IR 05000333/1980004
| ML19318B272 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 05/05/1980 |
| From: | Baunack W, Kister H, Stetka T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19318B270 | List: |
| References | |
| 50-333-80-04, 50-333-80-4, IEB-79-01B, IEB-79-1B, NUDOCS 8006250190 | |
| Download: ML19318B272 (8) | |
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GV U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No.
80-04 Docket No.
50-333 License No. DPR-59 Priority
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Category c
Licensee:
Power Authority of the State of New Yorg 10 Columbus Circle New York, New York 10019 Facility Name:
James A. FitzPatrick Nuclear Power Plant Inspection at:
Scriba, New York
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Inspection conducted:
March 31-April 4',
1980 SE N
Inspectors:
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dat( signed T. F. Stetk, Reactor In ector h), k.
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$O W. H. Baunack, Reactor Inspector date signed f)). f\\
W YO J. C. Linville, Resident Inspector (Trainee)
'date signed date signed Approved by:
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8D H. B. KistAChief, Reactor date signed Projects Section No. 4, RO&NS Branch Inspection Summary:
Inspection on March 31-April 4, 1980 (Report No. 50-333/80-04)
Areas Inspected:
Routine, unannounced inspection of plant operations as part of a turnover of NRC Principle / Resident Inspectors, licensee progress on pipe hanger installations and modifications and licensee action on previous inspection items. This inspection also included an independent review of the instrumentation required to be vivironmentally qualified in accordance with IE Bulletin 79-01B. The inspection involved 91.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> on-l site by two region-based inspectors and one resident inspector trainee and i
10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> or.-site by one Reactor Projects Section Chief.
l Results:
No items of noncompliance were idencified.
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Region I Form 12 (Rev. April. 77) 8 0 062 5'O f'g l
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DETAILS 1.
Persons Contacted N. Brosee, Mechanical Engineer (Maintenance)
- R. Burns, Radiation & Environmental Services Superintendent
- V. Childs, Assistant to the Resident Manager
- R. Converse, Operations Superintendent W. Fernandez, Assistant to Maintenance Superintendent J. Flaherty, Assistant to I&C Superintendent
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B. Gorman, Environmental Supervisor L. Johnston, Plant Engineer (Civil)
H. Keith, I&C Superintendent B. Mays, Water Systems Supervisor L. Milesi, Security / Safety Supervisor C. Orogvany, Reactor Analyst Supervisor
- R. Pasternack, Resident Manager P. Smalley, Radiation & Environmental Services Senior Technician D. Tall, Training Coordinator
- Denotes those present at the Exit Interview.
2.
Licensee Action on Previous Inspection Items (Closed)Noncampliance(333/79-04-02): The licensee provided a Supplementary Response on October 12. 1979 to address the actions to be taken to prevent recurrence. This response stated the licensee's position that this event was an isolated case.
PORC quorum require-ments will be reviewed during the next inspection of on-site review committee activities.
(0 pen) Unresolved Item (333/79-04-01):
The licensee submitted and received approval for TS Amendment No. 48 that should have resolved this item, but due to an administrative error, this issue has not been corrected. A new TS amendment request has been issued to resolve this issue.
(Closed)
Followup Item (333/77-16-03):
The licensee has developed P.M. Task Sheets that identify the fuel handling equipment to be checked either prior to use or on a yearly basis.
(Closed) Unresolved Item (333/78-14-03):
Quality Control Inspection Report F78-167, the General Electric outage report, section 7, and Target Rock vendor report were reviewed to verify installation of modifications FI-77-55.
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(0 pen) Unresolved Item (333/79-09-05):
All accessible instrument and safety related plant valve labeling has been completed. The necessary balance of plant valves has also been labeled and this labeling will be verified when the next valve lineup is conducted. Thirty-four of the safety related operations valves and thirty-four of the instrument valves that affect safety systems and are inaccessible during operation remain to be labeled. This labeling will be completed during the May 1980 refuel outage.
(Closed) Unresolved Item (333/79-17-01):
Review of the Control Room Operator's Log and Station Shift Supervisor's Log on subsequent inspections indicate log keeping is improved with respect to accuracy and consistency.
(Closed) Unresolved Item (333/79-16-06):
The licensee issued LER 79-064 on October 3,1979 describing this event as logged in the plant log books and reported in OR 79-135.
This event is a licensee identified iten. and all corrective action has been completed.
(Closed) Noncompliance (333/7916-05):
The licensee has revised Procedure 10.1.3, Placement of Jumpers / Blocks on Lifted Leads, revision 2 dated December 21, 1979, to provide an improved accounting system for jumpers, lifted leads and blocks.
Review of the Jumper and Lifted Lead Log during IE inspection 80-02 and this inspection indicates that the new log keeping system appears to be effective.
In additier.. during inspection 80-02, an independent check of. selected jumpers and lifted leads by the inspector verified the effectiveness of the licensee's program.
(Closed) Unresolved Item (333/79-17-02):
Extensive investigation of the APRM thermal power trip circuits by the instrumentation and control personnel indicate that the trip light actuation has no effect on reactor protection system operation.
Discussion with both I&C and operations personnel confirm these investigation findings and this item is considered to be resolved.
(Closed) Noncompliance (333/79-14-01):
The licensee has written and issued procedure F-ST-40H, Instrument Valve and Instrument Root Valve Line-up, Ravision 0, dated September 18, 1979 to assure control and identification of the instrument root valves. This procedure and the completed valve lineups performed on September 3, 12, and 13, 1979 were reviewed and no inadequacies were identified.
(Closed) Unresolved Item (333/79-17-03):
Checks made during subsequent inspections of the licensee's security force response to vital area doors that fail to close indicate guard response is adequate.
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(Closed) Unresolver' Item (333/78-14-04):
Plant Standing Order No. 12, Certification of Spare Parts, revision 0 dated August 8,1978 ms issued to incorporate the provisions established in memorandu.a 'AF-QF-78-18. The inspector reviewed this procedure and verified that action on this item is complete.
(Closed) Unresolved Item (333/79-02-09):
Review of reorder traces for the reactor vessel upper and lower regions and recirculation loop A and B temperatures indicate that the TS limit was not exceeded.
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(Closed) Unresolved Items (333/79-17-06 and 333/80-02-02):
F-390-33 has been revised as revision 1 to include the additional items identified during procedure review.
(Closed) Noncompliances (333/78-17-03 and 333/78-17-06):
These items were previously identified by the licensee prior ta the inspection findings and are therefore considered to be licensee identified items.
Corrective actions to prevent recurrence have been completed and these issues are considered resolved.
(Closed) Unresolved Item (333/80-02-03):
The licensee completed retraining of the shift assigned operators on March 17. The inspector interviewed one of the operators on the shift on April 2 to determine the effectiveness of thi: retraining and was satisfied with the results.
(Closed) Noncompliance (333/79-14-02):
Review of the status of locked valves during plant tours and notes to operators documen'ed in the t
Night Orders of November 27, 1979 verified completion of the corrective actions stated in the November 27, 1979 response letter. In addition, the licensee has issued a temporary change to procedure F-ST-40G that requires operators to physically grasp and shake the locking device to verify it is properly installed on a valve.
(Closed)UnresolvedItem(D3/78-17-04): Amendment No. 46 to the Environmental Technical Specifications revised section 4.0 to reduce the number and types of organisms requiring surveillance. As a result the licensee now conducts all environmental analysis at the TI field laboratory in Oswego, New York. All raw sampling and analytical records are available at this local field office.
(0 pen) Unresolved Item (333/77-21-07): The licensee has constructed an Environmental Analytical Laboratory in the auxiliary access point building within the protected area.
The laboratory is partially operable with full operation expected by September 1, 1980. The inspectors exa.nined the laboratory during a plant tour.
This item remains open pending full operation of the lab.
(0 pen) Unresolved Item (333/78-05-03):
The licensee has made a TS amendment request to the New York corporate office to revise section G.5.1 (B).
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3.
Turnover of NRC Principle / Resident Inspectors As of April 4,1980, Mr. Walter H. Baunack assumed the duties of Principle / Senior Resident Inspector and Mr. James C. Linville assumed the duties of Resident Inspector (in training) for James A. FitzPatrick, replacing Mr. Thomas F. Stetka.
4.
Review of Plant Operations The inspectors toured areas of the facility to determine that operations were in accordance with Technical Specifications.
The facility was operating close to full power during the period of this inspection.
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Tour of Accessible Areas Facility tours were conducted of the following areas:
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All levels of the reactor building;
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Turbine Building;
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Control Room; Radwaste Building;
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Diesel Generator Rooms;
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Re1ay Room;
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East and West Crescents;
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Pump House Screen Well;
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Environmental Laboratory; and
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Protected Area Perimeter.
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During these tours the following observations were made:
(1) Monitoring Instrumentation. The following instrumentation was observed to verify that indicated parameters were in accordance with Technical Specifications (TS) Limiting Conditions for Operations (LCO):
Reactor Vessel Level and Pressure;
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Recirculation Flow;
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Reactor Power;
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Control Rod Position;
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Equipment Operating Status;
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Area Radiation and Stack Gas Monitors;
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Reactor Coolant System Conductivity; and i
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j Process Computer Core Operating Faraneters.
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(2) Annunciator Alarms. The inspector observed various alann
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j conditions existing during the tour. These alarm conditions
were discussed with the Shift Supervisor on duty who was i
knowledgeable of the alarms, the conditions causing the alarms, and the actions required by the alarms.
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(3)
Shift Staffing. The inspectors verified by spot checks that the operating shift met Section 6 of the Technical Specifications (TS) with regard to numbers and licenses.
(.4)
Radiation Areas. The inspectors noted that the continuation sheet for one RWP was incorrectly numbered.
The licensee corrected this error immediately.
At several step of pad areas the inspectors found protective clothing and trash mixed in disposal containers.
In one case the container was removed from the area and the protective clothing was spread around the area.
The licensee corrected this situation immediately.
This situation will be examined during future inspections.
(5) Plant Housekeeping and Conditions. The inspectors observed that post maintenance cleanup appears to leave considerable room for improvement. This was particularly so in areas of pipe support work, which is almost complete, and instru-ment / equipment maintenance.
Interviews with two licensed operators led to opposing viewpoints as to the timely identification and completion of work requests. The effectiveness of administrative maintenance and ho'sekeeping controls will be examined during subsequent inspections.
(6)
Fluid and Steam Leaks. The steam leak on the steam reheat system for the main turbine and the watar leak on the "B" condensate booster pump suction line, reported in NRC R:1 report 50-333/80-01, remain.
Since they cannot be repaired during operation, repairs will be made during the refueling outage scheduled for May 1980.
Although the leakage from the condensate booster pump suction line has increased, neither of these leaks pose radiological problens.
Repair efforts and subsequent performance will be monitored during future inspections.
(7)
Piping Vibration.
No excessive piping vibration was noted.
(8)
Fire Protection.
Fire extinguishers and fire fighting equipment were observed to be unobstructed and recently inspected for operability.
No evidence of smoking was observed in designated "No Smoking" areas.
Tank inventories in the Cardox Tanks were observed to be within TS required limit,
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The inspectors noted that empty wooden crates for low level radioactive waste were stored in an area posted to
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remain clear of combustible materials outside the radwaste building. The licensee was advised of this at the exit interview. The inspector will monitor this condition during a subsequent inspection.
(9) Pipe Hanger /Siesmic Restraints. Several pipe hangers and i
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seismic restraints (snubbers) on safety related systems were observed.
Findings were acceptable.
5.
Review of Automatic Depressurization System (ADS)
The inspectors and licensee representatives discussed the system reset following an ADS initiation.
Results of an avaluation by the licensee revealed that depressing the reset buttons following an automatic ADS initiation would terminate ADS for a 120 second period.
The inspectors noted that this did not appear to be the most conservative system design. The licensee stated this matter would be reviewed further. The inspectors stated that until this matter is resolved the operators should be reinstructed in the reset feature design.
This item is unresolved pending licensee resolution and NRC review (50-333/80-04-01).
6.
Review of Special Procedures The inspectors performed a review of all licensee special procedures (SP-1, Loss of Coolent; SP-3; Main Steam Line Break; F-E0P-33, Small Break Accident; etc.) in order to develop a master list of electrical equipment which is required to function under postulated accident conditions to mitigate design basis events.
This list will be used during IE's independent evaluation of the licensee's responses to IE Bulletin 79-018.
No items of noncompliance were identified.
7.
Pipe Restraint Modifications I
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As a result of a required reanalysis of piping systems, 67 pipe l
supports were icentified as requiring some modification.
The inspectors verified on a sampling basis that 63 of the 67 restraints requiring modification have been modified.
This verification was accomplished as follows:
Review of a log listing each restraint modified and the date
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l the modification was completed.
Review of approximately 20 completed Work Requests (WR) used to
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modify restraints.
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Field inspeccion of modified restraints to verify modification in
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accordance with specifications.
The following restraints were inspected:
(1) H 66-12, Containment. Purge Pipe Support.
Completed January 19, 1980, WR 2879.
(2) H 10-177, RHR Service Water Return Pipe Support. Completed October 26, 1979, WR 2825.
(3) PFSK-727, "A" RHR ripe Support.
Completed October 21, 1979, WR 2026.
(4) H 66-35, SGTS Pipe Support.
Completed November 2, 1979, WR 2839.
(5) H 66-33, Containment Purge Exhaust Pipe Support.
Completed November 2, 1979.
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(6) BFSK 659, Fire Pump Pipe Support.
Completed January 10, 1980, WR 2802.
8.
Unresolved Items Unresolved items are those items for which further information is required to determine whether they are acceptable or items of noncompliance.
An unresolved item is contained in Paragraph 5 of this report.
9.
Exit Interview The inspectors met with licensee representatives (denoted in Paragraph 1) at the conclusion of the inspection on April 4,1980 and summarized the scope and findings of the inspection as they are detailed in this report.
During these meetings, the unrcsolved item was identified.
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