IR 05000313/1973018
| ML19309D839 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 01/08/1974 |
| From: | Kidd M, Murphy C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19309D834 | List: |
| References | |
| 50-313-73-18, NUDOCS 8004110698 | |
| Download: ML19309D839 (7) | |
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8 '%s UNITED STATES h
1 *g ATOMIC ENERGY COMMISSION
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DIRECTORATE OF REGULATORY OPERATIONS g
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At taur 4, osoncia mm RO Inspection Report No. 50-313/73-18 Licensee:
Arkansas Power and Light Company Sixth and Pine Streets l
Pine Bluff, Arkansas 71601 Pacility Name: Arkansas Nuclear One, Unit 1 Docket No. :
50-313 License No.:
CPPR-57 Category:
B1 Location: Russellville, Arkansas Type of License: B&W, PWR, 2568 Mwt
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Type of Inspection: Routine, Unannounced Dates of Inspection: December 4-7, 1973 Dates of Previous Inspection: November 6-13, 1973 Inspector-in-Charge:
W. W. Peery, Radiation Specialist, Radiological and Environmental Protection Branch Other Accompanying Personnel:
G. R. Jenkins, Radiation Specialist Radio gical and Environmental Protection Branch Principal Inspector:
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M. S. Kidd, Readcor Inspector, Facilities Test Date and St rtup Branch Reviewed by:
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V C. E. Murphy,Wef, Fedi11 ties Test and Startup Branch
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RO Rpt. No. 50-313/73-18-2-
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SU MAKY OF FINDINGS I.
Enforcement Action A.
Violations None B.
Safety Items None II.
Licensee Action on Previously Identified Enforcement Matters
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Violations None
B.
Safety Items Nr ne III. New Unresolved Items
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73-18/l Emergency Planning I
Certain aspects of emergency planning have not been completed.
(Details I, paragraph 2)
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73-18/2 Location of Meter and Chart Readings for Radiation Monitoring Instrumentation Meter and chart readings for radiation monitoring instrumentation
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are located outside the control room.
(Details I, paragraph 3)
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73-18/3 Calibration of Radiation Monitors Calibration of area, liquid and gaseous monitors has not been completed.
(Details I, paragraph 4)
IV.
Status of Previously Reported Unresolved It. ems 72-9/1 Incorporation of Safety R21ated Equipment in the FSAR Q List Not inspected.
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B0 Rpt. No. 50-313/73-18-3-72-9/3 Preparation of Test Procedures to Cover Tests in " Guide for the Planning of Preoperational Test Programs" i
Not inspected.
i 73-3/1 Completion of Radiological Waste Disposal Systems The status of this item is unchanged, the solid waste disposal system has not been completed.
(Details, paragraph 5)
73-5/2 Core Flood System Flow Rate Test Wot inspected.
73-8/1 Procedural Coverage Per Safety Guide 33
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Not inspected.
73-10/1 Administrative Controls Manual Net inspected.
73-10/5 Gaseous and Clean Radwaste Systems Test Procedures
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Revision of procedure T. P. 232.72 remains to be accomplished.
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(Details I, paragraph 6)
73-10/6 Respiratory Protection Program and Procedures Procedures have been completed; however, other aspects of the program have not been completed.
(Details I, paragraph 7)
73-10/7 Representative Sampling of Gaseous Wastes
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This item has not been completed, but plans have been made to
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do so.
(Details I, paragraph 8)
73-12/2 Diesel Generator Trips Not inspected.
73-12/3 Control Rod Trip Test Not inspected.
I 73-14/2 Initial Core Load Procedure Not inspected.
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30 Rpt. No. 50-31
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73-14/3 Leak Testing of the Personnel Hatch Not inspected.
73-17/1 Pressurizer Electromagnetic Relief Valve Not inspected.
73-17/2 Emergency Operating Procedures Not inspected.
73-17/3 operational Test I regram Not inspected.
V.
Unusual Occurrences None VI.
Other Significant Findings None N
VII. Management Interview.
A management interview was held December 7,1973, with J. W. Anderson, Plant Superintendent, C. A. Halbert, Technical Support Engineer, and J. L. Orlicek, Quality Control Engineer.
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New unresolved items in Section III of this summary were discussed.
Details and management positions on these matters are given in Details I, paragraphs 2,3 and 4.
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The status of previously identified unresolved items listed in Section IV of this stanmary were also discussed for those items on which actual inspection effort was expended. The details are given in Details I, paragraphs 5,6,7 and 8.
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RO Rpt. No. 50-313/73-18 I-1
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DETAILS I Prepared by:
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M W. W. Peery, Radq@ lion Specialist
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Radiological and Environmental Protection Branch Dates of Inspection: December 4-7, 1973 Reviewed by:
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n J/T.Sutherland, Chief,' Radiological
/Da(e and Environmental Protection Branch 1.
Individuals Contacted Arkansas Power and Light Company J. W. Anderson, Plant Superintendent R. R. Culp. Test Administrator C. A. Halbert, Technical Support Engineer J. L. Orlicek,. Quality Control Enginaer M. H. Shanbhag, Procedure Administrator T. C. Baker, Chemical and Radiation Protection Engineer R. G. Carroll, Chemical and Radiation Protection Engineer
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Bechtel Corporation s/
l Neil Covington, Startup Engineer 2.
Emergency Planning The licensee has not verified that the filter is in place in the i
ventilation system of the decontamination facility at the St. Mary's Hospital in Russellville, Arkansas. A major drill of the emergency plan had not been accomplished. A Butler type building has been
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moved into place near the visitor center location to serve as an emergency control point, $f needed. However, the building had not been equipped in any way.
It was confirmed to the inspector during the management interview that determination will be made that the filter is in place at the St. Mary's Hospital. The practice d-111 of the Emergency Plan is scheduled for mid-December.
Assurance was l
received in the management interview that an Emergency control building will be fully equipped by the end of hot functional testing.
The
inspector stated during the management interview that this would be carried as an unresolved item.
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3.
Location of Meter and Chart Readings for Radiation Monitoring Instrumentation
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The inspector pointed out to licensee personnel that the read out meters and charts for radiation monitoring instrumentation were all located ('"'g outside the control room such that it would be necessary for personnel j
to leave the' control room to view the read outs.
%s Licensee management
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RO Rpt. No. 50-313/71-18 1-2
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was informed by telephone that.this would be carried as an unresolved l
item. There was no commitment by the licensee to modify this sitaa-tion. This item will be pursued with the licensee on the next inspec-
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l tion from the standpoint of obtaining assurance from the licensee that I
observations of these read outs will be adequate, consistent with maintaining adequate manning in the control room.
4.
Calibration of Radiation Monitors
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Calibration of area, liquid and gaseous monitors has not been completed. At the time of this inspection it was found that the calibration of the stack gas monitor flow was in progress.
A date for completion of calibration of all radiation monitors was not availabic, however, commitment was received from a manage-
ment representative that all of the calibrations will be completed prior to fuel loading. This item remains open.
5.
Completion of Radiological Waste Disposal Systems The status of completion of the solid waste systems remaina un-changed. Management position is that this has low priority at
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the present time because capability exists to store spent resins l
for one year. The facilities for spent resia disposal have not
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been completed as described in Section 11.1.3.3 of the FSAR, therefore, this item remains open.
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6.
Gaseous and clean Radwaste Systems Test Procedures Radwaste system procedures TP232.72, Gaseous Radwaste System
Acceptance Test and TP 230.68, Clean Radwaste Acceptance Test
Procedure were both found to be apparently inadequate in full-filling the test acceptance criteria as specified in the proce-l l
dures. Detailed review of the procedures with licensee and
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Bechtel representatives revealed that TP 232.72, Gaseous Radwaste System Acceptance Test, does satisfy the test acceptance criteria, therefore, this part of the unresolved item is considered closed.
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Detailed review of TP 230.68, Clean Radwaste Acceptance Test Procedure revealed that this procedure still apparently fails to meet the test criteria. The licensee and Bechtel representatives
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agreed cnat the procedure (TP 230.68) will be revised to satisfy
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the test criteria. They stated that this would be accomplished at the conclusion of hot functional testing. Management agreed
with this position at the time of the exit interview.
7.
Respiratory Protection Program and Procedures-The licensee's procedure entitled Selection and Use of Respiratory Protection Equipment, 1602.03, was reviewed in draft form and
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comments furnished to the licensee representative responsible for the procedure. The respiratory protection program was incomplete k
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i in that storage for masks had not been installed and training was not considered complete. Licensee representatives stated that they hope to complete thu mask storage and training within two to three weeks. This understanding was confirmed with management during the exit interview.
8.
Representative Sampling of Gaseous Wastes
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Inspec. tion rev.ealed that no measures had been taken to minimize halogen condensation losses in the portions of the stack monitor sample delivery lines that are located outside buildings. A manage-ment representative informed the inspector that the stack sample lines outside buildings will be insulated to minimize halogen condensation losses in the sample lines.
9.
Moisture separators Moisture separation capability had not been provided for the 8aseous waste discharge filter of the gaseous radioactive waste
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system shown in FSAR Figure No. 11-3.
When asked if moisture buildup in these filters would not be a problem, a licensee representative stated that there were no plans to provide moisture protection.
N 10. Laundry Dryer Exhaust
The laundry dryer exhaust had been found to be installed to exhaust directly to the room. This inspection revealed that this had been corrected by connecting the laundry exhaust to the ventilation duct as originally planned.
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