IR 05000322/1982020
| ML20028B449 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 11/12/1982 |
| From: | Nimitz R, Shanbaky M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20028B443 | List: |
| References | |
| 50-322-82-20, NUDOCS 8211300393 | |
| Download: ML20028B449 (8) | |
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V. S. NUCLEAR REGULATORY COMMISSION Region I Report No. 50-322/82-20 Docket No. 50-322 License No. CPPR-95 Priority
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Category B
Licensee: Long Island Lighting Company 175 East Old Country Road Hicksville, New York 11801 Facility Name: Shoreham Nuclear Power Station Inspection at: Shoreham, New York Inspection conducted: October 12 - 15, 1982 Inspectors:
Q.L. dM llllLlBL R. L. Nimitz, SenioW Radiation Specialist date signed Facilities Radiation Protection Section Approved by:
M.
//[/2 [92 M. ii. Shanbaky, Chief [ Facilities Radiation d' ate ' signed Protection Section
Inspection Summary:
Inspection on October 12 - 15, 1982 (Report No. 50-322/82-20)
Areas Inspected: Routine, announced inspection of the licensee's preoperational testing of: area radiation monitors; process and effluent radiation monitors; and solid, liquid and gaseous waste processing systems. The inspection involved 32 inspector-hours on site by one NRC region-based inspector.
Results: No violations were identified.
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Details 1.
Persons Contacted J. Baron, System Engineer, Stone and Webster, Inc.
M. Miele, Health Physics Engineer
- T. Paulantonio, Lead Start-Up Engineer
- R. Petricek, Engineer - Radiochemistry
- R. Purcell, Lead Start-Up Engineer J. Ricardo, Lead Start-Up Engineer T. Scharton, ANC0 Engineers, Inc.
J. Schmitt, Radiochemistry Engineer
- R. Warner, Operating QA Engineer
- E. Youngling, Start-Up Manager
- J. C. Higgins, Senior Resident Inspector, USNRC
- P. Hannes, Resident Inspector, USNRC
- Denotes those present at the exit interview on October 15, 1982.
The inspector also contacted other licensee personnel during the inspection.
2.
Purpose and Scope of Evaluation The purpose of this inspection was to verify that the licensee has conducted preoperational testing of the solid, liquid and gaseous waste systems to
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verify their operability and that the area radiation and effluent and process monitoring systems have been tested and calibrated.
Licensee test procedures were reviewed for technical adequacy to ensure adequate testing was performed and/or planned to satisfy licensee commitments and regulatory requirements. The implementation of licensee administrative controls for the tests was also reviewed.
3.
Area, Process and Effluent Radiation Monitoring Systems 3.1 Documents Reviewed
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FSAR 3ection 11.4, " Process and Area Radiation Monitoring System" FSAR Section 14, "Inittel Tests and Operations"
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Regulatory Guide 1.68, Revision 0, "Preoperational and Initial Startup Test Programs for Water-Cooled Power Reactors"
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ANSI-N13.10 - 1974, " Specification and Performance of On-Site Instrumentation for Continuously Monitoring Radioactivity in Effluents"
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Shoreham Start-Up Manual
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CS:630.001, " Process Radiation Monitoring Nuclear Measurements
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Corp.," dated January 13, 1982
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CS:630.002, " Radiation Monitoring System, Process and Effluent Radiation Monitors - Main Steam," dated January 16, 1982
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CS:630.003, " Radiation Monitoring System - Reactor Building Refueling Level Ventilation Exhaust System," dated January 16, 1982
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CS:630.004, " Process Radiation Monitoring System - Off-Gas Radiation Steam det Air Ejector," dated January 16, 1982
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CS:630.005, " Process Radiation System - Off-Gas HEPA Filter Discharge Monitor," dated January 16, 1982
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CS:630.006, " Process Radiation Monitoring - Post Accident,"
dated September 10, 1982
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CS:630.007, " Process Radiation Monitoring - Post Accider.t (Containment High Range)," dated September 10, 1982
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PT:630.001, "Preoperational Test Procedure, Radiation Monitor-ing System (Pre-Fuel Load)," dated January 16, 1982
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PT:630.002, "Preoperational Test Procedure, Radiation Monitor-ing System (Post Fuel Load)," dated June 10, 1982
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SP:66.640.04, Rev. 0A, " Calibration Check of ARM Portable Calibration Unit (Draft)"
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SP:66.640.01, Rev. 1, " Calibration (Gar.ra) of GE ARMS"
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SP:66.640.02, Rev. 2, " Calibration (Electronic) of GE ARMS" 3.2 Area Radiation Monitors The review of preoperational testing and calibration of area radiation monitors (ARMS) indicated that the licensee has established and approved check-out/ initial operation and preoperational test procedures for the ARMS.
The review of procedures and discussions with licensee personnel indicated that the licensee had not yet completed ARM check-out and initial operational testing.
In addition, preoperational testing, including calibration, was still outstandin e
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The review of the preoperational test procedures indicated that procedures were not established for calibration of the Nuclear Measurements Corporation (NMC) ARMS and that the procedures for calibration of the General Electrical (GE) ARMS did not provide radiation dose rates at which the monitors were to be tested.
In addition, discussions with licensee personnel indicated that the vendor supplied instrument calibrator, to be used for calibration of the GE ARMS, was capable of providing radiation dose rates which were less than 1/3 of the dose rate range of the ARMS.
Discussions with licensee representatives indicated that procedures were in the process of being revised and established to address the above and that an instrument calibrator, capable of calibrating the higher ranges, would be used for ARM calib.ation.
The discussions also indicated the ARMS were to be calibrated by fuel load. The inspector noted that the licensee's planned action would provide for adequate calibration of the ARMS.
The preoperational testing of ARMS will be reviewed during a subsequent inspection prior to fuel load.
(50-322/82-20-01).
No violations were identified.
3.3 Process and Effluent Monitors The review in this area indicated the licensee has established and approved preoperational test procedures for process and effluent radiation monitors.
Discussions with licensee personnel indicated that NMC process and effluent monitors and associated electronics, needed for calibration, are being sent from the vendor to a national laboratory for calibration.
After calibration, the systems are sent to the site.
Upon installation at the site, the monitors will undergo source checking to ensure the systems have remained in calibration.
The review and discussions with licensee chemistry personnel indicated the calibration methodology was acceptable. The inspector examined the primary calibration data, sensitivity and monitor range for the station ventilation system particulcte and gaseous monitoring channels and for the radwaste liquid discharge monitor.
Excluding the range of the gaseous monitoring channel, the sensitivity and monitor ranges were consistent with FSAR described values.
Licensee chemistry personnel indicated the range of the gaseous monitor was currently being reviewed.
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The review of the status of process and effluent monitor calibra-tions indicated the licensee had not yet completed primary calibra-ton of all monitors and performed all onsite source checks.
The licensee had not yet completed the primary calibration of the GE process.ponitors. These monitors are not sent off-site for calibration.
Discussions with licensee personnel indicated the procedures for testing and calibration of these monitors are being reviewed and revised.
During the review of this area, the licensee's process and effluent monitor test procedures were found to reference vendor and/or national laboratory procedures.
Several of these procedures were not available for inspector review.
Licensee representatives attributed the unavailability of the procedures to the need for off-site revisions necessitated by monitor hardware changes. The procedures were apparently sent to the instrument vendor for review.
Licensee representatives indicated all monitors were to be calibrated by fuel load.
The process and effluent monitor t.esting, calibration, and range determination will be reviewed during a subsequent inspection prior to fuel load.
(50-322/82-20-02).
No violations were identified.
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Ventilation System Testing 4.1 Documents Reviewed
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CG.000.004-5," Instrument and Control Component Checkout and
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Calibration," dated January 23, 1981 i
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CG.000.037, "In-Place Testing of HEPA Filters and Charcoal Adsorber Stage," dated July 30, 1982 l
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ANSI-NS10. 1975, " Testing of Nuclear Air-Cleaning Systems"
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Regulatory Guide 1.08, Revision 0, "Preoperational and Initial Startup Test Programs for Water-Cooled Power Reactors"
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Shoreham Start-Up Manual 4.2 Control Room Ventilation System Testing The review of procedures and discussions with licensee personnel indicated that an instrument and control component checkout was ongoing and that preoperational test procedures for the Control Room Ventilation system were in revision and/or being written.
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The licensee had performed a preliminary housing leak test, but had not yet performed testing of HEPA filters and charcoal absorbers.
Because the licensee has not yet established and/or revised procedures to address all preoperational tests of the Control Room Ventilation System (CRVS), the inspector indicated that Control Room Ventilation System testing will be reviewed during a subsequent inspection prior
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to fuel load.
(50-322/82-20-03).
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4.3 Reactor Building Standby Ventilation System Testing i
The review in this area indicated the licensee has established generic procedures for testing of HEPA filter and charcoal adsorber trains. Generic procedures also have been established for air balance testing.
At the time of this inspection, the testing of this system was just beginning.
On October 14, 1982, the inspector observed preliminary preparations for leak testing of the filter /adsorber housing of the Reactor Building Standby Ventilation System (RBSVS).
This leak test was being performed to verify system integrity following gasket replacement.
ANSI-N510, 1975, specifies in Table 1, Test and Minimum Test Frequency, that housing leak tests be made after completion of initial construc-tion and after any major system modification and/or repair.
Inspector discussions with licensee personnel indicated the filter /
charcoal housing was previously tested after initial construction.
The review of the test preparation in progress indicated that the test was to be conducted per ANSI-N510, 1975; however, no start-up test procedure was established for the test. The test procedure would normally include such items as prerequisites, test objectives, data collection, acceptance criteria, approval, etc.
The above was brought to the attention of licensee start-up test
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personnel who indicated that a procedure would be revised to include provisions for the housing leak test.
The review of the specification of the gasket material used for the replacement indicated it was Quality Assurance Category II.
The RBSVS was noted, however, to be a Category I System. This matter will be followed up to assure that QA requirements are properly satisfied.
(50-322/82-20-04).
The preoperational testing of the RBSVS will be reviewed during a subsequent inspection prior to fuel load.
(50-322/82-20-05).
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Radioactive Waste Systems 5.1 Documents Reviewed FSAR Section 11, " Radioactive Waste Management"
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FSAR Section 14, " Initial Tests and Operations"
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Regulatory Guide 1.68, Revision 0, "Preoperational and Initial Start-Up Test Programs for Water-Cooled Power Reactors"
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Shoreham Start-Up Manual
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C.S. 713.000, " Solid Radwaste Solidification Test," dated July 21, 1982 PT 710.000, " Low Conductivity Liquid Radwaste," dated November
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21, 1980
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PT 711.001, "High Conductivity Liquid Radwaste System," dated July 20, 1982
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PT 716.001, " Recovery Sample Tank, Liquid Radwaste System,"
dated November 25, 1980
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PT 717.001, " Liquid Radwaste System - Discharge Waste Sample Tanks," dated November 28, 1980 5.2 Solid Radwaste The review of solid radioactive waste system testing indicated the check-out and initial operation test (Procedure CS 713.000) was on hold due to the licensee's need to obtain parts for the cement agitator. The licensee anticipates that the parts will be received by mid-November and that the check-out testing will be completed by late November 1982. The preoperational testing of the system was still outstanding.
In reviewing procedure CS 713, the inspector found that the acceptance criteria for solidifying waste did not include verification that the solidified product from the system satisfied all burial site waste solidification criteria (i.e., one gallon of free-standing water).
The licensee's criteria did include the criterion of less than 0.5%
free-standing liquid by waste volume.
Licensee start-up test personnel indicated that the test procedures will be reviewed and appropriate revisions made (50-322/82-20-06).
The preoperational testing of the solid radioactive waste system will be reviewed during a subsequent inspection prior to fuel load (50-322/82-20-c?).
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5.3 Liquid Radwaste The review of liquid radwaste system preoperational testing indicated the licensee has established check-out/ initial operation and preopera-tional test procedures for system testing.
The review of liquid radwaste resin system testing indicated the testing is on hold due to the inability to transfer resin from the phase separator to radwaste. The phase separator is being modified to correct the situation. The licensee plans to revise preoperational test procedures to address the modification.
The preliminary reviews of the completed tests for the low and high conductivity liquid radwaste, liquid radwaste Sample Discharge tanks, and Recovery Sample tanks did not identify any apparent testing deficiencies.
The licensee has not yet completed preoperational testing of all liquid radioactive waste systems.
The preoperational testing of Liquid Radwaste Systems will be reviewed during a subsequent inspection prior to fuel load.
(50-322/82-20-08).
5.4 Gaseous Radwaste The review of gaseous radwaste system test procedures and discussions with licensee personnel indicated the gaseous waste system preopera-tional test procedures had not yet been established and approved.
The preoperational testing of the gaseous waste system will be reviewed in a subsequent inspection prior to fuel load.
(50-322/
82-20-09).
6.
Exit Interview The inspector met with licensee representatives (denoted in Section 1) at the conclusion of the inspection. The inspector summarized the purpose, scope, and findings of the inspection.
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