IR 05000271/1981020
| ML20040C920 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 01/13/1982 |
| From: | Collins S, Gallo R, Raymond W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20040C918 | List: |
| References | |
| 50-271-81-20, IEB-79-03A, IEB-79-19, IEB-79-3A, IEIC-81-14, IESC-81-14, NUDOCS 8201290376 | |
| Download: ML20040C920 (23) | |
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U.S. NUCLEAR REGULATORY COMMISSION 0FFICE OF INSPECTION AND ENFORCEMENT TERA 5 -271 Region I J811018 811104 Report No. 81-20 811109 811125 Docket No. 50-271 811121 License No. DPR-28 Priority Category C
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Licensee:
Vermont Yankee Nuclear Power Corporation 1671 Worcester Road Framingham, Massachusetts 01701 Facility Name:
Vermont Yankee Inspection at:
Vernon, Vermont Inspection conducted:
December 1, 1981 - January 4, 1982 Inspectors:
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W. J. Raymofd, Sehior Resident Inspector date signed
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I AIA1 S. 'J. Collins, Resident Inspector dat'e signed date signed Approved by:
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i fl3 f 9 2-R. M. Gallo, Chief", Reactor Projects da'te signed Section 1A, Projects Branch #1 Inspection Summary:
Inpsection on December 1, 1981-January 4, 1982 (Report No. 50-271/81-20)
Areas Inspected:
Routine announced inspection on regular and backshifts by Resident Inspectors of: action taken on previous inspection findings; IE Bulletin review and followup; IE Circular followup; review of shift logs and operating records; plant tours; followup of refueling activities; observations of physical security; surveillance testing; review of plant operations; Fire Protection; and, In-Office review of licensee event reports. The inspection involved 46 inspector hours onsite by two resident inspectors.
Results: Of the eleven areas inspected, no items of noncompliance were identified.
Region I Form 12 8201290376 820115 (Rev. April 77)
gDRADOCK05000
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DETAILS 1.
Persons Contacted The below listed technical and supervisory level personnel were among those contacted:
Vermont Yankee Nuclear Power Corporation Mr. R. Branch, Operations Supervisor Mr. F. Burger, Quality Assurance Coordinator Mr. B. Buteau, Reactor Engineering and Computer Supervisor Mr. P. Donnelly, Instrument and Control Supervisor Mr. R. Kenny, Engineer, Assessment Coordinator Mr. D. Girroir, Mechanical Engineer Mr. L. Goldthwaite, Instrument and Control Foreman Mr. S. Jefferson, Technical Services Superintendent Mr. B. Leach, Health Physicist Mr. M. Lyster, Operations Superintendent Mr. W. Murphy, Plant Manager Mr. J. Pelletier, Assistant Plant Manager Mr. D. Reid. Engineering Support Supervisor Mr. S. Vekasy, Senior Systems Engineer 2.
Action Taken on Previous Inspection Findings a.
(Closed) Unresolved Item (50-271/78-27-02):
Licensee objection to coating structural steel in diesel generator rooms. A verification of item 3.1.12, Protection for Structures, of Table 3.1, Amendment 43 by the licensee reported this item as comple(e. The inspector
verified that structural steel supporting the walls and ceiling of I
the DG rooms has been coated. This item is closed.
b.
(Closed) Unresolved Item (50-271/78-27-03): Outside access to service water pump area. A verification of item 3.1.15, Access to Fire Areas, of Table 3.1, Amendment 43 by the licensee reported this item as complete. The inspector verified that Door 208 has been restored to an operable condition and is locked from the outside. This item is closed.
c.
(Closed) Unresolved Item (50-271/81-18-01): Licensee investigation and repair of MSIV 80C. Licensee Event Report 50-271/81-27 was sub-mitted by letter dated December 7, 1981, to describe the event and scheduled corrective actions. This item is closed, d.
(Closed) Unresolved Item (50-271/81-19-01): Licensee submission of the 14-day followup report to LER 81-33/1P and subsequent NRC
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review of licensee corrective actions. The licensee subsequently l
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issued LER 81-33/1T dated December 9, 1981, to describe the event and scheduled corrective actions. This item is closed.
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3.
IE Bulletin Review and Followup Licensee responses and actions taken for the IE Bulletins listed below were reviewed to verify that:
the bulletins were received onsite and reviewed for applicability
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to the facility; bulletin action items, if applicable, and identified problems were
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appropriately dispositioned; corrective actions taken, or planned, were appropriate; and,
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responses to'the NRC were accurate and within the time period
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specified in the bulletin.
Inspector followup on selected bulletins is summarized below. The inspector had no further comment on the subject bulletins, except as indicated below, a.
IE Bulletin 79-03A, Longitudinal Weld Defects in ASME SA-312, Type 304 Stainless Steel Pipe, dated April 4, 1980 Vermont Yankee responded to the concerns of IEB 79-03A in a letter dated August 5,1980, WVY 80-111, L. D. Marsolais to B. H. Grier. The licensee determined that none of the subject pipe is in use or planned for use at the facility in safety-re-lated systems subject to design stresses greater than 85 percent of the Code allowable stresses. This item is closed..
b.
IE Bulletin 79-19, Packaging of Low-Level Radioactive Waste for Transport and Burial, dated August 10, 1979 Vermont Yankee responded to the concerns of IEB 79-19 in a letter dated September 26, 1979, WVY 79-112, D. E. Moody to B. H. Grier.
This area was subsequently inspected by a Region-based inspector during December 5-6, 1979, as noted in IR 50-271/79-22. A followup inspection in the Radwaste Transportation area was conducted during March 24-27, 1981, as noted in IR 50-271/81-07. This item is closed.
4.
IE Circular Followup The following IE Circular was reviewed to determine whether the acticns listed below were taken by the licensee:
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Corporate management forwarded the Circular to the facility for review;
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A review for applicability was perfomed; and
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Appropriate corrective actions have been taken or are scheduled
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to be taken by the licensee.
a.
IE Circular 81-14. Main Steam Isolation Valve Failures to Close, dated November 5, 1981. Vermont Yankee responded via internal Memo File No. 3.2, December 11, 1981, G. Cappuccio to J. Pelletier as follows:
no cases of binding between valve stem and packing at VY
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similar problem with gauling between the guide rods and
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springplatebushingsoftheactuator,(LER 79-11,20and35).
Cause determined to be similar metals; bushing material was
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steel and was replaced with bronze to prevent qauling.
Maintenance program to replace all bushings; presently 3 of 8 actuators have been modified.
poorqualityofcontrolairtoMSIV's,(LER's 81-22, 78-04
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and 77-35) for pilot valve failures due to dirt. VY has made modifications:
replaced all carbon steel. piping with stainless steel tubing from downstream of 1 micron filter to the pilot valves.
Instrument air dryers, prefilters and afterfilters placed on maintenance schedule to assure air quality (OP 5303,11SIV Pilot Valve Ma~intenance), Control and Instrument Air System monitored and drained of moisture by Auxiliary Operators once per shift per AP 0150. Recomended 6 month PM cycle for control air compressor dryer, prefilter and afterfilter.
Based en the above actions, this item is closed, 5.
Shift Logs and Operating Records a.
The inspector utilized the following plant procedures to detemina the licensee established administrative requirements in this area in preparation for review of various logs and records.
AP 0831, Plant Procedures, Revision 8, dated November 24, 1981
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AP 0150, Responsibility and Authority of Operations Department
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Personnel, Revision 16, dated October 21, 1981 AP 0153, Operations Department Comunications and Log Main-
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tenance, Revision 9, dated August 17, 1981 m
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AP 0140 VY Local Control Switching Rules, Revision 5, dated
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October 16, 1981 AP 0020, Lifted Lead / Installed Jumper Request Procedure,
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Revision 4, dated October 16, 1980 AP 0021, Maintenance Requests, Revision 10, dated December 30, 1981
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AP 0030, Plant Operations Review Committee, Revision 6, dated
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January 7, 1980 The above procedures, Technical Specifications, ANSI N18.7-1972
" Quality Assurance Requirements for Nuclear Power Plants" and 10 CFR 50.59 were used by the inspector to detemine the accepta-bility of the logs and records reviewed.
b.
Shift logs and operating records were reviewed to verify that:
Control Room logs and surveillance sheets are properly
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completed and that selected Technical Specification limits were met.
Control Room log entries involving abnormal conditions pro-
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vide sufficient detail to communicate equipment status, lockout status, correction and restoration.
Log Book reviews are being conducted by the staff.
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Operating and Special orders do not conflict with Technical
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Specifications requirements.
Jumper (Bypass) log does not contain bypassing discrepancies
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with Technical Specification requirements and that jumpers are properly ppproved prior to installation.
c.
The following plant logs and operating records were reviewed periodi-cally during the period of December 1, 1981-January 4, 1982:
Control Room Log
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Night Order Book Entries
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CR Infomation Book
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Jumper / Lifted Lead Log Book
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Safety Related Maintenance Requests
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Control Room Operator Pound Sheet
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Auxiliary Operator Rounds Sheet
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Communications Log
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Control Room Chemistry Log Sheets
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Shift Turnover Checklist
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No items of noncompliance were identified, d,
Operational Safety Veri.fication:
Duringtheinspectionperiod;theinspectorconductedareytew
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of the status of the Control Rod Drive System valve lineup, _ ion A
review of the completed Valve Lineup File for OP 2111, Revis 12 was conducted and no inadequacies were identified.
Plant Tour The inspector conducted a tour of accessible areas of the plant including the Control Room Building, Turbine Building, Reactor Building, Diesel Rooms Intake Structure, Security Gate House 2 and Alam Staticn, Radwaste Building and Control Point Areas:
a.
Monitoring Control Room Panels Routinely during the inspection period, the inspectors conducted.re-views of the control ~' room panels. The following items were reviewed to determine the licensee'-s adherence to Licensee Technical Specifica-tion - Limiting Conditions for Operation and to verify the licensee's adherence to approved procedures:
Switch and valve positions required to satisfy LCO's, where
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applicable, personnel knowledge of recent changes to procedures, facility configuration and existing plant conditions.
Alarms or absense of alams. Acknowledged alams were reviewed
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with on shift licensed personnel as to cause and corrective actions being taken where applicable.
Review of " pulled alarm cards" with on shift personnel.
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Meter indications and recorder values.
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Status lights and power available lights,
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Front panel bypasses.
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Computer printouts.
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Comparison of redundant readings.
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No items of noncompliance were identified.
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b.
Radiological Controls
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Radiation controls established by the licensee, including: posting of radiation areas, radiological surveys, condition of step-off pads, and disposal of protective clothing were observed for confomance with the requirements of 10 CFR 20 and AP 0503, Establishing and Posting Controlled Areas, OP-4530, Dose Rate Radiation Surveys, i
OP 4531, Radioactive Contamination Surveys, AP 0504, Shipment and Receipt of Radioactive Materials.
Confimatory surveys were conducted in the 'following areas to
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verify licensee posted results: Reactor Building general areas -
all elevations.
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Periodically, Radiation Work Permits were reviewed by the inspector
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to verify conformance with licensee procedure AP 0502, Radiation Work Pemits.. Controls established in accordance with the following RWP was reviewed: RWP 81-01109.
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No inadequacies were identified.
c.
Plant Housekeeping and Fire Prevention Plant housekeeping conditions, including general cleanliness and storage of materials to prevent fire hazards were' observed in all
areas toured for confomance with AP 0042, Plart Fire Prevention and AP C024, Plant Housekeeping.
No inadequacies were identified.
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Fluid Leaks and Piping Vibrations Systems and equipment in all areas toured were observed for the
existence of fluid leaks and abnomal piping vibrations.
No inadequacies were identified.
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Pipe Hangers / Seismic Restraints During routine tours of-the plant,' pipe hangers and restraints installed on'various piping systems were observed for proper installation, tension, and condition.
No inadequacies were ide~ntified.
f.
Control Room Manning / Shift Turnover Control Room Manning was reviewed for confonnance with the require-ments of 10 CFR 50.54 (k), Technical Specifications, AP 0152, Shift.
Turnover AP 0150, Responsibility and Authority of Operations Depart-ment Personnel and AP 0036, Shift Staffing. The inspector verified, during the inspect'on, that appropriate licensed operators were on shift. Manning requirements were met at all times. Several shift'
turnovers were observed during the course of the inspection.
A',1 were noted to be thorough and orderly.
No items of noncompliance were identified.
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Equipment Tagout and-Controls Tagging and controls of equipment released from service were reviewed during inspection. tours to verify equipment was controlled in accordance with AP 0140, YY-Local-Control Switching Rules.
No inadequacies ware identified.
h.
Analyses of Process Liquids and~ Gases Analyses results from samples of process liquids and gases were re-viewed periodically during the inspection to verify conformance with
, regulatory requirements. The results of. isotopic analyses from reactor coolant, off-gas and stack samples were reviewed routinely.
from the " Daily Plant Status Report" to verify that Technical Speci-fication Limits were not exceeded and that no adverse trends were apparent.
No inadequacies were identified.
7; Followup of Refueling' Activities-Refueling and related activities in progress during the period were reviewed to verify compliance with licensee administrative and regulatory-
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requirements, The specific areas reviewed are discussed below.
(1)_ Preparations for reactor startup conducted on December 1, 1981, including:
Review of Reactor Startup Prerequisite List, VYOPF 0100.01,
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dated Decenber 1, 1981 Reactor Criticality Check Sheet, VYOPF 0100.02, dated
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December 1, 1981.
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No inadequacies were identified.
8.
Observations of Physical Security The inspector made observations, witnessed and/or verified during regular and offshift hours that selected aspects of plant physical security were in accordance with regulatory requirements, the physical security plan and approved procedures, a.
Physical Protection Security Organization observations indicated that a full time member of the security
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organization with authority to direct physical security actions was present as required.
manning of all shifts on various days was observed to be as
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required.
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Access Control identification, authorization and badging.
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access control searches, including, when applicable, the use
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of compensatory measures during periods when equipment was inoperable.
escorting.
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c.
Physical Barriers selected barriers in the protected areas and vital areas were
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observed and random monitoring of isolation zones was performed.
Observation of vehicle searches were made.
inspector tours of gate house 2, the Central and Secondary Alarm
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Stations were conducted at random periods.
No items of noncompliance were identified, t
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9.
Surveillance Testing The inspector observed or reviewed portions of the following surveillance tests to verify that testing was performed in accordance with procedures, that results were in confomance with Technical Specifications and proce :
dure requirements, that test instrumentation was calibrated, that redun-dant system (s) or component (s) were available for service, that work was being perfomed by qualified personnel, and that activities were-in com-pliance with AP 4000, Surveillance Testing Control, a..
Review of HPCI overspeed testing data conducted on December 2, 1981, per VYOP 4120, High Pressure Injection System Surveillance, Revision 11 as recorded on VYOPF 4120.06.
b.
Review of RCIC overspeed testing data conducted on December 2, 1981, per OP 4121, Reactor Core Isolation Cooling System Surveillance, Revision 15 as recorded on VYOPF 4121.06.
Review of Plant Operations The following operations were observed or reviewed by the inspectors during the inspection period as described below:
a.
Reactor Startup from 1981 ~ Annual ~ Refueling ' Outage Reactor startup commenced at 7:45 P.M. on December 1,:1981 and
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the reactor was critical at 9:05 P.M.
At 9:18 P.M. on December 2 and 12:50 A.M. on December 3, 1981, turbine trips
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occurred on High Moisture Separator Level A and B.
Investiga-tion revealed an-improper high level switch line valve-lineup on A moisture separator.
The licensee experienced turbine generator bearing excessive
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vibration indications and performed a balance shot on the main turbine'on December 3 and 4, 1981.
On December 4,1981, the 'B' RHR loop was declared inopera-
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ble due to reported high chloride sample results (150 ppb) in-dicating service water in-leakage, The
'A' RHR loop was sampled and results were satisfactory and alternate testing per TS 3,5.C.
was commenced. During alternate testing of the core spray system per VYOP 4123, CS-11A valve was declared inoperable when its ACB tripped as the control switch was moved to the close position. A normal reactor shutdown commenced while evaluating CS-11A perfomance. The core spray system was~
' declared operable following resetting of CS-11A ACB, success-fully cycling the valve twice, and verifying a normal running current of CS-11.
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During reactor startup 'A' recirculation pump indicated
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excessive outboard seal leakage. On December 5, 1981, the reactor was shutdown to replace the 'A' RCP seal. A reactor startup commenced on December 7,1981, following completion of repairs and the Rx was cirtical at 2:45 A.M.
Power escala-tion was completed at 8:35 P.M. on December 11, 1981.
b.
Reactor Trip on High Flux Signal At 7:41 P.M. on December 26, 1981, control room indications
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recorded a aressure/ flux spike which resulted in a reactor scram on a ligh flux signal. During scram recovery, the turbine pressure regulators did not respond and the RCIC system was utilized in the full flow test mode to control reactor pressure and level. During preparations for shut-down cooling RHRSW pump 'A' was declared inoperable, all other system responses were nomal.
Investigation by the licensee indicated that the reactor system pressure spike was caused by turbine control system oscillations. Reactor restart commenced at 7:52 P.M. on December 27, 1981, with the reactor critical at 9:35 P.M.
Low power turbine control testing and adjustment continued during power escalation.
PCIOMR power escalation was complete at 7:30 P.M. on December 31, 1981.
11. Fire Protection USNRC letter, dated January 13, 1978, Amendment 43 to Facility Operating License added a license condition relating to the completion of facility modifications for fire protection. The issued Safety Evaluation to Amendment 43, section 3.1 listed plant modifications the licensee planned to make to improve the fire protection program as a result of both licensee and NRC staff evaluations. At the NRC's request, Vemont Yankee conducted a review of the status of implementation of the plant modifications.
In a letter, FVY 81-175 dated December 18, 1981, the
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licensee notified the NRC that a portion of the bem around and between the recirculation pump motor generator sets was not complete. This dis-crepancy was identified to the Resident Inspector on December 3.1981, and bem construction between the motor generator sets was completed on December 9, 1981. The inspector verified berm construction and had no further questions in this area.
12.
In-Office Review of Licensee Event Reports Thelicenseeeventreports(LERs)listedbelowwerereviewedintheNRC Resident / Regional Office. The reports were reviewed to detemine whether; the information provided was clear in the description of the event and identification of safety significance; the event cause was identified and corrective actions taken (or planned) were appropriate; the report satis-fled requirements with respect to information provided and timeliness of a
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submittal per NUREG 0161 and Technical Specification 6.7 criteria. Those reports annotated with an asterisk (*) concern events that required inspector followup action and inspector review / evaluation of the event is documented elsewhere, in this or other inspection reports,
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- LER 81-27 MSIV-80C failed to close upon receipt of a Group 1 isolation signal during a reactor scram.
Event date October 16, 1981, report date December 7, 1981.
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LER 81-29, during a two rod interlock functional test, the rod block associated with the one control rod withdrawal pennit circuit was found to be inoperable.
Event date October 8, 1981, report date November 17, 1981.
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LER 81-30, during replacement of RWCU piping, an inspection of valves V12-29A and B revealed cracks on internal surface of the valve bodies.
Event date November 4, 1981, report date December 4, 1981.
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- LER 81-31, during routine surveillance of Standby Liquid Control Relief Valves, the setpoint of relief SR-39-B was found to be 1540 psig.
Event date November 9, 1981, report date December 9, 1981.
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- LER 81-33, failure to follow plant procedure while welding a strongback to the reactor building roof hatch. Event date November 25, 1981, report date December 9, 1981.
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LER 81-34, Exceeding Surveillance Test Schedule for the Operating Cycle Test of the SBGT HEPA filters.
Event date November 21, 1981, report date December 18, 1981.
13. Management Meetings _
During the period of the inspection, licensee management was periodical.ly notified of the preliminary findings by the resident inspectors. A summary was also provided at the conclusion of the inspection and prior to report issuance.
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