IR 05000245/1982002
| ML20041E562 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 02/19/1982 |
| From: | Elsasser T, Lipinski D, Shedlosky J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20041E557 | List: |
| References | |
| 50-245-82-02, 50-245-82-2, 50-336-82-04, 50-336-82-4, NUDOCS 8203110084 | |
| Download: ML20041E562 (11) | |
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U.S. NUCLEAR REGULATORY COMMISSION
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50-245/82-02 Report No. 50-336/82-01 50-24b Docket No. 50-336 DPR-21 License No. DPR-65 Priority Category C
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Licensee:
Northeast Nuclear Energy Company P.O. Box 270 Hartford, Connecticut 06101 Facility Name:
Millstone Nuclear Power Station, Units 1 & 2 Inspection at:
Waterford, Connecticut 06385 Inspection conducted: January 3, thru February 6, 1982 Inspectors:
42/h e/p/B2 ( T. Shedlosky,
, Resident Inspector
' date signed b
8fd832 nu U. R. Lipiftski, Resident Inspector date signed date signed Approved by:
/n/4 V
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T. C. E er, Chief Reactor Projects Section 1B,
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Division of Resident & Project Inspection Inspection Summary:
Inspections on January 3 - February 6,1982 (Combined Report Numbers 50-245/82-02 and 50-336/82-04.)
Unit 1 Areas Inspected: Routine inspections by two resident inspectors including Facility tours, and evaluation of plant operations, radiation protection, physical security, fire protection, plant operating records, maintenance and modifications, surveillance testing, instrument calibration, and formal reporting to the NRC.
The inspection involved 82 hours9.490741e-4 days <br />0.0228 hours <br />1.35582e-4 weeks <br />3.1201e-5 months <br /> of onsite, regular and backshift, inspection effort by two resident inspectors.
Results:
No violations were identified.
Unit 2 Areas Inspected:
Routine inspections by two resident inspectors including facility tours and evaluation of plant operations, radiation protection, physical security, fire protection, plant operating records, maintenance and modifications, surveillance testing, instrument calibration, and formal reporting to the NRC.
Region I Form 12 (Rev. April 77)
8203110084 820222 PDR ADOCK 05000245
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Inspection Summary:
(cont'd.)
The inspection involved 225 hours0.0026 days <br />0.0625 hours <br />3.720238e-4 weeks <br />8.56125e-5 months <br /> of onsite, regular and backshift, inspection effort by two resident inspectors.
Resul ts: No violations were identified.
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DCS IDENTIFICATION NOS.
NRC INSPECTION N0. 50-245/82-02 50-336/82-04 No.
Report Paragraph 50245-811124
50245-811203
50245-811208
50245-811215
50245-811116
50336-811206
50336-811226
50336-811207
50336-811209
50336-820122
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DETAILS 1.
Persons Contacted The below listed technical and supervisory level personnel were among those contacted:
A. Cheatham, Radiological Services Supervisor J. Crockett, Unit 3 Superintendent F. Dacimo, Quality Services Supervisor E. C. Farrell, Station Services Superintendent j
B. Granados, Health Physics Supervisor
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H. Haynes, Unit 2 Instrumentation and Control Supervisor R. J. Herbert, Unit 1 Superintendent
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-J. Kangley, Chemistry Supervisor
i J. Keenan, Unit 2 Engineering Supervisor J. J. Kelley, Unit 2 Superintendent E. J. Mroczka, Station Superintendent V. Papadopoli, Qual'ty Assurance Supervisor
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R. Place, Unit 2 Engineering Supervisor R. Palmieri, Unit 1 Engineering Supervisor W. Romberg, Unit 1 Operations Supervisor S. Scace, Unit 2. 0perations Supervisoa F. Teeple, Unit 1 Instrumentation and Control Supervisor
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W. Varney, Unit 1 Maintenance Supervisor P. Weekley, Security Supervisor 2.
Status of Unresolved and Open Items l
New items:
None Old items:
l Unit 1 245/81-16-01 (open) Training for plant operators in process computer topics. Training lesson outlines have'been prepared by the plant nuclear engineering staff. Training is expected to begin on February 11. The resident inspectors have reviewed the lesson outline. This item will remain open until completion of this training series.
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245/81-14-01 (closed) The gauge and instrument calibration program has been expanded to include instrumentation required for Inservice Inspection (ISI) of the fuel pool cooling system.
245/81-11-06 (closed) Battery charging procedures have been revised to reduce the probability of reaching the high voltage protection features of the ATWS/ARI power supplies. Modifications to the power supplies have reduced the plant impact of inadvertent actuation of the high voltage protection feature of these power supplies. This item is resolved.
245/81-11-08 (closed) The distinction between system evolutions falling within the scope of operations and those falling within the' scope of main-tenance has been clarified.
This item is resolved.
245/81-11-09 (closed). The limited scope of evolutions which may be accom-plished while using a " blanket RWP" has been reviewed with plant operating personnel. This item is resolved.
3.
Review of Plant Operation - Plant Inspections (Units 1 and 2)
The inspectors reviewed plant operations through direct inspection and observation of Units 1 and 2 throughout the reporting period.
Unit 1 operated at full power through the inspection period with the exception of minor power reductions for surveillance testing.
Unit 2 continues in a refueling and maintenance outage status.
Refueling and subsequent core verification has been completed. Other outage work is continuing.
It is estimated that the outage will be completed and the unit returned to service by February 26, 1982, a.
Instrumentation Control room process instruments were observed for correlation between channels and for conformance with Technical Specification requirements.
tio unacceptable conditions were identified.
b.
Annunciator Alarms The inspector observed various alarm conditions which had been received and acknowledged.
These conditions were discussed with shift personnel who were knowledgeable of the alarms and actions required. During plant inspections, the inspector observed the condition of ~ equipment associated with various alarms, flo unacceptable conditions were identified.
c.
Shift Manning The operating shifts were observed to be staffed to meet the operating requirements of Technical Specifications, Section 6, both to the number and type of licenses.
Control room and shift manning was observed to be in conformance with Technical Specifications and site administrative procedure.
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d.
Radiation Protection Controls Radiation protection control areas were inspected. Radiation Work Permits in use were reviewed and compliance with those documents as to protective clothing and required nonitoring instruments was inspected.
Proper posting of radiation and high radiation areas was reviewed in addition to verifying requirements for wearing of appropriate personal monitoring devices.
There were no unacceptable conditions identified.
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Plant Housekeeping Controls Storage of material and components was observed with respect to prevention of fire and safety hazards.
Plant housekeeping was evaluated with respect to controlling the spread of surface and airborne con-tamination. There were no unacceptable conditions identified.
f.
Fire Protection / Prevention The inspector examined the condition of selected pieces of fire fighting equipment. Combustible materials were being controlled and were not found near vital areas. Selected cable penetrations were examined and i
fire barriers were found intact. Cable trays were clear of debris.
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There were no unacceptable conditions identified.
g.
Control of Equipment
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During plant inspections, selected equipment under safety tag control was examined.
Equipment conditions were consistent with information in plant control logs.
h.
Instrument Channels
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Instrument channel checks recorded on routine logs were reviewed.
An independent comparison was made of selected instruments. No unacceptable conditions were identified, i.
Equipment Lineups The inspector examined the breaker position on switchgear and motor control centers in accessible portionc of the plant. Equipment conditions, including valve lineups, were reviewed for conformance with Technical Specifications and operating requirements. No unacceptable
conditions were identified.
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4.
Review of Plant Operations - Logs and Records - (Units 1 and 2)
During the inspection period, the inspector reviewed operating logs and records covering the inspection time period against Technical Specifications and Administrative Procedure Requirements.
Included in the review were:
Shift Supervisor's Log
- daily during control room
surveillance Plant Incident Reports
- 1/3/82 through 2/6/82 i
Jumper and Lifted Leads Log
- all active entries Maintenance Requests and Job Orders
- all active entries Construction Work Pennits
- all active entries Safety Tag Log
- all active entries Plant Recorder Traces
- daily during control room surveillance
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Plant Process Computer Printed daily during control room
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Output surveillance Night Orders
- daily during control room surveillance The logs and records were reviewed to verify that entries are properly made; entries involving abnormal conditions provide sufficient detail to comunicate equipment status, deficiencies, corrective action restoration and testing; records are being reviewed by management; operating orders do not conflict with the Technical Specifications; logs and incident reports detail no violations-of Technical Specification or reporting requirements; and logs and records are maintained in accordance with Technical Specification and Administrative Control Procedure requirements.
There were no unacceptable conditions identified.
5.
Licensee Event Reports (LERs)
The inspector reviewed the following LERs to verify that the details of the event were clearly reported including the accuracy of the
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description of cause and adequacy of corrective action. The inspector determined whether further information was required, and whether generic implications were involved. The inspector also verified that the reporting requirements of Technical Specifications and Station Administrative and Operating Procedures had been met, that appropriate corrective action had been taken, that the event was reviewed by the Plant Operations Review J
j Comittee, and that the continued operation of the facility was conducted
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within the Technical Specification limits.
Unit 1 81-39 Failure of one of four R.P.S. High Main Steam Flow sub-channel trip relays.
81-40 Inoperable primary containment isolation valve 1-CU-3 due to motor operator failure.
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Unit 1 (cont'd)
81-41 Failure of Emergency Gas Turbine Generator during surveillance testing. The unit output breaker tripped after the unit had been running for approximately 45 minutes. The cause of the trip is attributed to engine governor instability caused by control oil contamination.
81-42 Inoperable primary containment isolation valve 1-SD-1 due to mechanical binding of valve internals.
Information letter Setpoint drift of two dated December 21, 1981 steam tunnel ventilation radiation monitors.
Unit 2 81-40 Inoperable power operated relief valve 2-RC-402 due to failure of the motor 0,7erator of its block valve 2-RC-403. This has been identified as a consequence of leakage reported earlier in LER 81-33.
81-41 Unanticipated degradation of steam generator U-tubes identified during inservice testing.
Evaluation of causes continues.
Present course of action will result in plugging 427 tubes in No. I steam generator and 284 tubes in No. 2 steam generator. These numbers are estimated as of February 1, 1982.
81-42 Failure of containment nitrogen purge line isolation valve 2-EB-92 to pass Type "C" Local Leak Rate Test.
81-43 Loss of reactor Shutdown Cooling system (SDC) due to improper control of r'itchyard breaker testing.
82-1 Inadvertent discharge of radioactive liquid waste without continuous radiation monitoring recorder in service. The continuous radiation monitor and its alarm remained in service throughout the discharge.
6.
Quality Assurance Program Topical Report Review The inspectors revieved a draft of revision 4 to the Northeast Utilities Quality Assurance Program Topical Report (NUQAP). The draft was reviewed against the presently approved NVQAP revision 3A and against requirements of respective unit Technical Specifications. Briefly summarized, the changes include the following:
--- Changes in the program to reflect a corporate office reorganization.
Broadened scope of an annual internal " Management Quality Assurance
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--- Clarification of audit follow-up responsibilitie.
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Quality Assurance Program Topical Report Review (cont'd)
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Revision of the qualifications required of the Northeast Utilities
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Service Company Quality Assurance manager.
Expansion of the Nuclear Review Board (NRB) from 7 to 11 members
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with the elimination of " alternate members." A " quorum," however, remains defined as four or more members, no more than a minority of which may be from Nuclear Engineering and Operations organization.
This definition is consistent with Technical Specifications of Units 1 and 2.
The licensee has identified this as an exception to ANSI N18.7 American National Standard for Adninistrative Controls of Nuclear Power Plants.
7.
Plant Maintenance and Modifications During the inspection period, the inspector frequently observed various maintenance and problem investigation activities. The inspector reviewed these activities to verify:
compliance with regulatory requirements, including those stated in the Technical Specifications; compliance with applicable codes and standards; required QA/QC involvement; proper use of safety tags; proper equipment alignment and use of junpers; personnel qualifi-cations; radiological controls for worker protection; fire. protection; retest requirements; and reportability as required by Technical Specifications.
In a similar manner, the implementation of design changes and modifications were reviewed, including the associated 10.CFR 50.59 safety evaluation.
Compliance with requirements to update procedures and drawings were verified and post modification acceptance testing was evaluated. The following activities were included in this review:
Unit 1 Installation of Post Accident Sampling System.
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l-Reactor Building Closed Cooling Water heat exchanger cleaning.
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"B" Emergency Service Water Pump removal and refurbishment.
Unit 2
--- Turbine Driven Auxiliary Feed Punp overhaul.
In-Core Instrument (ICI) replacement and tube cleaning.
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--- Steam Generator U-tube Eddy Current Testing (ECT).
--- Steam Generator U-tube removal.
Steam Generator U-tube plugging.
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--- Reactor Building Closed Cooling Water heat exchanger ECT.
--- Fuel and Control Element Assembly movements (sample).
Reactor vessel internal component reassembly (sample).
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--- Reactor vessel closure stud ECT, Containment High Range Radiation Monitor installation.
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--- Local Leak Rate Testing (LLRT) on No.1 and No. 2 Steam Generatcr blowdown penetrations.
Concrol board modifications.
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8.
Inspector Witnessing of Surveillance Tests The inspector witnessed the performance of surveillance testing of selected components to verify that:
the surveillance test procedure was properly approved and in use; test instrumentation required by the procedure was calibrated and in use; technical specifications were satisfied prior to removal of the system from service; the test was performed by qualified personnel; the procedure was adequately detailed to assure performance of a satisfactory surveillance; and test results satisfied the procedural acceptance criteria or were properly dispositioned. The inspector witnessed the performance of:
Unit 1
--- " Core Spray System Operability Test" per SP621.10, Revision 3,on January 14.
" Core Spray Pump Vibration and Hydraulic Test" per SP1060.2, Revision 1,
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on January it.
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"A.P.R.
L.P. Core Cooling Pump Interlock Functional and Calibration Test" per SP413, Revision 1, on January 21.
Unit 2
--- " Reactor Trip Switchgear Undervoltage Trip Device Test" per PT21429, Revision 0, on January 15.
" Containment High Range Monitor RIT 8240 and 8242 Calibration" per
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SP2410E, Revision 0, on January 26.
--- " Boric Acid Pump
'B' Operational Readiness Test" per EN 21126-1, Revision 2, on January 26.
--- " Borated Water Source and Flow Verification" per OP2601A, Revision 6, on January 26.
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"R.C.S. Temperature Instrument Calibration" per IC2418B, Revision 1, on January 27.
--- " Engineered Safety Features (ESF) Integrated Test" per SP2613C, Revision 6, on January 2,
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" Reactor Protective System Response Time Testing" per SP2401N,
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Revision 4,on January 29. Testing was conducted on Channel A during the cycle 5 refueling outage.
" Safety Injection and Containment Spray Valve Operational
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Readiness Test" per EN21136, Revision 2 with Change 2,on February 1.
Testing was conducted on system check valves using section 7.12 of the procedure.
8.
Review of Periodic and Special Reports Upon receipt, periodic and special reports submitted by the licensee pursuant to Technical Specification 6.9.1 and 6.9.2 and Environmental Technical Specification 5.6.1 were reviewed by the inspector. This review included the following considerations:
the report includes the information required to be reported by NRC requirements; tast results and/or supporting information are consistent with design predictions and performance specifica-tions; planned corrective action is adequate for resolution of identified problems; determination of whether any information in the report should be classified as an abnormal occurrence; and the validity of reported information.
Within the scope of the above, the following periodic reports were reviewed by the inspector:
--- Monthly Operating Report Unit 1 and 2, December 1981 9.
Review of Radioactive Material Shipments - (Unit 1)
The inspector reviewed the activities concerning the shipment of radio-active waste to the Barnwell, S.C., burial site. Those activities included receipt inspections of the shipping cask and liner, solidification of material, radiation surveys and the completion of administrative and quality control requirements prior to shipment. These inspections concerned:
--- Dewatered Purification Media January 26, 1982 L.S.A. Drums January 26-27, 1982
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10.
Exit Interview
At periodic intervals during the course of the inspection, meetings were held with senior facility management to discuss the inspection scope and
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