IR 05000312/1975008
| ML19317G083 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 09/16/1975 |
| From: | Crews J, Malmros M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML19317F868 | List: |
| References | |
| 50-312-75-08, 50-312-75-8, NUDOCS 8002210775 | |
| Download: ML19317G083 (11) | |
Text
{{#Wiki_filter:= - . . U. S. NUCi. EAR REGULAT01Cf C0!eilSSION ' " - . < ' '. ~0FFI 0F INSPECTION AND ENFORCEMEN7 ' . ION V -
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,IE Inspection Report No.
.50-312/75 58 Licensee Sacramento Municioal Utility District Docket No.
50-312 ' '
P. O. Box 15830, License No. DPR-54
- / Sacramento, California 95813 Priority - . Facility Rancho Seco category C Clay Station, California
. . Type of Facility PWR, B&W, 913 MWe (2772 MWt) . Routine Unannounced Type of Inspection Dates of Inspection September 2-5, 1975 Datas, of Erevious bspection June 4,10-12,1975 . ' Principal Inspector D hw /t /7d' - . M. H. Malmros, Reactor Inspector 'Dat'e -
None - Accompanying Inspectors _ , Date \\ - .. Date Other Accompanying Personnel: None ) I i .-; - . Reviewed by b ' -f [ [[/(.A / /d ? \\
/ l * P /", Reactor Testing and Operations Branch .Dat e' I Crews (Ehief i J. L ( . . , . . . N.
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SUMARY OF FINDINGS Enforcement Action , ' he Licensee Action on previously Identified Enforcement Items . The corrective action described by the licensee in its letter of July 7, 1975 in response to the enforcement item described in IE Inspection Report ~ No. 50-312/75-05 was verified.
(Paragraph 2 of Details.)
Unusual Occurrences ..Jhe circumstances and corrective action described in Abnormal Occur- ' . rence Report Nos. 75-10 and 75-11 submitted by the licensee to Licensing were confirmed.
(Paragraph 3ofDetails.)
, Other Sionificant Findings Current Findings A.
Plant operations were found consistent with the Technical Speci-fication requirements.
(Paragraph 5ofDetails.)
g B.
The operator recualification program has been implemented. Uccu- --). unresolved item for followup during the next scheduled inspection.
mentation inconsistencies were identified and are designated an (Paragraph 6ofDetails.)
, C.
Turbine repairs and control; rod drive stator replacement were in progress curing the inspection.
(Paragraph 10 of Details.)
D.
The licensee's responses t'a IE Bulletin 75-04A were verified.
(Paragraph 4ofDetails.); . Status of Previously Recorted Unresolved Items Not applicable.
. Management Interview k\\ . The results of the inspection were discussed with Messrs. Rausch, Rodriguez and Schwieger and other members of the licensee's staff at the conclusion of the insoection on September 5,1975. The licensee commented that the apparent inconsistencies in documentation of activities performed in accordance with the Operator.Requalification . e ( \\_
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. - . -3- . . - Program would be evaluated and resolved as appropriate. The in-spector stated the corrective acticn by the licensee in response to i / the item of nonce:pliance-for the control of jumpers and bypasses had been verified and no further information was required at this i - time.
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lv) DETAILS . 1.
-Persons Contacted - . R. Rodriguez, Manager fluclear Operations P. Oubre, Assistant Plant Superintendant, Operations , L. Schwieger,. Quality Assurance Director ' . R. Miller, Chemical / Radiological Supervisor D. Whitney, Plant Nuclear Engineer L. Stephenson, Supervising Engineer ,. . M. Brock, Instrumentation and Control Engineer R. Dieterich, Senior.'luclear Engineer C. Linkhart, Assistant Instrumentation and Control Engineer M. Montenero, Instrument Foreman "' ~ W. Ford, Shift Supervisor / Training Coordinator W. Spencer, Shif t Supervisor - M. Hieronimus, Control Rocm Operator - A. Locy, Electrical Maintenance Foreman J. Field, Mechanical Engineering Assistant D. Gardiner, Chemical / Radiological Assistant F. Eisenhuth, Nuclear Engineering Assistant J. Sullivan, Quality Assurance Engineer J. Walker, Quality Assurance Engineer p 2.
Followuo on Item of Noncomoliance The corrective measures described in the licensee's letter of July 7,1975, in response to the item of nonccmpliance described in IE Inspection Report No. 50-312/75-05 were verified to have been implemented. Facility records and administrative controls required by AP-26, " Abnormal Tag Procedure" were examined.
The recuire-ments for the control of jumpers and bypasses within the electrical maintenance group and the instrument and control group had been implemented and the interface with the shift supervisor for in-sta11ation control of abnormal tags was found consistent with the requirements of AP-26.
The S'4UD quality assurance organization audit number 0-14 on July 22, 1975, found no deficiencies related to the implementation of AP-26.
i 3.
Rev.iew of Abnormal Occurrence Recorts Abnordiai Occurence Reports Nos. 75-10, " Auxiliary Feedwater Pump Motor Trip" and 75-11, " Quarterly Surveillance of Wasta Gas Decay Tank" were submitted by the licensee since the previous inspection.
Based on an examination of facility records and discussions with - licensee representatives, the inspector verified the following: , a( .--e++ --y==- w.- .. w w ..-....e--- we..- . . . .
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, b.
The corrective actions described in the reports to prevent recurrence 'f the events were implemented by the licensee.
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c.
The abnormal occurren:es had been reviewed by the Plant ~ Review Committee.
d5 The surveillance requirement (Technical Specification Table 4.1-3) for quarterly sampling of the 'Aste Gas Decay Tank . D was not met for the first quarter e i975 (item of non-compliance) as raported by the licensea in Abnormal Occur- , rence Report No. 75-11. Surveillance procedure, SP 202.07 - had been implemented to preclude recurrence.
e.
System and component failures have been reported to the plant staff for review and properly identified as abnormal occ'fr-rences when applicable.
4.
IE Bulletin Followuo ' a.
75-04A " Cable Tray Fire - Browns Ferry" O The information contained in the licensee's final status U report dated July 21, 1975 was verified. The following new - procedure and revisions to existing procedures have been reviewed, approved and implemented by the licensee as ad-ministrative control modifications addressing fire prevention and the effects of fire on plant shutdown cooling systems.
(1) AP-29-Rev 0, "Use and Control of Combustible Materials and Ignition Sources."
(2) AP-3-Rev 3, " Work Request."
(3) M-113-Rev 2, " General Welding Procedure."
f (4) D-14-Rev 2 " Loss of Steam Generator Feed."
. -(5) D-16-Rev 2, " Loss of Decay Heat Removal System."
(6), B-4-Rev 2, " Plant Shutdown and Cooldown."
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Review of Plant Ocerations a.
Shift Loos and Operatino Records - . Operating logs and records, maintained in accordance with the licensee's administrative controls, were examined for the periods, June 7 through July 13 and September 1-4, 1975. The following observations were noted by the inspector: (1) The log sheets were complete and contained appropriate - signatures and initials of personnel responsible for - log entries and log review.
' (2) Abnormal cunditions described in the logs contained ' sufficient information to communicate equipment or , system status and results of corrective action taken.
(3) Special Orders (Nos. 39-75 through 44-75) issued by the Assistant Plant Superintendent, Operations, did not conflict with the intent of the Technical Specifications.
(4) Jumpers and bypasses issued in accordance with AP-26, , " Abnormal Tag Procedure", did not contain bypassing discrepancies with Technical Specification requirements.
] b.
Site Tour A tour of the facility, including controlled access areas in the reactor building and auxiliary building, was conducted with the plant in a cold shutdown conditica for turbine repairs.
No signs of abnormal piping vibrations or fluid leaks resulting from facility. power operation wero. observed.
Proper position of safety feature valves (N6s'.~ DHS.006 and 056; and CBS 014, 016 and 018) was verified by direct obser-vation.
The instrumentation for monitoring shutdown neutron counts, reactor coolant system level and temperature, and decay , heat removal flow were verified to be operational. Contain- , ment requirements were consistent with the cold plant shut-down conditions.
Clearance tags issued under Clearance Nos. 9951, 10052 and 10063 were examined on installed components during the tour and verified to have been properly installed through exami-nation of control documentation maintained in the control . . . . a !
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i Discussions were held with the control room operator and the shift supervisor regarding safety related annunciators which indicated an alarm condition.
Both individuals were know-ledgeable as to the cause and significance of the apparent alarm conditions. Control room manning was in conformance with the facility Technical Specifications.
6.
Training
- .., The licensed operator retraining program has been implemented by the licensee. The program is administered by the Training , Coordinator in accordance with the requirements of administrative ' procedure, AP-25, " Licensed NRC Operator Retraining". Based on discussions with the Training Coordinator and an examination of facility records, the training activities were found consistent with the requirements of 10 CFR 55 and commitments in the facility application.
The following observations were made by the inspector, a.
Lecture schedules have been established for required lecture [] items.
V , b.
The program includes the use of training aids, films and tapes.
- c.
Procedure changes and modifications have been communicated to the operating staff through Special Orcers and routing of procedure changes.
d.
Annual written and oral examinations had been administered.
-- e.
Records of the required manipulation of reactor controls were being maintained for each operator.
f.
Quarterly audits and annual supervisory evaluations of examinations, manipulations and simulations were being , performed.
g.
Training manuals were being maintained by each operator to document individual study, lecture participation and manip-ulations performed.
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.. h. ~ The individual training files require up' dating to indicate the required simulations of abnormal and emergency conditions - that have been performed by licensed operation.
Documentation indicating that all licensed operators had completed each reading 1ssignment was not available.
During a subsequent inspection the training records will be reexamined to verify that appropriate documentation is complete with regard to the retraining program.
The records of recently hired SMUD employees were examined and found to indicate that the required indoctrination to security practices,. health physics and the emergency plan had been accom- ,,' , plished.
- 7.
Organization and Administration The licensee's organizational structure was examined and found to be consistent with the Technical Specification requirements.
The following observations were made by the inspector.
a.
Personnel qualification levels were in conformance with , ANSI 418.1 and the Technical Specifications.
b.
Authoritie's and responsibilities of licensee personnel were " as delineated in the Technical Specifications, the FSAR and the Quality Assurance Program.
c.
The overall shift crew composition schedule was in conformance with the Technical Specifications.
d.
The makeup of the Plant Review Committee and the Management Safety Review Committee was in conformance with the Technical Specifications.
e.
No changes have been made in the licensee's organization that require reporting to the NRC.
8.- Caljbration Based on discussions with licensee representatives and an exami-nation of facility records, the calibration of components and equipment associated with safety related system and/or functions , was found in conformance with the recuirements of the Technical - Specifications.
The frecuency of calibration was verified to have been met for the.following: s , m L.)
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Reactor coolant temperature instrumentation.
. b.
Power range nuclear instrumentation.
- c.
Power imbalance / flow comparators.
d.
Steam generator water level instrumentation.
. Reactor building drain sump alarm instrumentation.
e.
f.
Reactor coolant pump motor relay protection.
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. Diesel generator voltage and speed controls.
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High pressure infection flow instrumentation.
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Reactor building pressure instrumentation.
I I During the calibration of the above items, service status of the I' affected systems was in conformance with the applicable limiting i condition for operations.
The voltage set points for instruments ! providing a reactor trip signal were verified to be correctly set , ' to conform with itmiting safety system settings.
Procedures used I , to perform the calibration of the above components were found to l 'y-have been reviewed and approved and to contain acceptance values and detailed stepwise instructions.
The qualifications of indi- ) vidual performing calibrations were found to be in conformance j with licensee requirements.
[ The records of three measuring / testing devices used as primary t standards during the performance of the above calibrations were j examined with the following results observed:
, i Calibration frequency was met and accuracy verified as a.
prescribed by licensee procedures.
' , b.
Accuracy was traceable to an independent testing organization.
t ' ' j c.. Storage and control of the test equipment was proper.
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9.
Rev'iew of Startuo Recort ' ' The licensee Startup Report dated March 1975 and Supplement flo.1 .
dated July 10, 1975 were reviewed and the information contained within the reports was found to be consistent with facility records.
's ' ' The reports contained the information required by the Technical . ' O -
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. ~ . - i - . , , ~ . ., (O-10- ) .. . Specifications for testing through 92.6% of full power. Testing ^ deficiencies identified in the reports were verified to have been resolved by the licensee.
~ 10.
Indeoendent Inspection a a.
CRDM Stator Reoair
The repair of-control rod drive mechanism (CRDM) stators as-a result of insulation damage caused by overheating was , examined. The CRDM stators were damaged when power was not secured following rod logic trip tests with the CRDM cooling system shutdown. All CRDM stators have been returned to the .., manufacturer for retiinding and reinsulation.
Inspection of . ' stator reinstallation was being perfomed by SMUD personnel in accordance with QA program requirements.
A special test procedure, STP 804, was being prepared for startup testing of the control rod drive system to verify system conformance to design specifications and Technical Specification requirements. - To preclude recurrence of the . stator overheating situation, procedure revisions were being prepared by the licensee ar.d an intericek to prevent manual . closing of the power supply breaker to the stator coils with CP.DM cooling flow less than the low flow alarm setpoint was , being reviewed and approved for installation.
' b.
Reactor Coolant pumo Studs.
! The results of the evaluation of possible crack indications in the' reactor coolant pump studs at Three Mile Island Unit No. 2 were discussed with licensee engineering personnel.
The licensee'was fully aware of the circumstances and no corrective
action will be required with regard to the Rancho Seco plant.
c.
Earthouake Data Analysis' l The seismic monitoring data from the Oroville earthquakes on . August 1 and 2,1975 were reviewed. The USGS free field de- . tectors-indicated values of. approximately.01g.
The licensee's , ' free field detectors indicated values of approximately.06.9 The licensee has sent three accelerometers to the manufacturer - for calibration in an attempt to resolve the difference in values for the free field effect. Results.of the calibration . ~ will be examined during a subseque,nt inspection.
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- ' U ,d.- Turb'ine Reoair ' The' repair of the main turbine resulting from blade failure in the "B" low pressure spindle was observed to be in progress.
Magnetic particle examination of both low pressure spindles has revealed several cracks in the steeples of the third and fourth stage of the "A"' low pressure spindle and cracks in the steeples of the second and third stage of the "B" low pressare . spindle. These cracks appear, according to the licensee's evaluation, to be the cause of the blade failure in the "B" spindle on June 30, 1975. As a result both low pressure spindles are being replaced, with repairs scheduled for com-pletion about October 12, 1975. The licensee, turbine manu-facturer and several consultants are evaluating the source and ., cause of what appears to be a stress corrosion cracking mechan- . ism. The results of these evaluations will be examined during , a subsequent inspection.
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