IR 05000397/1983016
| ML20023C451 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 05/04/1983 |
| From: | Book H, Wenslawski F, Yuhas G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML20023C441 | List: |
| References | |
| 50-397-83-16, NUDOCS 8305170343 | |
| Download: ML20023C451 (5) | |
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U. S. NUCLEAR REGULATORY COMMISSION
REGION V
Report No.
50-397/83-16 Docket No.
50-397 License No.
CPPR-93 Licensee:
Washington Public Power Supply System (WPPSS)
P. O. Box 968 Richland, Washington 99352 Facility Name:
Washington Nuclear Project No.2 (hWP-2)
Inspection at:
kWP-2 Site, Benton County, Washington Inspection conducted:
April 18-22, 1983 b
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$ /4 /(f 3 Inspector:
G. P. Ytdras Radiation Specialist Ddte ' Signed D
Approved By:
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F. A. Wenslawski, Chief DatV Signed Reactor Radiation Protection Section Approved By:
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//H. E. Book, Chief Datt Signed rft Radiological Safety Branch Summary:
Inspection on April 18-22, 1983 (Report No. 50-397/83-16)
Areas Inspected: Routine, unannounced preoperational inspection of the licensee's radioactive waste management systems including: review of the preoperational test program, status of gas, liquid, and solid waste treatment systems, and review of several preoperational test procedures.
The licensee's response to several IE Bulletins, Circulars and Information Notices were also reviewed. During this inspection, the inspector participated in a meeting between licensee representatives, NRC Nuclear Material Safety and Safeguards, and Region V licensing personnel regarding a seperate byproduct material license for the Emergency Operating Facility (EOF). The inspection involved 32 hours3.703704e-4 days <br />0.00889 hours <br />5.291005e-5 weeks <br />1.2176e-5 months <br /> onsite by one regionally based inspector.
Results: Of the areas inspected, no items of noncompliance were identified.
8305170343 830505 PDR ADOCK 05000397 O
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DETAILS 1.
Persons contacted
- G.
K. Afflerbach, Assistant Plant Manager
- J.
W. Baker, Acting Operations Manager
- R.
Barbee, Plant Engineering Supervisor
- L.
G. Berry, Health Physics Supervisor C. A. Cauthon, Planner Scheduler A. I. Davis, Radiochemist S. Denison, Principle Engineer
- R. G. Graybeal, Health Physics / Chemistry Manager R._J. Hintz, Health Physicist H. J. Hodges, Startup Engineer
- M. M. Monopoli, Manager, Operations Assurance Programs R. B. Koch, TST Group Supervisor D. E. Larson, Manager Radiological Programs
- J.
F. Peters, Plant Administrative Manager N. W. Pike, Startup Engineer G. C. Sorensen, Manager Regulatory Programs J. M. Thomas, Startup Engineer
- Indicates those individuals attending the exit interview on April 22, 1983.
In addition to the individuals noted above, the inspector met with and held discussions with other members of the licensee's staff.
2.
Licensee Action on IE Bulletins, Circulars and Information Notices The licensee has implemented two procedures to assure appropriate processing and utilization of NRC and other external operational experience sources. These procedures; WNP-2, Project Instruction PMI-10-4, " Processing of NRC Inspection and Enforcement Bulletins, Circulars and Information Notices;" WNP-2 Plant Procedure 1.10.4,
" External Operational Experience Review," were reviewed and found to
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contain sufficient guidance. The licensee's response to the NRC documents listed below focused on implementation of the two procedures l
for each item. The item is considered closed if the licensee received
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the document, put it into the system, and is developing or has developed an appropriate response to the information provided.
(Closed) IEB-80-03, " Loss of Charcoal From Standard Type II, 2-inch Tray Absorber Cells." The licensee responded to this concern in a March 18, 1980 letter to Region V (G02-80-68). This letter stated that the absorber cells would be inspected on delivery.
A March 15, 1983, WPPSS Memorandum to File NSAG-0ER 80043A documenting inspection of the Control Room and Technical Support Center absorber cells was reviewed. No problems were identified by the inspection.
(0 pen) IEC-79-21, " Prevention of Unplanned Releases of Radioactivity."
This document was received, however, it has not been put into the system and the review is incomplete.
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(0 pen) IEC-80-14, " Radioactive Contamination of Plant Demineralized Water Systems and Resultant Internal Contamination of Personnel." This document has been received and reviewed.
It has not been put into the system and the administrative controls recommended, have not been implemented.
(0 pen) IEC-80-18, "10 CFR 50.59 Safety Evaluations For Changes to Radioactive Waste Treatment Systems." This document has been received, it is not in the system, and the review or actions to be taken have not been documented.
(Closed) IEC-81-07, " Control of Radioactively Contaminated Material."
The licensee received, reviewed and implemented appropriate actions in the form of Plant Procedures. Although this item is closed, the inspector discussed with the licensee's representative the need to include this item in their system.
(0 pen) IEC-81-09, " Containment Effluent Water that Bypasses Radioactivity Monitor." This item has been received and reviewed, however, it has not been handled in the licensee's system.
(Closed) IEN-82-43, "Deficiences in LWR Air Filtration / Ventilation Systems." This item has been received, reviewed and implemented in accordance with the licensee's system. The inspector noted that filters in Chemistry Laboratory and Hot Shop fume hoods had not been addressed in the review. This was discussed with the licensee representative.
(Closed) lEN-82-51, "Overexposures in PWR Cavities." This document was received, and reviewed in accordance with the licensee's system. The inspector emphasized the need to assure that licensed operators are made aware of how these circumstances apply at their facility.
(Closed) IEN-82-49, " Correction for Sample Conditions for Air and Gas Monitoring." This document has been received, reviewed, and is being handled in accordance with the licensee's system.
(Closed) IEN-83-05, " Obtaining Approval for Disposing of very Low-Level Radioactive Waste - 10 CFR Section 20.302."
This document has been received, and is being processed in accordance with the system.
(Open) IEN-83-10, " Clarification of Several Aspects Relating to Use of NRC-Certified Transport Packages." This document has been received but has not been entered into the system.
(Closed) IEN-83-14, "Dewatered Spent Ion Exchange Resin Susceptibility to Exothermic Chemical Reaction." This document has been received, and reviewed in accordance with the licensee's system.
3.
Byproduct Radioactive Material and the Emergency Operations Facility (EOF)
The licensee submitted a request for a separate license to use radioactive material at the EOF. The EOF is located within the WNP-2 site boundary and use of radioactive material could also be permitted pursuant to the reactor license. A meeting to discuss the licensee's
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application was held an April 21, 1983. As a result of these discussions one item surfaced which will require further action. The licensee representative stated their intention to transport radioactive materials from WNP-2 to the EOF without meeting the packaging and shipping requirements ' expressed in the Department of Transportation regulations.
This onsite transport would be made using the WNP-2 access road.
Except during emergencies, use of this road which runs through the site,is not restricted. The road is used for access to the Bonneville Power Authority's H. J. Ashe Substation and by members of the general public.
The extent to which this road will be used to transport radioactive materials from WNP-2 to the EOF will be reviewed in subsequent inspection.
(50-397/83-16-01)
4.
Radioactive Waste Management Systems The inspector reviewed the "WPPSS Test and Startup Administration Responsibilities, Controls, and Procedures, Program Manual," Revision 19 to gain a better understanding of how the licensee plans to implement the commitments presented in Chapter 14, of The Final Safety Analysis Report (FSAR).
The status of gaseous, liquid and solid radwaste systems were determined from review of the Startup Test Index and discussions with the responsible Test Engineers. None of the systems of interest have been turned over for preoperational tests.
It appears most preoperational tests of the radwaste systems will be performed from May through July 1983. Several systems have been provisionally accepted and system lineup tests are in progress. The following preoperational procedures which have been drafted and approved by the Test Working Group (TWG) but not yet approved by the Startup Manager were reviewed by the inspector.
System Number / Title TWG Approval PT-033.0A Chemical Waste Processing 81-25 PT-035.0A Radioactive Drains and Sumps 79-27 PT-036.0A Process Safety Monitoring 83-05 PT-036.0D Liquid Process Stream 83-05 PT-036.0E Liquid Effluent Stream 83-05 PT-106 D Radwaste Building Sampling 83-13 One System Lineup Test, SLT 85.1, "Radwaste Building HVAC Dalancing" was reviewed in combination with preoperation test PT-85.0A, "Radwaste Building HVAC System." All procedures were reviewed to evaluate compliance with Test and Startup Program, TSP-7, Revision 4, " Test Procedures." Based on this review, the following comments were offered to the licensee representatives:
System Number Comment PT-033.0A Steps 5.1.1.3 and 5.1.1.4 appear to have water level too high. Steps 5.2.1.8,..
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23, 5.3.1.13 and 5.3.1.25 need acceptance criteria.
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PT-035.01.
Steps 5.10 and 5.10.13 appear to be addressing the-Turbine Building Equipment Drain Sump rather than the floor drain sump.
PT 36.0A These procedures all assume the radiation monitoring PT 36.0D equipment has been calibrated by the SLT. TSP-7 under PT 36.0E
"I. Generic and Specific System Lineup Tests" does not require the procedure format include " Acceptance Criteria."
PT 106.D This procedure does not address a determination of the minimum sample flush times for each system.
PT 85.0A Neither procedure requires verification of flow direction SLT 85.1 from areas of low contamination to those of potential high contamination. SLT 85.1 does not include acceptance criteria. An inspection of the Post Accident Sample Station room did not identify an exhaust duct intended to keep the room negative with respect to surrounding areas.
The lack of an installed flow measuring and recording device on the Radwaste Building exhaust will likely complicate evaluations of effluent releases.
Based on this review the inspector discussed with licensee management the advisibility of including " Acceptance Criteria" in the SLT procedures.
The licensee representative responded by stating that SLT's frequently reference vendor data sheets which typically include acceptance criteria that have been reviewed and approved by the TWG.
Since the inspector's sample size was small during this inspection, this matter will be reviewed during a subsequent inspection.
(50-397/83-16-02)
No items of noncompliance or deivations were identified in this area.
5.
Exit Interview The inspector met with the licensee representatives (denoted in paragraph 1) at the conclusion of the inspection on April 22, 1983. The inspector summarized the scope and findings of the inspection.
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