ML20041G398
| ML20041G398 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 03/16/1982 |
| From: | Baxter T SACRAMENTO MUNICIPAL UTILITY DISTRICT, SHAW, PITTMAN, POTTS & TROWBRIDGE |
| To: | Buck J, Kohl C, Rosenthal A NRC ATOMIC SAFETY & LICENSING APPEAL PANEL (ASLAP) |
| References | |
| NUDOCS 8203220207 | |
| Download: ML20041G398 (3) | |
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SHAW, PITTMAN, PoTTs & TROWBRIDGE _
6800 M ST AC CT, N W WASHINGTON. D. C 20036 g
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WsL(I AM P SARR MANNAME.M LIE gE RM AN J Av E StLSERG wtNTMROP N BROWN SUSAN M FREUND SANDRA E. FOLSOM SARSARA M ROSSOTTs JAMES a seAML8N JOMN L CARR JR MARCea 4 NaRE NSTg sN GEORGE V ALLEN. JR Rose RT E. ZAMLER PMILIP J MARVEY JuDaT** A SANDLE R F RE D ORASNE R R*CMAND E GALEN WRi?E R S DeRECT DsAL NUMBER Roggmy u goRDON ED*ARD D TOUNG tat R mENLv wtaSTER ROSERT e ROSSsNS nqq qggg DARBARA J MORGEN WENDEL4N A WMITE' NAT*eAN EL P 3 REED JR STEVEN M LUCAS 044_AvJv aONNeE S GOTTLtEB wot Aoenens o e= o c March 16, 1982 Alan S.
Rosenthal, Esquire Dr. John H. Buck Chairman Atomic Safety and Licensing Appeal Atomic Safety and Licensing Appeal Board Board U.S.
Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Washington, D.C.
20555 Christine N.
Kohl, Esquire Atomic Safety and Licensing Appeal g
A Board U.S. Nuclear Regt$latory Commission RECElyED 9
Washington, D.C.
20555 s
"f4RJg7bh In the Matter of Aj' Sacramento Municipal Utility District 8% g (Rancho Seco Nuclear Generating Station D8Mr Q p Docket No. 50-312 Sc 1,
4 Administrative Judges Rosenthal, Buck and Kohl:
G Please find enclosed, for your information, a copy of a letter from the Sacramento Municipal Utility District (Mattimoe) to l
the NRC Staff (Eisenhut), dated March 9, 1982, on the subject "Make-up Nozzle Abnormalities."
The letter is relevant to certain aspects of the questions posed in the Appeal Board's Memorandum and Order of i
March 9, 1982, in this docket.
Respectfully submitted, Thomas A.
- Baxter, P.C.
Counsel for Licensee TAB:jah Enclosure 0g cc:
per Certificate of Service b k 8203220207 820316
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PDR ADOCK 05000312 I
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h S.U J SACRAMENTO MUNICIPAL UTILITY DISTRICT D 6201 S Street. Box 15830. sacramento. Califomia 95813: (916) 45 March 9, 1982 DIRECTOR OF NUCLEAR REACTOR REGULATION
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ATTENTION DARRELL G EISENHUT DIRECTOR DIVISION OF LICENSING U S NUCLEAR REGULATORY COMMISSION WASHINGTON D C 20555 DOCKET 50-312 RANCHO SEC0 NUCLEAR GENERATING STATION UNIT 1 MAKE-UP N0ZZLE ABNORMALITIES Yesterday, March 8,1982, I met with other me'mbers of the B&W Owners Regulatory Re:ponse Group, you, and your staff concerning the abnormalities which have been discovered in the Crystal River Unit 3, Oconee Unit 3, and Unit 2 make-up nozzles. As comitted to during this meeting, the Sacramento Municipal Utility District held a meeting today of the Plant Review Comittee and Management Safety Review Comittee. The purpose of this meeting was to discuss and detemi te if any safety implication existed with the continued operation of Rancho SeSo Unit 1 at this time.
Both of these comittees unani-mously decided that c1ntinued operation is justified.
g There are several factors which led to the above conclusion.
First, it has been determined that since prior to fuel loading at Rancho Seco, leakage has occurred in the pressurizer level control valve such that flow through the make-up nozzle has only recently been reduced to as low as fifteen gallons per minute during normal plant operation.
Even though the bypass valve around the control valve was adjusted initially for a low flow of only one to three gallons per minute, this low a flow has only existed at Rancho Seco Unit 1 duri.ng heatup when the leak through of the pressurizer level control valve combined with reactor coolant system expansion exceeds letdown capability. The large number of thermal cycles which contributed to the Crystal River 3 failures, has not existed at Rancho Seco.
Similarly, it is felt that the 2A2 and 3A2 nozzle failures at Oconee may have l
l resulted from starved flow since the 2Al and 3Al no:zles are sound.
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a DARRELL G EISENHUT March 9, 1982 A second factor leading to our conclusion is the fact that the cracking phenomenon which has been discovered at Crystal River 3 and the Oconee units would lead to a leak before a break of the pipe would occur. This is evidenced by the leakage which was discovered and detected at Crystal River Unit 3, which led to the inspection which uncovered the problem. We have also had experience in detecting these magnitudes of leaks at Rancho Seco Unit 1.
This belief in a leak before a break in this situation is agreed to by metallurgists from the Electric Power Research Institute who have indicated to us that this type of cracking would have a slow growth. This conclusion is also supported by our make-up piping configuration which has a pipe support very near the injection nozzle.
A third factor influencing our decision was the fact that all of the Rancho Seco injection lines, including the make-up line, incorporate the proper attenuation length between the nozzle and first valve. At Rancho Seco the make-up nozzle safe end is welded directly to an elbow which is, in turn, welded to a pipe which drops almost two feet before reaching the elevation of the valve.
The Rancho Seco operators will be informed of these recent events and will be instructed to notify their management of any significant increase in primary system leakage even it if remains within technical specification limits. The District also connits at this time to perform both radiographic and ultrasonic examinations of the make-up nozzle during the first outage requiring a cooldown.
We believe this incident has demonstrated the excellent communication which exists between the B&W Owners and the NRC and feel that we can properly revise our decision if necessary as new info'nnation becomes available.
If we can provide any additional information for your use at this time, please advise.
John J. Mattimoe Assistant General Manager and Chief Engineer 4
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING APPEAL BOARD In the Matter of
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SACRAMENTO MUNICIPAL UTILITY DISTRICT
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Docket No. 50-312
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(Rancho Seco Nuclear Generating
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Station)
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CERTII'ICATE OF SERVICE I hereby certify that copies of Licensee's letter to the Appeal Board with attachment were served this 16th day of March, 1982, by deposit in the U.S. mail, first class, postage prepaid, to the parties identified on the attached Service List.
Thomas A.
- Baxter, P.C.
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O UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING APPEAL BOARD In the Matter of
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SACRAMENTO MUNICIPAL UTILITY DISTRICT
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Docket No. 50-312
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(Rancho Seco Nuclear Generating
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Station)
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SERVICE LIST Alan S. Posenthal, Esquire David S. Kaplan, Esquire Chairman Secretary and General Counsel Atanic Safety and Licensing Appeal Sacramento Municipal Utility District Board P.O. Box 15830 U.S. Nuclear Regulatory Cmmission Sacramento, California 95813 Washington, D.C.
20555 Richard L. Black, Esquire Dr. John H. Buck Office of the Executive Legal Director Atanic Safety and Licensing Appeal U.S. Nuclear Regulatory Comnission Board Washington, D.C.
20555 U.S. Nuclear Regulatory Comnission Washington, D.C.
20555 Christopher Ellison, Esquire California Energy Ommission Christine N. Kohl, Esquire 1111 Howe Avenue Atanic Safety and Li nsing Appeal Sacramento, California 95825 Board U.S. Nuclear Regulatory Comnission Lawrence Coe Lanpher, Esquire Washington, D.C.
20555 Hill, Christopher and Phillips, P.C.
1900 M Street, N.W.
Elizabeth S. Bowers, Esquire Washington, D.C.
20036 Chairman Atanic Safety and Licensing Board Docketing and Service Section U.S. Nuclear Regulatory Camussion Office of the Secretary Washington, D.C.
20555 U.S. Nuclear Regulatory Camussion Washington, D.C.
20555 Dr. Richard F. Cole Atanic Safety and Licensing Board Panel U.S. Nuclear Regulatory Comnission i
Washington, D.C.
20555 Mr. Frederick J. Shon Atomic Safety and Licensing Board Panel j
U.S. Nuclear Regulatory Camission i
Washington, D.C.
20555 l
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