ML13316A985
| ML13316A985 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 03/30/1988 |
| From: | Trammell C Office of Nuclear Reactor Regulation |
| To: | Baskin K Southern California Edison Co |
| References | |
| TAC-67463 NUDOCS 8804080237 | |
| Download: ML13316A985 (8) | |
Text
o 9 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 March 30, 1988 Docket No. 50-206 Mr. Kenneth P. Baskin Vice President Southern California Edison Conpany 2244 Walnut Grove Avenue Post Office Box 800 Rosemead, California 91770
SUBJECT:
PUBLIC NOTICE OF APPLICATION FOR AMENDMENT TO OPERATING LICENSE FOR SAN ONOFRE NUCLEAR GENERATING STATION, UNIT 1 (TAC NO. 67463)
Dear Mr. Baskin:
The enclosed announcement has been forwarded to the Orange County Register for publication. This announcement relates to your application dated March 10, 1988 as supplemented March 22, 1988, for an amendment to Facility Operating License No. DPR-13'to revise the steam generator tube plugging criteria to allow tubes with defects below the uppermost one inch of sound roll to remain in service provided there are no imperfections in the uppermost one inch of sound roll until the next refueling outage, on or about July 15, 1988.
A separate notice will be published later in the Federal Register concerning revision to the tube plugging criteria for an additional period of time.
Charles M. Trammell, Project Manager Project Directorate V Division of Reactor Projects -
- III, IV, V and Special Projects
Enclosure:
Newspaper Announcement cc:
See next page 8804080237 880330'_
PDR, ADOCK 05000206 !
P PDR
March 30, 1988 Docket No. 50-206 DISTRIBUTION IDocket File
'-NRC & Local PDRs Mr. Kenneth P. Baskin PD5 Plant File Vice President GHolahan Southern California Edison Conpany CTrammell 2244 Walnut Grove Avenue DHickman Post Office Box 800 JLee Rosemead, California 91770 OGC
SUBJECT:
PUBLIC NOTICE OF APPLICATION FOR AMENDMENT TO OPERATING LICENSE FOR SAN ONOFRE NUCLEAR GENERATING STATION, UNIT 1 (TAC NO. 67463)
Dear Mr. Baskin:
The enclosed announcement has been forwarded to the Orange County Register for publication. This announcement relates to your application dated March 10, 1988 as supplemented March 22, 1988, for an amendment to Facility Operating License No. DPR-13 to revise the steam generator tube plugging criteria to allow tubes with defects below the uppermost one inch of sound roll to remain in service provided there are no imperfections in the uppermost one inch of sound roll until the next refueling outage, on or about July 15, 1988.
A separate notice will be published later in the Federal Register concerning revision to the tube plugging criteria for an additional period of time.
original signed by D.E. Hickman for C. Trammell Charles M. Trammell, Project Manager Project Directorate V Division of Reactor Projects -
- III, IV, V and Special Projects
Enclosure:
Newspaper Announcement cc:
See next page
- See previous concurrences.
DV DRSP/PDV OGC DRSP/D:PDV CTrammell:dr Wolmstead GWKnighton (by HRood) 88
/
/88 3/3q/88 3/30/88 OFFICIAL RECORD COPY
S0 Docket No. 50-206 DISTRIBUTION 00HTTIe NRC & Local PDRs Mr. Kenneth P. Baskin PD5 Plant File Vice President GHolahan Southern California Edison Conpany CTrammell 2244 Walnut Grove Avenue DHickman Post Office Box 800 JLee Rosemead, California 91770 OGC
SUBJECT:
PUBLIC NOTICE OF APPLICATION FOR AMENDMENT TO OPERATING LICENSE FOR SAN ONOFRE NUCLEAR GENERATING STATION, UNIT 1 (TAC NO. 67463)
Dear Mr. Baskin:
The enclosed announcement has been forwarded to the Orange County Register for publication.
This announcement relates to your application dated /14'A
/O,)
March 22, 1988, for an amendment to Facility Operating License No. DPR-13 to revise the steam generator tube plugging criteria to allow tubes with defects below the uppermost one inch of sound roll to remain in service provided there are no imperfections in the uppermost one inch of sound roll until the next refueling outage, on or about July 15, 1988.
A separate notice will be published later in the Federal Register concerning revision to the tube plugging criteria for an additional period of time.
Charles M. Trammell, Project Manager Project Directorate V Division of Reactor Projects -
- III, IV, V and Special Projects
Enclosure:
Newspaper Announcement cc:
See next page R /PDV DRSP/PDV DRSP/D:PDV CTrammell:dr GWKnighton
/88
/
/88
) /10/88 5>/p0/88 OFFICIAL RECORD COPY
Mr. Kenneth P. Baskin San Onofre Nuclear Generating Southern California Edison Company Station, Unit No. 1 cc Charles R. Kocher, Assistant Mr. Jack McGurk, Acting Chief General Counsel Radiological Health Branch James Beoletto, Esquire State Department of Health Southern California Edison Company Services Post Office Box 800 714 P Street, Office Bldg. 8 Rosemead, California 91770 Sacramento, California 95814 David R. Pigott Mr. Hans Kaspar, Executive Director Orrick, Herrington & Sutcliffe Marine Review Committee, Inc.
600 Montgomery Street 531 Encinitas Boulevard, Suite 105 San Francisco, California 94111 Encinitas, California 92024 Mr. Robert G. Lacy Mr. Dennis M. Smith, Chief Manager, Nuclear Radiological Programs Division San Diego Gas & Electric Company Governor's Office of Emergency Svcs.
P. 0. Box 1831 State of California San Diego, California 92112 2800 Meadowview Road Sacramento, California 95832 Resident Inspector/San Onofre NPS U.S. NRC P. 0. Box 4329 San Clemente, California 92672 Mayor City of San Clemente San Clemente, California 92672 Chairman Board of Supervisors County of San Diego San Diego, California 92101 Director Energy Facilities Siting Division Energy Resources Conservation &
Development Commission 1516 - 9th Street Sacramento, California 95814 Regional Administrator, Region V U.S. Nuclear Regulatory Commission 1450 Maria Lane, Suite 210 Walnut Creek, California 94596
0 PUBLIC NOTICE NRC STAFF PROPOSES TO AMEND OPERATING LICENSE AT SAN ONOFRE 1 The Nuclear Regulatory Commission staff has received an application dated.
March 10, 1988, and supplemental information dated March 22, 1988, from the Southern California Edison Company (licensee) for an exigent amendment to the operating licensee for San Onofre Nuclear Generating Station (SONGS) Unit 1, San Diego County, California.
If approved, the amendment would revise the steam generator tube plugging criteria to allow tubes with defects below the uppermost one inch of sound roll to remain in service provided there are nc imperfections in the uppermost one inch of sound roll.
The one inch distance includes 0.25 inches eddy current measurement uncertainty. The amendment would be in effect only until the next refueling outage which is scheduled for July 1988.
The Commission has determined that the licensee used its best efforts to make a timely application for the proposed change and that exigent circumstances do exist and were not the result of any fault of the licensee. The exigent circumstances result from the fact that the licensee has recently completed an inspection of the steam generator tubes following a mid-cycle outage that began on February 16, 1988.
The three Westinghouse Series 27 steam generators at San Onofre Unit 1 were fabricated with a partial depth roll expansion in the lower end of the tube above the tube to tubesheet weld. For SONGS 1 this partial depth roll expansion is two inches, measured upward from the bottom of the steam generator tube, based upon the prevalent Westinghouse steam generator design practice at the date of manufacture. The partial depth expansion, along with the tube to tubesheet weld, forms both a structural and pressure boundary for the steam
-2 generator tube. The inspection, which involved all three steam generators, revealed that some defects exist in the rolled region of the tubes within the tubesheet. The licensee requested that Westinghouse perform an evaluation to determine the amount of tube roll necessary to meet all regulatory requirements, including tube pullout under normal or postulated accident conditions. The evaluation determined that a sound roll of one inch, including 0.25 inches for eddy current measurement uncertainty, would provide a safety factor of 3 or more against tube pullout during normal or postulated accident conditions.
This evaluation had previously been performed for the Connecticut Yankee (CY)
Atomic Power Company which also uses the Series 27 steam generators at its Haddam Neck plant. The evaluation for Haddam Neck (Docket No. 50-213) was accepted by the NRC in a safety evaluation dated July 30, 1986 and in Amendment Number 96 to the Haddam Neck operating license (DPR-61). To avoid the radiation exposure that would otherwise be incurred by plant workers involved in tube plugging operations, to minimize the loss of margin in reactor coolant flow through the steam generators, and to assure that flowrates in excess of that required for full power operation are maintained, the licensee proposes to change the steam generator tube plugging criteria. This requires a change to the Technical Specification entitled "Inservice Inspection of Steam Generator Tubing." This inspection is required to be satisfactorily completed prior to restart of.the plant, which is currently scheduled for April 7, 1988. The NRC staff has determined that these exigent circumstances justify reducing the public notice period normally provided for licensing amendments and proposes to issue the amendment at the close of business on April 6, 1988.
-3 The licensee has evaluated this proposed change to determine whether or not a significant hazards consideration is involved. It has been demonstrated that one inch of sound tube roll expansion is sufficient to preclude pullout of the tube from the tubesheet.
Even with the conservative assumption that a tube could completely sever circumferentially below the uppermost one inch of the tube roll expansion, test results demonstrate that pullout of the tube is precluded under normal and postulated accident condition loadings. Tube rupture cannot occur because the contact between the tube and tubesheet does not permit sufficient movement of tube material. In a similar manner, the tubesheet does not permit sufficient movement of tube material to permit collapse of the tube during postulated accident loadings. In addition, one inch of sound tube roll expansion is sufficient to preclude significant leakage from tube degradation located below this region. Therefore, this proposed change would not significantly increase the probability or consequences of an accident previously evaluated. Any hypothetical accident as a result of tube degradation in the expanded portion of the tube would be the same as the existing steam generator tube rupture accident analysis. Therefore, operation of the facility in accordance with this proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated. The safety factors used in the determination of the required tube roll expansion are consistent with the safety factors in Section III of ASME Boiler and Pressure Vessel Code used in steam generator design. This distance has been verified by testing to be greater than the length of roll expansion required to preclude significant leakage during normal and postulated accident conditions. Therefore, the proposed change will not involve a significant reduction in any margin of safety.
4
-4 The NRC staff has evaluated the requested amendment against the standards in 10 CFR 50.92 and it appears that the criteria for no significant hazards consideration is satisfied for short-term operation of SONGS 1 until the next refueling outage, on or about July 15, 1988. The staff is continuing its evaluation of the proposed change to the long-term operation of the plant.
A notice of a proposed amendment authorizing long-term operation and an opportunity for a hearing will be published in the Federal REgster prior to consideration of issuing such an amendment.
Comments on the proposed determination of no significant hazards consideration for the short-term operation may be telephoned to George W.
Knighton, Director of Project Directorate V, by collect call to 1-(301)-492-1372, or submitted in writing to the Rules and Procedures Branch, Office of Administration and Resources Management, U. S. Nuclear Regulatory Commission, Washington, D.C. 20555. All comments received by April 5, 1988 will be considered in reaching a final determination. A copy of the application may be examined at the NRC's local public document room located at the General Library, University of California, P.O. Box 19557, Irvine, California 92713 and at the Commission's Public Document Room, 1717 H Street, N.W., Washington, D.C.