IR 05000312/1990013
| ML20028H217 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 10/29/1990 |
| From: | Wong H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML20028H216 | List: |
| References | |
| 50-312-90-13, NUDOCS 9011160177 | |
| Download: ML20028H217 (8) | |
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U. S. NOCLEAR REGULATORY COMMISSION l
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REGION V
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Report No:' 50-312/90-13 7,
f-Docket,No.
50-312
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License No.- DPR-54
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b1 Licensee: Sacramento Municipal Utility District
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14440 Twin Cities Road a i f,
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- Herald, California 95638-9799 m
hiw facility Name: Rancho-Seco Nuclear Generating Station
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. Inspection at: ' Herald, California (RanchoSecoSite)
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Inspection con' ducted: August 18, 1990 through September 28, 1990,
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- Inspectors:
. C. J. Myers, Resi ent Inspector
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Approved By:
bMM c*L-to-lh #o t
R. Wong, Chief Date Signed l
Reactor Projects Section 11 i'
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Summary:
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Inspection between August 18 and September 28, 1990 (Report 50-312/90-13)
Areas inspected: lThis routine inspection'by the Resident inspector
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involved the areas of operational safety. verification, health ^ physics and security observations, engineered safety features system walkdown,
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maintenance. surveillance an'd' testing,' quality assurance, followup items and a
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meeting with the licensee.- During this inspection. Inspection Procedures
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c, L71707, 717.10, 62703, 61726, 92701 and 30703 were used.
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DETAILS
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persons Contacted
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Licensee Personnel
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D. Keuter, Assistant General Manager (AGM), Nuclear
- J. Shetler, Deputy AGM and Nuclear Plant Manager
'V P. Bender, Manager, Quality and Assurance L
> P. Turner, Manager, Nuclear Technical Services y'
D. Brock, Manager, Nuclear Maintenance S. Redeker, Manager, Nuclear Operations
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C. Linkhart, Manager, Nuclear Support Services L. Houghtby, Manager Nuclear Security M. Bua, Manager Nuclear Radiation / Environmental Protection
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G. Delezenski, Supervisor, Nuclear Licensing.
0ther licensee employees contacted included technicians, operators,
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mechanics, security, and office personnel.
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' * Attended the Exit Meeting on September 28, 1990.
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Operational Status'of Rancho Seco During this inspection period, the plant remained shutdown with the
, reactor defueled and all fuel stored in the spent fuel pool. The reactor.
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coolant system and steam generators are being maintained in a full wet lay-up condition. The main turbine, condenser, and feedwater systems are layed up'in a dry condition with dehumidifiers installed. Approximately
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90% of:the planned lay-up activities has been completed, including most
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of the hardware modifications.
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Operational Safety Verification (7170_7)
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The: inspector reviewed control' room operations which included access control istaffing, observation of system alignments, procedural g
adherence, and log keeping. Discussions with the' shift supervisors and operators indicated an understanding by these personnel of the reasons fore annunciator indications, abnonnal plant conditions and maintenance.
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-work iii progress. The inspector also verified, by observation of valve and switch position indications, that emergency systems were properly
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'a'.igned as required by. technical specifications for plant conditions.
Tours ofE he auxiliary, reactor -and turbine buildings, including t
' exterior breas, were made to assess equipment conditions and plant
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radiological controls and adherence to regulatory requirements. The-
. inspector-also observed plant housekeeping and cleanliness, looked for
. potential fire and safety hazards, and observed security-and safeguards practices.
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During work activities, it appeared that the health' physics managers were g
conducting plant tours and monitoring work in progress. They appeared
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aware of significant work which occurred during this period.
The inspector's Radiation Work Permit (RWP)i eview revealed'that the RWP r
did include: job description, rediation levels, contamination, airborne radioactivity (if expected), respiratory equipment, protective clothing,
. dosimetry, special equipment, RWP expiration, health physics (HP)
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coverage, and signatures.
The RWP radiation and contamination surveys t
were kept current., Employees understood the RWP requirements.
The inspector observed that personnel in the controlled areas were-wearing the proper dosimetry and personnel exiting the controlled areas were using the monitors properly. Labeling of containers appeared
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appropriate.
The inspector walked down portions-of the protected and vital area
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boundaries to ensure that they were intact and that security personnel
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were properly posted where known deficiencies existed. The inspector also observed protected area access control, personnel screening, badge
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issuing and maintenance on access control equipment. Access control was
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observed.. Personnel entering with packages were properly searched and
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access control was in accordance with licensee procedures. The inspector
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observed no obstructions in the isolation zone which could conceal a person or interfere with the' detection / assessment system.
Protected area illumination appeared adequate.
No violations or deviations were identified.
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ESF System Walkdown (71710)
L During the' inspection period the inspector walked down the spent fuel
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pool. cooling system.-
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The inspector concluded that:
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All observed hangers and supports were properly made up and aligned.
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Housekeeping was adequate,.
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Noexcessivepacking, leakage'asobservedonval'ves, f
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Major system components $cre pr'operly labeled, lubricated and
L cooled. No excessive, leakage was,: apparent.'
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. Instrumentation appeared to 'be properly installed. '
No out of. calibration gauges were identified.-
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Flow path components appeared to be in the correct position.
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t Required support systems were'available.
- Proper breaker and switch positions were verified..
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No violations.or deviations were identified.
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. Monthly Surveillance Observation (61726)
Technical Specification (TS) required surveillance tests were observed
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and reviewed to ascertain that they were conducted in accordance with
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Technical Specification requirements.
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The following surveillance activities were observed:
SP 34A Nuclear Service Cooling Water System Surveillance,
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Loop A
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The following items were considered during this review:
testing was in accordance with adequate procedures; test instrumentation was calibrated;
. limiting conditions for operation were met; removal and restoration of the affected components were accomplished; test results conformed with TS
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and procedure requirements and were reviewed by personnel other than the individual directing the test; the reactor operator, technician or engineer performing the test recorded the data and the data was in agreement with observations made by the inspector, and that any t
deficiencies identified during the testing were properly reviewed and (!
resolved by appropriate management personnel.-
' j No violations or deviations were identified, i
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Monthly Maintenance Observation (62703)
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Maintenance activities for the systems and components listed below
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were observed and reviewed to ascertain that tiey were conducted in
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accordance with approved procedures, regulatory guides. industry
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^i codes o.r standards,.and the Technical Specifications.
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Corrective maintenance on the reactor building exhaust stack
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radiation' monitor, R-15845.
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- Installation activity for the redwaste blender / dryer.
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The fo11'owing items < were considered during this review: The limiting j;
conditions for operation were met while components or systems were
removed from service; approvals were obtained prior to initiating the i
work; activities were accomplished using approved procedures and were i
inspected as applicable; functional. testing or calibration was performed prior to returning components or systems to service; activities were y"
accomplished by qualified personnel; radiological controls were
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implemented; and fire prevention controls were implemented.
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No violations or deviations were identified.
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Followup Items (92701)
The following open items were reviewed by the inspector and determined not to be applicable in the current long-term defueled condition of the plant.
Further review or followup is considered to be deferred until final disposition of the plant status is determined. A'new open item will replace these deferred open items for tracking purposes.
(90-01-RS: Open).
Deferred Open items:
18 88-03 89-13-01 87-29-L1 18-88-08 89-15-01 88-10-L1 e
87-32-01 89-15-02 88-17-L1 87-37-04 89-22-01
- 88-20-LO 87-49-01 TI-15-65 88-21-LO 88-14-01 TI-15-88
'89-01-L1 88-31-02 87-20-P 89-02-L0
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88-33-02 88-17-P 89-03-LO 89-01-01-89-03-P 89-04-LO 89-01-02 89-05-P -
89-05-L1 89-01-03 89-08-P 89-11-L0 89-13-LO 89-01-04 89-14-P
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89-01-05 89-16-P 89-15-L0 89-01-06 89-18-P 89-19-LO 89-01-07 89-19-P 86-17-X0 89-01-09 89-25-P 89-01-10 89-04-01 89-04-03 8.
Meeting on Oeferred Comitments and Diesel Generators t
A meeting was held on September 19, 1990 with S. Reynolds. NRR Licensing Project Manager, H. Wong' Region V Section Chief, C. Myers,
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Resident inspector, and members of the Rancho Seco staff to discuss deferred comitments. This meeting was to provide followup to the letter from J. Martin, NRC, to D. Keuter, SMUD, dated June 28, 1990
. and the letter from D. Keuter, SMUD, to J. Martin, NRC, dated
' August 9. 1990. Appendix 1 (enclosed) provides a listing of the comitments discussed and the basis for deferral. All the listed items were found to be acceptable for deferral.
A discussion of the use of the emergency diesel generators as peaking-units was initiated; however, it was determined that appropriate licensae personnel were not available to provide a detailed discu',sion.
It was agreed _to resume the discussions in a conference call at a later date.
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Exit Meeting (30703)
The inspector met with licensee representatives (noted in paragraph 1)
at various times during the report period and formally on
--September 28, 1990. The scope and findings of this report were sumarized at the meeting.
Licensee representatives acknowledged the l
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Appendix 1 - Deferred Comitments
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Item Number BasisforDeferral
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860428003 Preventative maintenance will be done prior to use of refueling equipment 860715004 Previously evaluated as not being a concern and one diesel generator is maintained available for a loss of
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offsite power
, 1105109 No previous indication of this type of-problem l
8,3112301 No previous indications of this type of problem and bus
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loads are now significantly lower 870424136 This relates to a problem with indication of a breaker
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trip and not on actual trip function L
871027101 This has.not been a continuing ~ problem and with the
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reduced amount of personnel the potential for this problem is even less 880229005 There is no hazard which would cause a problem for the i
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control. room or technical support center based on a spent
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fuel pool dropped fuel accident 880718002 This concern was for a loss of offsite power and a fire.
Due to the: slow heat up of the spent fuel pool sufficient time was available to restore power to restart spent fuel pool cooling systems 880907001 A re-evaluation of fire zones is being performed and currently the alarm and detection system is considered t
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adequate
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880927002 This concern is not applicable to Rancho Seco
. 881025002 Valves associated with the spent fuel pool cooling system
do not have= to move to perform their spent fuel pool cooling function 881214012.
Modifications were completed to support defueling
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890109002 Alarms have been disabled for systems-in lay-up reducing the amount of nuisance alarms
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~ Procedure changes have been made and the TTC curve is not-considered a critical characteristic
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890515013
' The. entire EP program is+ being revised'
890621001 Fire watches were established and this aspect was n
previously discussed with C. Ramsey, NRC: Region V
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GenericLettersf
^ The licensee agreed to provide a separate document to discuss the basis for deferral of the generic letter issues'for: review by NRC:NRR a
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365-Safety-related breakers were modified and the change was to provide ~ indication of breaker position and did not affect breaker function L
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'The power supply was tested in an EP drill in October i
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813 Concern was.a documentation problem primarily and the fuses associated with spent fuel pool cooling are i
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,1036 The concern only involved high pressure systems and none are applicable now
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1225; A preventative maintenance program will monitor these
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transformers
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There is a reduced system flow demand now and this was
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considered a system upgrade
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1372.
Not a valid concern in that pressure switches will trip '
the fan and there is another exhaust fan
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t 1847-Precautions are in place to prevent this concern
1967 This is a personal safety issue, not a technical concern L
2335 Accumulators are not used in those systems being operated at Rancho Seco f@
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2347 This was considered a plant upgrade and few involved
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systems in operation now, none in any important system
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2414 (Same as previous item)
2550 Some compensatory actions taken and current system needs
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are significantly reduced i
2693 Low impact on the current plant condition and if there
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were any affect on spent fuel pool cooling, there is a very low heat up rate P
2844 Procedures have been upgraded and are considered adequate l
3018 This concern is only applicabic,to the BWST and boric
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acid system; this is not a current problem for these
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systems 3154 This is not a valid concern; overload trips are still operable
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3528 Therc is work going on-for this conce'rn, but is I
considered to be a long-term issue
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39091 This issue does not involve operable systems
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4011 This issue.is only for containment and is considered a plant upgrade -
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'4039 Appendix R.does not apply now
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~ Work is,being.done.to replace those affected in systems which are not being put into lay-up
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'4196 & 4197
. Non-EQ qualified components will be tracked using PDQs to
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This is not a current plant problem in that the TS
4212 radiation monitors are made by GA
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.From 08/09/90 SMUD letter to NRC -
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been demonstrated to be able to support spent fuel pool'
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cooling 4014 This issue is considered a plant upgrade and current.
systems are adequate; only minor problems exist
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4320, Compensatory measures are in place and regulatory relief
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k 4322 Procedure changes have been made to avoid the problem and standby chargers for the batteries are still available 4395 The licensee considers that reasonable controls exist now and that the reduced amount of personnel onsite lessens the potential for any problems
- 4518 This concern does not affect operable or available systems j
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