IR 05000315/1978028
| ML17317A730 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 10/10/1978 |
| From: | Schumacher M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML17317A728 | List: |
| References | |
| 50-315-78-28, NUDOCS 7811140189 | |
| Download: ML17317A730 (8) | |
Text
U. S.
NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No.
50-315/78-28; 50-316/78-26 Docket No.
50-315; 50-316 License No.
American Electric Power Service Company Indiana and Michigan Power Company 2 Broadway New York, NY 10004 Facility name:
D.
C.
Cook Nuclear Power Plant, Units 1 and
Inspection at:
Facility site Inspection conducted:
September 12-15, 1978
, @'d5~
Inspector:
.
C.
Schumacher
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Approved by:
W. L. Fisher, Chief Fuel Facility Projects and Radiation Support Section
/o o
Ins ection Summa Ins ection on Se tember 12-15 1978 (Re ort Nos. 50-315/78-28 '0-316/78-26)
Areas Ins ected:
Routine, unannounced inspection of radioactive waste systems, including:
effluent releases; records and reports of effluents; effluent control instrumentation; procedures for controlling releases; containment air-cleaning systems; reactor coolant water quality; solid radioactive waste; responses to IE Circulars; and followup on noncompliance items.
Also, completed review of Unit 2 shielding surveys and Unit 2 primary chemistry measurements to 100% power.
The inspection involved 40 inspector-hours onsite by one NRC inspector.
Results:
No items of noncompliance were identified as a result of the inspectio DETAILS 1.
Persons Contacted
+D. V. Shaller, Plant Manager
- L. D. McCullough, Staff Assistant to Plant Manager T. Kriesel, Environmental Coordinator
- D. C. Palmer, Radiation Protection Supervisor W. Ketchum, Engineer (Radiation Protection)
- J.
T. Wojcik, Chemistry Supervisor
- J. F. Stietzel, QA Supervisor C.
W. Kant, Performance Supervisor
- E. A. Abshagen, QA Auditor
- W, F. Scott, III, Environmental Engineer J. Fryer, Radiation Protection Foreman R. Lease, Production Supervisor
- K. Baker, USNRC Resident Inspector 2.
- Denotes those present at exit interview.
General The inspection began at approximately 6:15 a.m.
on September 12, 1978.
After gaining access to the plant, a tour was made of selected auxiliary building areas, including solid radwaste
'facilities, with the production supervisor.
Other visits to selected plant areas, including radwaste, effluent monitor locations, and the control room, were made later in the inspection.
Radiological conditions including controls and area postings were satisfactory.
Housekeeping appeared satisfactory.
Both units were operating at approximately full power during the inspection.
No items of noncompliance were identified.
3.
Licensee Action on Previous Ins ection Findin s (Closed) Deviation (50-315/78-11, 50-316/78-10):
Commitment date to develop air sample analysis procedure not met.
The corrective action stated in the licensee's response dated June 28, 1978 was verified.
4.
Radioactive Effluent Releases a.
Airborne Releases Selected records of airborne releases for July to December 1977 and January to July 1978 were reviewed and compared
with regulatory requirements for monitoring, sampling, analysis, release rate, and activity released.
Batch releases (gas decay tanks and containment purges)
are administratively controlled by release permits.
Continuous releases via the plant vents are monitored for noble gases, sampled continuously (changed weekly)
for iodine and particulates, and spot sampled weekly for noble gases.
Periodic ventings of containment are made via the one thousand cfm containment pressure relief system fan in order to maintain containment pressure between minus 1.5 and 0.3 psig.
The ventings (approximately
minutes duration each)
are through charcoal and HEPA filters.
Iodine and particulates released are sampled by the continuous samplers.
Noble gases released in the ventings are monitored at the plant vent but are not quantified.
The ventings are documented by the control room operator and monitor readings are noted.
The inspector's review indicates a resultant error of no more than three percent in effluent reports.
This matter was discussed at the exit interview.
The inspector reviewed radiological aspects of an unplanned release from gas decay tanks that occurred on August 12, 1978.
This event is described in RIII Inspection Report 50-315/78-25.
No problems were noted in the licensee's evaluation of this event and no release rate limits were exceeded.
No items of noncompliance were identified.
b.
Li uid Releases Selected records of liquid releases for the period July to December 1977 and January to July 1978 were reviewed and compared with regulatory requirements relating to release rates, concentrations, sampling, analyses, and monitoring of release points.
No items of noncompliance were identified.
5.
Records and Re orts of Effluents The inspector reviewed the semiannual reports for the second half of 1977 and the first half of 1978 and made selective comparisons with the licensee's primary release records.
No items of noncompliance were identifie Effluent Control Instrumentation Selected records of effluents and process monitor calibrations for the period August 1977 through August 1978 were reviewed.
Quarterly calibrations use vendor supplied solid sources.
The licensee also periodically (most recently December 1976 and September 1977) calibrates representative monitors, using liquid and gaseous sources as appropriate in representative geometries.
These calibrations are used to prepare monitor calibration curves, which are maintained in the control rooms.
No items of noncompliance were identified.
7.
Procedures for Controllin Releases aO Procedure Chan es No problems were noted in review of the following procedures reviewed since the last radwaste inspection.
THP 6010 RAD 590,
"R-33NMC Process Monitor Detector Calibration Radio-Gas Monitor," Rev.
1, May 3, 1978 THP 6010 RAD 592, "Liquid Process Monitor Detector Calibration,"
Rev.
3, July 18, 1978 THP 6010 RAD 594,
"RMS Radio-Gas Cap Source Calibration,"
Rev.
2, May 18, 1978 THP 6010 RAD 595,
"RMS Radio-Gas Geometry Calibration,"
Rev.
1, August 8, 1978 THP 6010 RAD 596, "Calibration of Stack Monitor Radio-Gas Detector, (R-31)," Rev.
1, November 30, 1977 THP 6010 RAD 597, "Air Particulate Detector Calibration,"
Rev.
3, September 12, 1978 THP 6010 RAD 598, "Calibration of the Stack Monitor Iodine Channel (R-32), Rev. 1, February 21, 1978 Problems with the following procedures were discussed with licensee representatives:
THP 6010 RAD 304, "Shipment of Radioactive Materials,"
Revision 3, January 30, 1978
The procedure appears to apply to all ~aste shipments.
The formula of curie estimation in Section 6.2 is inappropriate for use with dewatered resins or solidi-fied evaporator bottoms and is, in fact, not used by the licensee relative to these wastes.
The procedure does not make the fact clear.
THP 6010 RAD 332, "Liquid Waste Releases,"
Rev.
The procedure specifies the use of "insoluble" MPC values from Appendix B, Table II of 10 CFR 20.
This is inappro-priate for several isotopes, including iodine, cesium, and strontium.
In practice, the licensee uses the appropriate MPC values.
No items of noncompliance were identified.
b.
Com liance with Selected Procedures Compliance with procedure THP 6010 RAD 332 was confirmed by reviewing selected liquid waste release worksheets.
No items of noncompliance were identified.
8.
Containment Air Cleanin S stems Records of HEPA and charcoal filter tests for the control room ventilation, ESF ventilation, and spent fuel pit ventilation systems were reviewed against technical specification require-ments.
No items of noncompliance were identified.
9.
Reactor Coolant Water ualit The inspector reviewed measurements of reactor coolant quality, including 2 determinations.
The review also included measure-ments of Cl, Fl, 0
, tritium, gross beta gamma, and I-131 on Unit 2 primary coolant during ascension to 100% power.
No abnormal results were noted.
No items of noncompliance were identified.
10.
Solid Radioactive Waste The licensee packages and ships evaporator bottoms solidified with urea formaldehyde, dewatered resins, compressed trash in
drums, and noncompressible solids in drums or boxes.
The resins are dewatered in liners inside vendor supplied shipping casks HN100 and HN200.
Dewatering is verified by pumping from three well points at the botton of the liner until no more liquid can be withdrawn in accordance with li'censee procedures.
The first resin shipments from the plant were made in February and March 1978.
The licensee's records included requisite cask licensees and other documentation and the shipments appeared to meet regulatory requirements for packaging and shipment.
The licensee did fail to notify the AEC before first shipment as required by 10 CFR. 71. 12.
This omission was identified by the licensee and the NRC was notified on August 17, 1978.
Curie quantification for bottoms and resins were done by measurements made on samples taken during packaging.
Other solid wastes are quantified by use of a formula in licensee procedure THP 6010 RAD 304 (Paragraph 7).
Only evaporator bottoms are solidified at the plant.
A concrete vermiculite drumming system was installed but has never been used, apparently because of difficulties encountered in preoperational testing.
Personal doses associated with waste solidification were described, as low by licensee representatives.
A figure of 2.5 man-rems for 1978 through September 10, given for the five vendor employees doing bottom solidification, was said to account for most of the dose associated with waste solidification.
No items of noncompliance were identified.
11.
Unit 2 Shieldin Surve Review of the neutron and gamma shielding survey for Unit 2 ascension to 100% power was completed during this inspection.
The surveys were made in accordance with Licensee Procedure 2-P0-050-597,
"Radiation Surveys and Shielding Effectiveness."
Neutron fields were observed in only one area accessible during power operation.
The dose equivalent rates there were less than 20 millirems per hour.
No changes were required in plant facilities or procedures as a result of this survey.
12.
IE Circulars a.
Circular 77-14:
Se aration of Clean and Contaminated Water S stems Plant water systems were reviewed by personnel from the licensee's office in New York.
The results of this
~
~
4I review, transmitted by letter dated January 16, 1978, indicated no danger of cross contamination between water systems.
The plant has initiated a weekly sampling program of various water systems, including drinking water, well water, and demineralized water.
b.
Circular 78-03:
LSA Materials Greater than T e A The licensee's packaging of LSA materials was reviewed (Paragraph 10).
No problems were noted.
13.
Monitor Res onse Procedures The inspector reviewed control room procedures governing operator response to effluent monitor alarms.
It was noted that the response to the vent gas monitor (R26) did not explicitly require use of monitor response/release rate curves to assess compliance with release limits.
With respect to the vent radioiodine monitor (R32), licensee personnel indicated that noble gas adsorption on the charcoal could give mislead-ingly high readings similar to those experienced at Fort St. Vrain.
These matters were discussed at the exit interview.
No items of noncompliance were identified.
14.
Exit Interview The inspection results were reviewed with Mr. Shaller and others (Paragraph 1) of his staff at an exit interview on September 15, 1978, and by telephone with Mr. Shaller on September 22, 1978.
The licensee agreed to formalize a procedure for quantifying noble gas releases through containment pressure ventings.
The licensee agreed to strengthen alarm response procedures for the vent gas monitor (R26) and the vent radioiodine monitor (R32).
(Paragraph 13)
The licensee agreed to review and amend as needed Procedures THP 6010 RAD 304 and THP 6010 RAD 332 dealing with solid waste and liquid releases, respectively.
(Paragraph 7)