IR 05000263/1975003
| ML20024G085 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 03/06/1975 |
| From: | Choules N, Hunter D, Jordan E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20024G080 | List: |
| References | |
| 50-263-75-03, 50-263-75-3, NUDOCS 9102070518 | |
| Download: ML20024G085 (6) | |
Text
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U. S. NUCLEAR REGULATORY C0t411SS10M OFFICE OF INSPECTInN AND ENTORCTJtENT (
.y,
REGION III
Report of Operations inspection IE Inspection Report No. 050-263/75-03 i
Liecnsect Northern States Power Conpany 414 Micollet Itall
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Minneapolis. !!innesota 55401 Monticello Nuc1 car Generating Station License No. DPR-22 Monticello, Minnesota Category:
C i
Type of Licensee:
E1.'R - 54 5 We (CE)
Type of Inspection:
Special - Announced Date of Inspection:
February 7, 1975 Date.s. of Pr.evio,us Inspection:
January 23 and 24, 1975~(Construction)
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m Principal Inspector:
.C Nd$c
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D. Hunter Accottpanying Inspector:
'Other Accompanying Personnel None l( f/I)*%b*lhA.-
.) [ _7 I Reviewed By:
. L. Jordan
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Senior Reactor Inspector
.(1 ate)
Reactor Operations branch
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9102070518 750306 PDR ADOCK 05000263
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i SUK'tARY OF TIND11:r.S
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hforcenent Action
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-None.
License,e Action on Previousiv Identifled Enforcerent Matters hot Applicable.
Unusaal Occurrences None.
Other Si nificant Fin,d,ints l
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A.
Current Findings 1.
The licensee has replaced the sectionn of the 4-inch recir-culation bypass lines containing cracks with new sections of piping.
2.
The licensee perforned ultrasonic tests of welds in the core spray lines and other selected pressu.e retaining relds and found no cracks.
B.
Unresolved Matters
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None.
C.
Status of Previously Reported Unresolved Itens
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None.
Manatenent Interview The following persons were present at the managenent interview conducted at the conclusion of the inspection on Tebruary 7, 1975.
C. E. Larson, plant 11anager P. J. Krunpos, Quality Assurance Engineer C. llarmnen, Supervising Engineer, Plant Engineering and Construction Department
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l A.
The inspectors stated that the purpose of the inspection was to re-view the results and actions reinted to the ultrasonic testing of ausi.enitic pipe welds as required by 11: Bulletin ro. 75-01 and to-2
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review documentation associated with installation of new piping in the 4-inch recirculation bypass ifnes to replace piping with cracks.
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B.
The inspectors stated they had reviewed quality control docunan-tation associated with installation of two sections of 4-inch bypass piping in the A and B recirculation loop and there were no apparent discrepencies.
(Paragraph 1)
C.
The inspectors stated that they had reviewed the results of ultra-sonic testing (UT) perforned to conforn with IE Eulletin No. 75-01 with the licensce's representatives. The incpectors stated that the licensee's representatives indicated there no detectable cracks in any of the pipe welds examined and that all ultrasonic testing indications had been interpreted to be reflected fron surfaces other than cracks. The licensee confirmed this, statement and stated that velds with indications would be evaluated and decisions made as to which welds will be reinspected during the Ecptember outage.
(Paragraph 2)
D.
The inspectors stated that review of inspection records indicated that the licensee had inspected the welde required by IE Bulletin No. 75-01 with the exception of the 28-inch recirculation line velds and the reactor head spray forcing veld at the vessel head flanges.
The inspector stated that concurrence had been previously obtained from the Region Ill URC Office not to perfort. inspections of the welds. The lice.nsee confirmed this statement..(Paragraph;3),
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l REPORT DETAILS
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Persons Contacted Northern States Pove_r Corpany C. E. Larson, Plant Manager C. Harmsen, Supervising Engineer, Plant Engineering and Construction Department P. J. Krunpos, Quality Assurance Engineer D. D. Antony, Plant Engineer Operations R. E. Grabinski, Production Plant Clerk
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Nuclear Service Corporati_o_n1 T. G. Lambert Manager of Plant Testing
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Hartford Stean Boiler Insurance Conpany C. Lingford 1.
On January 20. 1975, the licensee discovere; crack indications by ultrasonic testing in both the loop A and loop B reactor r(circulation 4-inch *jpasslinea.
This occurrence ucs reported in the licensee's
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report As a result of these cracks indication,s, F ticensee removed,the
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sections of pipe containing the crachs in cions and replaced
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with new piping sections. The inspector'
icwed the follouing quality control documentation related to installation of tha new piping and there vere no apparent discrepencies.
Material test reports for piping and piping citovs.
a.
b.
Weld identification and veld history cards.
The inspectors viewed the two sections of pipe vhich S cre reroved from the bypass lines. The sections were approximately 5 feet long.
The licensee plans to cut out the welds with crack indicatiens and send them to Ar6cnne National Laboratory for evaluation.
2.
On January 30, 1975 IE Eulletin No. 75-01 was issued which required the licensee to take volumetric examinations of certain austenitic pipe welds.
The licensee performed ultrasonic testing on wolds as follows.
1/ Abnormal Occurrence 75-03, NSP to DRL dated 1/30/75.
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All stainlesu steci velds on both core spray lines up to the
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second isolation valves.
(21 velds total)
.w b.
Two velds on a control rod drive return Ifne.
Two velds on loop B kemidual 11 cat Renoval line to recirculation c.
line, d.
One veld on the Standby Liquid Poison Eyaten.
c.
Seven velds on jet purp risers, f.
Four velds on the kencter Cleanup 1.ine.
The inspectors revieved ultrasonic testing recorder traces for all of the above velds.
Feveral velds had indications which vert inter-preted by licensee's reprevent ative to be.,yeflected from surf aces other than cracks.
The licensee reported'- that there vere 5 and 12 velds thrt showed indicationr. greater than 20; and 50% DAC*
respectively Certifications which indicated that the personn(1 performing the exaninations vore either 1(vel 11 or level 111 l'T 'nspectors vcre
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revicued.
A functional teet of both core sprny systers was perforned using core spray systems tests 1os. 0094 and 0095.
Kevleu of the corpleted tests procedures indicated they were performed on February 4, 1975,
and no Icakare in either spray line vos observed.
b 3.
The licensee requested prior to the inrpcetion not to exarine velds on the 28-inch recirculation lines and the reactor head spray line veld uhere a stainless steel ferring is velded at the vessel head
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flenge. All other piping in the head spray lines is carbn ster 1, Region III, KRC office concurred in not performing these inspections based on the following:
Two velds in each of the recirculation linen were inspected a.
during the ref ueling outage in 1074 b.
The reactor head spray velds were innpected during the 1973 refueling outare and forging velds vero not the concern in the 1E hulletin 1:o. 75-01.
- Distance Amplitude Correction 2) Letter NSp to Director Region III, I&E, NRC dated 2/14/74.
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UM1(0 $1 Af[$
NUCLL AH R E G U L ATORY COMMISSION 0FFICE Or 113PECT10N AND ENFORCEMENT
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769 MOOttvELT Mo Ao GLE N LL Lvfd. ILLINOl$ 60137 A.
IE Inspection Report No.
050-79/75-03 March 6. 1975 Transmittal Date
Distribution:
Distribution:
IE Chief. FS6EB IE Chief. TS6Eis IE:llQ (5)
IE:11Q (4)
L:D/D for Fuels. 6 Materials DR Central Files Regulatory Standards (3)
DR Central Tiles IE Files Licensing (13)
IE Chief. M6 PPB IE Tiles L:D/D for Reactor Project
,
B.
IE Inquiry Report No. _
Trant:mittal Date
Distribution:
Distribution:
"
'IE Chief, TS6EB IE Chief fcFS&EB w.
IE:llQ (5)
IE:11Q DR Central Files DR Central Files Regulatory Standards (3)
IE Tilec Licensing (13)
.
IE Filer.
C.
Incident Notification From:
(Licensee 6 Docket No. (or License No.)
Trancmittal Date
Distribution:
Distribution:
IE Chief. FS6EB IE Chief. FSLEB IE: liq (4)
IE:llQ (4)
Licenning (4)
L:D/D for ruels & Materialr.
DR Central Files DR Central Files IE Files IE Files
.
O b
N(q.,9Yb 5 t
r s
w.,cu e
.