IR 05000245/1979027
| ML19305B152 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 01/10/1980 |
| From: | Baunack W, Blumberg N NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19305B127 | List: |
| References | |
| 50-245-79-27, NUDOCS 8003190234 | |
| Download: ML19305B152 (11) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No. 50-245/79-27 Docket No. 50-245 License No. DPR-21-Priority Category C
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Licensee:
Northeast Nuclear Energy Company P. O. Box 270 Hartford, Connecticut 06101 Facility Name: Millstone Nuclear Power Station, Unit 1 Inspection at: Waterford, Connecticut Inspection conducted: November 27-30, 1979
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O Inspectors:
N. Blumbergf, Reactor spector
'date signed
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date signed date signed Approved by'
/ /0 fo hW. Baunack, Acting Chief, Nuclear Support
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Section 2, RO&NS Branch Inspection Summary:
Inspection on November 27-30, 1979 (Report No. 50-245/79-27)
Areas Inspected:
Routine, unannounced inspection by a regional based inspector of licensee action on previous inspection findings; administrative control of safety related calibrations; surveillance calibrations of safety related components and equipment required by Technical Specifications; calibrations required by Technical Specifications of components and equipment associated with safety related systems and/or functions; calibration and control of test equipment; witnessing of calibrations; technician qualifications; and, control room tour.
This inspection involved 30 inspector-hours on site by one NRC regional based-inspector.
Results: Of the nine areas inspected, no items of noncompliance were found in eight areas, and one item of noncompliance was found in one area (Deficiency -
failure to establish surveillance procedures; failure to document temporary changes; and, failure to adhere to surveillance frequencies, Paragraphs 4.c (1),
(2),and(3)).
Region I Form 12 (Rev. April 77)
8008190 AM
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DETAILS 1.
Persons Contacted P. Callaghan, Maintenance Supervisor, Unit 1
- R. Herbert, Superintendent, Unit 1 V. Jones, Chemistry Foreman, Unit 1 R. King, Instrument Specialist, Unit 1-R. Liskiewicz, Instrument and Control Foreman, Unit 1 V. Papadopoli, Quality Assurance Supervisor
- W. Romberg, Operations Supervisor, Unit 1 C. Shine, Shift Supervisor, Unit 1 D. Stump, Health Physics Technician
- F. Teeple, Instrument and Control Supervisor, Unit 1 USNRC
- T. Shedlosky, Resident Reactor Inspector The inspector also interviewed other licensee employees, including members of the quality assurance staff, instrument and control technicians, reactor
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operators, and clerical personnel
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2.
Licensee Action on Previous Inscection Findings (Closed) Unresolved Item (245/79-05-01): Provide modification to crossconnect service water and emergency service water; and prepare an emergency procedure to cover actions upon loss of service water.
The licensee stated that the crossconnect modification has been completed and the inspector verified that OP 322, " Emergency Service Water," was revised on July _17, 1979, to provide a procedure for crossconnecting emergency service water to the service water system.
(0 pen) Unresolved Item (245/78-34-03):
TS Table 3.7.1 lists wrong positions for valves IC-3, IC-4, and CU-5; does not li:t valves FSD-9-75 A-D; and surveillance TS 4.7.D.l.c not accomplished for valve FSD9-75 A-8.
The licensee stated that valves FSD-9-75 A-D cannot be verified as required by TS 4.7.D.l.c as these valves are solenoid operated and position indication does not provide positive verification of actual valve position; and that an engineering study is necessary to determine whether or not these valves should be modified.
This engineering study has taken lower priority to other engineering items.
The licensee also stated that the positions for valves in Table 3.7.1 IC-3, IC-4, and CU-5 were obvious typographical
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errors and a TS change request would be submitted just for this. A TS change request concernino the entire item would be submitted at completion of.the engineering evaluation and modification of valves FSD-9-75 A-0, if determined to be necessary. This item remains open.
3.
Administrative' Control of Safety Related Calibrations The inspector reviewed the licensee's administrative procedures relating to the performance of calibration of safety related components as a basis for reviewing test procedures and calibration data sheets. The following procedures were reviewed:
ICA 700A, Calibration of Instruments Used to Satisfy Technical Specifi-
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cation _ Requirements and/or Ccmputer Core Performance Inputs, Revision 2, Feburary 22, 1979; ACP-QA-3.02, Station Procedures and Forms, Revision 10, October 24,
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1979; ACP-QA-9.02, Plant Surveillance Program, Revision 1, November 13,
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1978; and, ACP-QA-9.04, Control and Calibration of Measuring and Test Equipment,
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Revision 5, October 12, 1979.
No items of noncompliance were identified.
4.
Surveillance Calibrations for Safety Related Comoonents and Equipment Required by Technical Snecifications a.
The inspector reviewed calibration procedures and associated data sheets on a sampling basis to verify the following:
Calibration frequency requirements have been met;
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Applicable system status during component calibracion was in
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conformance with the Technical Specification limiting conditions of operation; Procedure format provided detailed stepwise instructions;
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Procedure review and approval were as required by Technical
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Specifications-
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4 Trip points of calibrated components were in conformance with
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Technical Specification requirements; and, i
Technical content of procedures was sufficient to result in
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satisfactory calibration.
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b.
The following calibration procedures / data were selected for the above review:
HP 912, Area Radiation Monitor (ARM) Calibration, Revision 7,
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July 29, 1979. Data were reviewed for calibrations performed September 14 and 28,1979; June 20,1979, and March 10, 1979.
(Accomplishes TS 4.5.E.1.d, Quarterly Calibration of Isolation Condenser Vent Line Radiation Monitors.)
SP 412H, Core Spray Header Differential Pressure Switch Functional
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and Calibration Test, Revision 1, March 13, 1979.
Data were reviewed for calibration performed November 5, 1979, August 6, 1979, May 10, 1979, April 10, 1979, and March 7, 1979.
(Accom-plishes TS 4.5.A.l.e, Quarterly Calibration of Core Spray Header Differential Pressure.)
IC-400A-12, Suppression Chamber Level Calibration (Data Sheet),
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Revision 1, January 11, 1979.
Data reviewed for calibrations performed January 4, 1979, August 18, 1978, and September 6, i
1977.
(Accomplishes TS 4.7.A.1.c, Semi-annual Calibration of
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Suppression Chamber Water Level Instrumentation.)
SP 411D, Pressure Suppression Chamber - Reactor Building Vacuum
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Breaker Associated Instrument Functional Test, Revision 2, March 9, 1979.
Data reviewed for calibrations performed September 7, 1979, June 18, 1979, March 7, 1979, and December 7, 1978.
(Accom-plishes TS 4.7.A.4.a Quarterly Test of Suppression Chamber to Reactor Building Vacuum Breaker Setpoint.)
SP 412L, Isolation Condenser Isolation Instrument Functional and
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Calibration, Revision 0, October 27, 1977.
Data reviewed for calibrations performed November 14, 1979, October 17,1979, and September 18, 1979.
(Accomplishes TS Table 4.2.1, Quarterly Calibration of Isolation Condenser Condensate Hight Flow Setpoint.)
SP 404B, Average Power Range Monitor Functional Test, Revision 0,
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March 14, 1977.
Data reviewed for calibrations performed October 27, 1979, October 1,1979, September 5,1979, and August 27, 1979.
(Accomplishes TS Table 4.1.1, Monthly Test of APRM Flow Biased High Flux Setpoint.)
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SP 408J, Condenser Low Vacuum Scram Functional and Calibration Test, Revision 1, December 7,1978.
Data reviewed for calibrations performed November 7,1979, October 27, 1979, September 5,1979, and August 7,1979.
(Accomplishes TS Table 4.1.2, Monthly Test of Condenser Low Vacuum Setpoint.)
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SP 411F, Drywell Torus D/P Instrument Calibration, Revision 0, August 8, 1979.
Data reviewed for calibration performed on November 27,1979 (new instrument installed August, 1979).
(Accomplishes TS 4.7. A.2.c, Semi-annual Functional Test of Torus to Drywell Different Pressure Setpoint.)
c.
Findings (1)
During review of surveillance calibrations required by the Technical Specifications, the inspector observed that the licensee had not established procedures for the following surveillances:
Calibration of suppression chamber level instruments as
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required by TS 4.7.A.l.c or d is being accomplished by
- use of data sheet IC-400A-12 and generic calibration procedure IC-400A, rather than use of a specific calibration procedure for this surveillance.
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Functional tests of four heat detectors in the diesel generator room as required by Technical Specifications 4.12.B.l.b.l.a, 4.12.E.1, and Table 3.12.2 appear not to be accomplished by use of a plant procedure.
During the inspection the licensee was unable to provide documentation that the heat detectors in the diesel generator room had ever been functionally tested but stated that such testing was accomplished by the fire insurance company's inspector.
Subsequent to the l
inspection, the licensee was able to provide documenation that fire detectors in the diesel generator room were being functionally tested on an annual basis by the
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fire insurance in system.
(See related unresolved item in Paragraph 4.c(4) below).
Prior to August,1979, calibration of pressure instruments
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used for drywell to torus differential pressure as required by Technical Specification 4.7. A.2.b or c was accomplished by use of data sheet IC-400A-45 and generic calibration procedure IC-400A.
Since installation of an actual drywell to torus differential pressure instrument, this instrument is being calibrated by procedure SP 411F.
Hence, this example has been corrected by the licensee, i
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.(2) The:"as left" temperature setpoint for the ' standby liquid
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. congrol system was recorded on Data Sheet IC-400A-3, as
"99 F" on July 16,-1979, with a pen and ink notation "*-set
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as pe5 operations." The data sheet specifies the setpoint
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as 90 + 1.5 F.
This change was not documented using the.
. Station ~' Procedure' Change Form, SF-302.
The licensee stated that the need for a temporary change was. overlooked by I&C personnel and the Data Sheet IC-400A-3 would be revised to
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reflect the new setpoint.
The actual change in setpoint was
to a more conservative value.
A' pen and ink change was made to the water pressure test inputs on Data Sheet IC-400A-2 for standby liquid control tank level instrument calibration performed on July 10,
t 1979.
This change was not documented using the Station Procedure. Change Form, SF-302; however, a subsequent reivsion to this data sheet was issued on July 11, 1979.
-(3) Technical Specification 4.12.E.1 -" tires a semi-annual functional test of fire detection
.ruments listed in
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Technical Specification Table 3.12...
Fire detectors in the hydrogen seal oil unit day tank room were being functionally tested annually per procedure SP 680I as required by Technical Specification 4.12.B.1.b.1.a.
SP 680I was last accomplished on April 28, 1978 and June 5, 1979, an interval in excess of six months required by Technical Specification 4.12.E.1.
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noted in paragrahp 4.c.(1) above, Fire detectors in the
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- diesel generator room were being functionally tested annually rather than semi-annually. ' According to the data provided by the fire insurance company, these detectors were last
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calibrated on June 6,1979 and May 8,1978.
Refer to paragraph 4.C(4) for related discrepancy.
r Technical Specification 4.7. A.1.c requires that the suppression chamber water level instrumentation be calibrated every six months.
These instruments were last calibrated on January
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5,1979 and September 17, 1979. This interval is in excess of six. months plus 25 percent.
l Failure to establish procedures for surveillance tests, to document temporary changes, to perfonn surveillance tests
within Technical Specification time intervals is contrary to Techncial Specifications 6.8.1, 6.8.3, and 1.Z.a and collectively
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- constitutes a deficiency level item of noncompliance (50-245/79-27-01).
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(4) Technical Speci?fcation 4.12.E.1 states that the fire detectors listed in TS Table 3.12.2 shall be functionally checked every six months by injecting a simulated electrical signal into the measurement channel rather than the instrument.
The inspector noted that virtually all the fire detector functional tests were being accomplished by applying heat directly to the detectors.
The licensee stated that almost all of the detectors were rate of rise heat detectors and an electrical siral could not be injected as specified in the Technical Specification.
The licensee had issued a Technical Specification Change request on October 5,1979, requesting that the method of doing the functional tests may be optional.
This item is unresolved pending resolution to the licensee's change request and subsequent NRC:RI review (50-245/79-27-02).
(5) ACP-QA-3.02, Station Procedures and Forms, states that surveillance data sheets, when used, shall contain "as found" and "as left" test data.
Data sheets for surveillance procedure HP 912, " Area Radiation Monitor (ARM) Calibration,"
did not provide for recording "as found" data.
The licensee stated that HP 912 would be revised to provide for recording of "as found" data.
This item is unresolved pending licensee action and subsequent NRC:RI review (50-245/79-27-03).
(6)
Procedure IC-414A, " Control Rod Drive Module Instrument Calibration," has not received a PORC review.
This procedure is within the scope of Technical Specification 6.8.1 and Regulatory Guide 1.33, Appendix A as a procedure which would require PORC review.
The licensee stated action would be taken to 'obtain PORC review for this procedure.
This item is unresolved pending licensee action and subsequent NRC:RI review (50-245/79-27-04).
5.
Calibrations Required by Technical Specifications of Components ara Equipment Associated with Safety Related Systems and/or Functions The inspector reviewed, on a sampling basis, the program established a.
for calibration of components associated with safety related systems required by ANSI 18.7-1972.
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 Technical Specifications.
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The following were verified:
Specific requirements have been established for the above calibra-
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tions including schedules and frequencies; Procedures have been reviewed and approved in accordance with the
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Technical Specifications, contain acceptance criteria consistent with the Technical Specifications, and contain detailed instructions commensurate with the complexity of the calibration; and, Technical content of procedures are adequate to perform a satis-
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factory calibration.
b.
The following components identified in facility surveillance test procedures were selected at random and the specific requirements established for their calibration were verified:
Data Sheet IC-400A-36, Reactor Circulation Loops A and B Temperature
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Calibration to Computer, Revision 1, April 27,1978.
Calibrates temperature elements TE-261-A through F.
Data reviewed for calibrations. performed on May 21, 1979 and April 9, 1978.
Data Sheet IC-400A-14, Isolation Condenser Temperature and Level
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Calibration, Revisicn 1, July 25,1979.
Calibrates shell side temperature recorder TR-340-4.
Data reviewed for calibration performed on July 11, 1979, August 11, 1978, and September 9, 1977.
Data Sheet IC-400A-24, Reactor Recirculation Jet Pump Flow Calibra-
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tion, Revision 0, March 8, 1978.
Calibrates FT-263-64 A-W, FTA-
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263-74 A-2, and FI-263-78 A-W.
Data reviewed for calibration performed on November 22, 1978.
ICA-400A-18, Reactor Water Cleanup Conductivity Calibration,
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Revision 0, March 1, 1978.
Calibrates CR-1290-3 and CR-1200-3 alarm switches.
Data reviewed for calibration accomplished on March 5, 1979.
Data Sheet IC-400A-13, Drywell Temperature Recorder, Revision 1,
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September 19, 1979.
Calibrates TR-1602-5 and TR-1602-5 (alarm switches).
Data reviewed for calibrations accomplished on September 13, 1979 and November 20, 1978.
i Data Sheet IC-400A-38, Fire Water Tank A and B Level Calibration,
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Revision 0, March 7, 1978.
Calibrates LI-7-56 and 57, LSH-7-56A
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and 57A, and LSL-7-56B and 578.
Data reviewed for calibration accomplished on June 19, 1979.
- IC-414A, Control Rod Drive Module Instrument Calibration, Revision
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0, February 28, 1978.
Calibrates rod control accumulator level alarms.
Data reviewed for calibrations accomplished on February 20, 1979, August 7, 1978 and October 24, 1979.
L Data Sheet IC-400A-3, Standby Liquid Control Temperature Calibration,
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Revision 1, August 16, 1978. Calibrates TS-ll55, TIC-ll54, and TI-1160. Data reviewed for calibrations accomplished on July 10, 1979 and June 19, 1978.
Data Sheet IC-400A-2, Standby Liquid Control Tank Level Calibration,
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Revision 1, July 11,1979.
Calibrates LT-ll53, LI-ll40-2, and LI-1140-4. Data reviewed for calibrations accomplished on July 10, 1979 and June 15, 1978.
Data Sheet IC-400A-16, Reactor Vessel and Head Flange - Shell
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Temperature Calibration, Revision 1, February 15, 1979. Calibrates TR-263-104 and 105 for reactor vessel shell temperature, reactor vessel shell flange temperature, and reactor vessel shell adjacent to shell flange temperature. Data reviewed for calibration accomplished on January 18, 1979 and August, 1978.
CP 801/2801Q, pH Meter, Balsbaugh (calibration), Revision 0,
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January 26, 1979. Meter calibrated weekly or more frequently.
CP 801/2801K, Orion pH Meter, Revision 1, January 26, 1979.
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Meter calibrated weekly or more frequently.
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Calibration of instruments used for monthly quality test of diesel generator and gas turbine fuel oil.
Fuel checks done by an outside laboratory and instrument calibrations are not available.
No items of noncompliance were identified.
6.
Cali' ation and Control of Test Equipment The inspector reviewed the calibration and control of five pieces of test equipment used as standards in the calibration of components identified in Paragraph 4.
Results of the review indicated measuring and test equipment are being maintained as required by administrative procedure.
Items verified included:
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Establishment and maintenance of a master test equipment list;
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Establishment and adherence to a calibration schedule;
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Maintenance of calibration records identifying standards used which
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have traceability to the National Bureau of Standards or other testing organization; Test equipment custody control records; and,
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Storage and labeling of test equipment.
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No items of noncompliance were identified.
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Inspector Witnessing of Calibration On November 27, 1979, the inspector witnessed the performance of SP 411F, Drywell Torus D/P Instrument Calibration.
This instrument is a newly installed and this was the first in place calibration since initial instal-lation.
The calibration was performed and data recorded as required by the procedure.
The procedure was adequately detailed to assure performance of a satisfactory surveillance. The procedure contained a typographical error and acceptance criteria for DPT-1605-1 A was given as + 5% rather than + 0.5%.
The data recorded was within + 5% but outside tee + 0.5%.
This error was not dis-covered during performance of the calibration but was noted during data review by a supervisor.
The test data was not accepted; the calibration was reaccomplished on November 29, 1979, and appropriate adjustments made.
No items of noncompliance were identified.
8.
Technician Qualifications The inspector reviewed the qualification records of three currently assigned technicians having responsibility for calibration testing of safety related systems and components. This review was performed to verify that the individuals experience level and training were in accordance with ANSI N18.1, " Selection and Training of Nuclear Power Plant Personnel."
No items of noncompliance were identifie._
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Control Room Tour 1.
The inspector observed control room operations on day shift for control room manning and facility operation in.accordance with Administrative and Technical Specification requirements.
No items of noncompliance were -identified.
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Unresolved Items Unresolved items are matters about which more information is required in
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order to ascertain whether they are acceptable items or items of noncompliance.
' Unresolved items identified during this inspection. are discussed in Paragraphs 4.c.(4),(5)and(6).
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Exit' Interview The inspector met with licensee representatives (denoted in Paragraph 1) at the conclusion of the inspection on November 30, 1979.
A subsequent telephone discussion concerning inspection findings was held between Mr. W. Romberg
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and Mr. N. Blumberg on December 3,1979.
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