ML19276H298
| ML19276H298 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 07/29/1971 |
| From: | Burzi A J, Howard E, Tillou J US ATOMIC ENERGY COMMISSION (AEC) |
| To: | |
| Shared Package | |
| ML19276H275 | List: |
| References | |
| 50-289-71-03, 50-289-71-3, NUDOCS 7910160642 | |
| Download: ML19276H298 (11) | |
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U. S. ATOMIC ENERGY COMMISSION DIVISION OF COMPLIldCE REGION I INSPECTION REPORT CO Report No.:
71-03 050-00320
Subject:
Metropolitan Edison Company Docket No. (s): 050-00289 Three Mile Island Units 1 and 2 License No. (s): CPPR-40 6 66 Location: On Susquehanna River, South of Category A
Harrisburg, Pennsylvania Date of Inspection:
June 24-25, 1971 Date of Previous Inspection: April 5-8, 1971 Type of Licensee:
Type of Inspection: Routine, Announced W
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Principal Inspector:
J. H. Tillou, Reactor Inspector Date b
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Accompanying Inspectors: A /V. J. Burzi, !(cactor Inspector (Const.)
Date
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. Hunnicutt, Sr. Reactor Inspector, CO:III Other Accompanying Personnel: W. H. Baunack, Reactor Inspector (Operations) 7' N ' 7 I
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Reviewed by. %
E. M. Howard, Senior Reactor Inspector Date Proprietary Information:
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60 rgs101
I.
O SECTION I Enforcement Action None Licensee Actions on Previousiv Identified Enforcement Matters A.
CDN, Dated Aoril 20, 1971 Recardine Cable Pull Slios and Lack of Separation In A Redundant 480 Volt Cable A reply was received on June 23, 1971 from Mr. J. G. Miller.
This was considered unsatisfactory by CO:I and a telecon was made to Mr. Miller A revised copy was promised and was subsequently explaining our concern.
received on July 2,1971, which acceptably stated the position and cor-rective action to be taken by the licensee.
This item is now considered resolved.
Concrete Poured In Reactor Buildine Wall in Contact With Less Than 32 F O
B.
Concrete The CDN covering this subject was forwarded to the liaensee on February 12, 1971.
An answer was received on March 8, 1971 which was not considered ac-ceptable nor to have established adequate corrective action for the entire problem.' The subject was next brought up at an ACRS subcommittee meeting at the reactor site on May 26, 1971. This meeting was continued at Bethesda on May 27, 1971 at which time the subject was discussed in detail with the DRL and CO technical support groups who accepted the preliminary verbal statements and reports of the licensee, which were to be verified and docu-mented in a formal report for DRL and C0 files. This item is consid.ered resolved.
C.
Grinnell Company Failure to Provide Material Certificates for Engineered ~
Safeguard Piping Systems In Accordance With Criterion VII, Accendix B, 10 CFR 50 The licensee has contacted the Grinnell Company at both their Kernersville, North Carolina and Warrcn, Ohio, plants and has scheduled audits for the at which time they intend to resolve the deficiencies first week in August, presented by this problem. This item will remain open and will be followed up on subsequent inspections.
(Paragraph 8)
Unresolved Items O
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q) 3-W Status of Previous 1v Reported Unresolved Items A.
Attachment Studs for Reflective Insulation This item remains unresolved.
(Paragraph 3)
B.
Licensee's Failure to Recuire OA/QC Particioation in Pinine System Over-Pressure ilydro Tests (A Resoonsibility of the Met Ed Ocerations Grouc The CO inspector will audit implementation of this program during subsc-quent inspections.
(Paragraph 4)
C.
1007. UT of the Reactor Vessel Shell and Nozzle Welds The C0 inspector will followup this it6m during the next inspection.
(Paragraph 5)
D.
Disposition of Three Reactor Vessel Nozzle Weld Preoarations, Damaced in 9
Transit This item is considered resolved.
(Paragraph 6)
E.
Core Flooding Tanks Fabricated Without NDTT Test Records The C0 inspector will continue to fo.11owup this item until resolved.
(Paragraph 7)
Persons Contacted Met Ed Mr. J. G. Miller, Vice President, Engineering Mr. George Bierman, Project Manager, Met Ed Mr. Matt Stromberg, Met Ed Senior Site QA Engineer Mr. Larry Lundstrom, QA Engineer, Structural and Piping Mr. Leroy Price, QA Engineer, Structure and Tendons Mr. Jack Wise, Operations Supervisor, Unit 1 Mr. William Shepard, Site Resident Engineer Mr. Joe Stoudt, OA Engineer, Electrical Mr. Vern Stuebner, Site Electrical Engineer UE&C O
Mr. J. Fant, Senior Site QA/QC Supervisor Mr. Carl Brooks, Piping Superintendent j
[,] [yg Mr. Robert Thomas, Site QA Engineer B&W ur.
Tack Ubic. Three Mile Island Site Manager
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9.
Management Exit Interview The following persons attended a site exit interview held on the afternoon of June 25, 1971.
Mr. M. Stromberg, Met Ed QA Supervisor Mr. W. S. Shepard, Three Mile Island Resident Engineer Mr. N. Goodenough, Met Ed/GPU QA Specialist Mr. L. Lundstrom, Met Ed QA Engineer Mr. L. Price, Met Ed QA Specialist Mr. J. R. Stoudt, Met Ed Electrical Engineer Mr. V. Stuebner, Met Ed Resident Electrical Engineer The following items were discussed.
Licensee's Failure to Reauire That Grinnell Supolv Comolete Material and A.
Fabrication Records for Pioine Soools in Class N-1 Systems 9.
Mr. Stromberg stated that Met Ed had been concerned regarding the Grinnell failure to comply with the requirements of Criterion VII, Appendix 3,10 CFR 50 and has scheduled an audit at their facility the first week in August 1971, to both bring the records up to date for material received on site and. arrange for simultaneous delivery of material and records in the future.
0 Placement of Concrete At Temperatures'Below 32 F B.
The CO inspector expressed his concern that this nonconformance, which occurred in January of 1971, still had not been resolved.
Mr. Shepard produced a preliminary copy of the Gilbert Associates report, 15,1971, " Evaluation of Concrete Placed in the Fuel Handling dated Janu: ry Wall on January 8,1971", which concluded that af ter tests of cores taken from the cancrete, micro-inspection, and engineering evaluation by consul-tants that. the concrete was "OK, as is, for service, durability, and safety".
Mr. Shepard further stated that this report has not as yet been completely reviewed and approved by Met Ed but will be expedited in time for form al presentation to DRL at a meeting scheduled in Bethesda on June 29 1971.
of Weldine Studs to the OD Surface of the Rea tor Vessel, the C.
Subject Pressurizer and the Steam Generators for Installation of Reflective O
Insulation Blankets Mr. Shepard produced evidence of an exchange of correspondence between Het Ed and B&W, Barbarton, which verified that prior to final stress 1419 150 6
O 5-rel_ieving each of the subject vessels had had one quarter inch thick pads welded to the exterior surface in the locations designated by the re-Mr.
vised GAI drawing to provide an area for welding insulation studs.
Shepard stated that E&W has not, to date, provided as-built drawings for these vessels but has agreed to expedite these and have them available in the very near future.
He will continue to followup on this item and make the drawings available to the CO inspector in the near future.
Ultrasonic Insocction of the Seam and Nozzle Welds on the Reactor Vessel D.
Mr. Neil Goodencugh reported that the UT is being conducted by a special CONAM research technician as insurance against the possible existence The work of rejectable defects such as were found in the Zion vessel.
has been completed on the reactor vessel and is planned for the steam generators and pressurizers, although this is being delayed by the site work stoppage since the CONAM technicians are affiliated with the oper-ating engineers union.
Mr. Goodenough also stated that the work being done manually by the CONAM technicians is considered an insurance-type The results cannot be used for the in-service inspection 9
inspection.
baseline records, which will be accomplished by an automated technique being developed by Southwest Research Institute.
Mr. Goodenough further stated that the results, when complete, will be made available to the CO inspector ac part of the package of records for the reactor vessel, steam generators, and pressurizer.
E.
Code Hydro Testing of Piping (Over-Pressure Tests)
Mr. Shepard stated that the responsibility for all hydro testing of com-pleted piping systems has been delegated to the site operations group.
They prepare procedures, test parameters, calibration of gages, establish water quality, venting requirements, valve check-off lists, and define the boundaries for each test.
In addition, they provide color roded The sign-off sheets for the testing technicians and QC representatives.
actual test work on site is delegated to the UE&C test and preoperational group under the supervision of the Met Ed operations personnel.
The special procedures used for the testing of the NSSS system are developed by B&W, approved by the Met Ed operations group, and implemented by the UE6C test and operational personnel, with all final tests witnessed by
.the B&W site representative.
The C0 inspector agreed that the planning appeared adequate and that preparations had been made to provide reliabic information by these tests.
1419 151
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Core Flooding Tanks Without NDTT Tests F.
Mr. Shepard stated that the core flooding tanks manufactured by Stearns-Roger
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The fabricated of material which had been NDTT tested.
for B&W were not However, Met Ed ha~s agreed tanks are presently in a " rejected" status.provided GAI develops a hot air heatin that they will be acceptable,.iaintain the core flgoding tanks and the in-tem and a shroud which will cluded water at all times s' ave the critical 115 F NDTT. The core flooding the other specification requirements for sur-tanks will also have to meet testing, operation and general service.
veillance, G.
Decay Heat Coolers the decay heat coolers, which had been cleaned in Mr. Shepard stated that a chlorinated solvent, were returned to the fabricator, Whitlock Manu-They are scheduled facturing Company, for recleaning and corrective action.
Met Ed has advised Whitlock Manu-for return to the site in July 1971.
facturing to hold the coolers at their manufacturing facility until the 9
present work stoppage on site has been settled.
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O ECTION II Additional Subiects Insoected, Not Identified in Section I, Where No De-ficiencies or Unresolved Items Were Found 1.
Feedvater System This system was selected for inspection, and the following areas relative to welding of this piping system were evaluated:
a.
Implementation of the QA program, Quality control procedures, uo-a performance procedures, and/or b.
record keeping for the follow.ng items applicable to this system.
(1) Qualification of weld pt c.dures, weIders, NDT techniques, and technicians.
(2) Identification of weld location, welders, NDT technicians, NDT procedures, and NDT results.
inspection (3; QC inspector's procedures to specify performance of root of joint preparation, environmental control, root gap, alignment, root pass, and completed welds.
h.nterpasstemperature, post-veldcon-(4) Verification of heat treat, trolled cooling, and stress relieving.
(5) Evaluation of radiographic quality, weld quality, magnetic particle, dye penetrant, and ultrasonic evaluation.
(6) Correlation of records to welds.
(7) Defect renoval techniques, removal icrification, and acceptance.
(8) Material receiving and post-issue environmental control of electrodes.
The following records were reviewed as applicable to this piping system.
c.
(1) Visual inspection.
(2) Heat treat records.
(3) NDT records.
3 153 (4) Repair records.
(5) Materials control.
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No work practices were observed since chere was nu work Laias perh rmed.
d.
on the construction site as a result of the operating engineers yprk,...,
stoppage.
The following items were inspected to verify that the licensee had met fabrication, and construction requirements on materials. procurement, erection.
Implementation of QA program.
a.
Quality control procedures and quarantine of aonconforming material.
b.
(1) Materials certifications covering the chemical, physical and nondestructive requirements.
(2) Receiving procedures and quarantine of nonconforming material.
(3) Storage identification, control and protection requirements.
(4) Installation of hangers, bellows, snubbers and installation NDT.
(5) Cleanliness and hydrostatic testing.
The following records were reviewed as applicable to this piping system.
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c.
(1) Material certificates covering chemical, physical and nondestructive testing, etc.
(2) Vendor's inspection report and site receiving records.
(3) No work practices could be observed since there was no piping activity on site due to the work stoppage by the operating engingers.
2.
Electrical Comoonents and Cables The following areas of this subject were inspected:
Implementation of QA program, a.
Quality control procedures for work performance 'and record keeping b.
applicabic to this program.
(1) Handling and storage, j,g
,1-154 (2) Receiving and quarantine of nonconfoming materials.
(3) Installation procedures and instructions.
TaenacH on and preoperational testing.
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. The following records were reviewed as applicabic to these activities:
c.
(1) Cable pull cards for safeguards and nonsafeguards cables.
(2) Color coding cables.
(3) Electrical connections tests.
(4) Cable receiving records.
(5) Installation records for cabic trays and conduit.
(6) NDT records from cable vendors.
Work practices were observed within the limitations of the slow down d.
in site activities created by the operating engineers work stoppage.
(1) Installation techniques.
(2) Storage protection of installed items.
(3) Use of specified materials.
(4) Cable routing.
(5) Wireway loading.
Details of Subjects Discussed in Section I 3.
Attachment Studs for Reflective Insulation No procedures or inspection planning for the welding of attachment studs to the exterior of the reactor vessel, steam generators and pressurizers could be produced.
Mr. William Shepard stated that he is following up B&W for up-to-date, as-built drawings of these vessels to verify that rne quarter inch thick pads have been welded to the exterior of the ves-the reflective insula-sels prior to its final stress relieving to accept He tion studs called out on the latest Gilbert Associates drawing.
arc. ecd to have these as-built B&W drawings available for the inspector's review at the next inspection.
This item remains unresolved.
O 1419 155
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Licensee's Failure to Recuire OA/0C Participation in Pioine System over-
'4 Pressure Hydro Tests Discussions with Mr. J. Wise, Head of the Met Ed Site Operations Group, indicate that they will prepare the generic specifications for testing, including the pressures to be used, the venting, valve check-off list, and will provide color coded sign-the defined boundaries for each test, Each specific system procedure will require review and ap-Specific procedures for the off sheets.
proval by Met Ed site QA/QC representative.
NSSS system are being developed by B&W to provide smooth interface and.
uniform testing procedures throughout all segments of each piping system.
It appears that the licensee has revised his procedures to be in conform-The C0 in-ance with the PSAR commitments for testing of the piping.
implementation of this program during subsequent in-spector will audit spections.
100% UT of RV Shell and Nozzle Welds 5.
9 Based on the defects identified in the Zion vessel during UT baseline in-spection, t>m licensee has elected to conduct a complete UT inspectionThi of his reactor vessel seam and nozzle welds.
It is incomplete to date, since the CONAM by the CONAM Inspection Agency. technicians are affiliated with the ope the reactor vessel and pressurizer have The preliminary results indicate that no defects in excess of the code but the steam generator has not yet been in-The CO inspector will followup on this item during the next scanned.
spection.
Disposition of Three RV Nozzle Weld Preoarations, Damaged in Transit 6.
The B&W site representative prepared an "NS.e5 Component Deviation Report" covering the damage to the " land" of the veld prepara-26, 1971, The repair was accomplished by machining one quarter inch off from on April forwarded by tions.
the damaged lip of the weld prep utilizing special equipmentThe entire repa B&W from their Barbarton plant. inspected and found to be acceptable by the shell weld was dye penetrantThis item is considered resolved.
B&W site representative.
1419 156 Core Flooding Tanks Fabricated Without NDTT Test Records 7.
the site; however a decision has been These items were rejected by B&W at made and agreed to by Met Ed that the core flooding tanks can be used with the addition of a shroud and a hot air heating system to maintain all pressure restraining portions of the tank at a temperature above the is working with NDTT level.
Mr. William Shepard, Met Ed Site Engineer, CAI on this design and has agreed to keep the C0 inspector current with developments as they occur.
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i Licensee's Failure to Recuire That The Pioing Fa'oricator Prcvide Oczn for Class N-1 pioine Spools _
8.
Documentation Records It was stated that the original purchase order to Grinnell had not from Grinnell.
- Rather, required complete documentation with each shipmentit i
upon the completion of shipment of each system.
the documents had that the UELC vendor inspection records showed thatthe Grinne finishing, the identification, workmanship, and nondestructive testing been reviewed at It was finally pointed out that for each item prior to its shipment.
Grinnell accompanying each shipment was a certificate of compliance from ification stating "The items on this shipment meet the Grinnell standard spec h
and the individual shop fabrication ske.tches" and d
The inspector by Gilbert Associates prior to their use in fabrication.the above hich pointed out that G
Met Ed stated will be backfitted to this facility.
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