IR 05000482/1982003
| ML20050D468 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 03/25/1982 |
| From: | Randy Hall, Stewart R, Westerman J, Westerman T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20050D463 | List: |
| References | |
| 50-482-82-03, 50-482-82-3, NUDOCS 8204120234 | |
| Download: ML20050D468 (9) | |
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APPENDIX U. S. NUCLEAR REGULATORY COMMISSION
REGION IV
Report: STN 50-482/82 w Docket: STN 50-482 Category A2 Licensee:
Kansas Gas and Electric Company P. O. Box 208 Wichita, Kansas 67201 Facility Name:
Wolf Creek, Unit 1 Inspection At:
Wolf Creek Site, Coffey County, Burlington, Kansas Inspection Conducted: January 26-29 and Febr-y 17-19, 1982 Av-Inspector:
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R. C. Stewar%ctor Inspector Date Reactor Project Section B Reviewed:
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T. F. Westerman, Chief Oate Reactor Project Section A Approved:
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R. E. Hall, Chief Cate /
Reactor Project Section C Inspection Summary:
Inspection during January 26-29, and February 17-19, 1982 (Report STN 50-482/82-03)
Areas Inspected: Licensee action on previous inspection findings and site tours.
The inspection involved 49 inspector-hours on site by one NRC inspector.
Results:
No violations or deviations were identified.
0204120234 820331 PDR ADOCK 05000482 A
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Details
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Persons Contacted Principal Licensee Personnel D. Colwell, QA Technologist G. Fouts, Manager, Wolf Creek Construction G. Koester, Vice President - Nuclear
- D. Prigel, QA Manager, Site
- C Perry, QA Technical Auditor
- G. Reeves, Assistant QA Manager, Site
- Denotes attendance at exit meeting.
The NRC inspector also interviewed other contractor personnel during the course of the inspection.
2.
Licensee Action on Previous Inspection Findings-(Closed) Construction Deficiency Report (STN 50-482/79-13) Flood Damage in Reactor Auxiliary Building.
During the late evening hours of June 7, and during the early morning hours of June 8,1979, torrential rains fell at the Wolf Creek site.
Totai accumulated rainfall durirg the period was nearly 6 inches.
Due to the construction status at that time, there were several pathways for water to enter the power block buildings; for example, roofs were not yet in place, temporary construction openings were not closed, and portions of backfill were not complete making a basin around portions of the buildings.
The Radwasto Building is connected to the Auxiliary Building basement by a large pipe tunnel.
Much of the water which fell into or ran into the Radwaste Building flowed through the tunnel into the Auxiliary Building basement, where most of the flood damage occurred.
The elevation of the Auxiliary Building basement is 1974 feet.
The high water point was 1975 feet 6 inches, or approximately 18 inches.above the basement floor.
Pumps, both electric and engine driven, were used to pump out the inflow; however, the electric sump pumps were fed power from a source located in the basement and subsequently power had to be shutoff.
The diesel engine pumps had a low head capacity, and since they were working against 25 feet of head, their capacity was greatly diminished; and because of the large amount of surface water around the power block, normal drainage was ineffective, thus causing a considerable amount of the pump discharge to flow back to the excavated area around the Auxiliary Building and back into the basemen.
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Safety-related components, which were totally or partially submerged in water and mud, were identified and listed on 25 Deficiency Reports and Nonconformance Reports.
Items involved included piping, valves, pumps, motors, limitorque valve operators, gear boxes, and electrical control equipment.
The licensee submitted written Interim Reports on July 13, 1979; December 28, 1979; March 31, 1980; January 2, 1981; July 15, 1981; and October 15, 1981.
A final written report was submitted to the NRC on January 15, 1982.
During this inspection, the NRC inspector conducted a detailed review of-the principal Nonconformance Reports (NCRs)/ Deficiency Reports (DRs),
associated inspection reports, internal correspondence and certification documentation.
i The following NRCs/DRs were reviewed:
0FF-SITE REWORK OF FLOOD DAMAGED EQUIPMENT NCR/DR ITEM ID NUMBER DOCUMENTATION ISN1026M Boric Acid Transfer Pumps SN 23446-7 & 8 P.O.# 400835 MRR # 46502 ISN1066M Valves 2RA74DZA P.O.# 252203 ISD1825M 3WA74DZA MRR # 46367 15D1816 Containment Spray Pumps PEN-01A/B P.O.# 10881RM-088 MRR # 50293 1SD1833M Check Valve S/N 2651 P.O.# 10466-M-221-1 MRR # 43134 ISD1835M Flex Wedge Gate Valve Serial # 1619 P.O.# 10466-M-223C-1 MRR # 38330 1SN1024M Charging Pump PBG05A Attached to NCR/DR
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ISN1025M Residual Heat Removal Pump PEJ01 A&B
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1SD1817E Induction Motors PALO1A/B
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1SD1818M Aux. Feedwater Pumps PALO1A/B
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PALO2 IND1821M Room Cooler Unit SGLO7
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NCR/DR ITEM ID NUMBER DOCUMENTATION ISD1822M Room Cooler Components SGL10 A&B Attached to NCR/DR
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ISD1834M Valves HV26, HV38, HV40, V-16, V-113
'1SD1852E Rust in Cubicle Frames BUSNB01
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1SD1897M Space Heaters Pipe Formation A-33-132 ISD6967M Bonnett on Check Valve 8958A Traveler M03EJ01Q In addition, the NRC inspector conducted a plant walk-through observing the present conditions and protective measures being implemented on the major equipment, which included the charging pumps, RHR pumps, and containment spray pumps.
It was also observed that construction progress was now far enough along so as to preclude the possibility simular flooding.
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No violations or deviations were identified.
This item is considered closed.
-(Closed) Unresolved Item (STN 50-482/80-02, paragraph 3) Union Allegation of Substandard Work.
In an. article published in the December 21, 1979, issue of the Emporia Gazette, allegations were made in relation to substandard work at Wolf Creek.
KG&E identified this article to Region IV on January 2, 1980.
At that time, the management official indicated that KG&E intended to conduct an investigation into the allegations..The NRC inspector determined that the allegers, including the local union representative of the Kansas Building and Construction Trades Council at New Strawn, Kansas, were_sent registered letters requesting them to contact KG&E by telephone or mail.
As of January 30, 1980, no one had made contact.
No telephone calls had been made by KG&E to the allegers.
The NRC inspector requested that a copy of the KG&E investigation report be made available for review upon completion of their efforts.
Since the NRC may conduct their own investigation, this item was considered unresolved.
During this inspection, the NRC inspector discussed this matter with the cognizant KG&E representatives and was informed that subsequent to the above reported NRC inspection, an NRC investigation regarding the
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newspger allegations was conducted dt. ring the period of March 18-28, 1980
, and as a result, an independent KG&E investigation was not conducted.
As indicated in the NRC investigation report, no items of noncompliance or deviations were identified.
The allegations were either not substantiated and/or were found to be withaut merit.
This item is considered closed.
-(Closed) Unresolved Item (STN 50-482/80-02, caragraph 5) Allegations in a Report to the Governor of Missouri.
The "Benson Report" to the Governor of Missouri contains allegations relating to piping problems at Callaway and Wolf Creek.
A Region III investigation has bee completed and the results forwared to the Governor of Missouri pj The allegations were concerned with piping
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subassemblies constructed by Gulf & Western.
The alleger confirmed that the utility audit addressed his concerns.
One additional concern of the alleger (significance of QC inspector's signature) has been passed to the Region IV Vendor Program Branch for review during a future inspection.
This item was considered unresolved pending completion of the vendor inspection.
The NRC inspector reviewed the Vendor Program Branch files and established that the Vendor Program Branch conducted an investigation on the matter during the period of April 23-25, 1980.
The_results of the investigation are contained in Vendo_r Inspection Report 99900704/80-01.
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This item is considered closed.
-(Closed) Infraction'(STN 50.482/80-18, paragraph'3.c.(4).)
Emergency Service Water (ESW) piping lwe_iding.
During a previous inspection, the RRI witnessed welding activities on an ESW piping header by two(Daniel welders.
It'was noted that low hydrogen electrodes (E7018) were being used.
Further observation established that, although heated containers (caddies) were nearby, they were not being used to store the electrodes.
The welders were using their stub buckets to store their electrodes.
Also, the heated containers were not plugged into an electrical outlet ~ and were therefore unheated.
1/ NRC Report No. STN 50-482/80-06, dated April 21, 1980.
2/ Region IV letter to Honorable Joseph P. Teasdale, Governor of Missouri, dated December 10, 197,
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This item was considered to be in noncompliance with 10 CFR 50, Appendix B, Criterion V, and was identified to the licensee by letter dated October 8, 1980.
(80-18-02).
In a written response by the licensee letter dated October 30, 1980, the licensee indicated that:
a.
The identified use of cold electrodes was' documented on Deficiency Report 1SD5033M.
To assure.the metallurgical soundness of the weld, the deficiency report disposition required the removal, by grinding, of the portion of the weld deposited by the Shielded Manual Arc process.
Such removal was verified by QC inspection.
Rewelding was performed in accordance with welding procedure CWP-503.
b.
The two welders responsible for the improper care of welding electrodes were reprimanded and given a 3-day suspension without pay.
In accordance with Daniel's policy on weld rod control, any further violation by these welders will result in their termination.
c.
Full compliance was achieved on October 28, 1980.
During this inspection, the NRC inspector reviewed Deficiency Report No.
ISD5033M and verified the reported disposition.
In addition, the NRC inspector conducted a plant walk-through to observe the storage control (caddies) on low hydrogen electrodes.
Although limited safety-related welding was in progress, no violations or deviations were observed.
This item is considered closed.
-(Closed) Unresolved Item (STN 50-482/80-04, paragraph 3) Project Housekeeping.
During a previous inspection, the NRC inspector examined the Reactor Building area for housekeeping requirements.
During the inspection, two men were observed eating lunch within a designated " Zone 4."
Daniel's Procedure, AP-XIII-05, paragraph 3.7, and Appendix II, states that within
" Zone 4" the use of tobacco and eating will not be allowed.
However, during the discussion and review of records of this item with the Project Safety Engineer, it was determined that " Zone 4" was designated (for an area inside the shield walls) on February 22, 1980.
The Construction Manager was informed officially on Febraury 25, 1980, and thus the required training of personnel has not yet been done by the Area Construction Superintendent.
This item was considered unresolved pending a review during a subsequent NRC inspection.
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During this inspection, the ARC inspector reviewed the housekeeping inspection records for March 3 through March 31, 1980.
In addition, the NRC inspector was provided copies of training records and internal documentation which reported the corrective measures taken.
The NRC inspector had no further questions.
This item is considered closed.
-(Closed) Unresolved Item (STN 50-482/81-15, paragraph 3) KG&E audits.
During a review of KG&E audits, the KGLE site QA Manager informed the NRC inspector that a draft audit report on material traceability, Audit TE 57061-K48, would not be formally issued because it did not comply with site Audit Procedure KP 12-4, but would be filed as a QA record along with a letter of explanation.
A reaudit of material traceability had been rescheduled for October 1981.
The letter of explanation specifies that the reaudit would address the specific items presented in the draft report and would resolve all valid concerns.
This item was considered unresolved pending resolution of all identified concerns addressed in draft Audit Report TE 57061-K48.
During this inspection the NRC inspector was provided a copy of the reaudit of report TE 57061-K48, dated February 4,1982.
There were 10 items initially identified by a former KG&E auditor in the draft report as items of concern.
The reaudit report TE 53359-S429, established that the 10 items were incorrectly identified as deficiencies, and therefore, invalid finding.
Information contained in the reaudit supports the final determination of these matters.
The NRC inspector concurred with the final determination on the specific items and had no further questions.
This matter is considered closed.
-(0 pen) Unresolved Item (STN 50-482/81-11, paragraph 4)
Reactor Coolant Pressure Boundary Piping.
While observing the welding of temporary attachments for fit up of Weld F308, the NRC inspector noted that the welding machine was grounded to the base plate of a Steam Generator vertical support column which had the potential to cause damage to the two bearings in the support column.
A Deficiency Report, DR No. ISD 7059M, was issued by Daniel's Quality Inspection Manager.
During this inspection, the NRC inspector reviewed DR No. ISD7059M as to the final disposition.
It was observed by the NRC inspector that corrective measures taken for proper grounding for welding machines was resolved; however, the Daniel procedure for jacking up the steam
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generator to facilitate the examination of the column support bearings was unacceptable to the onsite W representative and as a result, inspection of the referenced bearings has not been completed.
This matter will remain open pending an NRC review of the column bearing inspection results and resolution of the Deficiency Report.
3.
Site Tour The NRC inspector toured the Reactor, Auxiliary, and Control Buildings to observe construction in progress and to inspect overall housekeeping.
No violations or deviations were identified.
4.
Exit Interview The NRC inspector met with the licensee representatives (denoted in paragraph 1) and the NRC Senior Resident Reactor Inspector, T. E. Vandel, on February 19, 1982, and summarized the scope and findings of the inspection.
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