IR 05000272/1978024
| ML18078A461 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 10/13/1978 |
| From: | Conte R, Zimmerman R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML18078A460 | List: |
| References | |
| 50-272-78-24, NUDOCS 7811290389 | |
| Download: ML18078A461 (12) | |
Text
Report N Docket N U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT 50-272/78-24 50-272 Region I License No. DPR-70
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Categor C
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- Licensee:
Public S~rvice Electric and G~s C Park Place Newark, New Jersey 07101 Facility Name:
Salem Nuclear Generating Station, Unit I Inspection at:
Hancocks Bridge*, New Jersey Inspection eptember 12-15, 1978 OM_/~~,~
Inspectors:
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. RlJ." J.. ~te, Reactor Jjnspect1r.
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L,.t,,,,._,
R. P. Zimmerman, Reactor i{);pector Approved by: ~
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H. B. Kister, Chief, Nuclear Support Section No. 2, RO & NS Branch Inspection Summary:
7da t~ signed
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ldat'e signed date signed 10/;1 /1?
dat~signed
- Ins ectfon on Se tember 12-15, 1978 Re art No. 50-272/78-24
. re~s Inspected: Routine, unannounced inspection.of surveillance calibrations o.f sa~ety related components and equipment required by Technical Specifications including associated procedures and completed data; performance of selected surveillance calibrations; calibration data for selected measuring/test equipment; calibrations required by Technical Specifications of components and equipmen associated with safety related systems and/or functions incl~ding procedures and completed data; qualification records of selected individuals who* performed
safety related calibrations; and, plant conditions as noted by a facility tou The inspection involved 58 inspector hours onsite by 2 ~egional}based NRC inspectors ults:
No items of noncompliance were identifie *
?81129 6 3&y Region I Form 12 (Rev. April 77)
DETAILS Persons Contacted
- L. Fry, Senior Performance Supervisor J. Kovacsofsky, Shift Supervisor
- D. Lyons, Quality Assurance Specialist
- H~ Midura, Manager, Salem Nuclear Generating Station
- L. Miller, Station Performance Engineer J. Nichols, Reactor Engineer
- L. Norrholm, Resident NRC Inspector J. Robbins, Performance Supervisor J. Robertson, Senior Maintenace Supervisor
- J. Stillman, Station Quality Assurance Engineer
- W. Treston, Resident.iQu.aTit.Y-Assuranc*e Ingineer
- J. Zupko,Jr., Chief Engineer*
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The inspector interviewed other licensee employees, including members of the engineering staff, QA Personnel, reactor operators, and technician * denotes those present at the exit interview Administrative Control of Safety Related Calibrations The inspector performed an audit of the licensee's administrative controls in this area by conducting a sampling review of the below listed administrative procedures with respect to the requirements of the Technical Specifications, Section 6, 11Administrative Controls,
ANSI Nl8.7, 11Administrative Controls for Nuclear Power Plants 11 and Regulatory Guide 1.33, 11Quality Assurance Program Requirements.
Administrative Procedure No. 10, Inspection Order System, Revision 1, February 17, 197 Administrative Procedure No. 20, Deficiency Reports, Testing Deficiency Reports and Corrective Action Requests, Revision 5, May 18, 197 Administrative Procedure No. 22, Calibration of Measuring and Test Equipment, Revision 2, October 24, 197 No items of noncompliance were identified.
- 3 Surveillance Calibration of Safety Related Components and Equipment Required by Technical Specifications The inspector reviewed calibration procedures and associated data sheets on a sampling basis to verify the following:
Calibration frequency requirements have been met; Applicable system status during component calibration was in conformance with Technical Specification limiting conditons for operations; Procedure format provided detailed stepwise instructions; Procedure review and approval were as required by Tech-nical Specifications; Trip points of calibrated components were in conformance with Technical Specification requirements; and, Technical content of procedures was sufficient to result in satisfactory component calibratio The following calibration procedures/data were selected for the above review:
PD-2.6.033, Channel Functional Test Steam Generator 11 Level Protection - Channel IV, Revision 0, August 197 Tests performed June 6, 1978; July 6, 1978; July 31, 1978 and, August 28, 1978. (LT-517)
PD-2.5.033, Channel Sensor Calibration Steam Generator 11 Level Protection -
Channel IV, Revision 1, August 197 Calibration performed October 24, 197 PD-2.2.033, Channel Calibration Check Steam Generator 11 Level Protection - Channel IV, Revision 1, January 197 Calibration performed July 31, 197 PD-2.6.034, Channel Functional Test Steam Generator 11 Level Protection - Channel III, Revision 1, November 1976. Tests performed June 30, 1978; July 10, 1978; July 24, 1978; and, August.22, 1978. (LT-518)
- PD-2.5.034, Channel Sensor Calibration Steam Generator 11 Level Protection - Channel III, Revision 1, August 197 Calibration performed October 20, 197 PD2-2.2.34, Channel Calibration Check Steam Generator 11 Level Protection - Channel III~ Revision 1,. January*
197 Calibration performed Juiy 24, 197 PD-2.6.035, Channel Functional*~Test Steam=Generato~ 11 Level Protection - Channel tr, Revision 1, January 197 Tests performed May 23, 1978; June 23, 1978; July 20, 1978; and, August 14, 1978. (LT-519)
PD-2.5.035, Channel Sensor Calibration Steam Generator 11 Level Protection -
Channel II, Revision 1, August 197 Calibration performed October 24, 197 PD-2.2.035, Channel Calibration Check Steam Generator 11 Level Protection - Channel II, Revision 1, July 197 Calibration performed March 17, 197 PD-2.6.030, Channel Functional Test Steam Generator Steam Pressure Protection - Channel I, Revision 1, January 197 Tests performed May 19, 1978; June 13, 1978; July Tl, 1978; and, August 8, 1978. (PT-514)
PD-2.5.030, Channel Sensor Calibration Steam Generator Steam Pressure Protection - Channel I, Revision 2, August 1977. Calibration performed August 14, 197 PD-2.2.030, Channel Calibration Check Steam Generator Steam Pressure Protection - Channel I, Revision 2, January 1977. Calibration performed December 16, 197 PD-2.6.018, Channel Functional Test Pressurizer Pressure Protection - Channel II, Revision 4, May 1978. Tests performed May 26, 1978; June 22, 1978; July 19, 1978; and, August 14, 1978. (PT-456)
PD-2.5.018~ Channel Sensor Calibration Pressurizer Pressure Protection - Channel II, Revision 1, August 197 Cali-bration performed September 23, 1977.
- PD-2.2.018, Channel Calibration Check Pressurizer Pressure Protection - Channel II, Revision 2, January 1977. Cali-bration performed March 7, 197 PD-2.6.019, Channel Functional Test Pressurizer Pressure Protection -
Channel III, Revision 4, August 1978~ Tests performed March 9, 1978; May 30, 1978; June 27, 1978; and, July 26, 1978. ( PT-457)
PD-2.5.019, Channel Sensor Calibration Pressurizer Pressure Protection - Channel III, Revision 3, May 1978. Cali-bration performed September 23, 197 PD-2.2.019, Channel Calibration Check Pressurizer Pressure Protection - Channel III, Revision 3, September 197 Calibration performed July 25, 197 PD-2.6.023, Channel Functional Test Pressurizer Pressure Protection - Channel IV, Revision 2, May 1978. Tests performed June 6, 1978; July 3, 1978; July 31, 1978; and, August 28, 1978. (PT-474)
PD-2.5.023, Channel Sensor Calibration Pressurizer Pressure Protection - Channel IV, Revision 2, August 197 Calibration performed September 23, 197 PD-2.2.023, Channel Calibration Check Pressurizer Pressure Protection - Channel IV, Revision 2, January 197 Calibration performed June 6, 197 PD-2.6.017, Channel Functional Test Pressurizer Pressure Protection - Channel I, Revision 5, May 1978. Tests performed May 18, 1978; June 13, 1978; July 10, 1978; and, August 8, 1978. (PT-455)
PD-2.5.017, Channel Sensor Calibration Pressurizer Pressure Protection - Channel I, Revision 2, September 197 Calibration performed September 24, 197 PD-2.2.017, Channel Calibration Check Pressurizer ~ressure
.Protection - Channel I, Revision 2, January 1977. Calibra-tion performed November 197 *
PD-16.1.002, Channel Calibration Check Intermediate Range, Revision 3, October 197 Calibration performed January 10, 197 PD-2.6010, Channel Functional Test Reactor Coolant Flow Loop III - Channel I, Revision 1, January 1977. Test performed August 28,.1978. (FI-434)
- PD-2.5010, Channel Sensor Calibration Reactor Coolant Flow Loop III - Channel I, Revision 1, August 197 Calibration performed September 2~, 197 PD-2.6014, Channel Functional Test Reactor Coolant Flow Loop IV. - Channel I, Revision 1, January 197 Test performed August 7, 197 (FI-444)
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PD-2.5014, Channel Sensor Calibration Reactor Coolant Flow Loop IV - Channel I, Revision l, October 197 Calibration performed January 17, 197 Procedure No. M-16 D, Containment Sump Level Alarm and Indication Tes Calibration performed MaY. 30, 1978..
Procedure No. M3T, Undervoltage and Under Frequency Trip Check and Time Response., Revision 4, March 1977. Tests performed February 28, 1978; May 31, 1978; July.6, 1978; August 1,1978; and, August 23, 197 During the review of the Reactor Coolant System Loop Flow Rate Calibration it appeared to the inspector that the minimum operating limit for loop flows per the control room log is less conservative than the Departure from Nucleate Boiling (DNB) Technical Specification (TS) limit in terms of percent indicated flo Based on latest data for calculated RCS loop flows that correspond to 100% indicated flow, the inspector determined that the DNB TS limit is. approximately 94% indicate For four. loop operation the minimum operating limit on the control room log is 88.3%(a less conservative value).
A review of selected completed logs revealed actual RCS loop flows were greater than 97%.
The licensee representative stated that a review would be conducted in this area to determine the basis for the 88.3% value.
This item is unresolved pending licenseeaction as stated above and subsequent NRC:Rl review. (272/78-24-01) Calibrations Required by Technical Specifications of Components
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and Equipment Associated with Safety Related Systems and/or Function The inspector reviewed on a sampling basis, the program est-ablished for calibration of components associated with safety related systems required by ANSI 18.7-1972 and Appendix 11A
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USNRC Regulatory Guide 1.33, November 197 These components are used to monitor system parameters to comply with the safety limits, limiting conditions of operation, and/or meet the surveillance requirements of the Technical Specification The licensee, through the use of a computerized Inspection Order System, has established calibration frequencies for all safety related plant instrumentatio The Inspection Order System also indentifies the procedure to be used for each calibration. These may be generic or specific procedures depending on the complexity of the calibratio Calibration data for the following components was reviewed~
PD-2.9.194,, Channel Sensor Calibration Accumulator 1l Pressure Indication and Alarm,*Revision O, November 197 Calibration performed September 22, 197 (PI-937 A)
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PD-2.10.194, Channel Calibration Check Accumulator 11 Pressure Indication and Alarm, Revision 0, April 197 Calibration performed May 1, 1978. (PI-937A)
PD-2.9.195, Channel Sensor Calibration Accumualtor 12 Pressure Indication and Alarm, Revision 0, November 197 Calibration performed October 13, 1977. (PI-937 B)
PD-2.10.195, Channel Calibration Check Accumulator 12 Pressure Indication and Alarm, Revision 0, April 197 Calibration performed April 25, 1978. (PI-9378)
PD-1.4.003, (Boron Injection Tank Level)~ General Instrument Calibration Procedure For Field Devices, Revision 3, October 197 Calibration performed October 18, 197 (FIA-940)
PD-1.4.003, (Auxiliary Feed Storage Tank Level), General Instrument Calibration Procedure For Field Devices, Revision 3, October 197 Calibration performed January 20, 1977 (transmitter); and May 13, 1977 (indicator).
(LA-1688)
PD-2. 10.200, Channel Calibration Check Boron Injection Tank Temperature, Revision 0, April 197 Calibration performed May 5, 1978. (TI-944)
PD-2.9. 173, Channel Sensor Calibration Refueling Water Storage Tank Level, Revision 0, November 197 Calibration performed August 4, 1978. (LI-920)
PD-2.10. 173, Channel Calibration Check Refueling Water Storage Tank Level, Revision 0, April 197 Calibration performed August 16, 1978. (LI-920)
PD-2. 1.180, Channel Calibration Check Spray Additive Tank Outlet Flow, Revision 2, June 197 Calibration performed March 4, 1977. (FT-930)
PD 2.5.001, Channel Sensor Calibration Reactor Coolant RTD Cross Calibration Check, Revision 1, November 197 Calibration performed November 17, 1977. (TI-442)
PD 2. 10.073 Channel Calibration Check Loop 14 Reactor Coolant Wide Range Temperature-Cold Leg,Revision 0, May 197 Calibration performed August 25, 197 (TI-442)
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PD-1.4.003, (Containment Air Temperature), General Instrument Calibration Procedure For Field Devices, Revision 3, Ocfober 197 Calibration performed f.ebruary,-,9, 1976:
(TA-4319, TA-4320)
- Inspector Witnessing of Calibrations The inspector witnessed the performance of selected calibrations, which were conducted during the inspection, to verify performance
... consistent with approved procedures and to verify the impl emen-
- *~\\>tation aspects for the control of test equipmen The following
- activities were reviewed on September 12~13, 1978.
- PD-16.2.003, Channel Functional Test Power Range, Revision 4, July 197 PD-2.6.011 Channel Functional Test Reactor Coolant Flow Loop 3 for IFT-435 Channel II, Revision 1, January 197 PD-16.4.020, Calibration Check Reactivity Computer, Revision 2, December 197 PD-2. 1.070 Channel Calibration Check Reactor Coolant Loop 14 6T/Tave Protection Channel IV, Revision 7, July 197 Each calibration. was performed and data re*corded as required by the procedur Each procedure was adequately detailed to assure performance of a satisfactory surveillanc The inspector had no further questions in this are.
Calibration and Control of Test Equipment a.. The inspector reviewed the calibration and control of test equipment used as standards in the calibration of components.identified in Paragraphs 3 and 4 to verify the following:
Establishment and adherence to calibration schedules; Maintenance of calibration records identifying standards used.which have traceability to the National Bureati of Standards or other independ~nt testing organizations; Proper storage c;i.nd labeling of test equipment; and, Adequate control of test equipment including recordkeepin The following devices were selected as a sampling:
Digital Voltmeter, PD-296, calibration performed April 197 Picoampere Source, PD-86, calibration performed July 1978 *
- Pressure Gauge, PD-103, calibration performed April 197 Dead Weight Tester, PD-342, calibr~tion performed July 197 Digital Voltmeter, PD-249, calibration performed April 197 Pressure Standard, PD-214, calibration performed April 197 During the review of data associated with the Vital Bus and Reactor Coolant Pump undervoltage and underfrequency Reactor Trip calibrations, it was observed that the completed procedures did not indicate serial numbers or other nomenclature for test equipment used during the conduct of the tes However, in four of five cases where a digital voltmeter was used, the licensee rep-resentative was able to identify that a particular meter (by serial number) was used on a specific date associated with the subject calibration procedure. This was accomplished by review of the licensee's test gage "Usage Log.
This log records the procedure and date in which a test gage fs use Based on this log, traceablity of the calibrations to National Bureau of Standards (NBS) could be determine However,.the serial number for the digital voltmeter, used in data acquisition on July 6, 1978 could not be determined and therefore traceability to NBS became questionabl The Mainteance Department representative indicated that perhaps a Performance Department gage was used, and therefore the Maintenance Department's Usage Log would not indicate the use of that gag Further, it was determined that Performance Department does not normally record the usage of test gages for Maintenance Department activities in the Performance Department Usage Log.
The inspector determined that test gage calibrations were traceable to NBS, but in general Maintenance Department test procedures do not provide for recording test gage serial numbers to complete the traceability 11 l i nk1
'. ** :-.,-*The licensee*
representative stated that Maintenance Department test procedures associated with Technical Specifications will be revised to record test gage serial numbers on the completed procedur This is unresolved pending licensee action as stated above and subsequent NRC:RI review.* (272/78-24-02) Technician Qualification The inspector reviewed the qualification records of selected technicians having responsibility for calibration testing of safety related systems and components to verify that the individuals' experience level and training were in accordance with ANSI Nl8. 1, Selection and Training of Nuclear Power Plant Personne No items of noncompliance were identifie.
Faci 1 ity Tour During the inspection a tour was conducted of both the turbine* and auxiliary buildings as well as the service water screen hous Observations of housekeeping and monitoring instrumentation and controls for Technical Specification compliance were performe In addition, control room operations on both day and evening shifts were observe The inspector compared several plant conditions with various Technical Specifications Limiting Conditions of Operation to verify complianc No items of noncomplianc~ were identifie.
Unresolved Items Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items or items of noncomplianc Unresolved items disclosed during the inspection are discussed in paragraphs 3.c and.
Exit Interview The inspector met with licensee representatives (denoted in Paragraph 1) at the conclusion of the inspection on September 15, 197 The purpose, scope and findings of the inspection were summarize Subsequent discussion on inspector findings occurred between Mr. Cont~~Rc:RILand Mr. W. Grau on September 20, 1978.