Letter Sequence Other |
|---|
TAC:3399, (Approved, Closed) TAC:42502, (Approved, Closed) TAC:61405, (Approved, Closed) TAC:61523, (Approved, Closed) TAC:64233, (Open) TAC:65291, (Open) TAC:6596, (Approved, Closed) TAC:6663, (Approved, Closed) TAC:7329, (Approved, Closed) TAC:7721, (Approved, Closed) |
Results
Other: 05000344/LER-1985-013-01, Forwards Rev 0 to 01-0300-1471, Preliminary Thermal Expansion Evaluation of Reactor Coolant Loop for Trojan Nuclear Plant, as Clarification of LER 85-013-01 in Response to 860430 Telcon, ML19267A316, ML19274E248, ML19274E250, ML20197E758, ML20198Q962, ML20198R016, ML20198R908, ML20198R985, ML20198S019, ML20198S051, ML20199B502, ML20199B510, ML20202C354, ML20204F441, ML20206F998, ML20210S227, ML20210V194, ML20211G407, ML20211G419, ML20212D368, ML20235K098, ML20235Z787
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MONTHYEARML20236A0651975-10-15015 October 1975 Informs of Potential Safety Question Re Design of Reactor Pressure Vessel Support Sys for Pwrs.Util Requested to Review Design Bases to Determine If Transient Loads Taken Into Account & Provide Results to NRC within 30 Days Project stage: Other ML20155J7791976-01-0505 January 1976 Requests Addl Info Re Reactor Vessel Support Design.Info to Be Provided by 760301.W/o Encl Project stage: Other ML20148F2811976-06-0707 June 1976 Forwards Request for Addl Info Re Adequacy of Pressure Vessel Supports When Calculating Subcooled Internal Loads Project stage: RAI ML20244A6211978-01-25025 January 1978 Forwards Background & Current Status of Review of Asymmetric LOCA Loads for PWR Facilities & Revised Request for Addl Info on Subj Project stage: RAI ML19326B2771978-03-0909 March 1978 Responds to NRC .Plans Re Asymmetric LOCA Loads Safety Question Underway Since Oct 1975.Requests .Nrc Meeting W/B&W Owners Group in mid-March & Clarification of Requirements in NRC Project stage: Meeting ML19319D3951978-04-10010 April 1978 B&W 177FA Owners Group Asymmetric LOCA Loads Evaluations Programs Project stage: Other ML19319D3911978-05-0404 May 1978 Responds to NRC 780125 Request for Schedule for Evaluation of Asymmetric LOCA Loads.Forwards Rept, B&W 177FA Owners Group Asymmetric LOCA Loads Evaluation Program. Util Plans to Use Generic Analyses Where Applicable Project stage: Request ML19273A9921978-10-10010 October 1978 B&W 177 Fuel Assembly Owners Group Asymmetric LOCA Loads Evaluation Program,Phase 2. Evaluated Components Include Reactor Pressure Vessel,Fuel Assemblies,Control Rod Drives & Core Flooding Piping Project stage: Other ML19267A3161978-12-29029 December 1978 Informs That Due to Control Bldg Proceeding,The Mod to Operating Status Alarms of Diesel Generators Will Not Be Completed Until 790131 Project stage: Other ML19273A9831979-01-26026 January 1979 Submits Plan for Proceeding with Phase 2 Re Asymmetric LOCA Loads Program.Forwards Rept B&W 177 Fuel Assembly Owners Group Asymmetric LOCA Loads Evaluation Program,Phase 2 Identified Content & Schedule Project stage: Other ML19261B7371979-01-26026 January 1979 Forwards Request for Addl Info in Order to Complete Review Re Revised Westinghouse Thermal Design Procedure & WRB-1 Critical Heat Flux Correlation.Requests Response as Soon as Possible Project stage: RAI ML19259B6041979-02-0707 February 1979 Forwards Request for Addl Info Re Revised Westinghouse Thermal Design Procedure & Critical Heat Flux Correlation for Facility Project stage: RAI ML19274E2481979-03-15015 March 1979 Forwards License Change Application 50 to Amend License NPF-1 Re Radiological Tech Specs.Certificate of Svc & Class III Fee Encl Project stage: Other ML19274E2501979-03-15015 March 1979 License Change Application 50 to Amend License NPF-1 Re Radiological Tech Specs Project stage: Other ML19207A3941979-08-13013 August 1979 Informs of Multiphase Program to Evaluate Effects of Asymmetric LOCA Loads.Program to Be Completed Jul 1980 Project stage: Other ML19254F2471979-10-31031 October 1979 Supplements 790315 License Change Application 50 Incorporating 10CFR50,App I,Radiological Effluent Tech Specs.Includes Spec Implementing 40CFR50.Util to Implement 10CFR190 Until Application 50 Approved & Issued as Amend Project stage: Supplement ML19296B2821980-02-15015 February 1980 Notifies Interim Rept BAW-1597, Effects of Asymmetric LOCA Loadings Responds to NRC 780125 Request.Rept Provides Justification for Continued Operation of Facility.Final Rept Will Be Forwarded by 800701 Project stage: Other ML14107A2851980-05-23023 May 1980 Memorandum & Order on Ucs 771104 Petition for Remedial Relief Re Fire Protection of Electrical Cables & Environ Qualification of Electrical Components.Reaffirms Commission 780413 Decision Re Possible Shutdown of Operating Reactors Project stage: Other ML19320A8941980-07-0303 July 1980 Responds to NRC Requesting All PWR Licensees to Evaluate LOCA loads.BAW-1597 & BAW-1621 Submitted 800214 & 0701,respectively,demonstrate Ability of Facility to Maintain Core Coolability in Event of Asymmetric LOCA Project stage: Other ML19320A8651980-07-0303 July 1980 Notifies That Evaluation of BAW-1621,re Overall Asymmetric LOCA Loads,Will Be Submitted by 800805 Project stage: Other ML19330C2781980-08-0505 August 1980 Advises of Review of BAW-1621, Effects of Asymmetric LOCA Loading - Phase II Analysis. Reactor Head Cable Access Platform Will Be Modified During Refueling Outage to Provide Horizontal Clearance at Svc Support Structure Project stage: Other ML19344E7801980-09-0505 September 1980 Forwards, Environ Qualification of Electrical Equipment, Master List, Revision K Per 800114 IE Bulletin 79-01B Requirements & 800829 Order for License Mod.Encl Available in Central Files Only Project stage: Other ML19347B8321980-09-29029 September 1980 Forwards Suppl 2 to IE Bulletin 79-01B, Environ Qualification of Class IE Equipment. No Written Response Required Project stage: Other 05000344/LER-1980-022, Forwards LER 80-022/01T-01980-10-31031 October 1980 Forwards LER 80-022/01T-0 Project stage: Other 05000344/LER-1980-022-01, /01T-0:on 801028,review of IE Bulletin 79-01B Resulted in Discovery of safety-related Equipment Not Meeting Environ Qualification.Caused by Change in Criteria for Environ Qualification of safety-related Equipment1980-10-31031 October 1980 /01T-0:on 801028,review of IE Bulletin 79-01B Resulted in Discovery of safety-related Equipment Not Meeting Environ Qualification.Caused by Change in Criteria for Environ Qualification of safety-related Equipment Project stage: Meeting ML20126L2181980-11-0707 November 1980 Environ Qualification of Safety-Related Electrical Equipment to Harsh Environs,Ie Bulletin 79-01B, Technical Evaluation Rept Project stage: Other ML19345B8121980-11-25025 November 1980 Responds to NRC 801001 Request for Info Re Environ Equipment Qualification Tests.Pressure Transmitter Tests Conducted by Util Transmitter Qualification Group, & Safety Valve Flow Monitoring Tested by Technology for Energy Corp Project stage: Request ML15223A7081981-01-0909 January 1981 Forwards Request for Addl Info Re B&W 177-FA Owners Group Submittal on Asymmetric LOCA Loadings.Owners Group Should Convene Another Meeting W/Nrc After Review & Before Submittal.Info Due in 60 Days Project stage: RAI ML19341D0021981-01-31031 January 1981 Degraded Grid Protection for Class IE Power Sys,Trojan Nuclear Plant, Technical Evaluation Rept Project stage: Request ML19347D1351981-02-26026 February 1981 Forwards 810109 Request for Addl Info Re B&W 177-FA Owners Groups Submittal on Asymmetric LOCA Loading.Response Should Be Submitted within 60 Days Project stage: RAI ML19347D3511981-03-11011 March 1981 Notifies That Util Will Provide Formal Response to NRC 810109 Request for Addl Info Re B&W 177-FA Owners Group Generic Submittal on Asymmetric LOCA Loadings by Jul 1981 Project stage: Request ML20003E1581981-03-26026 March 1981 Responds to 810109 Request for Addl Info Re B&W 177-FA Owners Group.Requests Technical Review Meeting on 810402-03 in Bethesda,Md to Resolve Remaining Questions Project stage: Meeting ML20003E2951981-03-26026 March 1981 Forwards Preliminary Results of NRC Review Re Environ Qualification of safety-related Electrical Equipment.Result of Review Identified Number of Potential Deficiencies. Response Required within 10 Days of Receipt of Ltr Project stage: Other ML16138A4971981-04-0909 April 1981 Summary of 810402-03 Meeting W/B&W Owners Group & Vendors in Bethesda,Md Re Proposed Responses to NRC 810109 Info Request Re Asymmetric LOCA Loadings Project stage: Meeting ML20126L2081981-05-27027 May 1981 Forwards Safety Evaluation Re Environ Qualification of safety-related Electrical Equipment.Evaluation Based on Util 800307,0425,0519,0905 & 810113 Submittals Project stage: Approval ML20126L2121981-05-27027 May 1981 Safety Evaluation Re Environ Qualification of safety-related Electrical Equipment.Equipment,Required to Mitigate LOCA Following Accident in Harsh Environ,Found Acceptable Except as Noted in Section 3 Project stage: Approval ML20009D4681981-07-13013 July 1981 Notice of Issuance of Directors Decision Under 10CFR2.206, Denying Coalition for Safe Power 790517 Request for Plant Shutdown Project stage: Approval ML20009D4651981-07-13013 July 1981 Directors Decision Under 10CFR2.206,denying Coalition for Safe Power 790517 Request for Plant Shutdown Project stage: Other ML20009D4631981-07-13013 July 1981 Forwards Directors Decision Under 10CFR2.206,denying 790517 Request for Plant Shutdown & Public Hearing Re Fire Protection & Environ Qualification of Electrical Equipment Issues Project stage: Other ML20030D1851981-08-26026 August 1981 Forwards Detailed Response to NRC 810527 Safety Evaluation Re Environ Qualification of safety-related Electrical Equipment.Addresses Outstanding Info in Section 3.0 & Provides Resolutions to Deficiencies in Section 4.0 Project stage: Other ML20140B6461981-09-0909 September 1981 Reiterates 810722 Request for Documents Re Show Cause Petition on Environ Qualification of safety-related Equipment at Facility Project stage: Request ML20031B3051981-09-24024 September 1981 Advises That Responses Submitted in Util Satisfy Questions Raised from Review of BAW-1621 Rept, Effects of Asymmetric LOCA Loadings-Phase II Analysis Project stage: Other ML20040G1221982-02-0303 February 1982 Forwards Info Requested by NRC for Equipment Environ Qualification Review.W/O Encl Project stage: Other ML20041A2251982-02-12012 February 1982 Advises That Addl Info Re Environ Qualification of safety-related Electrical Equipment Has Been Forwarded to Franklin Research Ctr,In Response to NRC 820112 Request Project stage: Other ML20041C0401982-02-17017 February 1982 Advises of Preliminary Review of Util Submittals Re Environ Qualification of TMI Action Plan Electrical Equipment. Response Should Be Sent to Franklin Research Ctr within 30 Days of Ltr Date Project stage: Approval ML20050A4721982-03-29029 March 1982 Forwards Editorial Changes to 810826 Response to NRC Request for Info Re Radiation Qualification Envelopes Project stage: Request ML20028F0681983-01-21021 January 1983 Forwards Response to NRC 821217 SER Re Environ Qualification of safety-related Equipment.Continued Safe Operation Reaffirmed & Discrepancies Noted in Section 5 of Technical Evaluation Rept Resolved Project stage: Other 2CAN018406, Comments on 830921 Draft Safeguards Agreement Under Npt Between USA & IAEA Subsidiary Arrangements, Intended to Be Implemented Through Facility License Amend.Markup Copy of Agreement Encl1984-01-23023 January 1984 Comments on 830921 Draft Safeguards Agreement Under Npt Between USA & IAEA Subsidiary Arrangements, Intended to Be Implemented Through Facility License Amend.Markup Copy of Agreement Encl Project stage: Draft Other ML20151J0531984-06-0606 June 1984 Forwards Request for Addl Info Re Asymmetric LOCA Loads. Addl Info Needed in Order to Complete Safety Evaluation of plant-specific LOCA Analysis.Response Requested by 840731 Project stage: Approval ML20138H8951985-06-30030 June 1985 Rev 0 to Leak-Before-Break Evaluation of Reactor Coolant Loop, Final Rept Project stage: Other 1980-08-05
[Table View] |
Discusses Insp on 860318-0428 & Two Special Insps on 860513- 0612 & 860804-14 & Forwards Notice of Violation & Proposed Imposition of Civil Penalty| ML20235Z787 |
| Person / Time |
|---|
| Site: |
Trojan File:Portland General Electric icon.png |
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| Issue date: |
10/15/1986 |
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| From: |
Martin J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
|---|
| To: |
Withers B PORTLAND GENERAL ELECTRIC CO. |
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| Shared Package |
|---|
| ML20235Z789 |
List: |
|---|
| References |
|---|
| EA-86-113, TAC-3399, TAC-42502, TAC-61405, TAC-61523, TAC-64233, TAC-65291, TAC-6596, TAC-6663, TAC-7329, TAC-7721, NUDOCS 8710210318 |
| Download: ML20235Z787 (3) |
|
Text
_ _ _ _ _ _ _ _ _ _ _ _ _ _
f.
[pra m UNITED STATES j'
NUCLEAR REGULATORY COMMISSION o
i REGION V
~
I o
1450 MARIA LANE, sulTE 210 WALNUT CREEK.CAllFORNIA OCT 151986
. ;pc__.
{[fd Docket No. 50-344 License No. NPF-1 EA 86-113 Portland General Electric Company 121 S.W. Salmon Street Portland, Oregon 97204 s
Attention:
Mr. Bart D. Withers Vice President - Nuclear Gentlemen:
Subject:
NOTICE OF VIOLATION AND PROPOSED IMPOSITION OF CIVIL PENALTY (NRC INSPECTION REPORT NOS. 50-344/86-10, 50-344/86-24, AND 50-344/86-32) 1 This refers to the routine inspection conducted during the period March 18 -
l April 28, 1986 and to two special inspections conducted May'13 - June 12, 1986 and August 4 - 14, 1986 of activities authorized by NRC License NPF-1 for the Trojan Nuclear Power Plant.
Two violations of NRC requirements were identified by NRC inspectors during the inspections and the results of these inspections were sent to you by letters dated May 16, July 1, and August 20, 1986, respectively.
The violations involved the inoperability of the Residual Heat Removal (RHR) system and an unacceptable quality control inspection conducted during the installation of a pressurizer safety valve.
Enforcement conferences were held with you and members of your staff on July 9, 1986 at i
your offices in Portland, Oregon and on September 5, 1986 at our offices in Walnut Creek, California, to discuss the violations, the root causes of these violations, your corrective actions, and the NRC enforcement policy.
Violation I in the enclosed Notice of Violation and Proposed Imposition of Civil Penalty (Notice) involves the inoperability of one of the emergency core cooling system (ECCS) subsystems.
On March 31, 1986, the flow path for RHR system cold leg injection to two of the four reactor coolant system loops was isolated for one hour and ten minutes in violation of technical specification requirements.
This violation appears to be the result of an incomplete under-standing of the safety system design bases by your plant staff, a topic previously discussed with you in a March 27, 1986 enforcement conference involving the control room emergency ventilation system.
Although we recognize that your actions to correct the underlying causes of the violations involving control room emergency ventilation system were in progress at the time that the circumstances described in Violation I occurred, this is another example of a violation that we consider significant.
This violation emphasizes the importance for you to expedite the programs already initiated to establish design basis documents with accurate system descriptions and to CERTIFIED MAIL RETURN RECEIPT REQUESTED B710210318 861015 PDR ADOCK 05000344 G
PDR
l 4
Portland General Electric Company 2
0 CI 151980 l
1 assure that your plant staff understands system design bases to prevent the recurrence of similar types of violations.
}
Violation II in the enclosed Notice involves an instance of an incomplete inspection by a contract quality control (QC) inspector.
On May 13, 1986,
)
an NRC inspector observed that a QC inspector failed to properly witness the j
torquing of the bolts on the inlet flange for a pressurizer safety valve as prescribed by the established procedures.
Although the QC inspector was in j
the work area, the '}C inspector was not actually witnessing the bolt torquing l
process.
However, apparently because of carelessness and a lack of attention to detail, the QC inspector signed the inspection record to indicate that the witnessing of the bolt torquing had taken place.
Upon learning of this problem, plant personnel took prompt and extensive corrective actions consisting of the immediate suspension of the QC inspector and subsequent investigation, reinspection and evaluations of the individual's work.
As discussed in the July 9, 1986 enforcement conference, Portland General Electric Company management should continue to be alert to conditions that contributed to this violation, including supervision of employees, adherence to established procedures, and training of personnel.
]
To emphasize the importance of ensuring that plant personnel understand the design basis operation of systems and that quality control personnel conscien-tiously perform their duties, I have been authorized, after consultation with the Director, Office of Inspection and Enforcement to issue the enclosed Notice of Violation and Proposed Imposition of Civil Penalty in the amount of Fifty Thousand Dollars ($50,000) for the violations described in the enclosed Notice.
In accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C (1986) (Enforcement Policy),
each of the violations described in the Notice have been classified as a Severity Level III.
The base value of a civil penalty for a Severity Level III violation is $50,000.
The escalation and mitigation factors of the Enforcement Policy were considered and no adjustment to the base civil penalty has been deemed appropriate for Violation I.
While the civil penalty could have been mitigated based on your prompt and extensive corrective actions for the indepth system review performed, there were also grounds for escalation of the civil penalty based on this violation being another example of the failure to maintain systems in an operable status because of a lack of understanding the system's design bases.
The base civil penalty was fully mitigated for Violation II because of your prompt and extensive corrective actions and your prior past performance given no similar types of violations have been previously identified.
You are required to respond to this letter and should follow the instructions specified in the enclosed Notice when preparing your response.
In your response, you should document the specific actions taken and any additional actions you plan to prevent recurrence.
After reviewing your response to this
' Notice, including your proposed corrective actions, the NRC will determine whether further NRC enforcement action is necessary to ensure compliance with NRC regulatory requirements.
\\
-.l' Portland General Electr.ic' Company 3
OCT i h1.980
)
t i
'In'accordance with Section 2.790 of the NRC's '! Rules' of Practice," Part 2
-Title 10, Code of. Federal Regulations, a copy of this letter and the. enclosure i
will'be placed in the'NRC's Public Document Room.
'The responses-directed by this. Notice,'are not subject;to the clearance
. procedures of the Office of Management and Budget as. required by'the Paperwork.
Reduction Act of 1980,.PL'96-511.
nce ely,
'l I{21 John B. Martin j
-Regional Admi_nistrator Enclosure-
. Notice ~of Violation cc w/ enclosure:
l W.-S. Orser, PGE I
J. W.' Durham,'Esq.
-l i
W. Dixon, DOE _
1 l
l
..