IR 05000010/1978006
| ML19340A821 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 02/08/1978 |
| From: | Barker J, Knop R, Shafer W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19340A820 | List: |
| References | |
| 50-010-78-06, 50-10-78-6, 50-237-78-05, 50-237-78-5, 50-249-78-05, NUDOCS 8009040649 | |
| Download: ML19340A821 (8) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
l Report No. 50-010/78-06; 50-237/78-05; 50-249/78-05 Docket No. 50-10; 50-237; 50-249 License No. DPR-2; DPR-19; DPR-25 I
Licensee: Commonwealth Edison Company P.O. Box 767 Chicago, IL 60690 Facility name: Dresden Nuc1 tar Power Station, Units 1, 2, and 3
Inspection at: Dresden Site, horris, IL I
Inspection conducted: January 4-C, 10, 13, 18-20, and 25, 1978 Inspectors:
W. D 2 '8~ 78 px S.&
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J. L. Barker (In-Office Review)
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h Approved by:
R. C. Knop, Chief
.? -8-765 Reactor Projects Section 1 Inspection Summary Inspection on January 4-6, 10, 13, 18-20, and 25, 1978 (Report No.
50-010/78-06; 50-237/78-05; 50-249/78-05)
Areas Inspected: Routine, unannounced inspection of Unit 1 Design Changes, Units 2 and 3 Relief Valve Surveillance, Units 1, 2, and 3 Equipment Out-of-Service Program, Unit 1 Startup Test Report, Unit 1 Compliance to Facility License Amendment #23, Units 1, 2, and 3 Review
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of Plant Operations, and a Plant Tour of the Reactor Facility. The
inspector also attended the meeting on January 19, 1978, relating to Units 2 and 3 diesel generator failure problems. The inspection
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involved 76 inspector-hours onsite by one NRC inspector.
Results: Of the seven areas inapected, no items of noncompliance or deviations were identified.
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DETAILS
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1.
Persons Contacted
a.
Exit Meeting for January 20, 1978
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- B. Stephenson, Station Superintendent
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- B.
Shelton, Administrative Assistant
- G.
Zeman, Industrial Relations
- R.
Ragan, Lead Operating Engineer
- B. Weibeler, Quality Assurance
- M. Wright, Tech Staff
- R. Kyrouac, Quality Control Engineer
- J.
Bowers, Tech Staff b.
Exit Meeting for January 25, 1978
- A.
Roberts, Assistant Station Superintendent
- R. Ragan, Lead Operating Engineer The inspector also talked with and interviewed several other licensee employees.
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- denotes those attending the exit interview.
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c.
_ Meeting Relating to Diesel Generator Failures Conducted on January 19, 1978 B. Stephenson, Station Superintendent
- B. Shelton, Administrative Assistant
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- R. Ragan, Lead Operating Engineer
- J.
Bowers, Tech Staff D. Farrar, Tech Staff Supervisor
- J. Martin, Tech Staff
- J.
Chan, Tech Staf f
- J. Eenigenburg, Maintenance Engineer
- G.
Frankovich, Master Electrician
- denotes those attending exit interview.
2.
Diesel Generator Failure Meeting On January 19, 1978, the inspector met with licensee members (as indicated in Paragraph 1.c), to discuss the licensee's plans regarding the recent series of diesel generator failures that have occurred on the Unit's 2, 2/3, and 3 diesel generators.
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The licensee stated that a meeting had been conducted on
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January 18, 1978, with representatives from the diesel manufacturer (Electromotor) and supplier (Western Supply).
As a result of this meeting, the licensee is considering modifications to various parts of the diesel generators.
The modifications being considered are:
(1) the installation of an air dryer on the air system and a blowdown on the pip-ing leading to the air start motor; (2) circuitry to provide multiple start sequence capability; (3) circuitry to allow the diesel to idle during testing and still perform an auto-matic function in the event of an auto start signal; and (4)
a modification to provide a new sample pump for the diesel fuel oil.
The licensee statn that in compiling all reportable and non-reportable problems with the three diesel generators since 1970, they identified a total of 76 failures. Regarding the year 1977 alone, the licensee reported that out of 203 tests they have incurred only 14 failures. The breakdown on the 76 failures identified since 1970, are as follows:
26% electrical component failures
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26% mechanical component failures
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20Z personnel error and procedural deficiencies 14% unknown 14% all others During this meeting, the inspector questioned the licensee regarding their commitment to perform a diesel generator failure analysis on the Units 2 and 3 facilities. The licensee stated that the diesel failure analysis report was in progress and would be received by our office by March 1, 1978.
No further concerns were identified.
3.
Design Change (Unit 1)
The following design changes were reviewed to verify that each change was conducted in accordance with formal procedures and received prcper review and approval. Equipment performance tests were conducted where appropriate, operating procedures were revised and as-built drawings were changed to reflect modifications as necess'ary.
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M12-1-76-17, Poison System N1-w
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i M12-1-76-20, HFA Relay Coils l
M12-1-77-32, Cap of One-Inch Line of Steam Drum
M12-1-17-33, Replace Bellows on Unit 1 Penetrations M12-1-77-42 Install Smoke Detectors in Unit 1 Cable Way M12-1-77-28, Primary Drum Low Water Switch Covers 4.'
Review of Relief Valve Surveillance The inspector conducted a review of the functional testing of
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l the licensee's relief valves, to determine that this safety
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subsysten is.in conformance with the regulatory requirements and the Technical Specifications.
The relief valve surveillance test was observed in progress,
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and the inspector noted the work involved was covered by a work request and was accomplished in accordance with properly
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i approved. procedures. By observation the inspector determinec l
that minimum crew requirements were met, test prerequisites l
as applicable were complete, special test equipment was properly
i calibrated, and required data was recorded for final review and analysis by proper personnel.
Personnel qualifications were. adequate.
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No items of noncompliance or deviations were identified.
5.
Special Review of Licensee's Out-of-Service Program i
The inspector conducted a review of the licensee's out-of-service
program to determine the extent of the licensee's compliance with the requirements of Dresden Administrative Procedure (DAP)
3-5.
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i In reviewing the data sheets for the out-of-service program the inspector noted that out of 100 out-of-service sheets, i
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only 41 were adequately and properly filled out by the licensee.
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The inspector also noted that in order to obtain 100 out-of-service data sheets, it was necessary to go from oucage request
- 585 to cutage request #1127.
In diecussions with the licensee on record retention the inspector was informed that many of the
missing outage data sheets were sent to the R3~ storage area.
However, no licensee representative could state that all the outage sheets were available for review. The licensee imple-
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mented an immediate audit of the outage sheets in order to make
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this determination.
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On January 25, 1978, the licensee informed the insnector
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that the audit of the OSS sheets has been successfully completed. The licensee further stated that all 00S sheets will be retained for a period of 12-months, except fo.r those sheets identified as accomplished for safety related work requests or modifications. These sheets will be maintained as life of the plant records. No further concerns were identi-fied.
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6.
Review of Unit 1, Cvele 11 Startup Test Report (J. Barker)
The inspector reviewed the startup test report, dated December 14, 1977, and verified that the report included information required to be reported by NRC requirements and that the test results and/or supportive information discussed in the report were consis-tent with design predictions and performance specifications. This review was conducted in office.
No items of noncompliance or deviations were identified.
7.
Review of Unit 1 Interim License Requirements An inspection of the Dresden Unit 1 facility was performed to
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examine the licensee's action relating to amendment #23 to facility operating license No. DPR-2.
The inspector reviewed the following items to verify the licensee's compliance to amendment #23.
Motor Operated Valve 130 Electrically Disarmed 345/138 KV Transformer Installed Electrical Motor Control Cabinets Containing Controls for Essential or Backup ECCS Equipment Restrained for Potential Seismic Loads Station Batteries Restrained to Withstand Potential Seismic Loads Installation of a Flexible Hase Connection Between the Unit Fire Pump and Suction to Core Spray System Five Smoke Detectors Installed and Operable in the Cable Tunnel Procedures Associated with Smoke / Fire Alarms Modified Reactor Protection System Surveillance Procedures for Functional Capability Operating Procedure to Open Motor Operated Valve #50 if the Feedwater Control Valve fails closed following a LOCA Surveillance Procedure of a Scram Circuitry No items of noncompliance or deviations were identified.
The inspector also reviewed the licensee's temporary diesel generator test program.(letter, Turbak to O'Connor, dated December 30, 1977).
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{s The inspector determined by visual observation that all tests
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were conducted in accordance with approved startup procedures having adequate acceptance criteria. The demonstration of
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operability was satisfactory. The inspector also reviewed the licensee's operating and surveillance procedures for the tem-porary diesel generator and identified no significant concerns.
The licensee's compliance with the interim license conditions appeared to have been satisfactorily achieved. No items of
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noncompliance or deviations were identified.
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8.
Review of Plant Operations (Units 1, 2, 3)
Throughout the month of January, the inspector conducted an ongoing review of the licensee's activities in the control room.
The review included a review of control room log books for each unit, a review of Units 2 and 3 computer printouts, determination of proper panel lineup and a discussion with the control room operator on those alarms that were presently '.it during this inspection. No significant concerns were identified. A review was also conducted of the licensee's deviation reports. No significant concerns were identified.
The inspector observed several shif t changes during the inspec-
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tion to determine the adequacy of transfer of information. The following concerns were identified.
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The inspector noted that the operator at the time of shift change does not have an opportunity to review the Unit control panel primarily because too many people are in the control room requesting the operator to perform specific functions for their particular work.
The inspector also noted that the routines conducted by the control room operator appear to take anywhere from 1.to 1 1/2 hours to complete. - A licensee representative stated that the requirement to conduct routines is once every eight hours and not necessarily at the beginning of shifts.
The inspector was informed by licensee personnel that on January 16, 1978, a " quiet hour" was established for control room personnel during the shift turnover. During this time the licensee informed the inspector that no personnel, other than operating personnel, were allowed in the control room.
The purpose of this " quiet hour" is to allow the operator to review his panel and instrumentation. The licensee also stated that the " quiet hour" is on a trial basis to determine it's effect on plant operations. No significant concerns were identified.
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During a review of the Unit 2 control room log book, the inspector
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noted that on January 11,12, and 25,1978, the unit experienced a load loss as a result of resin intrusien into the reactor vessel. In reviewing this incident the licensee also determined that a hydrogen and oxygen increase was noted during the resin intrusion. At this time the licensee has-not fully identified the cause of the resin intrusion, however, an ongoing investiga-tion is being conducted which includes a. review of demineralizer procedures and procedures for transfer of resins. The inspector reviewed the licensee's records of conductivity of primary water conductivity for the dates described above. At no time did the primary water conductivity exceed 1.4 MH0s. No significant con-cerns were identified.
9.
Plant Tour The inspector conducted a tour of the Unit 2 ar.d 3 reactor build-ing and turbine building and noted that monitoring instrumentation was recorded as required, radiation control was properly estab-lished, fluid leaks and pipe vibrations were minimal, seismic restraint oil levels in the torus appeared adequate, and equip-ment caution and hold cards agreed with control room records. No significant concerns were identified.
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10.
Exit Interview for January 20, 1978 The inspector met with licensee representatives (denoted in Para-graph 1) at the conclusion of the inspection on January 20, 1978.
The inspector summarized the scope and findings of the inspection.
The licensee representatives made the following remarks in response to certain of the items discussed by the inspector:
Acknowledged the licensee's comments regarding the adequacy of DAP 3-5 and the questionable record keeping of outage service checklists.
Acknowledged the inspector's concerns relating to the contori room operator's panel review at the turnover of the shift change.
Exit Interview for January 25, 1978 The inspector conductea an exit interview via telecommunications with licensee representatives (Paragraph 1.b) on January 30, 1978. The inspector summarized the scope and findings of the inspection for the month of January. The licensee representative made the following remark in response to one item discussed by the inspector:
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Stated that the record keeping requirements relating to
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out-of-service sheets-will normally be maintained for a
period of 12 months. Out-of-service sheets required as a result of safety related work and modification packages will be maintained as lifetime records.
(Paragraph 5).
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