ML19263D477
| ML19263D477 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 03/19/1979 |
| From: | Ziemann D Office of Nuclear Reactor Regulation |
| To: | Counsil W NORTHEAST NUCLEAR ENERGY CO. |
| References | |
| TASK-06-10.B, TASK-08-04, TASK-6-10.B, TASK-8-4, TASK-RR NUDOCS 7903290274 | |
| Download: ML19263D477 (7) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION yy g' ;j WASHINGTON, D. C. 20555 2,9 2
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March 19,1979 Docket No. 50-245 Mr. W. G. Counsil, Vice President Muclear Engineering and Operations Northeast Nuclear Energy Company Post Office Box 270 Hartford, Connecticut 06101
Dear Mr. Counsil:
Enclosed is a copy of our draft evaluation of Systematic Evaluation Program Topic VI-10.B.
You are requested to examine the facts upon which the staff has based its evaluation and respond either by confirming that the facts are correct, or by identifying any errors.
If in error, please supply corrected information for the docket. We encourage you to supply for the docket any other material related to this topic that might affect the staff's evaluation.
Your response within 30 days of the date you receive this letter is requested.
If no response is received within that time, we will assume that you have no comments or corrections.
Sincerely,
- G9n4, Dennis L. Ziemann, /
gym ief Operating Reactors Branch #2 Division of 01erating Reactors
Enclosure:
Topic VI-10.B cc w/ enclosure:
See next page 7003290'O3%
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I SEP REVIEW 0F SHARED ENGINEERED SAFETY FEATURES, ONSITE EMERGENCY POWER, AND SERVICE SYSTEMS FOR MULTIPLE UNIT STATION 5*
TOPIC VI-10.B
- This evaluation deals only with non-EI&C equipment and structures and should be corabined with the EI&C review of this topic when it is completed.
Mr. W. G. Counsil March 19,1979 cc William H. Cuddy, Esquire Day, Berry & Howard Counselors at Law One Constitution Plaza Hartford, Connecticut 06103 Anthony Z. Roisman Natural Resources Defense Council 917 15th Street, N. W.
Washington, D. C.
20005 Northeast Nuclear Energy Company ATTN:
Superintendent Millstone Plant P. 0. Box 128
. Waterford, Connecticut 06385 Mr. James R. Himmelwright Northeast Utilities Service Company P. 0. Box 270 Hartford, Connecticut 06101 Nuclear Regulatory Commission, Region I Office of Inspection and Enforcement ATTN: John T. Shedlasky 631 Park Avenue King of Prussia, Pennsylvania 19406 Waterford Public Libr;ry Rope Ferry Road, Route 156 Waterford, Connecticut 06385 K M C Inc.
ATTN: Mr. Jack McEwen 1747 Pennsylvania, N. W.
Suite 1050 Nashington, D. C.
20006
A-L k
a v) L INTRODUCTION The safety objective of Topic VI-10.B is to assure that:
(1) the
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interconnection of ESF, on-site emergency pever, and service systems
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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 e,onsequence 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 equip. cent and structures.
a 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 n :
-provided for the sais number of units located at separate sites. NRC d_
General Design Criterion o, " Sharing or structures, systems and
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components," was developed to ensure that sharing of structures, systems, and componants important t: safety among r.uclear pc.ier units will not significantly impai: thair ability to perforn thtir safety
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functions, including, in the event of an accident in one unit, orderly shutdown and -cooldown of the remaining units.
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. 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 ce evaluated later in tne 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 Sa 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 revic.; cencern which is normaMy addressed in tr.a course of ar Opsrating License revir...
The.:fr.al Infety Ar.;13:!s F. sport for San Onofre Units.2 and 3 discusses shared structures, systems ar.d
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v components for Units 2 and 3 only and does not identify any interfa:es 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) as the only shared component 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, and 2) the sharing of the SWR is in conformance with GDC 5.
Millstone 1 Millstone Unit 2 utilizes a pressurized water reactor for its nuclear steam supply system (NSSS), while Unit 1 utilizes a boiling water reactor for its NSSS. The Unit 2 Final Safety Analysis Report (Amendment 39, page 1.2-17) identifies facilities and systems which are shared between the units.
Based en our review of these fa:ilities an: systcas, we conc 5;te that
^ Refer to the SEP Review of Safe Shutcown Systems for Scn Onofre 1.
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- 1) the only shared system important to safety is the fire protection water system, which has been previously evaluated as a shared system in Millstone 1 License Amendment No. 53, dated September 26, 1978, and
- 2) the fire protection system is not needed for the safe shutdown of Unit 1*.
Therefore, the safety objective of Topic VI-10.8 is met for Millstone 1, and the fire protection water system is in conformance with GDC 5.