IR 05000010/1981010
| ML17194A135 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 08/25/1981 |
| From: | Jordan J, Reimann F, Tongue T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML17194A134 | List: |
| References | |
| 50-010-81-10, 50-10-81-10, 50-237-81-20, 50-249-81-14, NUDOCS 8109100098 | |
| Download: ML17194A135 (11) | |
Text
U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Reports No. 50-10/81-10; 50-237/81-20; 50-249/81-14 Docket Nos. 50-10, 50-237, 50-249 Licenses No. DPR-02, DPR-19, DPR-25 Licensee:
Commonwealth Edison Company P. 0. Box 767 -
Chicago, IL 60690 Facility Name:
Dresden Nuclear Power Station, Units 1, 2 and 3 Inspection At:
Dresden Site, Morris, IL Inspection Con~~~d:/, /July 3--31, 1981
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Inspectors:
T. M. Tongue
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M*. J. Jordan Approved By:
F, W. Reimann, Acting Chief Reactor Projects Section IC Inspection Swnmary
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Inspection on July 3-31, 1981 (Reports No. 50-10/81-10; 50-237/81-20; 50-249/81-14)
Areas Inspected:
Routine unannounced resident inspection of operational safety verification, Monthly Maintenance Observation, Monthly Surveillance Observation, Inspection during Long Term Shutdown, Plant Trips, Followup on open inspection items and Three Mile Island Modifications Trackin The inspection involved a total of 201 inspector-hours onsite by two (2)
NRC inspectors including 57 inspector-hours onsite during offshift Results:
Of the seven areas inspected, there were no-items of noncom-pliance identifie PDR ADOCK 05000010 G
- DETAILS.Persons Contacted
- '*D. Scott, Station Superintendent
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- R. Ragan, Operations Assistant Superintendent
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- J. Eenigenburg, Maintenance Assistant Superintendent i*D. Farrar, Administrative Services & Support Assistant Superintendent J. Brunner, Technical Staff Supervisor C. Sargent, Unit 1 Operating Engineer J. Wujciga, Unit 2.Operating Engineer M~ Wright, Unit 3 Operating Engineer E. Budzichowski, Unit Support Operating Engineer D. Adam, Waste Systems Engineer G. Myrick, Rad-Chem Supervisor B. Saunders, Station Security Administrator
- J. Meyer, Staff Assistant tq Security Administrator B. Zank, Training Supervisor
- W. Betourne, QA Engineer 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 instrument personnel, and contract security personne ;':Denotes those attending one or more exit interviews conducted on July 17 and 31, 198.
Operational Safety Verification The inspector observed control room operations, reviewed applicable logs and cqnducted discussions with control room operators during the period of July 3 through July 31, 198 The inspector verified the operability of selected emergency systems, reviewed tagout re-cords and verified proper return to service of affected component Tours of Units 2 and 3 reactor buildings and turbine buildings were conducted to observe plant equipment conditions, including potential fire hazards, fluid leaks, and excessive vibrations and to verify that maintenance requests had been initiated for equipment in need of maintenanc The inspector by observation and direct interview verified that the physical security plan was.being implemented in accordance with the station security pla The inspector observed plant housekeeping/cleanliness conditions and verified implementation of radiation protection controls. During the period of July 3 through July 31, 1981, the inspector walked down the accessible portions of the Unit 3 Standby Liquid Control, LPCI, and Core Spray, also Unit 2 Standby Liquid Control, and LPCI systems to verify operabilit The inspector also witnessed portions of the radioactive waste system controls* associated with radwaste shipments and barrelin * These reviews and observations were conducted to verify that facility operations were in conformance with the requirements established under technical specifications, 10 CFR, and administrative procedure No items of noncompliance was identifie Monthly Maintenance Observation Station maintenance activities of safety related systems and components listed below were observed/reviewed to ascertain that they were conducte in accordance with approved procedures, regulatory guides and industry codes or standards* and in conformance with technical specification The following items were considered during this review:
the limiting conditions for operation were met while components or systems were removed from service; approvals were obtained prior to initiating the work; activities were accomplished using approved procedures and were inspected as applicable; functional testing and/or calibrations were performed prior to returning components or systems to service; quality control records were maintained; activities were accomplished by qualified personnel; parts and materials used were properly certified; radiological controls were implemented; and, fire prevention controls were implemente Work requests were reviewed to determine status of outstanding. jobs and to assure that priority is assigned to safety related equipment maintenance which may affect system performanc The following maintenance activities were observed/reviewed:
Unit 2 Unit 2 Diesel Generator Disassembly of Condensate/Booster Pump motor Following completion of maintenance on the Unit 2 Diesel Generator, the inspector verified that this system was returned to servic~
properl No items of noncompliance were identifie.
Monthly Surveillance Observation The inspector observed technical specifications required surveillance testing on the Unit 3 - Quartly Timing of MSIVS, and Control Rod Drive Exercising and verified that testing was performed in accordance with adequate procedures, that test instrumentation was calibrated, that limiting conditions for operation were met, that removal and restora-.
tion of the affected components were accomplished, that test results conformed with technical specifications and procedure requirement and were reviewed by personnel other than the individual directing the test, and that any deficiencies identified during the testing were properly reviewed and resolved by appropriate management pe.rsonne *
The inspector also witnessed portions of the following test activities:
Unit 2 -
Rx Building Ventalator Radiation Monitor Security Check, Tip Traces, SRM Rod Block Calibration and IRM Rod Block and Scram Calibra-tion; Unit 3 - Calibration of Torus to Drywell D/P Gage, SRM Rod B.lock Calibration, Turbine Daily Tests, APRM Gain Adjustment, Quartly Timing of MSIVS, Control Rod Drive Exercising, 10% closure Test of MSIVS, Turbine Weekly; also Units 2 and 3 - Diesel Generator Survei!lance Tes No items of noncompliance were identified.* Inspection During Long Term Shutdown The inspector observed control room operations, reviewed applicable logs and conducted discussions with control room operators during the period of July 3 through July 31, 198 The inspector verified surveillance tests required during the shutdown were accomplished, reviewed tagout records, and verified applicability of containment integret Tours of Unit 1 accessible areas, including exterior areas were made to make in-dependent assessments of equipment conditions, plant conditions, *
radiological controls, safety, and adherence to regulatory requirements and to verify that maintenance requests had been initiated for equipment in need of maintenanc The inspector observed plant housekeeping/
cleanliness conditions, including potential fire hazards, and verified implementation of radiation protection control The inspector by observation and direct interview verified that the physical security plan was being implemented in accordance with the' station security pla.
Plant Trips Following the plant trips on July 15, 1981 the inspectors ascertained the status of the reactor and safety systems by observation of control room indicators and discussions with licensee personnel concerning plant parameters, emergency system status and reactor coolant chemistry. The inspectors verified the establishment of proper communications and re-viewed the corrective actions taken by the license All systems responded as expected, and the plant was returned to operation on July 16, 198 No items of noncompliance.were identifie Followup on Open Inspection Items Inspection Items 50-237/79-13-01 and 50-249/79-11-01, were to followup a change to Procedure DOP 1500-6, which would require assurance that if water was being transferred from the torus to the hotwell or Radwaste, the oncoming shift was adequately informed so the transfer of water would be terminated if a containment isolation were to occu Since the inspection of IE Bulletin No. 79-08, the licensee has installed air operated valves AO 2(8)-1599-61 and 62 that will automatically shut on a containment isolation signa Therefore, these items are considered close..
Open inspection Items 50-237/79-13-02 and 50~249/79-11-02, were in-tended to follow a modification (M-12-2/3-79-10) that was a proposal to install a single containment isolation valve in the common Unit 2 and 3 Torus to Radwaste/hotwell transfer line for automatic containment isolatio The licensee rejected that concept for a 2 valve isolation capability in the transfer lines from each unit under modification (M-12-2(3)-79-26).
These valves AO 2(3)-1599-61 and 62 discusaed above have been installed and will automatically shut on a containment isolation signa This meets the criteria of IE Bulletin No. 79-08 and is addressed in Section 7 under TMI modification Licensee personnel explained that the installed operators do not meet safety grade requirements (environmental and seismic) and they have placed orders for valves and operat'ors that meet the safety criteri These open inspection items will remain open until the present valves are upgraded or replaced with properly qualified equipmen During the refueling outage on Unit 2 earlier this year, the licensee was installing the RV head insulation using the 125 ton overhead cran During the lift the crane's moveable,block came in contact with the stationary block causing a two-block configuratio Initial -inspection of the I beam conitruction of the crane after the accident revealed no major damag The refueling outage was completed using the cran The licensee has since*contacted a private engineering contractor to inspect and evaluate the damag Initial inspection of the crane revealed some cracking in the weld in the dama~ed are~. The private engineering con-tractor is evaluating what repairs, if any, will be needed to correct the proble The licensee has derated the crane capacity to 62 ton capacity (50 percent), and has forbidden the crane to be used for irridiated fuel movements until after the. evaluation and necessary repairs are accomplished to allow rateing the crane to allow movement of the shipping cas This will remain as an open inspection item (50-249/81-14-02) until the*
- required evaluation by the private engineering contractor is completed and any necessary repairs that are required are accomplishe.
Three Mile Island Modifications-Tracking Since the TMI accident of March 28, 1979, and throughout 1980 and to present, the inspectors have been following the TMI modifica-tions and have documented only those specifically identified via IE Bulletins, et Temporary Instruction TI 2500/05 is the in-struction that uses a coordinated computer tracking system to follow all TM! related item Other Tl's have since been generated on inspection guidance, but there has been no guidance on documentation of these matters until March 12, 1981, when TI 2500/05 was issue Since there was no previous guidance on the documenting of TMI related inspections, it is being addressed here although numerous items were inspected prior to this tim An example is all Category A items were earlier periodically reviewed and the inspectors responded to further requests for inspection in October, December 1980, and January 1981, to reinspect all Category A items following the questions surround-ing the Off Gas Monitor of Nine Mile Point, which resulted in escalated enforcement actio Due to the urgency at the time, the requests and review results were transmitted via facsimile to and from Region III, and were not documented in an inspection repor As a result of recent requests for documentation of TMI Action Items to 'the Resident Inspections (from NRC HQ via Region III),
documentation of these items is presented her Note:
NUREG 0737 is the latest summary of all requirements related to TMI. and is the clasification and basis for modifications and corrective action By letter dated July 1, 1981, and other correspondence, CECo stated that all responses address Units 2 and 3 onl CECo also stated that since Unit 1 is undergoing an extended chemical cleaning, refueling and back fit outage, the issues of NUREG 0737 would be addressed prior to unit startup which is not scheduled until mid 198 Temporary Instruction TI 2515/42 Revision 2, TMI Action Plan Inspection Requirements-Procedures and Staffing This TI provided a partial listing of inspection requirements for operating reactors from the TMI Action Plan (Draft NUREG 0660, May 1980) and clarification of TM! Action Plan Requirement (NUREG 0737, November 1980).
It addresses inspections 9f licensee actions regarding Administrative Controls/Procedures and staffing response due in 198 Those inspected are as listed belo TI 2515/42, TASK I.A'.1.1, Shift Technical Advisor (STA) Interim Manning The inspectors have verified that CECo met the interim requirements as stated in NUREG 0578, Section 2.2.1.b,. Draft ANS 3.1, dated December 6, 1979; NUREG 0660; Generic letter October 30, 1979, and Item 1, NUREG 073 TI 2515/42, TASK I.A.1.1, STA Trained per Lessons Learned, Category By letter dated November 30, 1979, CECo committed to an STA Training program which was reviewed and accepted by NRR letter dated December 27, 198 Review by the inspectors has shown that the conditions of Item 3, NUREG 0737 have been met and individuals in these positions were on shift in early January 1981, and assumed full responsibilities on June 1, 198 TI 2515/42, TASK I.A.1.2, Shift Supervisor Responsibilities By letter dated October 18, 1979, CECo committed to meet NUREG 0578, Section 2.2.1.a by January 1, 1980, which was reviewed and accepted by NRR letter dated December 27, 197 The inspectors reinspected and verified that implementation by Dresden Administrative Pro-cedure DAP 7-1, latest revision continues to meet the con~itions of NUREG 0578, Section 2.2. TI 2515/42~ TASK I.A.1.3, Shift Manning The inspectors ~eviewed the matter of overtime limits in October and December 1980, plus reinspected in July 1981, and found that Dresden Administrative Procedure DAP 7-1 reflects the same words as Item 1, NUREG 073 Review has shown that present activities meet these procedures as state This matter was the subject of a Safety Evaluation Report (SER) written in June 1981, under TI 2515/56 w~ich stated documentation was not require However, since TI 2515/42 and TI 2500/05 require documentation this item is documented her TI 2515/42, TASK*l.A.2.1, 'Modify Training By letter dated October 29, 1980, Part A.2.C, CECo identified the modification to the training and retraining program for operators in resp~nse to NRR letter of March 28, 1980 from H. R. Denton to All Power Reactor Applicant The inspectors have reviewed the licensee's training/retraining program and found it in compliance with the commitment of the October 29, 1980 lette This completes the action of Item 4 for TASK 1.A.2.1 to NUREG 073 TI 2515/42, TASK I.C.1, Short Term Accident-and Procedure Review By licensee letter dated January 1, 1980, CECo committed to modify procedures and train operators for a small break LOCA event based on the G.E. BWR Owners Group recommendatio Procedures have been issued and training has been complete This was reviewed in October 1980, by the inspectors and reinspected again in July 198 Review shows this meets Item 1 of NUREG 073 This matter was also reviewed and licensee action accepted by NRR and documented in a letter dated March 5, 198 TI 2515/.42, TASK I.C.1, Short Term Accident and Procedure Review This item is not required to be implemented until the first refueling outage after January 1, 1982, and the licensee submittal date has not been determined per Items 2b and 3b, NUREG 073 TI 2515/42, TASK I.C.2, Shift Relief/Turnover Procedures By letter dated January 1, 1980, CECo stated that they meet Item 2.2.1.c of NUREG 057 This.matter was reviewed by the inspectors on several occasions since January 1, 1980, and was reinspected for this repor Review of Dresden Administrative
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Procedure DAP 7-1 and Appendix A, show that licensee actions are as stated and meet the criteria of Item 2.2.1.c of NUREG 057 TI 2515/42, TASK I.C.3, Shift Supervisor Responsibilities By letter date January 1, 1980, the licensee stated that the directives and procedures of NUREG 0578, Item 2.2.1.a and<!!"
clarification contained in the NRR letter of October 30, 1979, had been prepared and implemente This matter was reviewed by the inspectors early in 1980, and again in October and December 1980, and found to be acceptabl This criteria is implemented. via Dresden Administrative Procedure DAP 7-TI 2515/42, TASK I.C.4, Control Room Access By letter dated January 1, 1980, CECo committed to modify and implement procedures and directives to meet Section 2.2.2.a of NUREG 0578, and the clarification contained in the October 30, 1979, NRR letter. Dresden Administrative Procedure DAP 13-2 was reviewd by the resident inspectors early in 1980, and again in October and December 1980, when it was verified that the commit-tments were as stated.* The inspectors further verified that routine activities meet these condition This matter is addressed here for documentation purpose TI 2515/42, TASK I.C.5, Procedures for Operating Experience Feedback By letter. dated December 15, 1980, the licensee committed to meet the requirements of Section I.C.5 of NUREG 0737 by January 1, 198 Licensee internal memo of February 5, 1981, delineates these comit-tments in that the licensee's Operating Experience Assessment Review Program (OEAR) is performed by designated personnel under the Director of Nuclear Safet This has been reviewed by the inspectors in June 1981, under TI 2515/56, which stated no documentation was required since a Safety Evaluation Report was generate However, since TI 2515/42 and TI 2500/05 require documentation, this item is docu-mented her TI 2515/42, TASK I.C.6, Verification of Operating Activities The licensee outlined their program by letter dated December 15, 198 This program is current with the latest revision (Draft August 5, 1980) to ANS 3. The inspectors determined the adequacy and implementation of the verification system to be in compliance with NUREG 0737, which is provided in Dresden Adminis-trative Procedure DAP 3-This matter was reviewed in June 1981, and the subject of A Safety Evaluation Report (SER) under TI 2515/56, which required no follow-up documentatio It was later found that TI 2500/05 and TI 2515/42, require documentation on this subject, therefore, it is documented her TI 2515/42, TASK II.B.4, Training for Mitigating Core Damage By letter dated July 2, 1981, CECo stated training of operators on this subject had begun, and training of operators in the requal-ification program would be completed by October 1, 198 This action was reviewed by the resident inspectors and was found acceptable compared to the requirements of Items 2a and 2l;i.. of NUREG 073 TI 2515/42, TASK II.D.1, Relief and Safety Valve Test Requirements By lett~rs dated January 1, and December 15, 1980, CECo stated they would comply with the resolution of this matter reached through the BWR Owners Grou By letter dated July 1, 1981.,
referencing letters dated July 1, 1981, September 17, 1980, and March 31, 1981, from BWR Owners Group to NRR-NRC, the licensee feels the Relief/Safety valve testing criteria is acceptabl No action has been required by IE on this matte TI 2515/42, TASK II.F.2., Identification of and Recovery from Conditions Leading to Inadequate Core Cooling By letters dated December 15, 31, and July 1, 1981, the licensee has stated that a generic review by the GE-BWR owners group has determined that no further instrumentation is necessar This
- matter is subject to NRR-NRC review and commen TI 2515/42, TASK III.D.1.1, Primary Coolant Outside Containment By letters dated December 3, 1979, and January 1, 1980, CECo committed to identify a leak reduction and control program summary, which is implemented by Dresden Administrative Procedure DAP 14-The inspectors have reviewed the program, observed tests, etc.,
and found licensee actions to be within the criteria of Item 1, NUREG 073 This matter has been reviewed on several occasions since early 1980, and is documented her Temporary Instruction TI 2515/43 Revision 2, TMI Action Plan Inspection Requirements-Hardware Changes This TI is a partial listing of inspection requirements identified in the TMI Action Plan (Draft NUREG 0660, May 1980) and Clarifica-tion of TMI Action Plan Requirements (NUREG 0737, No~ember 1980).
It addresses inspections of licensee's actions regar~ing plant modifications or additions due in 198 Th6~e inspedted are as listed belo r TI 2515/43, TASK II.B.1, Reactor Coolant System Vents The licensee submitted the required material; by letters dated October 18, November 21, 1979, and December 15, 198 The licensee feels submittals meet Item 1 of NUREG 073 No further action by IE is deemed necessary at this tim TI 2515/43, TASK II.B.2, Plant Shielding By letters dated January i, and December 15, 1980, the licensee submitted the required information to NRR-NRC for design revie TI 2515/43, TASK II.D.3, Direct Indication of Relief and Safety Valve Positions
By letters dated January 1, December 15, 1980 and June 17, 1981 CECo stated that acoustical monitors had been installed to monitor relief and safety valv Although design of the monitors exceeded original criteria, the environmental and seismic qualification have not been certifie This is forthcoming in December 31, 198 The inspectors have observed installation and testing and have found the units acceptable and to be as stated by the license This was reviewed several time throughout 1980 and again during this report period and is being officially documented her The forthcoming environmental and seismic qualification certifica-tion is considered an open inspection ite (50-237/81-01)
(50-249/81-14-01)
,
TI 2515/43, TASK II.E.4.2, Containment Isolation Dependability By letters dated February 25, 1980 and September 13, 1979, the licensee provided the required information, completed the described modifications, and was found to meet Items 1-4 of NUREG 073 This was reviewed by the inspectors on several occasions in 1980, re-inspected for this report, and documented her By letters dated December 15, 1980, and December 31, 1980, CECo through the BWR Owners Group, concluded that modifications to the containment isolation pressure set points would not be advisabl Since the units are operated at 1 psig in the drywell and the set point is 2 psig is considered acceptable at this time and meets the criteria of Item Sb, NUREG 073 This was also accepted by NRR in D. Crutchfield letter dated July 20, 198 TASK II.E.4.2, Containment Isolation Dependability The licensee h~s responded to this task action item in letters dated November 14 and December 14, 1979; August 22 and December 31, 1980; and February 27, June 2, and July 6, 198 NRR responded to the licensee letters on October 22, and two letters on October 23, 1979; and December 2, 198 The licensee has submitted evaluations on qualifications of purge and vent valves and the licensee feels the loads and stresses on the valve components are within acceptable limits and stress margins are sufficient to ensure no deformation of active valve parts and that they meet the criteria of Item 6, NUREG 073 This matter is currently under review and evaluation by NRR-NR *-* * Meetings, Training and Off-Site Functions The Senior Resident Inspector (SRI) spent two days in Region III Offic On July 9, and. 10, 1981, there was a Senior Resident Inspector's seminar to brief and update the SRI's on the latest changes in the policies of the Commissio The inspectors attended a briefing on drug abuse and drug recognition held for th~ plant managemen The program was presented by the North-eastern Metropolitan Narcotics and Dangerous Drugs Enforcement Group (NEMEG).
The topics covered were the effects of lifestyle on drug abuse, identification of the different drugs, and effects of the drugs on the bod The inspectors and licensee management received a tour of the new technical support center and facilitie After the tour, the inspectors attended a licensee management training session on use of the technical support cente Mock accidents were presented to the manager The manager's response and responsibilities were then discusse.
Exit Interview The inspectors met with licensee representatives (denoted in Paragraph 1)
throughout the month and at the conclusion of.the inspection on July 31, 1981 and summarized the scope and findings of the inspection activitie The licensee acknowledged the findings of the inspectio