ML20235N649

Safety Evaluation Supporting Amend 56 to License DPR-34

ML20235N649
Person / Time
Site:	Fort Saint Vrain
Issue date:	07/13/1987
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20235N614	List: ML20235N612 ML20235N644 ML20235N649
References
TAC-56743, NUDOCS 8707200162
Download: ML20235N649 (4)

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UNITED STATES l g y g NUCLEAR REGULATORY COMMISSION

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g ..... j 1 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR R'tGULATION SUPPORTING AMENDMENT NO. 56 TO FACILITY OPERATING LICENSE NO. OPR-34 PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION DOCKET NO. 50-267 1.0' INTRODUCTION AND BArfGROUND By letter dated July 22, 1986,.Public Service of Colorado (PSC) requested changes to the. Administrative Controls Section of the Technical Specifications for Fort St. Vrain' Nuclear Generating Station'(FSV). PSC requested additional changes to the Technical Specifications by letter dated December 5, 1986. ,

i The staff evaluated the changes requested by' the letter of July 22, 1986, and requested further information. PSC has provided additional information'in Revision 4 of their updated FSAR with respect to the organizational changes but not to the changes to the Plant ~ Operations Review Committee (PORC) composition. By letter dated December 5, 1986, the staff requested additional information regarding the PORC

• quorum and continuity of operation. Hcwever, PSC has not responded to this letter. Therefore, the PORC item remains open. Following is a brief description and our evaluation of the proposed changes, except for the changes to the PORC.

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2. 0 EVALUATION

1. Figure 7.1 PSC has reorganized' the corporate _ organization that supports the operation of the FSV. This change deletes j the Maintenance and Engineering Services Division and the Pro- '

duction Fuels and Services Division. A new Division of Nuclear Licensing and Fuels.has been established. Additionally, the new j position of Vice President, Nuclear Operations has assumed the 'i responsibility for all nuclear operations and reports to the ~

Chairman and Chief Executive Officer. Formerly the President, Electric Production was responsible for nuclear operations. The membership of the Nuclear Facilities Safety Committee (Sec-tion 7.1.3) has been changed to reflect the revised organi-zation.

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4 We find these changes acceptable as they do not delete the .

necessary technical support for FSV and they meet the acceptance '

criteria of Section 13.1 of NUREG-0800, the Standard Review Plan.

2. Figure 7.1 PSC has revised the plant staff organization.

The new position of Support Services Manager has been created. j This new position is responsible for the radiation protection functions under a Health Physics Supervisor, and the training function under the new position title of Superintendent Train-ing. A new position of Superintendent Scheduling / Planning and Stores'has been established that reports to the Station Manager. A The two functional blocks titled I&C Supervisor have been com-bined into one block titid I&C Supervisors. Title changes have been made;throughout the Technical Specifications to.

l reflect the re ised orgf.ization."

We find these proposed changes acceptable as they do not delete any of the technical support currently reporting tn the Manager, '

Nuclear' Production Division.

3. Section 7.1.2.1 - (PORC Responsibilities)'- PSC proposes to delete 'l fromthissectionthe,referencetothe'FSVjiecurityCommittees We find this change acceptable as thersta'ff does'not require that changes to'the FSV Plant Security Plan be submitted to the FSV Plant Security Committee as a Technical Specification req'irement. u ,

The titles for the members of PORC'have been changed to reflect '

the organizational changes discussed above. <

4. Section 7.1.3 (Nuclear. Facilities Safety Committee)(

a. PSC proposes to 7 restate the function of the Nuclear Facilities Safety Committee (NFSC) from the present wording that is the same as the Standard Technical Specifications ,

to conform more closely with the wording of Section 4 of i

.j ANSI N18.7-1972.

IWe" find this proposal acceptable as Regulatory Guide 1.33 endorses ANSI.W18,7-1972.

b. PSC proposes to revise the membership of the NFSC to reflect a change of the title of the Manager, Risk Manage-ment to Safety and Security Director.

We find this proposed change acceptable as it reflects only a title change.

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c. PSC proposes to add a new subsection 7.1.3.4 - Chairman -

that states that the Chairman and Alternate Chairman of the NFSC shall be appointed in writing by the Vice President, Nuclear Operations and shall serve as members of the NFSC. Because of the new subsection, former sub-sections 7.1.3.4, 7.1.3.5, 7.1.3.6, 7.1.3.7, 7.1.3.8 and 7.1.3.9 have been relabeled 7.1.3.5, 7.1.3.6, 7.1.3.7, 7.1.3.8, 7.1.3.9 and 7.3.10 respectively.

We find the proposed addition of the new subsection

. 7.1.3.4 acceptable since the appointment of the NFSC is done by a high level company official and the change ,i does not compromise the continuity of the members of the NFSC from one meeting to the next.

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d. PSC has added a new subsection 7.1.3.8.b, Items 1, 2 and 4 i that require NFSC approval of certain safety issues. The l

former subsection 7.1.3.8.b has been renumbered 7.1.3.8.c.

l We find this proposed change acceptable as it is an addi- j tional requirement over and above the normal NFSC function. )

1 5. Section 7.4.b (Procedures, Administrative controls) - PSC pro-

proposes to delete the. reference to the FSV Security Committee.

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We find this proposed change acceptable as Security Plan pro- 1 cedures and changes thereto will continue to be reviewed by l the PORC. l

4.0 ENVIRONMENTAL CONSIDERATION

The amendment relates to changes in recordkeeping, reporting or administrative procedures or requirements. The staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that this amendment involves no significant hazards consideration and there has been no public comment on such finding. Accordingly, this amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR SSI.22(c)(10). Pursuant to 10 CFR $51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of this amendment.

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\ . 5. 0 CONCLUSION 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 Commission's regulations and the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.

1 Dated: July 13,1987 Frincipal Contributor: F. Allenspach, PEB/DLPQE l

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