IR 05000320/1985099
| ML20203B171 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 07/08/1986 |
| From: | Murley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Standerfer F GENERAL PUBLIC UTILITIES CORP. |
| References | |
| NUDOCS 8607180060 | |
| Download: ML20203B171 (3) | |
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JUL 0 81986
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i Docket No. 50-320 GPU Nuclear Corporation ATTN: Mr. F. R. Standerfer Vice President / Director, TMI-2 P.O. Box 460 Middletown, Pennsylvania 17057 Gentlemen:
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SUBJECT: SYSTEhATIC ASSESSMENT OF LICENSEE PERFORMANCE (SALP);
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REPORT NO. 50-320/85-99 This letter refers to the SALP of Three Mile Island Unit 2 for the period May
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1, 1984 to February 28, 1986, initially forwarded to you by our May 8,1986 This SALP evaluation was discussed with you and 22,1986 (see Enclosure 2 for attendees)your 1etter (Enclosure 1).
We staff at a meeting held on May
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have received your June 4,1986 letter (Enclosure 3) indicating that you did not desire to make written comments on our report. We herewith transmit our final report (Enclosure 4). We have made no changes to the original May 8, 1986 report. Note, however, that the report number in our May 8,1986 letter was in error; it should be 85-99 vice 86-99.
Our overall assessment is that you and your stiaff demonstrated competent
- nanagement, exercised good control over your defueling and cleanup activities, maintained a positive attitude and have been responsive to NRC concerns.
Your cooperation in the SALP program is appreciated.
Sincerely, Origi'nal signed by Tho:cas E. Murley, Thomas Regional Administrator
Enclosures:
1.
NRC Region I Letter, T. to F. R. Standerfer, May 8, 1986 2.
SALP Meeting Attendees 3.
GPUN Letter, F. R. Standerfer to T. E. Murley, June 4,1986 4.
SALP Report 50-320/85-99 8607180060 860708
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JUL 0 81986 GPU Nuclear Corporation
REGION I==
431 PARK AVENUE o,
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MAY 0 81996 Docket No. 50-320 GPU Nuclear Corporation ATTN:
Mr. F. Standerfer
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l Director of THI-2 P. O. Box 480 Middletown, Pennsylvania 17057 i
Gentlemen:
Subject:
Systematic Assessment of Licensee Performance (SALP); Report No.
50-320/86-99
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The NRC Region I SALP Board convened on April 3, 1986 to evaluate the performance of activities associated with the Three Mile Island (Unit 2) Nuclear Generating Station. The results of this assessment are documented in the enclosed SALP report, which covers the period May 1,1984 to February 28, 1986. A meeting to discuss the report is scheduled for 1:30 P.M. on May 22, 1986 at the NRC Region I office in King of Prussia, Pennsylvania.
At the meeting you should be prepared to discuss our assessment and any plans you have that will effect your performance.
In particular, we request you be prepared to discuss your plans to improve staff performalice in the development and review of new procedures. Any comments you have regarding our report may be discussed at the meeting. Additionally, you may provide written comments within twenty days af ter the meeting.
Following our meeting and receipt of your response, the enclosed report, your response, and a summary of our findings and your planned actions will be placed in the NRC Public Document Room.
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Your cooperation is appreciated.
Sincerely,
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II Thomas Regional Administrator n
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GPU Nuclear Corporation
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T. F. Densitt, Deputy Director, TMI-2 R. E. Rogan, Licensing and Nuclear Safety Director J. J. Syrne, Manager, TMI-2 Licensing W. H. Linton, Manager, Recovery Programs J. B. Lieberman, Esquire A. Miller, Manager, Plant Operations Ernest L. Blake, Jr., Esquire S. Levin, TMI-2 Site Operations Director Public Document Room (PDR)
local Public Document Room (LPDR)
Nuclear Safety Information Center (NSIC)
NRC Resident Inspector
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Commonwealth of Pennsylvania
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Enclosura 3
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GPU Nuclear Corporation
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M Nuclear
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Middletown. Pennsylvania 17057-0191 717 944 7821 TELEX 84-2306 Writer's Direct Dial Number:
(717) 948-8461 4410-86-L-0095 Document ID 0437A June 4, 1986 Office of Inspection and Enforcement-Attn: Dr. T. E. Harley Regional Administrator US Nuclear Regulatory Commission
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Region I 631 Park Avenue King of Prussia, PA 19406
Dear Dr. Murley:
Three Mile Island Nuclear Station, Unit 2 (TMI-2)
Operating License No. (FR-73 Docket No. 50-320 Systematic Assessment of Licensee Performance Report Your letter dated May 8,1986, transmitted the Systematic Assessment of Licensee Performance (SALP) Report for TMI-2 for the period of May 1, 1984, to February 28, 1986. GPU Nuclear views the report findings as objective, favorable and reflective of the GPU Nuclear commitment to excellence in every aspect of the recovery operation.
During the meeting on May 22, 1986, at the NRC Region I, GPU Nuclear representatives discussed prior and ongoing efforts tndertaken to improve the development and review process for new procedures. This issue was specifically identified as an issue of concern in the SALP Report. Based on an apparent favorable respcnse to our presentation, GPU Nuclear considers the ongoing actions appropriate, our response satisfactory, and elects not to provide a written response to the subject report.
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i GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation
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Dr. msrley-2-June 4, 1986
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4410-86-L-0095 GPU Nuclear emphasizes that-we will continue to strive for excellence in all areas related to the recovery operation at TMI-2 with particular emphasis directed to continued improvement of the procedural development, review and approval process.
Sincerely,
/s/ F. R. Standerfer F. R. Standerfer Vice President / Director, TMI-2 i
FRS/RDW/eml
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cc: Director - THI-2 Cleanup Project Directorate, Dr. W. D. Travers i
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Enclosure 4
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U. S. NUCLEAR REGULATORY COMMISSION j
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REGION I
SYSTEMATIC ASSESSMENT OF LICENSEE PERFORMANCE GPU NUCLEAR CORPORATION THREE MILE ISLAND UNIT 2
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MAY 1,1984 to FEBRUARY 28, 1986 I
i April 3, 1986
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SUMMARY (5/1/84 - 2/28/86)
THREE MILE ISLAND UNIT 2 HOURS
% OF TIME
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Shutdown Plant Operations /
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Defueling Preparation 2937
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Radiological Controls
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Effluent Monitoring and Control 400
328
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Quality Assurance 233
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Maintenance 6.
Design, Engineering and Modifications N/A N/A 7.
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Security
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Licensing Activities N/A N/A Total 6009 100%
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TABLE 2 INSPECTION ACTIVITIES L.
THREE MILE ISLAND UNIT 2 INSPECTION REPORT NUMBER AREAS INSPECTED 84-09 Resident inspection
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-10 Resident HP inspection, radwaste
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-11 Resident inspection, preparation for
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head lift
-12 Quality Assurance Program-13 Review licensee's failure to close and deactivate isolation valve on "A" purge train with second isolation valve inoperable-14 Plant operations, radioactive material shipments, Resident HP inspection, radiological control practices-15 Resident HP inspection, reactor building operation
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-16 Reactor operator examinations-17 Resident inspection, plenum lift preparations-19 Resident inspection, polar crane modifications-20 Security plan and implementation of security programs
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-21 Resident HP inspection, dosimetry-22 Operational radiological environmental
- J monitoring program-23 Resident inspection
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-24 Resident inspection
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T2-2
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h-25 Resident HP inspection 85-01 Resident inspection Protection of Safeguards Information i-02-03 Unplanned radiation exposure to skin of three individuals-05 Enforcement Conference Security plan and implementation of-06 security programs-07 Enforcement Conference-08 Resident inspection-09 Reactor operator examinations-10 Resident inspection, plenum Iift preparation-11 Defueling Water Cleanup System design and fabrication-12 Resident inspection-13 Examination of the requalification program for certification of presently licensed SR0s to directly supervise defueling operations-14 Resident inspection-15 Resident HP inspection, misclassified f
radioactive waste material shipped from site
-16 Resident inspection-17
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Reactor operator examinations-18 Resident inspection, defueling preparation-19 Resident inspection, defueling-l
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operations
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Special inspection conducted to-20 evaluate method of determining Sr-90 by beta spectroscopy ResidenE inspection, de' fueling-21 operation Resident inspection, defueling 86-01 operations Resident inspection-02 Reactor operator examinations-03
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D TABLE 3 ENFORCEMENT DATA THREE MILE ISLANO dNIT 2 A.
Number and Severity Level of Violations and Deviations 1.
Severity Level Deviations
Violations S.L. I O
Violations S.L. II
Violations S.L. III
Violations S.L. IV
Violations S.L. V
Total
B.
Violations and Deviations vs. Functional Area
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FUNCTIONAL AREAS I
II III IV V
DEV 1.
Shutdown Plant Operations /
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Defueling Preparation
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Radiological Controls 3.
Effluent Monitoring and Control
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Quality Assurance
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Maintenance 6.
Design, Engineering and Modifications 7.
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Security
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Licensing Activities
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- Violation not applicable to activities during assessment.
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Summary Inspection Severity Summary of Report No./Date
. Level / Functional Area-Violation 84-09 V
Failure to post a 4/24/84-5/30/84 Rad Con Notice of Violation involving radiological working conditions as required by 10 CFR Part
84-10 V
Failure to calibrate a 5/14/84-5/29/84 Effluent Monitoring radioactive process effluent monitor' in accordance with writter, procedures 84-13 IV Violation of Technical 5/25/84-6/29/84 Operations Specification limiting condition of operation 84-21 IV Failure to control 10/16/84-11/26/84 Security Safeguards Information 84-21 IV Failure to adhere to 10/16/84-11/26/84 Rad Con Rad Con Procedure 85-01 V
Failure to attach Do 1/12/85-2/28/85 Maintenance Not Operate tag to inoperable breaker 85-01 V
Failure to check 1/12/85-2/28/85 Rad Con available dose for individual entering RWP area 85-03 III Failure to perform 1/14/85-1/22/85 Rad Con adequate rad survey 85-03 III Failure to adhere to 1/14/85-1/22/85 R'ad Con RWP 85-03 III Doses above 1/14/85-1/22/85 Rad Con administrative limits 85-06 IV Failure to properly j
3/4/85-3/8/85 Security control photo ID badges
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85-06 IV Failure to complete 3/4/85-3/8/85 Security annual physical fitness tests by three
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protection personnel 85-08 IV Failure to comply with 3/1/85-4/10/85 Maintenance procedures regarding ventilation system maintenance practices 85-10 IV Failure to comply with
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4/11/85-5/17/85 Security procedures regarding security practices 85-15 III Failure to properly 7/31/85-8/5/85 Rad Con package and classify
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waste in accordance with Reg Guide 85-16 V
Failure to inspect 8/6/85-9/6/85 Rad Con respiratory equipment 85-20 IV Failure to properly 9/30/85-10/2/85 Rad Con indicate Sr-90 content on rad material shipping papers 85-20 IV Failure to properly 9/30/85-10/2/85 Rad Con classify rachtaste shipment 85-20 IV Failure to properly 9/30/85-10/2/85 Rad Con indicate Sr-90 activity on rad material shipping papers 85-21 IV Failure to comply with 10/7/85-11/8/85 Operations a double isolation valve requirement
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85-21 IV Failure to perform
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10/7/85-11/8/85 Rad Con adequate surveys prior to entry I&E Headquarters &
II Personnel harassment 01 Report Operations i
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b TABLE 4 LERhYNDPSIS THREE MILE ISLAND UNIT 2 May 1, 1984 - February 28, 1986 LER Number Summary Description Operation of RB purge system outside bounds of 84-007 Technical Specifications Examination and evaluation of pressure and level 84-008 transmitters for core flood tanks Incore thermocouple N-4 was declared inoperable 84-009 84-010 Operation of containment isolation valves without proper administrative approval
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Exceeded timeclock without enter.ng action statement i
84-011 after defeating the Control Room' air inlet radiation monitor, HP-R-220, interlock Failure to test within the required interval a Fire 84-012 System detector located in Control Building Reactor Building airlock doors were operated using a 84-013 Temporary Change Notice that had not been submitted to the NRC for approval 84-014 Representative reactor coolant samples were not obtained due to failure to verify opening a manually operated valve Hourly fire watch was not performed when a fire door 84-015 was breached Incore thermocouples M-3, 0-10 and F-3 were declared 84-016 inoperable Sections of submerged toe of the dike exhibited 84-017 evidence of degradation
"A" diesel generator was out of service to replace 84-018 cylinder assembly and exceeded timeclock
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.84-019 Action statement was not entered when the Fuel Handling Building ventilation exhaust flowrate dropped below the minimum limit of the Technical Specifications.84-020 The RCS sample performed through the TNS system was non-representative because sample line not adequately purged I
84-021 Incore thermocouples F-12, 0-5, and G-11 were declared inoperable 85-001 Minor degradation of the Flood Protection dike 85-002 Incore thermocouple E-4 declared inoperable 85-003 Incore thermocouple G-13 declared inoperable 85-004 Reactor Building Internal Pressure Indicator Registered Value in excess of Technical Specification limit 85-005 Reactor Building Internal Pressure Indicator Registered Value in excess of Technical Spec.ification limit
.85-006 Administrative error in operating procedure stating wrong valve position 85-007 Containment isolation valve operated without an NRC approved procedure 85-008 Fire Suppression System inoperable for Emergency Diesel Generator 85-009 Opened Containment Isolation Valve 85-010 Failure to test the TMI-2 Fire Suppression Water System Valves86-001 Inoperability of Emergency Diesel Generator exceeds
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7-day timeclock 86-002 Containment Isolation Valve opened without identifiable cause
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w TABLE 5 SIMiARY OF SIGNIFICANT LICENSING ACTIONS AND SUPPORTING ACTIVITIES
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THREE MILE ISLAND UNIT 2 This table provides a summary of significant licensing actions and related activities during the SALP evaluation period from the 1st of May 1984 through the 28th of February 1986.
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1.
Updates to the Programmatic Environmental Impact Statement (1 completed)
Issuance of a Final Supplement Dealing with Occupational Radiation
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Dose 2.
Major Cleanup Evolutions (21 completed, 6 ongoing)
Reactor Pressure Vessel Head Removal
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Head Removal SER
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Reactor Pressure Vessel Plenum Removal
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Plenum Removal Prep Activities SER
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Plenum Jacking SER Reactor Building Heavy Loads Analysis for Plenum Lift
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Polar Crane Auxiliary Hoist
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Plenum Load Drop Analysis Defueling Actions
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Defueling Canister TER *
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Boron Dilution Hazards Analysis
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Fuel Storage Rack TER
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Defueling Water Cleanup System TER, Rev. 4
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Heavy Load Handling SER for Defueling
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Filter Canister QA Approval *
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Fuel Pool "A" Refurbishment SER
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Reactor Building Decontamination and Dose Reduction Program SER
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Internals Indexing Fixture Processing SER
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Modifications of Fuel Canisters
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Modifications of Fines / Debris Vacuum System
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NES Canister Closeout
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Use of Debris Canisters
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Canister Handling - Preparations for Shipping *
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Reactor Building Sump Criticality *
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Temporary RCS Filtration System
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Defueling Water Cleanup System TER, Rev. 7-9 *
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Ancillary SDs, TERs and SERs (5 completed,1 ongoing)
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SER for Core Stratification Sample Acquisition *
Relocation of Missile Shields SER
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Purification Demineralizer SER - Cs Elution
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- Ongoing as of February 28, 1986 Submerged Demineralizer System TER Update
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Once Through Steam Generator Layup TER
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Containment Air Control Envelope TER
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4.
Other Documents in Support of Cleanup (6 completed, 2 ongoing)
Applicability of Seismic Design Criteria to GPUNC Recovery Efforts
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Clarification of the General Project Design Criteria
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Containment Access Control Envelope Design Criteria
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Solid Waste Staging Facility TER *
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Waste Handling Packaging Facility *
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GPU/0RNL Criticality Report
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Fuel Characterization in the Lower Vessel Head
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PWST and Recycle System / System Description
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5.
Exemptions (10 completed, 2 ongoing)
Waste Classification of EPICOR II Resin Liners
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In-Service Inspection *
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Core Accountability
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Fire Protection *
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Pressurized Thermal Shock
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Residual Head Removal System and Testing Requirements for the ECCS
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Code Safety Valves
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Seismic Monitoring Requirements
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FSAR Updating Requirements Relative to the QA Revisions
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Containment Penetration Design
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Seismic Requirements for Containment Penetrations
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Containment Isolation Valves
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6.
Changes to the Technical Specification Issued: 8
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Ongoing: 0
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7.
Recovery Operations Plan Change Requests Issued:
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Ongoing: 1
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License Amendments
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Issued: 2
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Ongoing: 2
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Organization Plan Changes l
Issued: 4
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10. Licensee / Commission Briefings - 2 Cleanup Schedule and Funding
- Ongoing as of February 28, 1986
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