ML20134D083
| ML20134D083 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 08/09/1985 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20134D082 | List: |
| References | |
| NUDOCS 8508190058 | |
| Download: ML20134D083 (4) | |
Text
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E o,i, UNITED STATES i
NUCLEAR REGULATORY COMMISSION l
- E WASHINGTON, D. C. 20555
%...,.. )
t SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION l
SUPPORTING AMENDMENT NO. 94 TO FACILITY OPERATING LICENSE NO. DPR-59 POWER AUTHORITY OF 7FE STATE OF NEW YORK JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333
1.0 INTRODUCTION
The Power Authority of the State of New York (PASNY, the licensee) has requested, by letter dated February 22, 1985, changes to the Administrative Controls Section of the Technical Specifications for the James A.
FitzPatrick Nuclear Power Plant. Below is a brief description and our evaluation of the changes.
2.0 DISCUSSION A.
A proposed change to Section 6.5-1 would clarify the responsibility of the Plant Operations Review Conunittee (PORC) to include review of
+he Safeguards Contingency Plan as a part of the PORC review of the Security Plan.
B.
The Saf
.eview Consnittee (SRC) membership is to be revised to include a next-to-highest level management in the Nuclear Generation, Engineering and Quality Assurance, and Reliability Departments. The existing and proposed membership of the SRC are shown below.
Present:
Chairman:
Manager-Nuclear Safety Evaluation Vice-Chairman:
Vice President-Quality Assurance Member:
Vice President Nuclear Support-BWR Member:
Vice President Nuclear Support-PWR Member:
Manager-Radiological Health and Chemistry Member:
Director-Nuclear Design and Analysis Member:
Director-Electrical Design and Analysis-Member:
Director of Environmental Programs Member:
Director-Civil / Structural Design and Analysis Member:
Director-Mechanical Design and Analysis Member:
Director-Piping and Process-Design and Analysis Member:
Manager Operational Analysis and Training s
P
. Proposed:
4 Chairman:
Manager-Nuclear Safety Evaluation Vice-Chairman:
Director-Quality Assurance Member:
Vice President Nuclear Support-BWR Member:
Vice President Nuclear Support-PWR Member:
Vice President-Generic Nuclear Support Member:
Vice President-Design and Analysis Member:
Resident Manager-IP-3 Member:
Resident Manager-JAF Member:
Consultant This change in the committee membership reduces the committee to nine (9) voting members. Title changes have been made throughout Section 6 to reflect the new membership.
I C.
The SRC's function described in Section 6.5.2.1 has been modified to be consistent with NUREG-0123, Revision 3. " Standard Technical Specifications for Boiling Water Reactors." The specific change is shown below:
Present:
6.5.2.1 The SRC shall collectively have the competence required to review problems in the following areas:
Proposed:
6.5.2.1 The SRC shall function to provide independent review and audit of designated activities in the areas of:
3.0 EVALUATION A.
The proposed revision described in Item A above is a clarification of the responsibilities currently assigned to the PORC and would not decrease the duties of the PORC as now described in the plant Technical Specifications. Furthermore, the revision is not inconsistent with the wording of the Standard Technical Specifications for Boiling Water Reactors NUREG-0123, Revision 3.
Accordingly, we find the change acceptable.
B.
The staff considered the safety implications of the removal of the Design and Analysis Directors from the membership of the Safety Review Committee.
For the following reasons, it was determined that no measurable decrease in the effectiveness of the SRC would eqcur.
1.
The qualifications of the Vice President (VP) level ma'hagers to be included on the SRC are: A BS in Engineering or Science and 6 years of professional level experience in nuclear services, nuclear plant operations, or nuclear engineering, and the
i.
necessary overall nuclear background to determine when,to call consultants and contractors for dealing with complex problems beyond the scope of the owner-organization expertise. The s
qualifications of the Directors removed from the SRC are: a BS in Engineering or Science and 3 years in design, operation or other related activities of nuclear power plants.
The experience level of the VPs in actual operations, service or engineering of nuclear power plants is acceptable.
2.
The reporting responsibilities of the SRC Chairman are not 4
affected by the SRC membership changes. The Chairman shall s.
continue to report directly to the Executive Vice President-Nuclear Generation.
3.
The implementation of the SRC charter usually relies on outside organizations or the Technical Divisions to perform the actual
~,
review and/or audit for which the SRC is responsible. Therefore, although the Technical Division Directors were removed from the SRC membership, they will, in essence, continue to remain involved with the SRC review process. Moreover, the Directors replaced from the Engineering and Generation Departments will be the alternates to the new VP level voting members from their same departments.
4.
The SRC is an oversight body which ordinarily meets every 6 j
months to review actions and reports that have already been implemented or accomplished.
In most cases, the Plant Operations Review Committee and/or the Independent Safety Engineering Group (ISEG) have previously perfonned reviews of the same actions t
i being reviewed by_the SRC.
5..
The addition of the consultant as a voting member was considered a strength and could bring specific expertise to be used in the resolution of problems, if required.
6.
The reduction in the number of SRC membership from 12 to 9 was considered a strength. The SRC should be more effective in i
bringing about closure of any identified safety issues with the l
smaller number of members and the increased level of decision-making capability.
)
7.
The increased participation of upper management attention and involvement in the safety review process should aid in achieving safe plant operation.
The propcsed change is in accordance with the guidance provided~in Section 13.4 of tne Standard Review Plan, NUREG-0800 and the Standard Technical i
Specifications for Boiling Water Reactors, NUREG-0123 Revision 3.
i Accordingly, the proposed change is acceptable.
. C.
The proposed change described in Item C above is in accordance with the guidance provided in Section 13.4 of the Standard Review Plan, NUREG-0800 and the Standard Technical Specifications for Bolling Water Reactors, NUREG-0123, Revision 3.
Accordingly, the proposed change is acceptable.
4.0 ENVIRONMENTAL CONSIDERATION
S This amendment relates to changes in administrative procedures.
Accordingly, this amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(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.
S'. 0 CONCLUSION
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We have concluded, based on the considerations discussed above, that:
(1) there is reasonable assurance that the health and safety of the will not be endangered by operation in the proposed manner, and (2) public
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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.
Principal Contributor:
L. Crocker Dated: August 9,1985 4
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