IR 05000029/1978016
| ML19270F031 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 11/24/1978 |
| From: | Kalman G, Keimig R, Lazarus W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19270F028 | List: |
| References | |
| 50-029-78-16, 50-29-78-16, NUDOCS 7901110187 | |
| Download: ML19270F031 (12) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Repo-t No.
50-029/78-16 Docket No.50-029 License No.
DPR-3 Priority
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Category C
Licensee:
Yankee Atomic Electric Company 20 Turnpike Road Westborough, Massachusetts 01581 Facility Name:
Yankee Nuclear Ponr Station (Yankee Rowe)
Ir.spection at:
Rcwe, Massachusetts Inspection conducted: October 30 - November 2 & 7-9f, 1978 Inspectors:
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W.fgiarus,GeactorInspector date signed
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.?f G. Kalman, Reactor Inspector date signed date si ned M
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Approved
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.. R. Keimfg, Chief, Reactor Projects
' date signed Section No. 1, R0&NS Branch Inspection Summary:
Inspection on October 30-November 2 and 7-9, 1978 (Report No. 50-029/78-16)
Areas Inspected: Routine unannounced inspection by regional based inspectors of plant operations, including: a tour of accessible areas; a review of shift logs and operating records; review of Licensee Event Reports (LER's);
followup on previous inspection findings; refueling preparations; refueling activities; major outage maintenance; and refueling restoration planning.
The inspection involved 77 inspector-hours onsite by two regional based inspectors and 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br /> by one supervisor.
Results:
Of the seven areas inspected, two items of noncompliance were identified in two areas (Deficiency - failure to follow procedure for main-taining the Jumper and Bypass Log; and, Deficiency - failure to wear required protective clothing in radiation work area).
Region I Form 12 7901110\\S1 (Rev. April 77)
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DETAILS 1.
Persons Contacted
- R. Aron, Engineering Assistant
- H. Autio, Plant Superintendent W. Billings, Chemistry and HP Supervisor
- T. Danek, Operations Supervisor
- D. Dees, Quality Assurance Representative M. Ebert, Reactor Supervisor
- D. Kaupinen, Tech. Asst. Operations P. Laird, Maintenance Supervisor R. Mitchell, Engineering Asst.
- J. Staub, Tech. Asst. to Plant Superintendent
- N. St. Laurent, Asst. Plant Superintendent J. Trejo, Health Physicist
- T. White, Quality Assurance Representative USNRC
- D. L. Caphton, Chief, Nuclear Support Section No.1 In addition to the above listed individuals, shift supervisors, control room operators, auxiliary operators, maintenance, and contractor personnel were contacted during the course of the inspection.
- denotes those present at exit interviews.
- present at exit interview November 9,1978.
2.
Licensee Action on Previous Inspection Findings (Closed) Noncompliance (29/77-28-01): Control Rod drop time measure-ments performed with Tavg less than 5150F.
The inspector verified that the noncompliance had been reviewed by the licensee and that corrective action had been completed in accordance with the YR letter of February 2,1978.
Procedure OP 4703, Revision 6, now reflects the TS requirement that Tavg be greater than 5150F for this test.
(Closed) Noncompliance (29/77-28-02): Intermediate Power Range trip setpoints not set to trip at less than 25 percent power.
The inspector verified that corrective action had been taken in accordance with the YR letter of February 2,1978.
Amendment 47 to the TS deleted this requiremen.
(Closed) Followup (29/78-04-02): The inspector observed the instal-lation of new radiation monitoring instrumentation in the Control Room which is intended to upgrade the reliability and performance of the radiation monitoring system.
(Closed) Unresolved (29/78-13-01): The inspector reviewed procedures OP 3000, Revision 6, and OP 3003, Revision 3, which had been revised to incorporate instructions to operators previously issued by a standing order.
3.
Shift Logs and Operating Records a.
The inspector reviewed the following plant procedures to determir.e the licensee established administrative requirements in this area in preparation for a review of selected logs and records.
AP-0003, Plant Operations Review Committee Responsibilities
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and Authorities, Revision 3.
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AP-0004, Plant Information Reports, Revision 3.
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AP-0017, Switching and Tagging of Plant Equipment, Revision 4.
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AP-0207, Equipment Control, Revision 1.
AP-0018, Bypass of Safety Function and Jumper Control
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Log, Revision 5.
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AP-0021, Operating Memos, Revision 3.
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AP-2007, Maintenance of Operations Department Logs, Revision 4.
AP-0216, Housekeeping and Cleanliness Control, Original.
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AP-0042, Housekeeping for Maintenance and Modifications, Original.
The inspector had no questions in this area.
b.
Shift logs and operating records were reviewed to verify that:
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Control Room log sheet entries are filled out and initialed;
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Auxiliary log sheets are filled out and initialed;
Shift Supervisor and Control Room log entries involving
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abnormal conditions provide sufficient detail to commun-icate equipment status, 1ockout 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-cation requirements;
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" Plant Information Reports" confirm there are no violations of Technical Specification reporting or LC0 requirements; and, Logs and records were maintr.ined in accordance with
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Technical Specifications and the procedures in 4.a above.
c.
The review included discussions with licensee personnel and the following plant shift logs and operating records:
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Shift Supervisor's Log, September 15 - November 1,1978; All Operating Memos issued since last inspection of this
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area;
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All effective Standing Orders; Bypass of Safety Function and Jumper Control Log Control
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Sheets78-106 through 78-160; Switching / Tagging Orders (active) through 78-870;
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Plant Information Reports (PIR) 78-05 and 78-06;
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Minutes of Plant Operations Review Committee (PORC)
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Meetings 78-34 through 78-56.
Except as noted below, no discrepancies were identified.
In the review of the Bypass of Safety Function and Jumper Control Log, the inspector compared the Master Index which indicated 20 active bypass / jumper requests with the active section in the log which indicated only 10 active requests.
The closed out section was checked for the remaining 10, but they could not be accounted for immediately.
Investigation by the licensee disclosed that
9 of the 10 had been closed out and removed from the book.
The status of the last unaccounted for request had not been determined by the end of the inspection.
Procedure AP-0018,
" Bypass of Safety Function and Jumper Control Log," requires the Master Index to be updated when a jumper request is closed out.
With discrepancies between the Master Index and the active requests in the log, the Shift Supervisor cannot determine which is correct and thus cannot know the status of jumpers or bypassed safety functioris in the plant.
Failure to keep the Master Index updated as required by AP-0018 and Technical Specification 6.0 represents a deficiency level item of noncompliance.
(78-16-01)
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, Vapor Container, Spent Fuel Building, Radwaste Building, and HP Control Point Area.
Details and findings are noted below.
a.
Monitoring Instrumentation and Annunciators Plant instrumentation for Main Coolant system temperature, charging flow, source range neutron monitors, and STC manipulator crane and SFB crane radiation monitors were observed during a plant tour to verify that Technical Specification required instrumentation was operable and that indicated parameters were within prescribed Limiting Conditions for Operation (where applicable). No abnormal annunciator alarms were identified (plant in refueling mode).
No items of noncompliance were identified.
b.
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 Radiological Surveys."
No items of noncompliance were identified.
c.
Plant Housekeeping Plant housekeeping conditions, including general cleanliness and storage of materials to prevent fire hazards, were observed
in all areas toured to verify conformance with AP-0216, " Housekeeping and Cleanliness Control." The inspectors expressed concern over the cleanliness of the Spent Fuel Pool area which contained tools and equipment associated with a pool modification and temporary pool pumps and filters which were being used to clean the p:,vl water.
The area was cleaned and unnecessary equipment removed before the end of the inspection in preparation for fuel handling.
On re-inspection, conditions were acceptable.
No item of noncompliance were identified.
d.
Fluid Leaks and Pipirg Vibration
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Systems and equipment in all areas toured were observed for the existence of fluid leaks and abnormal piping vibration.
No inadequacies were identified.
e.
Pipe Hanaers/ 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.
f.
Equipment Caution / Lockout Tacs The caution / lockout tags associated with Tag Orders78-822, 78-815, and 78-869 were verified for proper posting.
No discrepancies were identified.
g.
Licensee Plant Tours The licensee's pclicy 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 identifie.
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h.
Control Room Manning 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 follCWJp.
The following LER's were reviewed:
78-12, Purification Pump Mechanical Seal Failure.
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78-13, Loop Seal Radiation Monitor Failure.
78-18, VC Air Particulate Monitor Failure.
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78-19, Primary Coolant D.E. Iodine Greater Than 1.0 uCi/gm.
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78-20, Secondary Water Chiaride Concentration Greater Than 0.5 ppm.
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78-21, Primary Vent Stack RMS Iodine Channel Failure.
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78-22. High Level Radiation Monitor Failure.
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78-23, Primary Coolant D.E. Iodine Concentration Greater Than
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1.0 uCi/gm.
78-24, Secondary Water Chloride Concentration Greater Than 0.5 ppm.
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78-25, Failure of Main Coolant Leakage Air Particulate Monitor.
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78-26, Frimary Vent Stack RMS Particulate and Iodine Channels
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Failure.
77-52, CIV PU-MOV-541 Failed to Open Electrically (Supplemental
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Report).
78-02-E, Failure to Collect Vegetation Samples.
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78-03-E, Failure to Collect Aquatic Plant Samples.
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The inspector discussed the report format requirements with the licensee and brought their attention to the fact that NUREG-0161 requires each section of the LER form to be completed, specifically that items 10 " Event Description and Probable Consequences" and 27, "Cause Description and Corrective Actions" must be completed with a concise, meaningful descrtption for use in putting information into a computer data bank. Any amplifying information required to provide additional technical details is to be included on a supplemental sheet.
The licensee has been using a supplemental sheut exclusively without completing the sections 10 and 27 as discussed above.
The licensee has agreed to complete the LER's as required by NUREG-0161 for future reports.
This item is unresolved pending review of subsequent LER's received in the RI office.
(78-16-02)
No other reporting inadequacies were identified.
6.
In Office Review of Monthly Statistical Reports The inspector reviewed the licensee's Monthly Statistical Reports for the period July - September 1978 to verify that reporting
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requirements were being met.
No reporting inadequacies were identified.
7.
Preparation for Refueling a.
Scope The inspectors reviewed the receipt and inspection records associated with the 40 new fuel asse ?.blies for core XIV.
Technical Specification requirements were verified to be included in the refueling procedures.
The fuel sipping procedures and the sipping equipment design were reviewed.
The inspector verified that the licensee had completed a safety evaluation associated with the proposed sipping operation.
The results of refueling related equipment inspections and equipment operability tests were checked for completeness.
Reactor vessel disassembly procedures were reviewed and several phases of the disassembly were observed.
Refueling equipment and related areas of the facility including the spent fuel storage pool were inspecte *
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b.
Documents Reviewed (1) Procedure OP-7202, Revision 0, Fuel Sipping.
(2)
EDCR No. 77-21, Revision 2, Spent Fuel Sipping Equipment.
(3) Procedure OP-1700, Revision 6, Cycle XIV Reactor Refueling and Component Inspection.
(4) Procedure OP-7200, Revision 3, Receiving, (Jnloading and Inspecting New Reactor Fuel.
(5) Exxon fuel shipment and quality assurance documents.
(6) Procedure AP-0216 Revision 0, Housekeeping and Cleanliness Control.
(7)
Procedure OP-4505, Revision 5, Inspection and Testing of Fuel Handling Equipment, including the completed check list.
(8)
Procedure OP-5951. Revision 3, Inspection and Maintenance of the V.C. Polar Crane, including the completed check list.
(9)
Procedure OP-1100, Revision 3, Dismantling and Reassembly of the Reactor Systems for Core XIV Refueling.
(10) Procedure OP-1209, Revision 5, Operation of the V.C.
Manipulator Crane, Handling Fixtures and Transfer Equipment.
(11) Procedure OP-4226, Revision 6, Testing of Fuel Handling Equipment with Dummy Fuel Assembly, including completed check list.
c.
Findings The inspectors identified no problems during the course of the document review.
While an inspector was observing the removal of control rod guide tubes in preparation for refueling, the grapple mechanism malfunctioned and latched the control rod train along with the guide tube which was being removed. The control rod was inadvertently withdrawn from the core as the guide tube was lifted.
The shift supervisor became aware of the malfunction when the ithdrawn control rod train came into view below the ascending
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guide tube.
The shift supervisor imediatefy directed the operator to lower the guide tube and control rod into the core.
The faulty grapple was repaired and the guide tubes were subsequently removed without further problems.
At the time of the inadvertent control rod withdrawal, the primary coolant was borated for refueling and all other rods were inserted.
In this condition individual rods may be with-drawn safely and are actually withdrawn during subsequent opera tions. However, the subject rod withdrawal was inadvertent and, therefore, a safety concern.
The licensee stated that operating precautions will be added to appropriate refueling procedures prior to the next refueling to prevent a similar occurrence. This matter is unresolved and will be reviewed during a subsequent inspection.
(78-16-03)
8.
Refueling Activities a.
Scope The inspection verified that Technical Specification pre-requisites were satisfied during the refueling and that the refueling proceeded in accordance with approved procedures.
Fuel transfer activities in the vapor containment and the spent fuel storage building were observed.
Fuel status boards were checked for accuracy.
General housekeeping and radiation protection practices were inspected.
b.
Findings No operational discrepancies were identified during the refueling.
The inspectors visually observed a new fuel assembly being lifted out of the spent fuel pool by the new fuel elevator.
The licensee representative stated that this was done to verify the assembly serial number.
The inspectors identified a concern over the speed at which the elevator brought the assembly out of the water in that an irradiated fuel assembly inadvertently placed on the elevator or a contaminated new assembly could result in a potential radiation hazard before the elevator operator could react to stop the upward motion of the elevator.
The licensee's representative was requested to review the operation of the elevator to determine whether existing administrative / mechanical controls are adequate to assure safety during the conduct of the subject operation.
This item will be reexamined during a future inspection. (78-16-04)
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During fuel transfer operations in the spent fuel pool building, it was noted that a member of the plant security force was in the building without gloves as required by the applicable radiation work permit (RWP).
Subsequently another member of the security force commenced his duties in the building without a head cover as required by the RWP.
Failure to wear prescribed protective clothing is contrary to procedure OP-8415, Radiation Work Permit. This constitutes a deficiency level item of noncompliance with Technical Specification 6.0.
(78-16-05)
9.
Major Outaae Maintenance a.
Scope The inspectors ascertained that approved procedures exist for the maintenance activities scheduled during the refueling outage. Maintenance activities were observed on a sampling basis to verify that procedures were being followed.
b.
Documents Reviewed Procedure OP-5967. Revision 0, Installation of Fuel
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Sipping Equipment.
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Procedure SP-49716-700, Revision 0, Installation Procedure for Yankee Rowe Fuel Pool Gate Bracket.
(Mercury Company of Norwood Inc. ).
Yankee Rowe PORC Review of Procedure SP-49716-700.
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c.
Findinas No discrepancies were identified in the inspection of the above items.
10.
Refueling Restoration Planning a.
Scope The post refueling schedule, procedures fer restoring systems to operating conditions and the associateo testing program was reviewed.
b.
Findings No discrepancies were identified in the inspection of the above item >
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11.
Unresolved items Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items, items of noncompliance, or deviations.
Unresolved items disclosed during the inspection are discussed in paragraphs 5 and 7.c.
12.
Exit Interview The inspectors met with licensee representatives (see paragraph 1 for attendees) on November 2 and 9,1978.
The inspectors summarized the scope and findings of the inspection as detailed in this report.