IR 05000387/1993016
| ML17157C472 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 09/14/1993 |
| From: | Bores R, Jang J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17157C471 | List: |
| References | |
| 50-387-93-16, 50-388-93-16, NUDOCS 9309210020 | |
| Download: ML17157C472 (7) | |
Text
Report Nos.
Docket Nos.
License Nos.
U. S. NUCLEAR REGULATORY COMMISSION
REGION I
50-387/ 3-16 and 50-38 / 3-16 50-387 and 50-388 NPF-14 and NPF-22 Licensee:
Penns Ivania Power and Li ht Com an P&L 2 North Ninth Street Allentown Penns lvania 18101 Facility Name:
Inspection At:
Sus uehanna Steam Electric Station Units 1 & 2 Berwick Penns lvania Inspection Conducted:
Au ut23-27
Inspector:
Jas C. lang, Sr. Radiation Spec
'st E
uents Radiation Protection Section (ERPS)
Facilities Radiological Safety and Safeguards Branch (FRS &SB)
Date Approved by:
robert J..Bor s, Chief, ERPS, FRS&SB, Division of diation Safety and Safeguards I 4/ i Cjg Date
~A<<R:A H fyi p i
fh Ch i
liquid dg I
control programs including: management controls, audit, Offsite Dose Calculation Manual, calibration of effluent/process radiation monitoring systems, air cleaning systems, and implementation of the above programs.
Results:
Within the areas inspected, the licensee maintained excellent effluent control programs.
The responsible individuals in the Chemistry Department had very good knowledge regarding the implementation of the above programs.
No safety concerns or violations of NRC requirements were identified.
9309210020 930914 PDR ADOCK 05000387 Q
DETAILS 1.0 Individuals Contacted 1.1 Licensee Personnel T. Ball, Chemical Engineer, Chemistry R. Breslin, Chemistry Supervisor W. Height, Instructor, Nuclear Training L. Humpf, Assistant Chemistry Foreman, Chemistry D. Kennedy, Assistant Chemistry Foreman, Chemistry P. McGregor, System Engineer, I@C J. Metter, Compliance Engineer R. Prego, Supervisor - Site Quality Verification B. Rhoads, Chemistry Support Supervisor H. Stanley, Vice President - Nuclear Operations R. Takacs, Chemist, Chemistry P. Treier, Assistant Chemistry Foreman, Chemistry G. Yerry, Project Manager, Vent Stack Monitoring Enhancements Project 1.2 NRC Personnel
- S. Barber, Senior Resident Inspector
~ Denotes those present at the exit meeting on August 27, 1993.
Other licensee employees were contacted and interviewed during this inspection.
2.0
~Pu ore The purpose of this inspection was to review the licensee's capability to implement the radioactive liquid and gaseous effluent control programs during normal and emergency operations.
3.0 Mana ement Controls 3.1 Pro ram Chan es The inspector reviewed the organization and administration of the radioactive liquid and gaseous effluent control programs and discussed with the licensee any changes made since the previous inspection conducted in March 1992.
The inspector determined that the organization and administrative control of these programs have not changed since the last inspection.
The Chemistry
Department still has the responsibility to implement the radioactive liquid and gaseous effluent control programs.
3.2 Audit The inspector reviewed the licensee's 1992 NQA/SRC Audit of the Effluent Release Program (Audit ¹: 92-093).
This audit covered following areas.
o Effluent Release Permits o Chemistry Sampling and Analysis o Instrumentation and Monitoring Requirements o Calibration of Measurement Systems o Operability of Waste Systems o Performance - based Observation of Effluent Release o Release Permit - related activities The inspector noted that the audit was performed by qualified auditors, and thoroughly assessed the radioactive liquid and gaseous effluent control programs.
Audit members identified no findings, but 8 observations/recommendations were identified.
However, none of them had a safety significance.
The inspector had no further questions in this area.
3.3 Review of the Semiannual Radioactive Effluent Release Re orts The inspector reviewed the 1992 Semiannual Effluent Release Reports.
The inspector determined that the licensee met the Technical Specification (TS)
reporting requirements.
These reports provided total released radioactivity for liquid and gaseous effluents including projected radiation exposures to the public.
The inspector also reviewed available 1993 effluent release records and determined that these records did not contain anomalous measurements or omissions.
The inspector had no further questions in this area.
4.0 Radioactive Li uid and Ga.eou.
Effluent Control Pro ram The inspector reviewed selected radioactive liquid and gaseous discharge permits and the following procedures as part of the examination of the implementation of the TS and the Offsite Dose Calculation Manual (ODCM) requirements for both unit o SC-069-001, Liquid Radioactive Sampling and Pre-Release Analysis o CH-ON-001, SPING Alarm Response o CH-ON-004, Dose Projections for Discharge of Gaseous Effluents without Treatment o CH-TP-016, Ventilation Exhaust Sampling o CH-TP-107, Containment Atmosphere Sampling o CH-SY-004, Functional Test of Unit 1 & 2 Post Accident Sampling Station o CH-SY-011, Post Accident Vent Stack Sampling System Functional Test The inspector noted that the above effluent control procedures were detailed and well written to allow performance of all necessary steps.
The inspector also deterinined that the reviewed discharge perinits were completed and met the Technical Specification requirements for sampling and analysis frequency, and for lower limits of detection.
As part of the examination of the implementation of the radioactive liquid and gaseous effluent control programs, the inspector reviewed two unusual event reports (Report Nos.92-352 for gaseous effluent and 93-206 for liquid effluent) related to the effluent control programs.
On November 12, 1992, the Chemistry Department (licensee) discovered short-lived activation gases (F-18 and N-13) from the Auxiliary Boiler system.
The presence of N-13 and the absence of activation products, such as Co-60 and Mn-54, indicated that the Auxiliary Boiler contamination occurred via main steam.
The licensee found a leaking valve in the steam flow pathway, from the Steam Jet AirEjector to the Auxiliary Boiler system.
The licensee, therefore, was able to estimate the potential total amount of release of noble gases and projected doses to the public with conservatism.
The projected total body dose at the site boundary was determined to be 2.12E-5 mrad which was insignificant compared to the Technical Specification limit (a quarterly limit of 5 mrad).
On July 9, 1993, the radioactive liquid release (Release Permit No.93-191) from the Evaporator Distillate Tank was isolated due to high radiation alarm.
After the isolation, the licensee took grab samples from the tank to identify the cause of the trip. Analytical sample results prior to the release and after the isolation samples were same.
The licensee investigated other possible causes of the trip, such as the operability of the RMS and residual radioactivity of the water in the pipe left from the previous release.
The licensee determined that the latter case was the cause of trip.
The licensee required flushing of the pipe to prevent recurrence.
The inspector determined that the licensee's investigation processes and the preventive actions were excellent.
The effluent RMS was declared inoperable during the above actions and
the liquid was released in accordance with the Technical Specification requirements (Limiting Condition for Operation).
The inspector noted further that the Chemistry Department personnel conducting the radioactive liquid and gaseous effluent control programs had excellent knowledge in the areas of: (1) dose projection calculation; (2) quantifying the total amount of gaseous effluent release using RMS; (3) protection of the public health and the environment; and (4) ODCM requirements.
Based on the above reviews and discussions with personnel, the inspector determined that the licensee continued to implement excellent radioactive liquid and gaseous effluent'control programs.
The inspector had no further questions in this area.
5.0 Calibration of Effluent/Process Radiation Monitors The inspector reviewed the most recent calibration test results for the following radiation effluent/process monitors to deterinine the implementation of the Technical Specification requirements for both units.
o Liquid Radwaste Effluent Monitor (common)
o Service Water Effluent Monitors o RHR Service Water Radiation Monitors
'
Standby Gas Treatment Vent Monitors (common)
o Reactor Building Vent Noble Gas Monitors (low, mid, and high ranges)
o Turbine Building Vent Noble Gas Monitors (low, mid, and high ranges)
o Cooling Tower Blowdown Flow Device o Control Room Emergency Outdoor AirIntake Radiation Monitor The Chemistry and the INC Departments had the responsibilities to perform radiological and electronic calibrations, respectively, for the above monitors.
During the review of the calibration results, the inspector noted that the radiological calibration technique for the liquid radwaste effluent monitor continued to be excellent.
Radiological calibrations of the liquid radwaste effluent monitor were primary calibrations using a mockup system.
The mockup calibration standards (Cd-109, Cs-137, and Co-60) were traceable to the National Institute of Standards and Technology (NIST). All reviewed calibration results were within the licensee's acceptance criteria.
During the previous inspection conducted in March 1992, the inspector conducted an independent evaluation to assess the reliability of the liquid radwaste effluent monitor.
The inspector compared the RMS calibration results with the measured effluent
sample activity from a number of recent liquid discharge permits.
The results of this independent evaluation were in good agreement and indicated that this liquid radwaste effluent monitor was functioning properly.
During this inspection, the inspector noted that the licensee had developed the comparison method for comparing grab sample measurements and RMS monitored results.
The inspector reviewed the 1993 comparison results and the results were in excellent agreement.
Based on the above review and discussions with the licensee, the inspector determined that the licensee had excellent calibration techniques and implemented these techniques for the above monitors.
6.0 RMS Trainin and Enhancements During this inspection, the inspector evaluated an RMS training program conducted by the Nuclear Training Department through review of the Training Manual (CH-063, SPINGs for Chemistry), interviews with the instructor, and a tour of the training facility. SPINGs (System Particulate Iodine and Noble Gas) are being used to monitor gaseous effluent from vent stacks.
The inspector noted that the Training Manual contained excellent learning objectives and training sequences.
This training requires 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> in class and a test upon completion of the training (passing grade: 70% or better).
The training facility was equipped with an actual SPING.
After this training, chemistry technicians received on-the-job training for calibrations and functional tests for the SPING.
Appropriate individuals from the Operations and I&C Departments take similar training as the Chemistry Department personnel.
Licensee management recognized that improvements are needed for several areas of the SPINGs (routine effluent and emergency monitoring systems) for the better reliability and operability.
The licensee established the project, "Vent Stack Monitoring Enhancements Project."
This project contained (1) develop scope and estimate, (2) design system, (3) procurement, (4) installation -dependent on plant CPU replacement, and (5) SPING/PASS upgrade.
The inspector attended the project initial meeting.
The inspector noted that the meeting was executed in an excellent and professional manner, and the meeting results were productive.
Based on the above reviews and discussions with the licensee, the inspector determined that the licensee had an excellent SPING training program and enhancement project.
7.0 Air Cleanin S stems The inspector reviewed the licensee's most recent surveillance test results to
determine the implementation of the Technical Specification requirements.
The test results for the (1) control room emergency outside air supply system and (2) standby gas treatment system were reviewed.
For the above systems, the inspector reviewed the results of the following inspections and tests.
o Visual Inspection o In-Place HEPA Leak Tests o In-Place Charcoal Leak Tests o System AirFlow Rate Tests o Pressure Drop Tests o Laboratory Tests for the Iodine Collection Efficiencies Based on the above reviews, the inspector noted that the licensee performed these surveillance tests more frequently than Technical Specification requirements and also met Technical Specification acceptance criteria.
The inspector also reviewed the licensee's following surveillance tests performed on the Control Room Emergency Outdoor Air Supply Subsystem Operability Test.
o Pressure Difference at Operating Air Flow Rate o High Chlorine Trip Test o High Radiation Trip Test o Reactor Building Isolation Test o Heater Dissipate Test All test results were within the licensee's acceptance criteria. The inspector had no further questions in this area.
8.0 Exit Interview The inspector met with the licensee representatives denoted in Section 1.1 of this inspection report at the conclusion of the inspection on August 27, 1993.
The inspector summarized the purpose, scope, and findings of the inspection.
The licensee acknowledged the inspection findings.