IR 05000010/1978035
| ML19282B908 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 02/07/1979 |
| From: | Barker J, Knop R, James Smith NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19282B904 | List: |
| References | |
| 50-010-78-35, 50-10-78-35, 50-237-78-34, 50-249-78-35, NUDOCS 7903190015 | |
| Download: ML19282B908 (12) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-10/78-35; 50-237/78-34; 50-249/78-35 Docket No. 50-10; 50-237; 50-249 License No. DPR-2, DPR-19, DPR-25 Licensee:
Commonwealth Edison Company P.
O.
Box 767 Chicago, IL 60690 Facility Name:
Dresden Nuclear Power Station, Units 1, 2, 6 3 Inspection At:
Dresden Site, Morris, IL Inspection Conducted:
December 1-29, 1978
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Inspectors:
J. L.
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Approved By:
R.
C. Knop, Chief Reactor Projects Section 1 Inspection Summary Inspection on December 1-29, 1978 (Report No. 50-10/78-35; 50-237/78-34; 50-249/78-35)
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, surveillance of core power distri-bution limits, radioactive waste systems - operations, calibration of safety related equipment not identified in technical specification, Units 2 and 3, refueling activities, Unit 1, QA program - annual reviev, design changes / modifications, and procurement.
The inspection involved 160 inspec tor-hours onsite by two NRC inspectors.
Results:
Of the 13 areas inspected, there were no ' items of noncompliance identified in 12 areas.
One deviation (inadequate storage of Class B area material - paragraph 14) was identified in one area.
7903190015
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DETAILS 1.
Persons Contacted
- B. Stephenson, Station Superintendent
- A.
Roberts, 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
- W.
Hildy, Fbster Instrument Mechanic
- J.
Bell, Master Mechanic
- C.
Frankovick, Master Electrician
- G.
Reardant, QA Coordinator
- R.
Stobert, QA
- D.
Wheeler, Substation Construction
- W.
Fancher, OAD 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, electrical, mechanical and maintenance personnel, and contract security personnel.
- Denotes those attending one or more exit interviews conducted on December 15, 21 and 29, 1978.
2.
Maintenance The inspector, through direct observations and record review, veri-fled that reactivity control and power distribution; instrumentation, reactor coolant, emergency core cooling, and plant and electrical power systems were conducted in accordance with established procedures and Technical Specifications; verified that required administrative approvals were obtained prior to initiating work; verified that maintenance activitice were accomplished using approved and tech-nically adequate procedures; verified that the activities were inspected in accordance with the provisions of licensee's requirements; verified that the activities included functional testing and cali-bration 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-2-
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personnel; verified that radiological controls were established for worker protection, including minimizing personnel exposi re; verified that materials or components used were certified as re-quired 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.
The inspector observed maintenance in progress concerning the following work requests:
(1) Unit 1, WR 9655, "B" SSG tube leaks plugging; (2) Unit 2, WR 8807, 24/48 VDC battery discharge test, WR 9654, HpCI steam line drain pot bypass and, UR 9476, reactor high pressure trip switch; and (3) Unit 3, WR 9750, hydro 3D re-circulation pump seal.
The inspector also reviewed the following completed work requests:
(1) Unit 2, WR 9615, 250 VDC battery charger and (2) Unit 3, WR 9344, diesel generator day tank oil fill solenold, and WR 9403, scram inlet valve on CRD 22-93.
No items of noncompliance or deviations were noted.
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 j umper and tagout logs for the month of December 1978. 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 f acility operations were in conformance with the requirements established under Technical Specifications, 10 CFR, and Administrative Procedures.
A review of the licensee's deviation reports 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, equipment caution and hold cards agreed with control room records, plant housekeeping conditions / cleanliness were adequate, and fire hazards were minimal.
The inspector observed shift turnovers to verify that plant and component status and problem areas were being turned over to relieving shift personnel.
The inspector observed sampling and chemical analysis of water chemistry samples to verify that water chemistry was being maintained in accordance with Technical Specifications.
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No items of noncompliance or deviations were noted.
4.
Physical Protection - Security Organization The inspector verified by observation and personnel interview (once during each operating shift) that at least one full time member of the security organization who has the authority to direct the physical security activities of the security organization was onsite at all 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 their assigned tasks.
There were no weapons qualifications conducted during this monthly inspection.
No items of noncompliance or deviations were identified.
5.
Physical Protection - Physical Barriers The inspector verified that certain aspects of the physical barriers and isolatien 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 ceuld aid an intruder in penetrating the protected area.
No items of noncompliance or deviations 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 to entry into a PA, all persons authorized in the PA vere issued and displayed identification badges, records of access authorized conformed to the PSP, and all personnel in vital areas were authorized access; verified that all persons, packages, and vehicles were searched in accordance to regu-latory requirements, the PSP, and security procedures; verified that persons authorized escorted access were accompanied by an escort when within a PA or vital area; verified that vehicles authorized escorted access were accomplanied by an escort when within the PA; and verified by review of the licensee's authorization document that the escort observed above was authorized to perform the escort function.
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No items of noncompliance or deviations were identified.
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.
No items of noncompliance or deviations were identified.
8.
Surveillance of Core Power Distribution Limits
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The inspector verified through examination of various P-1 print outs that linear heat generation rates (LHGR) were within Technical Speci-fications limits and that if core maximum peaking factors were above design value total peaking factors for that class of fuel, APRM setpoint adjusts 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 (MCPR) and average planar linear heat generation rate ( APLHCR) were with Technical Specifications limits.
No items of noncompliance 01 deviations were noted.
9.
Radioactive k'aste Systems - Operations The inspector verified through record review that all e.
2ent releases which occurred during the week of December 10, 1978, 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 December 15, 1978, and verified that the release was accomplished in accordance with approved procedures.
No items of noncompliance or deviations were noted.
10.
Calibration of Safety Related Equipment not Identified in Technical Specifications (Units 2 and 3)
The inspector reviewed plant calibration records for the below listed components.
This review was performed to determine if the operating range / accuracy of components were consistent with-5-
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applicable Technical Specification /SAR; the procedures used to calibrate the components were reviewed and approved as required by Technical Specifications; the procedures used contained accept-ance criteria consistent with Technical Specifications SAR: the procedures used contained detailed instructions commensurate with the complexity of the calibration and that the technical content of the procedures would result in satisfactory calibration.
Reactor pressure transmitter, PT 654 and PR 640-28, Procedure a.
DIE 600-2 b.
Standby liquid control pump suction temperature, T1-1160, Procedure DIS 1100-3 Core spray header delta-p, DPIS 1459A and 1459B, Procedure c.
DIS 1400-1
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d.
F actor pressure (feedwater control), PT 647A and 647B, rocedure DIS 600-1 e.
Nitrogen storage tank level calibration, Procedure DIS 1600-14 f.
Containment cooling pump flow calibration, FT 1542A and 1542B and FI 15401A and 15401B, Procedure DIS 1500-11 g.
Circulating water pump trip on high condenser pit wate. level, LS 4441-24A and 24B and LS 4441-25A and 25B, Procedure DIS 4400-1 h.
Suppression pool temperature, TR 1640-1, Procedure DIS 1600-13 1.
Standby gas treatment flow calibration, Fir 7541-1 and 7540-13, Procedure DIS 7500-2 j.
Main steam line air pilot valve temperature, TR 200-2, Procedure DIS 250-7 The inspector selected the below listed test equipment used in the calibration of safety-related equipment and determined that the accuracy of those instruments were traceable to the National Bureau of Standards or other independent testing agencies.
a.
Heise pressure gage, Serial No. CM 9047 b.
Heise pressure gage, Serial No. C57639 c.
Heise pressure gage, Serial No. C57640-6-
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No items of noncompliance or deviations were noted.
11.
Refueling Activities, Unit 1 The inspector reviewed the licensee's actions concerning a fuel assembly which was dropped in the spent fuel area on December 1, 1978. The licensee reported the incident on December 4, 1978.
A rereview of this event indicates that no items of noncompliance are warranted.
In the future, the licensee will report within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the occurrence of similar events.
This matter had been previously documented and presented to the licensee in the inspec-tor's preliminary findings.
12.
QA Program - Annual Review The inspector reviewed all changes or revisions to the licensee's
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QA program during 1978 and verified that they were in conformance with the program described in the application relating to 10 CFR 50, Appendix B, and applicable codes, standards, or regulatory guides. The inspector verified by questioning of the licensee personnel having responsibility f or implementing the QA program changes understand the significance of the specific changes and verified that implementing procedures associated with identified program changes or revisions were revised to reflect the new requirements.
13.
Design Changes / Modifications The inspector reviewed design changes / modifications listed below and verified that changes have been reviewed in accordance with 10 CFR 50.59, that changes aere reviewed and approved in accord-ance with Technical Specifications and established QA/QC controls, that changes were controlled by established procedures. that test results were within previously established acceptance criteria, that deviations were resolved and retesting accomplished as appro-priate, that operating procedure changes were made and approved in accordaace with Technical Specifications, and that as-built drawings were changed to reflect the modifications.
The inspec-tor observed modifications to Unit 3 HPCI suction line, M12-3-78-13, and Unit 3 Recirculation flow control, M12-3-78-31 and verified that change activities were being conducted in accordance with appropriate-7-
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specifications and drawings, that acceptance and startup testing
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were conducted in accordance with technically adequate and approved procedures, and implementation of appropriate safety controls (firewatch, fire fighting equipment, and welding and cutting permits)
appeared adequate.
Unit 1 M12-1-78-24, High temperature alarm for core spray area Unit 2 a.
M12-2-15, Diesel generator air start strainer blowdown b.
Fu2-2-78-21, Pump back process controller Unit 3 a.
M12-3-78-1, Two new NA200 LPPM strings b.
M12-3-78-7, 125 VDC battery charger c.
M12-3-78-8, 125 VDC divisional cable separation d.
Fu2-3-78-12, CRD return nozzle e.
M12-3-78-13, CRD safe-end f.
M12-3-78-37, 3A recirculation pump seal g.
M12-3-78-43, 3D2 feedwater heater drain line No items or noncompliance or deviations were noted.
14.
Procurement The inspector conducted a tour of the licensee's storage areas and verified that safety related material and spare parts received were inspected by qualified personnel, that storage and packaging requirements have been defined and met, that preventative maintenance is being accomplished, that identification tagging was adequate, and that control of items with limited shelf life was in accordance with approved procedures.
The inspector reviewed licensee procedures DWP-1, " Packaging, Receiving, Handling and Storage of Items in Storeroom," DWP-2, " Control of Items with Limited Shelf Lif e,"
DWP-3, " Storage of Chemicals," and DWP-ll, " Preventative Maintenance for Items in Storage." During a tour of Unit 3 Turbine Building the inspector noted that equipment identified as being in Class B storage were resting on the turbine floor. ANSI 45.2.2, Section 6.1.2.(2)
requires such equipment be placed on " pallets or shoring to permit air circulation.
The licensee's QA program commits the licensee to follow regulatory guide 1.38, which references ANS1 45.2.2 for-8-
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implementation.
ibis item is considered a deviation from a commit-ment to the NRC.
The licensee took immediate corrective action to place the switchgear on pallets and instructed the appropriate personnel in implementation of ANSI 45.2.2 requirements to prevent The inspector has no further concerns regarding this recurrence.
item.
15.
Exit interview The inspector met with licensee representatives (denoted in Paragraph 1) on Friday of each week, December 15, 21, and 29, 1978, and sum-marized the scope and findings of tl.at week's inspection activities.
Atta:hment: Preliminary Inspection Findings
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OFFICE OF INSPECTION AND ENFORCEMEN
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PRELIMINARY INSPECTION FINDINGS 1.
LICENSEE 2.
REGIONAL OFFICE Commonwealth Edison Company U.S. Nuclear Regulatory Com ission Dresden Units 1, 2,
799 Roosevelt Rd.
Glen Ellyn, IL.
60137 Region III 3.
DOCKET NUMBERS 4.
LICENSE NUMBERS 5.
DATE OF INSPECTION Y - h [/[
50-010, 50-237, 50-249 DPR-02, DPR-19, DPR-25
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Within the scope of the inspection, no items of noncompliance or deviation were found.
Y 7.
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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[cleiirRegulatoryCommissionInspector
OFFICE OF INSPECTION AND ENFORCEMET
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PRELIMINARY INSPECTION FINDINGS 1.
LICENSEE 2.
RECIONAL OFFICE Commonwealth Edison Company U.S. Nuclear Regulatory Co= ission Dresden Units 1, 2, 3 799 Roosevelt Rd.
Glen Ellyn, IL.
60137 Region III 3.
DOCKET NUMBERS 4.
LICENSE NUMBERS 5.
DATE OF INSPECTION S0-010, 50-237, 50-249 DPR-02, DPR-19, DPR-25 g,
gyy 6.
Within the scope of the inspection, no items of noncompliance or deviation were found.
V 7.
The following matters are preliminary inspection findings:
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These preliminary inspection findings will be reviewed by h7C Supervision /
Managdment at the Region III Office and they will correspond with you concerning any enforcement action.
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Nuefear Regulatory Commission Inspector
OFFICE OF INSPECTION AND ENFORCEMES
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PRELIMINARY INSPECTION FINDINGS
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1.
LICENSEE 2.
REGIONAL OFFICE Commonwealth Edison Company U.S. Nuclear Regulatory Co=nission Dresden Units 1, 2, 3 799 Roosevelt Rd.
Glen Ellyn, IL.
60137 Region III 3.
DOCKET NUMBERS 4.
LICENSE NUMBERS 5.' DATE OF INSPECTION
/y,_ y g.f 50-010, 50-237, 50-249 DPR-02, DPR-19, DPR-25
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g 6.
k'ithin the scope of the inspection, no items of noncompliance or deviation were found.
7.
The following matters are preliminary inspection findings:
8.
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.
Se
m Nucd(ar " Regulatory Commission Inspector