IR 05000333/1985024
| ML20137X154 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 09/24/1985 |
| From: | Holsopple K, Mark Miller, Pasciak W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20137X152 | List: |
| References | |
| 50-333-85-24, IEB-79-19, NUDOCS 8510040466 | |
| Download: ML20137X154 (10) | |
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U.S. NUCLEAR REGULATORY COMMISSION
REGION I
Report No.
50-333/85-24 Docket No.
50-333 License No.
OPR-59 Priority
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Category C
Licensee:
New York Power Authority P. O. Box 41 Lycoming, New York Facility Name: James A. FitzPatrick Nuclear Power Plant Inspection At:
Scriba, New York Inspection Conducted: August 19-23, 1985 Inspectors:
h$td[N///dA.,
f.3!/I M. M111er, Radiltlon Specialist Idatd
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,Rpiatif1 Specialist
' dat Approved by:
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j j(tb (N.' Pas 6iik, Chief,BWRRadiological d e Protection Section Inspection Summary:
Inspection on August 19-23,1985 (Report No. 50-333/85-24)
Areas Inspected:
Routine, unannounced safety inspection of the licensee's Ra-dioactive Waste Management Program and improvements to the Post Accident Sam-pling System including:
licensee action on previously identified items, man-agement control, training, liquid waste processing, solid waste processing and packaging, quality assurance, surveillances, and low level radioactive waste storage.
The inspection involved 76 inspector-hours onsite by two region-based inspectors.
Results: No violations were identified.
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4 DETAILS i
i 1.0 Licensee Personnel I
- R. Converse, Resident Manager i
- W. Fernandez. Superintendent of Power
- D. Lindsey, Operations Superintendent
- E. Mulcahey, Radiological and Environmental Services Soperintendent (RESS)
- R. Patch, Quality Assurance Superintendent
- R. Locey, Assistant Operations Superintendent and
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Acting Waste Management General Supervisor
- A. McKeen, Assistant RESS i
T. Bergene, ALARA Supervisor
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- B. Gorman, Chemistry General Supervisor L. Johnson,.QA Supervisor
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E. Isern, Site-Engineer S. Masciulli, Supervisory Radiat!nn Engineer (Corp.)
D. Robert, Radiological Waste Supervisor R. Sarkissian, Assistant Shift Supervisor K. Szeluga, Radiation Protection Supervisor
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J. Wierowski, Radiation Protection Training Supervisor A. Young, Decontamination and Shipping Supervisor D. Grodi, Assistant QA Engineer J. Austin, Nuclear Operator Grade C C. Camerchioli, Nuclear Operator Grade C K. Wells, RES Senior Technician
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The inspector also contacted other licensee and contractor employees
during the inspection.
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- Denotes attendance at exit interview, i
2.0 The purpose of the routine safety inspection was to review the licensee's Radioactive Waste Management Program and status of Post Accident Sampling
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System ~ follow-up items.
The following areas were reviewed:
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Status of Previously Identified Items j
Radioactive Waste Management Control
Training
Liquid Waste Processing
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Solid Waste Processing and Packaging
l Quality Assurance
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Radioactive Waste Surveillances Low Level Radioactive Waste Storage Facility
3.0 Status of Previously Identified Items 3.1 (Closed) Inspector Follow-up Item (333/80-20-22):
Expedite repair of augmented Off-Gas Treatment System to permit operation. The inspector noted that the recombiner and charcoal filters for the Off-Gas System were operational after the 1985 refueling outage as committed to NRC by licensee management. Mod-ifications and repairs to the system to ensure operability included refrigeration units to improve dew points and new hydrogen monitors.
3.2 (Closed) Inspector Follow-up Item (333/84-09-02):
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Provide method for shipment tracking when burial site receipt is not received. The inspector reviewed procedure F-0P-48A, " Documentation of Radwaste Shipments", Revision 7 dated July 10, 1985.
Procedural steps had been addressed to track shipments, investigate and report to the NRC, if verification of receipt of shipment was not received from the burial site within twenty days of transfer from the FitzPatrick site.
-3.3 (Closed) Inspector Follow-up Item (333/84-09-03):
Improve training of RES Technicians in Transportation Area. The inspector reviewed a four day training program entitled, " Radioactive Material Packaging, Transportation and Disposal" which addressed the requirements of.IE Bulletin 79-19. The training program for RES technicians was verified by the inspector to have been completed on January 28, 1985. A two year training cycle has been specified.
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inspector noted lab exercises using the Radman computer program was a
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part of the training curriculum.
3.4 (Closed) Inspector Follow-up Item (333/84-24-01):
Revise the PASS procedure to assure that no dilution water is held t
up in the line. The inspector noted procedure PSP-17 was revised to address injecting air into the dilution line to prevent water hold-
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up.
3.5 (C'osed) Inspector Follow-up Item (333/84-24-02):
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Revise the PASS procedure so that personnel are aware of the proper loading and installation of iodine / particulate filter assembly.
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The inspector noted that instructions were =dded to PSP-17 delinea-l
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ting proper loading and installation of the iodine / particulate filter assembly.
In addition, the inspector observed this assembly was color coded to aid technician handling.
3.6 (Closed) In'spector Follow-up Item (333/84-24-10):
Address sample purging and-in plant field analysis in applicable procedures.
Sample purging to remove trapped noble gases from iodine cartridges was included in the applicable procedures.
3.7 (Closed) Inspector Follow-up Item (333/84-24-12):
Calibration. stickers to instruments on PASS panel were incorrectly filled in. The inspector observed that new calibration stickers had been attached to the instruments which included the " calibration due date".
3.8 (Closed) Unresolved Item (333/85-18-03):
Ball valve in PASS panel observed leaking during 1985 annual exer-cise. The inspector discussed with the General Chemistry Supervisor
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the actions taken by the RES technicians during the observed exer-cise.
In addition, the licensee stated that the water observed leaking was water from the dilution flask that escaped through a ball
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valve.
The licensee stated that there have been no reoccurrences of this problem. However, a new ball valve has been ordered and will be replaced.
The following inspector follow-up items remain open pending further corrective action in accordance with licensee commitments.
3.9 (0 pen) Inspector Follow-up Item (333/84-24-06):
Establish preventative ~ maintenance program for PASS. The licensee had drafted a formal preventative maintenance program for those PASS components recommended by the vendor.
This action should be c.om-pleted by December 31, 1985. With regard to coordinating calibra-tions between the RES and I&C departments, this action should be com-pleted by November 30, 1985.
The inspector noted that the PASS ra-diation monitor alarm setpoints were lowered to the level specified in the PASS Operating Procedure (PSP-17).
This procedure was re-vised also to address installation 'of silver zeolite cannisters during use of the PASS.
3.10 (0 pen)
InspectorFollow-upItem(333/84-24-08)
Improve particulate iodine sampling capabilities. The inspector noted emergency procedure EAP-21, Revision 7, " Meteorological Data Acquisition System" was revised to address incorporation of iodine
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results into the source term assessment process. -The licensee's other planned actions to improve particulate / iodine sampling were scheduled to be completed by December 31, 1985.
3.11 (0 pen) Inspector' Follow-up Item (333/84-24-09):
Improve high range containment monitoring.
The inspector reviewed an engineering evaluation that recommended one of the two contain-ment detectors he relocated to decrease direct dose rate effects from adjacent plant equipment. The licensee expects to complete
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this action during the 1986 refueling outage. The inspector also noted that procedure RTP-34, " Containment Radiation Monitoring-Post Accident".will be revised by October 31, 1985 to include specific response curves for estimating percent of core damage.
3.12 (0 pen) Inspector Follow-up Item (333/84-24-11):
Improve calibration for PASS monitors.
The licensee has made plans to procure a calibration source that would provide a three point radiation dose rate input for the four decade PASS monitors. The licensee expects to complete this action by November 30, 1985.
4.0 Management Control The. responsibility for the administration, technical direction and proper processing and shipment of radioactive waste is the function of the Waste Management General Supervisor.
The licensee had documented the management control for radioactive waste processing in Administrative Procedure No. 1, Revision 11 " Operating Staff Responsibilities and Authorities." The inspector discussed with the Waste Management General Supervisor, who was promoted recently to Assistant Operations Superintendent, the responsibilities and authorities designated in the Operations Department Organization chart, and as ad-dressed in the Radwaste Supervisory position descriptions. The inspector noted that a replacement for the WMGS had not been selected. The inspec-tor also discussed the recent change (July 1985) to a new vendor for operations and monitoring of the solidification process. A copy of the vendor's topical report was available and the vendor procedures were re-viewed by the Quality Assurance Department.
(For details, see Section 8.0 of this report).
The inspector reviewed selected program procedures and toured the Radwaste Control Room, Reactor and Turbine Buildings, dry active waste storage and compactor work area, and Mobile solidification area.
In addition, radwaste operators and the Radiological Waste Supervisor were interviewed to determine their knowledge of the liquid and solid radwaste systems and processin~g procedure _ _ -
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The inspector also discussed with the WMGS and the Decontamination and Shipping Supervisor, the following management programs: Water Inventory
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Balance, Volume Reduction and Material Control, and Reclamation of Con-taminated Areas. These programs were receiving adequate management
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attention.
The licensee also stated that there were no Licensee Event Reports (LERs) associated with the Radwaste Systems for the past two l
years.
Within the scope of this review, no violations were identified.
5.0 Training
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Personnel training in radwaste processing and handling activities was
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reviewed against the criteria contained in IE Bulletin 79-19, " Pack-l aging of Low Level Radioactive Waste for Transport and Burial."
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i The licensee's performance relative to this criteria was determined by I
discussions with the Decontamination and Shipping Supervisor, RES Training Supervisor and radwaste operators, and by review of training
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documentation.
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Within the scopedf this review no violations were identified.
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6.0 Liquid Radioactive Waste Processing
6.1 Liquid Radioactive Waste Systems l
The licensee's liquid radioactive waste system was reviewed with respect to Technical Specification 6.8 " Procedures," for the collection, transfer, concentration and limiting of liquid waste, and ANSI N197-1976, "BWR Liquid Radioactive Waste Processing System," for proper operation and adequate maintenance of the system.
The licensee's performance in this area was determined by discus-sions with the Radioactive Waste Operations Supervisor, plant tours including the R/W Control Room, selected waste tank and pump cubicles, and review of operator shif t logs and procedure F-0P-49, Revision 16, " Liquid Radioactive Watte."
Within the scope of this review, no violations were identified. How-ever, the inspector noted that the liquid discharge goal for 1985, which was 2,000,000 gallons, would be exceeded slightly.
The licensee indicated this was because of many leaks in the turbine building closed loop heat exchangers. The inspector was informed that these heat exchangers were being replaced.
6.2 Liquid Effluent Releases
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The inspector reviewed the following procedure and records for liquid radioactive waste discharges to determine if the licensee was
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in compliance with the requirements of Environmental Technical Speci-fication 2.3, " Radioactive Discharge":
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Procedure ~No. F-0P-49, Revision 17, " Liquid Radioactive Waste
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System" i
Procedure No. PSP-4, " Waste Water Sampling and Analysis"
Liquid Radioactive Waste Discharge Permits for 1985
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Additionally, the inspector interviewed selected radwaste and chemistry personnel.
The inspector determined that the licensee was in compliance with
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l its Environmental Technical Specifications and implementing i
procedure.
I 6.3 Unmonitored Release Paths l
The inspector reviewed the licensee's surveillance program that ad-
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this review were Procedure No: PSP-9, " Miscellaneous Plant Systems l
Sampling and Analysis", and associated surveillance records for 1985.
f Additionally, the inspector interviewed selected chemistry personnel.
No items of noncompliance were identified.
i 6.4 Radwaste Modifications The inspector reviewed a list of modifications requested for the Radwaste System. The list included modifications that were re-
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quested back to 1976. The inspector noted that the intent of the majority of the modifications was to reduce occupational radiation i
exposure.
L Through discussions with licensee's ALARA staff, both at the J. A.
FitzPatrick site and at the White Plains Office, it was determined
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that no formal ALARA review was performed for these modifications.
However, the licensee was currently developing a program that would facilitate detailed ALARA reviews for requested plant modifications.
The inspector stated to the licensee that the implementation of this program is encouraged and will be reviewed in a future inspection (50-219/85-24-01).
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7.0 Solid Waste Processing and Packaging The licensee's solid radioactive waste program was reviewed with respect to Technical Specification 6.8, " Procedures," for the control, handling,
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packaging and limiting of solid radioactive waste, and 10 CFR 50.59,
" Changes, tests and experiments," for changes to the solid radioactive waste systems.. The licensee's program for waste solidification and com-pliance to 10 CFR 61.55 and 10 CFR 61.56 was reviewed, 'owever the Tech-nical Specification for the Process Control Program was awaiting approval.
The licensee's performance in this area was determined by discussions with Radioactive Waste operations and shipping personnel and RES staff; plant tours including the Dry Active Waste (DAW) sorting and compactor area and mobile waste solidification area; review of safety evaluations for Radioactive Waste Systems; and review of selected program procedures including:
F-OP-48, Revision 8, " Solid Radwaste System," dated August 4, 1982
F-0P-488, Revisicn 10, " Waste Packaging and Handling", dated
August 29, 1984 F-0P-48C-9, Revision 0, " Handling Procedure for the NUS14-170 Cask"
F-0P-48E, Revision 0, " Radioactive Material Segregation," dated
November 16, 1983 SS.001, Revision G.1, " Process Control Program for Radwaste Solidifi-
cation" WACP-10.1.6, Revision 6, " Control of Modifications, Component
Changes, and Safety and Environmental Impact Reports," dated July 7, 1982 PSP-8, Revision 11, " Radioactive Material Shipping Procedure," dated
August 13, 1984 With the scope of this review, no violations were identified. However, the following concerns were identified.
Procedures and flow diagrams (operator aids) for the processin~g of
radwaste were being updated to describe the actual transfer opera-tions.
For example the former methods for transfer of solid waste to the centrifuge and transfer of spent resin via the spent resin pumps were detailed, along with the modified and currently implemented methods for transfer of solid waste to the mobile solidification system and transfer of spent resin via the waste concentrator pump.
This project was initiated January, 1984 and the completion of the revision of all the radwaste procedures is expected to be completed by December, 1985. The inspector noted that this project should be completed, as scheduled, given the numerous changes to the Radwaste Systems.
This item will be reviewed during a subsequent inspection (333/85-24-02).
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With regard to radwaste system changes, the inspector requested the
safety evaluation report for the use' of the mobile solidification system that had been used instead of the centrifuge since 1982. The inspector also noted that a new vendor had replaced the original vendor solidification system in July,1985.
The licensee indicated they were unable to locate the safety evaluation and believed that one may not have been performed.
The inspector discussed at the exit interview IE Circular No. 80-18, 10 CFR 50.59 Safety Evaluations for Changes to Radioactive Waste Treatment Systems to which the licensee stated they would review for applicability. Given the recent change to a new vendor solidifica-tion system, this recent change need only to be addressed.
This item is considered unresolved and pending review of the
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licensee'saction(333/85-24-03).
8.0 Quality Assurance
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The implementation of the licensee's Quality Assurance Program (QAP), as applied to the "Radman" classification / characterization program, was re-viewed against the cri'teria contained in 10 CFR 50, Appendix B and 10 CFR 20.311(d)(3).
The licensee's performance relative to this criteria was determined from l
discussions with the QA Supervisor, Associate QA Engineer, and the RES
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Supervisor; and from review of QA procedure reviews and monitoring reports for 1985 with regard to radioactive waste solidification and classifi-cation, and review of an independent appraisal (JAF:84-01) dated July,
1984.
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l Nithin the scope of this review, no violations were identified, however
the following concern was identified:
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Based on a review of 1984 and 1985 audit reports, additional QA
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surveillances should be made of the Radman computer program to ensure
compliance with 20.311 (d)(3).
The licensee stated increase sur-
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veillances had been planned for review of the PCP by performing a value line-up audit and that the Radman program will also be includ-ing as part of the surveillances.
This item will be reviewed during a subsequent inspection (333/85-24-04).
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'I 9.0 Radioactive Waste.Surveillances
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9.1 In-Place Filter Tests f
The inspector reviewed the reports for the 1985 in place filter I
a tests for the following filter trains with respect to Technical
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Specifications 4.7(B) and 4.11(A), and ANSI /ASME N510-1980, " Testing of Nuclear Air Cleaning Systems:
SGTS filter train
Control Room filter train
Technical Support Center filter train
Within the scope of this review, no violations were identified.
9.2 Effluent Monitor Calibration The inspector reviewed the 1985 calibration records for the following effluent monitors with respect to the Environmental Tech-nical Specification 2.3, " Radioactive Discharge" requirements and ANSI N13.10-1974, " Specification and performance of on-site instru-mentation for continuously monitoring radioactivity in effluents":
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l Liquid waste discharge monitor
Stack monitor
Vent monitors
Within the scope of this review, no violations were identified.
10.0 Low-Level Radioactive Waste Storage Facility The licensee has started construction of a Low-Level Radioactive Storage Facility at the James A. FitzPatrick site.
Projected completion is December, 1985. The licensee stated that the facility would provide 113 years storage for liners, 2 years storage for LSA waste and a trench for
~ 60 high level waste drums.
The plans for a second on-site storage building (a mirror image of the present building) are available, if addi-tional storage capabilities would be necessary af ter January 1986.
'11.0 Exit Interview The inspector met with licensee representatives (denoted in Section 1) at the conclusion of the inspection on August 23, 1985. The inspector summarized the purpose, scope and findings of the inspection. At no time during this inspection was written material provided to the licensee by the inspectors.
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