IR 05000312/1982021
| ML20054J353 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 06/09/1982 |
| From: | Canter H, Obrien J, Thomas Young NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML20054J345 | List: |
| References | |
| 50-312-82-21, NUDOCS 8206280527 | |
| Download: ML20054J353 (8) | |
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U. S. NUCLEAR REGULATORY COMMISSION
REGION V
Report No. 50-312/82-21 (OPS)
Docket No. 50-312 License No. DPR-54 Safeguards Group Licensee: Sacramento Municipal Utility District P. O. Box 15830 Sacramento, California 95813 Facility Name:
Rancho Seco Unit 1 Inspection at:
Herald, California (Rancho Seco Site)
Inspection conducted: May 3 to June 1, 1982 h
Inspectors:
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. Canter, Seni Reside I pectof Date Signed del Mi 0 lbt, d-9- L2
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i P.~%3rien,UnitResJoent Inspfc; tor (
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Approved by:
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T.7 oung, Jr., Chief @actorPrpje Section 2 Date Signed Reactor Operations Wrojects Bean Sunmary:
Inspection between May 3 to June 1, 1982 (Report No. 50-312/82-21)
Areas Inspected: Long term shutdown activities; maintenance observations; surveillance observations; review of plant operations; receipt of new fuel; parti-cipation in NRR/ Licensee meetings; licensee event report follow-up; follow-up on Headquarters request; follow-up on Regional requests; and independent inspection effort. The inspection involved 162 inspector hours by the Resident Inspectors.
Results: Of the ten areas inspected, no items of noncompliance or deviations were identified.
r206280527 820611 PDR ADOCK 05000312 O
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DETAILS 1.
Persons Contacted
- R. Rodriguez, Manager, Nuclear Operations
- P. Oubre', Plant Superintendent
- D. Blachly, Operations Supervisor E. Bradley, Emergency Planning Coordinator
- R. Colombo, Technical Assistant
- G. Coward, Maintenance Supervisor
- S. Crunk, Associate Nuclear Engineer D. Gardiner, Senior Chemical and Radiation Assistant F. Kellie, Assistant Chemistry and Health Physics Supervisor
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R. Miller, Chemistry / Radiological Supervisor J. Newey, Senior Chemical and Radiation Assistant
- T. Perry, On-site Quality Assurance Supervisor.
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J. Price, Surveillance Test Coordinator
- L. Schwieger, Quality Assurance Director.
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- B. Spencer, Shift Supervisor T. Tucker, Planner / Scheduler
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J. Uhl, Mechanical Engineer
- D. Whitney, Engineering and Quality Control Supervisor B. Wichert, Plant Mechanical Engineer
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The inspectors also talked with and interviewed several otU r licensee employees, including members of the engineering, mainJ
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tenance, operations, and quality assurance (QA) organizations.
- Denotes those attending the exit interview on June 1,1982. _
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Long Term Shutdown Activities The plant was in cold shutdown for the entire month to perform repairs to the "A" and "B" High Pressure Injection Nozzles and Thermal Sleeves, and the Aux'iliary Feed headers in both Once-Through-Steam Generators (OTSGs).
During the report period, the inspectors observed control room operations, reviewed applicable logs, and conducted discussions with control room operators. The inspectors verified that sur-veillance tests required during the shutdown were accomplished, reviewed tagout records, and verified containment integrity. Tours of the Auxiliary Building and Reactor Building, including exterior areas were made to assess equipment conditions and plant conditions.
Also, the tours were made to assess the effectiveness of radiological controls and adherence to regulatory requirements. Maintenance work requests were verified to have been -initiated for equipment maintenance. The inspectors observed plant housekeeping / cleanliness conditions and looked for potential fire hazards. The inspectors, by observation and direct interview, verified that the physical
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security plan was being implemented in accordance with the station
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security plan. The inspectors reviewed the licensee's jumper / bypass controls to verify there were no conflicts with technical specifications.
Finally, the inspectors witnessed portions of the radioactive waste systems controls associated with radwaste shipments and solidification.
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The following is a summary of information about the two significant
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items which have kept the plant shutdown since April 2,1982.
By the end of April 1982, the repair work on HPI "A" and "B" nozzles
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was complete except for a system hydrostatic test which will be performed prior to startup of the unit.
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HPI Nozzle "A" Repairs The licensee removed the defective safe-end, ell, and portions of the 2.5 inch makeup pipe. Then dye penetrant exams of the nozzle
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to cold leg inner radius cladding, plus areas of wear on the bore of the nozzle cladding, were performed.
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Ultrasonic exams of the inner radius lose metal from the cold leg
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nozzle outer surface were then performed. The licensee then replaced the safe-end and thermal sleeve with new configurations as supplied
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by B&W. They also installed a new ell and pipe spool piece, using welding and nandestructive examination procedures referencing ASME Section XI, Summer 1974 addenda. The licensee must submit an analysis per 10 CFR 50.59 to address continued operations with the
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missing thermal sleeve. The licensee also has committed to an augmented inspection portion of the ISI program to monitor and verify the new thermal sleeve's position.
(See LER 50-312/82-09 Follow-up, dated April 29,1982.)
HPI Nozzle "B" Repairs
Essentially the same work was done for this nozzle.
Since the "B"
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thermal sleeve was not missing, a 10 CFR 50.59 analysis was not necessary. The same commitment to nonitor the "A" thermal sleeve's position exists for this side too.
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Auxiliary Feedwater Internal Header Repairs Since discovering the damaged internal headers in April 1982, the licensee has gone ahead with designing and installing an external feedwater header on each OTSG. The resident, inspectors have reviewed the licensee's QA/QC program and management controls for these repairs. They will continue to review these programs as changes occur.
In addition, the inspectors have been monitoring repair
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activities. As of this writing, six holes have been drilled through the "B" 0TSG shell and two through the shroud. Appropriate 10 CFR 50.59 reviews have been made for this work. The licensee is-looking towards a July 7,1982 OTSG hydrostatic test and a plant startup commencing mid-July.
No items of noncompliance or deviations were identified.
3.
Maintenance Observations The inspectors observed portions of the maintenance activities listed below and verified that work was accomplished in accordance with approved procedures, that work was accomplished by qualified personnel, that provisions for stationing a fire watch to oversee activities involving welding and open flame were complied with, and that LC0 requirements were met during repair.
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Flange repair on discharge of the "B" Reactor Building Spray Pump b.
Diesel driven fire pump maintenance c.
NSRW leak on "B" Reactor Building Spray Pump d.
"A" and "B" HPI nozzle repairs e.
Mockup training for drilling 5" holes in OTSGs No items of noncompliance or deviations were identified.
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Surveillance Observations The inspectors observed portions of the below listed surveillance testing to verify that the ' tests were covered by properly approved procedures, that the procedures used were consistent with technical specification requirements, that minimum crew requirements were met, that test prerequisites were completed, that special test equipment was calibrated and in service, and.that the test results were adequate.
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SP203.07C
"A" NSRW system quarterly surveillance b.
SP201.03C - Monthly surveillance of plant fire pump and power supplies c.
SP206.03B - Monthly "B" diesel surveillance No items of noncompliance or deviations were identified.
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5.
Review of Plant Operations During May 1982, the inspector reviewed the following activities:
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On May 18, 1982, the resident inspector attended a training session for county planners on the l subject of Relocation Drill and Congregate Care. The session was held at Micke Grove Park in Stockton, California. The training'and exercise involved personnel from the three counties that surround the Rancho Seco plant (Sacramento, San Joaquin, and Amador), FEMA; and the Red Cross. The San Joaquin County personnel, along with the Utility, hosted the training and demonstrated their (1) check-
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in and reception procedures and (2) ability to provide housing, emergency notification of relatives, food, pet control, child.
care, and decontamination of the evacuated citizens.
The inspector verified that the agencies.were familiar with
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their role in the emergency plan. The inspector also_ observed ~
an emergency drill and verified that the licensee has a program for correcting identified discrepancies. He also verified that equipment disrupted during the drill was returned to its proper location after the drill, b.
On May 24, 1982, both resident inspectors witnessed a test of one of the emergency sirens. Upon. completion of the test, the inspector verified the equipment was restored to_ a' proper lineup.
No items of noncompliance or deviations were identified.
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Receipt of New Fuel The resident inspector verified prior to receipt of new fuel that technically adequate, approved procedures were available covering
the receipt, inspection, and storage of new fuel.
He observed receipt inspection and storage of five new fuel elements and verified
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these activities were performed in accordance with the licensee's
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procedures.
Finally, the inspector verified that the licensee followed up resolutions of deficiencies found during new fuel
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inspections.
No items of noncompliance or deviations were identified.
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Participation in NRR/ Licensee Meetings On May 7, 1982, the Senior Resident Inspector attended a a.
meeting in Washington, D.C., with the NRR staff and the B&W owners group concerning an update on causes and effects of the HPI nozzle crack issue.
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On May 13, 1982, both resident inspectors attended a meeting at the licensee's headquarters in Sacramento, California. The attendees included members of the licensee's staff, the NRC's NRR staff, and the NRC's Region V operations staff. The purpose of the meeting was to solicit the licensee's comments on setting up a management control system to track outstanding items and to discuss proposals for a new method with which the NRC imposes new requirements on the nuclear industry.
No items of noncompliance or deviations were identified.
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Licensee Event Report Follow-up Through direct observation, discussions with licensee personnel, and review of records, the following event report was reviewed to determine that reportability requirements had been fulfilled, and immediate corrective action was accomplished in accordance with technical specifications.
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LER 81-11 (OPEN): Spray Additive Tank Check' Valve Failures:
The inspectors reviewed the circumstances surrounding this event and feel that corrective action to prevent recurrence was not adoressed in the LER or in the Plant Review Committee discussion of this event.
Further, the inspectors have determined that there is a possibility of sodium hydroxide entering the primary system through the Reactor Building spray system. The probability 'of this occurring has not been determined, but based on this event and a lack of preventative maintenance on Containment Building Spray. (CBS)
system valves, the inspector has decided to fcrward information on this event and the CBS system to the Region for assistance.
This LER will remain open pending regional review.
No items of noncompliance or deviations were identifie..
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Follow-up on Headquarter's Requests During the month of May 1982, personnel from the NRC Headquarters in Bethesda, Maryland, requested information from the Reside it Inspectors about the operation, design, and maintenance of the Rancho Seco power plant.
Information was obtained and transmitted to the NRC Headquarters regarding:
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Refueling surveillance and ISI inspection schedules b.
Inspection Outstanding Items List c.
High Pressure Injection nozzle repairs d.
Auxiliary feedheader inspection and repair, c.
High Pressure Injection pump lube oil cooler modifications f.
Tower Crane commitments: On May 25, 1982, the ~ licensee comaleted the final commitment concerning this issue by taking down tie Tower Crane.
It is r.o longer required for construction!of the Nuclear Service Electrical Building. Unresolved item (81-20-01). is closed.
J No items of noncompliance or deviations were identified.
10;. Follow-up on Regional Requests During the month of May 1982, personnel from the Region V office of the NRC in Walnut Creek, California, requested information from the Resident Inspectors regarding the operation and maintenance of the Rancho Seco power plant.
Information was obtained and transmitted to the Region V office concerning:
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Maintenance and repairs being conducted b.
Nuclear Service Electrical Building c.
New fuel receipt d.
Radioactive waste shipments e.
Licensee's Part 21 report of bad electrical cable f.
Emergency Sirens installation and testing No items of noncompliance or deviations were identifie _.
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Independent Inspection Effort
Discussions were held between the resident inspectors and operations,
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security, and maintenance personnel in an attempt to better understand
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problems they may have which are related to nuclear safety. These discussions will continue as a standard practice.
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On numerous occasions, during the month of May 1982, the resident
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held by the Planner / Scheduler Office to provide all disciplines
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onsite with an update on the plant status and ongoing maintenance
work.
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In addition to the above, independent inspection effort was performed on the following items:
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Plant emergency conmunications
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Review of plant maintenance procedures associated with HPI nozzle repairs, Auxiliary feed header repairs, and QC procedures
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NSE8 construction and licensee control of onsite contractors
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d.
Control Room Operator Medical problem: The licensee informed
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the resident inspectors of an incident in which a licensed
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Control Room operator was taken to a doctor due to an apparent
" diabetic" attack while on watch. The licensee took action to limit the licensed individual's activities until the doctor's
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medical program for rehabilitation has been satisfactorily 4 -
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completed. No effect on the plant was noted during this event
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because of ample technical specification required shift
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manning.
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The licensee will keep NRC's Operator Licensing Branch appraised
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to this operator's status until rehabilitation has been completed
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or the problem has reached another satisfactory conclusion.
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No items of noncompliance or deviations were identified.
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Exit Interview
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month and at the conclusion of the inspection on June 1, 1982 (see
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The inspectors met with licensee represeitatives throughout the
paragraph 1). The inspectors summarized their inspection findings.
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