IR 05000456/1986054
| ML20215M553 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 10/27/1986 |
| From: | Grant W, Greger L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20215M548 | List: |
| References | |
| TASK-2.F.1, TASK-TM 50-456-86-54, 50-457-86-41, NUDOCS 8611030017 | |
| Download: ML20215M553 (6) | |
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U.S. NUCLEAR REGULATORY COMMISSION
REGION III
Reports No. 50-456/86054(DRSS); 50-457/86041(DRSS)
Docket Nos. 50-456; 50-457 Licenses No. CPPR-132; CPPR-133 Licensee: Commonwealth Edison Company Post Office Box 767 Chicago, IL 60690 Facility Name: Braidwood Station, Units 1 and 2 Inspection At: Braidwood Site, Braidwood, Illinois Inspection Conducted: October 6-8, 1986
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W. B. Grant 10 / 2 3 04te
/0b7/8(o Approved By:
L. R. Greger Chief
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Facilities Radiation Protection Section Date Inspection Summary Inspection on October 6-8, 1986 (Reports No. 50-456/86054(DRSS);
No. 50-457/86041(DRSS))
Areas Inspected: Routine unannounced inspection of the preoperational radiation protection progrcm for Units 1 and 2, including: training and qualifications; external occupational exposure control; facilities and equipment; ALARA activities; and status of certain TMI action plan items.
Results: No violations or deviat'ons were identified.
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DETAILS 1.
Persons Contacted
- R. Aker, Radiation Chemistry Supervisor J. Anspaugh, Health Physicist, Group Leader
- L. Davis, Assistant Superintendent, Technical Services J. Petro, Radwaste Coordinator
- H. Pontious, Regulatory Assurance D. Shamlin. Lead Foreman
- Denotes those present at the entrance / exit meeting.
2.
General This inspection, which began at 8:45 a.m. on October 6, 1986, was conducted to examine aspects of the preoperational radiation protection program, licensee action on previous inspection findings and status of certain TMI action plan items.
3.
Licensee Action on Previous Inspection Items (Closed) Open Item (456/86002-04):
Calibration and testing of ARM /PRM's need to be completed. Unit 1 ARM /PRMs and those common to both units have been tested and calibrated.
See Section 8.
(Closed) Open Item (456/86002-08):
Complete installation, procedures, and training or use of post-accident noble gas effluent monitors per NUREG-0737 Item IIF.1.1.
Calibration and testing of these monitors has been completed.
Procedures have been written and RCTs have been trained on the use of the procedures.
See Section 11.
(Closed) Open Item (456/86002-10):
Complete installation, calibration, procedures and training on use of containment high-range radiation monitors per NUREG-0737 Item IIF.1.3.
High range containment monitors have been installed and calibrated, procedures have been written and training on the use of the monitors has been completed. See Section 12.
4.
Training and Qualifications This inspector reviewed the training and qualifications aspects of the licensee's radiation protection, radwaste, and transportation programs, including:
training responsibilities, policies, goals, programs and methods; qualifications of radiation protection personnel; and the adequacy of the training for employees, contractors and visitors.
Also reviewed were management techniques used to implement these programs and the licensee's completion of FSAR and other commitments.
The inspector reviewed the following new procedures. RCTs have recently completed training in these procedures and are completing a walkdown of all process and area radiation monitors to determine exact location in the event alarm response is required.
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BWRP 1280-2, Revision 0, Response to High Radiation Monitor Alarms.
BWRP 1280-3, Revision 0, Process Radiation Monitor Gas Grab Sampling.
BWRP 1280-5, Revision 0, Area Radiation Monitoring System Alert /High Alarm Setpoints.
BWRP 1280-8, Revision 0, Process Radiation Monitor Liquid Grab Sampling.
BWRP 1280-9, Revision 0, Process Radiation Monitor Particulate Filter and Iodine Cartridge Replacement.
BWRP 1280-15, Revision 0, Tritium Grab Sampling from General Atomic Process Radiation Monitors.
No violatio6: or deviations were identified.
5.
External Exposure Control and Personal Dosimetry The inspector reviewed the licensee's external exposure control and personal dosimetry programs, including:
adequacy of facilities, equipment, personnel and procedures; adeouacy of the dosimetry program to meet routine and emergency needs; and completion of requirements and FSAR commitments.
The licensee currently uses a vendor supplied film badge for personal dosimetry. An in house TLD system is scheduled to be operational for CECO station operating personnel about November 1, 1986. The TLD system has had some operational equipment problems which have apparently been corrected.
No problems were noted.
The only items remaining open in this area are construction of the onsite TLD calibration facility and completion of the RWP/ dosimetry issue facility.
6.
Respiratory Protection Program The inspector reviewed the licensee's respiratory protection program to determine whether it is consistent with the requirements of the FSAR, 10 CFR 20.103, and Regulatory Guide 8.15, the inspector noted that procedures had been implemented, that an adequate supply of respirators had been procured, and that a fit testing program had been implemented.
In a letter to NRC Region III dated September 23, 1986, the licensee informed the NRC of their intention to implement a respiratory protection program under the provision of 10 CFR 20.103 prior to initial criticality which is expected to take place about November 30, 1986. This notification satisfies the requirements of 10 CFR 20.103(g).
The respirator issue, cleaning, and storage facility is being constructed on the 426' level of the Auxiliary Building.
The adequacy of this facility will be reviewed during future inspections (456/86002-03; 457/86002-03).
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7.
Radiation Protection Procedures The inspector reviewed the following new radiation protection procedures to determine if they are consistent with 10 CFR requirements, FSAR commitments, and good health physics practices. No problems were noted.
BWRP 1340-3, Revision 0, Routine Operation of Permenent Fastscan WBC BWRP 1750-1, Revision 0, Determination of Compliance with 10 CFR 20 Liquid Release Limits BWRP 1750-2, Revision 0, Determination of Compliance with 10 CFR 20 Airborne Release Limits BWRP 1750-3, Revision 0, Determination of Compliance with 10 CFR 20, Appendix I, Design Objectives for Liquid Releases BWRP 1750-4, Revision 0, Determination of Compliance with 10 CFR 20, Appendix I, Design Objectives for Gaseous Releases 8.
Facilities and Equipment The inspector reviewed the facilities and equipment used by the licensee for radiation protection activities to determine whether they are described in the FSAR and are adequate to support the radiation protection program.
The licensee has completed calibration of ARM /PRMs for Unit 1 and those common to both units required by fuel load. According to the licensee
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the 83 monitors required by fuel load have been calibrated and are operational. Records of calibration were selectively reviewed; no problems were noted.
Items remaining to be completed in this area include completion of the health physics instrument storage room and completion of the tool and equipment decon and storage facility.
9.
Maintaining occupational Exposures ALARA The inspector reviewed the licensee's program for maintaining occupational exposures ALARA, including:
established formal ALARA policy and procedures and worker awareness of the ALARA program.
A corporate assessment of the Braidwood ALARA Program was conducted in April 1986. The ALARA assessment reviewed ALARA procedures, awareness, Radiation Evaluation Program (REP), photofile, area contamination control, training, and plant knowledge. The assessment report included summaries of ALARA strengths and improvement items. The licensee has made satisfactory progress in resolving the improvement items.
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The licensee has contracted a vendor to complete a photofile of plant systems to be indexed and stored on a laser disc for use in maintenance / repair activities.
Items remaining to be completed are the plant photofile, an ALARA awareness program implementation, and ALARA training for health physics foreman and shift qualified RCTs.
10. NUREG-0737 Item II.F.1.1, High Range Noble Gas Effluent Monitors Section E.30.1 of Apper. dix E to the FSAR describes the post-accident high range noble gas effluent monitoring system. The system consists of a General Atomic Wide Range Gas Monitor (GA WRGM) for the auxiliary building vent and area monitors (compensated for loss of low energy gamma radiation) mounted external to each of the four main steam lines upstream of the safety and relief valves.
'he inspector reviewed the status of the high range noble gas effluent monitors and their commitment compliance documentation. The monitors were turned over to the system test engineer in August 1986.
Preoperational testing, calibration, and procedures were completed in mid-September. All of the 29 compliance action plan items have been completed.
Thus, the applicant appears able to adequately demonstrate compliance with FSAR commitments to NUREG-0737, Item II.F.1, Attachment 1.
RCT training in the operation of these monitors was completed in September 1986.
The inspector selectively reviewed records of calibration of equipment and training of RCTs. Calibrations were conducted is accordance with Procedure BWIS 3.3.6-211, Revision 1, Surveillance Calibration of Auxiliary Building Vent Stock WRGM Radiation Monitoring System. No problems were noted.
This item is considered
closed.
11. NUREG-0737 Item II.F.1.2, Sampling and Analysis of Iodine and Particulate Effluents Section E.30.2 of Appandix E to the FSAR describes the post-accident effluent sampling system and the analysis of iodine and particulate effluent samples.
The iodine and particulate sampling system is a part of the General Atomic system described above for Item II.F.1.1 and provides for obtaining grab samples from the auxiliary building vent.
The sample media will be analyzed in the station's counting rooms by gamma ray spectrometers which utilize Ge (Li) detectors.
The inspector reviewed the status of the accident range iodine and particulate effluent sampling system. The sampling system was turned over to the system engineer in August 1986.
Preoperational testing, calibration and procedures were complettd by mid-September. Thirty compliance action plan items have been completed.
Three modifications remain to be completed as noted in Inspection Report No. 50-456/86002; and No. 50-457/86002 before the licensee can demonstrate compliance with FSAR commitments to NUREG-0737, Item II.F.1, Attachment 2.
Completion of
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RCT training, including the operation of this system and sample analysis equipment, was completed in September 1986.
The inspector selectively reviewed records of calibration of equipment and training of RCTs.
Calibrations were conducted in accordance with Procedure BWIS 3.3.6-211, Revision 1; no problems were noted.
This item remains open pending necessary system modifications and testing.
12. NUREG 0737 Item II.F.1, Attachment 3, Containment High-Range Radiation Monitor Section E.30.3 of Appendix E to the FSAR describes the Containment High-Range Radiation Monitors, contains commitments to install Containment High-Range Radiation Monitors as specified by Table II.F.1-3 of NUREG-0737, and prcvides a plant drawing indicating the location of the monitors. The monitoring system consists of General Atomic Company RD-23 high range radiation detector, Model RM-80 microprocessors, and RM-23 remote display units. Detectors 1RE-AR020 and 2RE-AR021 are located in the Unit I containment at elevation 514' 8" at azimuths 90 and 277, respectively. Detectors 2RE-AR020 and 2RE-AR021 are located at elevation 514' 8" at azimuths 90 and 263, respectively. Appropriate procedures have been revised to ensure that the polar crane will not be inadvertently parked such that the monitors would be significantly shielded.
The inspector reviewed the status of the containment high-range radiation monitors and their commitment compliance documentation. The monitors were turned over to the system test engineer in August 1986.
Preoperational testing, calibration, and procedures were completed in mid-September. All of the 14 compliance action plan items have been completed; thus, the applicant appears able to adequately demonstrate compliance with FSAR commitments to NUREG-0737, Item II.F.1, Attachment 3.
The inspector selectively reviewed records of calibration and testing. Calibrations and testing were conducted in accordance with Procedure BWIS 3.3.6-210, Revision 1, Surveillance Calibration of Accident Area Radiation Monitors.
No problems were noted.
Records of RCT training in response to alarms of these monitors were also reviewed; no problems were noted. This item is considered closed.
13.
Exit Meeting The inspector met with licensee representatives (denoted in Section 1) at the conclusion of the inspection on October 8, 1986. The scope and findings of the inspection were summarized. The inspector also discussed the likely information content of the inspection report with regard to documents of processes reviewed by the inspector during the inspection.
The licensee identified no such documents / processes as proprietary.
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