IR 05000454/1983057
| ML20083J785 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 12/23/1983 |
| From: | Paperiello C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Reed C COMMONWEALTH EDISON CO. |
| Shared Package | |
| ML20083J787 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737 NUDOCS 8401050418 | |
| Download: ML20083J785 (2) | |
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Docket No. 50-454 Docket No. 50-455 Commonwealth-Edison Company ATTN:
Mr. Cordell Reed Vice President Post Office Box 767 Chicago, IL 60690 Gentlemen:
This refers to the routine safety inspection conducted by Mr. L. J. Hueter of this office on November 28 - December 2, 1983, of activities at Byron Nuclear Power Station, Units 1 and 2, authorized by NRC Construction Permits No. CPPR-130 and No. CPPR-131 and to the discussion of our findings with Mr. R. Querio
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and other members of your staff at the conclusion of the inspection and subse-quent to the inspection in a telephone conversation with Mr. J. VanLaere and other members of your staff on December 5, 1983.
The enclosed copy of our inspection report identifies areas examined during the inspection. Within these areas, the inspection consisted of a selective examination of' procedures and representative records, observations, and interviews with" personnel.
No items of noncompliance with NRC requirements were identified during the course of this inspection.
In accordance with 10 CFR 2.790(a), a copy of this letter and the enclosure will be placed in the NRC Public Document Room unless you notify'this office, by' telephone, within ten days of the date of this letter and submit written application to withhold information contained therein within thirty days of the'date of this letter.
Such application must be consistent with the re-quirements of 2.790(b)(1). If we do not hear from you in this regard within the specified periods noted above, a copy of this letter and the enclosed inspection report will be placed in the Public Document Room.
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C. J. Paperiello, Chief Emergency Preparedness and
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Radiological Safety Branch
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Enclosure:
Inspection Reports
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No. 50-454/83-57(DRMSP) and i
No. 50-455/83-40(DRMSP)
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REGION III==
Reports No. 50-454/83-5?(DRMSP); 50-455/83-40(DRMSP)
Docket Nos. 50-454; 50-455 License Nos. CPPR-130; CPPR-131 Licensee: Commonwealth Edison Company Post Office Box 767 Chicago, IL 60690 Facility Name: Byron Station, Units 1 and 2 Inspection At: Byron Site, Byron, IL Inspection Conducted: November 28 - December 2, 1983 Inspector:
L. J ueter
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23 83 Date l
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Approved By:
L. R. Greger, Chief Id 4 3!S 3 i
Facilities Radiation Protection Section Date Inspection Summary Inspect'en on November 28 - December 2, 1983 (Reports No. 50-454/33-57[DRMSP];
50-455/(~
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Areas Ins;ected:
Routine, unannounced inspection of preoperational radiation protection program for Units 1 and 2.
The inspection included organization, staffing, training, radiation protection procedures, facilities, instruments, equipment, respiratory protection program, status of certain NUREG-0737 items, status of certain preoperational systems demonstrations and tests, and open items. The inspection involved 45 inspector-hours onsite by one NRC inspector.
Resulte_:_ No items of noncompliance were identified.
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DETAILS 1.
Persons Contacted
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Barrett, Station Chemist W. Bowman, Health Physicist (Consultant)
R. Carballa, Inrtrument Maintenance (WISCO)
- W. Dean, Assistant Teclnical Staff Supervisor D. Herman, Chemist
- D. Johnson, Instrument Foreman
- C. Lenth, Licensing Staff (Station)
- B. Long, Instrument Foreman J, Ott, Vendor Representative, General Atomics D. Prisby, Systems Test Engineer
- R. Querio, Station Superintendent
- B. Scott, Health Physicist D. St. Clair, Technical Staff Supervisor
- J. VanLaere, Rad / Chem Supervisor
- R. Ward, Assistant Superintendent, Administrative and Support Services K. Weaver, Station Health Physicist C. Zion, Technical Staff
- J. Hinds, Jr., NRC Senior Resident inspector
- Denotes those present at the exit meeting.
2.
General This preoperational inspection, which began about 1:30 p.m. on November 28, 1983, wys conducted to examine the preoperational radiation protec-tion program, open items, and progress made on certain NUREG-0737 items and certain systems demonstrations and tests.
3.
Open Items The following licensee responses to open inspection items were reviewed during the inspection:
(Closed) Open item (454/83-08-01): Concerning review of the location of area monitors to assure that each is properly located to serve its inten-ded function. This activity has now been completed for all monitors in-volved with Unit 1, including the area monitors located in the radwaste building. All Unit 1 area monitors now appear to be properly located.
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(0 pen) Open Item (455/83-06-01):
Concerning review of the location of area monitors to assure that each is properly located to setve its inten-ded function. This activity is incomplete for Unit 2 containment.
4.
Organization, Staffing, and Training Rad Chem Department organizatior nd staffing are essentially unchanged from that described in Inspect' n Reports No. 50-454/83-08 and 50-454/
83-34, and appear compatible with FSAR and SER commitments (including SER Supplement No. 3 issued November 23, 1983).
Seven new RCTs have been in basic training since September at Braidwood Training Center attending the 14 week course covering generic Rad / Chem training and PWR specific train-ing. These seven will augment the 18 RCTs previously trained in basics and more recently involved in the RCT certification program. The latter involves practical factors and demonstration of ability to operate equip-ment and perform procedures in both the areas of chemistry and radiation protection. The RCT certification program is essentially complete for chemistry while it is only about 50% complete in radiation protection due to priority given to the recent drill. The licensee plans to complete the RCT certification program by the end of December.
5.
Radiation Prctection Procedures The inspector reviewed the following radiation protection procedures.
They appear to be compatible with regulatory requirements and FSAR commit-ments except as noted below:
BRP 1000-Al Revision 1 Radiation Work Permit BRP 1000-Al Revision 1 Occupational Radiation Exposure Received at Off-Site Locations BRP 1000-Al Revision 1 Respiratory Protection BRP 1000-Al Revision 1 Unconditional Releases *
BRP 1110-1 Revision 0 Radiation and Contamination Limits *
BRP 1260-1 Revision 1 Radiation Protection Instrumentation Test and Calibration BRP 1300-A4 Revision 0 WBC Personnel Count Instructions
- The procedures for unconditional release of materials from the controlled area of a nuclear power plant, as provided in both the Radiation Protection Standards and in the Administrative Procedures, are not compatible with regulatory requirements. No deminimus levels exist in regulatory require-ments regarding fixed and/or removable contamination levels for uncondi-tional release of items from a nuclear power plant. However, the refer-enced procedures, as currently worded, provide for unconditional release of items if fixed and/or removable contamination is below specified levels.
This matter is considered an open item (454/83-57-01; 455/83-40-01).
The licensee's preparations for compliance with 10 CFR 61, which will become effective December 27, 1983, were discussed. The licensee is devel-oping specific procedures to effect compliance with 10 CFR 61.
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6.
Facilities, Instruments, and Equipment The status of the respirator fit test facility, whole body counting facility, dosimetry program, and IRT scintillation type portal monitors is unchanged from that described in Inspection Reports No. 50-454/82-23 and 50-454/83-34.
The invr.ntory of dosimeters and survey meters is as described in the inspection reports referenced above with the exception that the licensee now has two additional neutron survey meters onsite for a total of five and has additional dosimeters and survey meters on order.
The respirator issuance and maintenance room is currently under review as a Follow Up Engineering Item (FUEI) due in part to poor accessibility resulting from electrical cabinets located in front of the entrance to the room.
The general types and numbers of General Atomic area monitors and process monitors are as described in the inspection report referenced above.
Much progress has been made in installation of the monitors including piping and wiring. Two CRTs are now installed and operating in the reactor control room. Most of the initial calibration procedures and a few of the preoperational tests have been written and approved. The ini-l tial calibration and preoperational testing has been completed on a few l
of the monitcrs.
Initial calibration and preoperational testing of these monitors is being handled by the licensee as a high priority item due to its impact on fuel load.
Initial calibrations are being performed with sealed sources, provided by General Atomic, which are correlated with solid sealed source standards at General Atomic. These sources and stan-dards, in turn, are correlated with NBS sources including gas and liquid
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sources where appropriate. The licensee plans to calibrate effluent moni-tors with plant effluents when available after plant startup.
The preoperational tests of a monitor provide for testing reflash capabil-ity of annunciators in the control roem when other malfunctions occur with the same monitor. Another preoperational test is being developed to test the reflash capability of each monitor when there is an alarmed target from another monitor.
For information on the status of instruments and equipment required by NUREG-0737, refer to Section 8.
7.
Respiratory Protection Program The respiratory protection program facilities are as described in Section 6 and in previous inspection reports No. 50-454/82-23 and 50-454/83-34.
Respiratory protection training is included as part of the annual nuclear general employee training which has been implemented since early 1983.
Verification of medical fitness is a prerequisite to fit-testing.
Fit-testing is about 90 percent complete for station personnel and is being expedited for contractor personnel. Fit-testing of the guard force has been completed. The licensee plans to complete fit-testing by fuel load.
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I The licensee has MSA half-mask and full facepiece air purifying respira-tors and Scott full facepiece self-contained breathing apparatus.
8.
Status of Certain NUREG-0737 Action Items The description of licensee actions in response to TMI action items are provided in FSAR, Appendix E.
NUREG-0737 Item II.B.3, Post-Accident Sampling System Section E-21 o' ippendix E describes the post-accident sampling system for the reactor coolant and containment atmosphere.
It is also described in some detail in previous inspection report No. 50-454/83-34. The system is a modified Sentry high radiation sampling system (HRSS) consisting of three subsystems:
the liquid sample panel (LSP), the chemical analysis panel (CAP) which is attached to the LSP, and the containment atmosphere sample panel (CASP).
The LSP is designed to collect liquid samples from many locations which are classed into three groups:
reactor coolant, demineralizers, and rad-waste. The LSP has been preop tested under Preoperational Test 2.61.10, Primary Process Sampling System. During the test, no flow could be ob-tained from three of the radwaste sample locations and flow below what was expected was obtained from 4 of the demineralizer sample locations.
These flow problems are considered a deficiency in the test. The defi-ciency is currently being evaluated by the licensee. Procedures have been written and teaining conducted on the LSP.
The CAP system is partially operational. The licensee plans to have it fully operational by the end of December after which it will be tested under Preoperational Test 2.61.10 (currently an open item in the test package). Procedures have been written and part of the training has been conducted on the CAP system.
The CASP system, intended for use only during accident conditions, is not expected to be operational before early 1984. Heat tracing of the sample line is not in place. The sampling procedure has been written. Preopera-tional testing and training are to be conducted after the system becomes operational.
NUREG-0737 Item III.D.3.3, Inplant Iodine Radiation Monitoring The inplant radiation monitoring and analysis for airborne iodine (NUREG-0737 Item III.D.3.3) provisions are essentially complete. Portable air samplers are to use silver zeolite as the collection medium. Transport-able counting equipment, to be placed at a planned location in the turbine building (following post construction clean-up), is currently located in the regular counting room facility. Procedures writing and training have been accomplished.
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l NUREG-0737 Item II.F.1.1, High "ange Noble Gas Effluent Monitors The accident range noble gas effluent monitoring system (NUREG-0737 Item II.F.1.1) censists of a General Atomic wide range gas monitor 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. The wide range gas moni-tor is partially installed (not piped or wired). The monitors on the steam lines are physically Installed but are not wired. Calibration and preoperational testing is pending the operational status of these units.
NUREG-0737 Item II.F.1.2, Sampling and Analysis of Iodine and Particulate Effluents The accident range iodine and particulate sampling and analysis (NUREG-0737 Item II.F.1.2) system is not operational. The system is a part of the General Atomic systes described above for Item II.F.1.1 and provides for obtaining grab samt Dss from the auxiliary building vent and subsequent analysis of samples usi e facilities in the counting room. As noted above, the system is not pipec <r wired.
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NUREG-0737 Item II.F.1.3, Containment High Range Radiation Monitors The containment high range monitors (NUREG-0737 Item II.F.1.3) are in-stalled and calibrated but have not been preoperationally tested.
9.
Preoperational Systems Demonstrations and Tests WX 2.106.24 Coalescer This test has been completed and reviewed by the licensee. The inspector reviewed the completed tect. _ One minor outstanding deficiency appears to be adequately addressed by facility change request. No significant prob-less were noted.
WY 2.107.20 Laundry Equipment Floor Drain Radwaste This test has been completed and reviewed by the licensee. The inspector reviewed the completed test. Two minor outstanding deficiencies appear
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to be adequately addressed by facility changa requests. No significant problems were noted.
WZ 2.108.20 Chemical Radwaste Reprocessing and Disposal This test has been completed and reviewed by the licensee. The inspector reviewed the completed test. Two minor outstanding deficiencies appear to be adequately addressed by facility change requests. No'significant problems were noted.
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According to licensee personnel, the following systems demonstrations and tests are at the percentage completion indicated:
GW 2.38.10 Radioactive Waste Gas 100%
AR 2.6.10-16 Area Radiation Monitors 15%
OG 2.55.20 Off Gas 100%
PR 2.60.10-16 Process Monitors 25%
WX 2.106.20 Radwaste Processing Tanks and Pumps 100%
WX 2.106.21 Radwaste Evaporators 0%
WX 2.106.22 Radwaste Demineralizers and Filters 0%
WX 2.106.23 Stock Equipment 55%
WX 2.106.25 Integrated Performance Test 0%
These test packages will be reviewed (if completed) during the next radi-ation protection preoperational inspection.
10.
Exit Meeting The inspector met with licensee representatives (denoted in Section 1) at the conclusion of the inspection on December 2, 1983. The subject of instrument calibrations was subsequently discussed on December 5 in a telephone conversation with Mr. Vantaere and other staff members. The scope and findings of the inspection were discussed.
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