IR 05000327/1979072
| ML19305B423 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 01/10/1980 |
| From: | Cantrell F, Gouge M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19305B417 | List: |
| References | |
| 50-327-79-72, 50-328-79-35, NUDOCS 8003190632 | |
| Download: ML19305B423 (5) | |
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION o
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E REGION 11
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f 101 MARIETTA ST N.W SUITE 3100 e
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o ATLANTA, GEORGIA 30303 Report Nos. 50-327/79-72 and 50-328/79-35 Licensee: Tennessee Valley Authority 500A Chestnut Street Chattanooga, Tennessee 37401 Facility Name: Sequoyah Nuclear Plant Docket Nos. 50-327 and 50-328 License Nos. CPPR-72 and CPPR-73 Inspection at Seqyo 3ite near Chattanooga, Tennessee Inspector:
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Date Signed Approved by:
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F.'S trell, Section Chi RCES Branch
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SUMMARY Inspection on December 18-20, 1979 Areas Inspected
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This routine, unannounced inspection involved 21 inspector-hours onsite in the
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areas of 10 CFR 50.55(e) items, inspector followup items, IE Bulletins and
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observation of safety-related activities.
Results Of the four areas inspected, no items of noncompliance or deviations were identified.
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DETAILS 1.
Persons Contacted Licensee Employees
- G. G. Stack. Project Manager
- T. B. Northern, Jr., Construc 'on Engineer
- R. W. Olson, Assistant Cont.t.ection Engineer
- L. McCloud, QA Supervisor, G.quoyah Nuclear Station
- R. B. Bruce, Construction QA Unit
- S. Duhan, OEDC QA Staff
- J. A. Thompson, Supervisor, Unit 1 Coordination Unit J. A. Naik, Unit 1 Coordination Unit C. D. Wagner, Unit 1 Hanger Unit H. R. Rogers, Unit 1 Hanger Unit
.. D. Clift, Jr., Mechanical Engineering Unit J. A. Hauerter, Welding Inspection Unit o
- E. C. Pendergrass, QC Records Unit D. L. Wall, Nuclear Licensing (ENDES)
M. A. McBurnett, Nuclear Engineer, Regulatory Staff Other licensee employees contacted included various construction craftsmen, technicians, and office personnel.
NRC Resident Inspector W. T. Cottle 2.
Exit Interview The inspection scope and findings were summarized on December 20, 1979 with those persons indicated in Paragraph I above.
3.
Licensee Action on Previous Inspection Findings b
Not inspected.
4.
Unresolved Items c
Unresolved items were not identified during this inspection.
5.
Licensee Identified Items (Units 1 and 2)
TVA has reported a number of items to Region II as reportable in compliance
with 10 CFR 50.55(e). The Region II inspector reviewed the items listed
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below and the supporting documentation, and discussed the items with respon-sible licensee staff during the inspection.
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-2-a.
(Closed) Item 50-327/79-20-05 and 50-328/79-11-05: Containment Penetra-tions Seismic Reanalysis (NCR CEB 79-14). The inspector reviewed the TVA final report dated June 15, 1979, the closed NCR CEB 79-14, the closed ECN 2419, drawing BE-4160-105, and Support Modification Request (SMR) 1072HPRICSH-99. Completed Unit I hanger 1072HPRICSH-99 was inspected for proper installation in accordance with the above drawings and SMR. Weld records were reviewed for weld 1HZ99A shich attached the support plate to the containment spray piping. Records reviewed included fit-up, visual and penetrant inspection cards. The heat number on the stainless steel plate (heat # 345016) was traced back to supplier CMTR's and proper chemical properties were verified. Work plans 5183 and 8115 were used to control work on supports affected by NCR CEB 79-14.
Work on Unit 2 will be accomplished in accordance with drawings as revised by ECN 2548 and controlled by appropriate work packages.
b.
(Closed) Item 50-327/79-29-04 and 50-328/79-16-04:
Containment Piping Support Design Basis (NCR CEB 79-19). The inspector reviewed the TVA final report dated October 15, 1979, the closed NCR CEB 79-19, and the closed ECN 2419. This ECN affects Unit I hangers and was reviewed with TVA Civil Engineering Branch (ENDES) staff previously (IE report 327/79-53 and 328/79-28). The inspector selected completed hangers 1067HPRIERCW-076-22 and 1067HPRIERCW-076-31 to verify installation in accordance with drawings 47A053-874, 47A053-878, and support variance sheet 1067HPRIERCW-076-28.
Installation was in accordance with the above drawings. Work on Unit I hangers affected by ECN 2419 is complete. Work on Unit 2 will be in accordance with drawings revised I
by ECN 2548 and will be controlled by appropriate work packages.
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(Closed) Item 50-327/79-53-02 and 50-328/79-28-02: ERCW Isolation Valves not Seismically Qualified (NCR CEB 79-29). The inspector reviewed the TVA final report dated October 25, 1979, the closed NCR CEB 79-29 and the closed Unit 1 ECN 2665. Work is complete on Unit 1 and was conducted in accordance with work plans 5161, 8117 and 8118.
The installation of the supports for the ERCW valve operators was inspected to ensure conformance to revised drawings. Work on Unit 2 has not started but will be accomplished in accordance with drawings revised to reflect this support modification and appropriate work packages.
d.
(0 pen) Item 50-327/79-36-12:
Pressurizer Relief Piping Support (NCR
SWR-79-S-8).
This item involies the failure of support 1 RCH-93 during hot functional testinF that resulted in significant deformation of the six-inch pressurizer celief line. The licensee elected to return the piping to its or.ginal configuration by use of a weld bead draw procedure that uses w elding generated forces to deflect piping.
NRR has approved a reques*,by TVA to waive ASME Section XI waive hydrostatic testing of the repaired section of piping in accordance with IWA-4400 of the Summer 1978 addenda of the ASME code. The piping weld bead draw repairs did not penetrate through the pressure boundary.
NRR has raised several concerns about the stresses ir. the affected
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-3-section of pipe and possible sensitization of the stainless steel that could lead to stress corrosion cracking. NRR has asked TVA to provide weld parameter data to estimate heat input, system data to indicate the environment that the affected piping will be subjected to, and the results of testing in accordance with ASTM A262-70 Practice E on a prototype of the affected piping. This item requires resolution prior to Unit 1 fuel loading and remains open pending NRR review of the requested data.
e.
(Closed) Item 50-327/79-72-01 and 50-328.'79-35-01:
Computer Room Wall Partitions. On November 5,1979, TVA informed Region II of this reportable item identified as NCR MEB 79-42 and NCR 1938. TVA stated in a final report dated December 5, 1979 that the wall partitions that had been damaged daring preoperational testing will be replaced by panels with a minimum one and one-half hour fire barrier rating that can withstand expected carbon dioxide room pressures during operation of the carbon dioxide fire protection system. The new partitions have been installed in the affected areas in accordance with work plan 8132.
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(Open) Item 50-327/79-72-02 and 50-328/79-35-02: Seismic Support for Fire Extinguishers. On November 5, 1979, TVA informed Region II of this reportable item identified as NCR MEB 79-43.
TVA stated in a final report dated December 5, 1979 that seismically qualified mounting brackets will be installed to secure fire extinguishers located in Category I structures by May 30, 1980 for Unit I and before fuel loading for Unit 2.
ECN 2731 will be issued to existing drawings to document this modification.
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(0 pen) Item 50-327/79-72-03 and 50-328/79-35-03: Defects in Charcoal
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Absorber Trays. On November 16, 1979, TVA informed Region II of this
reportable item identified as NCR 17P. A 30-day written report is due December 16, 1979.
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(0 pen) Item 50-327/79-72-04 and 50-328/79-35-04: Departure from Nucleate Boiling (DNB) Ratio Following Rod Drop.
On November 16,
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1979, TVA informed Region II of this reportable item identified as NCR NEB 79-6.
A 30-day written report is due December 16, 1979.
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(Open) Item 50-327/79-72-05 and 50-328/79-35-05: Undetectable Failure in Solid State Protection System. On November 23, 1979, TVA informed Region II of this reportable item identified as NCR NEB 79-4.
This item is generic to Westinghouse PWR's and has been previously reported to the NRC by Westinghouse under 10 CFR 21.
A 30-day written report is due December 24, 1979.
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(0 pen) Item 50-328/79-35-06: Upper Head Injection System Seismic
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Analysis. On December 5,1979, TVA informed Region II of this reportable item identified as NCR CEB 79-36.
A 30-day written report it due January 4, 1980.
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-4-No items of noncompliance or deviations were identified.
6.
Inspector Followup Item (Unit 1)
(Closed) Item 50-327/79-63-02: Open Unit 1 Nonconformance Reports (NCR).
The approximately 20 NCR's that affect safety-related components in Unit 1 or common structures which were open at tne time of IE Inspection 50-327/
79-63 have been reviewed by the licensee's Unit 1 Coordination Unit staff.
These NCR's and subsequent NCR's initiated on Unit 1 or common structures have been resolved and closed or placed on the Outstanding Work Items List (0WIL) for Unit 1.
The OWIL will monitor the status of the problem docu-mented by the NCR and key completion of the work item that will resolve the NCR to fuel loading, if applicable.
7.
IE Bulletins (Units 1 and 2)
(Closed) IE Bulletin 79-4:
Incorrect Velan Valve Weights. Region II has reviewed the TVA response to the subject bulletin dated November 9, 1979.
TVA had previously determined that this generic problem affected the Sequoyah site and reported this to Region II in compliance with 10 CFR 50.55(e).
This problem is documented by closed NCR's MEB 79-13 and MEB 79-20.
These 10 CFR 50.55(e) items have been closed by Region II. TVA's response and corrective actions are acceptable.
8.
Observation of Safety-Related Activities (Units 1 and 2)
The project inspector conducted a general walk-through inspection of Units 1 and 2 Containment Buildings and the Auxiliary Building. Areas inspected included general housekeeping practices, storage of QA materials, rigging practices, measures to control cleanliness of piping, and installation of various supports for safety-related piping and valves.
In process welding of weld 2CX00203A was observed in the Unit 2 Containment building. This weld joined parts 2CVC144B to 2CVC142A. This 3" Class A weld was performed to weld procedure GT-88-01.
Areas inspected included documentation of fitup inspection, proper adherence to QC hold points, purge gas control, control of interpass temperatures, welder qualification,
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welding rod control, weld techniques and chemical composition of the welding J
rod.
l No items of noncompliance or deviations were identified.
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