ML20205J636
| ML20205J636 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 10/21/1988 |
| From: | Carrasco J, Kaplan H, Strosnider J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20205J611 | List: |
| References | |
| REF-GTECI-A-07, REF-GTECI-CO, TASK-A-07, TASK-A-7, TASK-OR 50-245-88-18, NUDOCS 8810310450 | |
| Download: ML20205J636 (11) | |
See also: IR 05000245/1988018
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U.S. NUCLEAR REGULATORY COMISSION
REGION I
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Report No. 50-245/88-18
Docket Nc.
50-245
License No. DPR-21
Licensee: Northeast Nuclear Energy Company
P.O. Box 270
Hartford, Connecticut 06141-0270
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Facility Name: Millstone - Unit 1
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Inspection At: Waterford, Connecticut
Inspection Conducted:
September 12-16, 1988
/G0//88
Inspector :
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, Senior Reactor Engineer
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Reactor Engineer
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Approved by:
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J. Strosnider, Chief, haterials and
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Processes Section
Inspection Summary:
Inspection on September 12-16. 1988
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Areas Inspected: A special announced inspection by two Region-based
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inspectors was conducted to determine if the licensee had modified the
Millstone Mark I containment in accordance with his commitment in the Plant
Unique Analysis Report (PVAR) in response to the Unresolved Safety Issue (USI
A-7).
The inspection included review of the design analyses and calculations,
installation drawings, and QA documents covering materials, welding and NDE
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employed during the installation of the saddles, SRV T Quencher and temperature
thersowells. An examination of photographs taken by the licensee at the time
of installation verified the implementation of the modification program.
Results: The licensee's actions in response to (USI A-7) satisfied the
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commitments in the PUAR. No violations or deviations were identified.
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- DETAILS
1.
Persons Contacted
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Northeast Nuclear Energy Co.
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J. Stetz, Unit Superintendent
W. Briggs, Supervisor, Civil Structure
W. Allan, Engineer, Civil Structure
S. Kane, Engineer
J. Stetz, Unit Superintendent
J. Quinn, Engineering
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W. Ruthesforth, Engineer Civil Structure
U.S. Nuclear Regulatory Commission
H. Kaplan, Senior Reactor Engineer
J. Carrasco, Reactor Engineer
L. Kolonauski, Resident Inspector
2.
Inspection Purpose and Scope
The purpose of the inspection was to determine if the licensee had
modified the Millstone Unit 1 Nuclear Power Station containment in ac-
cordance with commitments to NRC concerning USI A-7 involving suppression
pool (torus) hydrodynamic loads. The licensee's basis for the necessary
modifications was provided by Teledyne Engineering, Waltham, Massachusetts,
in the PVAR Revision 2, dated November 1984.
The NRC concluded in safety
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analysis report LS05-84-09-009 that all but a few of the modifications
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made by the licensee were in accordance with the generic acceptance
criteria contained in NUREG-0661. Where deviations to NUREG-0661 were
taken, they were found acceptable by the NRC. The modifications are shown
in figures 1 and 2.
The objectives of the inspection were accomplished by
(1) reviewing design calculations and attendant drawings of certain selected
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components in the torus to determine compatibility with the design loads
provided in the PUAR and (2) reviewing QA records covering materials,
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welding and NDE to determine conformance to specified code requirements.
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The internal modifications to the torus, except as noted, were performed
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by E. N. Flagg.
The external modifications were performed by Chicago
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Bridge and Iron (LBI).
The internal items selected for review were the
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Safety Re?ief Valve T-Quenchers and temperature heaterwells.
The external
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items selected for review were the saddles.
It is noted that temperature
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heaterwells were welded directly to the torus on both I.D. and O. D. surfaces.
The modifications were performed during the 1978, 1980, and 1982 outages.
The requirements of the modification work were specified in the 1977 Edition
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of Section XI of the ASME Code with addenda through Summer 1978. Materials
requirements were specified in the applicable sections of ASME Section
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III. The documents reviewed by the inspectors are shown in Table 1.
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3.
Findings
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3.1 Design Review
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The inspector reviewed selected design specifications, design calcula-
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tions, and fabrication and installation drawings generated by Taledyne
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. Engineering of Waltham, Massachusetts attendant with the issuance of
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the PUAR. The inspector reviewed the design of the modificat. ions to
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the SRV T-Quencher and its supports, and concluded that the structures
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were acceptable on the basis that the actual stresses were found to
be within the allowable stress values established in Section III of
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the ASME Boiler and Pressure Vessel Code.
It is noted that the
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drawings prepared by Teledyne were used for installation by
C. N. Flagg and Company, Inc. and Chicago Bridge and Iron. The
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inspector reviewed photographs of the as-built condition of the vent
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deflectors, T-Quencher and its supports, and the torus supporting
columns and saddles and concluded that the location and geometric
configuration of these items conformed to the fabrication-installation
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drawings.
The inspector observed a minor drawing deficiency involving the
T-Quencher support installations assembly. The vertical and skew
lines in Teledyne drawings 0-4818 and 0-4835 did not cross reference
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the other two sets of additional and complementary drawings 0-5375,
0-5376, E-7162 and E-7165. The licensee agreed to cross reference
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these drawings by adding appropriate notes.
3.2 Installation procedures
The inspector reviewed the QA documents on microfiche for the instal-
lation of the temperature thermowells, SRV Quenchers and saddles.
The twenty-eight thermowells, as shown in Figure 2, were installed by
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C. N. Flagg in accordance with TES drawings B-5264 and B-7195. The
inspector reviewed Carpenter Technology tertified mill test report
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dated June 19, 1980, and verified that the thermowells were fabricated
from solution annealed SA-479 type 316 stainless steel. The inspector
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reviewed appropriate welding records and concluded that the type 316
stainless thermowells were welded to the SA-516 Gr 70_ torus with an
acceptable ASME Section IX welding procedure (WP 8-33). The procedure
employed the Gas Tungsten Arc Weld (GTAW) Process with typo ER 309
filler wire. The filler wire was furnished by Teledyne McKay in
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accordance with SFA 5.9 requirements.
The procedure qualification
record identified as WP 8-21 was reviewed and found to be acceptable.
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A random check of a production welder (B 29) indicated conformance to
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Section IX performance qualification requirements. Quality Assurance
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Plan records were reviewed by the inspector which indicated that both
fit-up, and liquid penetrant inspection of the final layer had been
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performed by inspectors certified by Hartford Steam Boiler and
Nondestructure Test Division.
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The inspector reviewed the QA documents covering the installation of
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sixteen saddles as shown on TES drawing E-5208 Rev 3.
The installa-
tion was performed by Chicago Bridge and Iron during the outage of
1981.
The inspector verified by a review of operational records that
the torus was emptied during the saddle installation. The records
showed that the 1 1/2" thick saddle plates were purchased and cut by
Thames Valley Steel. Certified mill test reports indicated that the
saddle plate material was produced by Phoenix Steel and conformed to
SA 516 Gr 70 specification requirements as specified in the Owner
Specification 05-2138-2 including acceptable charpy impact properties
performed at 0*F.
The records showed that attaching the saddle
plates directly to the torus was avoided by prebuttering the torus
using a special butterbead/temperbead technique followed by magnetic
particle inspection a minimum of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after welding.
This
technique and welding with the torus empty were employed to preclude
brittle areas in the heat affected zone (HAZ) of the torus and
delayed cracking due to hydrogen. The inspector verified that the
CB&I manual metal arc welding procedures E7018-3 and E7018-4 which
were employed in the installation of the saddles conformed to ASME IX
and III qualification requirements as recorded in Procedure Qualifica-
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tion Record 4400. The record showed satisfactory impact tests at O'F
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for weld metal, base metal and HAZ.
Representative E7018 electrode
test reports were reviewed and found to conform to SFA 5.1 requirements
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along with satisfactory impact requirements at -20*F as shown in
Alloy Rods certified test report for material heat 421J461.
The inspector reviewed the QA records covering the installation of
the T-Quencher as provided by C. N. Flagg. Welding was performed
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utilizing qualified ASME IX wolders in accordance with welding
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procedure WP 1-34.
Representative NDE records were reviewed which
showed that the welds had been subject to visual and magnetic
particle testing.
No defects were reported.
3.2 Audits and Surveillance
The inspector reviewed several detailed licensee surveillance reports
covering CBI work on the internal components of the torus.
These
were identified a C-1266 (welding of Temper beads), C-1293 (magnetic
particle inspection of girders, C-1295 (welder qualifications) and
C-1322 and C-134 (welding of saddle plates). No problems were re-
corded.
The inspector reviewed several licensee reports covering C.
N. Flagg work inside the torus.
These included C-1258 (MT of ring
guide), C-1270 (baking of electrodes), C-1294 (MT of downcomer lugs)
C-1345 (Weld Rod Control) and C-1248 (general welding surveillance)
and C-1345 (weld rod-control). These reports did not disclose any
significant findings.
Several minor findings were reported involving
baking and weld rod control.
These were corrected with recom-
mendations to continue surveillance in these areas.
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3.3 Tour
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During a tour of the control room, the inspector observed that the
bulk water temperature in the torus was 80'F-82'F (Control Room
Panel 903) as compared to the Technical Specification requirement of
90'F maximum.
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4.
Conclusion
Based on the review of design calculations, drawings, photographs of as
built condition and QA records, the inspector concluded that the licensee
had modified the Mark I containment in accordance with the commitments in
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the Plant Unique Analysis Report. The records showed that the work was
performed under a comprehensive QA Program. No violations or deviations
were identified.
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An exit meeting was conducted on September 16, 1988 (see paragraph 1.0
for attendees) at which time the findings of the inspection were
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presented.
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At no time during the inspection was written material provided to the
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licensees by the inspectors.
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ATTACHMENT 1
DOCUMENTS REVIEWED
SPECIFICATIONS
1.
Teledyne Engineering Services, "Plant - Unique Analysis Report of the
Torus Suppression Chamber for Millstone Point Unit 1 Nuclear Power
Station." Division 2.
2.
Teledyne Engineering Services, Specification No. FS-2138-1 Revision 1;
"Millstone Point Unit 1 Nuclear Power Plant Structural Modification to
the Mark I Containment System.
3.
Northeast Utilities, Specification No. SP-CE-51/PA 77-651 Revision 1
"Specification for (Group One) 1980 Torus Outage Modification of the
Downcomer, Installation of New Downcomer Tie Straps, Installation of Vent
Header Deflectors, Modification of the LPCI Return Lines Inside the Torus
and Installation of Vacuum Breakers in the Drywell."
4..
Owner's Specification OS 2138-3 - Revision 0 "Structural Modifications to
the Mark 1 Containment for Millstone Point Unit 1 Nuclear Power Plant.
5.
Northeast Utilities Specifications SP-CE-101 1982 Torus Outage (Internal)
- Reinforcement of Vent Header and Downcomer Intersection, Reinforce
Existing Walkway and Installation of New Handrail Including QA
Requirements.
6.
Northeast Utilities SP-GEE-69 Technical Requirements for Torus
Temperature Monitoring System.
7.
Northeast Utilities Specifications SP CE-50 1980 Torus Saddles.
DRAWINGS
1.
D-4814 Revision 4 Teledyne Engineering Services Details 16" Pipe
Deflectors, Dated June 12, 1981.
2.
D-4813 Revision 4 Teledyne Engineering Services Details Vent Header Ring
Clevis and 16" Deflector Pipe Support, Dated June 14, 1981 (one L. H. and
One R. H.).
1.
D-4812 Revision 6 Teledyne Engineering Services Vent Header Deflector and
Support Assembly, Dated June 15, 1981.
4.
D-4818 Revision 4 Teledyne Engineering Service 10" Service Line with 12"
T-Quencher Installation Assembly, Dated October 15, 1979.
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ATTACHMENT 1
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5.
0-4819 Revistoa 3 Teledyne Engineering Service T-Quencher Support
Details, Dateu June 15, 1981.
6.
0-4835 Teledyne Engineering Service 10" Service Line with 12" T-Quencher
Installation Assembly.
7.
D-5375 Revision 1 Teledyne Engineering Service Modification to T-Quencher
Assy: Service Lines 0, E, and F, Dated July 24, 1988.
8.
D-5376 Revision 2 Teledyne Engineering Service Modification to T-Quencher
Assy: Service Lines A, 8, and C, Dated July 24, 1980.
9.
E-7162 Revision 2 Teledyne Engineering Service Reinforcement Modification
of T-Quencher Assy: SRV Lines D, E, and F, Dated March 3, 1983.
10.
E-7168 Revision 3 Teledyne Engineering Service Reinforcement Modification
to T-Quencher Assy:
SRV Lines A, B and C, Dated March 3, 1983.
11.
B-5118 Revision 0 Teledyne Engineering Service Shim Detail (T-Quencher
Support Modification @ Ring Girder No. 16 Only), Dated May 24, 1979.
12.
B-4094 Revision 0 Teledyne Engineering Service Inside Reinforcement Torus
Column Tube Millstone I, dated March 18, 1977.
13.
C-7322 Revision 1 Teledyne Engineering Service Vent Pipe Penetration
Stiffening 10" SRV Line A, B and C, Dated September 30, 1982.
14.
0-4154 Revision 2 Teledyne Materials Research Torus Support Column
(Outer) - Base Plate Tie Down Millstone Point I, Dated December 1, 1976.
15.
D-4130 Revision 2 Teledyne Materials Research Torus Support Column
(Inner) - Base Plate Tie Down sillstone Point I.
16. D-4093 Revision 2 Teledyne Matrials Research Modification to Torus Insida
Support Column Millstone Point I.
17.
D-4681 Revision 1 Teledyne Engineerini_ Service Modification to Torus
Outside Support Column Millstone Point I.
DESIGN CALCULATIONS
1.
Teledyne Engineering Service Calculation 5318F-266 Vent Pipe Penetration
Stiffening 16" Service Line A, B, & C, Millstone Unit 1.
hodification to "T"g Service Calculation 5318F-221 Calculation for
Teledyne Engineerin
2.
Quencher Support Assy at Millstone (Ref. DWGS D-5375
Revision 0 thru 1 and D-5376 Revision 0 thru 2)
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ATTACHMENT 1
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3.
Teledyne Engineering Service Calculations 5318F-223 Calculation for
Reinforcement Modification to "T" Quencher Service Line 0, E, and F -
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Millstone Dwg E-7162 Revision 1.
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4.
Teledyne Engineering Service Calculation 5318F-220 Calculation for
Millstone T-Quencher Support Beam (Ref OWG D-4818, 4819, 4835, 5118).
ANALYSIS
1.
Teledyne Engineering Service Analysis 2138-8 Millstone-Internal Structures
Geometry and loads.
2.
Teledyne Engineering Service Analysis 5318-36 Millstone T-Quencher
Analysis (Line E) with Vertical SRV Line.
3.
Teledyne Engineering Service Analysis 5318-85 Millstone T-Quencher
Analysis (Line C) with Inclined SRV Line.
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Owner's Specification 05-2138-3 - Rev. O "Structural Modifications to the Mark 1
Containment for Millstone Point Unit 1 Nuclear Power Plant.
Northeast Utilities Specifications SP-CE-101 1982 Tows Outage ('nternal) -
Reinforcement of Vent Header and Downcome Intersection Reinforce
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Walkway and Installation of ? Handrail including QA Requirements.
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Northeast Utilities SP-GEE-64 Technical Requirements for Torus Temperature
Monitoring System.
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Northeast Utilities Specifications SP CF-50 1980 Torus Saddles.
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Q = MOOl FIC ATIONS
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FIGURE 1:
Toru: Cross Section Showing Modified
Components
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TORUS SHELL
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CONAX B ARE WIRE
THERMOCOUPLE GLANDS
MODEL TYPE C
FIGURE 2:
Detail Of Torus Thennowell Modification
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