IR 05000275/1985038
| ML20138R326 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 12/09/1985 |
| From: | Cillis M, Hooker C, Yuhas G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML20138R304 | List: |
| References | |
| 5-323-85-36, 50-275-85-38, 50-323-85-36, GL-85-08, GL-85-8, IEIN-85-052, IEIN-85-060, IEIN-85-52, IEIN-85-60, NUDOCS 8512310176 | |
| Download: ML20138R326 (8) | |
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U. S. NUCLEAR REGULATORY COMMISSION
REGION V
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Report Nos.
50-275/85-38 and 50-323/85-36 f
Docket Nos.
50-275 and 50-323 License Nos.
' Licensee:
Pacific Gas and-Electric Company i
77 Beale Streef.,; Room 1435
San' Francisco, California 94106
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Facility Name:
Diablo Canyon Units 1 and 2
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Inspection at:
San Luis Obispo County, California
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Inspection conducted:
November 18-22', 1985
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Inspectors:
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M. Cil'lis, Radiation Specialist
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C. A. Hooker, Radiation Specialist Date Signed i
Approved By:
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. G. P. ?qh'Ap,. Chief Dat'e $igned Facilitibs) Radiological Protection Section
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Summary:
Inspection on November 18-22, 1985 (Report Nos. 50-275/85-38 and 50-323/85-36)
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Areas Inspected: Routine unannounced inspection by regionally based inspectors of licensee action on previous inspection' findings, transportation activities, solid waste management program, low-level waste management, review
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of licensee events, audits and records, facility tours, followup on
.Information Notices and Generic Letters.
Inspection procedures 84722, 86721, 84850, 92702 and 93702 were covered. The inspection involved 64 hours7.407407e-4 days <br />0.0178 hours <br />1.058201e-4 weeks <br />2.4352e-5 months <br /> onsite
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by two NRC inspectors.
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l Results: No violations or deviations were identified in the eight areas inspected.
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8512310176 851210 gDR ADOCK 05000275
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DETAILS 1.
Persons Contacted A.
PG&E Personnel
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C.'Thornberry, Plant Manager R. Patterson, Plant Superintendent -
- J.-M'_Gisclon, Assistant. Plant Manager, Technical Services
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- W. B. Kaefer, Assistant Plant Manager, Support Services
- D..A. Taggart, Acting Director, Quality Support, QA
- J. V. Boots, Manager, Chemistry and Radiation Protection
- J.lA. Sexton,, Manager, Operations Department
- R.,P. Powersi Senior,Che~mistry and Radiation Protection Engineer
- T. L. Grebel, Senior Regulatory Compliance Engineer M.'J. Peterson,. Senior Chemistry and Radiation Protection Engineer C. C. Miller,' Chemistry and Radiation Protection Engineer L'.fA. Vulchev, Chemistry and Radiation Protection Foreman R. L. Ewing,= Shift Foreman, Operations M. E. Craig, Senior Control ~ Operator K. R. Bieze, Chemistry and Radiation Protection Training Supervisor J. Polewczak, Auxiliary -Operator R. N. Clark,-Foreman, Chemistry and Radiation Protection
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J. A. Hayes, Foreman, Chemistry and Radiation Protection B.
N2_C Resident Inspectors T. M. Ross, Resident Inspector M. L. Padovan, Resident Inspector T. J. Polich, Resident Inspector
- Denotes those present at the exit interview on November 22, 1985.
In addition to the individuals identified above, the inspectors met and held discussions with other members of the licensee's and contractor's staff.
2.
Licensee Action on Previous Inspection Findings (Closed) Noncompliance (50-275/85-23-14 and 50-L/5/85-23-15): Violations concerning the fiilure to adhere to radiation protection procedures and the assignment of an unqualified Chemistry and Radiation Protection Technician in a responsible position. The inspectors verified that the licensee's response to the subject violations, as identified in PG&E letter DCL-85-297, dated September 10, 1985, was timely and the corrective actions outlined in the response were as described. The inspectors had no further questions regarding these matters.
(Closed) Open Item (85-23-13):
Inspection Repott 50-275/85-23, Paragraph 15.g.(2) documented discrepancies with the licensee's portable radiation detection instrument calibration program. The licensee's co-rective actions related to this item as provided in Paragraph B of En; osure 2 to PG&E letter, DCL-85-297, dated September 10, 1985, were verified and found acceptable. The licensee's staff informed the
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inspector that an instrument calibrator has been authorized for purchase in the 1986 budget.
The inspectors had no further questions regarding this matter.
(Closed) Open Item (85-02-01):
Inspection Report 50-275/85-02 documented discrepancies involving records of disposal for several small radioactive liquid sources possessed pursuant to NRC materials license No. 04-08134-03. This inspection disclosed that the licensee had corrected this item and incorporated changes in procedure RCP RW-1
" Collection, Packaging, Storage, and Inventory of Radioactive Waste," on April 1, 1985. These changes should be effective in preventing future problems in this area. The inspectors had no further questions regarding this matter.
3.
Radioactive Material Transportation The inspectors reviewed the licensee's radioactive ma.erial transportation program for compliance with the regulatory requirements prescribed in 10 CFR Parts 20.205 and 71, 49 CFR Parts 171 through 178,
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and the recommendations of NRC Regulatory Guides 7.1 through 7.10.
.A.
Management Controls
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'The. licensee's Quality Assurance program was found to b) consistent
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with the' QA requirements expressed in 10 CFR Part 71 Subpart H,
" Quality Assurance," and NRC Regulatory Guide 7.10, " Establishing Quality Assurance Programs for Packaging Used in the Transport of Radioactive Material."
B.
Procedures'
The following procedures were reviewed:
NPAP C-209 Advance Notification of Shipments of Nuclear Waste and Spent Fuel; NPAP D-502 Receipt of Radioactive Materials Shipments (HBPP and DCPP);
NPAP D-506 Radioactive Material Shipment; AP B-253 Radioactive Materials Packaging and Shipping Training Program; AP C-253S1 Dewatering Control Program; MP M-50.18 Radioactive Waste Transportation Cask Handling; RCP RW-4 Solid Radioactive Waste Shipment; RCP_RW-5 Receiving, Loading and Releasing of Transport Vehicle for Radioactive Waste Shipment; and
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RCP RW-10 Shipment of High Activity Radioactive Materials Using the PGandE Post Accident Sample Shipping Package.
-The above procedures and checklists used for shipment and receipt of radioactive materials provide instruction for assuring compliance with DOT and NRC regulations.
The inspectors reviewed implementation of the licensee's QA program with respect to the purchase of two Type B packages maintained by the licensee for transporting Post Accident Samples. The results of this review verified that the licensee had fully implemented their'
QA program.
s The licensee also maintained a burial site license, cask user / owner maintenance manuals, letters of authorization, maintenance records and procedures, and current DOT and NRC shipping regulations.
C.
Audits The inspectors discussed the licensee's QA audit and QC inspection, surveillance and review programs with licensee representatives. The
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licensee's initial QA audit cf radioactive material receipt, storage, handling, inventory, waste classification, shipping and transportation was performed during the period of November 4-14, 1985. The audit appeared to be comprehensive based on discussion with the licensee. The audit report and findings (Report No. 85270T) should be issued by December 13, 1985.
D.
Training and Qualifications The inspectors conducted interviews with several employees responsible for training and shipment of radioactive materials, and reviewed-lesson plans, training records and licensee qualification criteria. The inspectors noted that the C&RP staff involved in transportation activities had received specialized onsite training and had passed the licensee's examination to be qualified in this area.
E.
Radioactive Material Receipt and Shipment Records Selected licensee records for receipt add shipment of radioactive materials were reviewed for compliance with the requirements of licensee procedures NPAP D-502 and NPAP D-506, 10 CFR Part 20.205 and 71.5 and 49 CFR Parts 172.200-204, 173.415, 421, 425, 441 and 443.
The inspectors noted that the licensee had made four shipments of radioactive material during 1985 which consisted of two Type A shipments, one bulk exclusive use shipment of leased radioactive waste water demineralization equipment and one limited quantity shipment of Unit I reactor coolant samples. The licensee had not made any shipments of radioactive waste or shipments requiring Type B or NRC approved packages.
The licensee plans on shipping a batch of low-level waste drums by the end of 1985.
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F.
Transportation Incidents Discussions with licensee representatives established that no transportation incidents had occurred.
No violations or deviations were identified.
4.
Radioactive Solid Waste The inspectors reviewed the licensee's radioactive solid waste program for compliance with the requirements of 10 CFR Parts 20.311, 401 and 61.55, 56 and 50.59 and Technical Specifications 3.11.3, 6.8.1, 6.13 and the recommendations of NRC Regulatory Guides 1.143.
A.
Management Controls The Plant Manager has the overall responsibility for the solid radioactive waste activities, and the C&RPD is responsible for assuring compliance with regulatory requirements. The C&RPD had assigned a C&RP Engineer and a C&RP Foreman as key personnel responsible for solid and low-level radioactive waste activities.
B.
Procedures and Program Implementation The inspectors reviewed the following procedures:
AP C-253 Process Control Program; AP C-253SI Dewatering Control Program; AP C-254 Radioactive Waste Volume Minimization Program; AP C-256 Radioactive Waste Classification Program; AP C-257 Chem-Nuclear Systems, Inc. Mobile Equipment for Solidification and Demineralization Operations; RCP RW-1 Collection, Packaging, Storage, and Inventory of Radioactive Waste; RCP RW-3 Radioactive Waste Isotope Fractions and Correlation Factor Determination; RCP RW-4 Solid Radioactive Waste Shipment; RCP RW-7 Burial Site Disposal Criteria and Classification of Radwaste; RCP RW-8 Radioactive Waste Curie Content Calculations; RCP RW-9 UseJof the Drum Compactor; and TP TC-8503 Use of the. Box Compactor.
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It was noted that the licensee maintained procedures of the licensed contractor's process control program for radioactive waste solidification that had been approved by the licensee and were appropriately referenced in the licensee's procedures. The above procedures appeared to be comprehensive and provided instructions for evaluating, analyzing, and processing of solid radioactive wastes to comply with regulatory requirements.
C.
Processing and Storage The licensee had contracted the services of a vendor for onsite
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solidification of wastes and made a full revision of the process control program in 1984. The revision incorporated several vendor supplied programs to ensure that waste solidification met the
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requirements of 10 CFR Part 61.
Notification of this revision was submitted with the licensee's Semiannual Effluent Release Report dated August 29, 1984. The inspectors were informed by licensee representatives that they had not conducted any solidification of radioactive waste since the start of their licensed operations.
The inspectors toured the licensee's radioactive waste processing and storage facilities and inspected the waste separation area, drum compaction area, box compaction area, auxiliary building waste storage locations, waste solidification area, and the waste storage building. The inspectors noted that the licensee had started canstruction of additional facilities to increase their current waste storage capacity.
No violations or deviations were identified.
5.
Low-Level Waste Management The inspectors reviewed the licensee's program for control, classification, characterization, and shipment of low-level radioactive waste as required by 10 CFR Part 61.55 and 61.56.
The licensee had not disposed of any low-level waste; however, the inspectors noted from discussions, and by review of records, checklists, and procedures that the licensee classifies waste pursuant to 10 CFR Part 61.55.
The licensee also verifies that waste meets the characteristics of 10 CFR Part 61.56; and has procedures established for preparing waste manifests, and marking packages pursuant to 10 CFR Part 20.311.
The inspectors determined from a review of licensee procedures RCP RW-3,
" Radioactive Waste Isotope Fractions and Correlation," and APC-256,
" Radioactive Waste Classification Program," that acceptable methods have been established for' classifying and determining the waste activity content. The licensee used an offsite vendor for waste stream sample analysis to develop a set of normal expected nuclide concentrations and correlations for use in conjunction with the plant sampling and analysis programs to determine the radionuclide contained in each radioactive waste pacLage. Each waste stream is required to be sampled and analyzed
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No violations or deviations were identified.
6.
Onsite Review of Licenser Event Technical Specifications, Section 6.8.4.c requires the licensee to maintain procedures for monitoring of secor.dary water chemistry to inhibit steam generator tube degradation. Licensee's procedure OP F-5:II, " Chemistry Control Limits and Action Guideline for the Secondary Systems,"' Attachment 1, " Parameter / Action Guideline," Part A, " Steam Generator Blowdown System," requires the licensee, when in Mode 1, to initiate. Action Level?3 (reactor shutdown within four hours) when the cation conductivity is greater than 7 umho/cm or sodium concentration is greater than 500 ppb in the steam generator blowdown.
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On October 30,.1985, during Mode 1 operations, Unit I developed a main condenser tube leak that resulted in a cation conductivity level of 127 umho/cm and a sodium concentration of 1127 ppb. The licensee shut the
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unit down within four hours. The' inspectors elected to review the licensee's response and corrective actions to this event.
Based on discuss, ions with' licensee-chemistry personnel, review of chemistry sample data, review of licensee's p'rocedure OP F-5:II, the inspectors noted that the licensee had taken the proper corrective actions. The licensee's event report will be reviewed in the Region V office when submitted.
No violations or deviations were identified.
7.
Onsite Review of Incident.
On November 14, 1985, the licensee identified that an individual had entered a High Radiation Area (HRA) without contacting Radiation Protection (RP) as specified in the RWP special instructions of which he was aware.
In addition, this individual did not use a radiation monitoring device which continuously indicates the radiation dose rate in the area or a monitoring device which continuously integrates the radiation dose rate and alarms when a preset integrated dose is received as required by TS, Section 6.12.1.
The inspectors held discussions with the individual involved, operations personnel, RP personnel and reviewed the corrective actions being taken by licensee management.
Since this was a licensee identified problem, the individual received minimal exposure ( 2 mrem) and the licensee was taking proper corrective action the inspectors considered this matter closed.
No violations or deviations were identified; however, inspectors concerns were detailed to licensee representatives.
8.
Facility Tours The inspectors toured various areas throughout the auxiliary building of both units on two separate occasions. The inspectors made independent measurements of radiation levels using NRC ion chamber S/N 897 due for calibration on January 15, 1986. When touring HRA's on Unit I side the inspectors made confirmatory measurements and observed that the licensee's survey meter readings were in agreement with readings obtained by the inspectors.
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During the tours the inspectors observed that all radiation areas and HRA's were posted as required by 10 CFR Part 20.
Licensee access and posting controls for HRA's were noted to be consistent with TS, Section 6.12 and licensee procedures.
An examination of portable radiation and contamination survey meters and constant air monitors during the tours disclosed thct one personnel contamination survey meter No. RP 1.8.18 at the. waste drum compactor station was not operational. This was brought to the attention of the licensee who took immediate corrective action to correct this problem.
.The survey meter was not being used by individuals and no one had been working in this location that would have used it.
The inspectors also noted the plant to be very clean and free of clutter.
No violations or deviations were identified.~
9.
Followup on Information Notices The inspectors verified that the licensee had received and was in the process of taking or had completed action on Information Notice Nos. 85-52 and 85-60.
No violations or deviations were identified.
'10.
Followup on Generic Letter-The inspectors verified that the licensee had received and was in the proces's of taking action on the recommendations provided in Generic
- Lette r. 85-08, "10 CFR 20.408 Termination Reports - Format". The licensee's staff informed <the'~ inspectors that the recommendations
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provided in the~ Generic Letter'are expected to be included a new computer program ' system which fis in'the~ process of being installed. The
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licensee's staff, stated that they would continue to process termination reports in accordance with their existing procedures until such time that.
the computer program system'has been successfully installed and tested.
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No violations:or deviations were-identified.
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11.. Exit Interview
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LThe inspectors. met'withLthe 'icensee representatives (denoted in l
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.The scope and findings of the' inspection were summarized. The-licensee was informed that no. violations or deviations'were identified.
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