ML20059A209
| ML20059A209 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 08/14/1990 |
| From: | Beckman W CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20059A211 | List: |
| References | |
| GL-88-06, GL-88-6, NUDOCS 9008220164 | |
| Download: ML20059A209 (4) | |
Text
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C011 Sum 8tS Power
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Plant Manager MM AGEMEAFS MIS 8dtE55 Big Rock Point Nuclear Plant,10269 US 31 North, Charlevoix, MI 49720 I
1 August 14, 1990 1
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Nuclear Regulatory Commission f
Document Control-Dest Washington, DC-20555 k
DOCKET 50-155 - LICENSE DPR BIC ROCK POINT PLANT -
TECHNICAL SPECIFICATION CHANCE REQUEST - ADMINISTRATIVE AND ORGANIZATIONAL l
CHANCES j
Attached is a request for char.ge to the Big Rock Point Plant Technical Specifications.. These proposed changes are requested to reflect changes.in the organizational structure of the Operations and Engineering Departments.
The proposed changes have been-developed under the guidance of NRC Ceneric Letter 88-06 dated March 22, 1988, and reviewed against the Standard Technical Specifications (NUREC-0123, Revision 3).
Attached please find the i
Request for Change to the Technical Specifications as well as the Proposed Technical Specification page Changes.
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l L Beckman Plant Manager o
CC Administrator, Region III, USNRC NRC Resident Inspector - Big Rock point f
Attachment l-P K
OC0890-0387-NLO2 i.
9008220164 900814
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CONSUMERS POWER COMPANY Docket 50-155 Request for Change to the Technical Specifications License DPR-6 For the reasons hereinafter set forth, it is requested that the Technical Specifications contained in the Facility Operating License DPR-6, Docket 50-155, issued to Consumers Power Company on May 1,1964, for the Big Rock Point Plant be changed as described in Section I belowl 1.
Changes A.
Revise the first paragraph following Section 6.2.2.g(4) to read as followst "Any deviation from the above guidelines shall be authorized by the Plant Manager or his designated alternate, or higher levels of Management, in accordance with established procedures and with documentation of the basis for grating the deviation."
B.
Revise Section 6.5.1.2 to delete the Operations Supervisor as a member of the PRC and change " Production and Performance Superintendent" to " Operations Superintendent."
C.
Revise Section 6.3.4 to read as follows:
r "The Operations Superintendent shall hold a Senior Reactor Operator License. The Operations Superintendent shall be responsible for directing the activities of licensed operators.
lie shall meet the other requirements of Section 6.3.1 (as applicable to Operations Manager in ANSI N18.1)."
11.
Discussion Effective January 1, 1990 structure of the Operations and Engineering Departments were changed which has resulted in title changes described-in portions of the Big Rock Point Technical Specifications.
First, the title of the individual responsible for directing the activities of licensed operators has been changed from the " Production and Performance Superintendent" to " Operations Superintendent." Associated with the change was the deletion of the " Operations Supervisor" position which was an intermediate level manager between the licensed operators and the Production and Performance Superintendent. The licensed operators will now report directly to the Operations Superintendent who will hold a Senior Reactor Operator license. The Reactor Engineering group will still report to the Operations Superintendent, however, the Plant Performance group has been aligned to the Engineering Superintendent.
Change A removes the reference to titles from the portion of the Technical Specifications dealing with working hour limitations. This proposed change follows the intended guidance of Nuclear Regulatory Commission Generic Letter 88-06 dated March 22, 1988.
OC0890-0387-NLO2
Cisange B modifies the composition of the Plant Review Committee (PRC) due to the changes discussed above. This proposed change was. reviewed against the Standard Technical Specifications (NUREC-0123, Revision 3),
i Section 6.5.1, Unit Review Croup and found to be in compliance with the guidelines.
Change C changes the title of the individual required to hold an SRO License and responsible for directing the activities of licensed I
operators. This change was necessitated by the organization changes discussed above. This proposed change also follows the guidance in Generic Letter 88-06.
III. Analysis of No Significant_ Hazards Consideration These proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated because j
the organizational changes do not af fect plant operation.
Essential elements of the organizational structure have been retained through the addition of general requirement s modeled af ter the guidance and philosophy provided by the NRC in Generic Letter 88-06.
These proposed changes do not create the possible of a new or dif ferent kind of accident than previously evaluated because the changes are administrative in nature. No modifications to plant equipment, changes to setpoints or operating limitations are being proposed. These proposed changes do not involve a significant reduction in a margin of safety as defined in Technical Specification bases because there are no bases for administrative controls. However, the proposed changes still endorse the Standard Technical Specification guidelines for the " Unit Review Croup" which requires a chairman and minimum of four members.
l Through our Quality Assurance Program implementation and our commitment to maintain qualified personnel in all positions of responsibility and authority, it is assured that safety functions performed by both the onsite and offsite organizations will continue to be performed at a high level of competence. Therefore, these proposed. changes do not involve a significant hazards consideration.
IV.
Conclusion The Big Rock Point Plant Review Committee has reviewed this Technical Specification Change Request and has determined this change does not involve an unreviewed safety question and, therefore, involves no significant hazards consideration. This change has also been reviewed by the Nuclear Safety Services Department. A copy of this Technical Specification Change Request has been sent to the Sate of Michigan official designated to receive such Amendments to the Operating License.
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t CONSUMERS POWER COMPANY To the best of my knowledge, information and belief, the contents of this submittal are truthful and complete.
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By w
David P Hoffman, Vice
't i'j ent g
Nuclear Operation.
l Sworn and subscribed to before me this 17th day of August 1990.
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Elaine E Buehrer. Notary Public Jackson County, Michigan My commission expires October 11, 1993 r
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