IR 05000333/1979004
| ML19250C269 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 07/19/1979 |
| From: | Graham P, Mccabe E, Stetka T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19250C249 | List: |
| References | |
| 50-333-79-04, 50-333-79-4, NUDOCS 7911230126 | |
| Download: ML19250C269 (11) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No. 50-333/79 04 Docket No. 50-333 License No. DPR-59 Priority:
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Category: C Licensee:
Power Authority of the State of New York 10 Columbus Circle New York, New York 10019 Facility Name: James A. Fitzpatrick Nuclear Power Plant Inspection at: Scriba, New York Inspection cond ted. A il-27
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Inspectors:
Id F. St a,
a o inspe or dat si ned p. a FA 7/9 P
. GP. am Rea to I pe tor dat 'si gfied 7/9/7 Approved by:
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E. 'C. McCabd, Reactor Projects date signed Section No. 2, R0 & NS Branch Inspection Sumary:
Inspection on April 24-27, 1979 (Report No. 50-333/79-04)
Areas Inspected: Routine, unannounced inspection of plant operations, onsite review committee, organization and administration, post refuel-ing start-up testing, Licensee Event Reports (LER's),IE Bulletin /
Circular responses, and licensee action on previous inspection findings.
This report also documents in-office review of LER's and Annual Reports.
The inspection involved 56 hours6.481481e-4 days <br />0.0156 hours <br />9.259259e-5 weeks <br />2.1308e-5 months <br /> onsite by two regional based inspectors.
Results: Of the six areas inspected, no items of noncompliance were identified in five areas; one item of noncompliance was identified in one area (Deficiency - failure to E30sfy onsite review comittee quorum requirements).
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DETAILS 1.
Persons Contacted The following technical and supervisory level personnel were contacted:
R. Baker, Maintenance Superintendent R. Burns, Radiation and Environmental Services Superintendent
- R. Converse, Assistant Operations Superintendent
- M. Cosgrove, QA Site Engineer
- W. Fernandez, Assistant to Maintenance Superintendent P. Frawley, Personnel Officer H. Keith, Assistant to I & C Superintendent
- J. Leonard, Resident Manager R. Liseno, Assistant Plant Engineer (Systems)
- L. Milesi, Security and Safety Supervisor C. Orogvany, Reactor Analyst Supervisor
- R. Pasternack, Superintendent of Power Other personnel contacted included office, operations, engineering, maintenance, and health physics personnel.
- Present at the exit interview.
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-3-2.
Licensee Actions on Previous Inspection Items (Closed) Noncompliances (333/78-05-06; 333/78-12-02): The licensee has completed installation of the spring closures on the high radiation area doors. A review of completed work requests and observations of selected installations during the plant tour were made by the inspector.
(Closed) Noncompliance (333/78-24-01):
The licensee corrected the noncompliant condition the day it was identified by the inspector.
During this inspection, the inspector observed the licensee's control of contaminated areas during the plant tours and the controls appear to be adequate.
(Closed) Unresolved Item (333/78-08-01):
The subject relays were modified in accordance with Modification FI-78-22 which was com-pleted on December 8, 1978. This modification added a resistor in series with the relay coils to prevent excessive voltage damage.
The inspector reviewed the modification package and had no further questions on this item.
(Closed) Unresolved Item (333/79-01-04):
The control rod notch reactivity vs. core exposure curve was available on sita and was reviewed by the inspector.
(Closed) Unresolved Item (333/79-01-01):
The licensee has reviewed the log entries in the Jumper / Block Log and has properly validated the outstanding entries and closed all other entries.
(Closed) Noncompliance (333/79-01-03):
The inspector reviewed the startup test program checklist and data from tests conducted sub-sequent to inspection 79-01 to determine if the licensee was adhering to his procedures and properly completing data sheets.
No inadcquacies were identified.
(Closed) Noncompliance (333/77-22-01):
Procedure 7.3.9 was revised as stated in the licensee's response letter.
No further inadequacies were identified.
(Closed) Noncompliance (333/77-22-02):
Review of the Item Control Area (ICA) transfer forms during the Fall 1978 refueling outage (IE Inspection Report 50-333/78-24) indicated that the forms are being properly completed.
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-4-(Closed) Unresolved Item (333/78-12-01):
Procedure F-ST-40D has been revised to include a test of the EDG Alarm Panel alarms.
This test includes a check of the EDG status lights.
3.
Review of Plant Operations The inspector reviewed selected facility operations logs and toured areas of the facility to determine that operations are in accordance with the Technical Specifications.
The facility is presently engaged in an extended outage to re-evaluate seismic stresses in safety-related systecs, and therefore, the review of plant operations included cold shutdown ~ operations.
a.
Shift Logs and Operating Records The inspector reviewed the following records:
(1) Operations Department Night Orders for the period March 1,1979 to April 25, 1979.
(2) Station Shift Supervisor's Log for the period February 8,1979 to April 18, 1979.
(3) Jumper / Block Log for all outstanding entries.
(4) Protective Tagging Log for all outstanding entries.
(5) Control Room Operator's Log for the period February 27, 1979 to March 30, 1979.
The review consisted of verifying adequate management review, correct identification of problem areas, completeness, and determination that conditions contrary to the Technical Speci-fications did not exist.
This review combined with panel observations in the control room and observations of various paranieters throughout the facility during the plant tour verified that plant conditions conformed to the Technical Specification requirements for the shutdown mode of operation.
During the inspection, the inspector noted an inconsistency between the Technical Specification calibration frequency for the Rod Block Monitor Upscale and Downscale channels, Table 4.2-3, and the applicable notes for the Table (Note 3).
A licensee representative acknowledged the inconsistency and 1306 172
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-5-stated that it would be corrected with the next Technical Specification change.
This item is unresolved (333/79-05-01).
b.
Tour of Accessible Areas Facility tours were conducted of the following areas; All levels of the reactor building;
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Turbine building;
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Control room;
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Diesel generator room;
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Relay room;
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East and West Crescent Rooms; and
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Pump house screenwell.
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Due to the facility's outage status, emphasis was placed on radiation area controls, fire prevention controls and plant housekeeping conditions.
The tours identified the following:
(1)
Radiation areas were observed to verify that radiation control zones were properly established and identifed and that radiation controls for personnel exposure were effective.
These observations included review of step-off pad conditions, disposal of anti-contamination clothing and area posting.
No adverse conditions were identifed.
(2)
Plant housekeeping was observed to evaluate the licensee's effectiveness in this area with respect to prevention of safety and fire hazards.
The inspectors noted that the Crescent Rooms and the Refueling Floor were areas that require cleanup due to work in progress.
These areas will be reviewed during subsequent inspection.
(3) Shift staffing was observed to verify that the required number of licensed and unlicensed personnel were available on site consistent with the plant operating mode.
No discrepancies were identified.
4.
Review of Plant Operating Review Committee (PORC)
The inspector reviewed the activities of the licensee's onsite review committee, PORC, to assure compliance with Technical Specification requirements.
The following items were reviewed by the inspector:
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-6-Administrative Procedure 1.2, Plant Operations Review Committee,
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Revision 2, dated May 19, 1977; PORC Meeting minutes for the period of March 10, 1978 to
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March 15,1979; and Alternate Member appointing letters.
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Review of PORC Meeting 78-47, held on August 9, 1978, indicated that the meeting membership, two reguler members and four alternate members, did not constitute a quorum as specified in Technical Specification 6.5.1.
This failure to meet a quorum constitutes a deficiency level item of noncompliance (333/79-05-02).
5.
Organization and Administration The inspectors reviewed the licensees onsite organization and administration and verified the following:
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Changes in organizational structure and assignments have been reported as required by the Technical Specifications (TS);
Onsite organizational structure is as described in the TS;
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Persons assigned to new or different positions satisfy the
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qualification requirements of ANSI N18.1-1971; and,
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The authorities and responsibilities of positions a?fected by organizational structure changes are as delineated in the TS and applicable standards.
This review included administrative procedure.l.1, Composition and Responsibility of Plant Organization, Rev. O.
The inspectors noted that the following positions had personnel changes since the last inspection of this area:
Reactor Analyst;
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Security and Safety Superintendent;
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Instrumentation and Control Superintendent; and
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Four Auxiliary Operators.
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The inspectors verified by review of personnel records that the newly assigned personnel met the requinnents of the TS and ANSI N18.7.
No inadequacies were identified.
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-7-6.
Completion of the Startup Testing Program The licensee completed testing at 100% of rated power on February 1979. The inspector reviewed the results of this testing in the following areas:
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Core Thermal Power;
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Core Performance; Core Flow Evaluation;
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Process Computer Data; and
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Reactivity Anomalies Results.
The inspector verified that all data was complete and recorded as required and that the sign-off checklist of procedure 7.1.17, Refuel Startup Program, documented this completion.
No items of noncompliance were identified.
7.
Review of Licensee Event Reports a.
The inspector reviewed Licensee Event Reports (LERs) to verify that:
The reports accurately describe the events;
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The safety significance is as reported; The report is accurate as to cause;
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The report satisfies requirements with respect to
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infonnation provided and timing of submittal; Corrective action is appropriate;
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Action has been taken; and The event was reviewed and evaluated by the Plant
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Operations Review Committee (PORC).
LERs78-111, 79-01, 79-07, 79-08, 79-13, and 79-17 were reviewed.
This review identified the following items.
b.
LER 78-111 reported the occurrence of a high drywell pressure condition due to a failure of personnel to properly return valves to normal and the failure of the B RHR loop keep full system due to check valve sticking. The inspector reviewed operators logs, the applicable Occurrence Report, and the completed sign-off sheets for F.0P-65, Startup and Shutdown Procedure, to determine the licensee's actions during this event.
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-8-This review, and discussions with licensee representatives, indicate certain procedural inadequacies related to returning systems to normal.
The licensee will revise the Hot Startup Checkoff to be more specific with system return to normal requirements.
The revision will be completed by 7/1/79.
This item is unresolved (333/79-05-03).
c.
LER 79-13 reported the missing of surveillance on the reactor pressure instrumentation due to the implementation of a new surveillance procedure F-ST-400, Daily Instrument Surveillance.
During the inspector's review of this occurrence, it was determined that the file copy of the procedures was incomplete in that the procedure did not identify the revision number nor contain the items specified in Administrative Procedure 2.4.
The licensee representative stated that the procedure problems would be resolved by May 4.
This item is unresolved (333/79-05-04).
d.
LER 79-17 reported a valve failure in Sundby %s Treatment (SBGT) System A.
The date of this ever.t was recorded as March 2, 1979, whereas the actual date was March 20, 1979.
The licensee will submit a revised LER no correct the error.
This item is unresolved (333/79-05-05).
8.
Closecut of IE Bulletins and Circulars a.
Site documents related to the following IE Bulletins were reviewed to verify the licensee's responses were timely, accurate and adequate.
(1)
IEB 78-05, Malfunctioning of Circuit Breaker Auxiliary Control Mechanism - General Electric Model CR105X.
As previously discussed in NRC Inspection Report 78-24, the licensee was modifying the affected relays and adding locking compound to the plunger ann screws.
This work has been completed.
(2)
IEB 78-14, Deterioration of BUNA-N Components in Asco Solenoids.
The licensee has replaced two-thirds of the BUNA-N diaphrams and will replace the remaining one-third during the 1980 refuel outage.
The BUNA-N armature parts will be replaced during this current outage as time permits.
Those armature parts not replaced during this outage will be replaced during the 1980 refueling outage.
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-9-This schedule will assume that all BUNA-N parts are replaced within the seven year life expectancy cycle.
The licensee will add the replacement scheduling for the BUNA-N parts to their computer scheduling system.
The completion of the BUNA-N component replccement and addition of these components to the computer scheduling system will be reviewed during a subsequent inspection.
This item is unresolved (333/79-05-06).
(3)
_I_EB 79-01, Environmental Qualification of Class lE Equipment.
The inspector reviewed correspondence relating to this issue and discussed the replacement of Stem Mounted Limit Switches (SMLS) as~ identified in NRC Inspection Report 78-24.
The licensee will replace the SMLS used for valve position indication (VPI) and the main steam isolation valves (MSIV) with environmentally qualified SMLS's.
The parts for this replacement are on order and should be available by May 15.
The licensee will also investigate the use of SMLS's for VPI on two reactor water sample valves (02 A0V 39&40) to determine if these switches are unqualified.
At the conclusion of these replacements and investigation, the licensee will submit a revised Bulletin response.
This item is unresolved (333/79-05-07) pending replacement of MSIV SMLS's and completion of the investigation of the reactor water sample valve VPI SMLS's.
(4)
IEB 79-08, Events Relevant To Boiling Water Power Reactors Identified During Three Mile Island Incident The licensee's response to this bulletin was partially revised during this inspection. A detailed inspection of this bulletin's response and other items pertinent to the TMI incident will be reviewed during a subsequent inspection.
The licensee determined in their response to question 2 regarding containment isolation and initiation design IP6 177
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i-10-that a change to the Technical Specifications (TS) is required to properly identify the grouping of drywell penetrations. This item is unresolved (333/79-05-08)
pending review of this submittal.
The inspector's review of the response to question 5 identified that the licensee's operating procedures for Core Spray (CS), Low Pressure Coolant Injection (LPCI),
and Reactor Core Isolation Cooling (RCIC), do not caution operators to not override these systems unless continual operation of these systems will result in unsafe plant conditions. The licensee acknowledged the inspector's coments and will revise the procedures for CS, RCIC and LPCI to include these precautions.
These revisions will be completed by May 31, 1979.
This item is unresolved (333/79-05-09).
b.
The inspector reviewed the licensee's action with respect to the following Circulars to determine if the licensee had received them and had taken appropriate action.
(1)
IFC 77-32, Dropped Fuel Assemblies at BWR Facilities.
The licensee has completed all pertinent recommended actions identified in the circular.
The inspector has no further questions on this item.
(2)
IFC 78-02, Proper Lubricating Oil for Terry Turbines.
The licensee completed the oil changeout in the RCIC turbine during the Fall 1978 outage.
The inspector had no further questions on this item.
9.
NRC In Office Review a.
NRC:RI in office review of the following LERs has been completed with no unacceptable conditions identified:
78-109 79-09 79-18 79-02 79-10 79-19 79-03 79-11 79-04 79-12 79-05 79-15 79-06 79-16 1306 178
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NRC:RI in office review of Monthly Operating Reports for the months of January, February and March,1979 has been completed with no unacceptable conditions identified.
10. Unresolved Items Unresolved items are those items for which further information is required to determine whether they are acceptable or items of non-compliance. Unresolved items are contained in Paragraphs 3.a.
7.b, 7.c, 7.d, 8.a(2), (3), and (4) of this report.
11.
Exit Interview The inspector met with licensee representatives (denoted in Paragraph 1) at the conclusion of the inspection on April 27, 1979 and summarized the scope and findings of the inspection as they are detailed in this report.
During this meeting, the unresolved items and item of noncompliance were identified.
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