ML19210E920
| ML19210E920 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 12/07/1979 |
| From: | Moody D YANKEE ATOMIC ELECTRIC CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0578, RTR-NUREG-578 WYR-79-150, NUDOCS 7912130230 | |
| Download: ML19210E920 (3) | |
Text
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Telephone 617 366-9011 rwx 710-390 0739 YANKEE ATOMIC ELECTRIC COMPANY a 3.2.1 '
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WYR 79-150 W.
20 Turnpike Road Westborough, Massachusetts 01581
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December 7, 1979 United States Nuclear Regulatory Commission Washington, D.C.
20555 Attention:
Office of Nuclear Reactor Regulation Mr. Harold Denton, Director
References:
(a) License No. DPR-3 (Docket No. 50-29)
(b) YAEC Letter to USNRC dated November 19, 1979 (79-141)
(c) USNRC Letter to YAEC dated October 30, 1979
Dear Sir:
Subject:
Lessons Learned Short-Term Requirements This letter is written as a result of conversations with your staff on December 6, 1979 and an apparent misunderstanding of our letter, Reference (b).
We wish to inform you that the attachment to our letter, Reference (b) does in fact include the additional requirements detailed in your letter, Reference (c).
Furthermore, except where we have identified specific differences and/or exceptions as detailed in Attachment A, this letter reaffirms our commitment to the increased scope of your letter, Reference (c).
We trust this information is satisfactory; however, if you have any questions, please contact us immediately.
Very truly yours, YANKEE ATOMIC ELECTRIC COMPANY
.b.
D. E. Moody Manager of Operations RHG/kaf 1550 123 g
7912 2 a n 2 %
l ATTACHMENT A j
Section Abbreviated
,-y No.
Title Difference and Justification (Na 2.1.1 Emergency Power Supply The motive and control power for the PORV is supplied (Relief and Block Valves) by Battery No. 1, which is the same battery used to C~)
Clarification No. 2 to start the diesel generator supplying motive and control power for the block valve.
If power is availabic to open the valves, then the diesel generator is operating and will then be availabic to supply power for closing the valve.
In our opinion, the probability of a diesel generator to to continue operating once started is greater than the probability of starting another diesel with another battery, thus increasing the reliability of both opening and closing both valves.
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2.1.3b Subcooling Meter only one safety grade system pressure measurement Clarification No. 4 is available which is not part of the reactor protection system.
In our opinion, connecting to the reactor protection pressure channels would jeopardize the safety of the plant and the reliability of protection. A safety grade pressure transmitter has been ordered and delivery is expected in April, 1980.
It is our intention to install this redundant pressure measurement during the 1980 refueling outage.
2.1.6b Plant Shielding Review Yankee intends to implement on the SEP schedule those modifications found acceptable for deferment by NRC af ter their review of the description of modifications resulting from the plant shielding design review.
2.1.7a,b Auxiliary Feedwater System The NRC requirements for auxiliary feedwater systems.
at Yankee Rowe have been delineated in the NRC letter of November 9,1979. The schedule and commitment for implementation of required changes or actions will be submitted on the schedule specified in that.' letter.
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Section Abbreviated No.
Title Difference and Justification Lf)
N 2.1.8a Post Accident Sampling Yankee intends to implement on the SEP schedule those modifications found acceptable for deferment by NRC after their review of the description of C-)
modifications resulting from the sampling design Lf) review.
C 2.1.9 RCS Venting Seismic design of each vent will be consistent with Clarification No. C.6 the present plant seismic design.
When the SEP seismic review is completed, the vent will be seismically qualified to plant seismic values.
2.2.2.b Onsite Technical Support Center Yankee takes exception to the physical size and Clarification No. 3 staffing requirements for the onsite Technical Support Center. Yankee intends to take advantage of its ability to support emergency operations from its Westboro engineering of fice and has already implemented emergency procedures to activate engineering and management support upon notification of an emergency by the Yankee plant. Details of the implementation of this into the total emergency plan will be available to the emergency preparedness Task Force Review Team.
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