ML20214X336

Forwards Addl Info Supporting Final Hazards Summary Rept (Fhsr) Update Schedular Exemption Request Re Proposed Cross Indexing Sys.Key Function of Updated Fhsr Is to Reflect Current Safety Analysis Design Bases of Facility

ML20214X336
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	12/03/1986
From:	Frisch R CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 8612110070
Download: ML20214X336 (4)

Text

- . _ _ . __ . _ . _ .

.s ,.

Consumers

@retraamus Power AIEMJr5 PNSERE55 Generet offices: .1945 West Pernell Road, Jackson, MI 49201 + (517) 788-0550 December 3, 1986 Director, Nuclear Reactor Regulation US Nuclear Regulatory Commission Washington, DC 20555 DOCKET 50-155 - LICENSE DPR BIG ROCK POINT PLANT -

ADDITIONAL SUPPORTING INFORMATION IOR FINAL HAZARDS

SUMMARY

REPORT UPDATE SCHEDULAR EXEMPTION REQUEST By letter dated August 27, 1986, . Consumers Power Company requested a schedular exemption from the requirements of 10CFR50.71(e)(3)(ii) which would allow additional time for NRC concern s with our proposed cross indexing system to be resolved. The NRC preliminary review of the exemption request raised addi-tional concerns. Specifically the NRC requested Consumers Power Company to provide additional.information directed at enhancements to the proposed cross indexing system and a schedular date by which the enhancements would be implemented.

As discussed during earlier meetings and several conference calls with the staff, Consuiners Power Company will provide an update of the existing Final Hazards Summary Report (FHSR) dated November 14, 1961. The goal of this effort is to develop a document which provides a current snapshot of Big Rock

. Point Plant design and can be used by the plant staff to perform 50.59 safety evaluations. From NRC prerspective the document can be used by their staff to perform reviews of submittals efficiently. To the extent practicable, the past efforts expended on the cross indexing system will be utilized.

This update will basice.11y follow the existing FHSR outline and format and will not attempt to address the descriptions and degree of detail contained in the Standard Review Plan for Modern Plant Safety Analysis Reports. Attachment 1 outlines an initial " Table of Contents" for the update, however, changes are expected as drafting and review activities progress. Sections of the original

• FHSR discussing the f.esearch and Development Program and Initial Test Program will be deleted due co limited applicability to current operation.

The key function of this updated FHSR is to reflect the current Safety Analy-sis Design Bases of Big Rock Point and will be accomplished in the following manner:

. A review of s*.gnificant facility modifications will be performed to provide a current description of Big Rock Point Systems and components.

These system description sections of the update will reference updated engineering 3rawings or contain simplified system sketches as appropriate.

OC1286-0168-NTJ 4 f3612110070 861203 PDR ADOCK 05000155 A P PDR \

.a ~.

Director, Nuclear Reactor Regulation 2 Big Rock Point Plant Add'l Information FHSR Update December 3, 1986

. A review of Technical Specification Amendments will be completed to reflect the current operating requirements of the Big Rock Point systems, structures and' components. Conclusions and assumptions contained in the staff Safety Evaluations for the Amendments will be incorporated into the updated FHSR, where appropriate.

. A review of the final Integrated Plant Safety Analysis Report (IPSAR) and NRC staff Safety Evaluations to the completed Systematic Evaluation Program (SEP) topics will be performed. Conclusions reflecting design and operation of Big Rock Point will be included in the update where appropri-ate. Additional generic actions (ie, TMI action plan, Generic Letter 83-28) will also be included in the same manner.

. Sections of the FHSR will be updated to reflect the most current transient and accident analysis results for Bz3 Rock Point. This will not be a re-analysis of any events, but a coLpilation of previous analysis in support of Technical Specification Amendments, system modifications, and generic evaluations currently on the docket.

. Exemptions received from the staff to NRC rules and regulations will also be reviewed. Conclusions and assumptions from these exemptions will be reflected in appropriate sections of the FHSR to establish a current licensing basis.

Although it is difficult to accurately determine a scope and completion date to a project of this magnitude, Consumers Power Company intends to dedicate one person plus typing / clerical support to this effort until completion.

Assuming a start date following the 1987 Refueling Outage (approximately March 1, 1987), this updated FHSR should be available for submittal by December 1988. Consumers Power Company offers to review the progress of this effort with the staff on a quarterly basis to ensure the needs and expectations of the NRC will be met by the final submittal. As with any effort of this magnitude, inadvertent errors or omissions are expected. These will be corrected in subsequent submittals or included in annual revisions in accer-dance with 10 CFR 50.71(e)(4).

The FHSR Update will continue to be carried as Integrated Plan Issue A-035B and status will be reported semi-annually along with the other Integrated Plan issues.

N Ralph R Frisch Senior Licensing Analyst CC Administrator, Region III, USNRC NRC Resident Inspector - Big Rock Point Plant Attachment OC1286-0168-NLO4

• - [* r, .

ATTACHMENT Consumers Power Company Big Rock Point Plant Docket 50-155

/

FHSR TABLE OF CONTENTS December 3, 1986 I

l.

4 1

l 1 Page OC1286-0168-NLO4 i

',E " , ,,

TABLE OF CONTENTS Section 1 -

Introduction and Conclusions Section 2 -

Plant Site and Environment Section 3 - Containment Section 4 -

Reactor Section 5 -

Reactor Coolant System Section 6 -

Plant Engineered Safeguards Section 7 - Plant Instrumentation and Control Systems Section 8 - Plant Electrical Systems Section 9 -

Plant Auxiliary Systems Section 10 - Plant Radioactive Waste Control Systems Section 11 -

Plant Power Conversion Systems Section 12 -

Plant Operations / Operating Procedures Section 13 - Plant Transient and Accident Analysis l

l OC1286-0168-NLO4