IR 05000482/1981017
| ML20039G876 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 12/16/1981 |
| From: | Crossman W, Stewart R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20039G871 | List: |
| References | |
| 50-482-81-17, NUDOCS 8201190252 | |
| Download: ML20039G876 (7) | |
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APPENDIX
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U.S. NUCLEAR REGUUJORY COMMISSION
REGION IV
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Report:
STN 50-482/81-17
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
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Inspection Conducted:
November 2-5 and 16-19, 1981
/JM/[8 Inspector:
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R. C. Stewart, Reactor Inspector Date Reactor Projects Section 3 Approved:
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l2f/( fl W. A. Crossman, Chief, Reactor Projects Section 3 Date Inspection Summary:
Inspection during November 2-5 and 16-19,1981 (Report STN 50-482/81-17,)
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Areas Inspected:
Licensee action on previous inspection findings; site tour; and participation in Caseload Forecast Panel as panel member.
The inspection involved 52 inspector-hours on site by one NRC inspector.
Results: No violations or deviations were identified.
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8201190252 811222 PDR ADOCK 05000482
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DETAILS 1.
Persons Contacted Principal Licensee Personnel
+0. W. Prigel, QA Manager, Site
+G. Reeves, Assistant QA Manager, 5f te
+0. Sayre, QA Technician The NRC inspector also interviewed other contractor personnel during the course of the inspection.
NRC Caseload Forecast Panel Meeting Attendees (November 17 & 19, 1981)
Nuclear Regelatory Commission J. B. Hopkins W. H. Lovelace R. C. Stewart Kansas Gas and Electric
- E. W. Creel M. L. Johnson T. D. Keenan G. L. Fouts G. L. Koester G. P. Rathbun N. L. Hill
- C. L. Huston F. T. Rhodes
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D. W. Prigel l
- R. Kloefkorn L. Loerper Daniel International Company
- L. F. Warrick
- T. D. Borgman L. R. Smith l
Kansas City Commission
- M.
Keener l
i Wichita Eagle-Beacon G. L. Haden s
+0enotes those present at the exit interview.
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- 0enotes those present at NRC Caseload Forecast Panel Meeting on
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Burlington Daily
- T. Dippel KTSB-TV
- T. Erskine
- G.
Pennybacker Kansas City Power and Light F. D. Crawford KEPCO
- L. J. Hamman A. Mee SNUPPS
- R. L. Straight Bechtel
- J. H. Smith Union Electric
- T. A. Esswein Phoenix Power Services, Inc.
- M. E. Stern WIBW-TV
- W. Parker
- W. Ricker 2.
Licensee Action on Previous Inspection Findings During this inspection, the NRC inspector conducted a detailed review of the status of 35 unresolved items identified during previous NRC inspections.
During the review. the cognizant licensee representatives indicated that 17 items were awaiting NRC verification; however, after an evaluation of the information provided the NRC inspector, the NRC inspector detennined that insufficient documentation was available to resolve 12 of the 17 items.
These matters will be reviewed during a subsequent NRC inspection.
- Denotes those present at NRC Caseload Forecast Panel Meeting or.
November 17, 1981, only.
- Denotes those present at NRC Caseload Forecast Panel Meeting on November 18, 1981, only.
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(Closed) Deviation (STN 50-482/81-05-05):
Internal Color Coding - During an NRC inspection conducted March 23-27, 1981, the NRC inspector reviewed Bechtel Specification 10466-E-009 for the Class lE 4160 Switchgear during closecut of a potential 50.55(e).
The NRC inspector found that Appendix A of the Bechtel specification specifies a different color coding for redundant separation groups than that specified in the Final Safety Analysis Report (FSAR).
The Wolf Creek FSAR, Section 7.1.2.3, identifies the color coding for the separation groups as follows:
Separation Group 1:
Red Separation Group 2: White Separation Group 3:
Blue Separation Group 4:
Yellow Nonsafety
Black Bechtel Specification 10466-E-009, Appendix 7, Revision 6, paragraph 5.2.2, states, " Wiring of the various separation groups within the switchgear shall be identified (color-coded) in accordance with the following:
" Separation Group 1:
Red Separation Group 2: White Separation Group 3:
Blue Separation Group 4: Green" This was considered a deviation to the FSAR commitments by the NRC inspector.
During this inspection, the NRC inspector was informed that the Wolf Creek FSAR was revised to conform with the color coding as stated in the Bechtel Specification and as observed in the Class lE 4160 Switchgear.
The revision to the ESAR involved the rewording of Section 8.3.1.3, which clarifies the color coding requirements. The NRC inspector verified the FSAR revision contained in Amendment 6 to the FSAR.
This matter is considered closed.
(Closed) Unresolved Item (STN 50-482/81-11):
Other Safety-Related Welding -
During the NRC inspection conducted June 1-5, 1981, the NRC inspector discussed a 1980 ASME B&PV Committee interpretation with Daniel International and Kansas Gas and Electric personnel.
Interpretation III-80-65 states that all new performance qualifications for welders shall be in accordance with the latest edition of Section IX.
Daniel International takes the position that a 1976 ASME B&PV Committee Code interpretation permits new qualifications
to be performed in accordance with'the 1974 Edition through Summer 1975 Addenda of Section IX.
Since the 1980 interpretation does not support the Daniel International position, this item was considered unresolved pending a clarification of the two interpretations.
During this inspection, the NRC inspector was provided a copy of a letter addressed to Daniel Construction Company from the ASME Assistant Secretary, B&PV Committee, dated September 16, 1981, which states,
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" Question (1):
QW-100.3 states that a manufacturer may perform any new qualifications needed for a particular contract to the Addenda mandatory for that particular contract.
These qualifications to previous Addenda may not be used on new orders.
This appears to be in conflict with the Preamble which requires all new qualifications to be made to the Addenda mandatory on the date of qualification.
May a manufacturer qualify all new welding procedure specifications and per-formance qualifications to the requirements of the Code Edition and Addenda made mandatory at the date of order?
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Yes.
" Question (2): May a manufacturer qualify all new welding procedures and welders or welding operators for a specific job to any Code Edition and Addenda after the Code Edition and Addenda made mandatory at the date of order?
" Reply (2):
Yes."
This matter is considered resolved.
(Closed) Unresolved (STN 50-482/79-17):
Deterioration of Protection for Equipment Anchor Bolts - During an NRC site tour during the period September 17-20, 1979, the NRC inspector noted an accumulation of water around, and deterioration of protection for, equipment anchor bolts of major safety-related equipment in the RCB; and the temporary storage of stainless steel drain lines.
Also, the inspector noted potential account-ability problems relating to storage of several pieces of small pipe.
These small pipe pieces had been flooded and were awaiting clean up.
(See KG&E Report on Flood Damage in Auxiliary Building, dated July 13,1979.) During the tour, the licensee representatives initiated corrective action on these items.
In addition, these items were discussed at the exit interview and were considered as unresolved items by the NRC inspector.
During this inspection, the NRC inspector was informed that the NRC inspector's concern regarding the water accumulation around anchor bolts was corrected at the time of the NRC inspection.
The other matters relating to the flood damage are contained in a Construction Deficiency Report as required by 10 CFR 50.55(e) and identified in NRC report STN 50-482/79-13-01.
These matters will be addressed in a subsequent report.
The matter concerning water accumulation around anchor bolts is considered closed.
(Closed) Infraction (STN 50-482/79-09):
Failure to Follow Storage Pro-cedures for Reactor Vessel Internals - During the NRC inspection, April 23-26, 1979, the NRC inspector observed that five deficiencies noted on upper and lower internals storage in QC inspection report 052 were not documented in a Deficiency Report (DR) as required by Daniel Procedure QCP-1-01, Revision 5.
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In a written response to the above infraction, dated July 6, 1979, the licensee stated that corrective measures included the following:
Storage Surveillance Reports initiated prior to May, 1979, are being
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reviewed to assure DRs are written as required.
Revision 6 to QCP-I-01 has been issued to clearly define when
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Deficiency Reports are to be initiated for failure to provide and maintain a proper storage environment.
A training class was conducted for the responsible Quality Control
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Inspectors on May 3, 1979, relative to the requirements of QCP-I-01, Revision 6.
During this inspection, the NRC inspector made a review of surveillance reports versus comparable DRs to verify conformance with Daniel Procedure QCP-I-01, Revision 6, Section 4.2.2.1.
In addition, the NRC inspector observed that QC training records reflect a May 3, 1979, training session for QC inspectors on QCP-I-01, Revision 6, dated May 2, 1979.
This matter is considered closed.
(Closed) Unresolved (STN 50-482/78-08-04): Audit Program Effectiveness -
During an NRC inspection of the licensee's QA Audit Program conducted during the period June 19-23, and July 11-28, 1978, the NRC inspector reviewed audit reports and held discussions with the licensee represen-tative in order to evaluate the adequacy and effectiveness of the site audit program. At the conclusion of the NRC inspection, the NRC inspector indicated that the area of inspection required additional review pending receipt of the licensee QA Staffing Plan.
During this inspection, the NRC inspector observed that a special team inspection of the licensee and contractor programs for control of quality assurance, conducted September 28 - October 2,1981, (STN 50-482/81-05) included the area of CA staffing and QA auditing activities which resolves tr.is item.
This inatier is considered closed.
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Site Tour In conjunction with the Caseload Forecast Panel 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.
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Ca3eload Forecast Panel Meetings Meetings were held on November 17 and 19, 1981, in Burlington, Kansas, with representatives of the licensee to discuss the status of construction of
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the Wolf Creek facility.
An assessment was made to determine a fuel load date in order to establish NRC manpower requirements for the review of the Wolf Creek operating license application.
In a letter dated November 13, 1981, to Harold R. Denton, Director, Office of Nuclear Reactor Regulation, KG&E indicated that a recent evaluation of construction progress resulted in a new fuel load date of December, 1983, rather than the previous schedule of December,1982.
At the conclusion of the Caseload Forecast Panel review, and at the meeting held in Burlington, Kansas, on November 19, 1981, the NRC Forecast Panel members stated that the assessment by the Panel members indicated that although a fuel load date of December, 1983, was attainable, a projected date of July,1984, would appear to be more feasible.
The Panel members indicated that the major consideration in their assessment was the status and rate of installation of large bore pipe hangers, conduit, and instrumentation; notwithstanding an impressive early preparation and manage-ment controls in the startup organizational area.
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Exit Interview In addition to the Caseload Forecast Panel exit meeting on November 19, 1981,
the NRC inspector met with the licensee representatives (denoted in para-graph 1), and the NRC Resident Reactor Inspector, T. E. Vandel, on November 5,1981, and summarized the scope and findings of the inspection.
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