ML13331B075
| ML13331B075 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 10/13/1988 |
| From: | Trammell C Office of Nuclear Reactor Regulation |
| To: | Baskin K Southern California Edison Co |
| References | |
| TAC-67902 NUDOCS 8810260508 | |
| Download: ML13331B075 (4) | |
Text
October 13, 1988 Docket No.:
50-206 DISTRIBUTION:
Docket File NRC & LPDRs CTrammell (2)
GHolahan Mr. Kenneth P. Baskin JLee Vice President OGC-White Flint Southern California Edison Company PDV Plant File 2244 Walnut Grove Avenue EJordan Post Office Box 800 JPartlow Rosemead, California 91770 ACRS (10)
JStewart
Dear Mr. Baskin:
SUBJECT:
NUCLEAR INSTRUMENTATION SYSTEM UPGRADE (TAC NO. 67902)
Re:
San Onofre Nuclear Generating Station, Unit No. 1 In reviewing your amendment request of April 15, 1988 relating to the nuclear instrumentation system upgrade, we have determined that the additional infor mation identified in the enclosure is needed to continue our review. In order to maintain our review schedule, your response is requested within 30 days of your receipt of this letter. These questions were discussed with your previously in August.
The reporting and/or recordkeeping requirements contained in this letter affect fewer than ten respondents; therefore, OMB clearance is not required under Pub. L.96-511.
Please contact us if you should have any questions regarding this request.
Sincerely, original signed by Charles M. Trammell, Senior Project Manager Project Directorate V Division of Reactor Projects -
- III, IV, V and Special Projects
Enclosure:
Request for Additional Information cc w/enclosure:
See nex page D
D5 DRSP/D:PD5 T m ell:bm GKnighton 88 1o A/%
/888 fol 8810260508 S8)1013 PDR ADOCK 05000206 P
ow UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 October 13, 1988 Docket No.: 50-206 Mr. Kenneth P. Baskin Vice President Southern California Edison Company 2244 Walnut Grove Avenue Post Office Box 800 Rosemead, California 91770
Dear Mr. Baskin:
SUBJECT:
NUCLEAR INSTRUMENTATION SYSTEM UPGRADE (TAC NO. 67902)
Re:
San Onofre Nuclear Generating Station, Unit No. 1 In reviewing your amendment request of April 15, 1988 relating to the nuclear instrumentation system upgrade, we have determined that the additional infor mation identified in the enclosure is needed to continue our review. In order to maintain our review schedule, your response is requested within 30 days of your receipt of this letter. These questions were discussed with your previously in August.
The reporting and/or recordkeeping requirements contained in this letter affect fewer than ten respondents; therefore, OMB clearance is not required under Pub. L.96-511.
Please contact us if you should have any questions regarding this request.
Sincerely, Charles M. Trammell, Senior Project Manager Project Directorate V Division of Reactor Projects -
- III, IV, V and Special Projects
Enclosure:
Request for Additional Information cc w/enclosure:
See next page
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 1600 Pacific Highway Room 335 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
Enclosure REQUEST FOR ADDITIONAL INFORMATION NUCLEAR INSTRUMENTATION SYSTEM REPLACEMENT AND TECHNICAL SPECIFICATION CHANGE AT SAN ONOFRE UNIT 1 (TAC NO. 67902)
- 1) In Attachment 3 (Safety Review Report) of the April 15, 1988 submittal, the statement is made (page 1) that "the basic design is very similar to that supplied by Westinghouse to a number of other nuclear plants."
Identify the plants which have the very similar NIS.
- 2) Appendix C to the Safety Review Report identifies several pieces of equipment for which complete qualification or additional qualification is required.
Identify any equipment which will not have the necessary environmental and seismic qualification completed prior to restart.
- 3) In Attachment 2 (Proposed Technical Specifications) several changes have been made to make these Tech Specs more consistent with the Standard Tech Specs.
Table 4.1.1 of the proposed Tech Spec is not in complete agreement with the Standard Tech Spec in that the surveillance modes are not included. They should be included or justification for exclusion should be provided.
- 4) Explain in more detail what happens upon loss of power to the NIS and when power is restored following the loss of power. In particular, address the impact upon the memory constants and actions needed to assure operability upon repower.
- 5) Provide an explanation of the particular Verification and Validation Plan used for the development of NIS software. Address how you comply with R.G.
1.152 "Criteria for Programmable Computer System Software in Safety-Related Systems of Nuclear Power Plants" and provide a comparison with ANSI/IEEE 7-4.3.2-1982 "Application Criteria for Programmable Digital Computer Systems in Safety Systems of Nuclear Power Generating Stations."
- 6) Provide a more detailed hardware description including input/output capabilities, sampling rates, testing rates (manual or automatic), setpoint adjustment method and degradation recognition.