ML20082J085

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Proposed Tech Specs Re Administrative Changes to License DPR-40
ML20082J085
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 04/07/1995
From:
OMAHA PUBLIC POWER DISTRICT
To:
Shared Package
ML20082J078 List:
References
NUDOCS 9504180096
Download: ML20082J085 (6)
v • d • e


Text

I 5.0 ADMINISTRATIVE CONTROLS i

.5.5.1.7* b. Render determinations in writing with regard to whether or not each item considered under 5.5.1.6(b) through (f) above constitutes an unreviewed safety question.

c. Provide immediate written notification to the Division Manager - Nuclear Operations and the Safety Audit and Review Committee of disagreement between the Plant Review Committee and the Manager - Fort Calhoun Station; however, the Manager - Fort Calhoun Station shall have  ;

responsibility for resolution of such disagreements pursuant to 5.1.1 I above. l Records 5.5.1.8 The Plant Review Committee shall maintain written minutes of each meeting and l copies shall be provided to the Division Manager - Nuclear Operations and l Chairperson of the Safety Audit and Review Committee.

5.5.2 Safety Audit and Review Committee (SARC) l Function i

5.5.2.1 The Safety Audit and Review Committee shall function to provide the independent 1 review and audit of designated activities in the areas of:  ;

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a. nuclear power plant operation
b. nuclear engineering
c. chemistry and radiochemistry
d. metallurgy
e. instrumentation and control
f. radiological safety
g. mechanical and electrical engineering
h. quality assurance
i. fire protection -

Comoosition 5.5.2.2 The Safety Audit and Review Committee shall be composed of :

Chairperson: Divisica hh=ger Nac!cc.: Scr/ ice: $51ddsfi6sid@

Member: Senier Vice President Member: '/ ice I're:;; den: Divisi6hjMa'n ags@d61sESgvices]

Member: Division Manager - Nuclear Operations Member: Division Manager - Production Engineering Member: Manager - Fort Calhoun Station Member: Other qualified OPPD personnel Eist/or consultants as required and as determined by the SARC Chairpersor. m ,o y y ,

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  • i; OL/) E ") V l 5-5 Amendment N 93,"),101, 115,119,132,141,149,157,150 9504180096 950407 PDR ADOCK 05000285 P PDR

D.S. Nuclear Regulatory Comission LIC-95-0082 ATTACHMENT B

DISCUSSION, JUSTIFICATION AND NO SIGNIFICANT HAZARDS CONSIDERATIONS DISCUSSION AND JUSTIFICATION:

Omaha Public Power District (OPPD) is proposing to revise the Fort Calhoun Station Unit No.1 Technical Specifications (TS) to implement administrative The changes are administrative in nature and changes to TS 5.2 and 5.5. reflect organizational changes in OPPD Senior Manageme titles of personnel serving on the Plant Review Committee (PRC), revise the makeup of the PRC quorum, revise the membership of the Safety Audit and Review Committee (SARC), delete SARC audit frequencies Also, and theadd minor clarifications amendment numbers to the descriptions of SARC reviews and audits.

listed at the bottom of each page were reviewed and revised as necessary to t

show previous amendments that were inadvertently deleted and correct a typographical error.

f Administrative Chanaes Specifications 5.2.1. 5.5.2.8. 5.5.2.9 & 5.5.2.10 Due to an organizational change in OPPD Senior Management, the SeniorAVice Vice President is no longer responsible for OPPD's nuclear organization.

President has assumed the nuclear related duties and responsibilities heretofore held by the Senior Vice President. Consequently, these Specifications are being changed to reassign these duties and responsibilities from the Senior Vice President to the Vice President.

Specifications 5.5.1.2. 5.5.1.3 & 5.5.1.5 The specific titles of PRC members are proposed for deletion fromThe titles will Specification 5.5.1.2. The members PRC shall contain at least six but not more than eleven members.

shall be either department heads or " supervisory staff" representing operations, maintenance, engineering, chemistry, radiation protection and Supervisory other technical disciplines as determined by the PRC Chairman.

staff consists of professional-technical personnel qualified to ANSI N18.1- The 1971, Section 4.4 standards, department heads and shift supervisors.

proposed change is similar to changes already approved by the NRC for River Bend Station, Unit No. 1 (Amendment 61 to Operating License NPF-47).

The limitation on the number of alternates (2) allowed to participate in PRC Specification activities is proposed for deletion from Specification 5.5.1.3.

5.5.1.5 is proposed for revision to allow an Alternate Chairman and restrict the number of alternates participating as voting members in PRC activities to a minority of the quorum. These changes will facilitate the conduct of PRC meetings yet assure adequate management oversight by restricting the number of alternates participating as voting members in PRC activities to a minority of the quorum.

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8ISCUSSION AND JUSTIFICATION: (Continued)

Soecification 5.5.2.2 \

The membership of the SARC is being revised to reflect the Senior Vice  ;

President as the Chairperson (presently a member of the SARC) and the Division Manager - Nuclear Services as a member (presently the Chairperson).

Additionally, the membership is being clarified by adding the word "and" to l indicate that membership may be from qualified OPPD personnel "and/or" consultants.

I Soecifications 5.5.2.7 & 5.5.2.8 Minor clarifications to the descriptions of SARC reviews and audits are proposed for Specification 5.5.2.7 and 5.5.2.8. Also, the frequencies associated with SARC audits are being deleted from Specification 5.5.2.8.  !

The audit frequencies will be maintained in accordance with the NRC approved )

Quality Assurance (QA) Program. Any changes that could reduce the effectiveness of the QA Program must be approved by the NRC in accordance with 10 CFR 50.54(a)(3). This proposed change is similar to changes already 1 approved by the NRC for the South Texas Project, Units 1 and 2 (Amendments 56 i and 45 to Operating Licenses NPF-76 and NPF-80 respectively).

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hASIS FOR NO SIGNIFICANT HAZARDS CONSIDERATION:

The proposed changes do not involve significant hazards considerations because l operation of Fort Calhoun Station Unit No.1 in accordance with these changes I would not 1

(1) Involve a significant increase in the probability or consequences of an accident previously evaluated.

The proposed changes are administrative changes to reflect organizational changes in Omaha Public Power District (0 PPD) Senior Management,' remove specific titles from the membership of the Plant Review Committee (PRC), revise the membership of the Safety Audit and ,

Review Committee (SARC), add minor clarifications to SARC reviews and I audits and delete statements concerning the frequency of SARC audits I from the Technical Specifications (TS).

The proposed change to revise the overall corporate responsibility for plant nuclear safety from the Senior Vice President to Vice President is ,

administrative in nature as it only reflects an organizational change. l Section 12 of the Updated Safety Analysis Report describes the management structure and reporting responsibilities of OPPD. Section 12 provides an organizational chart to differentiate the Vice President-in charge of nuclear activities from other Vice Presidents within OPPD.

Therefore, changing the corporate reporting responsibility does not involve a significant increase in the probability or consequences of an accident previously evaluated.

The proposed changes to the membership of the PRC and SARC are administrative in nature since only the specific titles of the members are being removed from the TS for the PRC, and a different member is assuming the position of Chairperson for the SARC. The management level and expertise of personnel who are PRC or SARC members is not being changed. The review of plant operations is still required to be in compliance with ANSI N18.7-1976 and Regulatory Guide 1.33, Revision 2, as committed to in the Fort Calhoun Station Quality Assurance (QA)

Program. Any changes in the QA Program which reduce the effectiveness of the program must be approved by the NRC in accordance with 10 CFR 50.54(a)(3). Therefore, the proposed changes to the membership of the PRC and SARC do not involve a significant increase in the probability or consequences of an accident previously evaluated.

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NASISFORNOSIGNIFICANTHAZARDSCONSIDERATION: (Continued)

Clarifications of SARC reviews and audits and the. deletion of SARC audit i

frequencies from the TS are administrative changes. The audit ]

frequencies are required by the NRC approved QA Program and any changes  ;

that could reduce the effectiveness of the QA Program must be approved  :

by the NRC in accordance with 10 CFR 50.54(a)(3). Therefore, the '

clarifications and deletion of the specific audit frequencies do not  !

involve a significant increase in the probability or consequences of an  ;

accident previously evaluated.

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. (2) Create the possibility of a new or different kind of accident from any L accident previously evaluated.

1 The proposed changes are administrative in nature to reflect organizational changes in OPPD Senior Management, remove specific titles

, from the membership of the PRC, revise the membership of the SARC, 4

provide minor clarifications of SARC reviews and audits and delete

statements concerning the frequency of SARC audits from the TS. The proposed changes'do not revise any equipment setpoints, change the

, manner in which any plant equipment is operated, or propose any new _

operating modes. :Therefore, the proposed changes do not create the possibility of a new or different kind of accident.from any accident

previously evaluated.

I I (3) Involve a significant reduction in a margin of safety.

! The proposed changes revise organizational and administrative requirements contained within the Administrative Controls section of the  ;

TS. The proposed changes do not revise any equipment setpoints, change  !

. the manner in which any plant equipment is operated, or propose any new l 4 operating modes. Therefore, the proposed changes do not involve a

significant reduction in a margin of safety.

4 Therefore, based on the above considerations, it is'0 PPD's position that this proposed amendment does not involve significant hazards considerations'as defined by 10 CFR 50.12 and the proposed changes will not result in a

condition which significantly alters the impact of.the Station on the environment. Thus, the proposed changes meet the eligibility criteria for i categorical exclusion set forth in 10 CFR 51.22(c)(9) and pursuant to 10 CFR
51.22(b) no environmental assessment need be prepared.

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