IR 05000206/1979017
| ML13323A637 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 01/18/1980 |
| From: | Faulkenberry B, Andrea Johnson, Miller L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML13323A632 | List: |
| References | |
| 50-206-79-17, NUDOCS 8003050126 | |
| Download: ML13323A637 (8) | |
Text
U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION V
Report N /79-17, 50-206 DPR-13 Docket N License N Safeguards Group Licensee:
Southern California Edison Company 2244 Walnut Grove Avenue Rosemead, California 91770 Facility Name:
San Onofre Unit 1 Inspection at:
San Onofre December 10-13, 1979 Inspection conducted:
December_10_13,_1979 Inspectors:
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/F 1990 L. ler, Reae ctor
/bate'Signed
,o to LD ate Signed-A. J-nsf, Reat6. In pector aeSge JCs1&1r 11 o~rn, Re6actor pector DA e Signed rA. Chaffee, eacto Inspector Approved By:.
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s if S900 B. H. Faulkenberry,, ChieReactor Projects Section #2, bate Signed Reactor Operatio s and Nuclear Support Branch Summary:
Inspection on December 10-13, 1979 (Report No. 504667-174 Areas Inspected: Routine, unannounced inspection of quality assurance program; onsite review; procedures; plant operations; plant tour; and licensee's responses to IE Bulletins and Circulars. The inspection involved 72 inspector-hours by four NRC inspector Results: Of the six areas inspected, no items of noncompliance or deviations were identified in five areas; one apparent item of noncompliance (deficiency failure to report a degraded mode of operation - paragraph 2) was identified in one are.RV Form 219 (2)
S003050
- DETAILS 1. Persons Contacted J. Curran, Plant Manager
- G. Morgan, Superintendent, Units 2 and 3
- J. Dunn, Project QA Supervisor M. Wharton, Supervising Engineer, Unit 1
- S. Scholl, Associate Nuclear Engineer, Unit 1 B. Curtis, Plant Supervising Engineer
- J Tate, Supervisor, Plant Operations
- W. Frick, Nuclear Engineer The inspectors also interviewed several other licensee employees including licensed operator *Denotes those present at the exit intervie. Review of Plant Operations The inspectors reviewed the shift logs and operating records, including the following:
a. "Operator's Routine Test Check-Offs" and "Control Room Daily Log Sheets" for November 1-10, 1979 were completed in accordance with regulatory requirement b. Watch Engineer's and Control Operator's logs for November 1-10, 1979 appeared to provide sufficient detail to communicate plant status and significant events, including the November 7, 1979 480V Bus N failure. Log reviews by the operating staff during this period also appeared complet Station Incident Reports 79-35 through 79-39 were reviewed. These
.reports were reviewed by the licensee in accordance with regulatory requirements except for Station Incident Report 79-39, dated October 11, 1979. This report noted that at 0255 the loop "C" Tave channel failed low, causing the control rods to begin moving out, changing the pressurizer level control level, and changing the channel 3 variable low pressure trip setpoint to an erroneously low value. The operating logs for this date indicated that the control operator immediately took manual action to trip the affected channel and restore the degree of redun dancy required by Technical Specification 3.5.1.B. For the period from the failure of the Tave channel until the operator manually tripped the affected low pressurizer pressure channel, the facility was in a degraded mode, with less instrument redundancy than that
-2 required by Column II of Table 3.5.1 of the Technical Specification Contrary to Technical Specification 6.9.2.b(2) this condition was not reported within 30 days. (79-17-01)
This is an apparent item of noncompliance at the deficiency leve. Plant Tour The inspectors conducted a tour of the facility during which the follow ing conditions were observed:
a. Licensee monitoring of control room instrumentation was found to be in accordance with the licensee's regulatory requirements and commitments. The inspectors observed that in some instances follow ing a reactor startup the plant did not appear to be in "steady state conditions" when 01 S-3-3.13 "Reactor Power Calculations" was per formed, to set the power range gain signals, as required by the pro cedure. For example, on April 9 at 2:20 p.m. and on April 22, 1979 at 2:30 p.m. reactor power as recorded on NLR 1200-3 ramped steadily upward throughout the heat balance procedure. A licensee representa tive stated that this procedure would be revised to provide more detailed guidance to the operators regarding 1) what "steady state con ditions" are, and 2) what amount of change in nuclear power gain settings can be made without supervisory review or a calculation check. (79-17-02)
b. Radiation controls observed were properly establishe c. No significant fluid or steam leaks were observe d. No abnormal pipe vibrations were observed. The inspectors observed that considerable new pipe was being fitted up by contractor personnel, reportedly as part of the TMI lessons learned commitments made by the licensee. Several hydraulic snubbers were.checked for proper oil level and freedom of motion, and they appeared to be operabl e. Selected valves-in the refueling water supply system were verified to be correctly positione f. The control room was manned in accordance with the requirements of 10 CFR 50.54(v), the facility Technical Specifications and IE Bulletin 79-06C. Control room operators and supervisors appeared knowledge able about the reasons for selected annunciators. The shift turn over was observed, and appeared adequate to ensure system status continuit g. Fire extinguishers and alarms, fire watches and no smoking areas in the vicinity of the lube oil reservoirs and 4.16 KV room were observe No discrepancies were identified. Selected fire watches were inter viewed and they appeared to be both knowledgeable and conscientious about their responsibilitie h. The battery room ventilation system was observed to be operabl No items of noncompliance or deviations were identifie. Independent Inspection The inspectors observed in the December 7, 1979 edition of "Edison News",
an informal publication of Southern California Edison Company that the off site organization of the company would be changed as of January 1, 198 A new Department of Nuclear Engineering and Operations was to be formed from the nuclear functions currently assigned in the Engineering and Con struction Department and the nuclear functions currently assigned in the Power Supply Department, according to this article. Further, the article stated that the Vice-President for this department, the Vice-President for the Advanced Engineering Department, and the Vice-President for the Engi neering and Construction Department would report to the Executive-Vice President. A licensee representative confirmed this plan and stated his understanding that this change had been or would be submitted to the NRC as a Technical Specification change. The inspector stated that this reor ganization would be reviewed further at a subsequent inspection. (79-17-03)
No items of noncompliance or deviations were identifie. Bulletins The licensees responses to several IE Bulletins were reviewed as follows:
a. (Open)Bulletin 79-14 The inspectors reviewed the current status of the licensee's respons A licensee representative stated that the results of the licensee's inspections of inaccessible supports would be made by July 1, 1980, provided the facility returned to power in early June following its scheduled refueling outage. He also agreed to include in SCE's December 21, 1979 report a summary of the portion of the Bechtel-SCE contract which described the work which was done in producing those drawings which SCE has designated as "certified as-built."
This Bulletin remains open pending completion of the required licen see inspections and their review by the NR b. (Open)Bulletin 79-17 The licensee's response appeared adequate to the inspectors. How ever, to clarify that response, licensee personnel stated that a system-by-system count of ultrasonic inspections which were performed would be done to confirm their opinion that a minimum of 10% of the affected welds in each system were inspected. In addition, the inspec tors reminded licensee personnel that the licensee had agreed during inspection 79-14 to include their assessment of the effect of the near-ocean environment on exposed piping. A licensee representative confirmed this commitment and stated that the work, which was still in progress, would be reported when complet c. (Open)Bulletin 79-13 - Cracking in Feedwater System Piping The regional based and resident construction inspector observed the actions taken by the licensee in response to notifications of feed water system piping cracks prior to issuance of IE Bulletin 79-1 There observations are reported in Inspection Report 50-206/79-1 The licensee's written response to Bulletin 79-13 was received on time and includes the information required to be reported. The licensee's only exception is the requirement to volumetrically examine all feed water line welds up to the first piping support or snubber and high stress points in containment. This requirement is not applicable to this licensee since repairs and examinations were completed prior to issuance of bulletin 79-1 The licensee's written response includes adequate corrective action commitments based on information presented in the bulletin and the licensee's response. The licensee has commited to perform the volumetric and visual examinations required in items 2a and 2c of bulletin 79-13 rev. 1 at the next refueling outage, currently scheduled for the second quarter of 1980. Revision 2 to bulletin 79-13, paragraph 2a more specifically defines the areas to be volumetrically examined. (79-17-0d)
The inspector reviewed the revisions to the licensee's operating procedures S-3.5.20 "SIG High Energy Pipe Break", S-3-5.7 "Abnormal SIG Water Level", and S-3-5.23, "Reactor Coolant System Leak Proce dure", and verified that these revisions adequately addressed the requirements of the Bulleti This bulletin will remain open until completion and evaluation of examination required in paragraphs 2a and 2c of the bulleti II
-5 d. (Open)Bulletin 79-24 The inspector reviewed the licensee's contracted study for the San Onofre Site. This study predicted statistically that in forty years of operation San Onofre would experience 240 hours0.00278 days <br />0.0667 hours <br />3.968254e-4 weeks <br />9.132e-5 months <br /> of subfreezing weather, with at least three periods where temperatures would be below freezing for as long as seven ho8r The lowest temperature anticipated by this study was about 25 F. Licensee personnel stated that the operating procedures would be revised to include provisions for ensuring that systems remained operable under these condition The inspector stated that this approach would be evaluated after the revised procedures had been reviewed at a subsequent inspectio e. (Closed)Bulletin 79-21 The inspectors reviewed the licensee's response and the revised high energy line break procedure, S-3-5.20. The inspector stated that the licensee's revised procedures adequately complete the actions required by this Bulleti f. (Open) Circular 79-05 Licensee personnel confirmed that additional review by the station engi neering staff was being conducted regarding the possibility of mois ture incursion in stranded wire conductors. The inspector agreed that such a review seemed appropriate and would be reviewed at a subse quent inspectio No items of noncompliance or deviations were identifie. Procedures The following procedures were verified to have been reviewed and approved in accordance with the Technical Specifications:
S-3-Plant startup from cold conditions to minimum loa S-3-2.24 Two loop operation of reactor coolant system S-3-1.10 Seal water system and reactor coolant pump startup S-3-2.10 Startup,-normal operation, shutdown of the component cooling system S-3-2.20 Sphere enclosure building ventilation system S-11-1 Service water system S-3-2.22 Controlled area and sphere atmospheric control system S-6-6 Procedure for placing main transformer and auxiliary transformers
'A'
and 'B in service S-3-Loss of condenser vacuum S-3-Loss of containment sphere integrity S-3-5.12 Reactor control and protection system trouble
-6 S-3-5.21 Stuck control rod S-3-5.27 Earthquake S-I-1.64 Reactor Coolant Pump Maintenance S-M-4 Maintenance of Transformers S-I-1.14 General Maintenance Procedure S-I-1.18 Battery Maintenance S-I-1.14 Inspection, Repair, and Testing of Pressurizer Relief Valves 532 and 53 S-M-101 Rod Control System Maintenance Unit 1 S-S-9 Control of Temporary Modifications S-A-109 Station Documents. -
Preparation, Revision and Review The inspectors examined two Quality Assurance audits (501-16-79 & 501 87-79) that identified deficiencies; corrective actions for these defic ien 'cies have been initiated by the license To meet requirements of the facility Technical Specifications to comply with ANSI 18.7-1976; the licensee has contracted with NUS Corporation to review and rewrite all of the pro cedures. Also, the licensee has committed to have all emergency proce dures related to TMI findings completed by January 1, 198 Others will be completed by November, 1980. Further, the licensee's staff is review ing procedures as committments to other TI related finding The inspectors noted that it was not clear in the licensee's administra tive procedures what constituted adequate, periodic review of procedures and form The licensee committed to establishing criteria or guidelines for procedure and form review by the end of the spring refueling outage (est. April 1980). (79-17-05)
The inspectors also noted that procedures covering rod/rod control abnor malities or emergencies did not clearly define inoperable rods. Technical Specification 3.5.2 D. states that "no more than one inoperative rod shall be permitted during critical operation". The licensee committed to re viewing their procedures to clarify circumstances applicable to this specification. (79-17-06)
No items of noncompliance or deviations were identifie.7. QA Program The inspector examined changes made to the QA program manual during 197 The changes update the program by changing titles of personnel to be con sistent with reorganizations as a result of units no. 2 and no. 3 nearing the preoperational phase of constructio In addition the changes clar ified certain responsibilities and requirement I.e., the reporting requirements of 10 CFR part 21 have been specifically addressed in the pertinent procedure The inspector verified from licensee records and discussion with personnel for implementing the changes that the changes had been incorporated in the appropriate station instructions and that the responsible personnel were knowledgeable of the change No items of noncompliance or deviations were identifie.
On-Site Review Committee The inspector examined the records relative to the activities performed by the onsite safety review committee during the period of July 1978 thru November, 1979 and discussed the committee's activities with the respon sible licensee personne The inspectors examination included:
a. Charter of the Committee b. Plant Modifications c. Proposed Changes to Technical Specifications d. Reportable Occurrences e. Noncompliance items and Corrective Actions Proposed and Taken f. Meeting Minutes No items of noncompliance or deviations were identifie. Exit Interview The inspectors met with.licensee representatives (denoted in Paragraph 1)
on December 13, 1979 to summarize the purpose, scope and the findings of the inspection.