ML19317G978
| ML19317G978 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 03/24/1978 |
| From: | Mattimoe J SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | Reid R Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8004020638 | |
| Download: ML19317G978 (4) | |
Text
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REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
DISTRIBUTION FOR INCOMING MATERIAL 50-312 REC: REID R W ORG-MATTIMOE J J DOCDATE: 03/24/78 NRC SACRAMENTO MUN UTIL DIST DATE RCVD: 03/31/78 DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED
SUBJECT:
LTR 1 ENCL 1 FORWARDING COPY OF B&W LTR DTD 03/23/78 PROVIDING RECOMMENDATION RELATIVE TO RETURNING SUBJECT FACILITY TO PWR OPERATION, IN ACCORDANCE WITH TELECON OF 03/24/78.
PLANT NAME: RANCHO SECO (SMUD)
REVIEWER INITIAL:
XJM DISTRIBUTOR INITIAL:$$,
coo **on********** DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS ******************
GENERAL DISTRIBUTION FOR AFTER ISSUANCE OF OPERATING LICENSE.
(DISTRIBUTION CODE A001)
FOR ACTION:
PD "Ll/7 ENCL
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INTERNAL:
/ ENCL NRC PDR**W/ ENCL I & E**W/2 OELD**LTR ONLY HANAUER**W/ ENCL CHECK **W/ ENCL EISENHUT**W/ ENCL SHAO**W/ ENCL BAER**W/ ENCL BUTLER **W/ ENCL GRIMES **W/ ENCL J COLLINS **W/ ENCL J.
MCGOUGH**W/ ENCL EXTERNAL:
LPDR'S SACRAMENTO, CA**W/ ENCL REGION V**W/ ENCL TIC **W/ ENCL NSIC**W/ ENCL ACRS CAT B**W/16 ENCL hISTRIBUTION:
LTR 41 ENCL 40 CONTROL NBR:
780?OOGT1
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THE END 8004020 [ 2 8 f
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$SMUD SACRAMENTO MUNICIPAL UT!UTY DISTRICT O 6201 S Street, Box 15830, Sacramento, Califomia '95813; (916) 452-3211 El 19 h,
March 24, 1978 "4
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Director of Nuclear Reactor Regulation jj j, ((
Attention: Mr. Robert W. Reid, Chief
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Operating Reactors, Branch 4 U. S. Nuclear Regulatory Comission Washington, D. C.
20555 Docket No. 50-312 Rancho Seco Nuclear Generating Station, Unit No. 1
Dear Mr. Reid:
In accordance with Mr. Raasch's comitment to Mr. Zwetzig in their telephone conversation of March 24, 1978, you will find enclosed a copy of a letter from B&W to SMUD providing B&W's recomendation relative to returning Rancho Seco to power operation.
The Rancho Seco operating staff has been directed to follow this B&W recomendation.
Sincerely yours, I'
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. Mattimoe Assistant General Manager and Chief Engineer Enclosure 7C ^ &p 4M A
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P.O. Box 1260, Lynchburg, Va. 24505 Telephone: (804) 384-5111 March 23, 1978 NA:1 2 7 1970 Mr. R. J. Rodriguez A8#Ch0SEgg Manager, Nuclear Operations Sacramento Municipal Utility District 6201 S. Street Sacramento, California
Subject:
Rancho Seco Nuclear Generating Station - Unit No.1 Evaluation of NSS Cooldown Transient
Dear Mr. Rodriguez:
B&W has reviewed the data provided by SMUD regarding the March 20, 1978 reactor trip and resulting cooldown transient, and have performed the following evaluations:
1.
Evaluation of RCP seal performance data prior, during and subsequent to the transient.
2.
Evaluation of transient t.onditions with respect to RCP's and CRDM's.
3.
Evaluati'on of transient conditions with respect to fuel assemblies, i
4.
Evaluation of transient conditions with respect to RV, RC piping, pressurizer, and OTSG's.
As a result of these evaluations, B&W concurs with SMUD's intent to return Rancho Seco to power operation at a power level at or below 75% full power with the following recommendations-1.
The following maneuvering limits be applied for this plant startup:
a.
The maximum rate of power increase below 20% full power shall be 10% per hour.
b.
The maximum rate of power increase between 20% and 40% full power shall be 30% per hour.
c.
Above 40% full power, escalation shall be limited to 3% per hour.
2.
Increased ' surveillance of the loc,se parts monitoring system for at least a one week period.
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JANIS TO, RODRIGUEZ MARCH 23, 1978 3.
Performnce of an operability check of on-line and redundant NNI instrumen-tation.
4.
Establishment of a procedure for restoring NNI power in the event of a power loss and a commitment to establish by April 7,1978 operator instructions for immediate action to limit NSS transient if UNI power cannot be im=ediately,istored.
5.
Surveillance of primary and secondary radiochemistry on a minimum of a daily basis for at least one week following startup.
B&W NPGD's concurrence with operation of Rancho Seco above 75% full power is contingent upon our QA evaluation _ of data input provided by SMUD and analyses performed by B&W Engineering, and you will be informed of completion of those activities and our concurrence in a timely mnnner.
In addition, B&W is performing an evaluation to determine the effects of the transient conditions on the Reactor Coolant System ac. cumulative usage factor and will advise you of those results. As a further measure of verification of OTSG tube integrity, B&W requests additional inspection of the OTSG tubes during your next refueling outage.
Those inspection recommendations will be forwarded to SMUD along with B&W's proposed refueling inspection plan prior to the outage.
If you have any questions or require additional infor=ation, please advise.
Very truly yours, Q
ocl T. Jan*s Service Manager JTJ/hh cc: JJ Mattimoe DG Raasch RP Oubre' JH Johnston t