ML20150A996

Safety Evaluation Supporting Amend 115 to License DPR-40

ML20150A996
Person / Time
Site:	Fort Calhoun
Issue date:	07/01/1988
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20150A974	List: ML20150A971 ML20150A992 ML20150A996
References
NUDOCS 8807110198
Download: ML20150A996 (4)

Text

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[ga arog'o UNITED STATES  !

! [g n NUCLEAR REGULATORY COMMISSION l

$ fr $ WASHINGTON, D. C. 20555 r.....J I SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.115 TO FACILITY OPERATING LICENSE NO. OPR-40 OMAHA PUBLIC POWER DISTRICT FORT CALHOUN STATION, UNIT NO. I DOCKET N0. 50-285

1.0 INTRODUCTION

By letter dated May 23, 1988, Omaha Public Power District (0 PPD) requested changes to the Administrative Controls Section of the Technical Specifica-tions (TS) for the Fort Calhoun Station, Unit 1. A supplemental letter dated June 7, 1988, provided additional position changes not included in the previous submittals. The proposed changes incorporate recent job title and administrative changes, changes in the composition of the onsite and offsite review comittees, and the replacement of the organizational charts presently in the TS with more general organizational requirements.

The propcsed change wculd remove Figures 5-1, OPPD Support Staff, and E-2,  ;

Fort Calhoun Station Organizational Chart. Must of these elements are already required by regulation, other TS, or the Updated Safety Analysis Report, as described below. These general requirements describe the organizational features that were depicted in the charts that are important to the NRC for ensuring that the plant would be operated safely. Guidance for these proposed changes to the TS was provided to licensees and applicants by Generic Letter 88-06, dated March 22, 1988.

2.0 EVALUATION l

The licensee's proposed changes to its TS are in accordance with the guidance provided by Generic Letter 88-06 and addressed the items listed below.

(1) Specifications 5.2.1 and 5.2.2 were revised to delete the references to Figures 5-1 and 5-2 that were removed from the TS.

(2) Functional requirements of the offsite and onsite organizations were defined and added to Specification 5.2.1, and are consistent with the guidance provided in Generic letter 88-06. The specification notes that the implementation of these requirements is documented in the Updated Safety Analysis Report (USAR),

(3) The Supervisor - Operations, the Shift Supervisors, and the Licensed Senior Operators of the unit staff were added to Specification 5.2.2.

Therefore, this requirement that was identified on the Figure 5-2 for the station organizational chart will be retained.

88071101o8 8807o1 PDR P ADOCK 05000285 PDC

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1 (4) The licensee has confirmed that no specifications, other than those noted above, include references to the figures that are being retroyed from the TS. Hence, this is not an applicable consideration with regard to the need to redefine referenced requirements as a result of the removal of these figures.

The licensee proposes to revise the composition of the Plant Review Comittee (PRC) and the Safety and Review Comittee (SARC) to reflect changes in the organizational structure at OPPD.

The composition of the PRC will change as follows:

(1) The positions of Supervisor - Technical, Supervisor - Instrument Control and Electrical, and Plant Engineer have been tieted. The Manager - Training, Supervisor - Systens Engineering, and Plant Chemical are added in their place.

(2) The Manager - Safety Review Group has been substituted for the Peactor Engineer.

(3) The Supervisor - Chemistry and Radiation Protection h6s been changed to Supervisor - Radiation Protection.

(4) The position of Manager - Quality Assurance and Quality Control j has been added to the PRC. This increases the membership by '

one member.

The composition of the SARC will change as follows:

(1) The position of Division Manager - Quality Assurance and Regulatory Affairs has been changed to Division Manager - Quality and Environmental Affairs.

(2) The position of Division Manager - Engineering has been changed to Division Manager - Production Engineering.

i (3) The position of Vice President - Engineering and General Services has been deleted as a member.

(4) The position of Manager - Fort Calhoun Station has been substituted for the member from OPPD Operations, Engineering, and Technical Support staff.

(5) The position of Manager - Emergency Planning has been added to the SARC.

The licensee has additionally proposed several job title and administrative changes as noted below:

(1) The title of Division Manager - Nuclear Production has been chanced to Division Manager - Nuclear Operations.

i (2) The title of Supervisor - Station Training has been changed to Manager - Training. The reference to Appendix A of 10 CFR Part 55 l for the requirements of this po:ition has been clarified to '

reference only 10 CFR Part 55.

(3) The title of Senior Vice President - Nuclear Production, Producticn Operations, Fuels, and Quality Assurance & Regulatory Affairs has been changed to Senior Vice President - Nuclear Operations, Production Engineering, and Quality and Environmental Affairs.

(4) The title of Supervisor'- Chemical and Radiation Protection has been changed to Supervisor - Radiation Protection. This change results from the division of the original position into the newly titled position and Plant Chemist.

(5) The respcnsibility for the training program for the fire brigadc that was under the Manager - Fort Calhoun Station now is under the Manager - Training.

On the basis of its review of the above items, the staff concludes that the licensee has provided an acceptable response to these items as addressed in NRC guidance en renoving organizational charts from the administrative control requirements of the TS. Furthermore, the staff finds that these changes are censistent with the staff's generic finding on the acceptability of such changes as noted in Generic Letter 88-06.

The remaining changes were found to neet the acceptance criteria of Section 13.1 of NUREG-OSCO, the Standard Review Plan. Accordingly, the staff finds that each cf the proposed changes to be acceptable.

?.0 ENVIRONMENTAL CONSIDERATION The amendment relates to changes in recordkeeping, er administrative pro-cedures or requirements. Accordingly, the amendment meets the eligibilitv criteria for categorical exclusion set forth in 10 CFR Section 51.22(c)(l'0).

Pursuant to 10 CFR 51.?2(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.

4.0 CONCL USION The Comission made proposed determinations that the amendments involve l no significant-hazards consideraticn, which was published in the Federal l Register (53 FR 19835) on May 31, 1988. The Comission consulted with the State of Nebraska. No public comnents were received, and the State of Nebraska did not have any comments.

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The staff has concluded, based on the considerations discussed above.

-that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (2) such activities will be conducted in compliance with the Comission's regulations, and the issuance of the amendment will not be inimical to the comon defense and security or to the health and safety of the public.

Principal Contributor: P. Milano Dated: July 1, 1988 -

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