IR 05000206/1979006
| ML13323A592 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 05/10/1979 |
| From: | Canter H, Faulkenberry B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML13323A591 | List: |
| References | |
| 50-206-79-06, 50-206-79-6, NUDOCS 7906250472 | |
| Download: ML13323A592 (3) | |
Text
U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION V
Report No. 50-206/79-06 Docket No. 50-206 License N DPR-13 Safeguards Group Licensee: Southern California Edison Comany P. 0. Box 800, 2244 Walnut Grove Avenue Rosemead, California 91770 Facility Name:
San Onofre Unit 1 Inspection at:
San Onofre Site Inspection conducted: April 10-11, 1979 Inspectors: '
,
1(011 4c H. L. Canter, Reactor Inspector ffate Signed Date Signed Date Signed Approved By:
0__________________
-/V/e B. H. Faulkenberry, Chief-,--Reacr Project Section 2 Date gigned Reactor Operations and N clear Support Branch Sumrmary:
Special Inspection on April 10-11, 1979 (Report No. 50-206/79-06)
Areas Inspected:
Briefing on the Three Mile Island events of March 28, 1979; verification of the dissemination of information contained in IE Bulletin 79-05A; and, examination of the licensee's review of plant features at Westinghouse facilities which may be similar to the Three Mile Island design. The inspection involved 12 inspector-hours by one NRC inspecto Results:
No items of noncompliance or deviations were identifie RV Form, 19 (2)
79,062509
DETAILS 1. Persons Contacted
- J. Curran, Plant Manager
- R. Brunet, Superintendent, Unit 1 The inspector also interviewed several other employees includ ng reactor operators and maintenance personne *Denotes attendance at exit intervie. Three Mile Island Briefing On April 10-11, 1979, the inspector covered the following identified material in a series of briefings he held for approximately 60 licensee personne The attendees consisted of Administrative, Maintenance, Chemistry and Radiation Control, Instrumentation and Control, Operations, and Management personne Question and answer sessions were held during and after each of these briefing Items 1-6 to I.E. Bulletin 79-05A (IEB 79-05A), Nuclear Incident at Three Mile Island ii. Paragraph 3 to IEB 79-05 iii. Paragraph 4 to IEB 79-05 iv. The sequence of events as described in IEB 79-05. Dissemination of Bulletin Information The inspector verified that IEB 79-05A was widely routed to onsite personne At the time of this inspection, not all personnel had read the complete bulletin, but a licensee representative stated that the information is available for all who want to review i Shortly after the Three Mile Island (TMI) event various licensee management personnel briefed site personnel on the TMI inciden At the time of the inspection another such briefing was being planne. Three Mile Island Action Plan As of April 9, 1979, based on the licensee's understanding of the TMI scenario, the following tentative action plan had been develope a. SCE will take an active part in.the NSSS vendor's short and long term Utility Action Plan b. Additional training may be provided for operators which emphasizes the need for returning systems to normal after testing or maintenanc Procedures governing activities in b. above may be examined to determine the need for revision to emphasize this requiremen d. Emergency Procedure S-3-5.4, "Pressurizer Relief or Safety Valve Trouble" was revised to emphasize the need for prompt action to isolate a faulty valve, and to identify that a faulty valve may lead to the same affect as a small break loss of coolan e. Additional training may be provided for the operators empha sizing the need for maintaining the reactor coolant system subcoole f. Procedures associated with e. above may be revised to reflect these concern g. The following procedures may be reviewed and/or revised: S-2-1 Main Feedwater Pump Operation ii. S-2-2 Operation of Condensate Pumps ii S-2-13 Auxiliary Feedwater Pump Operation and Testing iv. S-3-5.5 Loss of Coolant S-3-5.7 Abnormal Steam Generator Water Level v S-3-5.24 Cold Water Accident vi S-3-5.25 Failure of Pressurizer Pressure Control viii. S-3-5.31 Steam Generator Tube Failure ix. S-0-108 Locking of Critical Valves The licensee expects to finalize these plans and to have necessary revisons completed by May 15, 197.
Exit Interview The inspector met with the licensee personnel denoted in Para graph 1, at the conclusion of this inspection on April 11, 197 The inspector summarized the purpose, scope and findings of this inspection. No items of noncompliance or deviations were identified.