IR 05000312/1981031
| ML20039B168 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 11/23/1981 |
| From: | Canter H, Obrien J, Thomas Young NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20039B163 | List: |
| References | |
| 50-312-81-31, NUDOCS 8112220366 | |
| Download: ML20039B168 (8) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
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REGION V
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Report No. 50-312/81-31
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Docket No. 50-312 License No.
DPR-54 Safeguards Group Licensee:
Sacramento Municipal Utility District P.
O.
Box 15830 Sacramento, California 95813 Facility Name:
Rancho Seco Unit 1 Inspection at:
Herald, California (Rancho Seco Site)
Inspection conducted:
October 1-30, 1981 Inspectors:
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,Sengr eside/t Inspector Date Signed Har*ey L.
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John O'Brien, gnit Re(id gi inpcctor Date Signed
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Approved By: dN Mr.
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T. Youn'g, Chief,[Reacto(IPpjects Section 2 Date Signed Reactor OperatioVs Projects Branch Stanmary:
Inspection between October 1-30, 1981 (Report 50-312/81-31)
Areas Inspected: Long Term Shutdown Activities; Operational Safety Verification; Maintenance Observations; Monthly Surveillance Observations; Licensee Event Report Followup; Followup on Items of Noncompliance; Followup ~
Plant on Trips; and, Independent Inspection Effort.
The inspection activities involved 212 inspector-hours by the Resident Inspectors.
Results: Of the eight areas inspected, no i t'e m s ' o f non-compliance or deviations were identified.
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RV Form 219-(2)
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DETAILS l
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1.
Persons Contacted AR. Rodgriquez, Mancter, Nucleat Operations
- P.
Oubre', Plant Superintendent
- D. Blachly, Operations Supervisar N.
Brock, Electrical /I&E Maintenance Supervisor D.
Cass, Mechanical Maintenance Supervisor Q. Coleman, Quality Assurance Engineer
- R.
Colombo, Technical Assistant
- G. Coward, Maintenance Supervisor
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- S. Crunk, Associate Nuclear Engineer
- D. Elliott, Quality Assurance Engineer H.
Heckert, Quality Assurance Engineer J.
Jewett, Quality Assurance Engineer F.
Kellie, Assistant Chemistry and Health Physics Supervisor
- V.
Lewis, Site Project Engineer
- J. McColligan,-Generation Engineering
- R. Miller, Chemistry / Radiological Supervisor
- T.
Perry, On-site Quality Assurance Supervisor
- L. Schwieger, Quality Assurance Director T.
Tucker, Planner / Scheduler D. Whitney, Engineering and Quality Control Supervisor B.
Wichert, Mechanical Engineer The inspectors also. talked with and interviewed several other licensee employees, including members of the engineering, main-tenance, operations and Quality Assurance (QA) organizations.
- Denotes those attending the Exit Interview on October 1,-1981.
- Denotes those attending the Exit Interview on October 30, 1981.
Also attending this meeting were T.
Young and G.
Kellund from Region V, NRC.
2.
Long Term Shutdown Activities During the report period the inspectors observed control rcom
operations, reviewed applicable logs and conducted discussions with control room operators.
The inspector verified that sur-veillance tests required during the shutdown were accomplished, reviewed tagout records, and verified containment integrity.
Tours of the Auxiliary Building and Reactor Building, including exterior areas were made to assess equipment conditions and plant corditions.
Also, the tours were made to assess the
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effectiveness of radiological controls and adherence tc reg-l ulatory requirements.
Maintenance work requests was verified I
to have been initiated for equipment maintenance.- The inspectors observed plant housekeeping / cleanliness conditions and looked for potential fire hazards.
The inspectors, by observation and l
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direct interview, verified that the physical security plan was being implemented in accordance with the station security plan.
The inspectors reviewed the licensee's jumper / bypass controls to verify there were no conflicts with technical specifications.
Finally, the inspectors witnessed portions of the radioactive waste systems controls associated with radwaste shipments.
No items of noncompliance or deviations were identified.
3.
Operational Safety Verification The Reactor Plant was taken critical at 1:46 a.m.
on October 26, 1981, thus ending a 10-week outage for major turbine repairs.
In addition to the items mentioned in Paragraph 2, the inspretor witnessed portions of plant operations which required separation from the grid and primary plant power reductions for a turbine balancing effort 1 which'took about four days to complete.
The plant went on line and"$scalated to power on October 28, 1981.
No items o f noncomplian'ce ' or. devia tions.were identified.
4.
Maintenance Observations The inspectors observed portions-ofjthe_ maintenance activities
listed below and verified that work was accomplished in accordance with approvedfprocedures; that. work was accomplished by qealified personnel; thdt provisions for-stationing a fire watch to oversee
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activities involving welding and open flame were complied with; and, that LCO-requirements were' met during repair.
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a.
Reactor Building CCW Isolation Valve Repairs.
b.
Makeup Pump Motor Rewind, c.
Meteorological Tower Rework.
d.
Main Steam Sample Valve Rework.
e.
Diesel Governor Replacement.
f.
"B" NSRW Pump Control Repairs.
No items of noncompliance or deviations were identified.
5.
Surveillance Observations The inspectors observed portions of the below listed survei]1ance testing to verify that the tests were covered by properly approved procedures; that the procedures used were consistent with tech-nical specification requirements; that a minimum crew requirements were met; that test prerequisites were completed; that special test equipment was calibrated and in service; and, that the test results were adequat _
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a.
SP 200.01 Instrunentation Surveillance Performed Each Shift, b.
SP 200.02-DailyTInsirumentation Surveillance.
c.
SP 200.03 Weekly Instrumentation. Surveillance.
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d.
SP 200.05 Instrumentation Sur.vei,llance Prior to Each
. Start-Up.
e.
SP 200.17 Meteorological In s t r um en t'a tio n Surveillance.
'f.
SP 203.11
,, Dicay Heat Valve Seat Integrity Test.
No items of noncompliance or deviations were identified.
.j 6.
Licensee Event Report Follow-up
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The Resident Inspectors ~ performed'an examination of the following licensee event reports to ascertain whether additional inspection effort or other IE response is warranted, whether corrective action discussed in the lic^ensee's report appears' appropriate, and whether the information reported to the NRC appears to satisfy reporting requirements.
All of the event reports listed below appear to meet the above criteria and requ're no further follow-up at this time.
These items are CLOSED.
81-07 Instrument string error.
81-12 Resetting of RB high pressure trip.
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81-27 RB spray pump failed surveillance start.
81-31 Cable tray / fire barrier improperly installed.
81-32 Snubber oil leak.
81-35
"A" Diesel governor low on oil.
81-37 SP 207.07A surveillance test failure.
81-45 Replaced
"A" decay pump seal.
81-46 Snubber replacement and testing completed.
81-51 Failure of SFV 46014 to operate properly.
Licensee action committed to in each of the above lieted licensee event reports was verified to be complete and approprio e except as noted below.
LER 81-37 (CLOSED):
In response to this event and other similar events, and in light of the continuing problems that the licensee is experiencing with the Instrument Air System, the license has committed to the following:*
a.
Continue the revised preventative maintenance re-
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placement of the instrument Air filters which assures each set is replaced at least every 90 days.
- Reverence: _ Letter dated October 19, 1981 from R.
H.
Engelken to J.
J.
Mattimoe.
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Complete the' engineering review of the acceptability of'the close' proximity of the Indtrument Air filters and dryers.
This' review wi11 be completed by November 20, 1981.
c.
Continue to utilize-the newly' installed Instrument Air dew point monitoring system on a once per shift minimum, even though the system'has not been fully accepted due to temporary. cabling and the annunicatcr system being incomplete.
d.
Develop a process standard which will specify action to be taken for an unacceptable dew point.
This standard will be in effect by November 27, 1981.
e.
Continue to blow down the Instrument Air System from the installed blowdown manifolds every two weeks for at least the next six months.
This blowdown will be of sufficient duration and flow rate to provide assurance that no significant moisture or debris exists in the system.
All debris which may exit the system during this blowdown will be captured and identified and the results recorded.
f.
If another safety-related valve operator failure occurs which is traced to excessive moisture or foreign material in the Instrument Air system, a comprehensive system examination will be performed.
This examination will consist of disconnecting the air line to each air operated valve important to safety and performing a blowdown on each line and an examination.of the debris found, if any.
g.
The action described in Paragraphs 1 through 6 will continue for at least six months.
At the end of this period, the comprehensive engineering review of the Instrument Air system will be completed and appropriate changes to this special program will be 2dentified.
These commitments will be followed to completion by the Resident Inspectors (81-31-01).
No items of noncompliance or deviations were identified.
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Followup on Items of Noncompliance
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The inspector ascerta1ned by observation document review and discussions with plant personnel that the licensee's response for items of noncompliance identified in the listed IE corres-pondence is in conformance with regulatory requirements and that the corrective measures were completed.
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No Clear Snubber Accept'ance Criteria Item 80-35-02 (Deviation) was' responded to in letters dated January 26, 19 81.a'n d February 27;'1981.
This item is CLOSED.
Failure to Promptly Close NCRs-80-36-02kLevd1 V) was responded to in a letter dated Item January 26, 1,981.
This item is CLOSED.
No 10 CFR 50.59 Review Item 81-04-03 (Level IV) was responded to in letters dated March 26, 1981, and May 7, 1981.
This item is CLOSED.
Failure to Follow Procedures Item 81-21-01 (Level V) was responded to in a letter dated October 8, 1981.
This item is CLOSED.
No items of noncompliance or deviations were disclosed during this inspection activity.
8.
Followup on Plant Trips Following Rancho Seco's return to power during the evening of October 28, 1981, a reactor plant trip on high pressure occurred'
(7:38 p. m.).
The cause was apparently traced to a problem with the
"B" Main Feed pump controller.
The plant tripped from about 35 percent reactor power.
A review of the chart recorders for feed flow, reactor system pressure, reactor power, pressurizer level, and discussions with various plant personnel involved in the trip indicated an appropriate plant response occurred.
The licensee is troubleshooting the Main Feed Pump controller to find and correct the problem.
The licensee experienced problems with the feed pump controllers In June, 1981.
The controllers were installed during the last refueling outage which ended in June, 1981.
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The NRC Emergency Notification System was properly utilized to report the trip within one hour.
No items of noncompliance or deviations were identified.
9.
Independent Inspection Effort Discussions were held between the Resident Inspectors and opera-tions, security and maintenance personnel in an attempt to better understand problems they may have which are related to nuclear safety.
These discussions will continue as a standard practice.
On numerous occasions, during the month of October, 1981, the Resident Inspectors attended outage and operations status meetings.
These meetings are held by the Plant Schedule and Operations Supervisor, respectively, to provide all disciplines onsite with an update on the plant status-and ongoing maintenance work.
In addition to the above, independent inspection effort was performed on the following items.
These are items identified in past inspection reports which required followup inspection by the Resident Inspectors or were Unresolved Items which re-quired resolution.
These items are CLOSED.
(Note:
The item number refers to the IE report in which the item was first doc-umented.)
Item Number Item Type Subject 80-06-08 Followup Verify procedure revisions made on Code Safety Valve Maintenance.
80-23-01 Followup Qual. training for QA inspectors.
80-24-03 Followup Revise AP303 80-34-03 Followup Orep. of fire fighting strategy procedures.
80-36-04 Followup Revise QAP 10, 81-04-01 Followup Letdown cooler leak.
81-04-02 Followup H2 leak.
81-21-02 Followup Develop NCR training program.
81-21-03 Followup P&ID discrepancies.
81-21-05 Followup Design for'AFP flow includes two devices per OTSG.
81-25-01 Followup Need reason for loss of feed pumps.
81-25-04 Followup-N2 system contaminations.
81-29-02 Followup Added-QAP 2 figures to ECP 1.
81-29-03 Followup ECP 1,
2, and 3 are now controlled and reviewed and approved 79-21-04 Unresolved SFAS Signal Removal 80-31-04 Unresolved
' Revise AP.3.
- 81-07-03-Unresolved Dua,l' Verification (TMI 1.C.6)
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No items of noncompliance or deviations were identified.
10. Exit Intervie.
The inspectors met with licensee representatives (dentoed in Paragraph 1) throughout the month and at the conclusion of the inspection on October 30, 1981.
They summarized the scope and findings of the inspection activities.
The licensee acknowledged the statements of findings.
A number of commitments on the operation of the Instrument Air system were tendered. The commitments will be followed to com-pletion by the Resident Inspectors.
(Please see Paragraph 6.)
No items of noncompliance or deviations were identified in the Residents' October inspection effort,
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