IR 05000312/1978011
| ML19309A206 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 07/11/1978 |
| From: | Canter H, Crews J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML19309A203 | List: |
| References | |
| 50-312-78-11, NUDOCS 8003260911 | |
| Download: ML19309A206 (3) | |
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O U. S. NUCLEAR REGUIATOKY COMMISSION OFFICE OF INSFECTION AND ENFORCEMENT
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REGIDN Y
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Report No. 50-312/78-11
50-31 2 tic yo,-DPR-54 Safeguards Group Docket No.
Licensee:
Sacramento Municipal Utility District P. O. Box 15830 Sacramento, California 95813 Rancho Seco Facility Name:
Rancho Seco Inspection at:
Inspection conducted: June 28, 1978 Inspectors:
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J y[f H. L. Canter, Reactof Inspector
' Date Signed Data Signed Dace Signed i
Approved By:
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J. L. Crews, Chief,.fleactor Operations and Nuclear D'atefSigned Support Branch
Inspection on June 28, 1978 (Report No. 50-312/78-11)
Areas Inspected: Routine, unannounced inspection on June 28, 1978 of followup on Licensee Event Reports and the use of chemical decontamination solutions. The inspection involved three inspector hours onsite by one NRC inspector.
Results: No items of noncompliance or deviations were identified during the inspection.
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RV Form 219 (2)
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DETAILS
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1.
Persons Contacted
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- R. Colombo Technical Assistant J. McColligan, Engineering /QC Supervisor R. Miller, Rad-Chem. Supervisor J. Franaszek, Senior Health Physicist, State of California
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Department of Industrial Relations
- I. Goldberg, Health Physicist, State of California Department,of Health
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The inspector also talked with and interviewed several other licensee employees, including members of the technical and engineer-ing staff, technicians and a shift supervisor.
- Denotes those present at the exit discussion on June 28, 1978.
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Chemical Decontamination The objective of this inspection item was to verify that licensees using chemical decontamination solutions have taken adequate steps to prevent the uncontrolled introduction of decontamination solutions or their residues into components within the reactor coolant pressure
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boundaries of operating reactors.
The inspector verified that the licensee has not used nor does not plan on using chemical decontamination solutions on primary system components.
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This item is closed.
3.
Licensee Event Followu2 June 21, 1978 - DHR Pump Seal Failure The Region V office was informed of a pump seal leak in the "B" Decay Heat Removal Pump. The plant was in the cold shutdown con-dition wf th the "A" pump in operation, and the "B" pump in standby.
The first indication of leakage was a decreasing make-up tank level that was noticed at 0100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> on June 21, 1978.
The level was dropping at about five inches per hour (0 33 gal per inch). The licensee discovered the location of the seal leak in "B" DHR Pump at about 0400 on June 22, 1978. At that time, the leak was estimated at 1-2 gpm. Since "A" Decay Heat Removal System was already in service, tne "3" Pump was promptly valved out and placed under clearance for seal replacement.
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Because the plant was at cold shutdown conditions TS3.3.1 which requires both pumps to be operable while critical, was not appli-cable. However, surveillance TS4.5.3.1 limits the maximum allowable leakage from the decay heat. removal system components to 0.63 gallons per hour, so this event was considered by the licensee to be reportable within 30 days.
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The cause of the leak was apparently due to normal seal degra-
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dation. The corrective action consistad of replacing various seals i
and rings in the "B" Decay Heat Removal Pump.
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Test procedure SP203.09 D. H. System Leakage Surveillance Test, was perfonned on June 25, 1978. The test indicated zero leakage for both loops. The results were reviewed by supervisory personnel on. June 26, 1978.
A review of air sample records indicated levels of 200-300 cpm in the DHR east room at the time of the seal leakage problem. The warning level in this area is 1400 cpm and the alarm point is 14,000 cpm. The air sample monitor for this room was indicating about 300 cpm at the time of the inspection.
The event did not involve operation in such a manner as to represent a hazard to health and safety of the public or environment. No
items of concompliance or deviations were identified.
This item is closed.
4.
Exit Interview The inspector summarized the scope and findings of the inspection with a licensee representative and a State of California repre-sentative (denoted in Paragraph 1) at the conclusion of the inspection on June 29, 1978.
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