IR 05000029/1979001
| ML19347A484 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 02/27/1979 |
| From: | Keimig R, Lazarus W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19347A483 | List: |
| References | |
| 50-029-79-01, 50-29-79-1, NUDOCS 7904200297 | |
| Download: ML19347A484 (12) | |
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n U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No.
50-29/79-01 Docket No.
50-29 Category C
License No.
OPR-3 Priority
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Licensee:
Yankee Atomic Electric Cemoany 20 Turnoike Road Westborough, Massachusetts 01591
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Facility Name: Yankee Nuclear Power Station (Yankee-Rowe)
Inspection at: Rowe, Massachusetts Inspection conducted:
January 22-26, 1979 Inspectors: /
/M e: f
4 W 6b.4.azaruy, Reactor Inspector cate signed date signed
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date signed
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Approved by:
- e re #
J-2 7-78 Chief, o ctor Projects cate signed
/R. R. Keim'
Sectic.io 1, R0 Sra.nch
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Inspection Summary:
Inscection on January 22-26, 1979 (Recort No. 50-29/79-01)
Areas Insoected: Routine, unannounced inspection by a regional based inspector of plant operations, including a tour of accessible areas and a review of shift legs and operating records; review and onsite followup of Licensee Event Reports (LER's); post refueling startup testing and return of plant systens to service; testing of new or modified systems; and followup on previous inspection findings. The inspection involved 31 inspector-hours onsite by one regional based NRC inspector.
Resul ts: No items of noncompliance were identified.
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Region I Form 12 (Rev. April 77)
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OETAILS 1.
persons Contacted
- R. Aron, Engineering Assistant
- H. Autio, Plant Superintendent W. Billings, Chem 13try and HP Supervisor T. Danek, Operations Supervisor
$H. Ebert, Reactor Supervisor T. Henderson, Technical Assistant G. Murphy, Security Administrator
- J. Staub, Technical Assistant to the Plant Superintendent
- N. St. Laurent, Assistant Plant Superintendent The inspector also interviewed several licensed operators and members of the technical and administrative staffs.
- denotes those present at the exit interview.
2.
Licensee Action on Previous Inspection Findings (Closed) Unresolved item (29/76-21-01): Post LOCA Containment sump baron concentration. A letter addressing this matter was submitted
'to NRR for review on November 10, 1978.
(Closed) Unresolved item (29/77-23-01): The licensee completed an evaluation of changing the setpoint tolerance for pressurizer code safeties from +0, -3 psi to +3, -3 psi. The accident analysis assumes a hign setting so +0 psi is required.
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(Closed) Followup item (29/78-04-01): Leaking fuel assemblies were
identified by fuel sipping during the refueling outage and removed from the core. The inspector reviewed Reactor Coolant System chemistry for the period since the startup in December 1978. No evidence of fuel clad failure was identified.
(Closed) Noncorap11ance (29/78-10-01): Evidence of smoking in "No Smoking" area.
The inspector verified that this noncompliance had been reviewed by the PORC and that adequate corrective action had been taken in accordance with the licensee's response (WYR letter 78-72 of 8/2/78).
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(Closed) Noncompliance (29/78-16-01): Discrepancy in Bypass of Safety Function and Jumper Control Log. The inspector verified that jumpers indicated as outstanding in the log index had been properly accounted for by the licensee and that operating personnel had been reminded to keep the index updated when jumpers / bypasses were cleared as indicated in the licensee's letter to the NRC dated December 15, 1978. No items of noncompliance were identified in this area during this inspection.
(Closed) Unresolved item (29/78-16-02): Lc.R Format. The inspector verified that LER's submitted since the last inspection of this area were completed in the proper format.
-(Closed) Unresolved item (29/78-16-03): Inadvertent control rod withdrawal. The inspector reviewed procedures OP-1209 and OP-4226 to verify that they had been revised to prevent similar occurrences of inadvertent rod withdrawal when removing control rod guide tubes.
(Closed) Noncompliance (29/78-16-04): Failure of security personnel to follow RWP requirements.
The inspector reviewed a copy of the memorandum issued to security force personnel which reminded them of their responsibility to know and follow the requirements of Radiation Work Pennits (RWP) when performing duties in areas which required RWP's.
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3.
Shift Logs and 0cerating Records a.
The inspector reviewed the following plant procedures to deter-mine the licensee established administrative requirements in this area in preparation for a review of selected logs and records.
AP-0003, Plant Operations Review Connittee Responsibilities
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and Authorities, Revision 3.
AP-0004, Pl!.nt Infonnation Reports, Rivision 3.
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AP-0017, Switchir.g and Tagging of Plant Equipment, Revision 4.
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AP-0207, Equipment Control, Revision 1.
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AP-0018, Bypass of Safety Function ind Jumper Centrol
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Log, Revision 5.
AP-0021, Operating Memos, Revision 3.
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AP-2007, Maintenance of Operations Department Logs,
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Revision 4.
AP-0216, Housekeeping and Cleanliness Control. Original.
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AP-0042. Housekeeping for Maintenance and Modifications,
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Original.
The inspector had no questions in this area.
b.
Shift logs and operating records were reviewed to verily that:
Control Room log sheet entries are filled out and initialed;
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Auxiliary log sheets are filled out and initialed;
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Shift Supervisor and Control Room log entries involving.
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abnormal conditions provide sufficient detail to connuni-cate equipment status, lockout status, correction, and restoration; Log Book reviews are being conducted by the staff;
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Operating orders do not conflict with Technical Specifi-
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cation requirements;
" Plant Infonnation Reports" confirm there are no violations
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of Technical Specification reporting or LCO requirements; and, Logs and records were maintained in accordance with
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Technical Specifications and the procedures in 3.a above.
c.
The review included discussions with licensee personnel and review of the following plant shift logs and operating records:
Primary and Secondary Log Sheets, December 1,1978 -
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January 15, 1979; Operating Memos 2C1, 2K, and 48;
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All effective Standing Orders;
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Bypass of Safety Function and Jumper Control Log Control
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Sheets78-160 through 79-11;
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Switching / Tagging Orders (active) through 79-82;
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Plant Infonnation Reports (PIR) 78-07 through 78-17;
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Minutes of Plant Operations Review Committee (PORC)
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Meetings 78-35 through 79-01.
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No items of noncompliance were identified.
4.
Plant Tour The inspector conducted a tour of accessible areas of the plant including the Primary Auxiliary Building, Turbine Building, Safety Injection Building, Switch Gear Room, Diesel Rooms, Control Room, Spent Fuel Building, Radwaste Building, and HP Control Point Area.
Details and findings are noted below.
a.
Observation of Plant Ooerations At the time of the inspector's initial arrival on site at the start of the second shift on January 22, 1979, the plant was shut down as the result of a trip earlier in the day. The inspector learned by discussions with plant personnel and review of the Control Room log, that one control rod failed to insert at the time of the trip. The rod was reenergized
shortly after the trip, cycled in one step, and deenergized at which time it inserted normally. The inspector witnessed rod drop timing tests which were conducted on all control rods twice,in accordance with procedure OP-4703. All rod drop times were within specification and a normal reactor startup was per-formed.
No items of noncompliance were identified.
b.
Monitorino Instrumentation and Annunciators The inspector checked plant instrumentation in the Control Room and other locations throughout the plant to verify that required instrumentation was operable and that indicated parameters were within prescribed limits. This check was done several times during the inspection including the time of the plant startup on January 22. The observed instrumentation included:
Control Rod position indication
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Main Coolant System flow, pressure and temperature
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Nuclear instrument and Reactor Protection System channel
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operability Primary Vent Stack radiation monitors
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Vapor container APD radiation monitors
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PWST and OWST tank levels
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Control Room annunicators
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The reasont for existing annunciators was satisfactorily resolved.
No items of noncompliance were identified.
c.
Radiological Controls Radiation controls established by the licensee, including posting of radiation areas, radiological surveys, condition of step-off pads, and the disposal of protective clothing were observed for conformance with the requirements of 10 CFR 20 and OP-8100,
" Establishing and Posting Controlled Areas," and OP-8101, " Plant
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Radiological Surveys."
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No items of noncompliance were identified.
d.
Plant Housekeeping Plant housekeeping conditions, including general cleanliness and storage of materials to prevent fire hazards, were observed in all areas toured. The inspector also checked installation of a temporary sand-bag dam surrounding the turbine lube oil sump, concrete dams installed to isolate each diesel generator room, and installation of permanent fire barriers between the switch-gear room and the control room. Housekeeping and cleanliness were good.
No items of noncompliance were identified.
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Fluid Leaks and Piping Vibration Systems and equipment in all areas toured were observed for the existence of fluid leaks and abnormal piping vibration.
No inadequacies were identified.
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Pipe Hangers / Seismic Restraints Pipe hangers and restraints installed on various piping systems through the plant were observed for proper installation and tension.
No discrepancies were identified.
g.
Equipment Caution / Lockout Taas The caution / lockout tags associated with Tag Orders 79-11, 79-15, 79-64 and 79-80 were verified for prcper posting.
No discrepancies were identified.
h.
Licensee plant Tours The licensee's policy and practice regarding plant tours was reviewed to verify conformance with procedure AP-2001, "Respon-sibilities and Authorities of Operations Department Personnel,"
Revision 3.
There have been no revisions to the licensee's tour policy since the previous inspection in this area.
No discrepancies were identified.
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1.
Control Room Manning l
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Control Room and refueling floor manning were reviewed several times during the inspection to verify conformance with the requirements of Technical Specifications.
No items of noncompliance were identified.
5.
In-Office Review of Licensee Event Reports (LER's)
The inspector reviewed LER's received in RI office to verify that details of the event were clearly reported including the accuracy of the description of cause and adequacy of corrective action. The inspector also determined whether further information was required from the licensee, whether generic implications were indicated, and whether the event warranted on-site followup. The following LER's were reviewed:
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78-27, Steam Generator Chloride Concentration greater than
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0.5 ppm.
78-28, Main Steam Safety Valve Setpoint Drift.
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78-29, r planned Reactivity Insertion.
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78-30, Steam Generator Tube Degradation.
78-31, Degradation of Fuel Cladding.
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78-32, Loss of Flow Path from BAMT to Charging Pumps.
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78-33, Loss of Flow Path from BAMT and SI Tank to Charging
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Pumps.
78-34 TV-207 Failed Type C Leak Test.
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78-35, PWST and DWST Combined Volume less than 85,000 gallons.
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78-36, Steag Generator Chloride Concentration greater than
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0.5 ppm.
78-37, SI Accumulator Cover Gas Pressure greater than 15 psig.
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78-38, VC APD Pump Motor Failure.
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78-39, VC APD Pump Motor Failure.
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The above LER's were closed based on satisfactory review in the Region I office, except those LER's selected for onsite followup.
- denotes those LERs selected for onsite followup.
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6.
On Site Followup of LER's For those LER's selected for onsite folicwup the inspector verified that reported description of events and corrective action were accurate.
that events were reviewed by the Plant Operations Review Committee (PORC),
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and that corrective action was adequate. The followup included dis-i cussions with plant personnel and review of selected logs, PORC minutes.
and Plant Information Reports.
Findings are as noted below.
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78-29, Unplanned Reactivity Insertion
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While removing the guide tube, the licensee inadvertently withdrew the associated control rod for a fuel assembly. The manipulator handling tool operator was unaware of the situation until the contr31.ed became visible at the top of the assembly.
The cause was due to an improper setting on the load cell con-troller. The controller was readjusted to the proper setting and associated refueling procedure CP-1209 was revised, as verified by the inspector, to add precautions concerning the load cell setting and operations. The inspector had no further questions on this event.
78-30, Steam Generator Tube Degradation
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Previous inspections had followed the status of primary to secondary leakage in Nos.1 and 4 Steam Generators. The leaking tubes were identified and plugged along with some others which had degraded but not failed during the recent refueling outage.
A review of steam generator chemistry records and Reactor Coolant
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System leak rate data since the startup shewed no evidence of further leakage.
78-31, Degradation of Fuel Cladding
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Reactor Coolant System iodine levels with Core XIII had indicated one or more cladding-failures. The licensee located and removed four fuel assemblies which had cladding failures during the recent refueling outage. The inspector reviewed coolant system chemistry records for the period since the startup for Core XIV.
No evidence of fuel cladding failure was identified.
78-35, PWST/DWST Combined Volume less than 85,000 Gallons
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Due to a failure of the Shift Supervisor and auxiliary operator to note the decreasing level of these tanks, the level was allowed to go below the required 85,000 gallons. The inscector verified
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that the required level was restored within the allowed time period and that plant operations were suspended until tank levels were back in specification. The inspector expressed some concern over the cumbersome calculations which must be made by the operators to verify canpliance with this specification, i.e. each tank level indicated in feet is converted to gallons, unuseable volume subtracted, and the gallons remaining in each tank added together.
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1 The licensee stated that normally greater than 85,000 gallons is maintained in the PWST so that this calculation is unnecessary and that operators and shift supervisors have been reminded to review logs promptly for off-normal conditions to preclude recurrence of this event. The inspector found this corrective action adequate.
7.
Post-Refueling plant Operations The inspector reviewed plant records, including logs and completed test procedures, to verify that systems disturbed or modified during the outage were returned to service in accordance with approved procedures and that control rod withdrawal sequence and rod with-
-drawal operation were in effect prior to startup. The following completed test procedures were reviewed.
OP-4222, Reactor Control System Precritical Check, performed
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December 17, 1978.
OP-4611, Nuclear Instrumentation and Reactor Protection System
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Precritical Check, performed December 16, 1978.
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0P-4645, Nuclear Instrumentation Channel Calibration, performed
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December 2,1978.
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OP-4703, Control Rod Drop Time Measurement, performed
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December 16, 1978.
OP-2103, Reactor Startup and Shutdown, performed December 17, 1978.
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OP-4702, Steam Generator Blowdown Line Trip Valves, performed
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December 1978.
OP-4630, Accumulator Time Delay Actuation Verificat1on, performed
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December 11, 1978.
OP-2000.49, Installation and Testing.of the Post-LOCA Recirculation
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System Alterations, performed December 1978.
Except as noted below, no items of noncompliance or other inadequacies were identified.
OP-4702 was used _ to conduct a Type C leak rate test of the Steam Generator Blowdown Line Trip Valves and the new emergency feedwater isolation valves The latter valves were installed in a new section
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of piping which taps into the blowdown lines near the Blowdown Line Trip Valves. A temporary change had been issued to include the new valves in the leak test, but che isolation volume for the piping involved had not been changed to reflect the new piping volume. The licensee recalculated the leak rates for the valves using the new volume at the inspector's request.
Leak rate was acceptable. The licensee stated that the procedure will be changed to reflect the correct isolation volume. This item is unresolved pending review of the revised proceduro.
(29/79-01-01)
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post-Refueling Startuo Testing The inspector reviewed the results of startup tests performed by the licensee to verify that the testing was performed in accordance with approved procedures, that the facility was operated in conformance with requirements of Technical Specifications and licensee pro-cedures, and that reactor physics test data was within allowable tolerances of-predicted values from the Core XIV Performance Analysis.
The following completed test procedures and associated data were reviewed.
OP-1701, Core XIV V.0.L. Zero Power Physics Test Procedures;
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completed December 21, 1978.
OP-1702, Core XIV Zero to Full Power Physics Test Procedure;
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completed December 26, 1978.
OP-2100, Plant Startup from Cold Shutdown; completed December 17,
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1978.
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OP-2103, Plant Startup and Shutdown; completed December 17,1978.
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OP-4601, NI Channel Functiont.. Test; completed January 8,1979.
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l OP-4611, NI and RPS Precritical Check; completed December 16, 1978.
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OP-4645, NI Channel Calibration; completed December 2,1978.
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l OP-4708, Determination of Shutdown Margin; completed December 16,
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OP-4703, Control Rod Drop Time Measurement; completed December 16,
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No items of noncompliance were identified.
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9.
In-Office Review of Monthly Statistical Reoorts The inspector reviewed the licensee's Monthly Statistical Reports for the period October - December 1978 to verify that reporting requirements were being met.
No reporting inadequacies were identified.
10. Unresolved Items Unresolved items are matters about which more infonnation is required in order to ascertain whether they are acceptable items, items of noncompliance, or deviations. An unresolved item disclosed during the inspection is discussed in paragraph 7.
11. Exit Interview The inspector met with licensee representatives (see paragraph 1 for attendees) on January 26, 1979.
The inspector sumarized the scope and findings of the inspection as detailed in this report.
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