ML12123A090
| ML12123A090 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 04/29/2012 |
| From: | Peterson D Pacific Gas & Electric Co |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| 47872 | |
| Download: ML12123A090 (8) | |
Text
0412912012 /U.S. NuclearRegulatory Commission Operations Center Event Report Paze I Power Reactor Event# 47872 Site: DIABLO CANYON Notification Date I Time: 04/29/2012 17:35 (EDT)
Unit: 1 Region: 4 State: CA Event Date / Time: 04/29/2012 (PDT)
Reactor Type: [1] W-4-LP,[2] W-4-LP Last Modification: 04/29/2012 Containment Type: DRY AMB DRY AMB NRC Notified by: DENNIS PETERSEN Notifications: DAVID PROULX R4DO HQ Ops Officer: DONALD NORWOOD PART 21 GRP BY EMAIL Emergency Class: NON EMERGENCY 10 CFR Section:
21.21 (d)(3)(i) DEFECTS AND NONCOMPLIANCE Unit Scram Code RX Crit Init Power Initial RX Mode Curr Power Current RX Mode N No 0 Refueling 10 Refueling PART 21 REPORT - CONTROLLERS DID NOT MEET EMI / RFI GUIDELINES "This report constitutes a 10 CFR Part 21 notification. On March 23, 2012, Scientech (a business unit of Curtis Wright Flow Control), sent a 10 CFR Part 21 report (Letter Number 12-09-BB) to Pacific Gas & Electric Company.
Diablo Canyon Nuclear Plant (DCPP) entered this report into its corrective action program on April 23, 2012. This Part 21 report identified that eight AMS286 and AMS287 hand controllers supplied to DCPP had a deviation from the purchase specification. DCPP specified the controllers to be qualified to meet electromagnetic interference (EMI) / radio frequency interference (RFI) emissions and susceptibility in accordance with NRC Regulatory Guide 1.180, Rev. 1. Contrary to this requirement, Scientech did not perform the EMI / RFI testing on the AMS286 controllers shipped to DCPP with a Certificate of Conformance to DCPP's specification. Scientech tested the AMS287 controllers, which failed some of the required testing, but were shipped to DCPP with a Certificate of Conformance nonetheless. DCPP accepted the controllers based on the Certificates of Conformance, but did not install them. Following acceptance of the controllers, DCPP identified the nonconformance with its specification, and had another vendor modify the controllers to subsequently pass required testing.
"DCPP determined the deviation could have potentially created a substantial safety hazard if the controllers were installed at DCPP. The controllers were intended to control auxiliary feedwater from the Unit 1 control room and the hot shutdown panel as part of an upcoming process control system modification. Following a postulated fire in the control room, plant shutdown would be managed from the hot shutdown panel. In this instance, radios would be used to communicate with operators at the panel. The controllers would be susceptible to EMI/RFI interference and could potentially affect the operators' ability the safely shut down the plant and maintain it in a safe shutdown condition. DCPP notified Scientech of this conclusion on 4/27/12."
The licensee notified the NRC Resident Inspector.
04/29/2012 U.S. Nuclear Regulatory Commission OperationsCenterEvent Report Paze I Power Reactor Event# 47872
HOO Hoc From: Padovan, Mark [MLPY@pge.com]
Sent: Sunday, April 29, 2012 5:58 PM To: HOO Hoc Cc: Baldwin, Thomas (DCPP); Petersen, Dennis
Subject:
Diablo Canyon Part 21 Report - EN 47872 Attachments: NRC Form 361 - 50 72 Report Scientech Flow Controllers.pdf; Scientech Part 21 Report.pdf HOO (Donald),
Here is a .pdf copy of the Part 21 report (EN 47872) we telephoned in from Diablo Canyon Nuclear Power Plant. As we discussed, I'm also attaching the Part 21 report that Diablo Canyon received from Scientech. Please let me know if you have any questions.
L. MarkjPadovan Regulatory Services Supervisor Diablo Canyon Power Plant 104/5/22A (805) 545-4540 (w) mark.padovan@pge.com 1
PAGE 1 OF 2 NRC FORM 361 U.S. NUCLEAR REGULATORY COMMISSION (12-2000) REACTOR PLANT OPERATIONS CENTER EVENT NOTIFICATION WORKSHEET EN 47872 NRC OPERATION TELEPHONE NUMBER: PRIMARY-- 301-816-5100 or 800-532-3469*, BACKUPS -- [1st] 301-951-0550 or 800-449-3694*,
ilnul ,.3u I-q IE-UU U dlU IalUn .dU I-l I30UUUO LIEU0 IUUbe WhoU I IIdallLOIIIWII n e 1r.w CaIr pIrUVIUtU eII *s eel IU*
one IlUlIIUWs.
NOTIFICATION lIME FACILITY OR ORGANIZATION UNIT NAME OF CALLER CALL BACK #
1735 EDT Diablo Canyon Power Plant 1 Dennis Petersen (805) 545-4022 EVENT TIME & ZONE EVENT DATE POWER/MODE BEFORE POWERIMOOE AFTER 04/29/2012 N/A N/A EVENT CLASSIFICATIONS 1-Hr. Non-Emergency 10 CFR 50.72(b)(1) (v)(A) Safe SID Capability ,ANA GENERAL EMERGENCY GEN/AAEC j TS Deviation ADEV (v)(B) RHR Capability AINB SITE AREA EMERGENCY SIT/AAEC 4-Hr. Non-Emergency 10 CFR 50.72(b)(2) (v)(C) Control of Rad Release AJNC ALERT ALE/AAEC (i) TS Required S/D ASHU (v)(D) Accident Mitigation AIND UNUSUAL EVENT UNU/AAEC (iv)(A) ECCS Discharge to RCS ACCS (xii) Offsite Medical AMED 50.72 NON-EMERGENCY (see next columns) (iv)(B) RPS Actuation (scram) ARPS (xiii) Loss Comm/AsmtlResp ACOM PHYSICAL SECURITY (73.71) 1JJJ (xi) Offsite Notification APRE 60-Day Optional 10 CFR 50.73(a)(1) ,
MATERIAL/EXPOSURE B??? 8-Hr. Non-Emergency 10 CFR 50.72(b)(3) Invalid Specified System Actuation AINV FITNESS FOR DUTY HFIT (ii)(A) Degraded Condition ADEG Other Unspecified Requirement (Identify)
OTHER UNSPECIFIED REvMT (see last column) (ii)(B) Unanalyzed Condition AUNA NONR INFORMATION ONLY NrNF (iv)(A) Specified System Actuation AESF NONR DESCRIPTION Include: Systems affected, actuations and their initiating signals, causes, effect of event on plant, actions taken or planned, etc. (Continue on back)
This report constitutes a 10 CFR Part 21 notification. On March23, 2012, Scientech (a business unit of Curtis Wright Flow Control),
sent a 10 CFR Part 21 report (Letter Number 12-09-BB) to Pacific Gas & Electric Company. Diablo Canyon Nuclear Plant (DCPP) entered this report into its corrective action program on April 23, 2012. This Part 21 report identified that eight AMS286 and AMS287 hand controllers supplied to DCPP had a deviation frof-tt e purchase specification. DCPP specified the controllers to be qualified to meet electromagnetic interference (EMI) / radio frequency interference (RFI) emissions and susceptibility in accordance with NRC Regulatory Guide 1.180, Rev. 1. Contrary to this requirement, Scientech did not perform the EMI / RFI testing on the AMS286 controllers shipped to DCPP with a Certificate of Conformance to DCPP's specification. Scientech tested the AMS287 controllers, which failed some of the required testing, but were shipped to DCPP with a Certificate of Conformance nonetheless. DCPP accepted the controllers based on the Certificates of Conformance, but did'not install them. Following acceptance of the controllers, DCPP identified the nonconformance with its specification, and had another vendor modify the controllers to subsequently pass required testing.
DCPP determined the deviation could have potentially created a substantial safety hazard if the controllers were installed at DCPP.
The controllers were intended to control auxiliary feedwater from the Unit 1 control room and the hot shutdown panel as part of an upcoming process control system modification. Following a postulated fire in the control room, plant shutdown would be managed from the hot shutdown panel. In this instance, radios would be used to communicate with operators at the panel. The controllers would be susceptible to EMI/RFI interference and could potentially affect the operators' ability the safely shut down the plant and maintain it in a safe shutdown condition. DCPP notified Scientech of this conclusion on 4/27/12.
NOTIFICATIONS YES NO WILL BE ANYTHING UNUSUAL OR NRC RESIDENTS NOT UNDERSTOOD? D YES (Explain above) [] NO STATE(s) _ / DID ALL SYSTEMS LOCAL _ FUNCTION AS REQUIRED? [ YES [ NO (Explain above)
OTHER GOV AGENCIES -_ MODE OF OPERATION ESTIMATED ADDITIONAL INFO ON BACK MEDIA/PRESS RELEASE / UNTIL CORRECTED: RESTART DATE: F-1 YES [] NO NRC FORM 361 (12-2000)
ADDITIONAL INFORMATION PAGE*2 OF 2 ADDITIONAL IELESESORHECTIONFILPANE 2critio2 RADIOLOGICAL RELEASES: CHECK OR FILL IN APPLICABLE ITEMS (specific details/explanationsshould be covered in eveIt descriotion)
LIQUID RELE-ASE I GASEOUS RELEASE UNPLANNED RELEASE IIPLANNED RELEASE_ ONGOING I TERMINATED MONITORED I 1UNMONITORED OFFSITE RELEASE IT. S. EXCEEDED RM ALARMS I 1AREAS EVACUATED PERSONNEL EXPOSED OR CONTAMINATED OFFSITE PROTECTIVE ACTIONS RECOMMENDED *State release path in description Release Rate (Ci/sec) % T. S. LIMIT HOO GUIDE Total Activity (Ci) % T. S. LIMIT HOO GUIDE Noble Gas 0.1 Ci/sec 1000 Ci Iodine 10 uCi/sec 0.01 Ci Particulate 1 uCi/sec I mCi Liquid (excluding tritium and 10 uCi/min 0.1 Ci dissolved noble gases)
Liquid (tritium) 0.2 Ci/min 5 Ci Total Activity_
PLANT STACK CONDENSER/AIR EJECTOR MAIN STEAM LINE SG BLOWDOWN OTHER RAD MONITOR READINGS ALARM SETPOINTS
% T. S. LIMIT (if applicable)
RCS OR SG TU1E LEAKS: CHECK OR FILL IN APPLICABLE ITEMS: (specific details/explanationsshould be covered in event description)
LOCATION OF THE LEAK (e.g., SG #, valve, pipe, etc.)
LEAK RATE UNITS: gpUSgpd T. S. LIMITS SUDDEN OR LONG-TERM DEVELOPMENT LEAK START DATE TINE COOLANT ACTIVITY PRIMARY SECONDARY AND UNITS:
LIST OF SAFETY RELATED EQUIPMENT NOT OPERATIONAL EVENT DESCRIPTION (Continuedfrom front)
'I Instrumentation & Controls Division CURTISS
, W 'iGHT" 200 S. Woodruff Ave.
ýJ Flow Control Company Idaho Falls, ID83401 (208&) 529-1000 March 23, 2012 Letter Number: 12-09-BB PG&E - Diablo Canyon Power Plant CIO The PG&E Piocurement Assessment Supervisor @DCPP PO Box 56 Avila Beach, CA 93424 Mailstop 115/2
SUBJECT:
Evaluation of Deviation for 10 CFR Part 21 Reportability
Dear PG&E Procurement Assessment Supervisor:
Scientech opened 10 CFR Part 21 Evaluation 21-12-03 (attached) on January 23, 2012, and has concluded that our organization is unable to determine if the deviation constitutes a defect as defined in. OCFR Part 21. This letter in conjunction with a letter to the Quality Verification Department Manager, formally forwards our Part 21 investigation to Diablo Canyon Power Plant :for further evaluation.
Please feel free to contact the Scientech Engineering Manager Jim Saunders, at (208)524-9245, with any technical questions you may have regarding this issue, or Vince Chermak, the Quality Assurance Manager for any quality related questions. You may contact me directly, using the information provided below, for any other issues.
Sincerely, Brian Braithwaite Applications Engineer I&C Division Scientech, a business unit of Curtiss-Wright Flow Control Company Office (208) 524-9337 IFax (208) 524-9238
Attachment:
10CFR21 Evaluation 21l- 12-03 Rev. 0
CURrTYS ] NF 15.1-1 Revision I Page 1 of 2 10CFR21 Evaluation No. 21-12-03 Rev. 0
Background
The I&C division of Scientech, a business unit of Curtiss Wright Flow Control Services Corporation, provides safety related instrumentation to commercial nuclear power plants for use in safety related applications.
Problem Reported On: 0202/2012 Prble Dcmented In: CAR 12-010, Problem__Reported __On: __02/02_.20_2 NCR 12N-013, NCR 12N-014 Description of Itent: (name, manf, model, part no, serial no, fimction)
AMS826,PIN: NUS-A228PA-1 Rev. 0 S/N: 1101685-1101694, 1101715, 1101716 AMS827 P/*N: NUS-A276PA-1, Rev. 1101021-1101032 Description of Problem: The modules did not meet specifications (EML'RFI Testing) as listed in customer supplied
.sLpccifications docun'ut.t 10083-J-NPG, Rcy. 4.
IOCFR2I: Detiationmeans a depar-turefrom the technical requirements included In a procurement document, or specified in early site permit infotmation, a standarddesign certification or standarddesign approval.
Is the problem a deviation? (include justification ror answer) Yes 2 No El Justification: Modules did not m.eet Ppecifications.
IF,NO,PROCEED TO CONCLUSION SECTION IF YES, CONTINUE Has an item with the deviation been supplied to a plant as a sal.ty-related item? Yes No-L IF NO, PROCEED TO CONCLUSION SECTION IF YES, INCLUDE PLANT INFORMATION AND CONTINUE Plants.supplied with item: Diablo Canyon IOCFR27: Deec means:
(1) A deviation in a basic component delivered to a purchaserfor use in afacility or an activity subject to the regulations in this part if on the basis of an evaluation,the deviation could create a substantia. safety hazard, (2) The installation,use, or operation ofa basic component containing a defect as defined in this section; (3) .4 deviation in a portionofa~facility subject to the early site pernit,standarddesign certification. standard design approval, constuctionpeprnit, combined license or mantifacturing licensingrequirements ofpart 50 or psart 52. of this chapter, provided the deviation could, on the basis of an evaluation, create a substantialsafety hazardandthe portion of thefacilit* containing the deviation has been offered to the purchaserfor acceptance; (4) A condition or circumstanceinvolving a basic component that could contribute to the exceeding ofu .aft),
lhinit, as defined in the technical specificationsof a license for operation issued underpart50 orpart 52 of this chapter; or (5) An error. omission or other circumstance in a design ce[lification,or standarddesign approval ihat, on the basis af an evaluation, could create a substantia saaety hazard.
10CFR21: Substantial safety hazardmeans a loss of sqfetyfiunction to the extent that there is a major reduction in the degree ofiprotection provided to public health and sacfetybr anyfacility or activity licensed or otherwise approved or regulated by the NRC Can Scientech determine if the deviation is a defect? Yes []-No 9 1FWNO, PROCEED TO CONCLUSION SECTION IF YES, CONTINUE Is the de.viationa defect? (include justification for answer) Yes UJ No H
- FQW.arrlC 4'C ... 15,-1
-sNF
.... . ........ Revision I age,2 of 2 I' 10CFR21 Evaluation No. 21-12-03 Rev. 0 Justification:
CONCLUSION I - [] There is no deviation. No report is required.
2- LI There is a deviation, but it does not exist in any safety-vilatcd item delivered to a plant. No report is required.
3 - ' MTere is a deviation, butit does not constitute a defect. No report is required-4" [. There isa deviation, but Scientech cannot determine if it is a defect. Forward to plant for evaluation.
5- El There is a defect. Report to thc NRC per IOCFR2I.
Prepared: Si 'atur atc Evaluated: Sipature f)Date Print Name: Z ne-hra Print Name : .Jim Sauwiders Title; QA Manager
Title:
Engineering Manager Approved: Si gnature / Date Approval requircd fbi Category 4 and 5 only.
Print Name: Bob Queenan
Title:
Division Manager NOTE:. For Category 5, a defect is docinnined upon the signatre of the Division Manager or his deignee.