IR 05000333/1999004

Insp Rept 50-333/99-04 on 990412 to 0529.Non Cited Violations Noted.Major Areas Inspected:Operations,Maint & Engineering

ML20196G315
Person / Time
Site:	FitzPatrick
Issue date:	06/18/1999
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20196G301	List: IR 05000333/1999004 ML20196G298
References
50-333-99-04, 50-333-99-4, NUDOCS 9907010125
Download: ML20196G315 (15)

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U.S. NUCLEAR REGULATORY COMMISSION )

REGION I

Docket No.: 50-333 l

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License No.: DPR-59

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Report No.: 99-04 Licensee: New York Power Authority i

Facility: James A. FitzPatrick Nuclear Power Plant Location: Post Office Box 41 Scriba, New York 13093 Dates: April 12 to May 29,1999 Inspectors: R. A. Rasmussen, Senior Resident inspector B. S. Norris, Resident inspector R. S. Barkley, Project Engineer 1 J. G. England, Resident inspector, Indian Point 2 l Approved by: J. F. Rogge, Chief Projects Branch 2 Division of Reactor Projects l

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9907010125 990618 PDR ADOCK 05000333 G PDR

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EXECUTIVE SUMMARY James A. FitzPatrick Nuclear Power Plant NRC inspection Report 50-333/99-04 April 12 - May 29,1999 OPERATIONS The inspectors considered the preparation, performance, and operation of the plant in support of the reactor recirculation pump motor generator maintenance to be an example of a well-planned and executed evolutio MAINTENANCE NYPA identified that a tagout had not been properly cleared during the refueling outage, resulting in the reactor core isolation cooling (RCIC) system being inoperable from December 1998 until April 3,1999. (NCV 50-333/99-04-01) The identification and immediate resolution of this issue was an example of a good questioning attitude by a senior licensed operator. However, the NRC noted that licensing and operations personnel did not correctly assess the operability of the RCIC in a post event operability determination and considered this a performance laps Selected portions of FitzPatrick's post-maintenance and post-work testing process were reviewed and found to adequately ensure that equipment is properly tested prior to its return to service. Past lapses identified by NYPA in the conduct of post-maintenance and post-work testing predominately involved administrative deficiencies, inadequate testing requirements for i

equipment for which specific regulatory or procedural performance standards did not exist and the failure of Operations to promptly identify an anomalous condition during breaker testin ENGINEERING During the performance of surveillance testing, technicians noted that the as-found setpoints for the suppression chamber to reactor building vacuum breakers were outside of the allowable tolerance.' NYPA determined the cause to be an incorrect assumption in the calculation for the setpoint adjustment. The failure to properly calibrate the pressure switches resulted in the i associated isolation valves being inoperable, a violation of the FitzPatrick TS, Section 3.7.A. (NCV 50-333/99-04 02)

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TABLE OF CONTENTS page

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1. OPERATION S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1

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'01 Conduct of Operations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 O1.1 General Comments ' . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 01.2 Single Loop Operation for Planned Maintenance . . . . . . . . . . . . . . . . . 1 08 . Miscellaneous Operations lasues . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 08.1 (Closed) Inspector Follow Item 50-333/97-06-01. . . . . . . . . . . . . . . . . 2 08.2 (Closed) Unresolved item 50-333/98-02-04 . . . . . . . . . . . . . . . . . . . . 3

I I . MAI NTE NANCE . . . . . . . . . . . . . . . . . . . . . -. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 M1 Conduct of Maintenance . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 M1.1 General Comments . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 M1.2 - Failure to Properly Restore the Reactor Core isolation Cooling (RCIC)

System During the Refueling Outage . . . . . . . . . . . . . . . . . . . . -. . . . . . 4 {

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. M3.1 Review of Post-Maintenance / Post-Work Testing Procedures . . . . . . . 6 lll . E NGI N E E RI NG . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 E1 Conduct of Engineering . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 E1.1 General Comments . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 E1.2 Review of the FitzPatrick Y2K Program Contingencies . . . . . . . . . . . . 7

.E8 - Miscellaneous Engineering issues . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 E8.1 (Closed) Licensee Event Reports 50-333/99-02 & 50-333/99-02-01. . 7 IV. PLANT S U PPORT . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 V. MANAGEM ENT M EETI NGS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9 X1 Exit Meeting Summary . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9 ATTACHMENTS 4

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Attachment 1 - Partial List of Persons Contacted-Inspection Procedures Used

- Items Opened, Closed, and Discussed

- List of Acronyms Used i

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REPORT DETAILS Summary of Plant Status

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The unit began the inspection period at 100% power. On May 22,1999, FitzPatrick conducted a planned power reduction to 65% for cleaning of the condenser water boxes, they returned the plant to 100% the same day. On May 26, a planned reduction to 35% was performed to enter single-loop operation and replace the tachometer for the "A" reactor recirculation pump motor generator; the plant retumed to 100% on the same day. The plant remained at 100% for the rest of the inspection perio l. OPERATIONS 01 Conduct of Operations O1.1 General Comments (71707)

Using NRC Inspection Procedure 71707, the resident inspectors conducted frequent reviews of ongoing plant operations. The reviews included tours of accessible and normally inaccessible areas of both units, verification of engineered safety features (ESF) system operability, veritication of adequate control room and shift staffing, verification that the units were operated in conformance with Technical Specifications (TSs) and Updated Final Safety Analysis Report (UFSAR), and verification that logs and records accurately identified equipment status or deficiencies. In general, the conduct of operations was professional and safety-conscious; specific events and noteworthy observations are detailed in the sections belo .2 Sinale Looo Ooeration for Planned Maintenance Inspection Scope (71707. 62707)

The New York Power Authority (NYPA) planned and completed maintenance on the "A" reactor recirculation pump (RRP) motor generator (MG). This required going single-loop and retuming to two-loop operation. The inspectors observed the training of the operations crew and the actual evolutio Observations and Findinos Following erratic speed Indications on the "A" RRP-MG, NYPA identified that the brushes for the tachometer for the "A" RRP-MG were wearing out faster than expected. To replace the tachometer, the MG set needed to be removed from service, which required the plant to be placed in single-loop operation. On May 26,1999, the operations and maintenance departments were able to secure the "A" MG set, replace the tachometer, and restore the plant to the normal two-loop configuratio The inspectors considered the training conducted in the simulator for the operations crew to be pro-active, in that single-loop operations are an unusual activity. The command and control of the operations crew management during the actual evolution was good, with appropriate communications. Senior FitzPatrick management was present during

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the training and the actual transition. The maintenance was also performed well, and the RRP-MG set was ready to be returned to service within two hours. The entire activity was completed in eight hour Conclusion l The inspectors considered the preparation, performance, and operation of the plant in l

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support of the reactor recirculation pump motor generator maintenance to be an example of a well-planned and executed evolutio Miscellaneous Operations issues O8.1 (Closed) Insoector Follow item 50-333/97-06-01: Refuelina Floor Smoke Detectors Out-Of-Service Since 1993 Inspection Scooe (92901)

In 1997, during a review of the equipment status log, the inspectors noted that the refueling floor smoke detectors had been out-of-service since 1993. Currently, the inspectors reviewed the FitzPatrick Nuclear Safety Evaluation (NSE), the UFSAR and I

TSs, and the fire protection program document Observations and Findinas During a review of the FitzPatrick equipment status log in 1997, the inspectors noted that the fire protection smoke detectors on the refueling floor had been out of service since 1993. . At that time, the inspectors questioned the longstanding equipment deficiency issue and the licensing basis associated with these detectors. During this inspection period, the inspectors reviewed NSE JAF-SE-97-023, " Elimination of Fire Detection Capability on the Refueling Floor," which stated that the detectors performed no safety !

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function and were an after-the-fact enhancement to the original fire p,c+ection progra In addition, the NSE concluded that the removal of the smoke detectors siid not affect reactor safety. As such, FitzPatrick plans to revise the UFSAR to remove the reference

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to the refueling floor smoke detecto However, the UFSAR, Section 9.8.3.3, states that smoke detection is provided on all elevations of the reactor building. As such, the licensee's failure to maintain the smoke

- detectors operable on the refuel floor is a violation of 10CFR50, Appendix B, Criterion ill, l Design Control. This violation of NRC requirements is of minor significance and is not

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subject to formal enforcement actio Conclusion i

The failure of FitzPatrick to maintain the refueling floor smoke detectors operable since 1993 is a minor violation of 10CFR50, Design Contro .. .

08.2 (Closed) Unresolved item 50-333/98-02-04: Poor Attendance at Licensed Operator Reaualification Trainina (92901) .

In 1998, the NRC noted during a review of the licensed operator requalification training (LORT) program that some operators did not attend all of the required classes. In addition, the makeup training was not accomplished in a timely manner. At that time, this was classified as an unresolved item pending additional review by the NRC headquarters staff. Concurrent with the NRC's efforte NYPA issued Deviation and Event Report (DER)98-902 to review the issue and initiate corrective action During this inspection period, the inspectors reviewed the DER response, the revised training procedure, and discussed the actions taken by NYPA with the NRC specialist inspector who identified the issue. FitzPatrick revised the associated training procedure

. (TP-5.05, " Licensed Operator Requalification Training Program") to require that missed classes be made-up within 14 weeks. Also, a letter was issued to each licensed reactor operator and senior reactor operator that attendance at training should be one of their highest priorities. The NRC considers the formalization of FitzPatrick management expectations to be acceptable to prevent recurrence; in addition, there was no violation

' of NRC requirements. This item is close II. MAINTENANCE M1 Conduct of Maintenance

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' M1.1 General Comments (61726. 62707)

Using NRC Inspection Procedures 61726 and 62707, the resident inspectors periodically observed various maintenance activities and surveillance tests. As part of the observations, the inspectors evaluated the activities with respect to the requirements of the Maintenance Rule, as detailed in 10CFR50.65. In general, maintenance and surveillance activities were conducted professionally, with the work requests (WRs),

problem identification documents, and necessary procedures in use at the work site, and with the appropriate focus on safety. Specific activities and noteworthy observations are detailed in the inspection report. The inspectors reviewed procedures and observed all or portions of the following maintenance / surveillance ectivities:

~ ST-2HA Low Pressure Coolant injection (LPCI) initiation Logic System "A" Functional Test While in Run Mode

• SP-1.04 Standby Liquid Control Sampling and Analysis a

' ST .1 H - - Primary Containment isolation Valve Inoperable Test

• ST-40D Daily Surveillance and Instrument Check

- ST-5D APRM Calibration

- ST-5E Core Performance Daily Surveillance

_ ISP-89 ' Suppression Chamber / Reactor Building Vacuum Breaker Isolation Valve Differential Pressure Switch Instrument Functional Test

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. ST-24E RCIC Logic System Functional and Simulated Automatic Actuation Test

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ST-24J RCIC Flow Rate and Inservice Test (IST)

PTR 98-451 VOTES As-Found / Operator PM, Sub-01 Sensor Check, Sub-02 VOTES As-Left

• ST-26K Recirculation Loop Start-Up Differential Temperature Check

. ST-23C Jet Pump Operability Test for Two-Loco Operation (EPIC Available)

ST-23D Jet Pump Operability Test for Single-Leop Operation

• WO 99-2510-00 Replacement of the "A" RRP Motor Generator Tachometer M1.2 Failure to Properly Restore the Reactor Core Isolation Coolina (RCIC) System Durina the Refuehna Outage Insoection Scone (62707)

In April 1999, NYPA identified that two electrical leads were disconnected for the RCIC system. The lifted leads would have prevented the automatic closure of the condensate storage tank (CST) suction valve to the RCIC pump during the automatic swap-over to the torus. Investigation revealed that the leads should have been re-connected during

the system restoration from the refueling outage. The inspectors reviewed the DER and corrective actions, the Operability Determination, the TSs and UFSAR, and NRC Generic Letter (GL) 91-1 System Descrir#90: The RCIC system is designed to automatically prov:de makeup water to the reactor vessel following isolation of the vessel from the main condenser or a total loss of offsite electrical power. The system uses a steam-turt>ine-driven pump, with the steam supply from the reactor vessel. The pump normally takes a suction from the l CST, but will automatically swap-over to the torus on a low level in the CST. The CST suction valve is designed to automatically close after the torus suction valves are fully open. For events other than pipe breaks, the RCIC system has sufficient makeup capacity to prevent the reactor vessel water level from uncovering the core without the

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use of emergency core cooling system (ECCS) pumps. Per TS Section 3.5.E, the RCIC system is required to be operable whenever there is fuel in the reactor vessel and the reactor is not in a cold shutdown condition, Observations and Findinas On April 3,1999, during preparation for a licensed operator requalification examination, a senior reactor operator (SRO) noticed that two leads inside one of the relay room

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Instrumentation panels were not connected and still had protective tagging request l (PTR) tags attached. The Shift Manager (SM) declared the RCIC system inoperable and !

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initiated action to have the leads re-connected; after which, the RCIC system was returned to service. The SM wrote DER 99-527 to document the issue and determine i the root cause. Other immediate corrective actions included: (1) a walk-down of all control loom and relay room panels for any other lifted leads, and (2) a review of all PTRs having lifted leads that were cleared during the outage. No discrepancies were identified.

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NYPA determined that the event occurred on October 25,1998, when the PTR was improperly cleared during the refueling outage. The corrective actions to prevent recurrence focused on the process for clearing PTRs, as described in FitzPatrick

. administrative procedure AP-12.01, ' Equipment and Personnel Protective Tagging."

This event was the result of an inadequate administrative procedure; in that, AP-12.01 did not require that personnel ensure all supplemental PTR sheets were also reviewed and cleared prior to closing the PTR. The NRC agreed with the NYPA conclusion that the safety significance of the CST suction valve not being able to close was minimal because of manual operator actions that would be prompted by the annunciator for CST low leve The inspectors reviewed the DER, the administrative procedure, the UFSAR, and the TSs, and considered the root cause analysis and corrective actions to be acceptabl Also, the identification and pursuit of this issue was an example of a good questioning attitude by the SR During the review of the event, NYPA concluded that the RCIC system had always been operable and was therefore not reportsbie to the NRC, per 10CFR73. However, the inspectors identified that the NYPA Operability Determination was in error and was based on the use of operator manual actions in lieu of an automatic design feature described in the UFSAR. The inspectors discussed the issue with FitzPatrick .

management. They agreed that the Operability Determination was wrong and they i declared that the RCIC system had been inoperable from December 18,1998 (when it j was first required to be operable after the refueling outage), until April 3,1999. They 1 informed the inspectors that the issue would be reported to the NRC in accordance with 10CFR73. The inspectors noted that licensing and operations did not recognize the inoperability of RCIC and considered this a performance laps I Notwithstanding, the failure to properly restore the system during the refueling outage :

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resulted in the RCIC system being unable to perform its safety function as described in the UFSAR, Section 4.7. Specifically, the CST suction valve to the RCIC pump would not have automatically closed during the swap-over to the torus. As such, the RCIC system was inoperable from December 18,1998 until April 3,1999. This is a violation o'

the FitzPatrick TS, Section 3.5.E. This NRC-identified Severity Level IV violation is being treated as a Non-Cited Violation (NCV), consistent with Appendix C of the NRC l Enforcement Policy. This violation is in the licensee's corrective action program as DER 99-086. (NCV 50-333/99-04-01) Conclusion i NYPA identified that a tagout had not been properly cleared during the refueling outage, resulting in the reactor core isolation cooling (RCIC) system being inoperable from December 1998 until April 3,1999. (NCV 50-333/99-04-01) The identification and ;

immediate resolution of this issue was an example of a good questioning attitude by a senior licensed operator. However, the NRC noted that licensing and operations did not i recognize the inoperability of RCIC in a post event operability determination and i

considered this a performance laps ,

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M3 . Maintenance Procedures and Documentation I

M3.1 Review of Post-Maintenance / Post-Work Testina Procedures Inspection Scope f71707)

The inspectors reviewed NYPA Administrative Procedure AP-5.07, Revision 11,

" Maintenance Testing and Post-Work Testing," to evaluate the adequacy of testing following maintenance activities as well as testing conducted to demonstrate the operability of a system or component (i.e., post-work testing). This review was conducted in response to an event in February 1999 when the "D" emergency diesel generator (EDG) output breaker, which was placed in service in January 1999, was found to have auxiliary contacts that were incorrectly wired. The miswired auxiliary contacts did not affect the operation of the breaker, but rather resulted in an erroneous control room alarm. This event was the subject of a non-cited violation as noted in NRC Inspection Report 50-333/99-01 J Observations and Findinas The inspectors reviewed NYPA's corrective actions for the February 1999 EDG breaker problem. NYPA concluded that the breaker was incorrectly wired by the breaker manufacturer when procured and that the breaker miswiring was not detected by electrical maintenance during receipt acceptance testing nor by Operations during the performance of the post-work testing conducted during breaker installation. No deficiencies were noted in the actual post-work test conducted as the test identified that the breaker was miswired via actuation of an unexpected alarm, but actuation of the I alarm was not identified by the operators during the test. Corrective actions included counseling of operators and revisions to electrica! maintenance procedures goveming the receipt testing of breakers; no changes to AP-5.07 were considered necessar The inspectors reviewed AP 5-07 as well as a printout of all DERs over the previous year 1 related to inadequate post-maintenance and post-work testing requirements and l discussed their observations with the Work Planning Manager. While opportunities for improving the post-work process were identified in the DERs reviewed, virtually all of the problems identified with this process centered on administrative lapses or deficiencies in leak rate testing unrelated to 10 CFR 50 Appendix J leak rate testing requirements. A review was also conducted of several work requests which prescribed post-work testing )

requirements, most particularly recent work requests related to the drywell continuous air monitors. The inspectors noted in several cases that while the post-work testing listed in the work request (WR) appeared limited, the WR often referred the test director to other documents which provided the detail necessary to the properly perform a through post-maintenance or post-work test of the system or componen Conclusions l

- Selected portions of FitzPatrick's post-maintenance and post-work testing process were reviewed and found to adequately ensure that equipment is properly tested prior to its l l

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retum to service. Past lapses identified by NYPA in the conduct of post-maintenance and post-work testing predominately involved administrative deficiencies, inadequate testing requirements for equipment for which specific regulatory or procedural performance standards did not exist and the failure of Operations to promptly identify an anomalous condition during breaker testin Ill. ENGINEERING E1 Conduct of Engineering E GeneralComments (37551)

Using NRC Inspection Procedure 37551, the inspectors frequently reviewed design and system engineering activities and the support by the engineering organizations to plant activities. Specialist inspectors in this area may have used other procedures during their reviews of engineering activities; these inspection procedures are listed, as applicable, for the respective sections of the inspection repor E Review of the FitzPerick Y2K Proaram Continoencies The NRC conducted an abbreviated review of the FitzPatrick Year 2000 (Y2K) activities and documentation using Temporary Instruction (TI) 2515/141," Review of Year 2000 Readiness of Computer Systems at Nuclear Power Plants." The review addressed aspects of Y2K management planning, documentation, implementation planning, initial assessment, detailed assessment, remediation activities, Y2K testing and validation, notification activities, and contingency planning. The reviewers used NEl/NUSMG 97-07, " Nuclear Utility Year 2000 Readiness," and NEl/NUSMG 98-07, " Nuclear Utility Year 2000 Readiness Contingency Planning," as the primary references for this revie The results of this review will be combined with the results of other reviews in a summary report to be issued by July 31,199 E8 Miscellaneous Engineering issues E (Closed) Licensee Event Reports 50-333/99-02 & 50-333/99-02-01: Sucoression Chamber to Reactor Buildina Vacuum Breaker Isolation Valve Differential Pressure Switches Out of Tolerance Inspection Scope (90712. 92700)

During surveillance testing, FitzPatrick instrumentation and control (l&C) technicians I noted that the as-found setpoints for the suppression chamber to reactor building vacuum breakers were outside of the allowable tolerance. The inspectors reviewed the surveillance test report, the DER, the TSs, and the licensee event report (LER) and its supplemen I

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b. Observations and Findinas On January 13,1999, during the performance of l&C surveillance procedure ISP-89, technicians noted that the as-found setpoints for the suppression chamber to reactor building vacuum breakers were outside of the allowable tolerance. Specifically, the differential pressure switch trip feature for the vacuum breaker isolation valves exceeded the TS allowable value of 0.5 psid (pounds per square inch differential).

NYPA determined the cause to be a wrong assumption in the calculation for the setpoint adjustment. Specifically, FitzPatrick assumed that the instruraent drift was less than that stated in the vendor manual. Corrective actions included immediate calibration of the pressure switches and establishment of an increased frequency for the surveillance tes Additionally, FitzPatrick was reviewing the process for determining instrument uncertainty analysi The inspectors reviewed the DER, the LER and its Supplement, and the TSs, and considered the root cause analysis and corrective actions to be acceptable. However, FitzPatrick TS, Section 3.7.A.4.a, requires two operable pressure suppression chamber reactor building vacuum breakers. Contrary to the above, improper assumptions used to calculate calibration requirements of the pressure suppression chamber to reactor building vacuum breaker isolation valve pressure switches caused the vacuum breakers to be inoperable. This Severity Level IV violation is being treated as a Non-Cited Violation (NCV), consistent with Appendix C of the NRC Enforcement Policy. This violation is in the licensee's corrective action program as DER 99-08 (NCV 50-333/99-04-02) Also, LERs 99-02 and 99-02-01 are close c. Conclusion During the performance of surveillance testing, technicians noted that the as-found i setpoints for the suppression chamber to reactor building vacuum breakers were outtide ,

of the allowable tolerance. NYPA determined the cause to be an incorrect assumption in the calculation for the setpoint adjustment. The failure to properly calibrate the pressure switches resulted in the associated isolation valves being inoperable, a violation of the FitzPatrick TS, Section 3.7.A.4.a. (NCV 50-333/99-04-02)

IV. PLANT SUPPORT Using NRC Inspection Procedure 71750, the resident inspectors routinely monitored the performance of activities related to the areas of radiological controls, chemistry, emergency preparedness, security, and fire protection. Minor deficientas were discussed with the appropriate management. There were no significant observations during this inspection perio l

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V. MANAGEMENT MEETINGS-X1 Exit Meeting Summary -

At periodic intervals, and at the conclusion of the inspection period, meetings were held with senior station management to discuss the scope and findings of this inspection. The final exit meeting occurred on June 4,1999. During this meeting, the resident inspector findings were presented. NYPA did not dispute any of the inspectors findings or conclusions. Based on the NRC Region I review of this report, and discussions with NYPA representatives, it was determined that this report does not contain safeguards or proprietary informatio r

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l 1-ATTACHMENT PARTIAL LIST OF PERSONS CONTACTED (

l - N. Avrakotos Emergency Planning Coordinator i P. Brozenich Operations Manager M. Colomb Site Executive Officer l R. Converse General Manager, Maintenance i

. D.' Lindsey - Plant Manager R. Locy - .

Training Manager l A. McKeen Radiological & Environmental Department Manager W. O'Malley General Manager, Operations l D. Ruddy Director, Design Engineering l G. Tasick - Licensing Manager i

T. Teifke Security Manager A. Zaremba General Manager, Support Services INSPECTION PROCEDURES USED l lP 37551 - On-Site Engineering IP 61726 Surveillance Observations IP 6270 Maintenance Observations IP 71707 . Plant Operations IP 71750 Plant Support IP 90712 in-Office Review of Written Reports of Non-Routine Events at Power Reactor Facilities IP 92700 ' Onsite Follow-up of Written Reports of Non-Routine Events at Power Reactor Facilities l lP 92901 Follow-up - Operations

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l Attachment 1 ITEMS OPENED. CLOSED. AND UPDATED OPENED NCV 50-333/99-04-01 Failure to Clear All PTR Tags Resulted in RCIC Being inoperable for Three Months NCV 50-333/99-04-02 As-Found Setpoint Not Within TS Allowable Value for Vacuum Breaker Isolation Valve Differential Pressure Switches CLOSED NCV 50-333/99-04-01 Failure to Clear All PTR Tags Resulted in RCIC Being inoperable for Three Months NCV 50-444/99-04-02 As-Found Setpoint Not Within TS Allowable Value for Vacuum I l

Breaker Isolation Valve Differential Pressure Switches IFl 50-333/97-06-01 Refueling Floor Smoke Detectors Out-Of-Service Since 1993 )

URI 50-333/98-02-04 Poor Attendance at Licensed Operator Requalification Training I l LER 50-333/99-02-00 Suppression Chamber to Reactor Building Vacuum Breaker Isolation .

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Valve Differential Pressure Switches Out of Tolerance LER 50-333/99-02-01 Suppression Chamber to Reactor Building Vacuum Breaker Isolation ;

Valve Differential Pressure Switches Out of Tolerance UPDATED

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Attachment 1 l l

LIST OF ACRONYMS USED APRM Average Power Range Monitor j CFR Code of Federal Regulations {

CST Condensate Storage Tank '

DER Deficiency and Event Report ECCS Emergency Core Cooling System GL Genenc Letter IFl Inspector Follow Item l&C Instrumentation and Control LER Licensee Event Report LORT Licensed Operator Requalification Training MG Motor Generator NCV Non Cited Violation NRC Nuclear Regulatory Commission NSE Nuclear Safety Evaluation 1 NYPA New York Power Authority {

PTR Protective Tagging Request  !

RCIC Reactor Core Isolation Cooling RRP Reactor Recirculation Pump SM Shift Manager TS Technical Specifications i URI Unresolved item UFSAR Updated Final Safety Analysis Report WR Work Request 4 A-3