ML20053C649
| ML20053C649 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 05/24/1982 |
| From: | Mattimoe J SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| TAC-48468, NUDOCS 8206020425 | |
| Download: ML20053C649 (3) | |
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SACRAMENTO MUNICIPAL UTILITY DISTRICT O 6201 s street, Box 15830, sacramento, California 95813; (916) 452-3211 May 24, 1982 1
DIRECTOR OF NUCLEAR REACTOR REGULATION ATTN:
DARRELL G EISENHUT, DIRECTOR DIVISION OF LICENSING-l U S NUCLEAR REGULATORY COMMISSION WASHINGTON D C 20555 DOCKET N0. 50-312 LICENSE NO. DPR-54 RE: TECHNICAL SPECIFICATION WAIVER In accordance with the Rancho Seco Unit I Technical Specifications Definitions, the Sacramento Municipal Utility District requests the following waiver from the license.
Section 1.2.8 of the Technical Specifications defines " Refueling Interval" as:
" Time between normal refuelings of the reactor, not to exceed 24 months for the first refueling and 18 months thereafter with-out prior approval of the AEC".
The District requests the 18-month interval to be extended, on a one-time-only basis, to 24 months, similar l
to the initial core interval.
This request also involves the definition in Section 1.9.8 of " Biannually",
which is only used for Diesel Generator overhauls. The District would like to defer this overhaul until the next refueling. Specific sur-veillances involved with these definitions are attached to this request.
l This waiver is requested because Rancho Seco has had extensive shutdowns i
due to turbine rotor repairs, and is presently performing auxiliary feed-water spray header modifications. These modifications are expected to extend to Auaust 1982.
The nuclear core burnup will not be complete for another five full power months. Between August, 1981, and the time our fuel burnup would require refueling, the Technical Specification defined refueling interval duration,. including the maximum 25% extension, will run out and the surveillance requirements within the Technical l
Specifications will be open to NRC citations.
If this request is denied, the series of tests, inspections and calibration will have to be per-formed prior to startup from our current outage and then be repeated approximately five months later.
The District feels that this request I
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~ Darrell G. Eisenhut May 24, 1982 is reasonable and will not present any health or safety problem to the general public.
In fact, approving this request would prevent unneeded-personnel radiation exposure consistent with ALARA principles and would prevent imposition of a financial burden that would not be warranted by the slight benefit, if any, to the safety of Rancho Seco.
1 We have determined that this request for wai<er requires a fee of
$4,000. as defined within 10CFR170.22 Class III.
If you have any questions concerning this request, please contact Ron Colombo at Rancho Seco, ohn. Mattimoe Assistant General Manager and Chief Engineer d sworn to before me SubscribedgdayofMay,1982.
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SURVEILLANCE TEST REQUIRED AT REFUELING AND DURING THE REFUELING INTERVAL TS NUMBER DESCRIPTION 4.14.4 Safety System Hyd. Snubber (functional)
Tabic 4.1-1 #20 SFAS Digital Channel "1A" Refueling Test Table 4.1-1 #21 SFAS Digital Channel "1B" Refueling Test 4
Table 4.1-1 #16, 17, 18, 19 SFAS Digital Channel 2A Refueling Test Table 4.1-1 #16, 17, 18, 19 SFAS Digital Channel 2B Refueling Test 4.5.1.1C Core Flooding System 4.5.3.2 Decay Heat Removal System Leakage 4.1-2 #13 Internal Vent Valve Tests 4.5.2.1A.1 and.3 RB Spray Sys. Loop A SFAS Test 4.5.2.1A.1 and.3 RB Spray Sys. Leap B SFAS Test 3.3.1.C.2 Refueling CBS/NaOH Surv. (Check Valves) 4.5.2.1B RF Emergency Cooling Sys. Dir & NSCW Flow Letter (4-11-80)
Reactor Building Spray Leakage ISI Program Refueling CBS "A" (B) Stop Check Valve j
Surveillance 4.4.1.2 Local Component Leak Rate Test 4.6.3 Biannual Diesel Engine Insp. G-886A 4.6.3 Biannual Diesel Engine Insp. G-886B l
4.6.3 Emerg. Diesel Generator Insp. ("A" Annual) 4.6.3 Emerg. Diesel Generator Insp. ("B" 4 Yr.)
4.6.2 Diesel Generator "A" SFAS Start Test 4.6.2 Diesel Generator "B" SFAS Start Test Testing of Pressurizer Code Safety 4.1-2 #3 4.1-2 #4 Main Steam Safety Valves 4.12 RB Emerg. Filtering Sys. Loop "A" 4.12 RB Emerg. Filtering Sys. Loop "B" Table 4.1-2 #8 Aux / Spent Fuel Bldg. Filter Sys. "A" Table 4.1-2 #8 Aux / Spent Fuel Bldg. Filter Sys. "B" Table 4.1-2 #3 Inservice Testing of Relief / Safety Valves-PSV-31900 Table 4.1-2 #10 Reactor Building Isolation Trip Verification
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