ML19319A734
| ML19319A734 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 08/11/1970 |
| From: | Kelley W, Murphy C, Seidle W US ATOMIC ENERGY COMMISSION (AEC) |
| To: | |
| Shared Package | |
| ML19319A733 | List: |
| References | |
| 50-269-70-07, 50-269-70-7, NUDOCS 7911280682 | |
| Download: ML19319A734 (16) | |
Text
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s U. S. ATOMIC E';EFGt' CCOUSS JON
!!EG ICil 1L DIVISION OF COMil.IANCE Rcport of Inspection CO Pr p:rt !; o, 10-/c9/iO-7 Lic en see :
Duke Pur Co @ ny Cc o r.e e 1 Lieense "n.
CNR- $ 3 Cj 0 ega r y 13 Date of Inspection:
li e 29 July 2, 1970 Date of Previous I:ispect io n :
May 25-23, 19/0 p______
,_7 /Lf,h3 lh
[/2 Inspected Ily: c
. tor T..pactor U.it e C. E. Murphy,4ct.
( Ti Charge) 4/
MLD' :h(/)
8:M0 p_
el ley, TCric t or Ir spector (C3nst ruct ion)
Date U.
D.
M 20 Reviewed liy :
Y 2'
" ~ ~ '
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W. C. Seidle, Scnice Re ' : tor Ins pe ct or
.2te I;0TE : The sections of thia repor t relatir; to a lding ar.d p ip in ; et e prepared in the main by W.
D. Kelley.
Proprietary Inf ormatic n :
N r. n e S COPE.
A rout ine, announced inspcction Ws node of the zS58 int pressurized water reactor under construction near Seneca, S:uth Cnclina, known as Oconee Station No. 1.
Purposes of the inspretien were: (1) to deteruine the con-struction status and s ignificant charp,a3 to schedule dates; (2) to review records and work perforrnnce relating to mrchanical equipment and piping systems; (1) to review work pe rforr.ance relative to stressing the reactor building tendons; and (4) to d i sc'n s t ha problems experienced with the prinary coolant pumps.
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9 (1 79//22868R L
00 Rpt. No. 50-269/70-7 2-SIMtARY S fety Items _ - None 3
Munc u n f o rp.u a c e Items'- f*one Status of previously Reported Probl eus_ -
-1.
The 28-day tests indicate that the Ltt eagth of t he co r.c r e t e is now within the FSAR limits.
(See Section C.)
2.
The II. ennce plans to mak.c final tepairs to the cont ainment liner immediately prior to performing the leak tests.
(See Sect ion G.)
j' 3.
The reactor coolant paaps are being replaced with Westinghouse puun, i-(See Sect f on F.)
I' 4.
Deficiencies previously noted in the welding of the borated uater storage tank have been cor rected.
(See Section N.)
5.
The modifications to the polar crane control circuits have not been ccmpleted.
(See Section H.)
6.-
The licensee has corrected the electrical penetration flange seal leakage problem. (See Section H.)
7.
The tendon stressing procedure has been revised and an herovement has been experienced in obtaintr:g proper clongations and seating forces.
(See Section G.)
Other Significant Items -
1.
The licensee has contracted with B&W to establish a program for the in-service inspection of the nucicar reactor coolant systems. B&W has prepared preliminary procedures and is presently c nducting base line measurements.
(See Sec t ion 1. )
' 2.L The engineering' department is now maintaining a. list o f quality assur-ance probices.
(See Section J.)
3.
Af ter further consideration, the licensee has decided to have the routing of the transducer tubing determined by designers in the
_ Sce Section H.1)
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Charlotte engineering of fices.
.-Outstanding Items - See Exhibit A for current status of outstanding items.
gnagement Interview - The management interview was held on July 2,1970, and was attended by Rogers, Beam and Wells.
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CO Rpt. !!o. 50-269/70-7 b 1.
The inspectors discussed' the nondest ruct ive test ing requirements for ptmips, valves and piping as outlined in Table A.
A review of L&W pur-chase specifications had indicated that the NDT requirements in some ec,cr. did not met the a f o !num r e qu i t erx" t s of Table A.
Ti e i mpa c t ers were assured that the 1icenscc would take the action necessary to com-ply with the Table A requirements.
(See Section 0.)
2.
The availability of r ecords for E&W supplied equipment was discussed.
Records of B&W fabr icated equipment are being kept by PW, but ti e records for equipment purchaned by B&W will be delivered to the licens ee for pe naancut storage. The licensec statcd that since these racotds were not readily available for audit, copics of tecords for P&W pur-chased items that were of interest to the incpect ots would be sent to the site prior to the next ins p c e t io n.
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3.
The licensee has agreed to supply the inspector with a history of the pressure vessel nozzles.1/
f 4.
The licensee stated thht the monthly report of cngineering related problems would be given the inspector each month.
(See Section J.)
l 5.
The inspectors advised the licensee that no itens of noncoaformance
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had been noted during the inspection.
DETAILS A.
Persons Contacted Duke Power Cotc.pany (Duke)
J. C. Rogers - Project Engineer D. C. Beam - Assistant Project Engineer J. R. Wells - Principal Field Engineer G. L. Ilunnicutt - Field Engineer, Civil R. E. Blaisdell - Velding Engineer C. B. Aycock.- Field Engineer, Electrical R. E. Miller - Mechancial Engineer, Charlotte J. L. Oestertag - Mechanical Engineer, Charlotte J. E. Smith - Plant Superintendent J. W.11ampton - Assistant Superintendent Babcock and Wilcox Company (P6V1 V. Faasse - Field Superintendent 1/ emo from CO:HQ (O'Reilly), dated 5/1/70.
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.C0 Rpt. No. 50-269/70-1 3 Pit tsburnh-Des Moines Steel Ceppany (PDM)_
D. R. Clutadler - Qt.al ity Cc.ntr ol !!,n.at;e r B.
Adrainist rat ion and Organization Ef fect ive June 1,1970, D. C. Beata was appointed assistant project engineer for the Ocence Stat lon.
C.
Qnality_ Assurance 1.
No changes have been mde in the lic ensee's quality assurance organization or precedures.
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f 2.
Quality assura[cc items are discussed in the individual t eort sections.
D.
Construction Pr_ ogress 1.
Placement of shield wall concr ete has been coupleted.
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2.
The restressing of the Unit 1 tendons is new in progress.
Creasir.3 of the tendons is being accomplished straultaneously with the stressing operations.
l 3.
The 36-inch primary coolant pipirg is now being erected.
4.
The permanent pressurizer support is be ing installed. The pres-surizer will not be coved into position, however, tutil the coolant pu:.0 volutes have been replaced.
5.
Erection of the turbine generator has begun. All major pieces have arrived at the jobsite.
E.
Schedule Dates The licensee is presently revising the construct ion and testing schedule to reficct the replacement of the primary coolant puaps. The inspector uas advised that a corrected schedule would be issued by the niiddle of July.
It is now expected that core loading will not occur until February 1970, but the 1*censee is hopeful that the' unit will be ready for operation in time to neet the su:.aner peak load.
F.
Reactor Coolant Pump The inspector _was advised by Wells that the pumps for Unit I were being replaced by Westinghouse Electric Corporc. tion (U) ptups from b,
the Diablo Canyon Nucicar St at ion. ' The volutes, which are at Diablo
CO Itpt. f o. 50-269/70 1 Canyon, are to be shipped to the Oconee Stat ion in the near future.
The internals for the pumps are presently at the H Cheswick plant.
Internals for two pumps are expected to be at Oconee in October and br.
Tbc ?;dn nifc h,c t < r ! c t i-s for the tuo reeaIning p Ts in ?b 4
of the' W ptups are very close to thosc of the Lin,;haa Peap Company (Bingham) pumps. Modifications will be required to the pumps, motors and piping, however, s ince the physi al arrangenents of the purr.ps differ. The nozzles on the Binghm pugps are 28 inches in diameter, whereas they are 31 inches on tbc g pumps.
Forged toducers are being obtained. from the Taylor Forge Company (Taylor Force) for use as transition pieces between the coolant pipe und the puma volut es.
Eight-foct-long nozzle sections are being ren oved f rom the priuary piping at Oconce and sent to Taylor Forge for. the at tachment of the reducers. The licensee plans to remove the pur.p volutes and nozzle i
sections using acetylene to cut the carbon steel and air-arc to cut
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the stainless steel.
The licensee does not ant ic ipate any trouble with the heat af fecting the new weld preparat ions since the cut ends are to -be nachined back 1-5/8 inches with a Froussand bar machine.
In that the Bingham pumps have a tangential discharge, whernas the g pumps have a radial discharge, the loop piping must be twdified soucwhat to obtain the necessary realignment. The pump n otor bases must also be modified to accomodate the pumps, but Uells stated that he did not
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know as yet if any modifications would be required to the shafts and couplings. The full extent of the modificat ions to the motor seismic braces have not been determined, but a preliminny review indicated that only the elevation of the attachuents to the containwent wall would require changing. Wells and Blaisdell ucre asked if they planned to develop written procedures for the replacenent of the pumps. Blaisdell stated' that complete precedures would be developed for the welding and cutting operations. The removal of the pump volutes is scheduled to take place within one month and the ncu pumps are to be installed la time to permit core loading in Fchruary 1971.
Volls also advised the inspectors that the decay heat systera would require modification and both the high pressure and low pressure injection systems would be affected. Details of these changes were nct'available.
G.
Containment 1.
Concrete Uells advised the inspector that 28-day tests made since the previous inspection have shown the strength of the concrete to be above 5000 psi.
The louest break uas on the order of 5085 pounds and the major ity were about 5500 pounds. lie stated that the cause of the low breaks had never been fully determined although some correlation had been noted between the tests run at the site and tests run by the cement manufacturer on the ccment. The last placement of con-
..Q crete in the. Unit i shicid wall area which was required to meet tie i
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CO Rpt. No. 50-269/70-7 6-i 5000 psi strength requirement has been made.
The liccusee plans to justify the previous use of low strength concrete by engineering analyses and the results of 90-day strength tests. This informa-
.. cal U d in r N m.c t-
.r t tinn it t o te
.. on &fi b cy not ic e issued as a result of a previous inspection.l/ No further action is planned by the Inspector at this tin,e p"nding t he licens 2c's response to the CDN.
2.
Tendons (4705.04.c.4 and 4705.09)
The inspector reviewed t he revised tendon stressing procedure and the records relat ing to the M. ress ing operat ions. The procedure now requires that the tendons be stressed up to three t ht.e s if upca initial stressing the elongat !cn is not within S7. of the calculated elongatlon. During an invest Igat fon oC the st reu Ing operations, j
the IIcensee found that t'ae hydraulic pressut e of tha jack lagged the pump pressure by 300 pounds. One pressure gauge used in deter-i inning seat ing pressures has been relocated fr<m the pucaps to the jacks. A review of the records by the inspector indicated that the cloagations, for t he n.cs t part, exceeded t he calculat ed clongat ions.
Approxinately 457. of the tendons had elongat icn3 ubich exceeded calculated values by greater than 107..
Ve r y few were w ith in 57..
I The seating pressures were all within the reo"tred range of 6300-6500 psig range as ocasured on the pressure gauges. The licensee is installing the end caps on the tendons and filling the tendon sheaths with a protective cunpound.
No problens have be. n experier.ced with these operations. The inspector plans no furthur action rela-tive to the tendon innpection until a reply is received f em the licensee relative - to the construction deficiency notice which had been issued concerning t.be out-of-tolerance clongat ions.2,/
3.
Containment Liner, The inspector was advised by llunnicut that the licensee planned a thorough inspection of the containment liner innediately prior to the containment icak tests.
He stated that all teraporary scaf fold clips and hangers would be rer.oved and all surface de fec* s ground out and repaired. The inspector plans no further action on this item until af ter the repairs are made.
I/- CO:11 Report No. 50-269/ 70- 5 anti CDN dated 6/19/70.
2./C0 ill Repott No. 50-269/70-6 and CDN dated 6/24/70.
l.s..
CO itpt. No. 50-269/70-7 i 4.
Jontainment Proof Testing (5405.04.f.6)
Procedures for the proof testing will be revicued as a part of the s up c i a L I. n.a test e x o gr a
- t. i a.. e t '. ne pi ec edures are 1lc I ng p repar ed by the licensee's plant operations group and the proof testing will be conducted by this group. The inspecto r will issue his comw..u.s prior to the start of test ing by the licensee.
11. Elect rical and Innt rumentat f on 1.
Elec t r ical Penet ra tJons, Aycock advised the inspector that it had been determined that the electricians had not followed the naproved procedures during the installat ion of the e etrical penetrat Ions and this had caused the
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flange seats to leak -
The prina ry cause of the leaks had been tb improper torquing of the flange bolts. The electticfans are now torquing the bolts in the proper sequence and rechecking the torques as r.uluired by the procedure. The "O" rings used in the seals are also being protected frem scratches and the seal seats are being cleaned to remove any part icles which might damage the "O" rings.
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2.
Polar Crane Modif icat ions The inspector was advised by Ayecek that the modifleations had not been made to the olar crane as yet.
These codifications, as pre-When viously reported,_./ were to have been accomplished much sooner.
the design changes had been reviewed by Aycock, however, he had found that all of the parts necessary, for the work had not been rccoived.
lie stated that as coon as the parts were received, the modifications would be made since it was becoming increasingly dif ficult to schedule the crane out of service.
3.
Instrument Transducer Tubing Aycock advised the inspector that, contrary to the advice previously given the inspector, the licensac now plos,to have the routing of transducer tubing determined by design engineers in Charlotte. The magnitude of the work involved was the primary reason for this change.
4.
Battery System - Attachment I Followup Record Review - ( 5105.05.a.3_ and b.1) a.
The inspector reviewed the records relo ing to the emergency bat t e r ie s. The battery cells had been -eceived in good 1/CO:II Report No. 50-269/70-6.
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1 CO ppt. tio. 50-269/70-7 condition. The reports indicate that the specific gravity of a pilot cell is taken daily. !!o deficiencies were noted.
!!aterial certifications are not required.
b.
Follo,a:p Obs e r vat ions o f Wo rk _ ( 510 5.06.a. 2, a. 4, and b.1)_
The batteries are stored in the turbine building cable spreading ro om. The inspector observed that the battery cells were in their shipping cartons and appeared to be in good condit lons.
Although one broken ec11 had been received, it had been replacad.
No special provistens relating to the quarantine of nonconforning material was necessary.
I.
!!uclear Steam Sofply Syffem In-Service Inspect fon j
The Inc.pectors were adviced by Wells that B&W had been given a contract to develop in-service inspect ion precedures for the nucicar steam sup-ply systcm. B&W has developed the preliminary procedures for the work.
These procederes are being used to conduct baseline measurements and will be revised on the basis of the experience gained during these measurements. The inspectors were advised that ASME Code,Section XI, was used as the basis for the procedures.
The Inspectors observed the
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ultratonic measurements being made on the steam generator skirts. The technician performing the work appeared to be well qualified and uas vary thorough in his work. Faasse told the inspectors that they could review the procedures af ter they were issued in final form.
J.
Engineering problems The Charlotte engineering of fice has begun issuing a monthly report of engineering related problems (Exhibit B).
The items in the reports will be numbered sequentially beginnIng with this first report and will be carried forward each month until satisfactory resolutions are obtained.
The licensee agreed to supply.the inspector with a copy of each monthly report.
K.
Letdown Coolers - Attachment L l.
Follouup Record Review (4905.05.a.2 and.06.b.1 and b.2)
The inspector reviewed the source inspection records relating to the letdown coolers, IllP-CIA and IHP-CIB. The reports indicated that. the material certifications, ucid records and NDT records were_found to be acceptabic. The reports further stated that the B&W inspectors had witnessed the final liquid penetrant testing of the tube to manifold welds and bad rcviewed the radiographs of the longitudinal-welds. No deficiencies were noted. The inspector also reviewed the receipt _ inspection forms for the coolers.- The k
forms stated that the coolers were received in good condition.
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A
C0 Ret. No. 50-269/70-7
.9-i' One cooler was received packaged in a special polyethylene wrapping and:was stored in.- the licensee's storage yard. The other cooler was stored in the warehouse. Since the coolers Wre received in good condition, they were not placed in qu.nantine. The licensee stated that the QC cettiiication.
wc 21d be available at the site for review during th, next incpections.
h.
Pressu.!.zer Support - Atta chment E 1.
Welding Followup Record Review (4805.05.a.3, a.4 and a.5) a.
i A review of the records for the pressurizer support structure j
welds indicated that they had been ultrasonically tested using a Kraut-Krarcecr portabic test set which had been cali-brated with a Mare Island Navy Shipyard calibration block.
The number of weld defects and details of their location and repairs had been properly recorded. Approved procedures had
' heen used in making the welds and the repairs.
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b.
Followup Observation of Work (4805.06.a.1, a.3 and a. 5)
A visual inspection was nade by the Compliance inspector of the welding and nondestructive test ing on the gusset plate supports. The identification o f the welds, weldor, and inspector is recorded on Form QU-22.
The ultrasonic inspec-t ion data is recorded on Form QC-20.
The E7018 electrodes were stored in electrode ovens and no loose electrodes were observed in the work area.
2.
Structures and _ Supports _
Followup Record Review (5405.05.a.2 and a.3) a.
Structural material received at the s ite is unloaded and inspected at the storage yard. Mill certifications for the structural members were reviewed and found to be in order.
The installation records were those reviewed in 4805.05 above.
b.
Followup Observation of Work _(5405.06.a.2 and a.3)
- Since the structural el eork was inspected at the fabricator's plant,'no QC inspwi 'n was made at the site. The support will be lif ted into ?. v-the bolted connections torqued 'in accordance with id u
,utrcrents.
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C0 Rpt. No. 50-269/70-7 t M.
1I1r0 Pressure and Low pressure Injection Pumps - Attachment L 1.
Review of QC System (4905.04.b.2, b.6, b.7, c.1, c.2 and c.3)
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The QC system for the PF and LP inject ion pumps was previously reviewed during an audit of the reactor coolant pumps.1/ The procedures were developed by B&U for their nacicar steam supply system components and a complete set is kept in the licensee's site of fices.
2.
Followup Record Review (4905.05.a.2 and a.3)
The inspector reviewed the rec e ip t insp ec t io n reportsforthehig}
pressure inject ion pumps lip-PIA, PIB and PIC.
The reports stated.
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that he pumps had been received in good condition. One ptup was.
stored in the licensee's storage lot covered with polyethylene; l
the other two pumps were stored in the turbine room.
The receipt inspection report for the low pressure injection pumps, LP-PIA, PIB and PIC, indicated that temporary covers were missing from two of the puras and for' ign matter was found in them.
The covers were replaced and the pumps were reinspected on October 8, 1969, and February 25, 1970. An installation inspection report dated g
May 28, 1970, indicated that the IIP injection pumps had been satis factorily installed. The manufacturer's QC records were not available during this inspect ion, but the licensee stated that he would have complete documentation at the site in time for the next ins pec t io n.
3.
Followup Observation of Work (4905.06.n.2g./3 b.1 and b.2)
The inspectors viewed the pump installation and discussed the in-sta11ation methods with McIls. No deficiencies were ncted. None of the pumps were placed in quarantine inasmuch as no deficiencies had been noted. The area where the pumps are installed has been placed of f limits except to approved personnel and the protection of the pumps is considered to be adequate.
N.
Borated Water Storage Tank The inspector reviewed the progr'ss being made in the fabrication of the borated wat'er storage tank.
PDM has submitted copies of all the required welding procedures and a weld repair procedure to B&U. These' procedures were reviewed and approved by B&W and the licensee. PD:1 has also submitted a vacuum box testing procedure to B&W for their approval.
'1/CO:1I Report No.' 50-269/69-9.'
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CO - Rp t. ' No. 50-269/70-7.
All nondestructive testing is now being performed by Chandler, and welding is being done by Burgess who has been qualified for welding in both the flat and horizontal positions. The first horizontal unld on the tank was rmeved completely and rtucided, ha v.u t ic al welds in the first course and two in the second course were also removed and reuelded. The tank crection has now progressed to the sixth cource.' The welding and testing is now being done according to ' approved procedures and no further action is planned by the insp ec to r.
O.
Main Sten. Pip ing 1.
Cencral
.l' Miller and Oestertag met with the Compliance inspector to review the main steam piping material certi fications, NDE records and the licensee's recordkeeping system. Miller stated that the licensee had reviewed the material certifications furnishcd by the Grinnell Company (Gri.ncil) and had found numerous typographical errors and ir. complete reports.
Crinnell had been.:dvised that they were to reaudit all of the records furnished to the licensee for Oconce and to correct or have the vendors correct all the mate':ials
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certifications.
2.
Records Review (5005.05.a.1, a.2 and a.3)
The inspector reviewed the records for the thirty-four-inch by twenty-four-inch 450 lateral that had been previoualy reported being properly certified.M The correct ed records indi-as not cated that the material was certified to ASTM, A216, Grade UCC.
' The fitting had been hydrostatically tested at 2100 psig which
' is twice the design pressure.
The inspector also revicwed the records for the thirty-four-inch by twenty-four-inch 900 wye that had been previously reported as being incompletc..l./ The radiography shooting sketch showed approximately fifty percent overlap o f the film and that code requirements had been met.
This item is con-sidered to be complete and the inspector plans no further action.
3.
Recordkeeping System for Table A 'Itens Miller showed_the inspector a QA documentation package for a shop fabricated spool piece. An identification sheet Indicates the
. components included in the spool piece and lists the ASTM speci-fication number of the material, the manufacturer and shop order number of the components, the heat number, and a cross reference M CO:II-Report No. 50-269/70-6.
CO Rpt. !!o. 50-269/70-7,
1 to the licensect s engineering files. Miller stated that all certifications sent to the site in the future would be documented in this manner and that the licensee was considering recalling t he those previously cent to the e it r M re h : 13 g t L ar.
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same. format.
J.
Reactor Vessel - Attachment J Followup Observation of Work (4905.06.a.2; a.4 and b.2) at the site during the period when the reactor The inspector was not vessel was placed on it s foundatlon. A review of the records and discussions with UcIls indicate that no problems were ex/crienced in the installation. The licensee has crected a temporaty cover over the vessel to protect it frcm damage. The vessel was inspected by the licensee on May 13, 1970, for storage dauage.
No daaage was noted.
The inspector considers thase items t o be complete and plans no further ac t io n.
Q.
Steam Generator - Attachment L Followup Observation of Uork (4905.06.b.1 and b.2),
ins t a l. led The steata generators were received in good condition and were on their foundations. The inspector reviewed a tcport of storage inspection dated May 13, 1970. The report stated that the vessels were in good condition. The inspector also examined the steata generators during a tour of the containment an,1 noted no de fic ienc ies.
R.
pressurizer - Attachment L_
Followup Record Review (4905.05.a.2 and a.3),
' A review of the records indicated that the pressurizer had been inspected on May 13, 1970, and that no damage was noted. The vessel No has been temporarily stored on I-beams in the refueling canal.
Since the special storage protection is considered necessary.
pressurizer was received in good condition, there was no quarantine requircraents.
.S.
Preoperational Test Procedures The inspector reviewed and commented on the following preoperational test procedures. Smith and llampton indicated that all of the inspec-tor's comdents would be incorporated in the approved procedures.
b.
s-v C0 Ret. tio. 50-269/70-7,
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Procedure !!o.
TP 1A 120_ 4 Dry Fuel llandling Test TP 1A-150 4-1 Equipwnt 1:atch !.cuk Rate Test Reactor Building Cooler Functional Test TP 1A 160 2 RB Vent System Functional and Performance Test TP 1B 161 2
_ Reactor _ Building Purge Systeta Functional.and TP 1A 161 3 Operational Test Core Flood Tank Level Instruments Calibration TP 1B 201 1A
' Attachment s :
Exhibit'A and B 4
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e i
a 4
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LICENSEE Duke Power' Cc:rpany_
FACII,ITY _
Oconco Station !!o. 1
__1 DOCim1' & LICENSE MOS.
50-269, CPli%33 REACTOR OUTSTANDING ITEMS TT1EI.tiFIED l ITEM l _
CLOSED 18-2, 3/5/68, ljC, concreto test cylinder breaks below specs 68-3, D. 5.,
6/19/68 l
t 68-3,6/19/6a,gG Unauthorized revisien to Cadue3d crecifications 68-4, Su m ary, 9/25/69 68-3, 6/19/68, E Failure to provide concrete inspector 68-h, Sumary, 9/25/69 68-4, 9/25/68, EC, Failure to properly test Cadwald oplices 69-1 Summary,
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1/$69
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69-8, 9/9/69, LC, Failure to properly qualify weld procedures 69-9, G,11/3/69 i
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- 69-8,9/9/69,EC, Failure to properly qualify weldors 69--9, G,11/3/69
'133,4/11/69 Procedure for repair of are strikes not availablo 70-5, Sununary I
h/27/70
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CDh,1/8/70 NDT of core flooding valves Memo, WCS to HQ, 2/2/70 70-1, 1/6/70,_NC-Welding and I'liYi deficiencies, CDN iccued Memo, WCG to Ea, 3/26/70
- Bin 6 an 69-1, I/ain coolant pt=p discrepancies Closed, !!cmo, WCS D '
- h to HQ, 4/21/70 l 12/9/69,pc t
i 70-4,1/2'(/70, NC, Lov strength concrete 1
t Ii IEB,5/1/*(0 Pressure vessel safe ends.
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70-6,5/25/70,EC, Tendon stressing discrepancies h
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O'o-1Dfi!'iM HDTColumn: S - safety-item; NC - noncompliance or nonconformance j
UN - unresolvcif item; IN - inquiry item; 1EB - Reactor Inspection
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k{f h/ tem; Tiircement Branch requeEY; ~O - other cource of identification
_and En j
(briefly-specify)
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Exhibit A i
j-T 2nge 1 of 1 j j:
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-DUKE POWEft COMPANY-Gt'NEllAL OrhlCE
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CHARLOTTE. f frc---23201 f.)
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O z le 3 0la o,.I R "i lir ' C C TInthias Eg
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7 oU",",P,a(p'1%p,,_ _g',, " *e o e 0'-
ul no:.0conco 1-3
,.. Quality Assuranco
- Listed belua nro tho qualit'y pro'21 cms 'that uo consider significent; that have chcun op in tho fiolil rather then in tho shop; and for which tha Engir.ccring ocpartmnt is participating ~In development of _a solution:
^
J,t3
. Prditen Present S ta_tjn 1.
Tendon grease, Field tost shoas that quarantined pending Tank to 1 Chicrido content exceeds additional testing.
I PPil.
2..' Personnel Escapo Door interloc'( system
.U J Uoolicy Co.upany to Loch 1;o=l poeds adjusting draako adjustracntgel(.
of July 6,1970
[- '- (~ : 3.
Concreto-23 day strength belou llald, pending 90-day
,. PM Unit 3 Baso Glab c 5000 psi.
test resul ts and do-j;*
L 1
- Unit 1 Coaal Flcor.
," sign analysis V, -,'a lh ~Prostress Systua
- 6) Tendon scating.
Execeds 0 73 f's Tendons bcIng relacd end restressed.
pressurc
~ b) Tendon clopgation Calcuinted vs racasured Refer to Prostrossing olongation epcceds 17.4 llamo dated 6-9-70.
c) Tendon.discrop-Largo and:sealI button.
Tendons having discrepancies
.cncles
.hcads, broken utros, cro querentined cotll evaluction plugged. tendon shcaths, is ccmpic,ted after prestressinn.,
s-nte shield wall Crack duc-to.flold.
Ibid placed "on be., ring plato 5.
Secondcry' bearing.
ri uciding on booring until annlosis cud evaluation prostress plnto.
canboperforend.
p1ato.
p'
- 26. JLP-injection Peop '
Internal rubbing Returnnd to ingersoll-Scod at
-Bul's request-cuoiting' report
. Uni t //2 LP-23 ~
7.: Unluorth Clo o Defect indicated -in Revicued-in fleid and referred Valvo - !!!Ci'.-Vla s baco mtal of wcld end to 001 ond Volucrth. Fictd'rc-
' A
-s {.
wol d.'
~
pair._ procedurca being pregered.
by! x-ray af ter field
!!ca x-ray after' repair.
s
'n
.. -c Exhibit B-
-C O P Ye
){
rage 1 o f 2 -
r s
4 s
P d
!;r C E Uathina Pago 2 Juna 26,197d 8.
Dinchma RC Vibration and mecimnical l'ecisien to rc;>1,cn ui th
- '. x.-Unit 1 ucar probic.us on test Ue s t i nt.;l ou se r en'i's. Analysis (shop).I and design of required loop and'systea cfnnges in pro ;ress.
- 9. 'Crano Clottanoog, Itis milancous discrop,nclos.!;ceting scheduled by Duke Valves - Ualt I noted in rocc,rds Engineering with Crano and i
Pi ttsburgh I'es ti ng 1.r.. or atcry representatives to retiolvo di scer,:,,acios and est.'bl ish sighter proccourcs.
- 10. Criar.oll liain Discrepancy noted Rev1cu of records under,ny wi th Steaa Lina-Uni t 1 in records by all discrepancies rcierred to Division of Ccmplianco Grinnall for trxacdiato resolution.
.y
(
U S Lcc Vice Prostdent, Engineering p
-RECEIVED UGL/ s (Ull29'l0 cc lir R L Dick c yr_,,
' Rogers OCONEE 13 CONST. DEPT.
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i-Exhibit 13 Page 2 o f 2
.