IR 05000285/1988201

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Discusses Safety Team Insp Rept 50-285/88-201 on 881031-1110 & Forwards Notice of Violation
ML20247B466
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 03/17/1989
From: Callan L
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To: Morris K
OMAHA PUBLIC POWER DISTRICT
Shared Package
ML20247B471 List:
References
NUDOCS 8903290403
Download: ML20247B466 (3)


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-In Reply Refer To:- .

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Docket: 50-285/88-201--

.0maha.Public Power District ATTN: . Mr.' Kenneth d. Morris

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Division Manager - Nuclear Operations

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1623 Harney. Street Omaha, Nebraska. 68102

, Gentlemen:

This refers to the Operational Safety Team Inspection l(OSTI) conducted by Mr. "J. E. Cummins and other NRC personnel from October 31 through November 10, 1988,. of activities authorized by NRC Operating. License DPR-40 'for the Fort Calhoun Statio The report and executive summary describing this inspection were forwarded to I you by separate letter dated February 9,1989, from Gary M.. Holahan of the 0fficelof. Nuclear Reactor Regulatio I The inspection report identified 20 unresolved items:which. required further NRC review to determine whether or not NRC regulations had been violated. . i Following a review and evaluation of:these unresolved items, it has been ,

determined that 14'of.the. activities identified as unresolved items were in l violation of'NRC requirements and are included in the 6 violations in the 1 enclosure to this' letter. Consequently,'you are required to respond to-these  :

. violations, in writing, in accordance with the provisions of Section- 2.201 of

- the NRC's " Rules of Practice," Part 2, Title 10 Code of Federal- Regulation Your response should be based on the specifics contained in the Notice of .

Violation enclosed with~this lette In addition to the response ' directed by the above paragraph, you are requested l-to include in your reply, a statement regarding the actions to be taken or l planned, for the unresolved items-listed below:

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' Inaccurate entry of information into the temporary modification lo (285/88201-04)

. Operability of the steam generator blowdown radiation monitor l (285/88201-06)

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Plant review committee review of temporary modifications within 14 day (285/88201-08)

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. The control room indication for Valves HCV-1107B and HCV-11088 was not tested. (285/88201-18)

., Quality assurance reviewed Procedure ST-DC-1 which had the acceptance criteria deleted and the quality assurance auditor did not identify the discrepanc (285/88201-23)

In a letter dated November 23, 1988, the NRC identified an item related to your practice of providing operating instructions in operations memoranda which should have been included in the appropriate documented procedures. This concern was identified as an item that must be completed prior to startup from the 1988 refueling outage. A review was performed of this item by the NRC resident inspectors prior to plant startup. The results of the review is documented in NRC Inspection Report 50-285/89-0 Because the review found that you had taken satisfachry action with respect to this item, no response is required for Violation B.2 (Unresolved Item 285/88201-03). Also, as a-result of the violation issued in NRC Inspection Report 50-285/89-03 concerning drawing control for temporary modifications, a response to Unresolved Item 285/88201-07 was not requested, since it is our understanding that your i'

response to the violation will address this issu In addition to responding to the items identified above, you may, if desired, respond to any open item discussed in the inspection report. The response directed by this letter and the accompanying Notice is not subject to the clearance procedures of the Office of Management and Budget as required by the Papemork Reduction Act of 1980, PL 96-51 Should you have any questions concerning this inspection, we will be pleased to discuss them with yo

Sincerely,

&&al kned B)+

A;B. BEACH L. J. Callan, Director Division of Reactor Projects Enclosure:

Appendix - Notice of Violation cc w/ enclosure:

W. G. Gates, Manager Fort Calhoun Station P.O. Box 399 '

Fort Calhoun, Nebraska 68023

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Harry H. Voigt,' Esq.m .

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Washington, DC 20036 Nebraska Radiation; Control Program Director RIV: bectoDMB-(IE01);

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