ML20064E476
| ML20064E476 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 10/11/1982 |
| From: | Shamla W NORTHERN STATES POWER CO. |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| Shared Package | |
| ML20064E467 | List: |
| References | |
| FOIA-82-514 NUDOCS 8301060019 | |
| Download: ML20064E476 (1) | |
Text
{{#Wiki_filter:. - f ' : ." Northem States Power Compeiry 414 NWtc l.tah Mmeapoks.Mmew'.a 554Di Teirphtme 612) 330 5500 Mcnticello Inclar Generating Plant P.O. Bac 6 00 Monticello, MN 55362 Ck:toler 11, 1982 Mr. J. G. Heppler, Director - Iugicn III . Office of Intpoeticn and Difcrectnent ?, U.S. Ibc1cnr Ibgulatory Ocranissicn ' 799 Roomvelt Ibad i Glen Ellyn, II, 60137 Dtnr it. rcppler, FO.VTICEIJD 10CIIAR GEIEIRTI!C PIAFTT Ibcket Ib. 50-263 Liecnm ib. DPR-22 01 Octeh r 9,1982 linear irx3icaticns were ecnfirrxx1 to exist cn three addi-ticnal welds in the recirculaticn system. Them welds are located cn the 12" rioers cn tle "B" recirculaticn ofstcra.
'ntis occurrence is Ining reported in accordance with 'Decinical Specificaticn 6 . 7 .B .1.c. Them indicaticns will be documental as a revisio) tz:) Mcnticello Ibpartable Ctcurrence 82-16 which was repcrta3 September 28, 1982. A resolu-ticn is being investigatal.
Ycarrn truly, W. A. Slumla Plant Manager VAS/biz c: Director; Office of Managment Ihfcrnaticn and Prograra Ccntrol Filo i copy runt by teleccpf to V4Tpler
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(PLEASE PRINT OH TYPE ALL REQUIRED INFORMATIONI O i l M ] LICENSEE NI MIN l P isel l@l 010 l - l 0 uCENst l 010lNuueER 0l 0 l - l 0 l 0 26l@l264 l 1uCENsE l 1111 11@l63 CAT-l l@ ) 3 8 9 CODE it TvPE Jo be > CON 7 . IE P S 0',t"E LL_)@l 01510l 010121613]@l0 19 l 2 l818 l 2'l@ll 60 68 DocutTNUMBER 68 69 EVENT DATE 74 )$ l 0111218 l 2 l@ REPORT DATE 80 EVENT DESCRIPTION ANO PROBABLE CONSEQUENCES h IOi2 I During normal ISI with reactor shutdown for refueling. three indications were l 0 3 1 found in the 22 inch diameter reactor recirculation system riser manifold end l I OTTI I can. Indication.s detected by Ur on 9/10/82. Syste[n was drained and indications __] O s I confimed as rejectable by RT on 9/28/82. This is an abnomal degradation of . 1 O s I the reactor ccolant pressure boundary (T.S. 6.7.B.1.c) . Maximum 14 percent thru O I wall indication had no effect on niant onerations or public health and safety. I LO 1s i l Previous similar event was A0-75-03. I y g g 80 1 C OE CO E SUSC E COMPONENT CODE SUSC DE $ E [OIT] 7 s l Cl Bl@ [E_J@ y@ IP 9 50 11 12 IJ lI l P l E lX lX l@ g@ @ @ 18 59 20 _ SE OutNTI AL OCCU A 8t E NCE REPORT REVISION LE RrRO EVENT YE AR REPORT NO. CODE TvPE NO. O,agig 18121 1-1 23 1011161 24 LdJ 1011I LT_J I-I 101 _ 29 22 26 27 28 29 30 33 32 TA EN A TO ON PL ANT ME HOURS S S IT FOR b S. $UPPLI MAN 8ACTURER L.NJ@ [f_j@ LF_J@L.C_j@ lasCj@ l_Zj@ l01010i0i [N_j@ lGl018IOl(E n 2 2. >> A0 A n n A. ., CAUSE DESCRIPTION AND CORRECTIVE ACTIONS iieoi1 Three indications in 304 stainless steel recirc line were discovered. A weld g ii ii i l overlay repair will be made to allow continued operation. Currently nian to I f7TT1 I renlace end cap during next anprooriate cutage. Probable cause is IGSCC. : i 3 l Maximum end to end length of defects is 1.375 inches. I ITTTII I
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Northem States PowsiC3rbisa'ny 414 Nicollet Ma5 Minneapoks Minnesota 55401 Telephone (612) 330-5500 October 12, 1982 Regional Administrator Region III U S Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137 MONTICELLO NUCLEAR GENERATING PLANT Docket No. 50-263 License No. DPR-42 Crack in "A" Recirculation System Riser Manifold End Cap The License Event Report for this occurrence is attached. This event is reported in compliance with Technical Specification 6.7.B.l.c since it represents abnormal degradation of reactor coolant pressure boundary components. NW David Musolf Manager of Nuclear Sup rt Services DMM/bd cc: NRC Document Control Desk (1) NRC Resident Inspector MPCA Attn: J W Fernan f .
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81 elbcu. No affect on public health and safety. Almomal degradation of reactor j FrTn coolant pressure boundary (T.S. 6.7.B.1.c). Previous similar event AD-75-03. l l
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84 NTO l On 9/28/82 during 151 an 11 ner cent thru wall in31 cation was found on A l E recirculation loon 22 inch end can. On 10/9/82 indications were fount on C, E, t E land F safe end to cine welds and the D riser elbow. On 10/20/82,10/31/82, arul l l 8 111/2/82 during preparation for repair of the E, c, and F safe ends, resnectively, 1 FrTn I thru v311 leaks were found on each safe end. No affect on public health and j A Isafety. Abnomal degradation of reactor coolant pressure boundary (T.S. 6.7.B.1.c); E I Previous similar event AD-75-03. )
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cAust otscawnow Ano Conntenvc Acnous @ E thobable cause IGSOC. Weld overlay repairs will be made to all welds with crack l [3))]ilikeindications. All material is 304 S.S. All leaks were from axial in31 cations. (ITi] I All leaks were sealed by weld!nr after drainint line. heating weld to dry out i [m] l crack and erindine anoroximately 1/4 inch into base netal. Seal weld around i E I fitnh and nenetrant tested nrior to 1,i-ifumine weld overlav. i
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- I SSINS NO.: 6820 IEB 82-03 UNITED STATES NUCLEAR REGULATORY COMMISSION i 0FFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C. 20555
- October 14, 1982 IE BULLETIN NO. 82-03: STRESS CORROSION CRACKING IN THICK-WALL, LARGE-DIAMETER, STAINLESS STEEL, RECIRCULATION SYSTEM PIPING AT BWR PLANTS Addressees:
Those licensees of operating boiling water reactors (8WRs) identified in Table 1 for action. All other licensees and holders of construction permits (cps) for information only.
Purpose:
This bulletin is to notify all licensees and CP holders about a matter that may have a high degree of safety significance, and to require specific actions as set forth below for those licensees listed in Table 1. Specifically, this matter involves the degradation in the recirculation system piping in the reactor coolant pressure boundary (RCPB) that was found at the Nine Mile Point Unit 1 Nuclear Generating Station. This information was described in consider-able detaiT in Information Notice 82-39, dated September 21, 1982. Action by the affected licensees identified in Table 1 is required to (1) provide a reasonable level of assurance that inspections which are currently being performed or scheduled are sufficient to detect cracking in BWR thick-wall recirculation piping welds and (2) to assist the NRC in determining the generic significance of the piping degradation found at Nine Mile Point. The affected licensees are those owners whose plants-are currently in or scheduled to be in a refueling mode or extended outage through January 31, 1983. This bulletin is provided to all other licensees and holders of construction permits for information only at this time. Licensees not listed in Table 1 will be notified by January 15, 1983 as to the scope and extent of any required actions. Description of Circumstances: During a primary system hydrotest in March 1982 at Nine Mile Point Unit 1 (NMP-1), leakage was visually detected at two of the ten furnace-sensitized, recirculation system safe-ends. Further visual inspection revealed three pinhole indications and a single \-inch-long axial indication, all of which were located in the heat-affec,ted zone of the welds where the safe-end joined the pipe. About nine months before the leak, these safe ends were ultrasonic-ally (UT) inspected; at that time, the inspection did not disclose any report-able indications. Subsequent to the leak, the UT procedure was modified; UT
,C 0#nb GlNb
. t IEB 82-03 October 14, 1982 Page 2 of 5 Table 1 4
Plants Currently in or Scheduled to be in
~
a Refueling Mode or Extended Outage Through January 31, 1983 , LICENSEE PLANT (S) Northern States Power Company Monticello Nuclear Generating Station Tennessee Valley Authority - Browns Ferry Unit 2 Nuclear Generating Station Commonwealth Edison Company Quad Cities Unit 1 Nuclear Generating Station Dresden Unit 2 Nuclear Generating Station Northeast Utilities Millstone Unit 1 Nuclear Generating Station Georgia Power Company Hatch Unit 1' Nuclear Generating Station Carolina Power & Light Company Brunswick Unit 1 Nuclear Generating Station
- Jersey Central Power & Light Company Oyster Creek Nuclear Generating Station Iowa Electric Light & Power Company Duane Arnold Nuclear Generating Station
*To be performed during the November 1982 refueling outage, not the current outage.
l l t
. r' IEB 82-03 October 14, 1982
- Page 3 of 5 examination of the two affected safe-ends and one other safe-end confirmed the presence of indications of intermittent cracking around the pipe's inside diameter (ID). Additional examinations revealed cracking in heat affected zones of recirculation pump discharge welds. Dye penetrant examination con-firmed these crack indications. The UT examinations were extended'to other welds in the five loops of the recirculation system. The results of these examinations disclosed ID cracking in a large number of the welds examined.
Two boat samples removed from the area of the through-wall cracks in one safe-end were sent for evaluation -- one to General Electric Co. and the other to Battelle Laboratories. In addition, a boat sample from the crack region of the elbow weld was evaluated by Sylvester Associates, consultants to the licensee. The results of these metallurgical evaluations concluded that the degradation resulted from intergranular stress corrosion cracking (IGSCC) in the sensitized region of the weld's heat affected zones. Based on the fact that NMP-1 has furnace-sensitized safe-ends, the licensee decided to replace all 10 recirculation system safe-ends without further investigation beyond that described above. Based on recirculation system findings, the licensee decided to also replace all recirculation system piping while the facility was shut down for safe-end replacement. On September 16, 1982, a meeting was held between General Electric, BWR licensees, and NRC staff to review past IGSCC experiences and the general implications of NMP-1 IGSCC degradation in main recirculation piping welds. The staff had the benefit of the metallurgical evaluation of the NMP-1 event and an update of the general IGSCC experiences relative to all operating BWR plants. On September 27, 1982, a meeting was held between BWR licensees and the NRC staff to discuss the extent and results of examining welds in the recirculation system for all BWR licensees with plants currently in or scheduled to be in a refueling mode or extended outage through January 31, 1983. As a result of this meeting, the NRC staff has determined that additional information is needed to assess the effectiveness of the UT methods employed or planned to be used and to determine whether such piping should be designated " service-sensitive" in accordance with NUREG-0313, Rev. 1, issued by NRC letter dated February 26, 1981. To provide a reasonable level of assurance that inspections which are currently being performed or scheduled are sufficient to detect cracking in thick-wall, recirculation system piping welds and to assist the NRC in further evaluating this issue, the affected licensees (identified in Table 1) are requested to take the following actions. Actions to be Taken by Licensees of BWR Facilities Identified in Table 1:
- 1. Before resuming power operations following the current refueling or extended outage, the licensee is to demonstrate the effectiveness of L
4 - r IEB 82-03 October 14, 1982 Page 4 of 5 the detection capability of the ultrasonic methodology used or planned to be used to examine welds in recirculatior, system piping. This demonstra- . tion shall be made on representative service-induced cracked pipe samples. ' Arrangements should be made to allow NRC to witness this demonstration. This demonstration shall employ those procedures and standards, the same . type of equipment (same transducer size, frequencies and calibration- ' standards), and representative UT personnel from the inservice inspection (ISI) organization utilized or to be utilized in the examinations at the plant site.*
- 2. Before resuming power operations following the current refueling or extended outage, the licensee is to provide a listing of results of recirculation system piping inspections.
- 3. Before resuming power operations following the current refueling or extended outage, the licensee (if the inspections indicate the presence of cracks) is to describe the corrective actions taken and report these in accordance with the appropriate regulations.
- 4. To assist NRC's further evaluation of this issue, the following shall be submitted by December 1, 1982:
- a. A description of the sampling plan used or to be used during this outage for UT examinations of recirculation system piping welds and the bases for the plan. The description should:
(1) Provide an isometric drawing of the recirculation system piping showing all the welds, and the number of welds and their loca-tion that have been examined or will be examined. (2) Identify criteria for weld sample selection (e.g., stress rule index, carbon content, high stress location, and,their values for each weld examined). (3) Describe piping material (s), including material type, diameter, and wall thickness. (4) Estimate the occupational radiation exposure incurred or expected and briefly summarize measures taken to maintain individual and . collective exposures as low as reasonably achievable.
*We understand that Electric Power Research Institute (EPRI) has arranged to have samples from the Nine Mile Point Unit 1 plant available for industry demonstrations of UT methodology. The samples have been taken to Battelle Memorial Institute in Columbus, Ohio for characterization and subsequent use.
, t IEB 82-03 October 14, 1982 Page 5 of 5
- b. A summary description of the UT procedures and calibration standards used or to be employed in the examination at the licensee's plant
,' site. This description should include the scanning sensitivity, the evaluation sensitivity and the recording criteria.
- c. A summary of the results of any previous inspection of the recircula-tion system piping welds which used the validated examination meth-odology as discussed in Action Item 1 above.'
- d. An evaluation of the crack-detection capability of ultrasonic meth-odology used or planned to be used to examine recirculation system piping welds. This evaluation should result from conducting the demonstration required in Action Item 1 above, and should include a comparison of the service-induced pipe crack sample to those welds actually examined in the licensee's plant in terms of pipe wall thickness and diameter, weld geometry, and materials.
- 5. The written reports required by Items 2, 3, and 4 shall be submitted to the appropriate Regional Administrator under oath or affirmation under provisions of Section 182a, Atomic Energy Act of 1954, as amended. The original copy of the cover letters and a copy of the reports shall be transmitted to the U.S. Nuclear Regulatory Commission, Document Control Desk, Washington, D.C. 20555 for reproduction and distribution.
This request for information does not require Office of Management and Budget approval since the number of plants asked to provide the information is limited to nine reactor plants. Although no specific request or requirement is intended, the following informa-tion would help the NRC evaluate the cost of implementing this bulletin: o Staff time to perform requested demonstration o Staff time to prepare written responses If you have any questions regarding this matter, please contact the Regional Administrator of the NRC Regional Office or one of the technical contacts listed below. l ,4%
/
Richard C. DeY, u g, Di tor Office of Inspection an Enforcement t i Technical
Contact:
William J. Collins, IE 492-7275 Warren Hazelton, NRR 492-8075 l i
l s . p . ! Attachment IEB 82-03 October 14, 1982 , LIST OF RECENTLY ISSUED IE BULLETINS Bulletin Date of No. Subject Issue Issued to , 82-01 Alteration of Radiographs of 08/18/82 All power reactor Rev 1, Welds in Piping Subassemblies facilities with . Supp 1 an OL or CP - 82-02 Degradation of Threaded 06/02/82 All PWR facilities Fasteners in the Reactor Coolant with an OL for Pressure Boundary of PWR plants action and all other OLs or cps for information 82-01 Alteration of Radiographs of 05/07/82 All power reactor Rev. 1 Welds in Piping Subassemblies facilities with an OL or CP 82-01 Alteration of Radiographs of 03/31/82 The Table 1 Welds in Piping Subassemblies facilities for action and to all others for information 81-02 Failure of Gate Type Valves 08/18/81 All power reactor Supplement to Close against Differential facilities with an 1 Pressure OL or CP 81-03 Flow Blockage of Cooling Water 04/10/81 All power ~ reactor To Safety System Components by facilities with an CORBICULA SP. (ASIATIC CLAM) OL or CP and MYTILUS SP. (MUSSEL) 81-02 Failure of Gate Type Valves 04/09/81 All power reactor to Close Against Differential facilities with an Pressure OL or CP 81-01 Surveillance of Mechanical 03/04/81 Specific power reactor Rev. 1 Snubbers facilities with a CP 80-17 Failure of Control Rods 02/13/81 To all specified BWRs Supp. 5 to Insert During a Scram with an OL & All at a BWR BWRs with a CP OL = Operating License CP = Construction Permit
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