IR 05000420/1988020
| ML20154R348 | |
| Person / Time | |
|---|---|
| Site: | Vogtle, 05000420  |
| Issue date: | 05/24/1988 |
| From: | Blake J, Kleinsorge W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20154R336 | List: |
| References | |
| 50-424-88-18, 50-425-88-20, NUDOCS 8806070279 | |
| Download: ML20154R348 (15) | |
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AR Cfo UNITED STATES _^
NUCLEAR REGULATORY COMM SSION
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R EGION 11
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Ij 101 MARIETTA STREET.N.W.
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Report Nos.: 50-424/88-18 and 50-425/88-20 Licensee;- Georgie.Pcw r Cr,npanl/
'P. O. Box 4545
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' Atlanta, GA 30?02
Docket Nos.:
50-424 and 50-425 License Nos.: NPF-61 and CPPR-109
% cilit'y Name:
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Vogtle 1 and 2
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8-22, 1988 and Roy 2-5, 1988 t
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Inspection CafytuctflbM
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SUMMARY
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Scope:
T!Hs youtine unt.nnounced inspection was in the ared of licensee
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', actions on prd9iout:enthrdement tatters (92701B) (927028), heating, ventilating
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j and air condtion%g' (FiW) ',ystem-(O'it 2), and readiness reviw Module 18A.
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'"Her, ting hntilatir..n,' aiW Air. to;idi tioi,"
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'Results : 'One Vio'eatic'.. vn Nejtified. "Failure To Ir. stall HVAC Systems In
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Accordance, ',ii th The FSAKa
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REPORT DETAILS 1.
Persons Contacted Licensee Employees
- A. B. Gallant, Project Compliance Coordinator
- E. D. Groover, Quality Assurance -(QA) Site Manager Construction
- I. D. Innes,-Civil Engineer
- R. W. McManuw, Readiness Review
- R. H. Pinson, Vice President
- P. D. Rice, Vice President / Project Director
- P. R. Thomas, Readiness Review Other licensee employees contacted included construction craftsmen, engineers, technicians, and office personnel.
Other Organization
- J. P. Hawlew, Bechtel Power Company (BPC) Project Engineer
- F. C. Ling, BPC - Engineering Group Leader NRC Resident Inspector
- R. Schepens, Senior Resident Inspection (SRI)
- Attended exit intervier I
2.
Exit Interview The inspection scope and findings were sumarized on May 5,1988, with those persons indicated in Paragraph 1 above.
The inspector described the areas inspected and discussed in detail the inspection findings.
No dissenting coments were received from the licensee.
The following new item (s) were identified during this inspection:
(0 pen)
Violation -
50-424/88-18-01 and 50-525/88-20-01:
"Failure To Install HVAC Systems In Accordance With The FSAR" -
Paragraph 3b (0 pen)
Inspection Followup Item -
50-424/88-20 n2:
"Unavailable HVAC Documents" - Faragraph Se l
The licensee did identify some material as proprietary during this
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3.
Licensee Action on Previous Enforcement Matters (92701B) (92702B)
a.
(Closed) Unresolved Item 50-425/88-03-01:
"Apparent Failure To Install and Inspect HVAC Duct Supports In Accordance With Drawings" This item identified the following ' condition:
completed, inspected
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and accepted HVAC Nuclear Safety-Related, Seismic Class 1, Duct Support No. 2-132-88 is depicted on Field Change Request (FCR) No.
FCRB-5367F and BPC Drawing No. ACD67WO41 Revision 1.
Drawing AXD672041, Details for Type 301, specifies dimension"D" (the distance between the center line of the duct section and a 5x5x3/8-inch square tube) to be 1-foot 0 inches maximum (12-inches maximum).
In point of fact the actual
"D" dimension is 14 1/2-inches.
Subsequent to the identification of this discrepant conditions by the NRC inspector the licensee documented the discrepancy in Deviation Report (DR) No.
PK-4184.
This condition indicates that the installing craftsman failed to install the duct in accordance with the applicable drawing and that the Quality Control (QC) inspector accepting the discrepant nuclear safety-related, Seismic Category 1 HVAC duct support failed to inspect the duct support in accordance with the applicable drawing.
Fa: lure to install and inspect the duct support in accordance with applicable drawing brings into sharp focus the following:
the craftsman exceeded the 12-inch maximum specified by the drawing; the craftsman failed to get an engineering evaluation of the discrepant condition; the craftsman offered for inspection a duct support that
deviated from the drawing; the QC inspector failed to identify fact that the "D" dimension exceeded the drawing maximum of 12-inches; the QC inspector accepted the discrepant condition; the QC inspector signed the inspector record indicating that the duct support conformed to the drawing when in point of fact it did not.
By installing and accepting this discrepant nuclear safety-related Seismic Category 1 HVAC duct support, the installing craftsman and the accepting QC inspector usurped the prerogative, responsibility, and authority of the designer to evaluate and accept conditions outside of design envelope as defined by drawings.
The above is an example of failure to follow procedure for activities affecting quality.
This matter will be closed as an unresolved item and became an example of W olation 50-424/88-18-01 and 50-425/88-20-01, discussed further in Peragraph 3.b.
b.
(Closed) Unresolved Item 50-425/88-03-02:
"Air Filter Housing
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Seismic Analysis" This item identified the following.
The 2-1561-N7-001 Engineered i
Safety Feature (ESF) air / filter housing assemblies is attached to the
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datum foundation by 3-1/2x3-1/2x1/4x4-inch angle clips. These angle clips share a horizontal interface with the foundation, and-a vertical interface with the air / filter housing.
The interfaces are
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secured by bolting.
The NRC inspector noted that several of these angle clips had only line contact at the top and bottom edge of the vertical interface the result of interference from a fillet weld on the air filter housing.
The Vogtle plant (VEGP) Final Safety Analysis-Report (FSAR) Section 6.5.1.3E states in part "the ESF filter systems are designed to Seismic Category 1 requirements. The NRC -inspector discussed the above with the licensee, pointing out, that those connections with only double line contact could not be considered as friction connection.
In view of the above, the NRC inspector questioned whether the lack of friction connections on the supports of a Seismic Category 1 component, abrogated the seismic analysis and qualification of the equipment, and thereby deviated from a comitment to the commission (FSAR 6.5.1.3.E).
The licensee contacted the manufacturer of the air filter housing, American Air Filer (AAF) relaying the NRC inspectors concern.
AAF indicated, to the licensee, that as long as the bolts connecting the clips to the filter housing were tight the seismic analysis and qualification was valid. AAF stated that they would send supporting documentation.
In addition to the above, but not documented in NRC Report Nos.
50-424/88-04, 425/88-03, The inspector noted that there were no washers installed between the bolt head and the angle clip's vertical surface, slotted hole (13/16 x 11 - inch).
As a result of this unresolved item, the licensee performed a reinspection of this air filter housing assembly's mounting bolts, as well as the mounting bolts for the remaining five Unit Two and eight Unit One other ESF air filter housing assemblies.
This inspection revealed that all the Unit One air filter housing assemblies were mounted with 3/4-10 snug tight (not torqued) unmarked (assumed Type A-307 which has a tensile strength 50 to 70 Kips / Square Inch (KSI)
bolts.
The inspection revealed that all but one bolt used to mount the unit two air filter units were 3/4-10 snug tight (not torqued)
Type A-325, or A-490 bolts (A-325 has tensile strength of 105 KSI and A-490 has a tensile strength of 150 KSI).
The remaining bolt was a snug tight (not torqued) 5/8-11.
The applicable drawing available to the craftsman who installed the mounting bolts and the QC inspection who accepted the installation of the mounting bolts was IX4AJ07-273-5 for unit one and 2X4AJ07-325-7 for unit two.
Section "B-B" from both drawings (Reproducerd as Attachment I herein) specifies "3/4-10 hardware provided by AAF."
The applicable procedure available to the craftsmen and inspectors for the installation of Type A 307 bolting, P/L-F JP-14.2, "Process Control Program" Exhibit 16 specifies snug tight with the warning
"Do Not Over Torque".
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The Applicable Procedures available to the Unit Two Craftsmen and QC inspectors were:
P/K-F JP-513 "Installation and Inspection of High Strength Bolts" (Applicable To All Unit Two assemblies) and P/K-F MIP/ Equip (ment Installation Special Instruction Sheet No 2-1561-N7-002 Housing Applicable To the 2-1561-N7-002 assembly only),
JP-513 Paragraph 5.4 requires that bolted contact surfaces shall have all burrs removed and shall be free of dirt, oil, loose scale, pits or other defects that would prevent solid seating or sound bearing of component parts.
JP-513 Paragraph 6.2.2.d.1 requires that washers shall be installed under the bolt head and nut when the hole enlargement exceeds 1/8".
P/K-F MPI/Equipnient Installation special Instruction 2-1561-N7-002, Page 2 of 39, Item 7 specifies the use of Type A-325 equivalent or better 3/4-inch diameter bolting hardware to a snug tight condition.
In view of the above the installing craftsmen and the accepting QC inspectors followed the appropriate drawing and procedure require-ments for Unit One and Unit Two with the following exceptions:
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The bolted contact surfaces were not free of defects (the interfering fillet welds) which prevented solid seating and sound bearing of the component parts.
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Washers were not installed under the bolt heads over the slotted holes.
3.
A 5/8-inch diameter bolt was used when a 3/4-inch diameter bolt was required.
The support documentation submitted by AAF in response to the GPC question related to this unresolved item stated in part:
"To meet the seismic qualification, the angle clips should be bolted
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to the base channels with Type A-449 high strength bolts, or equivalent, pretensioned to meet the friction connection require-ment."
(Note:
Type A-449 bolts are equal to Type A-325 with a 105-KSI specified tensile strength)
I The AAF letter indicates that neither the Unit One or Two air filter housing assemblies were installed in accordance with the FSAR, in that the Unit One assemblies were installed with under-strength bolts i
that were not pretensioned (torqued) and the Unit Two assemblies were installed with appropriate strength bolts that were not pretensioned (torqued).
The above clearly indicates the procedures and drawings were not of a type appropriate to the circumstance to assure that proper bolting
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materials would be correctly installed to comply with the Conmitments j
of the FSAR.
In addition, the installing craftsmen failed, to assure
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that bolted contact surfaces were free of defects that would prevent those surfaces to seat solidly and have sound bearing, and to install washers under bolt heads over slotted holes, and that bolts were of a proper diameter.
The accepting QC inspectors accepted the same discrepant condition and the QC inspectors signed the inspection record attesting to the fact that the ESF Scismic Category 1 air filter housing assemblies were installed in accordance with procedures and drawings when in point of fact they were not.
The above condition has existed in some part since April 24, 1984.
The licensee has had at least 14 opportunities to discover portions of this violation, once for each air filter housing assembly installation and inspection.
The above procedure inadequacies and, the examples of failure to follow procedures combined with the example of failure to follow procedure discussed in Paragraph 3a, show what activities affecting quality were not prescribed by documented drawings and procedures of a type appropriate to the circumstances and that those activities were not accomplished in accordance with those drawings and procedures.
This is a violation of Title Ten, Code of Federal Regulations, Part 50 (10 CFR 50) Appendix B, Criterion V.
This matter will be closed as an unresolved item and opened as violation 50-424/88-18-01 and 50-425/88-20-01:
"Failure to Install HVAC Systems In Accordance With The FSAR."
5.
Heating Ventilating and Air Conditioning (HVAC) Systems (50100) (Unit 2)
The i.1spector reviewed records tJ detennine: Whether the installation of safety-related HVAC system in compliance with Nuclear Regulatory Commission (NRC) requirements, licensee commitments, and applicable codes; whether the licensee was adequately preparing, reviewing, and maintaining a system of quality records; whether the records reflect work accomplished consistent with NRC requirements and Safety Analysis Report (SAR)
commitments; and whether the records indicate any potentially generic problems, management control inadequacies, or other weaknesses that could have safety significance, a.
The inspector reviewed selected documentation for the below listed components to verify seismic qualification per IEEE-344-1975,
"Seismic Qualification of Class 1E Equipment for Nuclear Power Generating Station", or other appropriate requirements.
Content Fan with motor for air handling assembly 2 15561-N7-001-000
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Cooling coils for air handling assembly 21555-A7-003
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The inspector reviewed selected documentation for the below listed mechanical components to verify conformance with the applicable portions of Regulatory Guide 1.52
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Components
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HEPA Filters Ser. No. 41344297-316 Neopreme Duct Gasket - ASTM-D-SCE-43,1 Silicone Ruber Sealant - 732 RTV c.
The inspector reviewed the below list Nonconformance (NCR) Reports to determine whether: The records are being properly identified, stored, and can be retrieved in a reasonable time; the records are legible, complete, and indicate that reports are promptly reviewed by qualified personnel for evaluation and disposition of the immediate problem as well as for generic implications and trending; the records _
adequately document. current status of nonconformances or deviation and corrective action; and resolution of nonconformances demonstrates good engineering practice.
NCR's Examined i
SQ-354 PK-3912 PK-2805 PK-3463 PK-3184 PK '009 PK-4152 PK-2632 PK-3700 PK-4133 d.
The inspector reviewed the relevant portions of the below listed license audit reports concerning the installation of safety-related supports and HVAC systems to determine whether:
The required audits have been performed in accordance with schedule and functional areas in established audit plans; audit findings have been reported in sufficient detail to permit a meaningful assessment by those responsible for corrective action, final disposition, and trending; and the licensee / contractor have taken proper and timely followup action on those matters in need of correction.
Audit Reports Examined CP-22-87/38 CP-22-87/03 CP-20/CP-22-86/50 CP-22-86/29 With regard to the inspection above the licensee was unable to e.
provide the documentation described in ANSI /ASFE N509-1980, "Nuclear Power Plant Air Cleaning Units and Components", Paragraph 5.4.2. for
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the 2-1561-N7-001-000, Moisture Separator Unit.
~The licensee indicated that they would located the documentation and make it available to the inspector.
Pending NRC review of this documen-
-+ation, this matter will be identified as Inspector Followup Item
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50-425/88-20-02: "Unavailable HVAC Documents."
Within the areas examined no devia+, ions or violations were identi-fied.
6.
Readiness Review, Module 18A "Heating Ventilation, and Air Conditioning"
Readiness Review Module 18A was submitted to the NRC on February 12, 1988, with an effective date of July 15, 1987.
The module was reviewed for program description, implementation, technical commitment adequacy, and program assessment.
The ~ specific commitments evaluated for adequacy are listed in Attachment 2.
Unit 2 HVAC activities were examined by the NRC and discussed in NRC Reports indicated below.
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Report No 50-4:4/87-11 and 50-425/87-07 50-424/88-04 and 50-425/88-03 50-424/88-18 and 50-425/88-20 Within the area examined no violations or deviations were identified.
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Acronyms and initialisums American Air Filter AAF
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Bechtel Power Company BPC
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Deviation Report DR
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Engineered Safety Features ESF
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FCR
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Field Change Request Final Safety Analysis Report FSAR
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Heating Ventilating and Air Conditioning HVAC
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FM0
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Maintenar.ce Work Order NRC
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Nuclear Regulatory Commission P&ID
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Piping and Instrumentation Diagram P/ K-F
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Pullman /Kenith - Fortson QA
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Quality Assurance QC
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Quality Control RII
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Region II Senior Resident Inspector SRI
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Title Ten, Code of Federal Regulation Part 50 Attachments:
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Attachment 1
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Attachm2nt 2,
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Pac No.
05/05/88 PLANT VOGTLE UNIT 2 READINESS REVIW PROGRAM COP 9fl1NENT MATRIX - MODULE 18A
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REF. COP 9fl1 MENT COPNI1NENT COPMI*INENT DOCINENT/
FSAR REMARKS NLMBER SOUNCE SECTION SUBJECT ITATURE MODULE DESIGN CONST AMEN
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X 1855.00 FSAR 1. 9. 31. 2 CONTHOL OF FERRITE HG 1.31 18A X
X CONTENT IN STAINLESS X
STEEL WELD METAL X
X X 1549.00 FSAR I. 9. 52. 2 DESIGN, TEST &
CONFOlptS TO ANSI 18A X
X
X MAINT. CRITERIA FOR N509-1976 OR 1980 X
POST-ACC. ESF DEPENDING ON DATE OF X
A1NOSPHENE CLEAN-UP P.O., OR CONFOINS M X
SYSTEM AIR ANSI N509-1980 WHEN FILTRATION &
SPECIFICALL7 CALLED ADSORPTION UNITS OUT IN SPEC X 1550.00 FSAR 1. 9. 52. 2 DESIGN, TEST &
COdF059ts TO ANSI 18A X
X
X MAINT. CRITERIA FUR N510-1975 OR 1980 X
POST-ACC. ESF EEPENDING ON DATE OF X
A1N0 SPHERE CLEAN-UP P.O., OR CONIDINS M X
SYSTEM AIR ANSI M510-1980 WHEN FILTRATION &
SPECIFICALLY CALLED ADSORPTION UNITS OUT IN SPEC X 715.00 FSAR 1. 9. 92 COMBINING M00AL DG 1.92, REV 1, 2/76 IBA X
0 SEE FSAR 3.7.B.
X RESPONSES & SPATIAL 3.7.N, 3.7.N.2.7 X
COMPONENTS IN X
SEISMIC RESPONSE X
ANALYSIS X 4973.00 FSAR 1. 9. St. 2. 9 VISUAL WELDING WE' DING VISUAL 18A X
X ACCEPTANCE CRITERIA INSPECTION X
ACCEPTANCE CRITERIA X
IN ACCORDANCE WITH X
AWS DI.1-75 FOR INSPECTIONS PERFOfMED PRIOR TO 12/02/85, AND NCIG-01, REY. 2 IVR INSPECTIONS PERFORMED AFTER 12/02/85.
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Attachment ~2 6 j2.
i Page No.
05/05/88 PLANT VOGTLE UNIT 2 READINESS REVIW PROGRAM COPMI1 MENT MATRIX - MODULE IBA
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REF. COPM11 MENT COPMI1NENT COPMI1 MENT DOCINFET/
FSAR REMARKS NIMBER SOURCE SECTION SUSJECT FEATURE MODULE DESIGN CONST AMEN
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X 2027.00 FSAR 3. 1.
CONFOHMANCE WITH NRC 10CFR50, APP. A, GDC 18A X
X GDC, PRIMARY SG X
CONTAIPMENT X
ISOLATION X
X 1012.00 FSAR 3. 7.B. 3. 1. 3 SEISMIC SUBSYSTEM MODAL RESPONSE 18A X
X ANALYSIS OF CAT. I SPECTRtM OR X
SUBSYSTEMS AND EQUIVALENT STATIC X
COMPONENTS IDAD METHOD X
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X 1014.00 FSAR 3. 7.B. 3. 5 SEISMIC SUBSYSTEM SEISMIC ACCELERATION 18A X
X ANALYSIS, USE OF VALUES... KE PEAK X
EQUIVALENT STATIC ACCELERATION VALUES X
IDAD METHOD OF MULTIPLIED BY A X
ANALYSIS FAC1DR OF 1.5 UNLESS A IDWER FACTOR IS JUSTIFIED X 4G88.00 FSAR 3. 7.B. 3. G SEISMIC SUBSYSTEM COPFONENT EARTHQUAKE IBA X
X ANALYSES - THREE EFFECTS COPSINED BY X
COMfVMENTS OF SRSS METHOD (FOR X
EARTHOUAKE MOTION.
QUAL. BY ANALYSIS).
x X 5025.00 FSAR 3. 8.
4. 5 WELDING OF WELDING OF 18A X
X 25 ADDED BY FSAR AMEND.
X STRUCTURAL STEEL STRUCTURAL STEEL,
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X MISC. STEEL, RACEWAY X
SUPPORTS, & HVAC X
DUCT SUPPORTS IS PERFOft1ED IN ACCORD.
WITH AWS DI.1-1975 OR LATER X 5117.00 FSAR G. 2.
4. 3.C CONTAIPMENT PREACCESS MINI PURGE 18A X
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X ISOLATION SYSTEM, LINE ISOLATION X
DESIGN EVALUATION VALVES SHUT IN LESS X
THAN 5 SEC.
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Attachment 2 C
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05/05/88 PLANT VOGTLE IINIT 2 READINESS REVIW PHOGHAM COPNI1NENT MATRIX - MODULE 18A
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REF. COPNI1NENT COPHI1NENT COPNI1NENT DOCIMENT/
FSAR REMARKS NIMBER SOURCE SECTION SUBJECT FEATURE MODULE DESIGN CONST AMEN
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X 5039.00 FSAR 6. 2.
5. 2. 2 CONTAlletENT H/2 EXHAUST FILTERS AND 18A
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22 ADDED BY FSAR X
PUHGE SYSTEM EXHAUST DUCT TO AMENDMENT 22 X
PLANT VENT ARE
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X DESIGNED AS SIESMI(.
X CAT. I X 5055.00 FSAR 6. 4.
2. 2. 2.J HABITABILITY SYSTEMS WO SETS OF DOORS IBA X
X WITH VESTIBULE ACT X
AS AN AIR LOCK AT X
CONTROL ROOM X
EXTRANCES X 5112.00 FSAR 6. 4.
2. 2. 2.J HABITABILITY SYSTEMS DOORS TO RECORD 18A X
X STOHAGE AREAS ARE X
EQUIPPED WITH
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X SELF-CIDSING DEVICES X
X 5113.00 FSAR 6. 4.
2. 2. 2.J HABITABILITY SYSTEMS ACCESS TO RECORD 18A X
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X S1DRAGE AREA THROUGH X
AN AIRIDCK OR 1WO X
DOORS IN SERIES
X
a X 507.'.00 FSAR 6. 4.
2. 3 HABITABILITY SYSTEMS CONVENTIONAL BLDGS, 18A X
X
- VENTILATION FOR REACTOR X
LEAK-TIGHTNESS CONTAll#ENT
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PUBLISHED BY ATOMICS X
INT'L, CAT.
NAA-SR-10100, 6-15-65
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X 5114.00 FSAR 6. 4.
2. 4.E HABITABILITY CONTHOL HOOM 18A X
X SYSTEMS, INTERACTION D00HWAYS WITH 1MO X
WITH OTHER ZONES SETS OF DOORS ACTING X
AS AN AIRIDCK i
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PLANT VOGTIE UNIT 2 REAlllNESS REVICJ PI(GRAM COPN11NENT MATRIX - MODULE. IBA
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REF. COPN11NENT COPNI1NENT COPHI1 MENT DOCLNENT/
FSAR REMARKS FEATURE MODULE 11ESIGN CONST AMEN NIMBER SOtIRCE SECTION SU,BJECT
= = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = =
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X 5115.00 FSAR 6. 4.
2. 4.E HABITABILITY DOORS TO RECORD 18A X
SYSTEMS, INTERACTION STORAGE AREAS ARE X
WITH OTHER ZONES EQUIPPED WITH X
SELF-CIDSING DEVICES X
X X 5116.00 FSAR 6. 4.
2. 4.E HADITABILIT7 ACCESS TO RECORD 18A X
SYSTEMS, INTERACTION STORAGE AREA THROUGH X
WIT 11 OTHER ZONES AN AIRIDCK OR '[WO X
DOORS IN SERIES X
X
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X 2123.00 FSAR G. 5.
I. 1.B ESF FILTER SYSTEMS DESIGNED TO MAINTAIN 18A X
DESIGN BASIS-1/4-IN. WG WITH l
X PIPING PENETRATION RESPECT 10 A1MOS.,
X FILTER EXHAUST NECATIVE WITH X
X SYSTEM RESPECT 'IO SURROUNDING AREAS X 2125.00 FSAR 6. 5.
1. 1.C ESF FILTER SYSTEM DESIGNED TO MAINTAIN 18A X
X DESIGN BASIS A SLIGHTLY NEGATIVE X
FHB POST-ACCIDENT PRESSURE IN THE FHB EXIIAUST SYSTEM FOLIDWING A FUEL X
HANDLING ACCIDENT.
X X 1015.00 FSAR 3. 4.
3. 2. 4 AUX. BLDG. DERG.
SMACNA,1975 8. ANSI 18A X
X
VENT. SYSTEM - DUCT M510. SECT. G, 1980 X
X LEAK TESTING X
X X 4066.00 FSAR 9. 4.
5. 2. 1 CONTROL BLDG. SAFETY BATTERY ROOM 18A X
X FEATURE ELEC.
MAINTAINED AT X
EQUIINENT ROOM HVAC SLIGHTLY NEGATIVE PRESSURE X
X X 4070.00 FSAR S. 4.
?.
3. 2 EIIC. PENETRATION UI'ON RECEIPT OF A 18A X
X ROOM FILTRATION AND CONTAlfMENT
.
X EXHAUST SYSTEM ISOLATION SIGNAL THE ELEC. PENETRATION X
ROOM EXHAUST X
FILTRATION UNITS ARE ACTIVATED
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Page No.
OC./05/HH PLANT VOGTLE UNIT 2 NEADINESS REVIW PROGRAM
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COPNI1NENT MATRIX - MODULE 18A
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REF. COPNI1NENT COPNI1NENT COPHI1NENT DOCUMENT /
FSAR REMARKS NIMBEH SOUHCE SECTION SUBJECT FEATURE MODULE DESIGN CONST AMEN
=========================================================================================
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X 4096.00 FSAR 9. 4.
5. 6 CONTHOL BLDG. ESF SMACNA 1975 & ANSI 18A X
X
X HVAC DUC1MORK LEAK N510, SECT. 6, 1980 X
TESTING X
X X 5094.00 FSAR 9. 4.
7. 4 DIESEL CEN. BLDG.
SMACNA, 1975 & ANSI 18A X
X
X VENT. SYSTEM N510, SECT. 6, 1980 X
DUCTWORK LEAK X
TESTING X
X 5095.00 FSAR 9. 4.
8. 5 AUX. FEEDWATER SMACNA, 1975 & ANSI 18A X
X
X PUMPHOUSE HVAC N510. SECT. 6, 1980 X
DtX*IWORK LEAK.
X TESTING X
X 5e96.00 rSin 9. 4.
9. 2. 4 MISC uvAC SvSTEMS, SMACNA, 1975 & ANSI 18A X
X
X ELECT. TUNNEL VENT. N510, SECT. 6, 1980 X
SYSTEM, DUC1 WORK X
LEAK TESTING X
.
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