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| {{Adams | | {{Adams |
| | number = ML20137W163 | | | number = ML20202F684 |
| | issue date = 02/04/1986 | | | issue date = 04/10/1986 |
| | title = Insp Rept 50-293/86-04 on 860102 by State of Sc of Shipment of Radwaste from Facility.Violation Noted:Failure to Meet Packaging Requirements for Low Activity Radioactive Matls. State of Sc Radioactive Shipment Insp Rept Encl | | | title = Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-293/86-04.Subj Actions Examined During 860324-27 Insp & Acceptable.Addl Info Will Be Contained in Insp Rept 50-293/86-10 |
| | author name = Miller M, Pasciak W | | | author name = Martin T |
| | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) | | | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| | addressee name = | | | addressee name = Harrington W |
| | addressee affiliation = | | | addressee affiliation = BOSTON EDISON CO. |
| | docket = 05000293 | | | docket = 05000293 |
| | license number = | | | license number = |
| | contact person = | | | contact person = |
| | document report number = 50-293-86-04, 50-293-86-4, NUDOCS 8602200073 | | | document report number = NUDOCS 8604140207 |
| | package number = ML20137W143 | | | title reference date = 03-11-1986 |
| | document type = INSPECTION REPORT, NRC-GENERATED, INSPECTION REPORT, UTILITY, TEXT-INSPECTION & AUDIT & I&E CIRCULARS | | | document type = CORRESPONDENCE-LETTERS, NRC TO UTILITY, OUTGOING CORRESPONDENCE |
| | page count = 3 | | | page count = 2 |
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| | APR 101986 |
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| | Docket No. 50-293 Boston Edison Company M/C Nuclear ATTN: Mr. William D. Harrington Senior Vice President, Nuclear 800 Boylston Street Boston, Massachusetts 02199 L Gentlemen: |
| | Subject: Inspection No. 50-293/86-04 This refers to your letter dated March 11, 1986, in response to our letter dated February 12, 1986. |
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| | Thank you for informing us of the corrective and preventive actions documented-in your letter. These ' actions were examined during an inspection conducted March 24-27, 1986 and are considered . acceptable to prevent a reoccurence. |
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| | Further documentation will be contained in NRC Inspection Report 50-293/86-10. |
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| | .Your cooperation with us is appreciated. |
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| | Sincerely, OFilihiSIEmoB7I |
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| | hom s , t. |
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| | vision of Radiation SafMy |
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| | and Safeguards-cc: |
| | A. V. Morisi, Manager, Nuclear Management Services Department C. J.'Mathis, Station Manager Joanne Shotwell, Assistant Attorney General Paul Levy, Chairman, Department of Public Utilities W. J. Nolan, Chairman, Plymouth Board of Selectmen Plymouth Civil Defense Director Senator Edward P. Kirby Public Document Room (PDR) |
| | local Public Document Room (LPDR) |
| | Nuclear Safety Information Center (NSIC) |
| | NRC Resident Inspector |
| | , CommonwealthofMassachusetts(2) |
| | l OFFICIAL RECORD COPY t8604140207 860410 'T i |
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| | PDR ADOCK OS000293:-' ,, |
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| | Boston EdisonL Company M/C Nuclear 2 bcc: |
| | ' Region I-Docket Room (with concurrences) |
| | Management Assistant, DRMA (w/o encl) |
| | Section' Chief, DRP |
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| | W. Raymond, SRI, Vermont Yankee T. Shedlosky, SRI, Millstone 1&2 H. Eichenholz, SRI, Yankee P. Leech, LPM, NRR |
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| | b ; RSS RI Miller /mm a's iak Bellamy 4/7/86 4/rl/86 4/lO/86 i |
| | 0FFICIAL RECORD COPY RL PILGRIM 86-04 - 0002.0.0 04/04/86 t |
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| - ; | | BOSTON EpisON COMPANY 800 BOYLSTON STREET BOSTON. MASSACHUSETTS 02199 l |
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| U.S. NUCLEAR REGULATORY COMMISSION
| | co........ ....... , March 11,1986 n . 6.. . |
| | BECo Ltr. #86-030 l |
| | Dr. Thomas I Regional Administrator - Region 1 . |
| | U. S. Nuclear Regulatory Commission 631 Park Avenue l King of Prussia, PA 19406 i Subject: Response to Notice of Violation as Contained in NRC Letter to Boston Edison dated 2/12/86 (Inspection Report No. 86-04) |
| | References: (A) Letter dated 1/07/86 from South Carolina Department of Health and Environmental Control, Containing Civil Penalty and (2) Items of l Non-Compliance ; |
| | (B) Letter dated 1/28/86 f rom Boston Edison Company to South Carolina ; |
| | Department of Health and Environmental Control, Responding to i Items of Non-Compliance and Civil Penalty |
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| | ==Dear Dr. Murley:== |
| | This letter is in response to the Notice of Violation as contained in Reference (A). As mentioned in our response to the South Carolina Department of Health and Environmental Control [ Reference (B)], we would like to assure you that Boston Edison Company has taken adequate corrective measures to ensure future compliance with the applicable provisions of federal and state laws as they apply to low-level radioactive waste shipments. |
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| | I trust that the attached response will adequately exhibit our serious commitment to continuing compliance in this area. |
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| | Please be advised that, upon review of this matter, Boston Edison has decided that further programmatic review and improvements are both necessary and desirable. The improvements are intended to impose enhanced quality requirements on radioactive waste processing, handling and shipping operations. Our approach will consist of a detailed review of 10 CFR 71 Subpart H and a more thorough integration of appropriate requirements into our existing Quality Assurance Program per 10 CFR 50 Appendix B. We expect to have a more detailed plan and schedule in approximately thirty days at which time a copy will be forwarded to the Senior Resident Inspector at Pilgrim Station. |
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| | Should you have further questions concerning these matters, please do not hesitate to contact me. |
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| ==REGION I==
| | Respectfully submitted, William D. Harring on Attachment |
| Report N /86-04 Docket N License N DPR-35 Priority --
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| Category C
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| ! Licensee: Boston Edison Company 800 Boylston Streets Boston, Massachusetts 02199 Facility Name: Pilgrim Nuclear Power Station Inspection At: Barnwell, South Carolina
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| ; Inspection Conducted: January 2, 1986
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| r a ed by: [ .&lhf/L%
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| M. M1Tler M adiation Specialist Y'lffG
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| ' date Approved by: )D- McAe d4 W. Pasciak, Chief, Effluents ' date Radiation Protection Section
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| . Inspection Summary:
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| ! Inspection on January 2, 1986 by a Representative of the State of South Carolina Department of Health and Environmental Control Areas Inspected: Boston Edison Company was the originator of a waste shipment
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| ; which was inspected at the Chem-Nuclear Systems, Inc., burial site in Barnwell,
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| South Carolin .
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| Results: One violation was identified (failuro to meet packaging requirements for low specific activity radioactive materials).
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| 8602200073 860212 PDR ADOCK 05000293 G PDR l
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| | ATTACHMENT |
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| | Violation As the result of the inspection conducted on January 2, 1986, by a representative of the South Carolina Department of Health and Environmental Control of a shipment of radioactive waste sent from your facility in Plymouth, Massachusetts on December 30, 1985, and in accordance with the NRC Enforcement Policy (10 CFR 2 Appendix C), the following violation was identified: |
| | 10 CFR 71.5, " Transportation of licensed material," states "each licensee who transports licensed material outside of the confines of its plant or other place of use, or who delivers 1 censed material to a carrier for transport, shall comply with the at:licable requirements of the regulations appropriate to the mode of transport of DOT in 49 CFR Parts 170 through 189." |
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| | 1. 49 CFR 173.425(b) (1) " Transport requirements for low specific activity (LSA) radioactive materials" states that materials must be packaged in strong, tight packages so that there will be no leakage of radioactive material under conditions normally incident to transportation." |
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| | Contrary to the above, on December 30, 1985, a waste shipment , |
| | of solid metallic oxides on noncompacted trash, containing 0.195 Curies in a Seatrain container was delivered to a carrier for transport to a burial site in South Carolina, and upon inspection of the container at the burial site on January 2, 1986, by a representative of the State of South Carolina Department of Health and Environment Control, it was determined that there were "three (3) small holes on the lef t rear side which allowed some of the contents to be visible." |
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| | 2. 49 CFR 173.475(b) " Quality Control requirements prior to each shipment of radioactive materials" state, "the shipper shall ensure by examination or appropriate tests that the packaging is in unimpaired physical damage condition, except for superficial marks." |
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| | Contrary to the above, on December 30, 1985, a waste shipment of solid metallic oxides on noncompacted trash, containing 0.195 Curies in a Seatrain container was delivered to a carrier for transport to a burial site in South Carolina, without ensuring prior to shipment that the packaging was in unimpaired physical condition. The container was inspected at the burial site on January 2, 1986, and at that time a representative of the State of South Carolina Department of Health and Environmental Control determined that the Seatrain container was corroded and damaged. |
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| | ResDonse |
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| DETAILS On December 30, 1985, the Boston Edison Company dispatched a shipment of LSA radioactive waste (solid metallic oxides on noncompacted trash) to the Chem-Nuclear Systems, Inc. burial site at Barnwell, South Carolina. The shipment was made in a Seatrain container, containing 0.195 Curies of licensed materia On January 2, 1986, a representative of the South Carolina Department of Health and Environmental control inspected the shipment at the burial sit The inspection consisted of a review of shipping papers, placarding,
| | Boston Edison agrees with both items. Although the subject container was duly inspected and signed off prior to shipment by experienced personnel in accordance with existing Pilgria Station Procedure 6.9.194 (" Loading Transport Vehicle for Radioactive Material and Waste Shipment"), it nevertheless appeared the metal of the cargo container was delaminating due to corrosion, and during transit, the lamination broke loose, leaving the small holes exposed. |
| , marking and labeling, iadiation measurements, selective contamination surveys and examination of the packages and the tractor-traile A copy of the report prepared by the representative is attached., The report states that upon inspection of the Seatrain container, the con-tainer had three small holes on the lef t rear side which allowed some of the contents to be visible, and the container was very corrode CFR 71.5, " Transportation of licensed material," states that "each licensee who transports licensed material outside of the confines of its plant or other place of use, or who delivers licensed material to a car-rier for transport, shall comply with the applicable requirements of the regulations appropriate to 49 CFR 173.425(b)(1), " Transport requirements for low specific activity (LSA) radioattive materials." 49 CFR 173.425 (b)(1) states " materials must be packaged in strong, tight packages so that there will be no leakage of radioactive material under conditions normally incident to transportation." | |
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| 49 CFR 173.475(b) " Quality control requirements prior to each shipment of radioactive materials" states "the shipper shall ensure by examination or appropriate tests that the packaging is in unimpaired physical condition, except for superficial marks." The failure to assure that the Seatrain container was a strong tight package and that the container was in an unimpaired physical condition, except for superficial marks, prior to shipment to the burial site represents a violation of 10 CFR 7 (50-293/86-04-01).
| | Corrective action taken to correct the condition and to preclude recurrence is that Procedure 6.9.194 (" Loading Transport Vehicle for Radioactive Material and Waste Shipments") has been revised and strengthened to include a checklist requiring receipt inspections be performed on Seatrain cargo containers. The procedure has also been improved to include further checklists assuring that the subject shipping container will be inspected for evidence of corrosion and/or damage prior to shipment. Any indication of corrosion and/or damage will be rectified prior to shipment. |
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| The Pilgrim Nuclear Power Station Assistant Chief Radiological Engineer-Radwaste was informed of this apparent item of noncompliance with NRC requirements in a telephone conversation with P. Clemons of the Region I office on January 14, 198 . . - - - - -
| | As further corrective action to preclude recurrence, the Training Department will re-emphasize (to individuals involved in the shipping process) the importance of compliance with pertinent regulations and requirements. The subject violation will be used as a specific example in training, as will the procedural improvements which have been made. |
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| c5 : ' SOUTM CAE0 TIE & MFARTMEur OF MEALTR AND INVIRO10(ENTAL CONTn0L ' .',, Q'i Burea3 of Radiclogical 5:alth
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| .. c Division of Radioactive Material Licensing and Compliance
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| , andiaastive shipment inspection Report *
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| ' General Zafeenstism Report Es. 85-1247
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| 'd Shipper Boston Ediaan Campany-Filgrant Station Address Plymouth. Massachesat b Carrier. rurai _ Tractor F 37 Trailer # on Type _v.. u i <
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| Type Packagaf**** Saatrafn Cask Containing Wid n er.#. m.,rs., - '.o
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| " shipping h ation: '
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| , A$f 42137 Volume Allocation i 12st.2&s-A
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| .i shipping Rama & Class: Radioactiva Materia 1. taA. n Permitf_nantsa_abr Total turial Vol.: 2560 1D( Id.# msels t
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| (L72.202(a ft 3(172.202(c) Total Curies o_tes (172.203 Radionuclides: Co-38660. ca-1374 B-3. Mn-54. Cm-13&. Pu 241. c-14 Describe chem./ phy. media n solid ameni tie nwid . on onnea-... .,e ev..h (172.203(d- Cholating Agente(%) Nana shippers Cartification: S tataw
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| (172.903(d DOAs (171.204)
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| Exclusive Use N Instructions N (173.425(b)) Total mA Check fort Radiation Survey N (173.441) (177.842(a) Compara Contamination Levels y (1 73.443)
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| Radionuclides v/ resin analysis NA Rad / Contamination Levels v/CNSI/BRH N
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| __ shipsest inspection Check List 3 Shipment Braced / Blocked (173.425(b)(6)
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| v 1 Lids (Drum, ox cask) accure (173.425)(b w isible Leakage (173.425(B)(1) _g_, Visible DamagT(173.423)
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| g Package Labelinas_W-I,__Y-II. III(172.403) E Cask Defects / Missing Parts (b) & (c) otQadio_ active LSp (.173.425) y Radiation Survey Cab /sieepe s Waste Class. MarkedLAJB-t; sta ol trailer / truck (173.441)
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| s Gross Weight Marked (172.310)
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| (LSA Exclusive Use Exempt) N Contamination Levels (173.443)
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| NA Type A/ Type 5 Package Marked (172.310) g Vehicle Placards (173.425(c) (172.507)
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| g Tiedowns Secure /Adequata
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| %~ Trailer / Tractor Defects t Offloading Discrepancies h" Packages banded / reinforced. palletired Radiation / Contamination Surveys (transport vehicle or package)
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| (mR/hr) Surfsce .0 2 meters:
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| I Surface: 30,0 Highest contamination detected: Arrival 0- nich, 2 meters: ___ dpm/100 cad Release ope /10cem2 l 18 beta nam.-. dpm/100cm2 dpm/100cm2 I
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| ' Results of Inspection: Su::: mary of violations and diserapancies Upon Department inspectio it was found .that the seatrain cargo carrier was vary corroded and had three (3) small holes
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| on the _lef t roar side which allowed some of the contacts to be visible. Since the mestrain
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| cargo carrier is the disposal package, this_ is contrary to the requiremante of Coidition 6 S.C._ Radioactive Material _ License 097. Amendment 41._and 49 CFR 173.425(b)(1).
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| | Full compliance was achieved on January 23, 1986, the date upon which Procedure 6.9.194 was revised to include the aforementioned improvements. |
| Each of these items of noncompliance constitute separate violatione_of Section 1.2. Department Regulation 61-5 __
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| L Date: January 2. 1986 Inspector's Signature s/ Richard S. Sappington Jz FSOM SES 9- 7L "7 O!'09'95 ! D 07 " d 707 L "
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217N8911999-10-15015 October 1999
Forwards Rept of Changes,Tests & Experiments at Pilgrim Nuclear Power Station for Period of 970422-990621,IAW 10CFR50.59(b).List of Changes Effecting Fsar,Encl
ML20217D3951999-10-13013 October 1999
Forwards Request for Addl Info Re Util 990806 Submittal on USI A-46, Implementation Methodology Used at Pilgrim Nuclear Power Station, Per GL 87-02
ML20217E1581999-10-0808 October 1999
Forwards Insp Rept 50-293/99-05 on 990726-0905.Three Violations Noted & Being Treated as Ncvs.Violations Include Failure to Assure That Design Bases Correctly Translated Into Specifications
ML20217C3151999-10-0606 October 1999
Forwards Scenario Package for Pilgrim Nuclear Power Station Nrc/Fema Evaluated Exercise Scheduled for 991207.Without Encl
ML20217D5591999-10-0505 October 1999
Documents Pilgrim Nuclear Power Station Five Yr Survey of Main Breakwater.Survey Has Determined That Pilgrim Main Breakwater Is Intact & Remains Adequately Constructed to Perform Designed Safety Function
ML20217C8051999-10-0505 October 1999
Forwards Proprietary Results of Audiologic Evaluations for Jp Giar,License SOP-10061-3.Attachment Clearly Shows Requirements for Operator Hearing Ability Are Met. Proprietary Info Withheld,Per 10CFR2.790(a)(6)
ML20212J8301999-09-30030 September 1999
Informs of Completion of mid-cycle PPR of Pilgrim Nuclear Power Station.Staff Conducts Reviews for All Operating NPPs to Integrate Performance Info & to Plan Insp Activities at Facility Over Next Six Months
ML20216J9961999-09-29029 September 1999
Forwards Resume of Person Identified as Acting RPM in Licensee to NRC Re Notification That Person Named in License Condition 11 of 20-07626-02,is No Longer Employed at Pilgrim Station.Resume Withheld,Per 10CFR2.790
ML20212F7871999-09-24024 September 1999
Advises That Util 990121 Application for Amend Being Treated as Withdrawn.Proposed Changes Would Have Modified Facility UFSAR Pertaining to Values for post-accident Containment Pressure Credited in Pilgrim Net Positive Head Analyses
ML20212H1381999-09-23023 September 1999
Submits Info in Support of Request Filed on 990730 to Grant one-time Exemption from 10CFR50,App E,Authorizing Biennial Full Participation Emergency Preparedness Exercise to Be Conducted in 2002 Instead of 2001
ML20212H1441999-09-23023 September 1999
Withdraws 990121 Request for License Change Re Emergency Core Cooling Sys Net Positive Suction Head,Due to Incorrect Datum Preparation
ML20216F3451999-09-16016 September 1999
Forwards Summary Rept Providing Results of ISI Conducted at PNPS on-line & Refueling Outage (RFO 12)
ML20212C2861999-09-16016 September 1999
Forwards SER Accepting Licensee 981123 Request for Relief RR-E1,RR-E5,RR-E6 Pursuant to 10CFR50.55a(a)(3)(i) & Request for Relief RR-E2,RR-E3 & RR-E4 Pursuant to 10CFR50.55a(a)(3)(ii)
ML20216E7111999-09-0909 September 1999
Forwards License Renewal Application Including Form NRC-398 & Form NRC-396 for Jp Giar,License SOP-10061-3.Without Encls
ML20216E5891999-09-0707 September 1999
Forwards Copy of Pilgrim Station Organization Structure. Encl Refelcts Changes in Upper Mgt Level Structure.Changes Were Effective 990901
ML20211M4501999-09-0303 September 1999
Informs That Pilgrim Nuclear Power Station Plans to Conduct Full Participation Emergency Preparedness Exercise with Commonwealth of Ma on 991207,IAW 10CFR50,App E,Section IV.F.2
ML20211M9161999-08-31031 August 1999
Submits Review & Correction of Info in Reactor Vessel Integrity Database (Rvid),Version 2,re Pilgrim Station
ML20211J8391999-08-30030 August 1999
Forwards Rev 1 to Provisional Decommissioning Trust Agreement for Plant,Changing Portions of Agreement to Permit Up to Two Distributions & Clarify Formula for Distribution
ML20211H5701999-08-27027 August 1999
Forwards Insp Rept 50-293/99-04 on 990610-0725.Two Violations Identified Being Treated as non-cited Violations
ML20211C3381999-08-19019 August 1999
Provides semi-annual LTP Update,Including Schedule, Commitment Descriptions,Progress Since Last Update & Summary of Changes.Rev Bars Indicate Changes in Status Since Last Submittal
ML20210U5761999-08-18018 August 1999
Responds to Opposing Merger of Bec Energy & Commonwealth Energy Sys in Commonwealth of Massachusetts. Informs That for Sale,Nrc Responsible for Only Ensuring That Entergy Technically & Financially Qualified to Operate NPP
ML20210U6691999-08-18018 August 1999
Forwards from Massachusetts State Senator T Murray Opposing Merger Between Bec Energy & Commonwealth Energy Systems
ML20210U7521999-08-18018 August 1999
Forwards from Massachusetts State Senator T Murray Opossing Merger Between Bec Energy & Commonwealth Energy Systems
ML20210U5151999-08-17017 August 1999
Forwards Notice of Withdrawal of Application for Approval of Indirect Transfer of FOL for Pilgrim in Response to .Approval No Longer Needed Since Beco Sold Interest in Pilgrim to EOI on 990713
ML20211B3841999-08-16016 August 1999
Forwards Response to NRC Second RAI Re Pressure Locking & Thermal Binding of SR power-operated Gate Valves
ML20210U4831999-08-13013 August 1999
Forwards fitness-for-duty Program Performance Data Sheets for Period of 990101-0630,per 10CFR26.71(d)
ML20210S0891999-08-0909 August 1999
Forwards Amend 11 to Indemnity Agreement B-48 Signed by Boston Edison Co & Entergy Nuclear Generation Co
ML20210R6251999-08-0606 August 1999
Provides Supplementary Info on USI A-46 Implementation Methodology at Pilgrim Station,To Enable NRC to Perform Evaluation & Issuance of Plant Specific SER for Plant
ML20210M9411999-08-0202 August 1999
Requests That NRC Treat Pending Actions Requested by Beco Prior to 990713,as Requests Made by Entergy.Ltr Requests That Minor Administrative Changes to License Amend 182 & Associated Ser, ,reflect 990713 Transfer
ML20210H8761999-07-30030 July 1999
Requests That NRC Grant Exemption from Requirements of 10CFR50,App E,Section IV F,Which Would Authorize Rescheduling of 2001 Biennial Full Participation Emergency Preparedness Exercise for Pilgrim Station to 2002
ML20210H8661999-07-29029 July 1999
Provides Revised Response to GL 96-06 & Addresses NRC Insp Concern for Containment Penetration X-12.Info Submitted to Facilitate NRC Review & Closeout of Subject GL for Plant
ML20216E2321999-07-26026 July 1999
Discusses GL 92-01,rev 1,suppl 1, Rv Structural Integrity. NRC Revised Info in Rvid & Releasing as Rvid Version 2
ML20216D4131999-07-22022 July 1999
Informs That J Conlon,License OP-11040-1,terminated Employment with Beco on 990703,per 10CFR50.74.Individual Will Not Participate in Util Licensed Operator Requalification Training Program
ML20210E2231999-07-20020 July 1999
Discusses Arrangements Made by Dennis & M Santiago During 990615 Telephone Conversation for NRC to Inspect Licensed Operator Requalification Program at Pilgrim During Wk of 991004
ML20210C4151999-07-19019 July 1999
Informs That Util Intends to Submit Approx Eight Licensing Actions in FY00 & Eight in FY01,in Response to Administrative Ltr 99-02.Actions Are Not Expected to Generate Complex Reviews
ML20210F3711999-07-14014 July 1999
Informs NRC That Effective 990713,listed Pilgrim Station Security Plans Have Been Transferred from Boston Edison to Entergy & Are Still in Effect
ML20210A9441999-07-14014 July 1999
Responds to Re Changes to Pilgrim Nuclear Power Station Physical Security Plan Identified as Issue 2,rev 14, Addendum 1,respectively.No NRC Approval Is Required IAW 10CFR54(p)
ML20209G2251999-07-0909 July 1999
Forwards Insp Rept 50-293/99-03 on 990419-0609.Five Severity Level IV Violations of NRC Requirements Identified & Being Treated as non-cited Violations,Consistent with App C. Several Individual Tagging Errors Occurred
ML20209C4661999-07-0707 July 1999
Forwards SE Accepting Addendum on Proposed Change in Corporate Ownership Structure Involving Entergy Nuclear Generation Co
ML20209C7761999-07-0606 July 1999
Submits Annual Summary Rept of Changes Made to QAP Description as Described in QA Manual,Vol Ii.Rept Covers Period of Jul 1998 Through June 1999.No Changes Made During Period
ML20209C3851999-07-0606 July 1999
Forwards Redacted Draft of Decommissioning Trust Agreement Re Transfer of PNPS & NRC Operating License & Matls License from Boston Edison Co to Entergy Nuclear Generating Co
ML20196J7251999-07-0101 July 1999
Informs of Completion of Licensing Action for GL 96-01, Testing of Safety-Related Logic Circuits, for Pilgrim Nuclear Power Station
ML20209B9411999-06-30030 June 1999
Discusses Deferral of IGSCC Welds to RFO 13.Deferral of Welds to Refueling Outage 13 Does Not Impact Acceptable Level of Quality & Safety Per 10CFR50.55(a)(3)(i) Since Plant in Compliance W/Exam Percentage Requirements
ML20209B9431999-06-30030 June 1999
Provides Formal Notification That Closing Date for Sale & Transfer of Pilgrim Station Scheduled to Occur on 990713. a Wang Will Be Verbally Notified of Time of Sale Closing
ML20209B9791999-06-29029 June 1999
Forwards Rev 13A to Pilgrims COLR for Cycle 13,IAW TS 5.6.5 Requirements.Rev 13A Provides cycle-specific Limits for Operating Pilgrim During Remainder of Cycle 13
ML20196H2381999-06-29029 June 1999
Forwards SER Denying Licensee 980820 Request for Alternative Under PRR-13,rev 2 for Use of Code Case N-522 During Pressure Testing of Containment Penetration Piping
ML20209A8761999-06-28028 June 1999
Forwards SER Authorizing Licensee 990317 Relief Request to Use ASME Code Case N-573 as Alternative to ASME Code Section XI Article IWA-4000 for Remainder of 10-year Interval Pursuant to 10CFR50.55a(a)(3)(i)
ML20209A8701999-06-25025 June 1999
Responds to NRC Request for Info Re Y2K Readiness of Computer Sys at Nuclear Power Plants. Y2K Readiness Disclosure for Plant,Reporting Status of Facility Y2K Readiness Encl
ML20210U5901999-06-25025 June 1999
Opposes Merger of Bec Energy & Commonwealth Energy Sys in Commonwealth of Massachusetts.Expresses Skepticism Re Claim by Companies That Consumers Will Benefit from Proposed Consolidation & four-year Freeze in Base Rates
ML20209C3431999-06-22022 June 1999
Forwards Addendum 1,Rev 14 to Pilgrim Station Security Plan,Iaw 10CFR50.54(p)(2).Changes Proposed Have Been Implemented & Constitute Increase in Plant Defense Plan Commitments.Encl Withheld,Per 10CFR73.21
1999-09-09
[Table view]
Category:NRC TO UTILITY
MONTHYEARML20062E0071990-11-14014 November 1990
Forwards List of Unimplemented GSIs at Facility,Per Generic Ltr 90-04
ML20062D6651990-11-0808 November 1990
Ack Receipt of Forwarding Util Evaluation of NRC Inspector General Rept 90N-02 Re Offsite Emergency Planning
ML20058G9761990-11-0707 November 1990
Forwards Safety Insp Rept 50-293/90-20 on 900816-1008 & Notice of Violation
ML20058C5501990-10-26026 October 1990
Requests Written Policies & Procedures Needed for NRC Preparation for Planned fitness-for-duty Insp
ML20062B4311990-10-17017 October 1990
Advises That 901012 Response to Generic Ltr 90-03 Re Vendor Interface for safety-related Components,Acceptable
ML20062B7161990-10-12012 October 1990
Extends Invitation to Attend 910220-21 Util Symposium/ Workshop in King of Prussia,Pa Re Engineering Role in Plant Support.Interest to Participate,Intent to Attend & Approx Number of Representatives to Attend Requested by 901115
ML20062B6281990-10-12012 October 1990
Forwards Insp Rept 50-293/90-21 on 900905-07.Insp Conducted to Review Event of 900902-03 Which Involved Number of Component Malfunctions & Operational Complications Following Shutdown
ML20059N7251990-10-0101 October 1990
Requests That Matls Listed in Encl Be Furnished to Assist Maint Program Team Insp Scheduled for 901105-16
ML20059K6901990-09-11011 September 1990
Forwards Transcript of 900906 Public Meeting in Plymouth,Ma W/State & Local Officials Re Emergency Planning.W/O Encl
ML20059H5871990-09-0101 September 1990
Advises That Reactor Operator & Senior Reactor Operator Exams Scheduled for 901203.Encl Listed Ref Matl Requested
ML20059J6521990-08-29029 August 1990
Forwards Safety Insp Rept 50-293/90-09 on 900806-10.No Violations Noted.Concludes That Engineering & Technical Support Organizations Continue to Provide Strong Station Support
ML20059A1481990-08-17017 August 1990
Forwards 900816 Summary of 900807 Meeting Re Inservice Testing Program
ML20058P0471990-08-0909 August 1990
Forwards Safety Insp Rept 50-293/90-18 on 900709-13.No Violations Noted
ML20058N0401990-08-0606 August 1990
Discusses Licensee Engineering Initiatives.Power Reactor Licenses in Region 1 Should Initiate Similar Program to Provide Sharing of Info & Experiences Involving Engineering Initiatives & Solution to Problems Common to All
ML20056A4801990-07-30030 July 1990
Forwards Safeguards Insp Rept 50-293/90-16 on 900625-29.No Violations Noted.One Unresolved Item Identified
ML20058L7051990-07-27027 July 1990
Forwards Safety Insp Rept 50-293/90-17 on 900625-29.No Violations Noted
ML20055F2461990-06-29029 June 1990
Forwards Safety Insp Rept 50-293/90-13 on 900501-0611.No Violations Noted.Repetitive Failures of Diesel Driven Fire Pump Noted,Requiring Increased Mgt Attention
ML20059M8421990-06-13013 June 1990
Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl
ML20247R8071989-09-21021 September 1989
Forwards SALP Rept 50-293/88-99 for 880516-890630.Instances of Deviation from Approved Practices & Lack of Attention to Detail Which Led to Challenges to Plant Equipment & Personnel Noted
ML20247K6661989-09-0707 September 1989
Forwards Insp Rept 50-293/89-07 on 890525-0710 & Notice of Violation
ML20246K5091989-08-24024 August 1989
Accepts Summary of QA Program Description Changes for 1989, Forwarded by
ML20246L7821989-08-23023 August 1989
Forwards Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $25,000.Failures to Properly Plan, Supervise & Inspect Tagout of Circuit Breakers Directly Contributed to Event
IR 05000293/19890071989-08-18018 August 1989
Approves Reactor Operation Up to 75% of Full Power Per Licensee Power Ascension Test Program.Nrc Findings Docketed in Insp Repts 50-293/89-07 & 50-293/89-08 & Status of Emergency Preparedness for Communities Encl
ML20246G1861989-08-18018 August 1989
Approves Reactor Operation Up to 75% of Full Power Per Licensee Power Ascension Test Program.Nrc Findings Docketed in Insp Repts 50-293/89-07 & 50-293/89-08 & Status of Emergency Preparedness for Communities Encl
ML20246J4811989-08-18018 August 1989
Clarifies NRC Position Re Definition of Extremity for Purposes of Setting Occupational Exposure Limits.Due to Misunderstanding,No Enforcement Action Planned If Licensee Procedures Incorporated Misunderstanding
ML20246D7261989-08-18018 August 1989
Submits Response to Re Plant Power Ascension Program.Util Proposal to Defer Phase 2 of Shutdown from Outside Control Room Test to Planned Fall 1989 mid-cycle Outage Accepted
ML20245F1781989-07-31031 July 1989
Forwards Insp Rept 50-293/89-06 on 890411-0524.No Violations Noted.Licensee Actions W/Respect to 890503 Turbine Trip/Reactor Scram Demonstrated Excellent Approach to Problem Investigation & Resolution
ML20247D0181989-07-18018 July 1989
Ack Receipt of Re Response to NRC Bulletin 89-003, Inadequate Latch Engagement in Hfa Type Relays Mfg by Ge. Necessary Actions Performed to Address Issues in Bulletin
ML20246N3921989-07-14014 July 1989
Forwards Safety Insp Rept 50-293/89-09 on 890619-22.No Violations Noted
ML20246D4961989-07-0606 July 1989
Advises That 880713 Response to NRC Bulletin 88-004, Potential Safety-Related Pump Loss Acceptable
ML20246A7561989-06-26026 June 1989
Approves Reactor Operation Up to 50% Full Power,Per Util Power Ascension Test Program & Confirmatory Action Ltr 86-10.Assessment of Licensee Readiness for Release from NRC Approval Point 3 & Related Info Encl
ML20246B5961989-06-22022 June 1989
Forwards,For Info,Nrr Ack Receipt of Petition Filed by Ecology Ctr of Southern CA & Stating That Petition Being Treated Under 10CFR2.206 of Commission Regulations
ML20245A5371989-06-0909 June 1989
Forwards Insp Rept 50-293/89-05 on 890311-0410.Weaknesses Noted Re Evaluation of Failure Rate & Root Causes for Failures of Airlock Doors & Interlocks
ML20244C2121989-06-0707 June 1989
Responds to Util 881011 Response to Generic Ltr 87-02, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors. Implementation Schedule Contingent Upon Resolution of Procedure
ML20244C2751989-06-0606 June 1989
Forwards Draft Safety Evaluation Re Plant Compliance W/ 10CFR50.62, ATWS Rule. Requests Response to NRC Concerns Re Diversity & Testability of Alternate Rod Injection & Reactor Pump Trip Sys
NUREG-1275, Informs That Util Fulfilled Requirements of Generic Ltr 88-14, Instrument Air Supply Sys Problems Affecting Safety Related Sys1989-06-0202 June 1989
Informs That Util Fulfilled Requirements of Generic Ltr 88-14, Instrument Air Supply Sys Problems Affecting Safety Related Sys
ML20247P5501989-06-0101 June 1989
Forwards Request for Addl Info on Proposed Tech Specs Change Re Visual Insp of High Energy Piping.Listed Concerns Based on Review of Bechtel Calculation 17322-S5,Rev 1
ML20247M2661989-05-26026 May 1989
Forwards Director'S Decision,Ltr of Transmittal & Fr Notice in Response to Ocre 2.206 Petition Expressing Concerns Re 880309 Power Oscillation Event at LaSalle Unit 2 & Request to Reopen Rulemaking on ATWS Issue.W/O Encls
ML20246P6051989-05-15015 May 1989
Forwards Notice of Withdrawal of Application for Amend to License DPR-35.Amend Would Modify Tech Specs Re ECCS Surveillance Requirements
ML20247D5481989-05-0808 May 1989
Forwards Augmented Insp Team Rept 50-293/89-80 on 890413-19 & 17-26.Team Concluded That Safety Significance of 890412 Pressurization Transient Was Minor,Though Event Raised Concerns Re Proximate Human Factors & Equipment
ML20246N7951989-05-0404 May 1989
Forwards Mgt Meeting Rept 50-293/89-04 on 890328-30 W/Commonwealth of Ma & Local Officials
ML20247A6911989-05-0303 May 1989
Extends Invitation to Attend Power Reactor Operator Licensing Seminar on 890531 in King of Prussia,Pa.Agenda & Info Re Lodging Arrangements Encl
ML20245H8371989-04-26026 April 1989
Forwards SAIC-89/1121, In-Progress Audit Rept of Dcrdr at Boston Edison Co Pilgrim Nuclear Power Station & SAIC-89-1119, In-Progress Audit Rept for Boston Edison Co Pilgrim Nuclear Poser Station Spds
ML20245H9551989-04-26026 April 1989
Forwards Insp Rept 50-293/89-01 on 890206-0310 & Notice of Violation
ML20245J1441989-04-25025 April 1989
Advises That 880921 & 890302 Responses to NRC Bulletin 88-007 & Suppl 1, Power Oscillations in BWRs Meet Requirements of Both Bulletins
ML20244E4611989-04-14014 April 1989
Requests Prompt Review & Reporting of Status of Implementation of TMI Action Plan Items at Facility.Printout of All TMI Items Annotated Where Tracking Sys Indicates That Implementation Not Complete Encl
ML20244C2771989-04-10010 April 1989
Informs of Completion of Followup on Plant Regulatory Effectiveness Review Effort & Activities Re TAC 56995. Previous Compensatory Measures Removed as Result of Implementing Corrective Action
ML20244A6931989-04-0707 April 1989
Forwards Mgt Meeting Rept 50-293/89-43 on 890309 to Discuss Util Followup Actions to 890304 Reactor Scram
ML20244A6281989-04-0303 April 1989
Forwards Insp Rept 50-293/88-37 on 881227-890205.Violation Noted Re Failure to Control Locked High Radiation Area Access
ML20235V7311989-03-0303 March 1989
Forwards Safety Evaluation Accepting Revised Temp Profile, Per GE EAS-98-0887, Drywell Temp Analysis for Pilgrim Nuclear Power Station. Profile Requested to Be Documented in Next Updated FSAR
1990-09-11
[Table view]
Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217D3951999-10-13013 October 1999
Forwards Request for Addl Info Re Util 990806 Submittal on USI A-46, Implementation Methodology Used at Pilgrim Nuclear Power Station, Per GL 87-02
ML20217E1581999-10-0808 October 1999
Forwards Insp Rept 50-293/99-05 on 990726-0905.Three Violations Noted & Being Treated as Ncvs.Violations Include Failure to Assure That Design Bases Correctly Translated Into Specifications
ML20212J8301999-09-30030 September 1999
Informs of Completion of mid-cycle PPR of Pilgrim Nuclear Power Station.Staff Conducts Reviews for All Operating NPPs to Integrate Performance Info & to Plan Insp Activities at Facility Over Next Six Months
ML20212F7871999-09-24024 September 1999
Advises That Util 990121 Application for Amend Being Treated as Withdrawn.Proposed Changes Would Have Modified Facility UFSAR Pertaining to Values for post-accident Containment Pressure Credited in Pilgrim Net Positive Head Analyses
ML20212C2861999-09-16016 September 1999
Forwards SER Accepting Licensee 981123 Request for Relief RR-E1,RR-E5,RR-E6 Pursuant to 10CFR50.55a(a)(3)(i) & Request for Relief RR-E2,RR-E3 & RR-E4 Pursuant to 10CFR50.55a(a)(3)(ii)
ML20211H5701999-08-27027 August 1999
Forwards Insp Rept 50-293/99-04 on 990610-0725.Two Violations Identified Being Treated as non-cited Violations
ML20210U7521999-08-18018 August 1999
Forwards from Massachusetts State Senator T Murray Opossing Merger Between Bec Energy & Commonwealth Energy Systems
ML20210U5761999-08-18018 August 1999
Responds to Opposing Merger of Bec Energy & Commonwealth Energy Sys in Commonwealth of Massachusetts. Informs That for Sale,Nrc Responsible for Only Ensuring That Entergy Technically & Financially Qualified to Operate NPP
ML20210U6691999-08-18018 August 1999
Forwards from Massachusetts State Senator T Murray Opposing Merger Between Bec Energy & Commonwealth Energy Systems
ML20210U5151999-08-17017 August 1999
Forwards Notice of Withdrawal of Application for Approval of Indirect Transfer of FOL for Pilgrim in Response to .Approval No Longer Needed Since Beco Sold Interest in Pilgrim to EOI on 990713
ML20216E2321999-07-26026 July 1999
Discusses GL 92-01,rev 1,suppl 1, Rv Structural Integrity. NRC Revised Info in Rvid & Releasing as Rvid Version 2
ML20210E2231999-07-20020 July 1999
Discusses Arrangements Made by Dennis & M Santiago During 990615 Telephone Conversation for NRC to Inspect Licensed Operator Requalification Program at Pilgrim During Wk of 991004
ML20210A9441999-07-14014 July 1999
Responds to Re Changes to Pilgrim Nuclear Power Station Physical Security Plan Identified as Issue 2,rev 14, Addendum 1,respectively.No NRC Approval Is Required IAW 10CFR54(p)
ML20209G2251999-07-0909 July 1999
Forwards Insp Rept 50-293/99-03 on 990419-0609.Five Severity Level IV Violations of NRC Requirements Identified & Being Treated as non-cited Violations,Consistent with App C. Several Individual Tagging Errors Occurred
ML20209C4661999-07-0707 July 1999
Forwards SE Accepting Addendum on Proposed Change in Corporate Ownership Structure Involving Entergy Nuclear Generation Co
ML20196J7251999-07-0101 July 1999
Informs of Completion of Licensing Action for GL 96-01, Testing of Safety-Related Logic Circuits, for Pilgrim Nuclear Power Station
ML20196H2381999-06-29029 June 1999
Forwards SER Denying Licensee 980820 Request for Alternative Under PRR-13,rev 2 for Use of Code Case N-522 During Pressure Testing of Containment Penetration Piping
ML20209A8761999-06-28028 June 1999
Forwards SER Authorizing Licensee 990317 Relief Request to Use ASME Code Case N-573 as Alternative to ASME Code Section XI Article IWA-4000 for Remainder of 10-year Interval Pursuant to 10CFR50.55a(a)(3)(i)
ML20195K3071999-06-15015 June 1999
Forwards Safety Evaluation Granting Licensee Request to Use Guidance of GL 90-05 to Repair Flaws in ASME Class 3 Salt Svc Water Sys Piping for Plant
ML20195K3851999-06-11011 June 1999
Forwards Copy of Notice of Consideration of Approval of Application Re Proposed Corporate Merger & Opportunity for Hearing.Application Seeks Approval of Proposed Indirect Transfer of FOL for Plant
ML20196K9921999-06-0404 June 1999
Informs That NRC Ofc of NRR Reorganized Effective 990328.As Part of Reorganization,Division of Licensing Project Mgt Created
ML20207E7351999-05-27027 May 1999
Responds to Requesting Reduction in IGSCC Insp Frequency Per GL 88-01 to Be Performed During Upcoming RFO 12.Forwards SE Re Reduction of IGSCC Insp of Category D Welds Due to Implementation of H Water Chemistry
ML20207B6341999-05-26026 May 1999
Informs That Licensee 990415 Submittal Re Financial Position of Entergy Intl Ltd,Llc Will Be Marked as Proprietary & Withheld from Public Disclosure Pursuant to 10CFR2.790(b)(5) & Section 103(b) of Atomic Energy Act
ML20207B7391999-05-24024 May 1999
Forwards from Kc Goss of FEMA to Cl Miller Forwarding FEMA Analysis of Prompt Alert & Notification Sys for Pilgrim Nuclear Power Station.Based on Review,No Significant Problems Exist with Alert & Notification Sys
ML20207B0701999-05-24024 May 1999
Responds to Sent to Ofc of Congressional Affairs Requesting Info on Concerns Raised by One Constituent,J Riel Re Y2K Compliance of Pilgrim NPP in Plymouth,Ma
ML20207C0321999-05-18018 May 1999
Forwards Fifth Rept Which Covers Month of Apr 1999. Commission Approved Transfer of TMI-1 Operating License from Gpu to Amergen & Transfer of Operating License for Pilgrim Station from Beco to Entergy Nuclear Generating Co
ML20206U7501999-05-17017 May 1999
Forwards Insp Rept 50-293/99-02 on 990308-0418.Two Severity Level 4 Violations Occurred & Being Treated as NCVs
ML20206M1891999-05-11011 May 1999
Forwards SE of 980826 Request to Use Guidance of GL 90-05 to Repair Flaws in ASME Class 3 Salt Svc Sys Piping for Plant
ML20206E0551999-04-29029 April 1999
Discusses Bulletin 96-03 Issued on 960506 & Beco Responses ,970207,981230,990121 & 990309 for Pilgrim Npp. Determined That Actions Taken Should Minimize Potential for Clogging of ECCS Suction Strainers
ML20206B3031999-04-20020 April 1999
Forwards Insp Rept 50-293/99-01 on 990125-0307.Two Violations of NRC Requirements Occurred & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy.Security Program Was Also Inspected
ML20205Q9491999-04-0909 April 1999
Informs That on 990225 NRC Staff Completed PPR of Pilgrim Nuclear Power Station.Staff Conducts Reviews for All Operating NPPs to Develop an Integrated Understanding of Safety Performance
ML20205B9391999-03-24024 March 1999
Forwards Second Request for Addl Info Re GL 95-07, Pressure-Locking & Thermal-Binding of Safety-Related Power-Operated Gate Valves
ML20204C7871999-03-17017 March 1999
Informs That Application Submitting Transfer of Facility Operating License & Matls License & Proposed Amend, Will Be Marked as Proprietary & Be Withheld from Public Disclosure Pursuant to 10CFR2.709(b)(5)
ML20199K8321999-01-22022 January 1999
Forwards Request for Addl Info Re Transfer of Facility Operating License for Plant
ML20199H5811999-01-20020 January 1999
Submits Exemption Withdrawal of 10CFR70.24(a) Re Criticality Accident Monitoring Requirements
ML20198L7781998-12-22022 December 1998
Forwards Insp Rept 50-293/98-10 on 981020-1208.No Violations Noted.Nrc Regional Specialists Reviewed EP & Fire Protection Programs.Ep Program Was Found to Be Well Implemented
ML20198J0891998-12-21021 December 1998
Forwards NRC Response to Me Lampert Re Transfer of Ownership of Pilgrim Station in Response to Senator Kerry Ltr Dtd 981019.NRC Will Terminate License Only When Licensee Remediates Site to Levels Specified in Regulations
ML20198J1041998-12-21021 December 1998
Forwards NRC Response to Me Lampert Re Transfer of Ownership of Pilgrim Station in Response to Congressman Markey Ltr Dtd 981019.NRC Will Terminate License Only When Licensee Remediates Site to Levels Specified in Regulations
ML20137T2211998-12-17017 December 1998
Responds to to Chairman Jackson Re Concerns About Possible Sale of Pilgrim Station & Waste Disposal Issues.No Application for License Received Nor Contract of Sale Between Beco & Entergy.Record Copy
ML20198J1161998-12-17017 December 1998
Responds to to Chairman Jackson in Which Recipient Expressed Concern About Possible Sale of Pilgrim Station & About Waste Disposal Issues.Nrc Has Not Received Application for Transfer of License to Date
ML20198P2781998-12-17017 December 1998
Final Response to FOIA Request for Documents.Forwards App a Records Being Released in Entirety.App B Records Being Withheld in Entirety (Ref FOIA Exemption 4)
ML20198B2021998-12-0909 December 1998
Advises of Planned Insp Effort Resulting from Licensee Irpm Review.Details of Insp Plan for Next 6 Months & Historical Listing of Plant Issues Encl
ML20197H8521998-12-0909 December 1998
Responds to Ltr Sent to Chairman SA Jackson on 981028 Re Concern That NRC Will Not Perform Environ Assessment in Connection with Consideration of Approval of Transfer of License for Plants to Permit Sale
ML20196J1201998-12-0404 December 1998
Ack Receipt of 971217 & 30 & 980112,0309,0423 & 0630 Ltrs Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-293/97-02,50-293/97-11,50-293/97-13, 50-293/97-80 & 50-293/98-01.Actions Found Acceptable
ML20196B5421998-11-24024 November 1998
Forwards Plant SRO & RO Initial Exam Rept 50-293/98-301OL During Wk of 981016-23
ML20196F7631998-11-24024 November 1998
Forwards Insp Rept 50-293/98-203 on 980928-1023.No Violations Noted.Three Issues Identified Re Containment Flooding,Surveillance Testing Criteria & Protection for RBCCW System from High Energy Line Break Inside Drywell
ML20196C1191998-11-20020 November 1998
Forwards Insp Rept 50-293/98-08 on 980907-1019.No Violations Noted.During Insp Period,Chemical Decontamination of Residual Heat Removal Sys Was Well Planned & Implemented Which Reduced Radiation Doses in Heat Removal Quadrants
ML20195H7361998-11-16016 November 1998
Informs of Individual Exam Results for Applicants on Initial Exam Conducted on 981016 & 981019-23 at Facility.Nine Applicants Were Administered Exam & Nine Passed.Licenses Issued & Individual Test Results Encl.Without Encl
ML20155C4781998-10-29029 October 1998
Forwards RAI Re Resoultion to GL 96-06 Issues at Plant,Unit 1.Response Requested by 981130
ML20154J7881998-10-0808 October 1998
Authorizes Mb Santiago to Administer Initial Written Exams to Applicants Listed (Except Applicants Redlined), on 981016.NRC Region I Operator Licensing Staff Will Administer Operating Tests During Week of 981019
1999-09-30
[Table view] |
Inspection Report - Pilgrim - 1986004 |
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APR 101986
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Docket No. 50-293 Boston Edison Company M/C Nuclear ATTN: Mr. William D. Harrington Senior Vice President, Nuclear 800 Boylston Street Boston, Massachusetts 02199 L Gentlemen:
Subject: Inspection No. 50-293/86-04 This refers to your letter dated March 11, 1986, in response to our letter dated February 12, 1986.
Thank you for informing us of the corrective and preventive actions documented-in your letter. These ' actions were examined during an inspection conducted March 24-27, 1986 and are considered . acceptable to prevent a reoccurence.
Further documentation will be contained in NRC Inspection Report 50-293/86-10.
.Your cooperation with us is appreciated.
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Sincerely, OFilihiSIEmoB7I
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and Safeguards-cc:
A. V. Morisi, Manager, Nuclear Management Services Department C. J.'Mathis, Station Manager Joanne Shotwell, Assistant Attorney General Paul Levy, Chairman, Department of Public Utilities W. J. Nolan, Chairman, Plymouth Board of Selectmen Plymouth Civil Defense Director Senator Edward P. Kirby Public Document Room (PDR)
local Public Document Room (LPDR)
Nuclear Safety Information Center (NSIC)
NRC Resident Inspector
, CommonwealthofMassachusetts(2)
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W. Raymond, SRI, Vermont Yankee T. Shedlosky, SRI, Millstone 1&2 H. Eichenholz, SRI, Yankee P. Leech, LPM, NRR
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0FFICIAL RECORD COPY RL PILGRIM 86-04 - 0002.0.0 04/04/86 t
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BOSTON EpisON COMPANY 800 BOYLSTON STREET BOSTON. MASSACHUSETTS 02199 l
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co........ ....... , March 11,1986 n . 6.. .
BECo Ltr. #86-030 l
Dr. Thomas I Regional Administrator - Region 1 .
U. S. Nuclear Regulatory Commission 631 Park Avenue l King of Prussia, PA 19406 i Subject: Response to Notice of Violation as Contained in NRC Letter to Boston Edison dated 2/12/86 (Inspection Report No. 86-04)
References: (A) Letter dated 1/07/86 from South Carolina Department of Health and Environmental Control, Containing Civil Penalty and (2) Items of l Non-Compliance ;
(B) Letter dated 1/28/86 f rom Boston Edison Company to South Carolina ;
Department of Health and Environmental Control, Responding to i Items of Non-Compliance and Civil Penalty
Dear Dr. Murley:
This letter is in response to the Notice of Violation as contained in Reference (A). As mentioned in our response to the South Carolina Department of Health and Environmental Control [ Reference (B)], we would like to assure you that Boston Edison Company has taken adequate corrective measures to ensure future compliance with the applicable provisions of federal and state laws as they apply to low-level radioactive waste shipments.
I trust that the attached response will adequately exhibit our serious commitment to continuing compliance in this area.
Please be advised that, upon review of this matter, Boston Edison has decided that further programmatic review and improvements are both necessary and desirable. The improvements are intended to impose enhanced quality requirements on radioactive waste processing, handling and shipping operations. Our approach will consist of a detailed review of 10 CFR 71 Subpart H and a more thorough integration of appropriate requirements into our existing Quality Assurance Program per 10 CFR 50 Appendix B. We expect to have a more detailed plan and schedule in approximately thirty days at which time a copy will be forwarded to the Senior Resident Inspector at Pilgrim Station.
Should you have further questions concerning these matters, please do not hesitate to contact me.
Respectfully submitted, William D. Harring on Attachment
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ATTACHMENT
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Violation As the result of the inspection conducted on January 2, 1986, by a representative of the South Carolina Department of Health and Environmental Control of a shipment of radioactive waste sent from your facility in Plymouth, Massachusetts on December 30, 1985, and in accordance with the NRC Enforcement Policy (10 CFR 2 Appendix C), the following violation was identified:
10 CFR 71.5, " Transportation of licensed material," states "each licensee who transports licensed material outside of the confines of its plant or other place of use, or who delivers 1 censed material to a carrier for transport, shall comply with the at:licable requirements of the regulations appropriate to the mode of transport of DOT in 49 CFR Parts 170 through 189."
1. 49 CFR 173.425(b) (1) " Transport requirements for low specific activity (LSA) radioactive materials" states that materials must be packaged in strong, tight packages so that there will be no leakage of radioactive material under conditions normally incident to transportation."
Contrary to the above, on December 30, 1985, a waste shipment ,
of solid metallic oxides on noncompacted trash, containing 0.195 Curies in a Seatrain container was delivered to a carrier for transport to a burial site in South Carolina, and upon inspection of the container at the burial site on January 2, 1986, by a representative of the State of South Carolina Department of Health and Environment Control, it was determined that there were "three (3) small holes on the lef t rear side which allowed some of the contents to be visible."
2. 49 CFR 173.475(b) " Quality Control requirements prior to each shipment of radioactive materials" state, "the shipper shall ensure by examination or appropriate tests that the packaging is in unimpaired physical damage condition, except for superficial marks."
Contrary to the above, on December 30, 1985, a waste shipment of solid metallic oxides on noncompacted trash, containing 0.195 Curies in a Seatrain container was delivered to a carrier for transport to a burial site in South Carolina, without ensuring prior to shipment that the packaging was in unimpaired physical condition. The container was inspected at the burial site on January 2, 1986, and at that time a representative of the State of South Carolina Department of Health and Environmental Control determined that the Seatrain container was corroded and damaged.
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ResDonse
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Boston Edison agrees with both items. Although the subject container was duly inspected and signed off prior to shipment by experienced personnel in accordance with existing Pilgria Station Procedure 6.9.194 (" Loading Transport Vehicle for Radioactive Material and Waste Shipment"), it nevertheless appeared the metal of the cargo container was delaminating due to corrosion, and during transit, the lamination broke loose, leaving the small holes exposed.
Corrective action taken to correct the condition and to preclude recurrence is that Procedure 6.9.194 (" Loading Transport Vehicle for Radioactive Material and Waste Shipments") has been revised and strengthened to include a checklist requiring receipt inspections be performed on Seatrain cargo containers. The procedure has also been improved to include further checklists assuring that the subject shipping container will be inspected for evidence of corrosion and/or damage prior to shipment. Any indication of corrosion and/or damage will be rectified prior to shipment.
As further corrective action to preclude recurrence, the Training Department will re-emphasize (to individuals involved in the shipping process) the importance of compliance with pertinent regulations and requirements. The subject violation will be used as a specific example in training, as will the procedural improvements which have been made.
Full compliance was achieved on January 23, 1986, the date upon which Procedure 6.9.194 was revised to include the aforementioned improvements.
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