ML20003G445
| ML20003G445 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 04/24/1981 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Kay J YANKEE ATOMIC ELECTRIC CO. |
| References | |
| TASK-03-06, TASK-3-6, TASK-RR LSO5-81-04-043, LSO5-81-4-43, NUDOCS 8104290455 | |
| Download: ML20003G445 (5) | |
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April 21,1981 h Iis
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-G.h Mr. James A. Kay M
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Yankee Atomic Electric Company 5
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25 Research Drive Westborough, Massachusetts 01581
Dear Mr. Kay:
SUBJECT:
SEP TOPIC III-6, SEISMIC DESIGN CONSIDERATIONS YANKEE R0WE Our letter to you dated August 4,1980 requested in accordance with 10 CFR 50.54(f) of the Commission's regulations that you submit plans and proceed with a seismic reevaluation program for the Yankee Rowe facility and that you provide justification for your conclusion that continued operation is justified in the interim until the seismic reevaluation program is co@lete. We have reviewed your seismic reevaluation pro-gram forwarded by your letter dated February 4,1981. We have determined that your program is deficient with respect to scope of structures, systems and cog onents to be evaluated.
Our August 4,198010 CFR 50.54(f) letter specified as a minimum, that your program should provide for an evaluation of:
1.
The integrity of the reactor coolar.t pressure boundary, 2.
The integrity of fluid and electrical distribution systems related to safe shutdown and engineered safety features, and 3.
The integrity and functionability of mechanical and electrical i
equipment and engineered safety feature systems (including con-I tainment).
t We have reviewed the systems at the Yankee Rowe facility which are important to safety and should be included in your seismic reevaluation program. These systems are identified in Enclosure (1).
You are requested to revise and resubmit within 30 days of receipt of this letter your seismic reevaluation program. Your revised prngram should include the systems identified in Enclosure (1) and their related structures and cogonents. A schedule for cogletion of seismic reevalua-tions, submittal of analysis results for NRC review and the installation of any necessary modifications should be included in your revised program.
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- Your schedule, if different from our August 4,1980 request, should be justified and should be consistent with your conclusion that continued operation is justified in the interim until the seistaic reevaluation i
program is conplete and any necessary modifications are implemented.
i Sincerely, i
Dennis M. Crutchfield, Chief Operating Reactors Branch No. 5 Division of Licensing
Enclosure:
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aj wasmorow, o. c.20ssa fg g Apri.1 24, 1981 Docket No. 50-29 LS05-81-04-043 Mr. James A. Kay Senior Engineer-Licensing Yankee Atomic Electric Company 25 Research Drive Westborough, Massachusetts 01581
Dear Mr. Kay:
SUBJECT:
SEP TOPIC III-6, SEISMIC DESIGN CONSIDERATIONS YANKEE R0WE Our letter to you dated August 4,1980 requested in accordance with 10 CFR 50.54(f) of the Comission's regulations that you submit plans and proceed with a seismic reevaluation program for the Yankee Rowe facility and that you provide justification for your conclusion that continued operation is justified in the interim until the seismic reevaluation program is co@lete. We have reviewed your seismic reevaluation pro-gram forwarded by your letter dated February 4,1981. We have determined that your program is deficient with respect to scope of structures, systems and ogonents to be evaluated.
Our August 4,198010 CFR 50.54(f) letter specified as a mininum, that your program should provide for an evaluation of:
1.
The integrity of the reactor coolant pressure boundary, 2.
The integrity of fluid and electrical distribution systems related to safe shutdown and engineered safety features, and 3.
The integrity and functionability of mechanical and electrical equipment and engineered safety feature systems (including con-t ainment).
We have reviewed the systems at the Yankee Rowe facility which are igortant to safety and should be included in your seismic reevaluation program. These systems are identified in Enclosure (1).
You are requested to revise and resubmit within 30 days of receipt of this l
letter your seismic reevaluation program. Your revised program should include the systems identified in Enclosure (1) and their related structures and components. A schedule for cogletion of seismic reevalua-tions, submittal of analysis results for NRC review and the installation of 1
any necessary modifications should be included in your revised program.
l
. Your schedule, if different fr:m our August 4,1930 request, should be justified and shculd be censistent with your conclusien that continued operation is justified in tne interim until the seis=ic reevaluation program is ceglete and any necessary nodifications are iglenented.
Sincerely, 7,g 1
Dennis M. Crutchfield, C~.ef Operating Reacters Branch No. 5 Division of Licensing
Enclosure:
As stated cc w/ enclosure:
Se rext page I
N
ENCLOSURE (1)
SAFETY RELATED SYSTEMS, STRUCTURES AND COMP 0NENTS YANKEE R0WE PLANT The scope of review for the seismic re-evaluation program should include the systems, structures, and components (including emergency power supply and distribution, instrumentation, and actuation systems) with the following functions:
1.
Thereactorcoolantpressureboundaryaswell1asthecoreandvessel internals. This should also include those portions of the steam and feedwater system extending from and including the secondary side of the steam generator up to and including the outermost containment isolation valve and connected piping of 25 inch or larger nominal pipe size, up to and including the first valve that is either normally closed or is capable of automatic closure during all modes of normal reactor operation.
2.
Systems or portions of systems that are required for safe shutdown as identified in the SEP safe shutdown review (SEP Topic VII-3). The system boundary includes those portions of the system required to perform the safety function and connected piping up to and including the first valve that is either normally closed or capable of automatic closure when the safety function is required.
3.
Systems or portions of systems that are required to mitigate design basis events, i.e., accidents and transients (SEP Topics XV-1 to XV-24). The functions to be provided include emergency core cooling, post-accident containment heat removal, post-accident containment atmosphere cleanup, as well as support systems, such as cooling water, needed for proper function-ing of these systems.
4.
Systems and structures required for fuel storage (SEP Topic IX-1).
Integrity of the spent fuel pool structure including the racks is needed. Failure of the liner plate due to the safe shutdown earthquake must not result in significant radiological releases, or in loss of ability to keep the fuel covered.
Failure of cooling water systems or other snems connected to the pool should not permit draining of the fuel pool. Means to supply make-up to the pool as needed must be provided.
5.
Structures that house the above equipment.
For the Yankee Rowe plant, the sca i cunsiuers cne ibilowing systems, and associated structures, and components should be addressed:
a) Reactor Coolant System (RCS) b) Portions of Main Steam System c) Portions of Main Feedwater System
.... d) Portions of other systems directly connected to RCS up to and including isolation valves e) Control Rod Drives f) Auxiliary Feedwater System g) Shutdown Cooling System h) Portions of the Chemical and Volume Control System
- 1) Portions of the Component Cooling Water System j) Portions of the Service Wat-se System k) Portions of the Pressure Control and Relief
- 1) Accumulators m) High Pressure Safety Injection System n) Low Pressure Safety Injection System o) Containment Air Recirculation (Post Accident) Fans p) Spent Fuel Pool and Makeup As discussed above, a " system" also includes the power supply, instrumentation and actuation systems.