ML19339B048
| ML19339B048 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 09/25/1980 |
| From: | Kintner L Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8011060223 | |
| Download: ML19339B048 (8) | |
Text
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,;k Ro, UNITED STATES 3
7, NL' CLEAR REGULATORY COMMISSION 3.
c [i WASHINGTON. O. C. 20555
%, '.....f Docket No. 50-364 W ? J 1980 APPLICANT: Alabama Power Company FACILITY:
Joseph M. Farley Nuclear Plant Unit No. 2
SUBJECT:
SUMMARY
OF JUNE 24, 1980 MEETING REGARDING REVIEW 0F OPERATING LICENSE APPLICATION The staff met with the applicant at its office in Bethesda, Md., to discuss outstanding review areas for the Farley Unit No. 2 plant operating license review. Enclosure 1 is the status of review of Non-TMI areas used as a handout for the meeting. Enclosure 2 is a list of attendees.
Mr. R. P. Mcdonald, Vice President, Nuclear Generation for Alabama Power Company (APCo), described his company's plans for completing Farley Unit 2 by September 1,1980. Applicant was familiar with the TMI review requirements in NUREG-0694 and had prepared responses, dated June 20, to these requirements, based on SECY-80-230, a May 2,1980 paper for the Coninission regarding TMI-2 Action Plan.
Mr. V. Moore and Mr. G. Rivenbark described the new requirements for shift staffing, resulting from lessons learned from the Three Mile Island accident.
Mr. G. Hairston, Plant Manager, said APCo planned to have a shift supervisor on each unit plus a senior reactor operator for the plant and one reactor operator for each unit plus a relief operator.
Mr. R. Bosnak mentione'c the need to respond to IE Bulletin 79-J2, Revision 1
" Pipe Support Base Plate Designs Using Concrete Expansion Anchor Bolts",
June 21, 1979 and to IE Bulletin 79-14, " Seismic Analyses for As-Built Safety-Related Piping Systems", June 2,1979. He stated that there was no design problems, but that tha applicant should work with I&E to complete the actions required by the bulletins. Mr. Mcdonald said the applicant was working with Region II, I&E, to complete the action items on these bulletins. Mr. Bosnak also mentioned that the staff was reviewing the valves separating high pressure from low pressure systems.
Mr. L. Phillips said that a reactor vessel level instrument must be developed and installed on Farley Unit 2.
Mr. Oliver Kingsley, Manager, Nuclear Engineering and Technical Support, APCo, said that applicant was not satisfied that the Westinghouse proposed system, using pressure difference between the top and bottom of the reactor vessel, would be accurate enough. He said that applicant was considering another system, using neutron detectors.
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'801106022 3 g
D 2 51960 Mr. O. Kingsley said that selected emergency operating procedures would be filed for NRR review, in accordance with TMI requirements.
Mr. V. Noonan stated the staff's requirements for ports in the steam generators above the top tube sheet to view clearances between tubes and support plate holes to detect potential denting of steam generator tubes. He stated that the staff is reviewing the Westinghouse program to investigate causes of tube leaks in the first row of tubes and that no further action by applicant is required at this time.
Mr. Noonan also described the review of safety related electrical equipment to show conformance to NUREG-0588.
Prior to issuing a full cower license, the applicant's report will be given a mini-review to find major deficiencies, if any.
The staff's SER on Environmental Qualification will be issued February 1,1981, and all equipment will be upgraded by June 30, 1982. Regional meetings will be held in July 1981 to clarify this review.
L L. Kintner, Project Manager Licensing Branch No. 2 Division of Licensing
Enclosures:
1.
Status of Non-TMI Review Areas 2.
List of Attendees cc w/ enclosures:
See next page 4
m M
9 4
Mr. F. L. Clayton, Jr., Senior Vice
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President Alabama Power Company Post Office Box 2641 Birmingham, Alabama 35291 cc: Mr. Alan R. Barton Executive Vice President i
Alabama Power Company i
Post Office Box 2641 l
Birmingham, Alabama 35291 1
Mr. Ruble A. Thomas l
Vice President Southern Company Services, Inc.
Post Office Box 2525 Birmingham, Alabama 35202 Mr. George F. Trowbridge Shaw, Pittman, Potts and Trowbridge 1800 ft Street, N. W.
Washington, D. C.
20036 i
Mr. W. Bradford l
NRC Resident Inspector P. O. Box 1814 j
Dothan, Alabama 36302 i
1 0
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ENCLOSURE 1 June 19,1980 STATUS OF NON-TMI REVIEW ARE.SS FARLEY 2 1.
Anticioated Transients Without Scram (ATWS)
Emergency procedure has been developed. LPM has requested copy from Farley resident inspector.
Staff June 13 letter requested procedure to be submitted by June 20.
2.
Containment Sumo Performance Safety evaluation accepts performance subject to development of " house keeping" program, reevaluation of equipment insulation in containment, development of procedures to detect and correct inadequate ECCS ficw.
3.
Control Rod Guide Tube Wear A surveillance program to demonstrate acceptable wear of control rod guide thimble tubes has been established for Salem Unit 1.
This issue is resolved for Farley 2.
4 Environmental Oualification of Barton pressure Transmitters Farley-2 used Barton Lot 2 oressure transmitters. Staff is evaluating test results.
5 Degraded Grid Voltace Staff is evaluating applicant's responses 5.
Secondary Water Chemistry Farley-2 water chemistry program is acceptable and will be referenced in a license condition.
Applicant is responding to staff positions on condenser tube plugging requirements, steam generator inspection ports, and plugging row I tubes in the steam generator.
Sa. Control Rod Guide Tube Succort pins Staff has required that suoport pins be replaced with new pins that have been given a neat treatment to minimize stress corrosion cracking.
Applicant has agreed to do this 7.
preservice Inscection Prooran Staff is evaluating the PSI program and is awaiting additional information.
S.
Accendix G&H Exemotions Staff has prepared a safety evaluation, but required a sucstantial aE'ount of additional information to complete its review.
. 9.
Seismic Qualification Review The NRC review team has selected equipment to be reviewed and plans an inspection of equipment and audit of qualification records for some of this equipment during the week of July 7.
10.
Inservice Testing of Pumps and Valves Interim approval of the test plan is given for the portion of the initial 120 montt. inspection interval required to complete the final review.
- 11. Accendix J Exemotions Staff has reviewed containment leakage testing methods and concluded they are acceptable, except for ECCS systens that recirculate water frcm the containment sump. Staff has requested additional information on the leakage limits for these systems and the basis including radiniggical assessmen t.
- 12. Containment Overcressure Due to a Main Steamline Break Staff.grees with applicant's finding that peak containment pressure is below containment design pressure assuming a LOCA with auxiliary feedwater at the pump runout flow rate.
- 13. Revised Radwaste Systems Applicant plans to use the Farley 1 solid waste processing system for both units. Staff concludes that proposed Farley Plant solid processing and drum storage facii' ties are adequate for both units.
14 Non-Radiolooical Environmental Technical Sceci fications Applicant has proposed specifications for environs around the Farley Plant. Staff is reviewing these specifications.
- 15. Revised Radiation Protection Features Applicant has provided additional information regarding the spent fuel trans fer tube, respiratory equipment, and radiation protection personnel at the plant. Staff is reviewing.
- 16. Revised Oceratino Personnel Requirements Minor changes in operations personnel requirements have been recorded in Amendments to the FSAR, and are under review.
17.
Revised Ouality Assuance Program Minor cnanges to tne Quality Assurance Program hasa been found to be acceptable.
- 18. Shared Systems Between Unit 1 and Unit 2 Shared portions of the cooling water systems and the onsite emergency
- electrical power systems (diesel generators) are under review to determine the acceptability of changes made since our previous safety evaluation in June,1977.
19.
Feedwater Pice Crackfy Applicant has been requested to inspect the feedwater piping of Farley 2 following hot functional testing, per I&E Bulletin 79-13 Rev. 2.
- 20. Confirmatory pioing Analysis Staff Consultants are performing an independent code analysis of the "A" Main Steam Line inside containment to confirm that stresses are within code allowable valves.
- 21. Q-List for Quality Assurance Program The staff is reassessing the list of safety related equipment required to ta included in the operations quality assurance program.
- 22. Containment Purge Valves Staff is evaluating the mechanical operability and containment functions of containment purge valves. A position regarding operability was transmitted to the applicant.
- 23. Revised Startuo Test Procram Minor changes in the program description in the FSAR are under review.
24 Reduced Startuo Physics Tests Applicant has proposed reduced physics tests, similar to those proposed by the applicant for North Anna. Staff is reviewing these.
- 25. Environmental Quali fication of Ecut onent Staff requested applicant to review equipment to show con formance to NUREG-0588.
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1 ENCLOSURE 2 L
LIST OF ATTENDEES NRC MEETING WITH ALABAMA POWER COMPANY JUNE 24, 1980 1
Nuclear Regulatory Commission 1
L. L. Kintner V. A. Moore G. W. Rivenbark i
T. L. Huang i
L. Phillips i
A. Schwencer R. L. Tedesco D. G. Eisenhut V. 6'conan
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R. Bosnak R. L. Ballard s
Southern Comoany Services, Inc.
T. M. Milton
- 0. Batum R. J. George Alabama Power Comoany-W. G. Hairston R. L. George R. P. Mcdonald
- 0. D. Kingsley F. L. Clayton 1
Westinghouse R. J. Sero J. L. Vota D. B. Pierce T. R. Puryear
. Bechtel A. A. Vreil i
i 1
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