52'," Revisien 4 6
.- 53, Revision 2 l
54, Revision 2
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55, Revision 2
- 56, Revision 3'? ,.
57, Revision 3 58, Revisio'n 3 ^ 59,~ Revision 4 j 60, Revision 4 [; l
~ ~
- 61. Revision 1 f
- 62. Revision 2 ,! t
- e. As-Built Drawines V 1. VermontYandeeDrawings: ,
+ ,
g.,s. 5920-9170, Revisi n U' M' j l 5920-9171, Revisi d 0 i f 5920-9175, Revis4p 0 , b i ie , O SS30R/lb.lf'1 I i
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. 5920-9180s Revis'!on 0
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"+ .' ~ 5920-9182,' RevisIc'n 0 O - ,
94.. -5920-9183 RevfAion.0N.
- I' m
- o L ", i ,
- - 5920-9187. :Revidon 0:
' 5920-4124; Revidion0 t, i fi e ,
i
? '
- 5920-9125,L Revision 0 '
- 5920-9126, Revision'0 ,
E F L5920-9127,- Revisiq,.0 -L 15920-230 Revision'5b. ;
+y ,
5920-446,: Revision 2'/. At 5920-9119,; Revision 0f ,<-
'!E ,5920-9120, Revision O ,
,. , "d.~'
s,} V -
~
592.0-9121, Revision 0i 3 5920-9122,; Revision G'< /G {f pii s s. .5920-9128,fRevision 0 , , b f$.A 5520-9129, Revision 0 Y 00 - 5920-9130,'.Rev.ision O. +
!'. ' M.
SP to -SlL3f Row n.4 0 _f.*. .:)y )) Procedures Gove- ningr(*
+ '
\
lv '; y[ 'h ,. i' 1. . Installation Work
} l,
' 1-9,lal '
-See' Microfilm' Rolls 1974 - Blip.1424; 1975 - Blips 93, 148,'370, i.
4.p^ . L2007; and 1976' Blip 440.. i - ! ( ,% ,
. fi 2. Welding [n~
4 s . . . See Microfilm Rolls 1974 - Blips 481, 1108; 1975 - Blips 2205,
,p 3 ";
~
2404;:1976 - Blip 2037; and 1964 -Blip 959.
.M q ;
,y ' '
- 3. ' Nondestructive b aaination
- J _
See Microfilm Ro11s-1974 -J,11 pag 664, 1287; 1975 - Blip 2007; ! j
- 1976 - Blips 254,'2323; and 1964 - Blip 909. j
,q '
', 4. Inspectilon , 1 g O e ,
6 , i 3 .- s X ,. .
# .See Microfilm Rolls 1975 y slips 157,196, 2007; and 1964 - ,
i Elips926,9645 ' N r l' g.,' Personnel Certification and Qualifications For: .
- ! 1. Welding ,
See Microfilm Rolls 1975 - 311ps 185, 977; 1976 - Blip 2115i and l' 1964 ( 311p 596. a 3
. 3,
- 2. Nondestructive T.xamination See Microfilm Rolls 1975 ' Blip 180; 1976 - Blips 26, 259, 709, --
0- 2237; and 1954'- Blip 70.' ( { SS30R/18.101 s ( E____.__ _ __ - __J
S 6 lp 3' . :. Quality Control- '
-ni L . ,,
See. Microfilm Rolls 1975 - B1ips 199, 225; and.1964 - Blip'513..
- p. ,
.h. . Material' Certifications For:
~ 1. . Structural Steel Blips 165,-1083; 1976 --Blip 571; and' See Microfilm'Ro11[ 1975 1964 - Blip.-1310.
- 2. Piping
.See Microfilm Rolls 1975 - Blips.165, 1083; 1976 - Blip 571;-and ,
1964 - Blip 1310. ,
- 3. Coating See Microfilm Rolls 197f'- Blips 165, 1083; 1976 - Blip;571; ~
'197,7 - Blip 42; and 1964 - Blip 1310.
~
- i. ' Documentation of 00 Inspection of Fabrication / Installation Activities-
- 1. See Microfilm Rolls 1974,1975,1976, and 1977.
J. Nonconformance Reports Generated'During the Modification Activity- ' lr I '1. 'See' Microfilm Ro11s1974 -l Blip 376; 1975 - Blip 831; and 1976'-
. Blips 434,.2015. ^
- k. Technical Specification' Changes i ,
1.- No Technical Specification changes as a result of EDCR 80-11. t 4 f
- 9 9 m m
, 5& "-
f
.5 SS30R/18.101 1
_ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ ._ _ _ _ _ _ _ _. a
8.4 Drvwell/k'etwell Differential Pressure t a. Installation Specifications (~'J L. '
- 1. Short-Term Program PDCR 76-9
- 2. Long-Term Program
'EDCR 80-56
- b. Structural Adequacy Calculations
- 1. Short-Term Program See Section 7.0 of PDCR package
- 2. Long-Term Program See Section 11.0 of EDCR package
- c. Contract and Procurement Documents
- 1. Short-Term Program See Microfilm Roll 710 - Elips 25, 67, 216 iQ
's > 2. Long-Term Program See Generic File 85-16 (Folder 1 of 2), Fred Burger's office at Vermont Yankee.
- d. Design / Construction Drawings
- 1. Short-Term Program Included in PDCR package .
- 2. Long-Term Program See Section 10.0 of EDCR package
- e. As-Built Drawines
- 1. Short-Term Program See PDCR package
- 2. Short-Term Package l See EDCR package
-k 5830R/18.101
l. I
- f. Procedures Governing For:
f^; v-
- 1. Installation Work (Short-Term Program)
See Microfilm Rolls 710 - Blips 25, 89, 269 Long-Term Program See Microfilm Rolls 2343 - Blips 1581,1683,1728,1829, 2026, 2142; 2344 - Blip 276; 2381 - Blips 3168, 3246
- 2. Welding (Short-Term Program)
See Microfilm Roll 710 - Blips 25, 209 ) Long-Term Program See Generic File 85-16 (Folder 2 of 2), Fred Burger's office at I Vermont Yankee.
- 3. Nondestructive Examination (Short-Term Program)
See Microfilm Roll 710 - Blip 25 Long-Term Program See Generic File 85-16 (Folder 2 of 2), Fred Burger's office at Vermont Yankee. _3, O) 4 Inspection (Short-Term Program) ."" .
' '~ ~ ~
See Microfilm Ro11'710' - B' lip'25~ . Long-Term Program See Generic File 85-16 (Folder 2 of 2), Fred Burger's office at Vermont Yankee.
- g. Personnel Certification and Qualifications For:
- 1. Welding (Short-Term Program)'
See Microfilm Roll 710 - Blips 144, 244 . . Long-Term Program - See Generic File (Folder 1 of 2), Fred Burger's office at Vermont Yankee. L 5830R/18.101
~-
- 2. Nondestructive Examination (Short-Term Program) 1
.(' 'See Microfilm Roll 710 - Blips 144, 239
'Long-Term Program See Generic File 85-16 (Folder 1 of 2), Fred Burger's office at Vermont Yankee. ,,
- 3. Quality Control (Short-Term Program)
See Microfilm Roll 710 '- Blip 144. Long-Term Program , 1 See Generic File 85-16 (Folder 1 of 2), Fred Burger's office at.
~
Vermont Yankee.
- h. ' Material Certifications For:
- 1. Structural Steel (Short-Term Program)
See Microfilm Roll 710 - Blips 25, 216. Long-Term Program See Microfilm Roll 2344 - Blips 338, 905. ['D d> 2. Piping (Short-Term Program)' )
- i See Mi,crofilm Roll. 710 - Blips 25, 216.
Long-Term Program See Microfilm Roll 2344 - Blips 338, 905
- 3. Coating (Short-Term Program) j See Microfilm Roll 710 - Blips 25, 216. ,
Long-Term Program See Microfilm Roll 2344 - Blips 338, 905 !
- i. Documentation of OC Insnection of Fabrication / Installation Activities
- 1. Short-Term Program See Microfilm Roll 710.
- 2. Long-Term Program See Microfilm Rolls 2343, 2344, and 2381.
(9 k/ 5830R/18.101 i
- -j. Nonconformance Reports Generated During the Modification Activity (Short-Term Program) t l
,~'
)
- 1. See Microfilm Roll 710 - Blip 410. ]
l Long-Term Program l None ,, i
. k. Technical Specification Changes (Short-Term Program)
- 1. See Section 13.0 of PDCR package.
Long-Term Program No Technical Specification changes as a result of EDCR 80-56. p wm
'L.l A.
e 9
, - ~
SS30R/18.101
8.5 SRV Tee-Quencher and Supports
# Installation Specifications a.
l %)1
- 1. EDCR 80-11 b ., Structural Adequacy Calculations
- 1. SeeTESCalculation$ 5319-36, 5319F-220, and 5319F-221.
- c. Contract and Procurement Documents .
- 1. See Microfilm Rolls 1964 - Blip 1310; 1974 - Blips 1460, 2325; 1975 - Blips 110, 416, 495; and 1976 - Blip 620 d ." Design / Construction Drawings
- 1. Teledyne Drawings:
D-4900, Revision 2 D-4901, Revision 2 D-5221, Revision 1
- 2. CB&I Drawings:
21 Revision 6 , 22, Revision 4 ('l 23. Revision 4 T
'- 30, Revision 2 31, Revision 5 32, Revision 9
- e. As-Built Drawings
- 1. Vermont Yankee drawings:
5920-9108 Revision 0 5920-9109, Revision 0 5920-9110, Revision 0 5920-9111, Revision 1 5920-9112, Revision 1 5920-9113 Revision 1 5920-9178, Revision 0 ' 5920-9179, Revision 0
- f. Procedures Governing:
- 1. Installation Work .
See Microfilm Rolls 1974 - Blip 1424; 1975 - Blips 93, 148, 370, 2007; and 1976 - Blip 440 0 5830R/18.101
- 2. Welding
- x See Microfilm Rolls 1974 - Blips 481, 1108; 1975 - Blips 2205,
(~')~ 2404; 1976 - Blip 2037; and 1964 - Blip 957 I.
- 3. Nondestructive Examination See Microfilm Ro11s,1975 - Blips 664, 1287; 1975 - Blip 2007;
*976 - Blips 254, 2323; and 1964 - Blip 909
- 4. Inspection -
See Microfilm Rolls 1975 -. Blips 157, 196, 2007; and 1964 - Blips 926, 964
- g. Personnel Certification and Qualifications For:
- 1. Welding See Microfilm Rolls 1975 - Blips 185, 977; 1976 - Blip 2119; and 1964 - Blip 596
- 2. Nondestructive Examination See Microfilm Rolls 1975 - Blip 180; 1976 - Blips 26, 259, 709, 2237; and 1964 - Blip 749
- 3. Quality Control
{ ]) See Microfilm Rolls 1975 - Blips 199, 225; and 1964 - Blip 513
- h. Material Certifications For:
- 1. Structural Steel See Microfilm Rolls 1975 - Blips 165, 1083; 1976 - Blip 571 and 1964 - Blip 1310
- 2. Piping See Microfilm Rolls 1975 - Blips 165, 1083; 1976 - Blip 571; and 1964 - Blip 1310
- 3. Coating See Microfilm Rolls 1975 - Blips 165, 1083; 1976 - Blip ",/1; 1977 - Blip 42; and 1961 - Blip 1310
- i. Documentation of QC Inspection of Fabrication / Installation Activities
- 1. See Microfilm Rolls 1974, 1975, 1976, and 1977.
l f} 5630R/18.101 i
.J. Nonconformance Reports Generated During the Modification Activity See Microfilm Rolls 1974 - Blip 376; 1975 - Blip 831; and 1976 -
i i 1.
Blips 434, 2015
- k. Technical Specification Changes
- 1. No Technical Specification changes as a result of EDCR 80-11.
l v o) - 1 < l N . t l i .. i:.; O 5830R/18.101 l i i i
i 8.6 ' Pool Temperature Monitoring System m
- a. Installation Specifications (v) .
- 1. EDCR 82-37
- b. Structural Adequacy Calculations
- 1. See YAEC Calculation VYC-165.
- c. Contract and Procurement Documents i,
- 1. See Microfilm Roll 2537 - Blips 77, 922
- d. Design / Construction Drawings See Section 10.0 of EDCR package
- e. As-Built Drawings
- 1. Vermont Yankee drawings:
See Section 10.0 of EDCR package
- f. Procedures Governing: (See Section 12.0 of EDCR)
- 1. Installation Work t
See Microfilm Roll 1963 - Blips 75, 83, 95, 140, 150, 190, 200, 224, 234, 258, 261
- 2. Welding i See Microfilm Rolls 2537 - Blip 592
- 3. Nondestructive Examination l See Microfilm Roll 1963 - Blips 83, 94', 150, 200, 234
- 4. Inspection See Microfilm Roll 2537 - Blip 824
- g. Personnel Certification and Qualifications For:
- 1. Welding See Microfilm Roll 2537 - Blip 268
- 2. Nondestructive Examination See Microfilm Roll 2537 - Blip 445 5830R/18.101
- 3. Quality Control
[ ', See Microfilm Roll 2537 - Blip 536
.v l h. Material Certifications For:
l
- 1. Structural Steel See Microfilm Ro112537 - Blips 77, 922
- 2. Piping See Microfilm Roll 2537 - Blips 77, 922
- 3. Coating i
~
See Microfilm Rolls 2537 - Blips 77, 922
- i. Documentation of OC Inspection of Fabrication / Installation Activities 1, See Microfilm Roll 1963
'j. Nonconformance Reports Generated During the Modification Activity
- 1. None
- k. Technical Specification Changes (m, .
l 1. No Technical Specification changes as a result of EDCR 82-37.
.- i r N, t
5830R/18.101 I
l l l 8.7 Saddle Anchor Bolts f
/~% l
(,) a. Installation Specifications
- 1. EDCR 80-11
- b. Structural Adequacy Calculations
- 1. See TES Calculations 5319-23, 5319F-230, and 5319F-231.
- c. Contract and Procurement Documents
- 1. See Microfilm Rolls 1964 - Elip 1310; 1974 - Blips 1460, 2325; 1975 - Blips 110, 416, 495; and 1976 - Blip 620
- d. Design / Construction Drawings
- 1. Teledyne Drawings:
A-5184, Revision 1 (~ A-5185 Revision 1
- 2. CB&I Drawings:
1 82, Revision 2
- e. As-Built Drawings j_
'~'-) - 1. Vermont Yankee Drawings:
5920-9142, Revision 0
- f. Procedures Governine For:
- 1. Installation Work See Microfilm Rolls 1974 ~ Blip 1424; 1975 - Blips 43, 148, 370, 2007; and 1976 - Blip 440 .
- 2. Welding See Microfilm Rolls 1974 - Blips 481, 1108; 1975 - Blips 2205, 2404; 1976 L Blip 2037; and 1964 - Blip 957.
- 3. Nondestructive Examination See Microfilm Rolls 1974 - Blips 664, 1257; 1975 - Blip 2007; 1976 - Blips 254, 2323; and 1964 - Blip 909.
- 4. Inspection See Microfilm Rolls 1975 - Blips 157, 196, 2007; and 1964 -
Blips 926, 964.
,f-
~'
5830R/18.101
i 1 l I
- g. Personnel Certification and Qualifications For-1
() 1. Welding
-See Microfilm Rolls 1975 - Blips 185, 977; 1976 - Blip 2119; and 1964 - Blip 596.
- 2. Nondestructive Exag{ nation See Microfilm Rolls 1975 - Blip 180; 1976 - Blips 26, 259, 709,
,2237; and 1964 - Blip 749.
- 3. Quality control !
See Microfilm Rolls 1975 - Blips 194, 225; and 1964 - Blip 513.
- h. Material Certifications For:
- 1. Structural Steel See Microfilm Rolls 1975 - Blips 165, 1083; 1976 - Blip 571; and 1964 - Blip 1310.
- 2. Piping See Microfilm Rollo 1975 - Blips 165, 1083; 1976 - Blip 571; and 1964 - Blip 1310. ,
<~)
k 1. 3. Coating i See Microfilm Rolls 1975 - Blips 165, 1083; 1'976 - Blip 571; ' ' ' 1977 - Blip 42; and 1964 - Blip 1310.-
- i. Documentation of QC Inspection of Fabrication / Installation Activities
- 1. See Microfilm Rolls 1974, 1975, 1976, and 1977. j
- j. Nonconformance Reports Generated Durine the Modification Activity .
- 1. See Microfilm Rolls 1974 - Blip 376; 1975 - Blip,831; and 1976 - .
Blips 434, 2015.
- k. Technical Specification Chances
- 1. No Technical Specification changes as a result of EDOR 80-11.
n
- . SS30R/18.101
- _ _ - _ _ __-.-_ - - - ._ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ - _ -________-_----.___ _ _ 2
~ 9.0 SURVEILLANCE TEST REQUIREMENTS m 4 i. Issue
.> j Provide t,> irveillance test requirements (for systems, components, or structures, as er , cable) that have.been instituted or changed as a result of USI A-7.
l I l
Response
See attached sheets. l t
.~
g i l O~ e N
~
m.. T l SS30R/18.101 l
I t. l y 10.0 PROCEDURES Issue
-U.
Describe the procedure (s) used to control additions to or changes in the plant design configurations of systems and structures. - Provide copies for i review. o 1
Response
'i For a description of'the procedures, see the introduction section of
, 1.
- YAEC " Engineering Manual."
- 2. See YAEC " Engineering Manual" for procedures used.
v l
-)
9 5830R/18.101 i _ __ __- ___ a
1
)
b 11.0 COMPUTER CODES r~x Issue j x,. I List all computer codes used in the USI A-7 efforts. Also, identify ! which versions of the codes were used,-how they were " benchmarked," and which 1 groups or organizations used them. o j
Response
F f GTSTRUDL Program GTSTRUDL was used by Cygna for pipe support analyses. GTSTRUDL was developed by Geor'iag Institute of Technology. GTSTRUDL Computer Program, Version 1, Modification Level' 7 (V1M7), February 1980 and GTSTRUDL User Information Manual. Revision.D. Copyright 1980 by CDC and Georgia Institute of Technology, were used during the TAP Program. PRE _STRUDL Program PRE _STRUDL was used to generate pipe support load combinations and' transformations. PRE _STRUDL was a project-unique computer program developed and used by Cygna specifically for the TAP Program. Program PRE _STRUDL was benchmarked by hand calculations. Benchmarking
.is described in Cygra's PRE _STRUDL Verification Report.
',~,
(,)
^
QA/QC of PRE _STRUDL Program Development is covered in Cygna Documents: (1) Cygna Energy Services Quality Assurance Manual and (2) PRE _STRUDL Verification Report. EPLATE j Program EPLATE was used for baseplate analyses. EPLATE was develo' ped and used by Cygna Energy Services. EPLATE Computer Program, Version 5.1 and
.EPLATE User's Manual, Version 5.1 were used during the TAP Program.
Jrogram EPLATE was benchmarked against the Ansys Program by Cygna. Benchmarking is described in Cygna's EPLATE Verification Report. , w, QA/QC of EPLATE program development is covered in Cygna Documents: (1) Cycna Enercy Services Quality Assurance Manual, (2) EPLATE Verification Report, and (3) EPLATE User's Manual. STARDYNE Program STARDYNE was used by Teledyne to perform almost all of their analysis. The version used was STARDYNE-3 System, 1977 - System Development Corporation, 2500 colorado Avenue, Santa Monica, California 90406. STARDYNE is a fully verified and accepted code in the industry. STARDYNE was marketed and verified by Control Data Corporation. l 5530R/18.101 i l
l u _ STAAD III
.- i r's e Program STAAD III was used by Teledyne to analyze various pipe g
supports. The version used Revision 4.05. STAAD III was developed by i l Research Engineers, Inc. which was marketed and verified by United Information Services .Inc. f l NOTE ,, A number of post-processors were written and uses by Teledyne in response to USI A-7. The post-processors are covered in Issue 12.0 response. l l
,m'
\s-)
t
}
9 8e WW W (') 5830R/18.101
)
12.0 STARDYNE POST PROCESSORS 7" s (,) 1ssue Section 1.0 of the structural PUAR states that post processors for STARDYNE were written and used. List all such codes and provide a description of each' code's function. Provide documentation of the QC coverage applied to l the development of these codes and copies of the user documentation. l
~
l Response' ~ l
- 1. SORT 58 Extracts Quad plates stresses and equilibrium check f nodal data from Tape 58.
l
- 2. FORCE 2 Searches Tape 58 nodal equilibrium check data for '
saddle and column loads to find the maximum time dependent and independent data.
- 3. SORT 70 Extracts proper Quad plate stress vectors from Tape 70.
- 4. SORTP4 Extracts Quad plate stresses and nodal equilibrium check data from Tape 4.
- 5. ADDUP Adds the static time varying interpolated uniform portion of the pool swell stress time history to the dynamic portion.
Calculates nodal force time history applied to shell ()
- 6. TORLOAD for pool swell, event.
- 7. PRESDIG Adjusts plant unique submerged and airspace curves' applied to torus during well events.
- 8. DISTRES Assembles all data stored on tape and completes the elastic and fatigue analysis of the torus shell.
I 9. LOCA JET Calculates LOCA jet loads on submerged structures. I 10. FSI Calculates fluid structure interaction from CO loads on submerged , structures.
- 11. CONDO- Calculates condensation oscillation randomly phased shell stresses from frequency domain data.
- 12. CONF 0 Calculates conversation oscillation randomly phafed j
saddle and column loads from frequency domain data.
- 13. EEAMFOR Calculates pool swell impact and drag forcing functions on vent header beam model.
- 14. FROGSUM Calculates the sum of the force quantities calculated by FSI program from 1 to 31 Ez (frequency domain data).
/~T 5830R/18.101 l
l l l l-L _____.__J
- 15. .NODESUM Extracts plate corner forces and calculates weld shear flow and stresses.
.f7-U 16. CONSTR2 . Transforms the vent header global coordinates to Theta, 2/L application guide coordinate system.
I
- 17. POOLS Calculates the impact, drag, and pool fallback lo' ads on all in,ternal torus structures.
- 18. HEDFORS Calculates pool swell impact and drag forcing functions on vent header detailed FEM.
- 19. TIMTUN Reformats RVFOR time histories for input to STARDYNE DYNRE1 runs.
- 20. TORPEN Calculates torus penetration loads for dynamic events on attached piping lines. .
- 21. THRUST- -
Modifies the RVFOR calculations in accordance with Appendix C of GE Application Guide No. 3, NEDE-24555-P.
- 22. FORSUM Reads Tape 70 of STARDYNE's DYNRE2 output, tabulates
' the maximum amplitudes within each one HZ band width ,
and calculates the resulting maximum stress vector for I condensation oscillation and post-chugging forcing functions. n 23. 00 CHUG Combines the source load output from program CONDFOR () (GE Application Guide No. 2) and the fluid / structure interaction loads output from program FSI (TG-10) in an absolute fashion and calculates their resultant ! loads, ordering them at each one hZ band width. l
)
24.' SUMRY Reformats STARDYNE Tape 4/58 data for use by STARPAS. l
/
- 25. STARPAS Performs a Class 2 code evaluation for piping systems.
- 26. BLOW Reformats Tape 58 DYNRE1 dynamic piping data for use ,
by STARPAS.
- 27. TIMEGEN Creates a full fourier transformer of frequency domain displacements time history data to the time domain.
- 28. READ 54 Reformats Tape 54 output to Tape 55 input for STARDYNE DYNRE1 piping.
- 29. DISCOMB Calculates overall displacements using displacements of individual load cases. l
- 30. SUMFACT Multiplies all support loads and pipe moments from dynamic SUMRY cases by a specified factor. l l3 V 5830R/18.101
_- - _ - 1
1 i
- 31. ASYS- Provide node coordinates as an aid in defining "ASYSG" (rotated coordinate systems) for STARDYNE models.
<,,g-.. ,\ /
NOTE-Documentation for the above is available upon request. I i i
. ~
l
'13 f
./ ~
l i
~
1 l l l
,s
'~ ) 5830R/18.101
- l L _--__ _
l
-' 13.0. TAP LINE ANALYSIS y 3-;
, L,,,) - Issue-
}l l
1 Itemize which tap lines were analyzed by Cygna and which.by TES. ;
-l
Response
i i All' torus attached pipe at ess analyses were performed by TES. i i I
.N U
G I 5630R/18.101 1
14.0 TAP SUPPORT ANALYSIS
,~
'! ,)
~ Issue.
Clarify whether piping supports were analyzed by TES or Cygna. Response -l. o '
- 1. TES was responsible ~for the analysis and modification of small bore tap supports.
2.- Cygna was responsible for the'analy' sis, modification, and design of all large bore tap supports. f. 1
.r ,
'%./ - .
. -)
1 I i l l
~
l i [ l ! 'Q ~' 5830R/18.101 1 . .
15.0. TAP LINE ANALYSIS INFORMATION rx.
< t, j Issue' The following information should be available at the beginning of the inspection for each line selected:
- a. Current.as-built piping, isometric
- b. Current support drawings
- c. Piping analysis d.. Applicable modification packages (including any additional stress-calculations, construction drawings. QC documentation, acceptance test data, etc.)
- e. Any applicable nonconformanca reports and their disposition
Response
See attached sheets.
!3 v.s L
l l l
=
l l-f-%,
!) 5830R/18.101
y- g . - - - , __ _ _ _ _ _ _ l l l 1 Problem No. 1 (AC/1)
.g,
!v a. Current As-Built Piping Isometric Drawings i 5920-9200, Revision 3 l
5920-9201, Revision 3 ii !
- b. . Current Support Drawings All support drhwings are listed on the isometric drawings,
- c. Piping Analysis See TES Calculation 5319-X218. .
- d. Modification Packages l
- 1. See EDCR 82-35 and EDCR 83-23.
- 2. See TES calculations for welded attachments.
- 3. See EDCR packages for construction drawings.
- 4. .No QC documentation, no piping modifications.
- e. Nonconformance Reports
.( '
No NCRs on piping for USI A-7 effort. j 1 1 l A 5830R/18.101 i m_______._ _ . _ _ _ .
Ii Problem No. 10 (CS/2 and RER/7) en
\' a. Current As-Built Piping Isometric Drawings j g
5920-9206, Revision 3 5920-9207 Revision 3 5920-9208 Revision 3 ,, 5920-92S7, Revision 3 - 5920-9288, Revision 3 ,
- b. Current Support Drawings All support drawings are listed on the isometric drawings.
- c. Piping Analysis See TES Calculation,5319-X210A/X211A.
- d. Modification Packages
- 1. See EDCR 82-35 and EDCR 83-23.
- 2. See TES calculations for welded attachments.
-l
- 3. See EDCR packages for construction drawings.
- 4. No QC documentation, no piping modifications.
) '
e' . Nonennformance' Reports . No NCR's on piping for,USI
-7 effort.
{ ' l 5830R/18.101
Problem No. 64 (HPCI/6)
- a. Current As-Built Piping Isometric Drawings 5920-9240, Revision 3 ,
- b. Current Support Drawings ,,
All support drawings are listed on the isometric drawing.
- c. Piping Analysis See TES Calculation 5319-X221.
- d. Modification Packages
-1. See EDCR 82-35 and EDCR 83-23.
- 2. See TES calculations for welded attachments.
- 3. See EDCR packages for construction drawings. .
\
- 4. No QC documentation, no piping modifications.
- e. Nonconformance Reports
(") No NCRs on piping for USI A-7 effort. U. see I 4
5830R/18.101 l
l
-- - - - - _ - - -- _ _ _ _ _ _ _J
I f l; l')) l Problem No.100 (RCIC/1) ~ ( g. a s ('
,ey -f
\2 .a. Current As-Built Piping Isometric Drawings j >,
i.
+
5920-9255., Revision 3 Current Support Drawings q.
- b. ,. .
, f i N, i
All support drawings are listed on the isometric drawings. \ c. Piping Analysis l See TES Calculation 5319-X227.
* \
'/
. j' t , ,
y *n
- d. Modification Packages j, a
- 1. See EDCR 82-35 and EDCR 83-23. .\c j/N S
- 2. See TES calculations for welded attachments.
'(k See EDCR packages for construction drawings.
3.
- 4. No QC documentation, no piping modifications.
/
- i. - ,
- e. Nonconformance Reports ,
hp > ' No NCRs on piping for USI A-7 effort. ,
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Penetration X-206A 5 ( ,7~
"# a. Current As-Euilt Piping Isometric _
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) I l' ,. L;'Jith 'pir'.ng analysis package. e ,,
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-b. CurrentSupporI, Drawings ,, , ,
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. ,X , Non/pplicabledN/A).
'I 1. ! / f ,
} l' s ( I' c. Pi ing Analysia t ,
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,/ See TAS Cniculation 5319 - Small Bcre Piping.
Modd ication Package <j ^ t . .
- d. ,
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s, .1,, 1. N/A t ,/ I
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,' 2. N/A
( j\ 3. N/A ,. ,, t ,- i /' <l
- 4. g.9/A ,f
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is. Nonconformance Reports
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\s - a. Curr0nt As-Built Piping Inometrie il 1, 1 Ilithpfping'analysispsckage. -
i
- b. Current Support Dras!nfg ,,
Thnapplicable (N/A). Piping Analysis 'c s
- c. >
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'd, See TES Calculation 5314 - Small Bore Piping.
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- d. ' Mod! fication ' Prickage 3
[ 5. N/A , -,
- 2. N/A - i , ,
- 3. N/A-
- 4. N/A 'i ,;
4
- e. Noncor.formance Reports 3 '
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Penetration X-216
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a.- Current'As-Built Piping Isometric With piping analysis package.
. b' . Current Support Drawings ,,
See piping analysis package (5319-X223) and pipe support analysis packages (5319C -. support at Node 110 and 5319C - support at Node 150).
- c. Piping Analysis-See TES Calculation 5319-X216.
'd. Modification Package
- 1. N/A ,
. 2. N/A
- 3. N/A
- 4., N/A
- e. Nonconformance Reports 5
N/A . , id a SS30R/18.101 l
t
.I I
l Penetration X-223 l"'t a. Current'As-Euilt Pipine Isometric (_/ With piping analysis package (5319-X223), also partial isometric on 5920-6562, Sheet 2 of 2, Revision'0.
- b. CurrentSupportiprawings
- 5920-6561, Revision 0 5920-6562, Sheet 1 of 2, Revision 0 Also see piping analysis package (5319-X223) and pipe support analysis packages.53190 - support at Node 42, 5319C - support at Node 57, and.
5319CL- support at Node 75. I
- c. Piping Analysis See TES Calculation 5319-X223.
- d. Modification Package
- 1. See EDCR'83-23.
- 2. See pipe support analysis packages listed above for welded attachment stress calculations.
, 3. See EDCR packages for construction drawings.
( s
- 4. No QC documentation, no piping modifications. ,
~ ' ~
- e. Nonconformance Reports No NCRs on piping for USI A-7 effort.
e ( 5830R/18.101
t 1 l 16.0. TAP SUPPORT ANALYSIS INFORMATION r' Issue N-
' The following information should be available at the beginning of the /
inspection for each support selected.
- a. Current as-built support drawings j
- b. Piping support stress analysis a
- c. Complete modification package (including any additional stress l" calculations, construction drawings, QC documentation, acceptance test data, etc.
- d. Any appl.icable nonconformance reports and their dispositions
Response
See attached sheets.
* ^&
9 0 e Q e W ( 5830R/18.101
E g.,.,. 1
, Problem No. l'(AC/1) ll .-
1 Current As-Built Support Drawings
- , . a. - :
Support ID -Drawing No. ACSP-HD22A 5920-6506,. Sheet;1 , ACSP-H22 / 59i0-9600, Sheets 1-3
~ 5920--9603, Sheets 1-5.
I , ACSP-H27
'ACSP-HD31EL . N/A Support Removed
'ACSP-H199' ' 5.920-9611,. Sheets 1-4 ACSP-HD203E 5920-6502, Sheet 1 b.- Piping' Support Stress Analysis ,
~
- 1 2 See Cygna' calculations on Microfilm Tape No. 434 (hard copies attached).
- c. Modification Package 1.-'See EDCR 82-35 and 83-23.
- 2. .See Cygna calculations on Tape No. 434..
.'3. 'See EDCR packages for construction' drawings.
' 4. See Tape No. 2541. (Blip 1143) for_ EDCR 82-35 QC. records. See Tape ~
No. 2543'(Blip'1) for EDCR.83-23 QC records.
- d. Nonconformance Reports
~
- No NCRs were written against the above listed pipe supports.
5830R/18.101 i
's I
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g ,- . w J' " a Problem No. 10-(CS/2-RHR/7)- (- ,
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ICurrent s-Built' Support Drawings a.t
. Support:ID . Drawing No.
CS-HD42 5929-6474,; Sheet 1-CS-H851 N/A Support Removed y < RHR-H98 5920-9644, Sheets 2-7' RHR-HD241- 15920-9651 Sheets 1-9 - RER-HD186A 5920-6465, Sheets 1-2' RHR-H188 5920-9645, Sheets 1-3
- b. Piping Support Stress Analysis-See: Cygna calculations on Microfilm Tape Nos. 435 and 436 (hard copies
. attached). .
l c..
- Modification Package
~
! 1. . See EDCRsl82-35 and 83-23.
c ,
- 2. See Cygna calculations on Tape Nos. 435 and 436.
- 3. See EDCR' package's-for construction drawings.
I,jq,. ( /. 4...'See Tape No. 25'41:(Blip 1143) f'or EDCR'82-35 QC records. See Tape
-No. 2543 (Blip 1) for EDCR 83-23 QC records.
. . . . e.
d.. Nonconformance Reports , . No NCRs'were written against.the above listed pipe supports.
~:.
4 e 9 e e 4 5830R/16.101
Problem No. 64 (HPCI/6) f-~s
\/ a. Current As-Built Support Drawings
. Support ID Drawing No.
HPCI-HD103 5920-6423, Sheet 1-HPCI-H108 5920-6431, Sheets 1-2 HPCI-H107 5920-6427, Sheets 1 HPCI-HD109A 5920-6721, Sheet 1 HPCI-HD107B 5920-6722, Sheets 1-2
- b. Piping Support Stress Analysis See Cygna calculations on Microfilm Tape No. 437 (hard. copies attached).
'c. Modification Package
- 1. See EDCRs 82-35 and 83-23.
- 2. See Cygna calculations on Tape No. 437.
- 3. See EDCR packages for construction drawings.
- 4. See Tape No. 2541 (Blip 1143) for EDCR 82-35 QC records. See Tape No. 2543 (Blip 1) for EDCR 83-23 QC records.
g .- i
- d. Nonconformance Reports No NCRs were written,against the above listed pipe supports.
1 V(D 5830R/18.101
; )
i l Problem No. 100 (RCIC/1)
'- ' a. Current As-Built Support Drawings Drawing No.
Sy port ID RCIC-H65 5920-9746, Sheets 3-4 ' RCIC-HD64A 5920-6436, Sheet 1 RCIC-HD63A 5920-6439, Sheet 1 RCIC-H63 5920-6440, Sheets 1-2 RCIC-H62 5920-6437, Sheets 1-2
- b. Piping Support Stress Analysis ,
See Cygna calculations on Microfilm Tape No. 438. (hwv4 'cortes 2A(acwed.) c.. Modification Package ..
- 1. See EDCRs 82-35 and 83-23.
- 2. See Cygna calculations on Tape No. 438.
- 3. See EDCR packages for construction drawings.
See Tape No. 2541 (Blip 1143) for EDCR 82-35 QC records. See Tape 4. No. 2543 (Blip 1) for EDCR 83-23 QC records.
/~
k_) ~ d. Nonconformance Reports No NCRs were written against the above listed pipe suppor,ts.
~
+se 7
k SS30R/18.101
1 Sma11' Bore Piping Penetration X-206A .4 The liquid level indication at Penetration X-206A does not have any supports. 1
)
i 9 t e G I f I 5830R/18.101 __ _- - - - - _ -. - 1
r., Small Bore Piping Penetration X-206E f% ' Shutoff valve,' instrument tubing at Penetration X-206E does not have any supports. i' e b 6 4 e e a e
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h-l Small Bore Piping Penetration X216 [T 1
\
- a. Current As-Built Support Drawing Support ID Drawing No.
53190 - Node 110 N/A See Support Calculation 53190 - Node 110
'N/A See Support Calculation 53190 - Node 150 (
5319C - Node 150 53190 - Node 200 N/A See Piping Calculation 5319-X216
.53190 - Node 220 N/A See Piping Calculation 5319-X216 53190 - Node 240 N/A See Piping Calculation 5319-X216 53190 - Node 260 N/A See Piping Calculation 5319-X216 5319C - Node 280 N/A See Piping Calculation 5319-X216 5319C - Node 340 N/A See Piping Calculation 5319-X216 ;
5319C - Node 360 . N/A See Piping Calculation 5319-X216 ; 1
- b. Piping Support Stress Analysis )
See Teledyne Piping Stress Calculation 5319-X216 and Teledyne Support Calculations 5319C - Node 110 and 53190 - Node 150.
- c. Modification Package N/A - No pipe support modifications required.
i
- d. Nonconformance Reports
(\ L ~ No NCRs written.
~ ~
i rs 5830R/18.101 E_
i Small Bore Piping Penetration X223 n a.- Current As-Built Support Drawing l Support ID Drawing No. 5319C'- Node 34 5920-6561, Sheet 1 5319C - Node 42 N/A See Photos in Piping Calculation 5319-X223 53190 - Node 50 N/A See Photos in Piping Calculation 5319-X223 53190 - Node 51 .N/A See Photos in Piping Calculation 5319-X223 53190 - Node 52 N/A See Photos in Piping Calculation 5319-X223 5319C - Node 57 N/A See Photos in Piping Calculation 5319-X223 j 53190 - Node 62 5920-6562, Sheets 1-2
- 5319C - Node 75 See Photos in Piping Calculation 5319-X223
- b. Piping Sunport Stress Analysis See Teledyne Piping Stress Calculation 5319-X223 and Teledyne Support Calculations 5319C - Node 42, 53190 - Node 57, 5319C - Node 75, 53190 -
RCIC-HD200 Node 34..and 53190 - RCIC-HD201 Node 62.
- c. Modification Package
- 1. See EDCR 83-23. l
- 2. See Teledyne Calculations 5319C RCIC-HD200 Node 34 and 53190 RCIC-HD201 Node 62.
/}
- 3. See EDCR package for construction drawings. .
- 4. See Tape No. 2543' (Blip 1) for EDCR 83-23 QA records.
l
- d. Nonconformance Reoorts No NCRs were written against small bore pipe supports.
I 1 l l V< SS30R/18.101 l \ l \ l u-__ -----_-_---.---- - -- j
17,0' 'IEB 79-02 AND IEB 79-14 l I'\a) - Issue Describe how the TAP analysis'and modifications affected or were related to the IEB 79-02 and 79-14 work and the resulting modifications. i Response ,, i 79-02 ; i o All Phillips redhead bolts replaced by F.ilti " kwik-bolts" bn seismic supports. o Evaluations were performed to assure a minimum factor of safety of 2 existed at the plant.
)
o After completion of EDCRs 82-35 and 83-23 all TAP supports vere in compliance.with IEB 79-02. l 79-14 0 o All computer analyzed seismic Class I piping was "as-built" and verified. j o NCRs were prepared and closed out. J j
,/ ~'( o TAP incorporates all data obtained from IEB 79-02 and IEB 79-14 '
.\_)
NOTE: An NRC audit of IEB 79-02 and IEB 79-14 was conducted April 9, 1985 i through Ag,ril 12, 1985. The bulletins were addressed for TAP in the ) same manner as was described during the audit. e o i l l [
,b !
5830R/18.101 > I
- l. 18.0 SECOND SET OF VACUUM BREAKERS Issue .l
.(n)
The structural PUAR states (Page 7) that "analys'es are ongoing to optimize the location of a second set of vacuum breakers on the SRV lines." Have these modifications been made? If so, provide pertinent details. 'If not, describe the current status., j
Response
I
' Yes, modifications have been made. Two ten-inch vacuum breakers were
.added to each SRV'line. Refer to PU/a TR-5319-2 for pertinent details.
- i m
') 5830R/18.101 ;
i _ _ _ _ _ _ _ . - - _ . . _ l
19.0 LICENSING CORRESPONDENCE Issue The licensing correspondence log provided by the licensee appears to be incomplete. Correspondence was found that was not included in this list. Clarify how documentation which is to be submitted to the NRC and subsequently docketed is approved, tracked, filed, and maintained for future reference and retrieval.
Response
The licensing correspondence log associated with this subject inspection topic was express mailed to Region I and EG&G offices, informally, in response to Mr. Varela's verbal request. Mr. Varela was informed at that time that the log was incomplete and represented a listing of related correspondence located in the Vermont Yankee licensing and project office subject files. Also, he was informed that the list was developed on a best-efi~ ort rush basis so as to be as responsive as possible to his verbal request within the time constraints he imposed. Additionally, copies of certain specified documents were also express mailed at that time in accordance with his verbal request. Further, Mr. Varela was informed that the correspondence list would be expanded to address the inspection scope, once documented, and made available prior to the actual inspection once the inspection date was finalized. Documents submitted by the Vermont Yankee Nuclear Power Corporation to the United States Regulatory Commission which are subsequent docketed in the O redtte noc"=e=t a re ervroved r=1 te e"d=itt 1 dY the ver= "t re=*ee Nuclear Power Corporation Vice President and Manager of Operations, or his designee in the VYNPC Corporate office located in Brattleboro, Vermont. Copies of correspondence subpitted to the NRC and subsequently documented in the Public Document Room are filed and maintained for future reference and retrieval at both the VYNPC Corporate office and at the Yankee Atomic Electric Company offices in Framingham, Massachusetts. The Vermont Yankee licensing engineer, located at the YAEC offices in Framingham, Massachusetts, logs and assigns an "FVY" prefix and chronological number to all VYNPC correspondence that is submitted to NRC for subsequent docketing in accordance with Vermont Yankee Project Procedure No. 2, " Fitting and Distribution of Documents," Section 2.3. Prior to the Framingham, Massachusetts office location, YAEC's offices were located in Westboro, Massachusetts and correspondence submitted by VYNPC to the NRC and subsequently docketed was assigned'an "WVY" prefix and chronological number. A chronological file of all-VYNPC correspondence submitted to NRC and subsequently docketed is maintained in chronological and numerical order by the Vermont Yankee Project secretary with the "FVY" Log. Additionally, copies of VYNPC correspondence to the NRC which is subsequently docketed are also filed and maintained in a chronological correspondence file by the Vermont Yankee licensing engineer. Further, in certain instances, copies of correspondence by VYNPC to NRC which are subsequently docketed are additionally filed by Vermont Yankee project licensing and engineering Staff O 5630R/18.101
I F-in personal subject files. safeguards information submitted by VYNPC to NRC which is subsequently docketed is filed and maintained in accordance with the Vermont Yankee Security Plan and Safeguards Procedures. Q ;
. All VYNPC correspondence submitted to NRC which is subsequently docketed, is forwarded by the Vermont Yankee licensing engineer to the Yankee Atomic Electric Company Document Control Center (DCC) for record keeping purposes. For each item of correspondence submitted by.VYNPC to NRC which is !
subsequently docketed, an IMS Doc'ument Input Form - Licensing is completed and forwarded to DCC. In accordance with the YAEC Document Control Center Manual, Procedure 0631p, Section 8.0, "Special Considerations," Subsection 8.1, !
" Licensing Records," the DCC microfilms each Vermont Yankee NRC document submitted to h70 which is subsequently docketed and inputs pertinent !
classification information for each document into the YAEC computer data Sase. Copies of the microfilm rolls are maintained and can be accessed by i reader / prints at DCC and the Vermont Yankee project offices. The original { microfilm is stored in a special vault in New York state. The computerized q information is retrievable by a number of access search methods off the data . 1 base by computer terminals throughout the YAEC office location on Fram.ingham. l
)
We trust that the above information is responsive to your request. l However, should you require more specific information, or need information j regarding the correspondence documentation process at the VYNPC Corporate ( office and/or plant site, please contact this office. Copies of pertinent documentation and procedures associated with YAEC"s I.icensing Correspondence Control System will be available at the YAEC office O at the time of your inspection should you desire. Further, copies of all
\ licensing correspondence associated with this inspection subject will be made available during your inspection upon request. Additionally, an updated I correspondence log of licensing correspondence related to this inspection area I will be made available prior to the inspection period upon request.
l SS30R/18.101
i 20.0 TAP ANALYSIS MODELING
,~, 1
_ ..e
) Issue l Confirm whether all lines listed for the individual piping analysis _l problems are included in one analysis model. l J
l Response _ , l
,{
Each of the piping problems were modeled separately. I 4 1 i
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5830R/18.101 i
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- 21.0 SUPPORTS TO BE REMOVED l 1
1
- s.
f) Issue -
'I k'ere piping supports to be removed included in EDCB documentation or was )
another method used to document the support removal activity? Response , The supports to be removed were listed in EDCRs 82-35 and 83-23. 9 4 I l l l h' 5830R/18.101 . l _ _ ._ __ __ m ___ __ _--__ _ -_ __m__ _ _ _ . _ _ - . . _ _ _ _ _ . _ _-____ __
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3 - 22.0.1: ACCESSIBILITY FOR'$1 ELD'WALKDOWN' l g ' Vf .? L Issue
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=Co'nfirm the" accessibility of the selected piping systems'and supports fi for field walkdown. .f !y . Response ,
Piping / Pipe Support Accessibility-' $ , y[ Problem No. l(AC/1) ,
'All piping"and pipe supports are accessible during' plant operation.
' Problem No. 10 (CS/2 RHR/7) .
-All-piping and pipe, supports'are accessible except as noted'., Support.
RHR-HD241 and.approximately 22 feet.of 24 inches RHR-29 is. located-in-the:drywell access enclosure. Problem No. 64 (HPCI/6)'
.5 All" piping.and pipe supports are accessible ~during plant operation.
Problem No.-100 (RCIC/1)' 9 ' lAll. piping'and' pipe' supports are accessible during'pland operation. , V . . - . '. . ' ' l- ,p - Small Bore' ' .
' . ' ~ "
All' piping and pipe supports are accessible.during plant operatiEn. 1-4
- .dl \
y 1 l.. l 1 TO SS30R/18.101 l: l _ - _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ -}}