ML20005G107

Application for Amend to License DPR-6,changing Tech Spec Pressure Temp Limits to Satisfy Fracture Toughness Requirements of Section V of 10CFR50.App G,Per Generic Ltr 88-11

ML20005G107
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	01/10/1990
From:	Berry K CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20005G108	List: ML20005G107
References
GL-88-11, NUDOCS 9001180139
Download: ML20005G107 (3)

Text

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i January 10, 1990 Nuclear Regulatory Commission Document Control' Desk Washington, DC 20555 j

DOCKET 50-155 - LICENSE DPR BIG ROCK POINT PLANT -

TECHNICAL SPECIFICATION CHANGE REQUEST - REACTOR TEMPERATURE LIMITS Attached is a request for change to the Big Rock Point Plant Technical

. Specifications,. This, change is requested to insure that the specifications for the Reacto. Vessel continue to satisfy the Fracture Toughness requirements of Section V of 10 CFR Part 50, sppendix G.

In compliance with the

-Schedular requirements of Generic Letter 88-11 dated July 12, 1988, and with consideration of the existing fluence effect on the Big Rock Point Reactor Vessel, Consumers Power Company is requesting a change to the Big Rock Point Technical Specification pressure-temperature limits, derived using the methodology contained in Revision 2 to Regulatory Guide 1.99.

Attachment I to this. letter contains the proposed Technical Specification page changes, contains the associated Technical Analysis.

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Kenneth W Berry Director, Nuclear Licensing CC Administrator, Region III, USNRC NRC Resident Inspector - Big Rock Point Attachment 9001180139 900110 PDR ADOCK 05000155 P

PDC OC0190-0244-NLO4

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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 Operations License DPR-6, Docket 50-155, issued to Consumers Tower Company on May 1, 1964, for the Big Rock Point be changed as described in Section I below:

1.

Changes A.

Change Section 4.1.l(i)4 to read as follows:

4 The reactor shall not be made critical, with the exception of physics testing, at temperatures below the criticality limit shown on Figures 4. l(b) and 4.l(c).

B.

Replace Figure 4-1(a) Hydrostatic Test Pressure / Temperature Limits, Figure 4-1(c) Heatup Pressure / Temperature Limits, and Figure 4-1(b)

Cooldown Pressure / Temperature Limits with the attached revised curves.

II.

Discussion The above proposed Technical Specification Change A is administrative in nature and is proposed to correct an editorial error. The proposed change uniquely identifies the two controlling Figures used to establish the lower limits of criticality.

The enclosed Attachment 2 provides the basis for Technical Specification Change B.

The limits specified by this change are being submitted to satisfy the requirements of 10 CFR 50 Appendix G by incorporating the methodology of Regulatory Guide 1.99 Revision 2.

III. Analysis of No Significant Hazards Consideration Proposed Change A is administrative in nature and provides clarification of existing requirements. It is not associated with any modification to plant equipment, systems, or components and does not change any existing administrative controls or operability limitations on existing equipment. The proposed change corrects an editorial deficiency inadvertently missed in a previous Technical Specification Change Request.

The proposed change, therefore, does not affect the probability or consequences of an accident previously evaluated. Because the proposed change does not involve any plant modifications, operability limits, or procedural controls, it does not create the possibility of a new or different kind of accident than previously evaluated nor involve a reduction in margin of safety. Consequently, the proposed change A does not involve a significant hazards consideration.

mil 289-0609A-BT01

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L The Big Rock Point Plant Review Committee has concluded that the proposed

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Pressure / Temperature Limits, proposed by Change B, do not involve an unreviewed safety question. The margin above Nil Ductility. Transition Tem;Srature (NDTT) is governed by 10CFE50 Appendix G and remains unchanged. The predicted shifts in NDTT are based on a revised reference temperature consistent with Regulatory Guide 1.99 Rev 2.

The method of revising the new Pressure / Temperature Limits is the same as in the past

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(ASME Code Section III, Appendix G).

The proposed curves were generated for an 18 Effective Full Power Year exposure and are conservative until that time. Based on the above, the margin of safety has not changed.

Therefore, the operation of the facility in accordance with the above proposed Change B would not:

1) involve a significant increase in the i

probability or consequences of an accident previously evaluated; or

2) create the possibility of a new or different kind of accident from any accident previouwly evaluated; or 3) involve a significant reduction in the margin of safety.

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 been reviewed by the Nuclear Safety Services Department. A copy of this Technical Specification Change Request has been sent to the State of Michigan official designated to receive such Amendments to the Operating License.

CONSUMERS POWER COMPANY To the best of my knowledge, information and belief, the contents of this submittal are truthful and complete.

By d

David P Hoffman, Vic ident Nuclear Operations Sworn and subscribed to before me this 10th day of January 1990.

f(.4 Elaine E Buehrer, Notary Public J?ckson County, Michigan My commission expires October 11, 1993 M11289-0609A-BT01