IR 05000244/1989025
| ML17261A919 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 01/10/1990 |
| From: | Blumberg N, Finkel A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17261A918 | List: |
| References | |
| 50-244-89-25, NUDOCS 9001240379 | |
| Download: ML17261A919 (16) | |
Text
U.S.
NUCLEAR REGULATORY COMMISSION
REGION I
Report No. 50-244/89-25 Oocket No. 50-244 License No.
DPR-18 Priority Category C
Licensee:
Rochester Gas and Electric Com an 49 East Avenue Rochester New York 14649 Facility Name:
R.E.
Ginna Nuclear Power Station Inspection At:
Ontario New Yor k Inspection Conducted:
November 6 9 1989 Inspector:
A. Finkel, enior Reactor Engineer date Approved By:
N. Blumbe
, Chief, Operati nal Programs Section, OB, DRS
/ /c date Ins ection Summar
Unannounced ins ection on November 6 - 9 1989 50-244/89-25 d:
A i
i d
R.E.
II Power Station surveillance testing, calibration, and inspection programs for compliance with Section 4 of the Technical Specification, calibration of safety-related instrumentation not specifically controlled by the Technical Specification, and its program for inservice inspection and testing of pumps and valves as required by 10 CFR 50.55a(g).
9001240379 900112 PDR ADOCK 05000244
\\
Results:
R.E.
Ginna Nuclear Power Station has established and implemented surveillance and inservice inspection and testing programs that comply with its requirements as described in Section 4 of the Technical Specification and as required by 10 CFR 50.55a(g).
The inspector did not identify any violations or deviations during this inspectio DETAILS 1.0 Persons Contacted R.E.
Ginna Nuclear Power Station
"S. Adams, Technical Manager
- D. Gent, IST/ISI Coordinator
- R; Marchionda, Director of Outage Planning
- S. Spector, Plant Manager
- J. St. Martin, Corrective Action Coordinator
"J. Miday, Superintendent, Ginna Production U.S. Nuclear Re viator Commission
"N. Perry, Acting Senior Resident Inspector The inspector also held discussions with other licensee personnel during the course of this inspection.
- Denotes those present at the exit meeting on November 9, 1989.
2.1 Ins ection - Sco e
The scope of this inspection was to determine if the programs the licensee has established to implement the surveillance testing; calibration, and inservice inspection program as required by Section 4 of its Technical Specifications and
CFR 50.55a(g)
adequately meet requirements.
The inspection also reviewed the program for controlling safety-related instrumentation not specifically controlled by the Technical Specification.
2.2 Surveillance Testin 61725 The licensee surveillance requirements of its technical specification Section 4 have been verified and documented in administrative procedure A-1106 titled, "Ginna Station Surveillance Schedule."
From this master schedule a monthly surve.illance schedule is issued.
The monthly schedule lists the following information:
Required Test Procedure Item Title Test frequency Responsible function to perform the test, and Date of test performancy
The Results and Test organization (R 8 T) has the responsibility for maintaining the yearly and monthly surveillance schedules.
R5T also updates the master schedule reflecting both new and deleted changes and technical specification criteria.
The inspector attended the pre-surveillance test meetings held prior to the testing of the following items:
Component Cooling Pumps Reactor Protection - Channe'ls 1-4 Boric Acid Tank Levels 1A Emergency Diesel Generator Alignment During these meetings specific surveillance procedures were discussed with precautions being identified.
The.inspector's review of the surveillance procedures, (listed in Attachment A) verified that the requirements of Section 4 of the technical specification were referenced in the survei 1-lance procedures and that the tests were performed within their required technical specification intervals.
The surveillance testing performed on the four items listed above was completed; however the surveillance test results were under review and had not been approved during this inspection.
A preliminary review of the test results by the inspector indicated that the test data was within the specification requirements.
The inspector selected for evaluation the surveillance tests performed on Main Steam Isolation Valves (MSIV's) 3516 and 3517 during the outage of May 1989.
With the plant in cold shutdown, the above MSIV's were tested per the r'equirements of Performance Test PT-2. 10.5, Revision 4.
The inspector reviewed the surveillance test data to verify that the require-ments of the technical specification were met and that the results were reviewed by the responsible organization.
The inspector,'s review verified that the MSIV's 3516 and 3517 met the procedure requirements and were reviewed and accepted as defined in administrative procedure A-1106.
To evaluate the R 4 T organization's -trending, program the inspector reviewed the historical data associated with the MSIV's Numbers 3516 and 3517.
The data selected was from the test performed during the cold shutdown periods of 1987, 1988 and 1989.
The R 5 T trending data plotted the stroke and i rvel times of these two MSIV's.
The trending data indicated that no major deterioration of the valves stroke and travel times had occurred.
However, the R 5 T data base did not include test data performed on these valves by the maintenance organization.
Preventive and corrective maintenance data is not necessarily factored into the R 5 T trending data base.
To obtain a complete history of these valves the maintenance and R 5 T data needs to be merged to obtain an overall data history on these valves.
The overall data base program is to be evaluated during 1990.
This subject was discussed with the licensee during the exit meeting of November 9, 1989 '
The present master surveillance schedule is a manually maintained program, however the R 8 T organization is establishing a computerized master surveillance schedule that is scheduled to be operational by the second quarter of 1990.
The planned program in addition to maintaining the master surveillance schedule is expected to have'rovisions for providing trending data reports.
2.3 Inservice Ins ection and Testin of Pum s and Valves
CFR 50.55a The Inservice Inspection program is described in the Quality Assurance Manual Appendix B titled, "Ginna Station Inservice Inspection Program for the 1980 - 1989 Interval."
This program is managed by the Material Engineering and Inspection Services organization (MEIS).
MEIS maintains the master component list and updates its control document on a six-month schedule.
The outage testing schedule is identified by the MEIS organiza-tion and the plant R
T organization schedules the testing.
Test results are reviewed by MEIS and they prepare all nonconformance reports.
On a sampling basis the inspector reviewed the MEIS Master Schedule of January 17, 1989, Revision 6 against the schedule of tests listed in the Quality Assurance Manual (QAM) Appendix B.
The sample reviewed indicat-ed that the required tests listed in the QAM Appendix B were reflected in the MEIS Master Schedule of January 17, 1989.
The master schedule lists the equipment items and inspection intervals for the following types of items:
Class 1 - Quality Group 'A components - Steam Generator Tubing Class 2 - Quality Group B components Class 3 - Quality Group C components High Energy System Components System Pressure Test Criteria Snubbers By System
'To facilitate the MEIS program with the plant outage scheduling, the li-censee has established a
new position titled ISI/IST Coordinator.
The job description for this position was in the management review cycle, but it was the inspector's understanding that one of the main functions of the ISI/IST Coordinator was to ensure that, the plant outage schedule is implemented in accordance with the schedule defined in the QAM Appendix B
Ginna Station Inservice Inspection Program for the 1980-1989 interval as up-dated in the MEIS schedule dated January 17, 1989, Revision 6.
The inspector verified that the requirements of Amendment 37 to the Ginna Technical Specification were in the process of being incorporated into the MEIS master program schedule.
The inspector also verified that Amendments 33 and 34 were in the surveillance procedure change cycle.
(Amendments are described in Attachment A).
~ '~ Qye
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2.4 Calibration of. Safet -Related Com onents Not Identified in Technical S ecification Administrative Procedure No. A-1201, Revision No.
15 titled, "Calibration and Control of Measuring and Test Equipment, Plant Instruments and Equip-ment," is the document. that establishes the requirements and assigns the responsibilities for establishing the plant calibration programs.
The inspector verified that Instrumentation and Control, Results and Test, Mechanical Maintenance and HP/Chemistry each maintains a list and recall schedule of the measuring and test equipment (M&TE) under their control.
The test equipment program for their, classified equipment Category I, II and III as defined in A-1201, Revision No.
15 follows -the guidelines of IEEE 498 entitled,
"Requirements for Calibration and Control of Measuring and,Test Equipment Used in Nuclear Facilities."
To ensure that calibrated METE was used to r'ecord surveillance te"t data the inspector selected the following surveillance reports:
PT2.7 Service Water System Monthly Test Reports
~
Loop A MOV 4616 Auxiliary Building SW Isolation Valve (Upper)
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Loop A MOV 4735 Auxiliary Building SW Isolation Valve (Lower)
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MOV 4780 Screen House SW Isolation ( Lower)
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MOV 4613 Turbine Building SW Isolation (Upper)
Boric Acid Tank Temperature Survei llanc'es Primary Auxiliary Log Sheet No.
2 - Recorded every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by operators, Main Control Board Temperature Readings - Recorded once per shift-operators log.
In each of the above samples, the inspection verified that the MME used by the personnel were controlled and met the requirements of procedure A-1201.
2.5 Conclusion The inspector determined that the licensee h;",: developed and implemented a formal system to control and evaluate testin~~, calibration, and inspection of its system and components as required by the Technical Specification and
CFR 50.55a(g).
The inspector also determined that the licensee was in compliance with Section 5'.8 of ANSI N18.7-1976 which specifies that a master schedule shall be prepared for control of surveillance testing, calibration and inspection, and RG 1.33, Revision
2, Appendix A, Section 8 which requires that procedures shall be prepared for each surveillance test, inspection, or calibration listed in the Technical Specification.
No deviations or violations were identified.
~Ei Licensee management was informed of the scope and purpose of the inspection at an entrance meeting conducted on November 6, 1989.
An exit meeting was,conducted on November 9, 1989 (see paragraph 1 for attendees)
at which time the results of the inspection was present.
At no time during the inspection did the inspector pr'ovide written material to the licensee nor did the'icensee indicate that areas covered by this inspection contained proprietary informatio ATTACHMENT A Surveillance Test Procedures A-1106 Ginna Station Surveillance Schedule Performance Test 2.8 - Component Cooling Pumps Performance Test 5. 10 -
Rx Protection Channel 1-4 Performance Test
Boric Acid Tank Levels Performance Test T.27. 1-1-A Emergency D/G Alignment Performance Test PT.2. 1 MSIV Cold Shutdown Exercising Requirements Control Procedures'
HP7
~ 6, Revision 24 - Survey Instrumentation, Calibration and Maintenance Records Quality Assurance Manual Section 12, Revision 9, 'Calibration and Control of Measuring and Test Equipoment, Plant Instrumentation and Equipment Quality Assurance Manual, Appendix B - Ginna Station Inservice, Inspection Program for the 1980-1989 Interval Administrative Procedure AP No.-1201, Revision No.
15 - Calibration and Control of Measuring and Test Equipment, Plant Instruments and Equipment Technical S ecification Amendments Amendment 33 - Revises T.S. to reflect modifications for the Residual Heat Removal Pump, Safety Injection Pump Systems and Boric Acid Storage Tanks.
Amendment 34 - Clarifies requirements and imposes staggered monthly testing on both trains of automatic trip logic contact sets.
Amendment 37 - Revises T.S. to reflect new testing for snubbers (Reflects next 10 year plan criteria - 1990-2000).
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