ML13333A441

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Forwards Revised Assessment of SEP Topic VI-10.B, Incorporating Editorial & Corrective Changes Re . Evaluation Will Be Basic Input to Integrated Assessment of Facility.W/O Encl
ML13333A441
Person / Time
Site: San Onofre 
Issue date: 11/15/1979
From: Ziemann D
Office of Nuclear Reactor Regulation
To: James Drake
Southern California Edison Co
References
TASK-06-10.B, TASK-6-10.B, TASK-RR NUDOCS 7911280025
Download: ML13333A441 (6)


Text

11V1 DISTRIBUTION Local PDR ORB #2 Reading NRR Reading Docket No. 50-206 DGEisenhut RHVollmer DLZiemann HSmith PWO'Connor OELD Mr. James Ii.

Drake I&E (3)

Vice President DCrutchfield (2)

Southern California Edison Company JRBuchanan 2244 Walnut Grove Avenue TERA Post Office Box 800 ACRS (16)

Rosemead, California 91770

Dear Mr. Drake:

RE:

COMPLETION OF SEP TOPIC VI-10.8 -

SAN ONOFRE UNIT 1 Your letter dated May 17, 1979,.indicated that 'you have examined our draft evaluation of the subject topic dated April 18, 1979. You suggested editorial or corrective changes to the assessment to make it more accurately reflect your facility design. We have incorporated your suggested modifications in the enclosed assessment. With these modifications our review of-SEP Topic VI-1O.B is complete and will be a basic input to the integrated assessment of your facility.

The subject assessment compares your facility design with the criteria currently used by the staff in licensing new facilities. This assessment may need to be re-examined if you modify your facility or if the criteria are.changed before we complete our integrated assessment.

Si qgerely, Thomas v0.

Dennis L. Ziemann, Chief Operating Reactors Branch #2 Division of Operating Reactors

Enclosure:

Completed SEP Topic VI-10.B cc w/encl osure:

gjffl1CP See next page VEC I

DOCKET (1E. COPY OC DOR:ORB 2 DO DOR:ORB #2 OFFICE Dd.............t........

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SUNMEPOConnor:ah DC fIel DLZiemann

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/79 NRC FORM 318 (9-76) NRCM-0240

  • U.S.

GOVERNMENT PRINTING OFFICE: 1979-289-369 C

Mr. James H. Drake 2 -

November 15, 1979 cc w/enclosure:

Charles R. Kocher, Assistant General Counsel Southern California Edison Company Post Office Box 800 Rosemead, California 91770 David R. Pigott Samuel B. Casey Chickering & Gregory Three Embarcadero Center Twenty-Third Floor San Francisco, California 94111 Jack E. Thomas Harry B. Stoehr San Diego Gas & Electric Company P. 0. Box 1831 San Diego, California 92112 U. S. Nuclear Regulatory Commission ATTN:

Robert J. Pate P. 0. Box 4167 San Clemente, California 92672 Mission Viejo Branch Library 24851 Chrisanta Drive Mission Viejo, California 92676 K M C, Inc.

ATTN:

Richard Schaffstall 1747 Pennsylvania Avenue, N. W.

Suite 1050 Washington, D. C. 20006

CCMPLETE -

November 15, 1979 SEP REVIEW OF SHARED ENGINEERED SAFETY FEATURES, ONSITE EMERGENCY POWER, AND SERVICE SYSTEMS FOR MULTIPLE UNIT STATIONS TOPIC VI-10.B

-2 INTRODUCTION

.The safety objective of Topic VI-1o.B is to assure that: (1) the interconnection of ESF, on-site emergency power, and service systems between different units are not such that a failure, maintenance or testing operation in one unit will affect the accomplishment of the protection function of the system(s) in other units, (2) the required coordination between unit operators can cope with an incident in one unit and safe shutdown of the remaining unit(s), and (3) system overload conditions will not arise as a consequence of an accident in one unit coincident with a spurious accident signal or any other single failure in another unit. This objective applies only to safety related equipment and structures.

The sharing of structures, systems and components important to safety for a multiple unit facility can result in a reduction of the number and of the capacity of on-site systems to below that which normally is provided for the same number of units located at separate sites.

NRC General Design Criterion 5, "Sharing of structures, systems and components," was developed to ensure that sharing of structures, systems, and components important to safety among nuclear power units will not significantly impair their ability to perform their safet.y functions, including, in the event of an accident in one unit, orderly shutdown and cooldown of the remaining units.

-3 This evaluation addresses only the non-Electrical, Instrumentation, and Control (EI&C) portions-of this topic i.e. fluid systems and components and structures. The EI&C portions will be evaluated later in the SEP.

In the course of this evaluation, we determined that the review of shared structures and equipment at the Dresden Unit Nos. 1 and 2 facilities could not be completed prior to the completion of other related SEP topic reviews. These related topics are identified in the evaluation; and, upon completion of these topics, this evaluation will be updated. Topic VI-10.B is applicable to the following SEP plants which are located at multiple unit sites:

San Onofre 1 Millstone 1 Dresden 1 and 2 Evaluation and Conclusion San Onofre 1 San Onofre Unit 1 is an operating plant which utilizes a Westinghouse pressurized water reactor for its nuclear steam supply system while Units 2 & 3, which utilize Combustion Engineering pressurized water reactors for their nuclear steam supply systems, are under review for the issuance of operating licenses.

Shared systems is a review concern which is normally addressed in the course of an Operating License review. The Final Safety Analysis Report for San Onofre Units 2 and 3 discusses shared structures, systems and

-4 components for Units 2 and 3 only and does not identify any interfaces between these units and Unit 1. Therefore, the staff conducted a review to identify and evaluate the structures and equipment shared between Unit I and Units 2 and 3. Based on this review, we identified the Service Water Reservoir (SWR) and its associated piping and components as the only shared components which could affect the safe shutdown capability of Unit 1*.

This is because the SWR provides water to both the Unit 1 fire protection water system, which can be used to supply water to the other units, and to the Unit 1 safe shutdown systems (Auxiliary Feed System). However, the Unit 1 Technical Specifications (Section 3.4 and 3.14) acceptably account for this sharing of the SWR by requiring the licensee to maintain adequate SWR water inventory for both safe shutdown and fire fighting purposes.

Based on the results of our review as summarized above, we conclude that

1) the safety objective of Topic VI-10.B is met for San Onofre 1, 2) the sharing of the SWR is in conformance with GDC 5, and 3) there are no electrical instrumentation and control systems shared between San Onofre Unit 1 and Units 2 and 3 except the switchyard as permitted by GDC 17.

(NRC Letter to Licensee dtd. 2/9/79)