IR 05000267/1982003
| ML20050D510 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 03/23/1982 |
| From: | Boardman J, Crossman W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20050D501 | List: |
| References | |
| 50-267-82-03, 50-267-82-3, NUDOCS 8204120268 | |
| Download: ML20050D510 (6) | |
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APPENDIX U. S. NUCLEAR REGULATORY COMMISSION
REGION IV
Report No. 50-267/82-03 Docket No. 50-267 License No. DPR-34 Licensee:
Public Service Company of Colorado P. O. Box 840 Denver, Colorado 80201 Facility Name:
Fort St. Vrain Nuclear Generating Station Inspection At:
Fort St. Vrain Site, Platteville, Colorado Inspection Conducted:
February 22-26, 1982 3[7.3[97, Inspector:
N RV Boardman, Reactor Inspector Date
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25/86 Approved:
W. A. Crossman, Chief Date Reactor Project Section B Inspection Summary Inspection Conducted During'The Period of February 22-26, 1982 Report 50-267/82-03 Areas Inspected:
Routine, uncnnounced inspection including annual review of licensee QA program, licensee organization and administration, licensee onsite review committee, and follow-up action on previous inspection findings.
The inspection involved 34 inspector-hours by one NRC inspector.
8204120268 820326 PDR ADOCK 05000267 G
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Details 1.
Persons Contacted
- M. Block, Superintendent of Operations
- T. Sorst, Radiation Protection Manager
- B. Burchfield, Results Engineering Supervisor M. Ferris, Supervisor, QA Technical Support
- W. Franek, Nuclear Site Engineering Manager C. Fuller, Technical Services Engineering Supervisor
- J. Gahm, Quality Assurance Manager
- F. Hill, Station Manager V. Lucero, Chemistry Supervisor
- M. McBride, Technical /Admistrative Services Manager M. Murphy, Training Instructor F. Novachek, Reactor Engineer
- L. Singleton, Supervisor, QA Operations R. Wadas, Training Supervisor
- D. Warembourg, Manager, Nuclear Production
- Denotes those persons present at the exit interview.
The NRC inspector also contacted other licensee personnel, including administrative and quality assurance personnel.
2.
Licensee Action on Previous Inspection Findings (Unresolved) Unresolved Item (8123-01) The apparent timeliness of comple-tion of corrective actions by the licensee had not substantially improved, though a program is now in effect which should provide requisite licensee visibility to permit meaningful management evaluation necessary to assure timely completion of corrective action responses.
Of the 151 open items identified before February 1, 1982, on the licensee's Open Corrective Action Action Request (CAAR) report dated February 13, 1982, 56 were past their closecut action target date.
An additional 15 open items had no target date; the report identified that 7 of these 15 had passed the target date and no new date had been committed.
The oldest open item identified by the inspector (CAla 214).had the original action initiated in 1975 according to licensee personnel.
All action on this item is now complete based on a discussion with licensee personnel.
There were a total of 167 open CARRs,on~the licensee's report, compared with 162 identified in NRC Inspection Report 81-23 of an inspection performed October 13-16,'1981.
This item remains an unresolved item.
3.
Licensee QA Program Annual Review The NRC inspector reviewed the following procedure revisions which had been made since NRC Inspection Report 81-10.
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Procedure Issue Effective Number Subject Number Date Q-3 Design Control
12/07/81 Q-4 Procurement Document Control
10/30/81 Q-9 Control of Special Process
10/30/81 Q-10 Inspection
05/18/81 Q-11 Test Control
12/29/81 Q-12 Control of Measuring Equipment
05/18/81 Q-17 FSV Station Vital Records
01/13/82 Q-18 QA Audit and Monitoring Program
12/07/81 G-2 FSV Procedure Systems
02/03/82 G-3 Action Request-Preparation and Processing
10/28/81 P-1 Plant Operations
02/19/82 These procedure revisions appear to be in conformance with the licensee's approved QA program and Technical Specifications.
Paragraph 2 discusses the review of the licensee's corrective action program of the QA program covered by licensee procedure G-3.
No violations or deviations were identified.
4.
Licensee Organization and Administration On February 25 and 26, the NRC inspector verified that the licensee's onsite organizational structure, personnel qualification and lines of authority were in accordance with the applicable Technical Specifications and standards.
No violations or deviations were identified.
5.
Onsite Review Committee On February 24, the NRC inspector attended a licensee Onsite Review Committee (PORC) meeting as a non-participant and observer.
The inspector verfied compliance with Technical Specification requirements relative to membership and frequency.
The NRC inspector also reviewed the minutes of PORC meetings #435 (week of October 19, 1981), #441 (week of November 30, 1981), and #450 (week of February 1 1982) for compliance with Technical Specification requirements.
No violations or deviations were identified.
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6.
Temporary Plant Configuration Control As an ancillary inspection to the licensee's Onsite Review Committee (PORC) and QA program, the NRC inspector reviewed the licensee's control of temporary plant configurations as set forth in procedure P-1, " Plant Operations," with the following findings:
a.
On February 24 and 25, the NRC inspector identified approximately 135 temporary plant configurations for the year 1975, for which records are not on file and no documentation existed that these temporary configurations were restored to normal.
This number does not include those temporary plant configurations which are identified as still open and for which documentation exists.
b.
On February 23, 24, and 25, the NRC inspector identified numerous missing records of temporary plant configuration which licensee personnel subsequently stated were misfiled because of apparently inadequate instructions to records center personnel, c.
Licensee " Temporary Configuration Report" (TCR), Attachment P-lJ, Issue 5, of licensee procedure P-1 requires verification of PORC review and approval by ascription of a signature, date, and meeting number in the appropriate blanks. Open TCR 80-8-53 did not have PORC review / approval indicated nor a signature.
The NRC inspector verified that this TCR was included in the minutes of PORC meeting 376.
d.
The licensee records control system requires retention of document-ation of temporary plant configurations for only 5 years, though some temporary configurations have been in effect for over 6 years.
e.
Licensee procedure P-1 does not specifically require PORC review of safety significant temporary configurations as required by licensee Technical Specification AC7.1.2.e.4.
Licensee CAAR 149 documents the only case found by the inspector where PORC review was not accomplished as required for TCR 81-2-9.
f.
CAAR 149 also documents that the Safety Evaluation Report (SER) for TCR 81-8-9 had been destroyed in violation of licensee Technical Specification Amendment 16, Section 7.3-3(10).
Licensee personnel stated that SERs were not thrown away, but retained by plant maintenance personnel.
TCRs for 1981 were still being reviewed by licensee Results Engineering.
Numerous SERs were not attached to the appropriate TCRs, but Results Engineering personnel stated they would be attached to required TCRs prior to transmittal to permanent records storage.
The NRC inspector identified approximately 10 missing SERs and these were obtained by licensee personnel on February 26.
It is noted t
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that licensee procedure requires that completed TCRs be sent by the requesting department to the Records Center, not to Results Engineering for transfer annually.
The above findings indicate numerous apparent weaknesses in the licensee's control of temporary plant configurations.
Licensee control of temporary plant configurations will remain an unresolved item (8203-01) pending analysis by the licensee that there are no installed temporary plant configurations not presently controlled as
" installed" which are important to safety and pending licensee clarification of related procedures.
7.
Unresolved Item An unresolved item is a matter about which more information is required in order to ascertain whether it is an acceptable item, a violation, or a deviation.
An unresolved item disclosed during this inspection is discussed in paragraph 6.
8.
Exit Interview An exit interview was conducted on February 26, 1982, with members of the licensee's staff as denoted in paragraph 1.
The NRC Senior Resident Reactor Inspector also attended.
The NRC inspector's observations and findings noted in the foregoing paragraphs were discussed.
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