ML19331C729
| ML19331C729 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 08/06/1980 |
| From: | Reinaldo Rodriguez SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| Shared Package | |
| ML19331C730 | List: |
| References | |
| RJR-80-379, NUDOCS 8008190453 | |
| Download: ML19331C729 (4) | |
Text
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Tills DOCUf.1ENT CONTAINS PCOR QUAllTY PAGES
- . esuun SACRAMENTO MUNICIPAL UTILITY DISTRICT C 6201 S Street, Box 15830, Sacramento, California 95813; (916) 452-3211 RJR 80-379 August 6, 1980 Director (10)
Office of Inspection & Enforcement U. S. Nuclear Regulatory Connission
Ashington, D. C.
20555 Re: Operating Plant Status Report
Dear Sir:
Enclosed is the July Operating Plant Status Report for Rancho Seco Unit One.
Respectfully submitted, R. J. Rodriguez Manager, Nuclear Operations Jim Eacl.
cs:
Region V (1)
Office of ?!anagenent Information and Program Control (2)
EPRI-NSAC (1) 7 \\
g 8008190 4 3 3
NARRATIVE SL'MMARY OF PLA1."r OPERATIONS 7-1 to Reactor at 96%.
7-23 7-23 0100 Reduced Reactor power to N53% due to condenser tube leak.
1739 Began increasing reactor power to 92% at 10 MWe/hr for 2-hour hold.
2108 Began increasing reactor to 96%.
2150 Reactor at 96%.
7-23 to Reactor at 96%.
7-31 SL? NARY OF CHANCES MADE IN ACCORDANCE WITH 10 CFR 50.59(b)
The technical specification changes for cycle 4, shown in the Cycle 4 Reload Report, BAW-1560, show that the proposed boron concentration is suf ficient to maintain k, of 0.95 or less with all control rods removed from the core. This tee.hnicalspe!kficationremovesallrestrictionsonmovementofthecontrolrod assemblies during fuel shuffling. The FSAR statement is therefore not necessary and unrestricted movement of control rods will not increase the consequences of any accident previously evaluated in the FSAR.
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CYCLE 4 POWER DISTRIBUTION COMPARISON In the District's letter to Mr. Robert W. Reid, dated February 27, 1980, we committed to perform Power Distribution Comparisons through Cycle 4 as a result of this being our first reload core utilizing Lumped Burnable Poisons.
The "50 EFPD" data was obtainsd July 8, 1980, with the burnup at approximately 51.5 EFPD. Prelininary analysis of this data by B&W has determined the RMS value to be 0.0298, with the continuing requirement that it be less than 0.0731.
The next data is to be taken at near 100 EFPD, which is anticipated to occur in September, 1980.
FOLLOWUP ON REPORTA3LE OCCURRENCE 80-15 During inspection of fuel discharged at the and of operating Cycle 3, one fuel assembly was found to have defective cladding on one fuel pin.
That finding was reported in the referenced RO 80-15.
Subsequent discussions with the NRC staff led to a request that a followup report be submitted which would relate the BOC-4 experience regarding fuel integrity. These data are the nominal values obtained at near full power:
BOC-3 EOC-3 BOC-4 (thru 63 EFPD)
I-131 1.0 (10-2) 1.5(10 2) 5.0(10-3) pC1/cc
!-133 4.0(10-2) 6.0(10-2) 2.5(10-2) uCi/cc 0.003 0.005 0.001
%FF These data substantiate that the failed fuel pin had likely been so for some time, and enat it was not an impediment to continued operation of the unit.
It also shows that the failed pin was located and discharged.
Failed fuel amounting to 0.001,*FF is less than one equivalent fuel pin.
This implies that, at this time, the core is effectively defect free.
This report closes this item.
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REFUELI:*C I!;TOPX4TIO: REQGST Rancho Seco Unit 1 1.
Naec of Facility:
2.
SchcJuled date for next refueling shutdown:
July 1981 Septembe'r 1981 3.
Scheduled date for restart folicving tofueling:
4: Technical Specification change or other license anendaent required:
a) Change to Rod In ~
- Power Level Curve (TS 3.5.2) b) Change to Core aence vs. Pouer Level Curve (TS 3.5.2)
^
~ c) Tilt Limits (TS 3.5.2) d) ' Safety Equipment Testing (TS 3.3.3)
May 1981 5.
Scheduica date(s) for subaitting proposed licensing action:
None 6.
Impertant licensing considerations associated with refueling:
7.
Nunber of fuel asse:.blies:
a) In the core:
177 b) In the Spent Fuel Pool:
m S.
Present licensed spent fuel capacity:
579 3
9.
Projected date of the last refueling that can be discharged 1787 to the Spent Fuel Pool:
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9 m
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