IR 05000315/1986009
| ML17326B202 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 03/17/1986 |
| From: | Hueter L, Schumacher M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML17326B201 | List: |
| References | |
| 50-315-86-09, 50-315-86-9, 50-316-86-09, 50-316-86-9, NUDOCS 8603250097 | |
| Download: ML17326B202 (12) | |
Text
U.S.
NUCLEAR REGULATORY COMMISSION
REGION III
Reports No. 50-315/86009(DRSS);
50-316/86009(DRSS)
Docket Nos.
50-315; 50-316 Licensee:
American Electric Power Service Corporation Indiana and Michigan Electric Company Riverside Plaza Columbus, OH 43216 Licenses No.
D. C.
Cook Nuclear Plant, Units 1 and
Inspection At:
D.C.
Cook Site, Bridgeman, MI
Inspection Conducted:
February 25-,28, 1986 Inspector:
L. J. Hueter~
Date lk Approved By:
M.
C.
Schumacher, Chief Radiological Effluents and Chemistry Section a/n/gg Date Ins ection Summar Ins ection on Februar 25-28 1986 Re orts No. 50-315/86009 DRSS
.
No.
50-316 86009(DRSS
)
P 'l radioactive program including:
effluent release records and reports of effluents; effluent control instrumentation; procedures for controlling releases; primary and secondary coolant chemistry and activity; gaseous effluent filtration; audits; and review of previously identified open items.
The inspection involved 33 inspector-hours onsite by one NRC inspector.
Results:
No violations or deviations were identified.
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Persons Contacted DETAILS
~A. Blind, Assistant Plant Manager
~R. Clendening, Plant Radiation Protection Supervisor S.
Dannhardt, Technical Physical Sciences',
Radiation Waste Handling Supervisor P. Holland, Radiation Protection Supervisor
"L. Holmes, Technical-Physical Sciences, Administrative Compliance Coordinator
"M. Horvath, AEPSC gA Supervisor S. Khalil, Performance Engineer, Senior
"T. Kriesel, Technical-Physical Sciences, Superintendent
~T. Postlewait, Technical-Engineering, Performance Supervisor
"J. St.
Amand, Technical-Engineering, Performance Engineer
"J. Stietzel, gC Supervisor
"B. Svensson, Assistant Plant Manager, Operations J. Wojcik, Plant Chemical Supervisor
"J. Heller, NRC Resident Inspector C. Wolfsen, NRC Resident Inspector The inspector also contacted other licensee employees, including members of the technical staff.
2.
"Denotes those present at the exit meeting.
Licensee Action on Previous Ins ection Findin s (Open)
Open Item (315/80-23-06; 316/80-19-06):
As noted in previous inspection reports, licensee efforts were made to reduce the background levels of liquid effluent monitor R-18 to increase the sensitivity of the monitor.
These efforts, including relocation of the monitor to an area having a lower background radiation level and flushing (including acid)
have met with partial success.
Licensee plans to replace this monitor were delayed to 1986 because of emphasis placed on completion of many post-TMI modifications.
Licensee plans to install the new monitor are progressing.
The licensee expects to complete installation, testing, and to begin use of the monitor by the end of the year.
3.
Gaseous Effluents The inspector reviewed selected records of radioactive gaseous effluent sampling and analysis for 1985 and the semiannual effluent reports for 1985.
The pathways sampled and the analyses performed appear to comply with Technical Specification Table 4. 11-2.
The noble gas release rate, which had increased significantly during the last half of 1984, continued higher than normal into the second quarter
of 1985, but on an annual basis remained about average for U.S.
pressurized water reactors.
Total curies of noble gas released in the first and second halves of 1985 were 4900 Ci and 43.8 Ci respectively or an annual average of about 2470 Ci per reactor unit.
The increased noble gas activity was attributed primarily to fuel cladding failures and pressurizer safety valve leakage for Unit 1 and steam generator tube leaks for Unit 2.
The Unit 1 pressurizer safety valve was repaired during a short outage in early 1985 and during the Unit 1 ten year ISI outage which began in April 1985, fuel was sipped and about twenty fuel elements with identified fuel cladding problems were replaced.
Unit 2 was shut down in early July for repair of steam generator tube leaks which were first identified about two months earlier.
Noble gas activity was very low during both the third and fourth quarters of 1985 as both units were down most of the third quarter and the problems had apparently been corrected when both units returned to power during the fourth quarter.
No problems were identified in the review of records.
The records show that releases were maintained well within applicable limits.
No violations or deviations were identified.
Li uid Effluents The inspector reviewed selected records of radioactive liquid effluent sampling and analysis for 1985 and the semiannual effluent reports for 1985.
The pathways sampled and the analyses performed appear to comply with Technical Specification Table 4.11-1.
Total liquid radioactive effluent (excluding tritium) during the first and second halves of 1985 was about 0.78 Ci and 1.5 Ci respectively or an annual average of about l. 1 Ci per reactor unit.
Total tritium released during the first and second halves of 1985 was about 400 Ci and 730 Ci respectively or an annual average of about 570 Ci per reactor unit.
Both the licensee's non-tritium and tritium liquid effluents are about average for U.S. pressurized water reactors.
No problems were identified in the review of records.
The records show that releases were maintained within applicable limits.
All batch releases are processed through the 30 gpm radwaste evaporator.
The new backup
gpm radwaste evaporator still has some heat tracing and electrical modifications to be made and has a relatively low priority for completion due to its intended use for backup purposes.
In 1986, the licensee plans to obtain a mobile demineralizer system, having a
high efficiency for Co-58 removal, as an alternate processing unit.
Co-58, on average, constitutes about 70 percent of the activity in batch releases.
During the inspection, the inspector accompanied an auxiliary equipment operator for the valve lineup steps of the procedure for liquid release, L86-17, from Monitor Tank No. 4.
The operator carried a copy of this procedure and demonstrated familiarity with i k
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'o violati ons or devi ati ons were identi fied.
Effluent Control Instrumentation The inspector reviewed calibration records and selected set points for the following monitors with no problems being noted:
Liquid Unit 1 Unit 2 Unit 1 Unit 2 Unit 1 Unit 2 Radwaste Monitor Vent Low Range Noble Gas Monitor Vent Low Range Noble Gas Monitor Gland Seal Exhaust Low Range Noble Gas Monitor Gland Seal Exhaust Low Range Noble Gas Monitor Steam Jet Air Ejector Low Range Noble Gas Monitor Steam Jet Air Ejector Low Range Noble Gas Monitor R-18 VRS-1505 VRS-2505 SRA"1805 SRA"2805 SRA-1905 SRA-2905 The instruments listed above have been calibrated on a timely basis.
A detailed geometry calibration involving four different concentrations of Cs-137 in a length of pipe was performed on R-18 (and other liquid process monitors) in November 1985.
This calibration showed that R-18 has reasonably linear response and good correlation to the response from the solid Cs-137 cap sources used in past calibrations.
The licensee continues to calibrate the low range noble gas monitors using two solid sources (Sr -90/Yr-90 cap sources)
of differing strengths, based on previous transfer calibrations in which gas sources were used.
The calibration data shows good stability in instrument response.
Procedures and records for setpoint determination for selected effluent and process monitors were reviewed and appear to comply with applicable Offsite Dose Calculation Manual (ODCM) and technical specification criteria.
About mid-January, 1986, the licensee submitted a request to NRR for a technical specification change involving some relief regarding the high alarm trip setpoint (currently designated as "< 2 times normal channel reading") of certain monitors.
As the licensee believes that the current criterion has resulted in a number of unnecessary notifications and reports to the NRC, they have submitted data in support of a high alarm/
trip setpoint based on specific values rather than "< 2 times normal channel reading."
Also, the licensee has requested that the high alarm/
trip setpoint criteria be applicable during the currently specified modes of operation but further limited to those times when containment purging is in actual progress.
No violations or deviations were identified.
6.
Primar and Secondar Coolant Radiochemistr The inspector selectively reviewed the licensee's reactor coolant and secondary coolant chemistry and radiochemistry results for 1985 to determine compliance with technical specification requirements for
)
R I
chemistry and radiochemistry limits and surveillance frequencies.
For the primary coolant systems, the inspector reviewed data for dissolved oxygen, chloride, fluoride, dose equivalent I-131 and E bar analysis.
For the secondary systems, the inspector reviewed gross activity determination and the isotopic analysis for dose equivalent I-131.
The selective review and discussion with licensee personnel indicated that all parameters for both primary and secondary systems remained less than applicable technical specification limits throughout the review period with the exception of the dose equivalent I-131 for the Unit 1 primary system on two occasions.
Dose equivalent I-131 spikes above 1.0 pCi/gm occurred for about a 16 hour1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> period on both occasions.
Both occasions were associated with power reductions for controlled reactor shutdowns on January 12, 1985 and on April 6, 1985.
These spikes, which peaked at about 1.5 and 4.5 pCi/gm dose equivalent I-131 respectively, were anticipated as Unit 1 had previously developed fuel cladding problems.
As noted in Section 3, following this second shutdown, the fuel was sipped and fuel elements with identified cladding problems were replaced.
These occurrences were reported to the NRC.
No problems were identified regarding compliance with frequency of required surveillances.
No violations or deviations were identified.
Air Cleanin S stems Technical specifications require testing of the control room emergency ventilation systems, the ESF ventilation systems and the fuel storage pool ventilation systems.
The in-place leakage test criteria specified both for DOP testing of HEPA filters and for freon testing of charcoal adsorbers is
< one percent.
The laboratory test criteria for carbon sample removal efficiency for radioactive methyl iodide is > 90K.
Records reviewed showed that the spent fuel storage pool ventilation system successfully met test criteria when tested in January and February 1985.
The control room ventilation systems and the ESF ventilation systems successfully met test criteria when tested in August and September 1985.
Surveillances reviewed met required frequency criteri'a.
In the past, testing was performed by vendors.
Following a transition period of joint testing, licensee personnel took over testing activities during this the past year.
During 1985, the licensee made extensive improvements to the ventilation air cleaning systems and the testing program.
These improvements include the areas of testing procedures, and maintaining and upgrading the systems.
The licensee is also working on a design change and technical specification modification to change to a manually operated deluge system for use in the event of charcoal fires due to recurring problems with water leakage on charcoal and on the floor of the filter housings.
No violations or deviations were identifie ~
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8.
Audits The inspector reviewed two reports of audits conducted in 1985 by the Nuclear Safety and Design Review Committee (NSDRC),
a corporate organization.
The November audit reviewed the process control program (including a review of the semiannual effluent reports).
The December audit reviewed conformance to technical specifications
'and included setpoint changes for ESF system instrumentation and operation of the waste gas holdup system.
No significant problems were identified with the gaseous or liquid radwaste programs by either of these audits.
The inspector also reviewed a 1985 plant gA Audit (Audit No. 85-03) of
"Radiation Monitoring and Protection."
This, audit included a review of the ODCM and selected monthly dose projection records calculated based on the ODCM criteria.
No problems were identified with this area of the audit.
In addition, the inspector reviewed four 1985 plant gA Surveillance Reports, S/R 2-85-08, S/R 1-85-13, S/R 1-85-72 and S/R 1-85-136.,
These surveillances involved charm'el functional tests'f the'team,'generator blowdown monitor, channel calibration of the condenser evacuation system noble gas monitor, determination of cumulative dose contribution from liquid effluents per ODCM at 31 day intervals, and determination that analysis and procedures are used by the licensee to assure that activity concentrations of liquid effluents at the point of release are within required limits.
No problems were identified by these gA surveillances.
No violations or deviations were identified.
Trainin and uglification Effectiveness As noted in Section 4, during the inspector's accompaniment of an auxiliary equipment operator during a valve lineup procedure for a liquid radwaste release, the operator carried a copy of the procedure and demonstrated adequate familiarity with the procedure and valve locations.
The radiation protection supervisor responsible for calibration of process monitors (including effluent monitors)
spends 40 percent of his time with the technicians he supervises.
Part of this time involves direct supervision of technicians during instrument calibration activities.
A formalized training and qualification program is being prepared for the radiation protection technicians.
As a part of the recent efforts to improve the ventilation air cleaning systems and testing program, the licensee has increased the training of technicians and engineers in operation, maintenance and surveillance of the filter systems.
Much of this training has been on-the-job training but some has been formal.
Supervisory personnel (for such activities as instrument calibrations, setpoint determinations, air cleaning system surveillance, ODCM dose determination and semiannual effluent report preparation),
who were interviewed during the inspection, appeared to have a good understanding of their areas of responsibilities including applicable regulations and procedures.
No violations or deviations were identifie C i
P I
II
, 8.
Exit Interview The inspector summarized the scope and findings of the inspection with licensee representatives (Section 1) at the conclusion of the inspection on February 28, 1986.
The inspector discussed the likely informational content of the inspection report with regard to documents or processes reviewed by the inspector during the inspection.
The licensee did not identify such documents or processes as proprietar W'l
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