IR 05000329/1979013
| ML19248D338 | |
| Person / Time | |
|---|---|
| Site: | Midland |
| Issue date: | 05/29/1979 |
| From: | Cook R, Knop R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19248D329 | List: |
| References | |
| 50-329-79-13, NUDOCS 7908150627 | |
| Download: ML19248D338 (10) | |
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U.S.. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMEhT
REGION III
Report No. 50-329/79-13; 50-330/79-13
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Docket No. 50-329; 50-330 License No. CPPR-81; CPPR-82 Licensee: Consumers Power Company 1945 West Parn.11 Road Jackson, MI 49201 Facility Name: Midland Nuclear Power Plant, Units 1 and 2 Inspection At: Midland Site, Midland, MI Inspection Conducted: April 2-30,1979
?c f Inspector:
R. J. C'cok 29 !79 P!79 Approved By:
R. C. Kno i
Projects Section Inspection Summary Inspection on April 1-30, 1979 (Report No. 50-329/79-13; 50-330/79-13 Areas inspected:
Examination of site conditions, settlement of diesel generator foundations and structures, adequacy of decay heat removal pump techn' cal literature, unconsolidated concrete at 568'
elevation of Auxiliary Building, presence of fluid in 350 MCM-3/C B-11 Power Cable, receipt of high carbon content ells, damage to Class IE battery cell, effects of Three Mile Island - 2 incident on site sperations, follow-up on alleged explosion onsite, observation of anti-nuclear demonstration, apparent overexposure of B&W radiog-raphers, hydrostatic tests of Unit 1 Incore Instrument Tank 1T-87, hydrostatic test of Unit 2 Incore Instrument Tank 2T-87.
This inspection effort involved a total of 144 inspector-hours b;. one NRC inspector.
Results: Of the 13 areas inspected, no apparent items of noncom-pliance or deviations were identified in twelve areas; one apparent item of noncompliance was identified (infraction - failure to adequately inspect tank vertical welds for zero leakage conditions -
paragraph 12).
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DETAILS Persens Contacted
- T. Cooke, Project Superintendent
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- B. Peck, Construction Supervisor M. Shaeffer, QA Engineer P. Kyner, Field QA Engineer E. Jones, QA Inspector D. Nott, QA Inspecs)r
- L. Dreisbach, Bechtel Corporation Project QA Engineer
- W.
Barclay, Bechtel Corporation Project Field QC Engineer
- R. SEope, B&W Project Engineer Nuiercus other principle staff and personnel were contacted during the reporting period.
- Denoted those present during at least one of the three exit inte r-ies - conducted during the report period.
Licensee Action On Previous Inspection Findings Reportable Deficienci.es - 50.55(e) Items Settlement of Diesel Generator Foundations and Structures
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(0 pen) Item No.(329/78-13-03; 330/78-13-03): The licensee has kept the Resident Inspector informed of activities being per-formed during the reporting period which are pertinent to the settlement of the diesel generator building. During the report period the licensee has completed adding twenty feet of sand in and around the diesel generator building. This is the maximum amount of sand planned for placement for preloading of the building.
The licensee also informed the Resident Inspector that test pits pertaining to the site settlement mouitoria: program are not scheduled for digging prior to May 1, 1979. Tre licensee indicated that they would attempt to give a nominal two week notice to the NRC prior to test pit excavation.
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Functional or Program Areas Inspected 1.
Site.ours At periodic intervals generalized tours of the facility were performed by the Resident Inspector. During the reporting period, these tours covered essentially every area of the site.
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These tours were intended to assess the cleanliness of the site, storage condition of equipment. and piping being used in site construction; the potential for fire or other hazards which might have a deleterious affect on personnel and equip-ment and to witness construction activities in progress.
During one of these tours, it was noted that debris anu solvent coaked polyethelene existed in the fuel pool and on the covering for the reactor vessel in Unit '. The solvent soah-d polyethelene was tested and would not sustain combustion. However, the licensee took prompt action to clean away the debris and install new polyethelene covering over the reactor vessel.
2.
Decay Heat Removal Pump Technical Literature During the report pericd the B&W Site Construction Consultant received an assembly diagram (Fig. 13A) for incorporating into the Decay Heat Removal Pump Instruction Manual.
This clarifying information, which was examined by the Resident Inspector, should remove any uncertainties and ambiguities pertinent to the installation of decay heat removal pump impellers during future maintenance.
3.
Receipt of High Carbon Content Four Inch Sch. 40 Ells During the reporting period, the Resident Inspector was informed that McJunkin Corporation had shipped to the site 4 Inch Sch.
40 Long Radius 90 Deg. and 45 Deg. Ells, which had a higher than allowable carbon content for SA-234 material. These items were manufactured by Tube Turn from material Heat Code No.
W6719. The high carbon material is classified as nonweldable and cracking may occur which is undetectable when welding is attempted. The licensee in-formed the Resident Inspector that U.S. Steel has issued a 10 CFR Part 21 report to the NRC Region IV office. The licensee has searched their files and determined that none of these high carbon items are installed in any aafety related system. The licensee has also taken administra-tive steps to preclude insta.11ation of items with Heat Code No.
W6719.
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Unconsolidated Concrete in Floor of 568' Elevation of Auxiliary Building During the reporting period the Resident Inspector examinei a section of unconsolicated concrete in the floor of the Aux;liary Building at the 568' elevation. The excavated section was
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approximately 4 1/2' x 1 1/2' x l' deep. A second smaller section of unconsolidated concrete was detected approximately 5' from the larger section on the same elevation. Noncompli-ance Report No. NCR 2034 has been generated and the licensee is assemblying an indepth evaluation program to de'. ermine the extent and significance of thess unconsolidated areas.
5.
Damage to Class IE Battery Cell During the report period one 2 cell GC-17 Exide Class 1E Battery became damaged and will require replacement. The cell became damaged during lug crimping cperatiens when the tool shorted one of the lugs. The lug partially melted and metal was spattered on the battery casing. During cleaning and retermination activities the battery casing top became cracked.
The licensee plans to replace the affected cell.
In the interim, to facilitate "ref reshing" charge, Exide Battery has recommended removing the affected cell from the system and charge in the
" float mode" rather than the " equalizing mode" Exide Battery has indicated that the battery can be operated in this mode for six months providec the average cell temperature is less than 80 F.
This item is identifed in Noncompliance Report No.
NCR-2040.
6.
Presence of Fluid in 350 MCM-3/C B-11 Power Cable During the reporting period the Resident Inspector was inf ormed that a water like fluid was de+_e:ted in one phase of a 3 phase No. 350 MCM Power cable from six different reels of cable supplied by Essex. This cable had been installed in a total of 14 circuits which are identified in Noncompliatee Report No.
NCR-2015. The exact composition of the fluid (or the source of the fluid) is not known at this time and is being analyzed.
The adequacy of the cabie insulation is also being evaluated by the licensee. The licensee is evaluating the quality of 350 MCM power cable used in safety related equipment.
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Effects of Three 311e Island Unit 2 Incident on the Midland Site As a result of the March 28, 1979 Three Mile Island incident the licensee has formed a task force to study the event and determine what similarities, if any, which might exist at the Midland Plant that could allow a similar event to occur, and to
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determine what corrective action may be necessary. The licensee has sent representatives to B&W facilities to gather information pertinent to these objectives. The Resident Inspector had discussions with the licensee pertaining to these activities.
8.
Allegations of Explosion During the report period allegations of an explosion at the Midland site was rec eived by the NRC Regional office. The Resident Inspector Lad no previous knowledge of such an event occuring at the Midland Site. The Resident Inspector discussed the possibility of such an event having occured at the Midland Site with Bechtel Corporation on Site Safety Office and Consumers Power Company. The only event which could be deter-mined which might give an illusion of an explosion was the planned " blow down" of a fossil fired boiler owned by Dow Chemical on April 10, 1979.
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Anti-Nuclear Demonstration On April 21, 1979, a peaceful antinuclear demonstration was conducted at Overlook Park which is near the site access road entrance. An estimated 3,000 persons were in attendance.
Local law enforcement officials maintained adequate crowd and traffic control. Onsite construction activities were curtailed on the date of the demeastration. The Resident Inspector was onsite during the demonstration strictly as an observer.
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Apparert Overexposure to LSW Radiographers On April 3, l'F, the Resident Inspector was informed that two B&W radiographers may have received an accidental over-exposure during the previous night. An investigative and technical specialist were dispatched frem the NRC Regional office and performed an investigation of this matter on April 4-5, 1979.
The results of their investigative efforts are contained in a separate NRC Inrestigation Report.
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Hydrostatic Tests.of Unit 1 Incore Instrument Tank 1T-87 During the report period Unit 1 Incore Instrument Tank 1T-87 was successfully hydrostatically tested.
It required more than one attempt before qualified personnel representing Eartford Boiler Authorized Inspector, CB&I Quality Control, Bechtel Corporation Authorized QC Inspector and interested Consumers Power Company representatives were available with adequate
equipment to perform the inspection.
Bechtel Cor-poration QC would rat accept hydrostatic testing until all the interested parties had examined all welds by a means which could physically establish zero leakage. This required use of a borescope to examine two vertical welds which pass through an anulus area created by flooring and areas " boxed in" by tank supports and yall. Consumers Power Company also issued QC Hold Tags to prevent any wor 9 being performed which would affect the Incore Instrument Tank hydrostatic test until an acceptable test could be completed. The examination of those welds in the above referenced anulous area and " boxed in" area with a borescope was witnessed by the Resident Inspector.
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Hydrostatic Test of Unit 2 Incore Instrument Tank 2T-87 During the report period several attempts were made to hyro-statically test the Unit 2 Incore Instrument Tank 2T-87.
All attempts failed because of the lack of availability of qualified personnel representing the Hartford Boiler Authorized Inspector; no access to the weld area in.ae anulous and " boxed in" areas formed by flooring and support structures; the lack of availability of equipment which would allow establishing zero leakage (borescope);
and the physical condition of the tank - no surface moisture present.
A previous sttempt had been made to hydrostatic test this tank (2T-87) on March 15-16, 1979. However, the technique used was to ex.mine the areas using a flashlight. The CB&I Master Checklist for Control and Certification and the CB&I Special Checklist were initialed and dated by the appropriate represen-tatives for the Authorized Inspection Agency, CB&I and Bechtel Co rpo ration.
The authorized Bechtel Corporation QC Inspector noted on his Construction Quality Control Subcontractor Surveillance Inspec-tion Record that approximately two feet of vertical weld seam on weld No. 1-A (e a s t',
and 1-B(west) could not be visually checked due to interference of structural steel and concrete
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floor. The width.pf the anulous area formed by flooring and tank wall was not wide enough to accomodate a nominal 1 "
diameter borescope. The thickness of the floor is estimated to be 24-30" thick.
Consumers Power Company made a similar notation in their Inspection /0verinspection Record on entry dated March 16,
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1979.
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The procedure used to hydrostatically test the tank, CBI Hydro-static Test Procedure HP-71701 states in Step 7.3, " Inspect all joints and connections" which is in agreement with the require-ments of 1974 ASdE Boiler and Pressure Vessel Code,Section III, Summer ' 76 Addenda, Art. NB-6000 which is referenced in Step 2.1 of the above referenced procedure.
Because of the geometric limitations the vertical weld seams penetrating the floor physically could not have been examined by use of a flashlight beam to establish zero leakage conditions.
On April 2,1979, the lice..;ee (Consumers Power Company) agreed.
Failure to " inspect all joints and connections" as presc /ibed in Step 7.3 of CBI Hydro Test Procedure HP-71701 is considered an itca of noncompliance with 10 CFR 50, Appendix B Criteria V.
(50-330/79-13-01)
Exit Interview The Resident Inspector attended the Exit Interviews conducted by R. Marsh aod M. Oestmann, RIII Investigator and Reactor Inspector on April 5 and April 27, 1979 respectively.
The Resident Inspector met with licensee representatives (denoted under Persons Contacted) on April 6, 13, and 26, 1979. The inspec-tor summarized the scope and findings of the inspection effort to date.
The licensee acknowledged the findings reported herein.
Attachment: Pcelimina ry Inspection Findings-7-
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PRELIM;I'ARY IN0?EC !ON FI!DI!:CS
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Consumers Power Company
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U.S. Nuclear Regulatory Comission 1945 West Parnall Road
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Jackson, MI
%9201 Office of Inspec 'on 4 Enforcemen:, RIII
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799 Roosevelt Road Midland Unit 1 (Midland, MI)
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Nidland Unit 2 (Midland, MI)
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DOCKET h'J.DERS 4.
LICENSE N C EERS 5.
DATE OF 1.NS?ECTICN 50-329 50-330 CPPR-al CPPR-82
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Q/ 7..The following matters ars preli=ina.ry".ino.paction findings:
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These preliminary inspection findings' vill be reviewed by'NRC Supe: vision /-
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P.anagement at the Region III Office and they vill correspond with you concerning any enforcenen; ac: ion.
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,,PRELDilhARY INS?ECTION FIUDISCS
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Cansomers Power Cumpanv 1945 West Parnall Road U.S. Nuclear Regulatory Concission Jackson, MI 49201 ce napect n & Enforcement, RIII Midland Unit 1 (Midland, MI)
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759 R osevelt Road Midland Unit 2 (Midland, MI)
glen Ellyn, IL-60137
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LOCKET NUMSERS 4.
LICENSE NUMBERS 5.
DNIE OF INSPECTICN 50-329 50-330 CPPR-81 CPPR-S2
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The fc11owing matters are prelimina{ inspection, findings 2
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These preliminary inspection findings vill be reviewed by'NRC Supervision /-
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,,PRELD'.!!'ARY I :S?ECTION FINDI!!GS
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LICENSEE
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Consumers Power Company g, 3 g
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DOCKET NUXSERS 4.
LICENSE NR'.3ERS 5.
DATE OF INSPECIION 51-329 50-330 CPPR-81 CPPR-82 g
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These preliminary inspection findings v 11 se' reviewed by'NRC Supe vision /-
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