ML20235J327

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Application for Amends to Licenses DPR-42 & DPR-60,deleting Requirement for Plant Mgt & Support Staff to Hold Current NRC Senior Operator License
ML20235J327
Person / Time
Site: Prairie Island  Xcel Energy icon.png
Issue date: 08/14/1987
From: Musolf D
NORTHERN STATES POWER CO.
To:
Shared Package
ML20235J242 List:
References
NUDOCS 8710010402
Download: ML20235J327 (7)
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j UNITED STATES NUCLEAR REGULATORY COMMISSION 

                                                          . NORTHERN STATES POWER COMPANY PRAIRIE ISLAND NUCLEAR CENERATING PLANT                         DOCKET NOS. 50-282           -

50-306 , REQUEST FOR AMENDMENT TO OPERATING LICENSES DPR-42 AND'DPR-60 LICENSE AMENDMENT REQUEST DATED AUGUST 14, 1987 l Northern States Power Company, a Minnesota corporation, requests authorization for changes to Appendix A of the Prairie, Island. I Operating Licenses as shown on the attachments labeled Exhibits A, B, and C. Exhibit A describes the proposed changes, describes 

                                                                                                                                                       .i the reasons for the changes, and contains a significant hazards evaluation. Exhibits B and C are copies of the Prairie Island Technical Specifications incorporating the proposed changes.

This letter contains no restricted or other defense infor-mation. ' q NORTHERN STATES POWER COMPANY g :) PDR 292 By Deo th- - P , David Musolf \ k Manager-Nuclear Support: services ] On this /M day of/L*8 d before me a notary public in and for said Countyt7 personally appeared David Musolf, Manag-er-Nuclear Support Services, and being first duly sworn acknowl-edged that he. is authorized to execute this document on behalf of 3 Northern States Power Company, that he knows the contents there- ' of,'and that to the best of.his knowledge, information, and be- j lief the statements made in it are true and that it is not inter-  ! posed.for delay. A 

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i 1 s Exhibit A Prairie Island Nuclear Generating Plant i License Amendment Request Dated August 14, 1987 l I Description and Evaluation of Proposed ' Change to Appendix A of Operating Licenses DPR-42 and DPR-60 

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Pursuant to 10 CFR Part 50, Section 50.90, the holders of Opera-ting Licenses DPR-42 and DPR-60 hereby propose the following changes to Appendix A, Technical Specifications:

1. Changes in Plant Organ'zation, Figure TS.6.1-2 -{

Proposed Changes l a. Delete Plant Superintendent Operations & Maintenance. Trans-fer responsibility for implementation of the fire protection program to the Plant Manager. I

b. Change Superintendent of Maintenance to General Superintendent j l

of Plant Maintenance. 1 

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c. Change Superintendent of Operationseqf" General Superintendent Plant Operations. 1
d. Change Plant Superintendent Engineering & Radiation Protection to General Superintendent Plant Engineering & Radiation Protec-  ;

I tion, ' j l 1

e. Add a new position of General Superintendent Planning and {

i Services. Remove Supervisor of Security and Services from the  ! organization diagram. " 1

f. Add a new position of Assistant to the Plant Manager.

G. Add the new positions of Shift Manager under the General Superintendent Plant Operations. Refer to Exhibit B, Figure TS.6.1-2 for the proposed changes. Reason for Changes The position of Plant Superintendent Operations & Maintenance has been eliminated and the positions of Superintendent of Mainte-nance and Superintendent of Operations have been upgraded to General Superintendents reporting directly to the Plant Manager. This change will provide direct access to the plant manager-in 

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  • EXHIBIT A the critical areas of plant maintenance and operations. In ac-cordance with our Operational Quality Assurance Program, Appendix C, the Plant Manager is the appropriate individual to designate as responsible for the fire protection program.

The title change to General Superintendent Plant Engineering & Radiation Protection has been made to be consistent with the upgrade in the title of'the maintenance and operations superin-tendents. A new position of General Superintendent Planning and Services has been created that reports directly to the Plant Manager. This new position will provide improved management control in the areas of planning, administration, security, and general house-keeping. A new position of Assistant to the Plant Manager has been created to provide support to the Plant Manager for special projects.

The new position of Shift Manager has been created to implement the Commission Policy Statement on Engineering Expertise on Shift. Refer to our letter dated May 9, 1986 which describes l actions being taken to phase in this new position which will

! fill the dual role of licensed Senior Reactor Operator and Shift Technical Advisor. Safety Evaluation and Determination of Significant Hazards Considerations The proposed changes to Appendix A of the Operating License have been evaluated to determine whether they constitute a

j. significant hazards consideration as required by 10 CFR Part 50, Section 50.91, using the standards provided in Section 50.92. This evaluation is provided below:
1. The proposed amendment will not involve a significant increase in the probability or consequences of an-accident previously evaluated.

The proposed amendment would revise the Technical Specifica-l tions to reflect a number of improvements in the plant organi-zation and changes in title of plant supervisors. As such, these changes do not affect existing plant systems or pro-

cedures and they cannot affect previously analyzed accidents.

EXHIBIT A 1

2. The proposed amendment will not create the possibility of a new or different kind of accident from any' accident previously evaluated.

The proposed Technical Specification changes relate to the structure of the plant organization. As noted above, no changes are made in plant systems or procedures. These purely administrative changes cannot create a new or different kind of accident from any previously evaluated.

3. The proposed amendment will not involve.a significant reduction in the margin of safety.

The proposed Technical Specification wording changes'do not, as stated above, affect anything other than the organization structure of the plant. Therefore, there can be no impact on any existing margin of safety. The Commission has provided guidance concerning the applica-tion of the Standards for determining whether a significant hazards consideration exists by providing certain examples of amendments that are considered not likely to involve significant hazards considerations. These examples were published in the Federal Register on March 6, 1986. Changes proposed in this License Amendment Request are rep-resentative of example (i) since they are administrative changes.

2. Requirements for Senior Reactor Operator Operator Licenses Proposed Changes
a. Delete the "(LS0)" notation for the General Superintendent Plant Engineering and Radiation Protection'in Figure 6.1-2.
b. Change the "(LS0)" for the General Superintendent Plant Opera-tions to "(FLS0)" in Figure 6.1-2.
c. Add a footnote to define "(FLS0)" at the bottom of Figure 6.1-2 as follows:

FL50 Formerly Licensed Senior Operator or Licensed-Senior Operator l l w_ - _. _ . _ _ _ - _ 

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i EXHIBIT A 1

d. Revise Specification 6.5.G to read, ...may be made with the concurrence of two members of the unit management staff, at least one of whom holds a Senior Reactor Operator's License." ,

Refer to Exhibit B, Figure TS.6.1-2 and page TS.6.5-4, for the 4 proposed changes. i l Reason for Changes j 

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Changes (a), (b)', and (c) would revise the Technical Specifica- - tions to change the requirements for Senior Reactor' Operator (SRO) Licenses for plant management to be consistent with the requirements of the NRC Standard Technical Specifications. Change (d) revises the SRO license requirements for management personnel who may authorize temporary procedure changes. This change is also consistent with the NRC Standard Technical Speci-fications, j In the past, Northern States Power Company (NSP) has encouraged plant management and technical support staff personnel to' obtain-and maintain current SRO licenses. .Recent changes to 10.CFR Part 55, and related NRC Staff guidance, have significantly upgraded SRO requalification program requirements. While.these changes will provide added assurance that all licensed personnel are competent in control room operations, the amount of time and effort required to maintain a current SRO license has become ' prohibitive for plant management and support personnel not directly involved in operations. NSP will provide alternative training for plant management and support personnel in lieu of maintaining an SRO license and par- - ticipating in license requalification training. This Program l will maintain a high level of knowledge of nuclear fundamentals, j reactor theory, and plant operations in management and support i personnel. Most plant management and support personnel not di-rectly involved in operations will participate.in this program in lieu of maintaining a current NRC SRO license. Most utilities operating nuclear generating facilities have similar programs, '] j The changes we have proposed would revise the SRO requirements for management personnel specified in the Prairie Island Techni-cal Specifications to be equivalent to the SRO requirements specified in the Standard Technical Specifications, NUREG-0452. This uould reduce the number of SRO licenses required for manage-  ; ment personnel, i l I l 

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EXHIBIT A Safety Evaluation and Determination of Significant Hazards Considerations The proposed changes to Appendix A'of the Operating License have been evaluated to determine whether they constitute a significant hazards consideration as required by 10.CFR Part 50, Section 50.91, using the standards provided in Section 50.92. This evaluation is provided below: l'. The proposed amendment will not involve a significant increase in the probability or consequences of an accident previously evaluated. The proposed amendment would revise the Technical Specifica-tions to eliminate certain excessive requirements for li-censing of plant management personnel. It would also revise the approvals needed for temporary procedure changes from two licensed members of management to one licensed and one un-licensed member of management. License requirements for plant operations staff, including the Shift Managers and Shift . Supervisors (both are SRO licensed management personnel), would not change. Alternative training will be provided for management and support personnel. Because there are no changes being proposed in the license requirements for'indi-viduals controlling the reactor and other plant systems, there will be no impact on the quality of plant operations. The proposed changes cannot, therefore, result in a degradation in the quality of plant operations which would increase.the probability of an accident.

2. The proposed amendment will not create the possibility of a new or different kind of accident from any accident previously evaluated.

l The proposed Technical Specification changes relate to the requirements for plant management personnel to hold active SRO licenses. No changes are proposed in the license requirements for personnel actually operating the reactor and other plant systems or their supervisors. The changes, therefore, cannot result in a degradation in the quality of plant operation or j an. increase in the probability of operator error resulting in I a new or different kind of accident from any accident previ-ously evaluated. l' 1 u___________ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

1 EXHIBIT A

3. The proposed amendment will not involve a significant
                                                            - reduction in the margin of safety.

The proposed Technical Specification wording changes ch) not, for the reasons stated above, affect the quality of plant operations. 'Therefore,.there can be no impact on any existing margin of safety. I The' Commission has provided guidance concerning the applica- 1 tion of the Standards for determining whether.a significant 1 hazards consideration exists by providing certain examples of amendments that are considered not likely to involve a significant hazards considerations. These examples were- l published in the Federal Register on March 6, 1986. i Changes proposed in this License Amendment Request are rep-  ! resentative of example (1) since they are administrative changes. l l J i 1 4 I 1 i l i l 

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