IR 05000312/1975010
| ML19317G656 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 01/07/1976 |
| From: | Crews J, Malmros M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML19317G641 | List: |
| References | |
| 50-312-75-10, NUDOCS 8003250711 | |
| Download: ML19317G656 (11) | |
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S. NUCLEAR REGULATOBY COMMIS."0N
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k*b.FICEOFINSPECTIONANDENFORC. 2NT
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REGION V
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50-312/75-10. '
'sIE Inspection Report No.
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P. O. Box '15830 License No.non_ca j
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Sacreic ::to, California 95813 *
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' Tacility Rancho Seco Category
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Location Clav Station. california
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Type of Facility PWR, B&W, 913 MWe (2772 MWt)
Type of Inspection Routine Unannounced
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Dates of Inspection December 15-18, 1975 Dates of Previous I pection September 2-5, 1975
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Principal Inspector N
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M. H. Malmros, Reactor Inspector
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i Acc m anying Inspectors None
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Other ccompanying Personnel: None i
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Reviewed by LDats J.
Cre k Chief, Reactor Operations and
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Nuclear Support Branch
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SUtHARY
Enforcement Action l
Records of material receiving inspections were not maintained for certain Class I spare parts.
(Paragraph 4ofDetails.)
Licensee Action on Previously Identified Enforcement Items Not applicable.
t Unusual Occurrences The circumstances and corrective actions described in licens' e Event e
Report Nos. 75-12 through 75-17 submitted by-the licensee were confirmed.
(Paragraph 2ofDetails.)
Other Significant Findings Current Findings A.
Plant operations were found consistent with the technical specifications.
(Paragraph 7ofDetails.)
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Turbine repairs and control rod drive stator replacement were 8.
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complete with startup testing in progress.
(Paragraph 11 of
Details.)
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The licensee's response to IE Bulletin 75-048 was verified.
(Paragraph 3ofDetails.)
- Status of Previously Reported Unresolved Items
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A.
Documentation inconsistencies in training records for the
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Operator Requalification Program were verified to have been corrected.
(Paragraph 10 of Details and IE Inspection Report
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No. 50-312/75-08.)
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Management Interview The results of the inspection were discussed with Messrs. Rausch and l
Rodriguez and other members of the licensee's staff at the conclusion of the inspection on December 18, 1975. The licensee representatives
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acknowledged the infraction related to material receiving inspection
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records and stated that they would evaluate their procedural controls for appropriate corrective action. The following items were identified
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by the inspector as open items for further evaluation during subsequent i
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A.
Completion of corrective action described in Licensee Event Report No. 75-15.
(Paragraph 2 of Details.)
B.
Completion of corrective action described in the licensee's response to IE Bulletin 75-048.
(Paragraph 3ofDetails.)
C.
Completion of surveillance testing required by technical
specification 4.5.2.1.B.2 (Paragraph 5 of Details.)
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DETAILS 1.
Persons Contacted R. Rodriguez, Manager, Nuclear Operations
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P. Oubre, Assistant Plant Superintendent, Operations
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R. Colombo, Technical Assistant R. Miller, Chemical / Radiological Supervisor
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D. Whitney, Plant Nuclear Engineer
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C. Linkhart, Assistant Instrumentation and Control Engineer
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W. Ford, Shift Supervisor / Training Coordinator
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~A. Locy, Electrical Maintenance Foreman j
F. Eisenhuth, Nuclear Engineering Assistant J. Sullivan, Quality Assurance Engineer
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J. Jewett, Quality Assurance Engineer J. Ravera, Manager, Purchases and Stores Department
N. Wood, Principal Buyer
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R. Lawrence, Mechanical Engineer
H. Heckert, Surveillance Scheduler F. Ozment, Mechanical Maintenance Foreman
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R. Daniels,. Electrical Engineer W. Guess, Administrative Assistant, Generation Engineering O
H. Funk, Plant Scheduler D. Gouker, Shift Supervisor
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B. Taylor, Test Technicain L. Bright, Facility Safety Technician F. Lopez, Warehouse Supervisor G. Albiani, Administrative Assistant, Nuclear Operations
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2.
Review of Nonroutine Event Reports
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Licensee Event Reports _Nos. 75-12 through 75-17 were submitted by I
the licensee since the previous inspection.
Based on an examination of facility records and discussions with licensee representatives,
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the inspector verified the following:
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a.
The cause of each event was identified and the details clearly reported to facility management.
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b.
The corrective actions described in report nos. 75-12, 13, 14, i
16 and 17 had been implemented by the licensee. The design change for the addition _of a drain valve to the hydrogen purge
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_ piping for the removal of condensation prior to use of the hydrogen purge blowers was being reviewed and was sceduled for
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actual installation by March 1976.
Upon installation of this
valve, the corrective action described in report no. 75-15 will
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i be complete.
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c.
The event reports had been reviewed by the Plant Review Conetttee.
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System and component failures have been reported to the plant
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staff for review and properly identified as reportable events when applicable.
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e.
The failure to properly perfonn snubber surveillance inspections (LER No. 75-17) was an item of noncompliance to Technical Specification 4.14 which was identified by the licensee.
3.
IE Bulletin Followup
The licensee had received IE Bulletin 75-08, PWR Pressure Instru-mentation, and a response was being prepared. The information contained in the licensee's response to IE Bulletin 75-048, Browns Ferry Fire, was verified. The status of the corrective action taken by the licensee in response to the deficiencies identified
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during the most recent fire inspection performed by NELPIA was examined and the following items remain as open items for completion by the licensee.
a.
Asbestos welding blankets need to be purchased for use during welding operations outgide the Machine Shop Area, b.
Fire alarm pull stations need to be installed in the Switchyard.
Control Building.
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4.
Frocurement
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Documentary evidence was available on site to demonstrate that
safety related spare parts were in conformance with procurement
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requirements. A review of procurement records for the following requisitions, for the systems indicated, verified that the purchase
specifications were properly reviewed and approved and specified
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applicable quality control inspection and record requirements.
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a. - Reactivity and Power Control System Requisition No. RS798G
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Auxiliary System Requisition No. RS 883G-1 c.
Electrical System Requisition No. RS616G-1
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Three safety related spare parts were randomly selected from the ready for issue storage area for examination with the following results indicated.
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a.
Each spare part was identified, handled and stored consistent with requirements in the licensee's administrative procedures and QA program.
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b. _ The vendor for each spare part was an " approved vendor" in accordance with the QA Program requirements.
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c.
Receiving inspection records were not available for spare parts
with stock numbers 4788 and 011140.
Discussions with the Ware-house Supervisor revealed that procedural guidance did not i
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clearly require the filling out of a Receiving Inspection Data Report (RIDR). Discussions with the Quality Assurance Engineer indicated that the "bc,iler plate" Receiving Inspection Daca
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' Report (RIDR) which had been supplied to the receiving inspection j
personnel was to be used for documenting Class 1 material in-
spections unless a specially '.repared RIDR accompanied the
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purchase requisition. This misunderstanding in the use of the i
" boiler plate" RIDR has resulted in the failure to provide a
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record of receiving inspections performed by warehouse personnel on certain Class 1 material which appears contrary to the re-quirements of Quality Assurance Procedures No. 6, Inspection Planning and No.10, Receiving Inspection.
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Surveillance
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The surveillance test program implemented by the licensee in response to surveillance requirements of the technical specifications was examined during the inspection. A review of selected surveillance procedures, records of results, and schedules verified that the program was consistent with the requirements of the~ technical speci-fications.- The licensee has identified the need to develop a pro-
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cedure for the performance of the surveillance test required by Technical Specification 4.5.2.1.B., Reactor Building Emergency
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Cooling System. The specific measurement of nuclear service cooling water flow and air flow of each reactor building emergency fan cooler had not been included in the existing refueling interval surveillance
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procedures.
The issuance of an approved procedure and performance
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of the surveillance test will be evaluated during subsequent inspec-
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' tions. Specific surveillance tests that were examined in detail in-cluded the following:
a.
200.08 Monthly RPS Surveillance
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b.
201.08: Surveillance of Hydrogen Purge System
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c.
203.01 High Pressure Injection System d.
203.02 Qsrterly HPI System
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203.08 Core Flooding System f.
204.01 Reactor Building Spray System g.
206.01 Biannual Diesel Generator Inspection h.
206.02 Diesel Generator SFAS Start Test
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206.03 Monthly Diesel Generator Test
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j. 207.03 Testing of Pressurizer Code Safety Valves
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208.03 Control Rod Program Verification
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209.01 Reactivity Balance (Anomalies)
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210.02 Main Steam Safety Valves n.
210.03 Turbine Steam Stop Valves 6.
Maintenance Records of activities associated with maintenance of the following j
items were examined by the inspector.
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Missle Shield
. Steam Generator Blowdown Valves
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Auxiliary Feedwater Pump Turbine
' Boric Acid Pump Inverter Circuitry Reactor Building Spray Pump
Control Rod Drive Stators
. Reactor Coolant Pump Seals
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From the information in the records related to the above maintenance items and through discussions with licensee representatives, the inspector. verified the following:
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a.
Required administrative approval's were obtained prior to
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initiating the work.
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The maintenance was performed in accordance with approved
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procedures.
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The maintenance was inspected in accordance with the licensee's j
QA Program requirements.
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d.
Prior to returning the' item to service, appropriate functional tests were performed.
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Quality control ~ records were available to appropriately show that the maintenance activities were properly performed.
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The maintenance work was performed by qualified personnel.
g.. Limiting conditions for operations of the reactor were met i
during the maintenance activities.
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Review of Plant Ooerations a.
Shift Logs and Ooeratino Records Operating logs and records, maintained in accordance with the licensee's administrative controls, were examined for the period October 27 through November 23, 1975. The following observations were noted by the inspector.
(1) The log sheets were complete and contained appropriate si7 natures and initials of personnel responsible for log entries and log review.
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l (2)' Abnormal conditions described in the logs contained
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sufficient information to communicate equipment or system status and results of corrective action taken.
(3) Special Orders-(Nos. 46-75 through 70-75) issued by the Assistant Plant Superintendent, Operations, did not conflic' with the intent of the Technical Specifications.
(4)JumpersandbypassesissuedinaccordancewithAP-26,
" Abnormal Tag Procedure", did not contain bypassing discrepancies with technical specification requirements.
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Site Tour
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l A tour of the facility, including controlled ai: cess areas in
the reactor building and auxiliary building, was conducted with
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the plant in a cold shutdown condition for turbine repairs.
No signs.of abnormal piping vibrations or fluid leaks from facility power operation were observed.
Proper position of
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valves in the Nuclecr Service Cooling System and the Nuclear Raw Water System was verified by direct observation.
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The instrumentation for reactor coolant system pressure, source range neutron counts and concentrated boric acid tank level and temperature were verified to be operational. Containment re-quirements were consistent with the cold plant shutdown conditions.
Clearance tags issued under Clearance Nos. 10472,10414 and 10435 were examined and found to have been installed with the appropriate installation and approval signatures consistent with the requirements of AP-4, " Tagging System."
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The control room manning was in conformance with the facility technical specifications.
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8.
Nonroutine Event Review
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Based on discussions with licensee representatives and a review of facility precedures, the licensee's system for identification, reporting and review of safety related events described in the technical specifications, was found to be functioning effectively.
Responsibilities and methods to assure conformance to technical specification requirements for the resolution of safety related s
events, including maintenance and testing activities, were pre-y scribed in the following procedures.
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AP-1 Responsibilities and Authorities b.
AP-22 Reporting of Abnonnal Occurrences
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AP-23 Control Room Watch Standing d.
AP-28 Post Trip Transient Report
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Fire Prevention / protection Based on discussion with licensee representatives and an examin-
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nation of facility procedures and records, the licensee's actions j
to emphasize fire prevention / protection controls as a result of'
the Browns Ferry fire were verified to have become a permanent part of facility procedures and practices.
The following obser-vations and findings were made by the inspector.
a..
Work control procedures have been implemented that provide for. the review and approval of maintenance prior to pe:-
formance within the facility.
Procedures require special authorization including the posting of a fire watch, if
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-10-applicable, for activities involving welding, open flame or the use of other ignition sources.
Procedures examined in-cluded the following:
AP-3-Work Request AP-5 Safety Manual AP-29-Use and Control of Combustible and Ignition Sources
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M-ll3 Welding Procedures AP-500 ~ Emergency Plan - Section C b.
Quality assurance procedures have been established that re-
. quire periodic audit of the maintenance activities to verify
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implementation of the requirements in the procedures listed above.
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c.
Cable penetration seals (fire barriers) are modified or repaired in accordance with procedure EM-158, " Resealing
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and Maintaining Fire Barriers for Electrical Cables."
Tests have been performed onsite to verify the fire retar-dent characteristics of material used to modify or repair fire barriers.
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Fire drills have been performed quarterly as required by Section C of the Emergency Plan.
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Emergency procedures exist that provide for alternate methods of decay heat removal should the normal'and preferrred alter-nate means of heat removal be unavailable.
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Fire inspections have been performed on a periodic basis by NELPIA (fire insurance inspection), and by SMUD personnel.
The results of the most recent fire inspection were examined and the identified daficiencies were verified to have been corrected except for those items described in Paragraph 3 of Details described above.
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The inspector toured the facility in company with a member of the plant staff and found the general housekeeping and
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operability of the fire alarms and extinguishing equipment
consistent with standard fire safety practices.
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10. Training The individual training records of personnel participating in the licensed operator requalification program were examined.
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records were found to be current and accurately represent the O
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v requalification training of facility personnel. The inconsisten-cie.; in training documentation described in IE Inspection Report
~No. 50-312/75-08 were observed to have been corrected by the licensce, and the item is considered closed.
11., Turbine Outage-Turbine repairs resulting from the loss of turbine blades which caused shutdown of the facility on June 30, 1975, have been com-pleted. Both low pressure spindles had been replaced, and the turbine systems were in the process of being started up during the dates of this inspection, Initial rolling of the turbine was
' scheduled for the last week in December 1975, with synchronization of the generator to the grid scheduled for approximately January 1, 1976.
The control rod drive stator replacements had been completed. Testing in accordance with special test procedure (STP-804) was in progress.
When completed, testing in accordance with STP 804 will verify the following:
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Stator electrical characteristics.
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Leak tightness of CRDM cooling water system.
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Low flow interlock in the CRDM cooling water system with the power supply breakers to the CRDM stators.
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Control rod travel times consistent with FSAR for reactivity insertion rates.
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Compliance to Technical Specifications 4.7.2, Control Rod Program Verification, and 4.7.1, Control Rod Drive System Functional Tests.
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