IR 05000333/1981014
| ML20009G155 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 07/15/1981 |
| From: | Doerflein L, Kister H, Linville J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20009G150 | List: |
| References | |
| 50-333-81-14, NUDOCS 8108030381 | |
| Download: ML20009G155 (8) | |
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DCS NUMBERS
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50333-810428 U.S. NUCLEAR REGULATORY COMMISSION 50333-610429 0FFICE OF INSPECTION AND ENFORCEMENT 50333-810505 50333-810515 Region I 50333-810518 50333-810526 Report No.
81-14 Docket No.
50-333 C
License No.
DPR-59 Priority Category
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Licensee:
Power Authority of the State of New York
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P. O. Box 41 Lycoming, New York 13093 James A. FitzPatrick Nuclear Power Station Facility Name:
Inspection at:
Scriba, New York Inspection conducted:
June 1 30, 1981 HEW [ MM vfkp/
Inspectors:
'C. LinvilM, Resi c' Inspector daXefigned
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. T. Doerflef5, Resident Inspector ddte signed
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date si ned Approved by: [
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H'. B. Kist'er7 Chief, Reactor Projects late (signed Section 1C l
Inspection Summary:
l Inspection on June 1, 1981 to June 30,1981 (Report No. 50-333/81-14)
Areas Inspected:
Routine and reactive inspection during day and backshift hours by
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the Resident Inspectors (71 hours8.217593e-4 days <br />0.0197 hours <br />1.173942e-4 weeks <br />2.70155e-5 months <br />) of licensee action on previous irefection findings; the review of Licensee Event Reports; licensee action on IE Circulars; control room observations; plant tours; surveillance observations; maintenance observEtions; PORC meeting observation; licensee action on TMI Task Action Plan Items.
Results: Of nine areas inspected no items of noncompliance were observed.
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PDR ADOCA 05000333
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Region I Form 12 (Rev. April 77)
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DETAILS 1.
Persons Contacted
- R. Baker, Superintendent of Power N. Brosee, Maintenance Superintendent
- R. A. Burns, Assistant to Superintendent of Power V. Childs, Assistant to Resident Manager
- R. Converse, Operations Superintendent M. Cosgrove, Site Quality Assurance Engineer W. Fernandez, Technical Services Superintendent H. Kieth, Instrument and Control Superintendent E. Mulcahey, Radiological and Environmental Services Superintendent C. Orogvany, Reactor Analyst Supervisor R. Pasternak, Resident Manager D. E. Tall, Training Coordinator The inspectors also interviewed other licensee personnel during this inspection in luding Shift Supervisors, Administrative, Operators, Health Physics, Security, Instrument and Control, Maintenance and Contractor personnel.
- Denotes those present at an exit interview.
2.
Licensee Action On Previous Inspection Findinas (Closed) UNRESOLVED ITEM (333/78-08-02): The licensee failed to resolve the matter of the inoperable humidity elements and controllers in the
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Standby Gas Treatment System by July 1, 1978 as committed. As a result, l
surveillance tests required by Technical Specification 4.7.B.1.f were not performed. This item is discussed further in paragraph 9 of this report.
(Closed)
INSPECTOR FOLLOWUP ITEM (333/78-25-03):
The inspectors were unable to locate this item in inspection report 50-333/78-25.
However, the Plant Design Change Modification definition in WACP 10.1.6, Control of Modifications, Component Changes, and Safety and Environmental Impact Evaluation Reports, Revision C, dated June 2, 1981 appears to be adequate.
(Closed)
INSPECTOR FOLLOWUP ITEM (333/78-14-00); The inadequacy of the licensee's control of modifications was the subject of items of noncompliance in inspection report 50-333/80-21 and 50-333/81-07. As a result of these items of noncompliance the licensee has revised the procedure for control of modifications and is conducting extensive reviews of in progress modifications as well as increasing efforts to close out old modification packages.
3.
Review of Licensee Event Reports (LER's)
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The inspectors reviewed LER's to verify that the details of the events were clearly reported. The inspectors determined that reporting requirements hed been met, the report was adequate to assets the event, the cause
appeared accurate and was supported by detaiis, corrective actions appeared
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appropriate to correct the cause, the form was complete and generic applicabil.ity to other plants was not in question.
LER's 81-038*, 81-039*,81-040, 81-041*, 81-042*, 81-043* were reviewed.
- Report selected for onsite followup.
Information about followup on LER's81-041 and 81-043 was documented in inspection report 50-333/81-12.
LER 81-039 reported that failure of limit switch rotors for A containment spray line containment isolation valves made containment spray loop A inoperable. This item is unresolved pending the licensee's submittal of a followup report describing the cause of the failure (333/81-14-01).
No items of noncompliance were identified.
4.
Licensee Action On IE Circulars For the IE Circulars listed below, the inspectors verified that the Circulars were received by licensee management, that a resiew for applicability was performed and that appropriate corrective actions were taken. The following IE Circulars are closed:
IEC 81-04, The Role of Shift Technical Advisors and Importance of
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Reporting Operational Events IEC8$-06,PotentialDeficiencyAffectingCertainFoxboro10 tosh
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Milliampere Transmitters No items of noncompliance were identified.
5.
Control Room Observations a.
Using a plant specific checklist, the inspectors verified selected plant parameters and equipment availability to ensure compliance with the limiting conditions of operation of the plant technical specifications.
Items checked included:
Power distribution limits
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Availability and proper valve lineup of safety systems
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Availability and proper alignment of onsite and offsite emergency
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power sources Reactor control panel indications
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Primary Containment temperature and pressure
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Drywell to suppression chamber differential pressure
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Standby liquid control tank level and concentration
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Stack monitor recorder traces
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b.
The inspectors directly observed portions of the following plant operations to ensure adherence to approved procedures:
Routine power operations
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Issuance of RWP's and Work Request / Event / Deficiency Forms
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Surveillance Tests
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c.
Selected lit annunciators were discussed with control room operators to verify that the reasons for them were understood and corrective action, if required, was being taken.
d.
Shift Logs and Operating Records (1) Selected shift logs and operat'ng records were reviewed to:
Obtain information on plant problems and operations
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Detect changes and trends in performance
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Detect possible conflicts with Technical Specifications
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or regulatory requirements Determine that records are being maintained and reviewed
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as required Assess the effectiveness of the communications provided
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by the logs (2) The following logs and records were reviewed:
Shift Supervisor Log
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Nuclear Control Operator Log
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Night Orders Shift Turnover Check Sheet
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Protective Tag Record Log
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Jumper Log Daily Instrument Checks
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Daily Core Surveillance Checks
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Liquid Radwaste Discharge Log
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Gaseous and Particulate Sample Logs
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Weekly Chemistry Status Log STA Log
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No items of noncompliance were identified.
6.
Plant Tours a.
During the inspection period, the inspectors made observations and conducted tours of plant areas including the following:
Control Room
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Relay Room
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Reactor Building
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Turbine Building
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Diesel Generator Rooms
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Electric Bays
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Pumphouse - Screenwell
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Standby Gas Treatment Building
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Radwaste Building
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- Cable Tunnels
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Refuel Floor
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b.
During the plant tours the inspectors conducted a visual inspection of selected piping between centainment and the isolation valves for leakage or leakage paths. This included verification that manual
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valves were shut, capped and locked when required and that motor operated or air operated valves were not mechanically blocked. Other items verified during the plant tours included:
Proper completion and use of selected radiation work pemits
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Proper use of protective clothing and respirators
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Proper personnel monitoring practices
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Proper control of ignition sources and flamable material
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Equipment tag outs in confomance with controls for removal of
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equipment from service Nomal security practices are being followed
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Plant housekeeping and cleanliness practices are in confomance
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with approved licensee programs No items of noncompliance were identified.
7.
Surveillance Observations The inspectors observed portions of the surveillance procedures listed below to verify that the test instrumentation, if required, was properly
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calibrated, the redundant system or component, if applicable, was available for service, approved procedures were used, and the work was performed by qualified personnel.
F-ST-9D, EDG Inoperative Test / Loss of 115 KV Reserve Power / Loss of
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Station Battery, Revision 2, dated January 16, 1981, performed on June 3, 1981.
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F-ISP-49, RWCU Area High Temperature Instrument Functional Test /
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Calibration, Revision 7, dated March 1981, perfomed on June 15, 1981.
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F-ST-9B, EDG Full Load Test and ESW Pump Operabilite Revision 9,
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dated June 8, 1981, performed June 18, 1981.
F-ISP-3-1, Reactor low Low Water Level, Revision ll, dated May 12,
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1981, perfors:ed June 30, 1981.
F-ISP-70, Reactor High Pressure Pemissive (RPS) Instrument Functional
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Test / Calibration, Revision 6, dated June 9,1981, performed June 30, 1981.
No items of noncompliance were observed.
8.
Maintenance Observations The inspectors observed portions of the maintenance activity listed below to verify that the redundant train, if applicable, was available for service,
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approved procedures we. e used, and the work was performed by qualified personnel..
WR 71-10034, Preventive Maintenance on 115KV Breaker #10012, perfomed
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on June 2, 1981.
No items of noncompliance were identified.
9.
PORC Meeting Observation On June 2, 1981 the inspectors attended PORC meeting no.81-054. The inspectors verified that the Technical Specification membership and frequency requirements were met. The inspectors reviewed the qualifications of the members of the PORC to assure that they meet the requirements of ANSI 18.1 1972. The inspectors will review the minutes of the meeting when they are published to ensure that they accurately reflect the decisions and recomendations made by the PORC members.
During the PORC meeting, F-ISP-84, Standby M s Treatment System Calibration, Revision 2, was resubmitted for approval. A licensee representative stated that the calibration of the humidity controllers portion had been reinserted in the procedure since PORC had objected to its deletion in the previously submitted version. Upon further investigation, the inspectors determined that the calibration of the humidity controllers had not been performed since before March 16, 1978 because the humidity transmitters 01-125HT-22A and 01-125HT-22B were removed. The licensee reported this in LER 78-10 and counitted to resolve the matter by July 1,1978 according to IE Inspection Report 78-08. Modification F1-78-42 was initiated but never approved for implementation. The licensee did not consider this to be a safety issue because without the humidity controllers in service tha heaters which ensure humidity is less than 70 percent run continuously insi.;ad of turning off at 70 percent. Thus, the humidity controllers have been jumpered out of service since 1978 and it appears that little action has been taken since to restore l
the system to its original design as described in FSAR Section 5.3.3.4.
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addition, Technical Specification 4.7.B.1.f requires calibration of the Standby Gas Treatment System humidity elements and controllers once per
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operating cycle. The data from F-ISP-84 as perfomed on February 28, 1980 l
for 01-125HT-22A and 01-125HT-22B is blank and has a note which says to refer
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to the mod package. The licensee stated that a Technical Specification Change Request would be submitted to delete the requirement to calibrate the humidity elements and controllers. This item is unresolved pending submittal of the Technical Specification Change Request and completion of the modification (333/81-14-02).
10. Licensee Action On TMI Task Action Plan Items II.E.4.1.2, Dedicated Hydrogen Penetrations In a response dated April 28, 1981, the licensee requested an extension until June 1982 because of the long lead time required for material
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procurement. This item is open pending implementation of the modification and approv.a1 of the extension by NRR.
II.E.4.2.7, Containment Vent and Purge Isolation Valves Must Close On A High Radiation Signal In a response dated December 16, 1980, the licensee stated that the plant design provides for isolation of the containment purge valves on a secondary containment high radiation signal. The licensee requested that the NRC clarify the type of signal to be utilized to isolate the purge valves. This item remains open pending NRR's response to this request.
II.K.3.13.B, Separation of High Pressure Coolant Injection and Reactor Core Isolation Cooling System Initiation Levels In a response dated April 28, 1981, the licensee requested an extension until October 1982 because of the long lead time required for material procurement. This item is open pending implementation of the modification and approval of the extension by NRR.
II.K.3.15, Modify Break Detection Logic to Prevent Spurious Isolation of High Pressure Coolant Injection and Reactor Core Isolation Cooling The licensee's response to these requirements dated January 8, 1981 indicated that modification number F1-74-11 was completed in March 1975. This modification included the installation of hydraulic snubbers and wider range instruments to sense pipe breaks in the HPCI and RCIC steam lines. The
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licensee stated that operating history has demonstrated the adequacy of the modification to prevent inadvertant system isolation due to the pressure spike on system startup. The inspector reviewed the modification package (
to verify that this modification had been completed.
II.K.3.27, Provide Conton Reference Level For Vessel Level Instrumentation In a response dated January 8, 1981, the licensee stated that no modifications were necessary because current reactor vessel level instrumentation provides operators level information that will permit them to make timely and correct descisions regarding reactor water control requirements.
In a subsequent response dated April 10, 1981 the licensee reaffirmed this position but stated that if it is unacceptable to the NRC that a means would be provided
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whereby the zero points of all level instruments would be referenced to the
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top of the active fuel by using fixed markers external to the level indicators to show the correlation of presently used level indication to the common l
reference level. The inspector verified that the licensee has installed red dymo tape markers by all control room level instruments which indicate the
relationship between instrument 0 and the top of the active fuel. The i
acceptability of this modification must be determined by NRR.
III.D.3.4.2, Control Room Habitability Requirements In a response dated January 8, 1981, the licensee committed to submit an
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evaluation by January 30, 1981. To date no evaluation has 'oeen submitted.
Tne licensee stated that it has been delayed due to an analysis of toxic gas hazards by the licensee's architect engineer.
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,
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or deviations. The unresolved items identified during this inspection are discussed in paragraphs 3 and 9.
12.
Exit Interview At periodic intervals during the course of this inspection, meetings were held with senior facility management to discuss inspection scope and findings.
On June 30, 1981, the inspectors met with licensee representatives (denoted in paragraph 1) and summarized the scope and findings of the inspection as they are detailed in this report. During the meeting the unresolved items were discussed.
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