IR 05000312/1977006
| ML19317F958 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 04/20/1977 |
| From: | Canter H, Crews J, Dodds R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML19317F955 | List: |
| References | |
| 50-312-77-06, 50-312-77-6, NUDOCS 8002210664 | |
| Download: ML19317F958 (12) | |
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N U. S. NUCLEAR REG'JIAIORY COMMISSIOh g
0FFICE OF INSPECTION AND ENFORCEMENI
REGION V
IE Inspection Raport No.
50-312/77-06 Licensee Sacramento Municipal Utility District Locket No.
50-312 P. O. Box 15830 License No.
DPR-54 Sacramento, Ca1ifornla 95813 Priority Facility Rancho Seco Category Location Clay Station Type of Facility PWR, B&W, 913 MWe (2772 MWt)
Type of Inspection Routine, Announced and Unannounced Dates of Inspection March 11 and April 4-7, 1977 Dates of Previous Inspection February 4 and 28,1977
[!/f 77 Frincipal Inspsetor
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R.'T.godds',
eac Inspector D
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Accompanying Inspectors
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H. L. Canter, Reactor Inspector Date Other Acccupanyir ersonnel:
J. L. Crews, i f/ Reactor Operations and Nuclear (April 7,1977)
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Reviewed by
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J.(. CM Chief, Reactor Operations and Nuclear
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i Support Branch l
l IE:V Form 219 l
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SUMMARY Enforcenent Act8on None.
Licensee Action on Previously Identified Enforcement Items A.
The licensee's commitments to (1) increase the extent of receiving inspection (2) evaluate and increase source inspection program activity, and (3) have Exxon Nuclear modify their Quality Assurance Program as described in SMUD's letter of January 10, 1977 were verified to have been accomplished.
(Item Closed.
Report No. 77-05)
B.
The turbine trip test was successfully completed on j
March ll,1977 in cortfomance with the licensee's letter of February 9,1977.
(Paragraph 3, Report No. 77-01)
Reportable Events A.
The circumstances and proposed corrective actions described O
in licensee Reportable Occurrence Report Nos. 76-16, 77-01, 77-02, and 77-03 were confirmed.
(Paragraph 2 of Details)
Design Changes Not applicable.
Other Significant Findings
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Current Findings I
A.
The turbine trip test demonstrated the reactor would not scram nor would technical soecification limits be exceeded should the turbine trip at 100 percent power.
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l (Paragraph 3 of Details)
B.
.The reactor continues to be operated at full power. The first refueling outage is still expected to commence in August or September 1977.
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It was verified that the' licensee has initiated an accelerated hydroitatic test program and was fonnulating an accelerated i
nondestructive testing program as stated in the licensee's reply to IE Circular 76-06 dated December 23, 1976.
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D.
It was verified that the licensee has the programs in effect
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for training and management audit as stated in the reply to IE Circular 76-07 dateu February 24, 1977.
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E.
1.icensee management has issued instructions to Maintenance j
and Plant Engineering requiring the testing of limitorque valves following maintenance. The question of checking the torque switch bypass settings had not yet been addressed.
(Item remains open)
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F.
The licensee determined and the inspector verified that the
" stab" connectors on motor control switch gear are not of the
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type to cause the problems identified in IE Circular 77-03.
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Status of Previously Identified Unresolved Items and Other Items of Interest I
A.
The procedures and training program for fire prevention /
protection were modified to include the inspection of fire barriers and fichting of fires in vital areas / cable trays. The procedure for welding was still to be modified to require the
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capability of the fire watch to communicate with the control room.
(Item remains open, Report No. 77-01)
8.
It was verified that the diesel-generator rooms were clean and free of significant oil deposits and rags.
(Item closed. ReportNo.77-01)
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C.
While work has been done on reviewing and approving the power
ascension test results, there were still several tests a
. awaiting final review and approval. A meeting of the Test
Work Group has been scheduled for April 23, 1977.
(Item remains open)
D..
It is expected by. licensee representatives that the overall training / retraining program would be formalized and implemented by June 1977.
(Itemremainsopen)
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The controls for filling the day tanks of the emergency diesel-generator have been adjusted so as to shut off the pumps before receipt of a high level alarm, reducing the necessity for a repeat alarm system in the opinion of the licensee.
(Iten considered closed pending licensee's response to NRR on ar.nunciator alarms for emergency generators. Report No. 76-10 and NRR letter dated March 28, 1977)
F.
Surveillance test records were being modified to include a record of returning the system to service.
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(Item closed. Report No. 76-10)
G.
The method of closing out nonconfomance reports related to material control in a timely manner was still being examined.
(Item remains open. ReportNo.76-10)
Management Interview The results of the inspection were discussed with Messrs. McColligan, Schweiger and other members of SMUD management. The following items were specifically addressed and comitments made by licensee representatives as indicated.
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A.
The setting of bypass switches on limitorque valves will be checked to assure that they are properly set so as not to negate safety feature actuation of the valve.
B.
The QA department's audit for management of " Operating Reporting Requirements" will be accomplished within the month.
(Paragraph 5 of Details)
C.
The practices relating to lifted lead tags will be examined to asrure that tags are current and properly controlled.
(Paragraph 8.a(4)ofDetails)
D.
The control of as-built prints by the Instrument and Control Department will be examined to assure that accurate prints are being utilized by the Department.
(Paragraph 4ofDetails)
E.
The spray pond level will be recorded in the daily surveillance log.
(Paragraph 4ofDetails)
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The utilization of test vents and drains on Class "C" penetrations will be examined and administrative controls implemented, if necessary. to assure compliance with
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Also, the inclusion of minimum
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sensitivity of test instruments with local leakaae rate testing results will be reviewed.
(Paragraph 9 of Details)
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O-S-DETAILS 1.
Persons Contacted R. Rodriguez, Plant Superintendent R. Columbo, Technical Assistant P. Oubre, Assistant Superintendent, Operations J. McColligan, Assistant Superintendent, Technical Support D. Blackly, Mechanical Engineer T. Tucker, Shift Supervisor D. Comstock, Shift Supervisor
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D. Whitney, Nuclear Engineer 3. Chun, I&C Technician R. Winks, B&W, Control Analyst D. Yount, Electrical Foreman J. Sullivan, QA Engineer
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A. Fraser, Senior Reactor Operator W. Morisawa, Reactor Operator W. Spencer, Shift Supervisor D. Abbot, Plant Engineer J. Neyman, Nuclear Engineer O
F. Eisenhutt, Nuclear Engineer R. Low, I&C Engineer N. Brock, I&C Supervisor 2.
Nonroutine Event Reports
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Licensee Event Reports Nos. 76-16 (diesel-oenerator failure to start); 77-01 (nuclear service raw water pump failed to auto-start when diesel was started): 77-02 (failure to reset auxiliary feedwater pump following testing); and 77-03 (partially collapsed reactor coolant system drain tank) were submitted since the previous inspection. Based on the examination of selective facility records and discussions with licensee representatives, the following were verified:
a.
Each event was investigated and the details reported to facility management.
b.
Corrective action was taken as described in the event report to preclude recurrence.
c.
The events had been reviewed by the Plant Review Committee and were scheduled for review by the Management Safety Review Committee.
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Safety limits, limiting safety system settings, and limiting conditions for operation did not appear to have been exceeded for the subject events.
3.
Turbine Trip Test _
The turbine trip test from 100% power was witnessed on March 11,
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1977.
Included in the inspection was a review of the test
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procedure, two of six prerequisite test results, calibration of test equipment, and an examination of Brush and Visicorder strip
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charts followino tha test. Pertinent observations made during the inspection were as follows:
a.
The test was conducted in confonnance 5,ith the latest changes to Test Procedure No. 800-14 which had been reviewed and approved in accordance with the licensee's and technical specification administrative requirements.
It was verified that all prerequisit tests, including
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calibrations, had been satisfactorily completed prior to the trip test.
b.
Sufficient operations and technical support personnel were present for facility operation, obs.:rvation and to provide assistance as needed..
c.
. The test demonstrated that the turbine could telp from 100% power without tripping the reactor or exceding technical specification limits. The reactor primary pressure varied only between 2280 and 2020 psig.
Preliminary analysis of the secondary plant indicated that system parameter limits had not been excegded except
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that the differential temperature limit of 350 F between the feedwater to steam genergtor shell may have been exceeded by approximately 25 F, 20 minutes after the trip. Apparently, the control valves for the " pegging" steam from the main steam lines to the feedwater heaters failed to open on the trip, necessitating manual operation of auxiliary steam. This action promptly brought the feedwater temperature within the specification limit. The apparent anomaly will be pursued by the licensee and B&W.
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Records The program for the control, storage ret % tion and retrieval of ecords and documents was examined by sampling selected items and N
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_7 discussion with 1fcensee personnel. No items of noncompliance with regulatory requirements were identified.
The records and documents examined were related to the following items:
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Item Procedure Frequency Record Dates Reactor Coolant System SP 200.08 Monthly June-Aug. 75 Reactivity & Power Control SP 200.01 Shift May 75 & Jan. 77 Power Conversion and SP 200.030 Weekly April 76
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Auxiliary Systems LR 20503 Continuous March-April 76 Strip Chart Emergency Core Cooling SP 203.05A Quarterly May 76, Feb. 77 SP 203.05C Monthly January 77 Engineered Safety Feature SP 203.07 Quarterly 1976 Electrical System SP 206.04 Weekly Sept. 76 Containment System SP 205.02 Refuel Aug. 76 The following items were also examined:
a.
NCR S-157 and associated as-built drawings nos. 596, 599, 621, 622, and 691.
b.
NCR S-343 and associated as-built drawing no. M-522.
i c.
Trending studies on reactivity effects, primary system i
leak rate, and reactor coolant pump seal performance.
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d.
DCNA-1457(TestWorkGroup).
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DCN A-982 (Control Rod Drive Motor).
The inspector noted that the I&C Dspartment did not have a complete up-to-date set of electrical diagrams. There were instruction manuals and electrical diagrams in the I&C shop, but not all of them were controlled accordino to procedures. The licensee committed to look into the document control policies in the I&C Department, especially because of the recently implemented document control system.
In reviewing SP.205.02 which deals with local leak rate tests, it was noted that the fuel transfer tube seal leak rate on August 17,1976 was 0.41 secm, but it was logged as O seem on the
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-8-sumary' data sheet (note:
196,000 sccm =.1 %/ day). The data on the sumary data sheet did not account for the minimum sensiti.vity of the: leak rate instruments. Therefore, the licensee stated that they would review the local leak rate test equipment sensitivities and recordkeeping systems to see if it is appropriate to log the minimum instrument sensitivity for the penetration leak rate if this minimum sensitivity is greater than the test results indicate.
~ The inspector attempted to review records.of the spray pond water
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level. The spray pond supplies cooling water to the decay heat removal system for long term cooldown use.
It was found that no requirement exists to log spray pond level'. The responsibility-
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of the control room operator is to take acthn when a pond low levei alarm annunciates. Therefore, the licensee has comitted to modify SP 200.02 (control room log) to add the level indication and appropriate level ranges of the pond as read on the two spray pond level meters.
5.
Review and Audits The onsite and offsite review and audit functions for the year i
1976 were examined by review of records and discussion with licensee O
personnel. ' Selected portions of the following records were included
.in the inspection:
v a.
Minutes of' Plant Review Comittee (PRC) meetings.
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Minutes of Management Safety Review Comittee (MSP.C)
meetings.
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Reviews of proposed tests, experiments and changes performed in accordance with 10 CFR 50.59.
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Reviews of reportable occurrence violations.
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Proposed changes to technical specifications.
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Records of QA audits * conducted under the cognizance of i
the MSRC including:
Procedures and checklists.
Personnel performing audit Documentation and review by management
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(* Note: A total of 54 audits were conducted by the
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QA Department.in 1976.)'
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Followup action and reaudit
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Frequency of audits It wa[noted that the licensee had cancelled the " semiannual" audit of " Operating Reporting Requirements" for December 1976,
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in a memorandum approved by the MSRC. E.posedly, this area had-been audited in June 1976. The inspec. tor determined that this aduit has always been an annual audit and that in fact it was last performed in December 1975 rather than June 1976. This oversight was quickly recognized by the licensee representative who promptly scheduled an audit to be completed in April 1977.
6.
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The inspector held discussions with the licensee, redewed selected records of the past year's operations, and performed j
independent calculations to verify that the licensee is ensuring adequate shutdown margin throughout the operating cycle. Also, i
the inst. : tor verified that calculation of the reactor shutdown margin is technically correct and in accordance with the facility's procedures and technical specifications. Procedures B.2, 8.4 and B.6 were examined. No inadequacies were identified O
during this review.
2.
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Core Thermal Power Evaluation
The inspector performed independent calculations, reviewed
- selected records of the past year's operations, and held discussions with the licensee to verify that.the calculation of
- core thermal power is technically correct and consistent with NRC requirements. Procedure B-7 was reviewed along with various ccmputer information sheets.
No anomalies were identified during this examination.
8.
Plant Operations
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Shift Logs and Operating Records Operating logs and records were selectively examined for the period December 15, 1976 through April 6,1977.
Observations from this examination were as follows:
-(1)_
The log sheets were complete and contained appropriate signatures and initials of personnel responsible for log entries and log ruiew.
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Abnomal conditions described in the logs contained sufficient information to cumunicate equipment or system status and results of corrective action
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taken.
(3)
Special orders examined that were issued by the Assistant Superintendent, Plant Operations, did not conflict with the intent of the technical specifica-tions.
(4)
The jumpers and bypass permits examined and issued in
accordance with AP-26 " Abnormal Tag Procedure" did not contain bypassing discreps.ncies with technical specification requiremants.
It was noted that the
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lifted lead tags in the Shift Supervisor's office l
dated back as far as January 1975. The items listed on tags nos. 3002 and 5003, dated June 28, 1975, had been corrected but the tags had not been cancelled.
b.
Site Tour (s)
Tours of the facility included the auxiliary building, turbine O
building, and control room. No signs of abnormal piping vibrations or fluid leaks were observed. Hangers, supports, and shock and sway suppressors cbserved appeared operational.
Proper position of several safety injection system valves and their tagging was verified by direct observation.
Radiation controls had been established for the controlled areas included in the tours.
The instrumentation for monitoring reactor power level and coolant system conditions were verified to be operational.
Discussions were held with control room operators regarding safety related annunciators which indicated an alarm condition. They were knowledgeable as to the cause and significance of the aoparent alarm conditions.
Control room manning was in conformance with the facility technical specifications. Shift change was observed on several occasions.
It appeared that the relieving shift was adequately appraised of plant conditions and expected operations for the day.
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Independent Inspection-
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The inspector performed a preliminary data search on the past Containment Integrated I.eak Rate Test (1974) and the upcoming Type A, B and C tests. One item, which will be followed up, was identified. This item deals with test, vent and drain lines, coming off lines penetrating the containment, between the containment isolation valves. Presently, these lines and associated test valves are not leak tested. However, the administrative controls required by 10 CFR 50, Appendix J, are, according to the licensee representative, in place requiring the valves to be closed and lines capped. The licensee stated that the administrative controls will be reviewed to assure the test, vent and drain lines / valves in question are not compromised should the valves be used for purposes other than local leak rate testing.
The inspector performed reactivity balance calculations using Procedure B.6 (Reactivity Balance Calculation) to crosscheck raw data hand calculations with the computer output. No inadequacies were identified in this effort. Other independent inspection activities included (1) examination of controls for C_ /
.T lifted leads and equipment bypass taos, (2) physical check of motor control bus bar connectors, (3) inspection of cable trays and fire barriers, (4) observing several shift changes, and (5) discussions with facility personnel.
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