IR 05000271/1979009
| ML19249F055 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 07/27/1979 |
| From: | Mccabe E, Stetka T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19249F053 | List: |
| References | |
| 50-271-79-09, 50-271-79-9, NUDOCS 7910030888 | |
| Download: ML19249F055 (7) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No.
50-271/79-09 Docket No. 50-271 Category:
C License No. DPR-28 Priority:
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Licensee:
Vermont Yankee Nuclear Power Corporation 20 Turnpike Road Westborough, Massachusetts 01581 Facility Name: Vennont Yankee Nuclear Power Station Inspection at: Vernon, Vennant Inspection cond
.ed :
Jul 4-6 1979 7/[7!77
Inspectors:
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Approved by:
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E. t. McCabe, Jr., Chief, Reactor d&te s'ign'ed Projects Section No. 2, R0&NS Branch Inspection Summary July 4-6, 1979 (Report No. 50-271/79-09)
Special, unannounced inspection of plant operations, including post-strike operations, action taken on IE Bulletin 79 02, previous inspection findings, and plant tours.
This report also documents in-office review of licensee event reports and monthly operating reports.
The site inspection began at 11 ?.M. on July 4 and involved 15 onsite hours by one region-based inspector.
No noncompliances were identi fied.
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DETAILS 1.
Persons Contacted Mr. S. Jefferson, Reactor and Computer Supervisor Mr. J. Lance, Engineer-Mechanical Engineering Group (Westboro)
- Mr. W. Murphy, Assistant Plant Superintendent Mr. J. Pelletier, Maintenance Supervisor Mr. W. Penniman, Security Supervf oor
- Mr. J. Sinclair, Records Clerk Mr. R. Sojka, Operations Supervisor
- Mr. D. Reid, Lead Technical Assistant Other persons interviewed included operations, engineering, and maintenance personnel.
- Present at the exit interview.
2.
Licensee Action on Previous Inspection Findings (Closed) Unresolved Item (271/79-08-01):
The licensee has completed retraining and briefing of both licensed and unlicensed operators prior to resuming their watches.
Details of this retraining are included in paragraph 3 of this report.
(Closed) Unresolved Item (271/79-08-09):
The following procedures were revised to emphasize and/or clarify the return to normal criteria: AP0153, Maintenance of Operations Department Logs, Rev. 7; AD0156, "alye Lineup File, Rev. 6; OP4202, Primary Containment Vacuum Breaker Inspection and Testing, Rev. 5 (By DI 79-9); and D.P. 1412, Jet Pump Inspection, Rev. 3.
(0 pen) Unresolved Item (271/79-08-0~/):
The licensee has revised procedures OP-4121 and OP-4124 by DI's 79-25 and 79-24, respectively, on June 19, 1979 to correct return-to-nonnal inadequacies.
Other identific; procedures remain to be revised.
(Closed) Unresolved Item (271/79-08-10):
The licensee has installed the latch on the RCIC room door.
This installation was verified during a tour of this area.
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Resumption of Normal Operations After the Strike The inspector observed the conduct of an operations turnover, verified the completion of retraining requirements, verified that shift crew schedule and manning were consistent with the Technical Speci Tications (TS), and observed control room operations at various times during this inspection to assure that the return to nonnal operations was adequate and complete.
These observations included discussions with licensee personnel who had been on strike, plant tours, and review of plant logs and operating records.
After the strike, union personnel began to return to work on Monday, June 25.
Staff personnel (not operators) received a briefing, which included an updating on the Three Mile Island (TMI)
incident prior to returning to their nonnal duties.
Operations personnel were placed into a training status for the first part of the week with a gradual phase-in to their nonnal duties.
Retraining for unlicensed operators (Auxiliary Operators) was conducted on June 25 and 26.
This retraining included a review of changes and events that occurred since the start of the strike, a QA and QC update, fire brigade training, and health physics requalification.
Retraining for the licensed operators was also conducted on June 25 and 26.
This retraining included a review of station systems, procedures, radiation control, Licensee Event Reports, recent operating events, and IE Bulletins and Circulars.
These operators were then tested by examination on June 27 (this will be considered to be the annual re-examination).
On June 28 the operators performed a " paper work" catch-up exercise by completing all
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required reading and returned to shift work on June 29.
The inspector reviewed the content of the training given to both unlicensed and licensed personnel, reviewed the examination results, and verified completion of all the required reading.
All watch-standing operators passed the re-examination.
No inadequacies were identified and the inspector had no further t estions in this area.
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Review of Plant Operations a.
Shift Logs and Operating Records The inspector reviewed the records listed below for compliance with the licensee's administrative procedure for Operations Department Logs.
(1) Night Orders for the period June 1, and June 22-July 5, 1979.
(2) Lifted Lead / Installed Jumper Log for all outstanding entries.
(3) Chemistry Logs for the period June 1,1979 through July 5, 1979.
(4) Maintenance Request Log for all outstanding entries.
(5) Control Room Operator (CRO) Log for the period June 1, 1979 through July 5, 1979.
(6) Auxiliary Operator's Logs for July 5,1979.
(7) Daily Supervisor's Log for the period June 1,1979 through July 5, 1979.
(8) Work Request Log for all outstanding entries.
(9)
Process Computer Data Sheets for July 4 and 5,1979.
(10) Reactor Coolant Leakage Calculations.
Inspection consisted of verifying adequate management review, correct identification of problem areas, completeness, and detennination that conditions contrary to the Technical Specifications did rot exist.
No unacceptable conditions were identified.
b.
Tour of Accessible Areas On July 4, at 11:00 P.M., the inspector arrived on site and proceeded to the control room to observe operations.
A tour of the plant was then conducted.
Subsequent plant tours were conducted at periodic intervals during the course of 1031 1" 6
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-5-this inspection. These tours included the Reactor Building (including Corner Rooms), Turbine Building, Diesel Generator Rocms, Radwaste Facility, Cable Spreading Room, and Switchgear Room.
(1) Monitoring Instrumentation.
The following instrumentation was observed to verify that indicated parameters were inaccordance with Technical Specifications (TS) Limiting Conditions for Operation (LCO):
Reactor Vessel Level and Pressure;
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Reactor Power Level;
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Control Rod Positions;
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Equipment Operating Status;
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Area Radiation and Stack Gar Monitors;
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Jet Pump Flow;
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Condensate Storage Tank Level;
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Suppression Chamber (Torus) Water Temperature and
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Vol ume; Process Computer Core Operating Parameters;
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Standby Liquid Control Tank Temperature, and,
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Suppression Chamber (Torus) to Drywell Differential
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Pressure.
(2) Annunciator Alarms.
The inspector observed variou; alarm conditions received and acknowledged by the Control Room Operator on duty.
These conditions were discussed with the operator who was knowledgeable of the alarms and the actions raquired by these alarms.
Continuous alarms were identified and the reasons for these were known to operating personnel.
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-6-(3) Shift Staffing.
The inspector verified by spot checks that the operating shift met Section 6 of the Technical Specification with regard te numbers and licenses.
The inspector also observed a shift turnover on July 5,1979 to verify that continuity of system status was maintained.
(4) Radiation Areas.
Radiation control zones were observed to verify proper identification and implementation.
These observations included review of step-off pad conditions, disposal of anti-contamination clothing and area posting.
No adverse conditions were identified.
(5)
Plant Housekeeping Conditions.
Storage of material and components was observed with respect to safety and fire haza rds.
General housekeeping appeared acceptable.
(6)
Fluid Leaks.
No significant leaks were noted.
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Piping Vibration.
No excessive piping vibration was noted.
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(8)
Pipe Hangers / Seismic Restraints.
Several pipe hangers and seismic restraints (snubber) on safety-related systems were observed.
Findings were acceptable.
(9)
Valve Position / Equipment Start Positions.
The position of valves in the Core Spray, Standby Liquid Control, HPCI, RCIC, and the Residual Heat Removal Systems and the Torus drains were observed to be locked in their required positions.
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Fire Protection.
Fire extinguishers and fire fight-ing equipment were observed to be unobstructed and recently inspected for operability.
No evidence of smoking was observed in designated "No Smoking" areas and *he cardox fire suppression.ystems were observed to be o;orable.
5.
Review of IE Bulletin 79-02 The licensee's iction with respect to IE Bulletin 79-02, Pipe Support Base Plate Design Using Concrete Expansion Anchor Bolts, was reviewed to determine the progress in this area.
Licensee representatives stated that ;he response to this Bulletin was
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-7-to be mailed on July 6 and that they were preparing to commence testing of the accessible anchor bolts.
Procedure 0P 5200.16, Concrete Expansion Anchor Test Procedure, was issued on July 5, 1979 and will be the controlling document for performing the:e tests.
The inspector reviewed OP 5200.16 and appr.ised the licensee of the reporting requirements if failures are identified.
Progress in this area will be followed on subsequent inspections.
6.
NRC In Office Review a.
NRC:RI in office review of LERs 79-05 through 79-10 has been completed with no unacceptable conditions identified.
b.
NRC:RI in office review of Monthly Operating Reports for the months of February 1979 through May 1979 has been completed with no unacceptable conditions identified.
7.
Exit Interview The inspector met with lic1nsee representatives (denoted in Paragraph 1) at the conclusion of the inspection on July 6,1979 and summarized the scope and findings of the inspection as they are detailed in this report.
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