IR 05000010/1979009
| ML19249C858 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 07/17/1979 |
| From: | Barker J, Mcgregor L, Spessard R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19249C852 | List: |
| References | |
| 50-010-79-09, 50-10-79-9, 50-237-79-16, 50-249-79-14, NUDOCS 7909190207 | |
| Download: ML19249C858 (14) | |
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U.S. NUCLEAR REGULATORY COMMISSION
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OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-10/79-09; 50-237/79-16; 50-249/79-14 Docket No. 50-10; 50-237; 50-249 License No. DPR-2; DPR-19; DPR-25 Licensee: Commonwealth Edison Company Post Office Box 767 Chicago, IL 60690 Facility Name: Dresden Nuclear Power Station, Units 1, 2 and 3 Inspection At: Dresden Site, Morris, IL Inspection Conducted: June 1-30, 1979
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WS 7!73 Inspectors:
J. L. B
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L. D. McGregor p 77/79 7// 7! 72
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Approved By:
R. L. Spessard, Chief Reactor Projects Section 1 Inspection Summary Inspection on June 1-30, 1979 (Report No. 50-10/79-09; 50-237/79-16; 50-249/79-14)
Areas Inspected: Routine, announced resident inspection of maintenance activities; plant operations; physical protection - security organization; physical protection physical barriers; physical protection - access control (identification, authorization, badging, search and escorting);
physical protection - communications; general station training; radiation protection - operations; thermal power evaluation; radioactive waste systems - operations; surveillance of core power distribution limits; review and audits; and calibration of safety related components required by technical specifications. The inspection invclved 151 inspector-hours onsite by two NRC inspectors.
Results: No items of noncompliance were identified.
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DETAILS
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1.
Persons Contacted
- B. Stephenson, Station Superintendent
- A. Robercs, Assistant Superintendent
- B. Shelton, Assistant to Station Superintendent
- R. Ragan, Lead Operating Engineer
- D. Farrar, Technical Staff Supervisor E. Budzichowski, Unit 1 Operating Engineer J. Wujciga, Unit 2 Operating Engineer C. Sargent, Unit 3 Operating Engineer B. Sanders, Station Security Administrator A. Stobert, QA
- E. Wilmere, QA Coordinator The inspector also talked with and interviewed several other licensee employees, including members of the technical and engineering staffs, reactor and auxiliary operators, shift engineers and foremen, elec-trical, mechanical and instrument personnel, and contract security personnel.
- Denotes those attending one or more exit interviews conducted on June 8, 15, 22 and 29, 1979.
2.
Maintenance The inspector, through direct observations and record review, verified that reactivity control instrumentation, containment, emergency core cooling, and plant and electrical systems maintenance activities were conducted in accordance with established procedures and Technical Specifications; verified that required administrative approvals were obtained prior to initiating work; verified that maintenance activities were accomplished using approved and technically adequate pre--dures; verified that the activities were inspected in accordance with the provisions of licensee's requirements; verified that the activities included functional testing and calibration as necessary prior to returning the component or system to an operating status; verified that quality control records were available; verified that activities were accomplished by qualified personnel; verified that radiological controls were established for worker protection, including minimizing personnel exposure; verified that materials or components used were certified as required by plant procedures; verified that QC hold points, plant status and safety controls, and tagging operations appeared adequate; and verified that, associated limiting conditions for operation were met in accordance with Technical Specifications.
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The inspector observed the following maintenance activities in progress:
(1) Unit 2, VR 4757, "A" Recirculation pump speed control; (2) Unit 3, WR 3775, Unit 3 Diesel generator oil tr.snsfer pump, WR 4631, Unit 3 Reactor building interlock doors, and WR 4791, Unit 3 125 VDC ground isolation and clearing; and (3) Unit 2/3, WR 4783, 2/3 Diesel generator interlock doors. The inspector reviewed the following completed work packages:
(1) Unit 2, WR 3871, Unit 2 HPCI pump cooling unit fan and WR 4000, Drywell floor drain isolation valve indication and (2) Unit 3, WR 3507, Unit 3 Main steam line high radiation monitor 3B.
No items of noncompliance were identified.
3.
Plant Operations The inspector reviewed the plant operations including examinations of control room log books, routine patrol sheets, shift engineer log book, equipment outage logs, special operating orders, and jumper and tagout logs for the month of June, 1979. The inspector 6 served plant operations during five offshifts during the month of J 1979.
The inspector also made visual observations of the routine surveillance and functional tests in progress during the period.
This review was conducted to verify that facility operations were in conformance with the requirements established under Technical Specifi-cations, 10 CFR, and Administrative Procedures. A review of the licensee's deviation repcrts for the period was conducted to verify that no violations of the licensee's Technical Specifications were made. The inspector conducted a tour of Units 1, 2 and 3 reactor buildings and turbine buildings throughout the period and noted that the monitoring instrumentation was recorded as required, radiation controls were properly established, fluid leaks and pipe vibrations were minimal, seismic restraint oil levels appeared adequate, equip-ment caution and hold cards agreed with control room records, plant housekeeping conditions / cleanliness were adequate, and fire razards were minimal. The inspector observed shift turnovers to verify that plant and component status and problem areas were being tur.ied over to relieving shift personnel. The inspector observed samp'ing and che.mical analysis of water chemistry samples to verify that water chemistry was being maintained in accordance with Technical Specifi-cations.
No items of noncompliance were identified.
4.
Physical Protection - Security Organization l
The inspector verified by observation and personnel interview (once during each operating shift) that at least one full time member of
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the security organization who has the authority to direct the physical
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security activitics of the security organization was onsite et all-3-
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times; verified by observation that the security organization was properly manned for all shifts; and verified by observation that members of the security organization were capable of performing
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their assigned tasks. There we e no weapons qualifications con-
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ducted during this monthly inspection.
No items of noncompliance were identified.
5.
Physical Protection - Physical Barriers The inspector verified that certain aspects of the physical barriers and isolation zones conformed to regulatory requirements and commit-ments in the physical security plan (PSP); that gates in the protected area were closed and locked if not attended; that doors in vital area barriers were closed and locked if not attended; and that isolation zones were free of visual obstructions and objects that could aid en intruder in penetrating the protected area.
No items of noncompliance were identified.
6.
Physical Protection - Access Control (Identification, Authorization, Badging, Search, and Escorting)
The inspector verified that all persons and packages were identified and authorization checked prior to entry into the protected area (PA), all vehicles were properly authorized prior ta entry into a PA, all persons authorized in the PA were issued and displayed identification badges, records of access authorized conforced to the PSP, and all personnel in vital areas were authorized access; verified that all persons, packages, and vehicles were searched in ar ardance to regulatory requirements, the PSP, and security procedurc.; verified that persons authorized escorted access were accompanied by an escort when within a PA or vital area; verified that vehicles autho-rized escorted access were accompanied by an escort when within the PA; and verified by review of the licensee's authorization document that the escort obse med above was authorized to perform the escort function.
No items of noncompliance were identitied.
7.
Physical Protection Communications The inspector verified by observation (during each operating shift)
that communications checks were conducted satisfactorily at the beginning of and at other prescribed time (s) during the security personnel work shift and that all fixed and roving posts, and each member of the response team successfully communicate from their remote location; and verified that equipment was operated consistent with requirements in the PSP and security procedures.
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No items of noncompliance were identified.
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8.
General Station Training The inspector verified by direct questioning of two new, two existing, and two temporary employees that administrative controls and procedures, radiological health and safety, industrial safety, controlled access and security procedures, emertancy plan, and quality assurance training were provided as required by the licensee's technical specifications; verified by direct questi'aing of two craftsmen and two technicians that on-the-job training, formal technical training commensurate with job classification, and fire fighting training were pievided; ari verified by direct. questioning of one female employee that female employees are provided instructions concerning prenatal radiation exposure. The inspector observed the following sessione in progress:
(1) Unit 2/3 Radwaste stack system, ;2)
Station fire fighting, and (3) Technical staff general training.
No items of noncompliance were identified.
9.
Radiation Protection - Operations The inspector examined all radiation protection instruments in use and verified their operability and currency of calibration. The inspector verified SWP requirements were being followed by observing activities conducted under SWP's, and he verified that high radiation area posting and 10 CFR 19 posting requiremerts were met.
No items of noncompliance were identified.
10.
Thermal Power Evaluation The inspector reviewed the results of the licensee's core theraal power evaluation for Units 2 and 3 (Unit I did not operate during the second quarter of 1979) and verified the technical adequacy of the evaluations and results and the frequency of evaluations were as prescribed by the facility's Technical Specifications.
No items of noncompliance were identified.
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Radioactive Waste Systems - Operations The inspector verified through record review that all effluent releases which occurred during the month of June 1979, were properly documented, that timely approvals of the releases were obtained, and that required sampling had been accomplished. He also observed the preparation for and release of liquid laundry waste on June 29, 1979, and verified that the release was accomplished in-accordance with approved procedures.
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No items of noncompliance were identified.
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12.
Surveillance of Core Power Distribution Limits The inspector verified through examination of various P-1 print outs that linear heat generation rates (LHGR) were within Technical Specifications limits and that if core maximum peaking factors were above design value total peaking factors for that class of fuel, APRM setpoint adjustments would be made by the amount specified in Technical Specification; and verified by examination of the OD-6,
" Thermal Data in a Specified Bundle," associated with its P-1 that minimum critical power ratio (Mr')R) and average planar linear heat generation rate (APLHGR) were with Technical Specifications limits.
No items of noncompliance were noted.
13.
Review and Audit The inspector observed a safety review committee meeting and veri-fied that provisions of the Technical Specifications dealing with membership, review process, frequency, and qualifications were met; subsequent to the meeting, rcviewed the meeting minutes and verified that. decisions made were reflected in the minutes and any corrective actions proposed were taken; and witnessed the performance of an audit conducted by the licensee and verified conformance with Technical Specifications requirements and station procedures.
No items of noncompliance were identified.
15.
Surveillance of Safety Related Components or Equipment a.
Purpose of Record Review The inspector reviewed plant surveillance records to verify:
(1) Test procedures are approved in accordance with the Technical Specifications.
(2) Test precedures include appropriate (a) prerequisites and preparations, (b) acceptance criteria, and (c) instructions to ensure tested item is restored to operation following the test.
(3) Technical content of procedures assures compliaace with the Technical Specifications and Inservice Inspection Program.
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(4) Tests were performed within the time frequencies specified in tSe Technical Specifications and Inservice Inspection Program.
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(5) Tests were performed by qualified ind!.viduals.
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(6) Test results were reviewed as required by facility administrative requirements.
(7) Test results were in conformance with Technical Specifi-cations and Inservice Inspection Program.
(8) Appropriate actica was taken for test results not meeting the acceptance criteria.
b.
Administrative Documents and Test Records Reviewed (1) Test Records Test Procedure Date of Test (a) High Drywell Pressure Scram 2-10, 4-10, 5-14, DIS 1600-2 and 6-9 of 1979 (b) High Reactor Pressure Scram 1-4, 2-3, 3-2, 4-9, DIS 500-1 5-2 and 6-8 of 1979 (c) Reactor Water Temperature 12-21, 12-22 of 1977 Calibration DIS 260-2 12-6 of 1978 Units 2 and 3 (d)
(1) APRM Gain Change 5-3, 5, 7, 10, 12, DIS 700-17 15, 17, 18, 20, 21, 22, 25 and 29 of 1979 (2) LPRM Amplifier Gain 4-29 and 5-23 of 1979 Calibration DIS 700-20 (e) LPRM Detector Plateau 5-1, 8, 19 and 6-9 DIS 700-22 of 1979 (f) Core Spray and LPCI Pressure 1-6, 2-7, 3-9, 4-7, Switch Calibration DIS 1400-4 5-9 and 6-9 of 1979 (g) LPRM Alarm Calibration Procedure 4-25-78 DIS 700-21 (h) Main Steam Line High Radiation 9-28-78, 1-2 Isolation DIS 1700-1 and 3-29 of 1979
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(i) Stand-by Gas Treatment System 3-22-79 Flow Calibration DIS 7500-2-7-(1
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(j) Main Steam Line High Flow 1-26, 2-22, 4-17,
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Isolation DIS 250-1 5-22 of 1979 (k) HPCI Turbine Trip High Reactor 1-17, 2-13, 3-12, Level Isolation DIS 500-3 4-16 and 5-19 of 1979 (1) Reactor Building Vent and Fuel 1-19, 2-17, 3-12 Alarm-High Radiat'on DIS 1700-7 and 4-16-79 (m) Emergency Fire Pump Discharge 2-10-79 Pressure and Flow Calibration DIS 4100-1 Units 2 and 3 (n) Reactor Building Closed Cooling 1-10, 2-15, 3-10, Water Radiation Monitor DIS 1700-3 4-13 and 5-18-79 (o) Diesel Oil Storage Tank Level 1-6-79 Calibration DIS 5200-1 Units 2 and 3 (p) Recirculation Pump Running 4-30-78, 10-30-78, D/P Switch Calibration DIS 1500-9 6-4-79 Units 2 and 3 (q) Core Spray Pump Discharge 7-3-78 Pressure Calibration DIS 1400-8 (r)
(1) Reactor Pressure (Feedwater 2-23 and 27-78, Control) DIS 600-1 Units 2 2-6 and 26-79 and 3 (2) EHC Low Pressure Scram Switch 1-27, 2-26, 4-12 DIS 500-8 and 5-26-79 (s)
(1) Turbine Cross Around High 2-27-78, 4-13-78 Pressure Switch DIS 5600-3 Units 2 and 3 (2) Turbine First Stage Pressure -
1-28, 4-25 and 45% Scram Bypass DIS 500-7 5-25-79 Units 2 and 3 (t)
(1) Drywell High Pressure J-28, 2-28, 4-19 Calibration DIS 1600-4 and 5-24-79 (2) Condenser Low Vacuum Scram 1-13, 2-10, 3-8, DIS 500-6 Units 2 and ?
4-10, 5-14 and 6-11-79-8-n'\\D t)([]
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(1) Reactor Low Pressure LPCI 1-26, 2-24, 3-19,
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Start Calibration DIS 1500-1 4-25 and N-23-79 (2) Main Turbine Vacuum Switch 10-23-77, 4-3-78 Calibration Units 2 and 3 and 4-13-79 (v)
(1) Low Pressure Pump On Auto 1-5, 2-8, 3-9, Blowdown ECCS DIS 1400-3 4-9, 5-8 and 6-4-79 (2) Suppression Pool Temperature S-15-78 Calibration DIS 1600-13 Units 2 and 3 (w)
(1) Containment Spray Interlocks 1-31, 3-3, 3-28, DIS 1500-3 4-25 and 5-24-79 (2) Containment Cooling Water 5-6-78, 5-t-?9 Service Water Pump Vault Temperature DIS 1500-12 Units 2 and 3 (x)
(1) Containment Pressure 12-14-78, 3-10, DIS 1600-10 5-15 and 6-13-79 (2) Containment Cooling Pump 5-8 and 9-78, 5-2 Flor Calibration DIS 1500-11 and 21-79 Units 2 and 3 (y)
(1) Torus Level Transmitter 2-8-78, 2-3-79 DIS 1600-5 (2) Torus to Reactor Building 2-2 and 4-13-79 High D/P Vacuum Breaker DIS 1600-3 (z)
(1) Drywell-Torus Pump Backup 5-16-79 D/P DIS 1600-15 (2) Off gas High Radiation 1-8, 2-9, 3-8, Dis 1700-2 Units 2 and 3 4-7, 5-15, 6-9-79 (2) Personnel Qualification Records The qualification records for two individuals involved in the tests identified in b.(1)(c) and b.(1)(f) above were reviewed to determine if the individuals were'. qualified in accordance with Technical Specifications and ANSI N18.1.
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(3) Administrative Documents
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The following facility administrative documents were used during the review:
(a) Technical Specifications Unit No. 2 Technical Specificatic Ucit No. 3 a.
(b) Training Records of plant personnel (c) Iastrumentation Calibration Procedures (d) Plant Calibration Records c.
Findings No items of noncompliance were identified.
16.
Exit Interview The inspectors met with licensee representatives (denoted in Para-graph 1) on June 5,15, 22 and 29,1979, and summarized the scope and lindings of that week's inspection activitici.
Attachment:
Preliminary Inspection Findings
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PRELIMINARY INSPECTION FINDINGS
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LICENSEE 2.
REGIONAL OFFICE Commonwealth Edison Company U.S. Nuclear Regulatory Commission Dresden Units 1, 2, 3 799 Roosevelt Rd.
Glan Ellyn, IL.
60137 Region III i
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DOCKET NUMBERS 4.
LICENSE NUMBERS 5.
DATE OT Tt:orcTTni:
50-010, 50-237, 50-249 DPR-02, DPR-19, DPR-25
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[6. Within the scope of the inspection, no items of noncompliance or deviation were found.
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The following matters are preliminary inspection findings:
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These preliminary inspection findings will be reviewed by NRC Supervision /
Managdment at the Region III Office and they will correspond with you concerning any enforcement action.
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PRELIMINARY INSPECTION FINDINGS
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LICENSEE 2.
REGIONAL OFFICE Ccar.onwealth Edisin Company U... Nuclear Regulatory Commission
"/"7 Roosevelt Rd.
Dresden Units 1, 2, 3 Glen Ellyn, IL.
60137 Region III 3.
DOCKET NUMBERS 4.
LICENSE NUMBERS 5.
DATE Or T':"JrcTTn'50-010, 50-237, 50-249 DPR-02, DPR-19, DPR-25 g,
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/. Within the scope of the inspection, no items of noncompliance or deviation
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The following matters are preliminary inspection findings:
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These preliminary inspection findings will be reviewed by NRC Supervision /
Managdment at the Region III Office and they will y rrespo d with you concerning any enforcement action.
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NucledF' Regulatory Commission Inspector L)hf.
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PRELIMINARY INSPECTION FINDINGS f
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LICENSEE 2.
REGIONAL OFFICE Co=monwealth Edison Company U.S. Nuclear Regulatory Commission Dresden Units 1, 2, 3 799 Roosevelt Rd.
Glen Ellyn, IL.
60137 Pegion III 3.
DOCKET NEiBERS 4.
LICENSE NLHBERS 5.
DATE OT TNCT'reTTm-50-010, 50-237, 50-?49 DPR-32, DPR-19, DPR-25 g
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Within the scope of the inspection, no items of noncompliance or deviation
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were found.
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The following matters are preliminary inspection findings:
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These preliminary inspection findings will be reviewed by NRC Supervision /
Managdment at the Region III Office and they will correspond with you concerning aay enforcement action.
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Nuclear Regulatory Commission Inspecto:
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PRELIMINARY INSPECTION FINDINGS
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LICENSEE 2.
REGIONAL OFFICE Commonwealth Edison Company U.S. Nuclear Regulatory Commission Dresden Units 1, 2, 3 799 Roosevelt Rd.
Glen Ellyn, IL.
60137 Region III 3.
DOCKET NUMBERS 4.
LICENSE NUMBERS 5.
DATE G TMcPrcTTo':
50-010 50-237,50-24S DPR-02, DPR-19, DPR-25 gg_7pg s'
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Within the scope of the inspection, no items of noncompliance or deviation were found.
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The following matters are preliminary inspection findings:
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hese preliminary inspection findings will be reviewed by NRC Supervision /
inagdment at the Region III Office and they will correspond with you concerning any enforcement action.
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