IR 05000423/1986030
| ML20215E008 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 09/30/1986 |
| From: | Jonson J, Prell J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20215E007 | List: |
| References | |
| 50-423-86-30, NUDOCS 8610140389 | |
| Download: ML20215E008 (5) | |
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U.S. NUCLEAR REGULATORY COMMISSION
REGION I
Report No.
50-423/86-30 Docket No.
50-423 License No.
NPF-49 Licensee:
Northeast Nuclear Energy Co.
PO Box 270 Hartford, Connecticut 06141-0270 Facility Name: Millstone Nuclear Power Station Unit 3
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't Inspection At: Waterford Connecticut Inspection Conducted:
September 8-12, 1986 Inspectors:
evnt/4 1/al,/B/,
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s Prell, Reactor Engineer datW
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Approved by:
b 4,k 7/38/ 8's Jon 06hnson, Whief date Operational Programs Section, 08, DRS Inspection Summary:
Routine Unannounced Inspection on September 8-12, 1986, (Report Number 50-423/86-30)
Areas Inspected: Surveillance Testing and Calibration Control Program for the I&C, Production Test, and Operations Departments.
Results: No violations were identified.
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DETAILS 1.0 Persons Contacted Northeast Utilities K. Burton Operations Supervisor J. Crockett MP-3 Unit Superintendent
- R.
Enoch I&C Supervisor
- J. Harris Engineering Supervisor
- M. Hornyak Operations Quality Assurance Auditor
- J.
LaWare Operations Quality Assurance Auditor D. Moore Assistant Operations Supervisor G. Patterson Production Test Supervisor M. Pearson Assistant Operations Supervisor T. Rogers I&C Planner B. Williams Production Test Coordinator U.S. Nuclear Regulatory Commission l
- F. Casella Resident Inspector
- T. Shedlosky Senior Resident Inspector
- Denotes those present at the exit meeting on September 12, 1986. The inspector also interviewed other personnel during this inspection period.
2.0 Surveillance Testing and Calibration Control Program The Instrumentation and Ccr.trel (I&C) Department, Production Test (PT)
Department, and Plant Operations (OPS) Department program for surveillance testing and calibration were reviewed for conformance with regulatory requirements.
2.1 References The following references were used:
Millstone Nuclear Power Station-Unit 3
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Technical Specification, Sections 4 and 6; Regulatory Guide 1.33, November 1972, Quality Assurance Program
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Rcquirements; ANSI 18.7 - 1976, Administrative Controls and Quality Assurance of
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the Operational Phase of Nuclear Power Plants; 10 CFR 50.55a(g) - Inservice inspection requirements.
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2.2 Program Review A review of administrative procedures, surveillance / calibration procedures, and the master surveillance schedule was made to determine:
that the requirements and commitments identified in section 2.1 above
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were met; that a master surveillance schedule and administrative control
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system has been established which identifies the frequency of each test, calibration, or inspection, the responsible group for performing each surveillance, and the status of each surveillance test; that responsibility has been assigned for maintaining the master
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surveillance schedule up to date;
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that procedures, written to an approved format, exist for conducting each surveillance or calibration; that responsibilities have been assigned for reviewing and evaluating
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the results of surveillance or calibration data; and, that calibration requirements have been established and maintained
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for equipment associated with safety related systems but which are not specified in Technical Specifications as requiring calibration.
(This was done by identifying eleven Technical Specification related instruments and verifying they were included in the licensee's recalibration program).
The following procedures were reviewed:
ACP-QA-9.02, Rev. 15, Station Surveillance Program
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QA-9.03, Rev. 5, Inservice Plant Testing
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SP-3610A.2, Rev. O, Residual Heat Removal Pump 3RHS*PIB Operational
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Readiness Test
OP-32098, Rev. O, Shutdown Margin
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A0P-3552, Rev. 0, Malfunction of the Rod Drive System
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SP-3670.1, Rev., Control Room Surveillances
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OP-3201, Rev. 1, Plant Heatup
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SP-3443 C21, Rev.
1, Protection Set Cabinet 3 Operational Test
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IC-3408A02, Rev. 1, Non Tech Spec Instruments with Licensing
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Requirements SP-3447C01, Rev. 1, Hydrogen Monitor Train A Channel Calibration
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SP-3447L01, Rev., Hydrogen Recombiner Instrumentation
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SP-3626.7, Rev. O, Service Water Pump 3WP*PID Operational Readiness Test PT-31400A, Rev. 2, Test Equipment Calibration Program
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PT-314000, Rev. 1, Protective Relay Calibration Program
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PT-314000, Rev. 1, Calibration Program for Timeing Devices
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PT-31400E, Rev. 1, Panel Meter and Transducer Calibration Program
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In addition, the inspector verified that event oriented surveillances are
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identified to the operators in either operating, abnormal operating, or I
emergency operating procedures; that periodic surveillances with a testing interval of a week or less are identified in weekly rounds and are being properly administered; and that periodic surveillances with a testing interval longer than a week are being identified, controlled and properly administered.
The inspector reviewed the following completed surveillances:
SP3601F.5-1 Cold Shutdown Check Valve Stroking
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SP3604A.6-2 Charging Pump Inoperability Verification SP3601C.1-1 Borated Water Source and Flow Verification
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SP3606.6-1 Containment Recirculation Spray System Train B Monthly Valve Lineup Check SP36010.1-1 Reactor Coolant Pump Operability Check
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SP3601F.4-2 Reactor Coolant System Pressure Isolation Valve Test
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The following surveillance tests were also witnessed by the inspector:
Residual Heat Removal Pump Operational Readiness Test
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Operational Test of Protection Set Cabinet Number 3, and Service Water Pumps Operational Readiness Test
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2.3 Findings No violations or unresolved items were identifie.
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3.0 QA/QC Interface The Operations Quality Assurance Group (0QA) conducted an audit between June 6 and August 26, 1986 of MP-3 implementation of the surveillance-testing program. The final audit report was in draft form.
In discussions with the lead auditor for this audit it was disclosed that the audit identified three findings and three unresolved issues. The three findings were all related to lack of adequate procedures but did not signify a programmatic breakdown due to the extensive number of procedures reviewed.
4.0 Plant Tours The inspector made several tours of the facility during the course of the inspection. This included tours of the control building, auxiliary building, and water intake structure. A review of the work in progress, security, cleanliness, and housekeeping was made and found acceptable.
5.0 Exit Interview An exit meeting was held on September 12, 1986 to discuss the inspection scope and findings, as detailed in this report (see paragraph 1.0 for attendees).
At no time was written material given to the licensee. The inspector determined that no proprietary information was utilized during this inspection.