ML20054C211
| ML20054C211 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 04/15/1982 |
| From: | Mattimoe J SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, TASK-1.A.3.1, TASK-2.B.2, TASK-2.B.3, TASK-2.B.4, TASK-2.E.1.2, TASK-2.E.4.2, TASK-2.F.1, TASK-2.K.2.10, TASK-TM TAC-44709, TAC-44755, TAC-51330, NUDOCS 8204200243 | |
| Download: ML20054C211 (3) | |
Text
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$SMUD SACRAMENTO MUNICIPAL UTILITY DISTRICT O 6201 S Street, Box 15830, Sacramer.to, California 95813; (916) 452-3211 W I c)
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April 15, 1982
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DIRECTOR OF NUCLEAR REACTOR REGULATION
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U S NUCLEAR REGULATORY COMMISSION WASHINGTON D C 20555 DOCKET 50-312 RANCHO SECO NUCLEAR CENERATING STATION UNIT NO 1 POST-TMI REQUIREMENTS Your letter of March 17, 1982 requested information on certain items scheduled in NUREG 0737 to be implemented between July 1, 1981 and March 1, 1982. The information requested follows and is listed by I
item number taken from Enclosure 1 to your letter.
Item Title Discussion l
I.A.3.1 Simulator Exams The District feels this item is completed. Arrangements have been made for examination of candidates for an operator's license to be examined at the B&W simulator. The last group of District candidates for an operator's license did receive examinations at the simulator in i
February of this year.
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II.B.2 Plant Shielding The District has scheduled a major outage for September of this year to
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I perform the bulk of the NUREG 0737 i
l modifications for refueling, and for f
a 10 year in-service inspection as i
/ O required by the technical specifica-tions. The September date for this outage was discussed at length with your staff during a meeting on Sept-ember 17, 1981, and can be summarized as follows: The Discrict has been unable to procure hardware to support an earlier outage date. Manpower has not been available, either within the "E*
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e DARRELL G EISENHUT April 15, 1982 Item Title Discussion II.B.2 (cont)
Plant Shielding to support design efforts leading to earlier date. A building is being constructed to house electrical equip-ment related to these modifications and the construction schedule cannot be improved to support an earlier outage.
A negative reserve margin is predicted for northern California should Rancho Seco be off-line during the summer peak months. The predicted end-of-cycle date for the present fuel cycle is about September 1, 1982.
The shiciding modifications are minor, but do require a plant shutdown. We feel the limited extent of these modi-fications justifies continued operation of the plant until the scheduled September date.
II.B.3 Post Accident Delivery of the post accident sampling Sampling system equipment will not be made until just prior to and during the September outage. We feel that the interim arrangements which have been made for offsite sampling of high level liquids justifies the September date for implementation of this item.
II.B.4 Training for This item has been completed as verified Mitigating Core in the NRC Inspection Report dated Damage March 19, 1982 for activities dated February 1 - 26, 1982.
II.E.1.2 Auxiliary Feed-The equipment to complete these modifica-water Initiation tions will not be available to support and Flow Indication their implementation before the September outage. During this outage, one auxiliary feedwater pump will be modified to auto-matica11y 1 cad on a diesel generator upon initiation of the safety features actuation system.
In addition, the flow indication will be upgraded to a safety grade status.
The above modifications will provide for a safety grade initiation of auxiliary feedwater; however, it should be noted that the District intends to upgrade the auxiliary feedwater control system such that safety grade control, as well as initiation is availabic at the next refueling outage presently scheduled for 1984. This upgrade will provide an auxiliary feedwater system which is compar-able to any other engineered safety feature at the plant.
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DARRELL G EISEN11UT April 15, 1982 i
Item Title II.E.4.2 Containment Isola-Part 5 of this requirement has been satis-g tion Dependability fled. The NRC determined the pressure setpoint to be adequate as documented in a letter dated July 14, 1981. The require-ment of Part 7 to isolate the purge valves on high radiation will be accomplished i
during the September 1982 outage. Equipment i
deliveries will not support an earlier modi-l fication.
In the meantime, the existing plant design incorporates a feature to termi-i nate purge fan operation on high radiation.
The District feels this measure is adequate justification to support the September date.
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II.F.1 Accident Monitoring Requirements 1 through 6 will all be made during the outage scheduled to begin September l
1982. Hardware deliveries will not support l
an earlier date and the District feels exist-ing instrumentation to be adequate justification supporting the September date.
I II.K.2.10 Safety Grade Trip The anticipatory reactor trips will be upgraded to safety grade during the September 1982 outage.
j We feel the existing control grade trips provide l
adequate protection and can justify this date.
j It should be noted that the anticipatory trip for a loss of feedwater will be based on a j
j pressure transmitter at this time. However, t
j the upgraded auxiliary feedwater control system to be installed in 1984 will provide a replace-ment for this signal based on reactor flux / feed-water flow.
The remainder of the items in Enclosure 1 to your letter are applicable only to boiling water reactors, and we are therefore not responding to these items.
If we can provide any additional information on the above items, please advise.
I would like to again reference our rather extensive meeting with your staff on September 17, 1981, which was docketed with your memo of September 25, 1981.
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ch John *J. Mattimoe Assistant General Manager and Chief Engineer Subscribed and sworn before me this /6N day of April 1982.
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My Comrmmen [xpres Ncvember 22,1933
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