ML19317G993
| ML19317G993 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco, Davis Besse |
| Issue date: | 03/28/1978 |
| From: | Mattimoe J SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | Reid R Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8004020652 | |
| Download: ML19317G993 (3) | |
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REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
DISTRIBUTION FOR INCOMING MATERIAL 50-312 REC: REID R W ORO: MATTIMOE J J DOCDATE: 03/28/79 NRC SACRAMENTO MUN UTIL DIST DATE RCVD: 04/03/78 DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED
SUBJECT:
LTR 1 ENCL 0 FURNISHING JUSTIFICATION FCR CONTINUED OPERATION OF UNIT 1 WITH REACTOR VESSEL MATERIAL SURVEILLANCE PROGRAM CONDUCTED AT OAVIS BESSE UNIT 1, PURUANT TO SECTION 4.2.8 OF TECH SPECS, IF DAVIS BESSE UNIT 1 FAILS TO ACHIEVE COMMERICAL OPERATION AT 100% PWR PLANT NAME: RANCHO SECO (SMUD)
REVIEWER INITIAL:
XJM DISTRIBUTOR INITI AL: pL co*************** DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS ******************
REACTOR VESSEL MATERIAL SURVEILLANCE (DISTRIBUTION CODE A021)
FOR ACTION:
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ZWETZIG**LTR ONLY(1)
INTERNAL:
ILE**LTR O 1)
NRC PDR**LTR ONLY(1)
I a-E**bTR-ONLY(2)
OELD**LTR ONLY(1)
MIPC*-
^NLY(1)
HANAUER**LTR ONLY(1)
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PAWL
_iR ONLY(1)
EISENHUT**LTR ONLY(1) i SHAD ~._TR ONLY(1)
BAER**LTR ONLY(1)
BUTLER **LTR ONLY(1)
GRIMES **LTR ONLY(1)
HAZELTON**LTR ONLY(1)
HOGE**LTR ONLY(1)
R GAMBLE **LTR ONLY(1)
RANDALL**LTR ONLY(1)
EXTERNAL:
LPDR'S SACRAMENTO, CA**LTR ONLY(1)
REGION V**LTR ONLY(1)
TIC **LTR ONLY(1)
NSIC**LTR ONLY(1)
ACRS CAT B**LTR ONLY(16) 4 DISTRIBUTION:
LTR 41 ENCL 0 CONTROL NBR:
780950011 SIZE: 2P g
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THE END 4
8004020(f2 W1)
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.geuuo SACRAMENTO MUNICIPAL UTILITY olSTRICT O 6201 S Street, Box 15830, Sacraniento, C&lifornia 95813; (916) 452 3211 March 28, 1978 0
s Director of Nuclear Reactor Regulation
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Attention: Mr. Robert W. Reid, Chief
[g T_y Operating Reactors, Branch 4 d5e-D.
U. S. Nuclear Regulatory Coninission B T;:
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.M Washington, D. C.
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Docket No. 50-312 0
u Rancho Seco Nuclear Generating Station, Unit No.1
Dear Mr. Reid:
Section 4.2.8 of the Rancho Seco Unit No.1 Technical Specifications requires that a report be submitted to the NRC if Davis Besse Unit No.1 fails to achieve commercial operation at 100% power by Janua~ 1,1978.
The purpose of this report is to provide justification for continued up:ra-tion of Rancho Seco Unit No. I with our reactor vessel mate' ial surveillance program conducted at Davis Besse Unit No.1.
This letter p ovides such justification.
Davis Besse Unit No.1 is currently operating at 2evels up to 75% of full power and expects to achieve full power operation by April 6, 1978.
Consequently, specimen irradfation will not be sign ficantly different from that which would be achieved had Davis Besser Unit No.1 achieved 100% operation by January 1,1978.
As stated in ;he Safety Evaluation by the Office of Nuclear Reactor Regulation, su1 porting Amend-ment No.15, to Facility Operating License DPR-54, Sacramelto Municipal Utility District, Rancho Seco Nuclear Generating Station, 'Jnit No.1, Docket No. 50-312, a conservative prediction of radiation damage can be made by using Regulatory Guide No.1.99 until data becomes available from the surveillance program.
The pressure-temperature (P-T) curves, Figures 1.1.2-1 and 3.1.2-2, of the Rancho Seco Unit No.1 Technical Specific itions are valid for two effective full power years (EFPY) of operation.
r<ancho Seco Unit No.1 is expected to reach this point in operation around September 1978.
This is an estimated 18 months before surveillance data from the Rancho Seco Unit No.1 reactor vessel material specimens being irradiated at Davis Bessee Unit No. I will become available.
This estimated time takes
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Mr. Robert W. Reid March 29,1978 into consideration the anticipated delay beyond January 1,1978 for Davis Besse Unit No. I to achieve 100% power operation, the 450 EFPD of the first Davis Besse Unit No.1 fuel cycle, and the time necessary to test the surveillance specimens and modify the P-T curves accordingly.
For the interim period, the time from which present P-T curves are not valid until new P-T curves are doveloped from surveillance specimens taken at the end of the first fuel cycle at Davis Besse Unit No.1, we will produce P-T curves valid for approximately 5 EFPY based on the criteria of Regulatory Guide 1.99.
These revised curves will be submitted to the NRC to be incorporated into the Rancho Seco Unit No.1 Technical Specifications prior to the expiration of the present curves.
The accumulated fluence of ~ the Rancho Seco Unit No.1 specimens at the end of the first Davis Besse Unit No.1 fuel cycle will be 6.0 x 1018 n/cm2 (E > 1 Mev) which is equivalent to.ll.4 EFPY with respect to the 1/4 t vessei location. The P-T curves can then again be modified by this data to extend the operating period from approximately 5 EFPY to approximately 11 EFPY.
Additional surveillance data will be available fror, additional cycles of operation of the Davis Besse Unit No. I reactor well before the 11 EFPY of operation has elapsed, thus allowing further extension of the operating period to end of life of the reactor vessel.
Sincerely yours,
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4 J. J. Mattimoe Assistant General Manager and Chief Engineer cc:
Mr. R. H. Engelken NRC - Region V