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| {{Adams | | {{Adams |
| | number = ML20135E467 | | | number = ML20204A376 |
| | issue date = 09/06/1985 | | | issue date = 05/01/1986 |
| | title = Insp Rept 50-219/85-25 on 850729-0801.Violation Noted: Failure to Conduct QC Program Re Radwaste Transfer to Land Disposal Facility | | | title = Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-219/85-25. Corrective Actions Will Be Examined During Future Insp |
| | author name = Clemons P, Kramaric M, 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 = Fiedler P |
| | addressee affiliation = | | | addressee affiliation = GENERAL PUBLIC UTILITIES CORP. |
| | docket = 05000219 | | | docket = 05000219 |
| | license number = | | | license number = |
| | contact person = | | | contact person = |
| | document report number = 50-219-85-25, IEB-79-19, NUDOCS 8509160407 | | | document report number = NUDOCS 8605120139 |
| | package number = ML20135E460 | | | title reference date = 04-10-1986 |
| | 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 = 7 | | | page count = 2 |
| }} | | }} |
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| | MAY n 11986 Docket No. 50-219 GPU Nuclear Corporation ATTN: Mr. P. B. Fiedler Vice President and Director Oyster Creek Nuclear Generating Station P. O. Box 388 Forked River, NJ 08731 Gentlemen: |
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| | Subject: Inspection No. 85-25 We acknowledge receipt of your letter dated April 10, 1986, in response to our letter dated September 11, 1985. |
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| U.S. NUCLEAR REGULATORY COMMISSION
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| ==REGION I==
| | Thank you for informing us of the corrective and preventive actions documented in your letter. These actions will be examined during a future inspection of your licensed program. |
| , Report N /85-25
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| Docket N License No. OPR-11 Priority --
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| Category C Licensee: GPU Nuclear Cg poration P. O. Box 388 Forked River, New Jersey 08731 i Facility Name: Oyster Creek Nuclear Station I Inspection At: Forked River, New ' Jersey l
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| Inspection Conducted: July 29 - August 1, 1985 Inspectors: [ b-m / _f
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| 'P. Clemons, Madiation Specialist d&te f0 M/lY M. Kramaric, Radiation Specialist
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| ]l.tuA wad $lh.> E Ji 6 M. ftH ie 4diation Specialist 'date Approved by: 'N L4 ~
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| bgTciak, Chief d [
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| /dat6 W.J(dadiologicalProtectionSection BWR
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| Inspection Summary: ,
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| Inspection on July 29 - August 1, 1985'(Report No. 50-219/85-25)
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| / Areas Inspected: Routine, unannounced safety inspection of transportation
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| , activities including: managemenV controls, training, quality assurance, audits, package selection, shipment of radioactive materials, and low-level
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| , radioactive waste storage facilit '
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| Results: One violation was identified: Failbr'e to conduct a quality control program paragraph i; a
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| w 8509160407 850911 PDR ADOCK 05000219 G PDR
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| | Your cooperation with us is appreciated. |
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| | Sincerely, |
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| | r ido151rre??7~ |
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| | h .as) . Mar n, irect Ok Division of Radiation fety and Safeguards cc: |
| | M. Laggart, BWR Licensing Manager Licensing Manager, Oyster Creek Public Document Room (PDR) |
| | Local Public Document Room (LPOR) |
| | Nuclear Safety Information Center (NSIC) |
| | NRC Resident Inspector State of New Jersey C |
| | G 0FFICIAL RECORD COPY RL OYC 85-25 - 0001.0.0 ' |
| | 04/24/86 - |
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| DETAILS
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| 1.0 Persons Contacted a
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| 1.1 Licensee Personnel
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| ! *P. Fiedler, Vice President and Director, Oyster Creek
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| * Sullivan Jr. , Plant Operations Director
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| ; * Turner, Radiological Controls Director
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| * Fenti, Quality Assurance (QA) Mod / Ops Manager, Oyster Creek
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| * Fuller, Ops QA Manager
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| * Markowski, QA Program Development / Audit Manager, GPUN
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| * Simonetti Jr. , Audit Manager, Oyster Creek
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| *T. Snider, Radwaste Operations Manager
| | GPU Nuclear Corporation 2 bcc: |
| "A. Wacha, Radwaste Shipping Supervisor
| | Region I Docket Room (with concurrences) |
| ! R. Hurley, Group Radwaste Shipping Supervisor B. Schlotens, QA Lead Monitor t W. Spoulos, Group Radwaste Packaging Supervisor
| | Management Assistant, DRMA Section Chief, DRP R SS RI S RI:DRSS MMiller/ms PascFak Bellamy 4/21/86 4/$b/86 f/ \ /86 0FFICIAL RECORD COPY RL OYC 85-25 - 0002.0.0 04/24/86 I |
| [ *P. Czaya, Licensing Engineer j *B. Hohman, Licensing Engineer i 1.2 Vendor Personnel j M. O' Kelly, Waste Management Inc.
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| 1.3 NRC Personnel
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| 4 *B. Bateman, Senior Resident Inspector | |
| ! * denotes attendance at the exit interview on August 1, 1985.
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| 2.0 Purpose The purpose of this routine inspection was to review the licensee's .
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| transportation activities with respect to the following elements: !
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| Management Control
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| Training
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| Quality Assurance
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| Audits
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| Solid Radioactive Waste System and Processing
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| Package Selection
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| Shipment of Radioactive Materials !
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| Low-Level Radioactive Waste Storage Facility Status l
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| - 3.0 Management Control | | _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _______ _______ . -_ |
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| i The responsibility for the administration, technical' direction and imple- !
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| mentation of the licensee's Process Control Program (PCP) for liquid and solid radioactive waste and for shipment of radioactive material is the
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| | OPU Nuclear Corporstkm |
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| d function of the Radwaste Operations Manager. Overall responsibility for radioactive waste management resides with the Plant Operations Director, ,
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| who reports to the Vice President and Director of Oyster Cree ,
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| l The licensee had documented the management control for radioactive waste :
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| management in Procedure 101, Revision 15, " Organization and Responsi- i
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| bility." The inspector discussed with the Radwaste Operations Manager 7 and Radwaste Shipping Supervisor the responsibilities and authorities of
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| ; the individuals designated in the Radwaste Operations organization char ! The inspector noted that vendor support was being used for operations and .
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| monitoring of the solidification process, and for classification and char-acterization of radioactive wast All of these activities were governed by procedures which specify methods ;
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| for handling, processing, sampling, and shipment of radioactive wast '
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| For example, Procedure 101.3, Revision 12, " Shipment of Radioactive t l Material" described the requirements for radioactive material and radio- l active waste shipments. This procedure also detailed the responsibilities '
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| of the Radwaste Shipping Supervisor and the responsibilities of other sup-
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| port grou i
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| Within the scope of this review, no violations were identifie ,
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| 4.0 Training Personnel training in transportation activities was reviewed against the i i criteria contained in IE Bulletin 79-19, " Packaging of Low-Level Radio-t active Waste for Transport and Burial." .
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| t i The licensee's performance relative to this criteria was determined by l discussions with the Radwaste Operations Manager, Radwaste Shipping !
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| Supervisor and other supervisory personnel, and by review of training
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| , documentatio :
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| ; Within the scope of this review no violations were identified. However,
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| { the following concern was identified: ,
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| On September 24, 1979, in response to Item 5 of IE Bulletin 79-19, ;
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| the licensee stated that training and periodic retraining in the DOT '
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| and NRC regulatory requirements was being provided to the health >
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| i physics personnel. The inspector discussed with the-licensee, that !
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| I since a new organization was now performing the radwaste packaging i and shipment function, the licensee's training commitments should be i
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| revised to define the current training and retraining program. The '
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| inspector also noted that during 1984 no formalized training was i provided to licensee personnel responsible for radioactive waste / i
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| ; material shipment. Another letter, clarifying the intent of the j
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| licensee's response to IE Bulletin 79-19, should be submitted to the Regional Administrator in the near future. This item will be
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| ' j reviewed during a subsequent inspection (219/85-25-01).
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| i 5.0 Quality Assurance Program "
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| i The implementation of the licensee's Quality Assurance Program (QAP) for
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| | NggIg{ Post Office Box 388 Route 9 South Forked River, New Jetsey 08731-0388 l |
| transport packages was reviewed against the criteria contained in 10 CFR 71, "Subpart H - Quality Assurance," and 10 CFR 50, Appendix B.
| | 609 971 4000 Writer's Direct Dial Number: |
| | April 10, 1986 Dr. Thomas E. Murley, Administrator Region I U.S. Nuclear Regulatory Comission 631 Park Avenue King of Prussia, PA 19406 |
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| ; The licensee's performance relative to this criteria was determined from !
| | ==Dear Dr. Marley:== |
| j discussions with the QA Mod / Operations Manager, QA Operations Manager,
| | Subject: Oyster Creek Nuclear Generating Station Docket No. 50-219 IE Inspection 85-25 dated September 11, 1985 As suggested by the subject inspection report, Attachment I of this letter updates our September 24, 1979 response to I&E Bulletin 79-19, |
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| | " Packaging of Low-Level Radioactive Waste for Transport and Burial". |
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| the QA Operations Lead Monitor, and from review of the QA Mod / Operations j Monitoring Program, Revision 5, and.the QA monitoring reports for 1985 l l with regard to radioactive waste processing and shipment [
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| Within the scope of this review, the following violation was identified: f I
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| 10 CFR 20.311(d)(3), " Transfer. for disposal and manifests" requires !
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| 1 .a licensee who transfers radioactive waste.to a land disposal facil- !
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| l ity to conduct a quality control program to assure compliance with !
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| l -10 CFR 61.55 and 10 CFR 61.5 !
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| The licensee has transferred several radioactive waste shipments to 'I a land disposal facility during 1984 and 1985 and the licensee has !
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| not conducted a quality control program to assure compliance with 10 [
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| CFR 61.55 and 10 CFR 61.56, inasmuch as the licensee has not verified t that spent resin contained less than 1*4 liquid by volume when the !
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| resin was in a disposal container (high integrity container) designed j to ensure stability; and neither did the licensee verify that the ;
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| : solidification process was as effective as described in the Topical !
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| 1 Repor In addition, the licensee QA inspection program did not i 1 verify that the computer program used in waste classification per- 'i j formed the required functions, t
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| [ Failure to conduct a quality control program to assure compliance !
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| with 10 CFR 61.55 and-10 CFR 61.56 represents a violation of 10 CFR ,
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| 20.311(d)(3) (219/85-25-02). -
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| Within the scope of this review, the following concern requiring !
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| licensee attention was also identified: i
| | As you are aware, since our original response to I&E Bulletin 79-19, an organizational change altered the department responsible for the radwaste packaging and shipping functions. Previously the responsibility was under the direction and control of the Radiation Protection Department. The present shipping organization is under the control and direction of the Manager of Radwaste Operations. Thus, the commitment to I&E Bulletin 79-19 Item 5 is being revised to reflect current training programs. We understand that this item will be reviewed during a subsequent inspection. |
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| The licensee had identified all structures, systems and compon- | |
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| | Should you require any further information, please contact Brenda Honman, Oyster Creek Licensing Engineer at (609)917-4642. |
| ents to.be covered by the quality assurance program on a docu-- .!
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| ment designated as a Q List. However, transport packages wer '
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| not included on this list. Rather, 10 CFR 71 was listed as an ;
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| ., area fnr which the quality Contml Pmgram would be applied. The !
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| licensee stated that the-Q List was being revised and only owner .
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| | Very truly yours, P |
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| | Yice President and Director Oyster Creek PBF/BH/ dam (0103A) |
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| | Attacnment cc: Mr. Jack N. Donohew, Jr. |
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| - -- _ - _ - -- -. - - - . - - . . - . - - - -- - -. - | | * U.S. Nuclear Regulatory Comission 7920 Norfolk Avenue, Phillips Bldg. |
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| * | | Bethesda, MD 20014 ,N,r&j~1 ~3<n/ D '' |
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| | Mail Stop No. 314 NRC Resident Inspector 0/ ster Creek Nuclear Generating Station GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation |
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| | r ATTACHMENT I |
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| | ' Revised Response to NRC 16E Bulletin 79-19 i |
| | Item 1 Maintain a current set of DOT and NRC regulations concerning the transfer, packaging, and t ransport of low-level radioactive waste material . |
| | Response A current set of Department of Transportation (49 CFR) and Nuclear Regulatory Commission (10 CFR) regulations concerning the transfer, packaging, and transport of low-level radioactive waste material is maintained at the Oyster Creek Station in the Radwaste Shipping Department. |
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| | Item 2 Maintain a current set of requirements (license) placed on the waste burial firm by the Agreement State of Nevada, South Carolina, or Washington before packaging low-level radioactive waste material for transfer and shipment to the Agreement State licensee. If a waste collection contractor is used, obtain the appropriate requi rement s from the contractor. |
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| equipment and components would be on the Q List. Therefore, ,
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| transport packages, as well as other non-owner equipment would i be addressed by QAP procedures or an appropriate vendor lis The inspector stated implementation of the QAP process will be reviewed during a subsequent inspection (219/85-25-03). ,
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| 6.0 Audits
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| i The adequacy and affectiveness of the licensee's audit program for trans- ,
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| port packages were reviewed against the criteria contained in Criterion ;
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| XVIII of Appendix B,10 CFR 50, and with respect to Technical Specifi- l j cation 6.5.3.5, " Audits."
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| ! The licensee's performance relative to these criteria was determined by l review cf Audit S-0C-84-14, "Radwaste Shipping and Operations," dated
| | Response A current set of requirements (license) placed on the burial site operators by their respective states are maintained on site in the Radwaste Shipping Department. |
| ; August 8 through October 8,1984 and discussions with the Audit Manager
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| and QA Program Development / Audit Manager. The qualifications of the j auditor were reviewed relative to ANSI N45.2, " Quality Assurance Program | | Items 3 Designate, in writing, people in your organization who are responsible for the safe transfer, packaging, and transport of low-level radioactive material. |
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| Requirements for Nuclear Facilities."
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| | Response Personnel in the Oyster Creek Station organization who are responsible for the safe transfer, packaging, and transport of the low-level radioactive material and those personnel qualified and authorized to sign shipping papers for transportation of radioactive waste have been designated in writing. |
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| Within the scope of this review, no violations were identified. However, the following concern was identified:
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| = | | Revised Response to NRC I6E Page 2 |
| The Audit System Plan addressed the 10 CFR 50 Appendix B criteria
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| ! for transport packages. However, the focus of the Radwaste Audit S-0C-84-14 was to determine the adequacy of procedure compliance.
| | Bulletin 79-19 Item 4 Provide management-approved, detailed inst ructions and operat ing procedures to all personnel involved in the transfer, packaging, and transport of low-level radioacti ve mat erial . Special attention should be given to controls on the chemical and physical fom of the low-level radioactive material and on the containment integrity of the packaging.. |
| | Response Management-approved operating procedures which are used in operations and in the transfer, packaging, and transport of radioactive material are provided. |
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| ; The inspector noted that performance against the other designated ;
| | Item 5 Provide training and periodic retraining in the DOT and NRC regulatory requi rements, the waste burial license requirements, and in your instructions and operating procedures for all personnel involved in the transfer, packaging, and t ransport of radioactive material . Maintain a record of t raining dates, attendees, and subject material for future inspections by NRC personnel. |
| 10 CFR 50, Appendix B criteria was marginally evaluated. The i
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| , licensee stated that subsequent audits would ensure Radwaste Shipping | |
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| activities would be audited against the applicable criteria. This ;
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| area will be reviewed during a future inspection (219/85-25-04). :
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| i j 7.0 Selection of Packages l
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| The licensee's program for selection of packages was examined against the ;
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| requirements of 10 CFR 71.87 and within the framework of the DOT require- i ments of 49 CFR Part 17 ;
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| For dry radioactive waste, the licensee used steel boxes or strong tight !
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| containers. Radioactive material shipments requiring the use of an NRC ;
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| Certified package (outer ccatainer) were made predominantly in. vendor l supplied containers.
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| ] Within the scope of this review, the following issues were identified: I l
| | Response Training and periodic retraining in the DOT and NRC regulatory requirements are presently provided to Radwaste Operators, Rad Con Technicians, Station Services, and Radwaste Shipping Supervisors. |
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| | The present Operations t raining program provides training and retraining on minimizing radioactive waste by those processes which |
| The inspector observed an NRC approved package (Certificate of Compli- i ance (C of C 9094) labeled as model 14-195 and 00T-7A. The C of C i i | | > generate wastes. A training program is administered for radwaste facility operators which covers Radwaste Operations including transfer, packaging, and shipping of radioactive material in the DOT, NRC, and waste burial requirements thereto. Personnel packaging DAW are bargaining unit personnel who are trained in the operations of the packaging as well as transfer and storage procedures. They are under the direct supervision of the Radwaste Shipping Supervisors who are training in all applicable regulatory criteria. |
| specifies Model number 14-195 as an approved package. However, the l 00T-7A. labeling is not permitted by C of C 9094, because it implies l l NRC approva ;
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| .. - . .- _ - - . - .- . - ... . ~ _ . - .- - | | Item 6 Provide t raining and periodic ret raini ng to Radwaste Operators who operate the processes which generate waste to assure that the volume |
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| | processed into acceptable chemical and physical fom for transfer and shipment to a low-level radioactive waste burial facility. |
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| : * The inspector noted that the licensee had made radioactive waste i shipment in an approved package (Certificate of Compliance 9079),
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| ! but was shipped as package model 14-170. Model 14-170 currently
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| ! is not approved by C of C 9079.
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| The licensee stated they would discuss these labeling conflicts with their vendor. The inspector stated these issues would be considered unresolved (219/85-25-05).
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| | Revised Response to NRC I6E Page 3 |
| | * Bulletin 79-19 Response See response to Item 5. |
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| ' | | Establish and implement a management-controlled andit function of all transfer, packaging, and transport activities to provide assurance that personnel, instructions and procedures, and process and transport equipment are functioning to ensure safety and compliance with regulatory recuirements. |
| Except as noted above, copies of the Certificate.of Compliance, including the drawings were available for all Type A and Type B l Casks in us .0 Shipment of Licensed Material for Disposal or Use The transportation of licensed material was reviewed against the criteria contained in 10 CFR 71, " Packaging and Transportation of Radioactive
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| Material," 10 CFR 20.311(d)(3), " Transfer for disposal and manifests," and 10 CFR 61.55, " Waste Classification," and 10 CFR 61.56, " Waste Character- 1 istics."
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| | Response A management-controlled audit function for the transfer, packaging, and transport of radioactive materials has been established and has been implemented. This function is provided by the Quality Assurance Department through the QA program development and audit sections. |
| The licensee's performance relative to these criteria was determined by
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| discussion with the Radwaste Shipping Supervisor and his staff;
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| - review of shipping manifests and related documents; and
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| review of selected program procedures including the following:
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| 101.3, Revision 12, " Shipment of Radioactive Materials."
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| | Item 8 Perform, within 60 days of the date of this bulletin, a management-controlled audit of your activities associated with the t ransfer, packaging, and transport of low-level radioactive waste. |
| 351.2, Revision 3, " Absorbing of Low-Level Radioactive Waste Oil for Off-Site Disposal."
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| 351.37, Revision 1, "Radwaste Processing of Solids and Liquid to the CNSI Cement Solidification System."
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| | Maintain a record of all audits for future inspections by NRC or DOT inspections. (Note: If you have an established audit function arx! |
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| | have performed such an audit of all activities in items 1-6 within the past six months, this audit requirement is satisfied.) |
| 352.0, Revision 4, " Processing Resins at the large Container l Filling Station Into a CNSI Enviro Safe High Integrity
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| Container."
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| t I Within the scope of this review, no violations were identified.
| | Response A management controlled audit of Radwaste Operations was conducted on March 7, 1979 (Audit No. 79-04) and have been conducted on an annual basis since the issuance of the 16E bulletin. In addition to annual audits conducted by the QC QA site audit section, routine inspections / monitoring of regular waste shipments are conducted by Operations QA monitors. |
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| l
| | ' . |
| | . |
| | ,s- . |
| | .. |
| | . |
| | Revised Response to NPC I6E Page 4 |
| | * |
| | Bulletin 79-19 Item 9 Provide answers for 1978 and for the first six months of 1979 to the following questions: |
| | 1. How many low-level radioactive waste shipments did you make? |
| | What was the volume of low-level radioactive waste shipped? |
| | (Power reactor licensees who _ report this information in accordance with Technical Specifications do not need to respond to this question.) |
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| |
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| 9.0 Low-Level Radioactive Waste Storage Facility
| | 2. What was the quantity (curies) of low-level radioactive waste shipped? What were the major isotopes in the low-level radioactive waste? |
| )^ | | (Power reactor licensees who report this information in accordance with Technical Specifications do not need to respond to this question.) |
| The licensee has started construction of a Low-Level Radioactive Waste Storage Facility at the Oyster Creek Site. Projected completion is March
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| 1986. The licensee estimated that 50% has' been completed as of July 31, 198 The Safety Evaluation Report is currently in draft.
| | 3. Did you generate liquid low-level radioactive waste? If the answer is "yes", what process was used to solidify the liquid waste? |
| | Response 1. Reported in Semiannual Reports for the years since 1978, |
| | " Radioactive Effluent Releases." |
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| i
| | 2. Same as No. I above. |
| !
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| I i
| |
| . | |
| ~,-e- ,-a .w--n- ,a --
| |
| -r--- --+ - --,n-8-- -- , , - - . - , - , , - ,.-a-na+er,--n-r--, ,.----.m,--,-----..-~ -.
| |
| -w ,~~ w,.r.,,- .. , nw - .w m n. , ,
| |
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| |
|
| .-
| | 3. Liauld low-level radioactive waste is generated. A process using line and cement is presently used to solidify filter sludge and evaporator bottoms. |
| *
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| . | |
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| 10.0 Exit The inspector met with the Itcensee representatives (denoted in Paragraph 1) at the conclusion of the inspection on August 1, 1985. The inspector summarized the scope of the inspection and finding _
| | 1950W/4 |
| }} | | }} |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217J3341999-10-19019 October 1999 Forwards Request for Addl Info Re Sale of Portion of Land Part of Oyster Creek Nuclear Generating Station Site Including Portion of Exclusion Area ML20217E0181999-10-0606 October 1999 Provides Nj Dept of Environ Protection Comments on Oyster Creek Nuclear Generating Station TS Change Request 267 Re Clarifications to Several TS Sections ML20216J7591999-09-30030 September 1999 Informs NRC That Remediation Efforts for Software Sys Etude & Rem/Aacs/Cico Have Been Completed According to Schedule & Now Y2K Ready 05000219/LER-1998-011, Forwards LER 98-011-02, Three Small Bore Pipe Lines Did Not Meet Design Bases for Siesmic & Thermal Allowables. Engineering Std Will Not Be Completed Until End of 4th Quarter of 1999 Due to Scheduling Conflicts1999-09-30030 September 1999 Forwards LER 98-011-02, Three Small Bore Pipe Lines Did Not Meet Design Bases for Siesmic & Thermal Allowables. Engineering Std Will Not Be Completed Until End of 4th Quarter of 1999 Due to Scheduling Conflicts ML20212J6721999-09-30030 September 1999 Informs of Completion of mid-cycle PPR of Oyster Creek Nuclear Generating Station on 990913.No Areas Identified in Which Licensee Performance Warranted Addl Insp Beyond Core Insp Program.Historical Listing of Plant Issues Encl ML20216K1421999-09-29029 September 1999 Provides NRC with Name of Single Point of Contact for Purpose of Accessing Y2K Early Warning Sys,As Requested by NRC Info Notice 99-025 ML20217D1661999-09-27027 September 1999 Forwards Proprietary Completed NRC Forms 396 & 398,in Support of License Renewal Applications for Listed Individuals,Per 10CFR55.57.Encl Withheld ML20217B2531999-09-24024 September 1999 Informs That on 980903,Region I Field Ofc of NRC Ofc of Investigations Initiated Investigation to Determine Whether Crane Operator Qualification/Training Records Had Been Falsified at Oyster Creek Nuclear Generating Station ML20212E1971999-09-16016 September 1999 Forwards Rev 11 of Gpu Nuclear Operational QAP, Reflecting Organizational Change in Which Functions & Responsibilities of Nuclear Safety & Technical Support Div Were Assigned to Other Divisions ML20212A7921999-09-13013 September 1999 Forwards Second RAI Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, Issued on 950817 to Plant ML20212B5571999-09-10010 September 1999 Forwards Rev 11 to Oyster Creek Emergency Dose Calculation Manual, IAW 10CFR50,App E,Section V ML20211N2941999-09-0303 September 1999 Responds to NRC 990802 Telcon Request for Environ Impact Assessment of TS Change Request 251 Concerning Movement of Loads Up to 45 Tons with RB Crane During Power Operations ML20211J9831999-09-0202 September 1999 Discusses 990804 Telcon Re Sale of Portion of Oyster Creek Nuclear Generating Station Land.Requests Info Re Location of All Areas within Property to Be Released Where Licensed Radioactive Matl Present & Disposition of Radioactive Matl ML20211J6771999-08-30030 August 1999 Submits Response to NRC 990802 Telcon Request for Gpu to Provide Environ Impact Assessment for Tscr 251 ML20211K2391999-08-23023 August 1999 Forwards fitness-for-duty Performance Data Repts for TMI, Oyster Creek & Corporate Headquarters Located in Parsippany, Nj ML20211C0161999-08-19019 August 1999 Advises That Info Submitted by Ltr,Dtd 990618, Licensing Rept for Storage Capacity Expansion of Oyster Creek Spent Fuel Pool, Holtec Rept HI-981983,rev 4,will Be Withheld from Public Disclosure,Per 10CFR2.790 ML20211B9011999-08-18018 August 1999 Forwards Rev 0 to EPIP 1820-IMP-1720.01, Emergency Public Info Implementing Procedure ML20210U4341999-08-17017 August 1999 Responds to to Chairman Dicus of NRC on Behalf of Fm Massari Concern About Oyster Creek Nuclear Generating Station Not Yet Being Fully Y2K Compliant ML20210Q7331999-08-12012 August 1999 Responds to Re TS Change Request (TSCR)264 from Oyster Creek Nuclear Generating Station.Questions Re Proposed Sale of Property within Site Boundary & Exclusion Area ML20210L6311999-08-0606 August 1999 Discusses Licensee Response to GL 92-01,Rev1,Suppl 1, Rv Structural Integrity, for Plant.Staff Has Revised Info in Rv Integrity Database & Releasing as Rvid Version 2 ML20210D2801999-07-22022 July 1999 Submits Response to Administrative Ltr 99-02 Operating Reactor Licensing Action Estimates. Estimate of Licensing Actions Projected for Fy 2000 Encl.No Projection Provided for Fy 2001 ML20209H5001999-07-14014 July 1999 Forwards Revised TS Pages 3.1-15 & 3.1-17 Which Include Ref to Note (Aa) & Approved Wording of Note H of Table 3.1.1, Respectively ML20210U4411999-07-12012 July 1999 Forwards Article from Asbury Park Press of 990708 Faxed to Legislative Officer by Mutual Constitute Fm Massari Indicating That Oyster Creek Nuclear Generating State Not Fully Y2K Compliant ML20209G1451999-07-0909 July 1999 Forwards Rev 1 to 2000-PLN-1300.01, Oyster Creek Generating Station Emergency Plan. Attachment 1 Contains Brief Summary of Changes,Which Became Effective on 990702 ML20209E0821999-07-0707 July 1999 Forwards TS Change Request 269 for License DPR-16,changing Component Surveillance Frequencies to Indicate Frequency of Once Per Three Months ML20209B7501999-07-0101 July 1999 Responds to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants.Generic Ltr 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Licensee Y2K Readiness Disclosure for Ocngs,Encl ML20196G1361999-06-23023 June 1999 Provides Status of Corrective Actions Proposed in in Response to Insp Rept 50-219/98-80 & Revised Schedule for Completion of Actions Which Are Not Yet Complete ML20196E6421999-06-22022 June 1999 Forwards Revised Pages of TS Change Request 261,dtd 990618. Replacement Requested Due to Several Dates Being Omitted on Certain Pages ML20195G6541999-06-0707 June 1999 Discusses 981204 Initiation to Investigate Whether Contract Valve Technician,Was Discriminated Against for Raising Concern Re Use of Untrained/Unqualified Workers Performing Valve Repairs.Technician Was Not Discriminated Against ML20195G6631999-06-0707 June 1999 Discusses 981204 Intiation to Investigate Whether Contract Valve Technician Was Discriminated Against for Raising Concern Re Use of Untrained/Unqualified Workers Performing Valve Repairs.Technician Was Not Discriminated Against ML20209B0561999-06-0404 June 1999 Informs That NRR Has Reorganized,Effective 990328.Forwards Organizational Chart ML20195D0551999-06-0303 June 1999 Forwards TS Change Request 226 to License DPR-16,permitting Operation with Three Recirculation Loops.Certificate of Svc & Tss,Encl ML20195C5511999-05-25025 May 1999 Forwards Book of Controlled Drawings Currently Ref But Not Contained in Plant Ufsar.Drawings Were Current at Time of Submittal ML20206N7711999-05-11011 May 1999 Forwards Rev 0 to Oyster Creek Emergency Plan, IAW 10CFR50.47(b) & 10CFR50.54(q).Changes Became Effective on 990413 ML20206H9441999-04-28028 April 1999 Forwards Application for Amend to License DPR-16,requesting Approval to Handle Loads Up to & Including 45 Tons Using Reactor Bldg Crane During Power Operations,Per NRC Bulletin 96-002 ML20206B6991999-04-26026 April 1999 Forwards Copy of Rev 11 to UFSAR & Rev 10 to Oyster Creek Fire Hazards Analysis Rept. Without Fire Hazard Analysis ML20206D3801999-04-26026 April 1999 Forwards Rev 11 to UFSAR, & Rev 10 to Fire Hazards Analysis Rept, for Oyster Creek Nuclear Generating Station, Per 10CFR50.712(e) ML20206A9931999-04-22022 April 1999 Forwards Number of Personnel & Person Rems by Work & Job Function Rept for Period Jan-Dec 1998. Included in Rept Is Listing of Number of Station,Util & Contractor Personnel as Well as Diskette Reporting 1998 Occupational Radiation ML20206C8261999-04-22022 April 1999 Submits Financial Info IAW Requirements of 10CFR50.71(b) & 10CFR140.21 ML20205P8411999-04-15015 April 1999 Forwards TS Change Request 267 to License DPR-16,modifying Items in Sections 2 & 3 of Ts,Expanding Two Definitions in Section 1 & Modifying Bases Statements in Sections 2,3 & 4. Certificate of Svc Encl ML20205P5381999-04-14014 April 1999 Ack Receipt of Re Request for Exception to App J. Intended Correction Would Need to Be Submitted as Change to TS as Exceptions to RG 1.163 Must Be Listed in Ts,Per 10CFR50,App J ML20205P9401999-04-12012 April 1999 Informs NRC That Gpu Nuclear Is Modifying Oyster Creek FSAR to Reflect Temp Gradient of 60 F & to Correct Historical Record ML20205P0651999-04-0909 April 1999 Discusses 990225 PPR & Forwards Plant Issues Matrix & Insp Plan.Results of PPR Used by NRC Mgt to Facilitate Planning & Allocation of Insp Resources 05000219/LER-1998-015, Forwards LER 98-015-01,as Original Submittal on 981028 Inadvertently Indicated That Suppl Would Be Submitted.Suppl Should Not Have Been Required as Only Change Is on Cover Page1999-04-0505 April 1999 Forwards LER 98-015-01,as Original Submittal on 981028 Inadvertently Indicated That Suppl Would Be Submitted.Suppl Should Not Have Been Required as Only Change Is on Cover Page ML20205J3281999-04-0101 April 1999 Discusses Arrangements Made on 990323 for NRC to Inspect Licensed Operator Requalification Program at Oyster Creek Nuclear Generating Station During Week of 990524 ML20205H1081999-03-31031 March 1999 Forwards Current Funding Status for Decommissioning Funds Established for OCNPP,TMI-1,TMI-2 & SNEC ML20205F0611999-03-25025 March 1999 Submits Info on Sources & Levels of Property Insurance Coverage Maintained & Currently in Effect for Oyster Creek Nuclear Generating Station,Iaw 10CFR50.54(w)(3) ML20205E1171999-03-24024 March 1999 Forwards Rev 39 to Oyster Creek Security Plan & Summary of Changes,Iaw 10CFR50.54(p).Rev Withheld ML20207F0331999-03-0404 March 1999 Forwards Insp Rept 50-219/98-12 During Periods 981214-18, 990106-07 & 20-22.Areas Examined During Insp Included Implementation of GL 89-10 & GL 96-05.No Violations Noted ML20207K2471999-02-25025 February 1999 Forwards Fitness for Duty Performance Data Repts for TMI, Oyster Creek & Corporate Headquarters Located in Parsippany, Ny 1999-09-30
[Table view] Category:NRC TO UTILITY
MONTHYEARML20058H9421990-11-16016 November 1990 Forwards List of Unimplemented Generic Safety Issues at Facility,Per Generic Ltr 90-04 ML20058J0451990-11-0909 November 1990 Forwards Insp Rept 50-219/90-20 on 901022-26.No Violations Noted.Review of Preparations for Drywell Occupancy During Fuel Movement Identified Areas of Concern ML20058C7291990-10-24024 October 1990 Discusses Insp Rept 50-219/90-80 on 900625 & 29 & Forwards Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $50,000.Violation Considered Severity Level III & Involved Unqualified Operators at Reactor Controls IR 05000219/19890811990-10-18018 October 1990 Ack Receipt of Informing NRC of Actions Taken to Correct Violations Noted in AIT Insp Rept 50-219/89-81 Re RPS Low Vacuum Setting ML20058A8241990-10-18018 October 1990 Forwards Safety Insp Rept 50-219/90-16 on 900823-0922 & Notice of Violation ML20058A6381990-10-18018 October 1990 Forwards SE Conditionally Accepting Util Insp & Repairs for Igscc,Per Generic Ltr 88-01 ML20058A6601990-10-16016 October 1990 Forwards Request for Addl Info Re Drywell Corrosion Program, Including Sampling of Shell Surfaces for UT Measurements ML20062B8641990-10-12012 October 1990 Extends Invitation to Attend 910220-21 Util Symposium/ Workshop in King of Prussia,Pa Re Engineering Role in Plant Support ML20062A6871990-10-11011 October 1990 Documents Review of Util 900921 Integrated Schedule ABC List Update.Listed Projects Acceptable Except for Items B/A-328 ADA & B/A-402946 ML20058F3211990-10-0303 October 1990 Forwards Safety Insp Rept 50-219/90-17 on 900918-21.No Violations Noted.Schedule for Identification & Disposal of Contents of Tanks in Old Radwaste Bldg Requested within 45 Days of Ltr Date IR 05000219/19900091990-10-0101 October 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-219/90-09 ML20059M5201990-09-21021 September 1990 Forwards Safeguards Insp Rept 50-219/90-15 on 900820-24.No Violations Noted ML20059J8021990-09-11011 September 1990 Advises That Util 900621 Response to Open Item Re USI A-46 & Schedule,Acceptable.Requests That Util Confirm Seismic Adequacy of CRD Hydraulic Control Units within 30 Days of Completion of Walkdown ML20059H3291990-09-0606 September 1990 Advises That 900831 Commitment to Install Hardened Wetwell Vent at Plant Acceptable ML20059G3911990-09-0505 September 1990 Recognizes Efforts of G Bond & W Douglas Re Implementation of Emergency Response Data Sys (ERDS) Link at Facility. ERDS Link at Facility Operational & Should Be Implemented in Emergency Response Planning ML20058Q4361990-08-15015 August 1990 Forwards Safety Insp Rept 50-219/90-11 on 900610-0711. Unresolved Item Noted ML20058P0801990-08-0909 August 1990 Forwards Requalification Program Evaluation Rept 50-219/90-05OL on 900409-0608.Util Should Respond within 30 Days of Receipt of Ltr Confirming Corrective Actions Committed to During 900424 Interim Exit Meeting ML20058M3581990-08-0808 August 1990 Requests Addl Info Listed in Encl Re Util 900521 & 0720 Responses to NRC Bulletin 90-002, Loss of Thermal Margin Caused by Channel Box Bow. Info Requested within 10 Days of Receipt of Ltr ML20058N0771990-08-0606 August 1990 Discusses Licensee Engineering Initiatives.Encourages Initiation of Initiative Similar to Region V Licensees Establishment of Engineering Managers Forum to Share Experiences ML20056A6071990-07-20020 July 1990 Forwards Insp Rept 50-219/90-09 on 900422-0609 & Notice of Violation.Util Should Identify & Correct Any Programmatic Weaknesses Re Failure to Perform Adequate Radiation Surveys ML20055G4141990-07-11011 July 1990 Requests Util Provide Ref Matls Listed in Encl for Senior Reactor Operator Licensing & Requalification Exams Scheduled for 901015 ML20058K5061990-06-28028 June 1990 Forwards Supplemental Safety Evaluation for Plant Dcrdr. NRC Concludes That Licensee Submittal Meets NUREG-0737, Suppl 1 Dcrdr Requirements & Therefore,Issue Considered Resolved ML20055E3021990-06-15015 June 1990 Forwards Backfit Analyses for Plant Re Installation of Hardened Wetwell Vent,Per Generic Ltr 89-16 ML20059M8321990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20055C3171990-02-16016 February 1990 Forwards Safety Insp Rept 50-219/89-29 on 891203-900106 & Ack Receipt of 900115 & 19 Responses to Insp Repts 50-219/89-21 & 50-219/89-27 ML20248B5511989-09-27027 September 1989 Informs of Correction to NRC Re Util Response to Generic Ltr 88-11 IR 05000219/19890031989-09-22022 September 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-219/89-03 NUREG-1382, Forwards Draft NUREG-1382, SER Re Full-Term Operating License for Oyster Creek Nuclear Generating Station, for Review1989-09-20020 September 1989 Forwards Draft NUREG-1382, SER Re Full-Term Operating License for Oyster Creek Nuclear Generating Station, for Review ML20247K4491989-09-14014 September 1989 Forwards Insp Rept 50-219/89-18 on 890724-28.No Violations Noted IR 05000219/19890051989-09-14014 September 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-219/89-05 ML20247K9771989-09-12012 September 1989 Forwards Safety Insp Rept 50-219/89-20 on 890829-30.No Violations Noted ML20247H7201989-09-0808 September 1989 Forwards Corrected SALP Rept 50-219/87-99 for Oct 1987 - Jan 1989 ML20246M7261989-08-30030 August 1989 Forwards Safety Evaluation Accepting Licensee 890624 Response to Integrated Plant Safety Assessment Section 4.11, Seismic Design Consideration, Items 4.11(1), Piping Sys & 4.11(3), Electrical Equipment ML20246J5961989-08-24024 August 1989 Forwards Safety Insp Rept 50-219/89-16 on 890702-29 & Notice of Violation.Attention Required to Ensure Engineering Evaluations of Potential Safety Problems Performed ML20246G1641989-08-21021 August 1989 Forwards SALP Final Rept 50-219/87-99 on Oct 1987 - Jan 1989 ML20246H5751989-08-18018 August 1989 Clarifies NRC Position Re Definition of Extremity for Purposes of Setting Occupational Exposure Limits & Requests to Ensure That Licensee Procedures Incorporate Applicable Dose Limits of 10CFR20 ML20246C3671989-08-15015 August 1989 Forwards Safety Insp Rept 50-219/89-19 on 890802-04.No Violations or Deviations Noted ML20247K0981989-08-15015 August 1989 Requests That Licensee Take Listed Actions Re Upgrade of Pipe Supports & Anchorages to Meet IE Bulletin 79-02 & 79-14 Requirements Using New Response Floor Spectra for Plant. Response Re Compliance Requested within 30 Days ML20246B0561989-08-14014 August 1989 Forwards Safety Insp Rept 50-219/89-15 on 890627-30.No Violations Noted.Items of Concern Noted in Area of Appointments to Technical & Supervisory Positions & Training Programs to Maintain & Upgrade Personnel Qualifications ML20245G1091989-08-10010 August 1989 Advises That Licensee 890726 Response to Generic Ltr 88-11, NRC Position on Embrittlement of Reactor Vessel Matls & Impact on Plant Operations, Acceptable ML20245G4931989-08-10010 August 1989 Advises That Util 890719 Response to Generic Ltr 89-08 Re Implementation of long-term Erosion/Corrosion Monitoring Program Meets Intent of NUMARC Program.Records & Results from Implementation Should Be Maintained ML20245L1971989-08-0808 August 1989 Forwards Safety Insp Rept 50-219/89-14 on 890604-0701.No Violations Noted.Insp Focused on Open Items Over 3 Yrs Old, Including Response to SALP Rept 50-219/85-99 ML20247P9641989-07-31031 July 1989 Advises That Category ABC List of Projects in Semiannual Update for 6 Months Since 881202 Considered in Compliance W/ Approved long-range Planning Program & Acceptable ML20247M4251989-07-26026 July 1989 Confirms Telcon on 890718 W/M Laggart & Eh Gray Re SSFI to Be Conducted at Facility During Wk of 890814-28.Insp to Focus on Design,Operation & Maint of Emergency Svc Water Sys.Background Info Requested by 890807 ML20245F6211989-07-26026 July 1989 Requests Util Provide Ref Matls Listed in Encl for Reactor Operator & Senior Operator Exams Scheduled for Wks of 891009 & 16,by 890905.Delay in Receiving Ref Matl May Result in Exam Being Rescheduled ML20247N1091989-07-25025 July 1989 Forwards Safety Insp Rept 50-219/89-11 on 890606-08.Due to Similarities Between 890524 Dress Rehearsal & 0607 Exercise, Exercise Does Not Qualify as Required Annual Test of Emergency Plan Since Same Staff Used & Scenario Known ML20247L7321989-07-25025 July 1989 Forwards Safety Insp Rept 50-219/89-12 on 890430-0603 & Notice of Violation IR 05000219/19880381989-07-24024 July 1989 Discusses Safety Insp Rept 50-219/88-38 on 881204-890114 & Forwards Notice of Violation.Violation Classified as Severity Level IV Since Unauthorized Entry Occurred as Result of Isolated Lapse in Vigilance by Security Officer ML20247A6731989-07-17017 July 1989 Forwards Safety Evaluation Accepting Licensee Response to Generic Ltr 83-28,Item 4.5.2 Re Reactor Trip Sys Reliability on-line Testing ML20246L6291989-07-11011 July 1989 Ack Receipt of Forwarding Payment of Civil Penalty in Amount of $50,000 Proposed in NRC 1990-09-06
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217J3341999-10-19019 October 1999 Forwards Request for Addl Info Re Sale of Portion of Land Part of Oyster Creek Nuclear Generating Station Site Including Portion of Exclusion Area ML20212J6721999-09-30030 September 1999 Informs of Completion of mid-cycle PPR of Oyster Creek Nuclear Generating Station on 990913.No Areas Identified in Which Licensee Performance Warranted Addl Insp Beyond Core Insp Program.Historical Listing of Plant Issues Encl ML20217B2531999-09-24024 September 1999 Informs That on 980903,Region I Field Ofc of NRC Ofc of Investigations Initiated Investigation to Determine Whether Crane Operator Qualification/Training Records Had Been Falsified at Oyster Creek Nuclear Generating Station ML20212A7921999-09-13013 September 1999 Forwards Second RAI Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, Issued on 950817 to Plant ML20211J9831999-09-0202 September 1999 Discusses 990804 Telcon Re Sale of Portion of Oyster Creek Nuclear Generating Station Land.Requests Info Re Location of All Areas within Property to Be Released Where Licensed Radioactive Matl Present & Disposition of Radioactive Matl ML20211C0161999-08-19019 August 1999 Advises That Info Submitted by Ltr,Dtd 990618, Licensing Rept for Storage Capacity Expansion of Oyster Creek Spent Fuel Pool, Holtec Rept HI-981983,rev 4,will Be Withheld from Public Disclosure,Per 10CFR2.790 ML20210U4341999-08-17017 August 1999 Responds to to Chairman Dicus of NRC on Behalf of Fm Massari Concern About Oyster Creek Nuclear Generating Station Not Yet Being Fully Y2K Compliant ML20210Q7331999-08-12012 August 1999 Responds to Re TS Change Request (TSCR)264 from Oyster Creek Nuclear Generating Station.Questions Re Proposed Sale of Property within Site Boundary & Exclusion Area ML20210L6311999-08-0606 August 1999 Discusses Licensee Response to GL 92-01,Rev1,Suppl 1, Rv Structural Integrity, for Plant.Staff Has Revised Info in Rv Integrity Database & Releasing as Rvid Version 2 ML20195G6541999-06-0707 June 1999 Discusses 981204 Initiation to Investigate Whether Contract Valve Technician,Was Discriminated Against for Raising Concern Re Use of Untrained/Unqualified Workers Performing Valve Repairs.Technician Was Not Discriminated Against ML20195G6631999-06-0707 June 1999 Discusses 981204 Intiation to Investigate Whether Contract Valve Technician Was Discriminated Against for Raising Concern Re Use of Untrained/Unqualified Workers Performing Valve Repairs.Technician Was Not Discriminated Against ML20209B0561999-06-0404 June 1999 Informs That NRR Has Reorganized,Effective 990328.Forwards Organizational Chart ML20205P5381999-04-14014 April 1999 Ack Receipt of Re Request for Exception to App J. Intended Correction Would Need to Be Submitted as Change to TS as Exceptions to RG 1.163 Must Be Listed in Ts,Per 10CFR50,App J ML20205P0651999-04-0909 April 1999 Discusses 990225 PPR & Forwards Plant Issues Matrix & Insp Plan.Results of PPR Used by NRC Mgt to Facilitate Planning & Allocation of Insp Resources ML20205J3281999-04-0101 April 1999 Discusses Arrangements Made on 990323 for NRC to Inspect Licensed Operator Requalification Program at Oyster Creek Nuclear Generating Station During Week of 990524 ML20207F0331999-03-0404 March 1999 Forwards Insp Rept 50-219/98-12 During Periods 981214-18, 990106-07 & 20-22.Areas Examined During Insp Included Implementation of GL 89-10 & GL 96-05.No Violations Noted ML20206U3551999-02-0505 February 1999 Refers to Concerns Recipient Expressed to V Dricks on 990126 Related to Oyster Creek About Event Which Occurred on 970801 & About Administrative Control of EDG Vendor Manuals ML20199L2471999-01-22022 January 1999 Discusses GL 96-01, Testing of Safety-Related Logic Circuits, Issued on 960110 & Gpu Nuclear 960418 & 981202 Responses for Ocngs.Informs That Based on Confirming GL 96-01 Commitments Review Effort Closed ML20199G8241999-01-12012 January 1999 Responds to Ltr to Senator Lt Connors, Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20199G8631999-01-0707 January 1999 Responds to Ltr to Senator Lt Connors, Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20198B2121998-12-0909 December 1998 Advises of Planned Insp Efforts Resulting from Licensee Irpm Review.Historical Listing of Plant Issues & Details of Insp Plan for Next 6 Months Encl ML20196C6001998-11-25025 November 1998 Forwards Insp Rept 50-219/98-09 on 980914-1025 & Notice of Violation.Inspector Identified That Security Force Member Left Running Unlocked Vehicle Unattended in Protected Area ML20195G8901998-11-17017 November 1998 Responds to to Lt Connors Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20195G9101998-11-17017 November 1998 Responds to to Lt Connors Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20195G8801998-11-17017 November 1998 Responds to to Senator Lt Conners Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20195G9181998-11-17017 November 1998 Responds to to Lt Connors Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community IR 05000219/19980031998-11-13013 November 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-219/98-03 Issued on 980717.Corrective Actions Will Be Examined During Future Insp of Licensed Program ML20196D1431998-11-10010 November 1998 Forwards Exam Forms with Answers,Results Summary for Plant & Individual Answer Sheets of GFE Section of Written Operator Licensing Exam,Administered on 981007.Without Encl ML20195C4111998-11-0606 November 1998 Discusses 980825 Gpu Submittal of Proposed Mod for Ocnpp Core Support Plate Which Involved Installation of Wedges During 17R Outage.Licensee Intends to Use Recommendations of BWRVIP-25 & BWRVIP-50.SE Accepting Proposed Mod Encl ML20195B7981998-11-0505 November 1998 Discusses Alternative Evaluation of Flaws in Ferritic Piping.Core Spray Sys Test Line Was Concluded to Have Acceptable Level of Quality & Safety ML20155C6881998-10-29029 October 1998 Responds to Ltr to Senator Connors, Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20155C7201998-10-29029 October 1998 Responds to Ltr to Assemblyman Connors, Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20155C7051998-10-29029 October 1998 Responds to Ltr to Senator Connors, Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20155C7481998-10-29029 October 1998 Responds to Ltr to Assemblyman Morgan, Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20155C6241998-10-29029 October 1998 Responds to Ltr to Senator Connors,Dtd 980926,re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20155C7021998-10-29029 October 1998 Responds to Ltr to Senator Connors, Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20155C6661998-10-29029 October 1998 Responds to Ltr to Senator Connors, Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20155C6841998-10-29029 October 1998 Responds to Ltr to Senator Connors, Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20155C6721998-10-29029 October 1998 Responds to Ltr to Senator Connors, Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20155C7251998-10-29029 October 1998 Responds to Ltr to Senator Connors, Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20155C7371998-10-29029 October 1998 Responds to Ltr to Senator Connors, Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20155C6981998-10-29029 October 1998 Responds to Recent Ltr to Senator Connors Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20155C6481998-10-29029 October 1998 Responds to Ltr to Sentor Connors, Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20155C7091998-10-29029 October 1998 Responds to Ltr to Assemblyman Connors, Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20155C8781998-10-29029 October 1998 Informs That Oyster Creek Generating Station Operating License,Paragraph 2.C.5 Re Evaluation of Core Spray Internals Insp Requires Authorization from NRC Before Plant Is Restarted from Refueling Outage.Plant Restart Authorized ML20155C7301998-10-29029 October 1998 Responds to Ltr to 9th District Legislative Offices, Re Possible Closure of Oyster Creek Nuclear Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20155D2041998-10-26026 October 1998 Forwards Synopsis of 980604 Investigation Rept 1-98-027 Re Possible Discrimination Against Employee for Contacting NRC in Nov 1997 with Security & Safety Concerns ML20154Q9021998-10-20020 October 1998 Forwards Insp Rept 50-219/98-08 on 980727-0913.No Violations Noted.Licensee Have Established & Implemented Effective Programs for Initial & Continuing Training of Workers, Especially Those Having Access to Controlled Areas ML20154L3001998-10-14014 October 1998 Forwards Safety Evaluation Re Reduced Scope of IGSCC Insp, During Refueling Outage 17 ML20154J8251998-10-0707 October 1998 Discusses Concerns Raised to NRC on 980913 Re Oyster Creek. Thoroughness of NRC Insps as Documented in NRC Integrated Insp Rept 50-219/98-03 Was of Concern 1999-09-30
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MAY n 11986 Docket No. 50-219 GPU Nuclear Corporation ATTN: Mr. P. B. Fiedler Vice President and Director Oyster Creek Nuclear Generating Station P. O. Box 388 Forked River, NJ 08731 Gentlemen:
Subject: Inspection No. 85-25 We acknowledge receipt of your letter dated April 10, 1986, in response to our letter dated September 11, 1985.
Thank you for informing us of the corrective and preventive actions documented in your letter. These actions will be examined during a future inspection of your licensed program.
Your cooperation with us is appreciated.
Sincerely,
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h .as) . Mar n, irect Ok Division of Radiation fety and Safeguards cc:
M. Laggart, BWR Licensing Manager Licensing Manager, Oyster Creek Public Document Room (PDR)
Local Public Document Room (LPOR)
Nuclear Safety Information Center (NSIC)
NRC Resident Inspector State of New Jersey C
G 0FFICIAL RECORD COPY RL OYC 85-25 - 0001.0.0 '
04/24/86 -
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GPU Nuclear Corporation 2 bcc:
Region I Docket Room (with concurrences)
Management Assistant, DRMA Section Chief, DRP R SS RI S RI:DRSS MMiller/ms PascFak Bellamy 4/21/86 4/$b/86 f/ \ /86 0FFICIAL RECORD COPY RL OYC 85-25 - 0002.0.0 04/24/86 I
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OPU Nuclear Corporstkm
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NggIg{ Post Office Box 388 Route 9 South Forked River, New Jetsey 08731-0388 l
609 971 4000 Writer's Direct Dial Number:
April 10, 1986 Dr. Thomas E. Murley, Administrator Region I U.S. Nuclear Regulatory Comission 631 Park Avenue King of Prussia, PA 19406
Dear Dr. Marley:
Subject: Oyster Creek Nuclear Generating Station Docket No. 50-219 IE Inspection 85-25 dated September 11, 1985 As suggested by the subject inspection report, Attachment I of this letter updates our September 24, 1979 response to I&E Bulletin 79-19,
" Packaging of Low-Level Radioactive Waste for Transport and Burial".
As you are aware, since our original response to I&E Bulletin 79-19, an organizational change altered the department responsible for the radwaste packaging and shipping functions. Previously the responsibility was under the direction and control of the Radiation Protection Department. The present shipping organization is under the control and direction of the Manager of Radwaste Operations. Thus, the commitment to I&E Bulletin 79-19 Item 5 is being revised to reflect current training programs. We understand that this item will be reviewed during a subsequent inspection.
Should you require any further information, please contact Brenda Honman, Oyster Creek Licensing Engineer at (609)917-4642.
Very truly yours, P
Yice President and Director Oyster Creek PBF/BH/ dam (0103A)
Attacnment cc: Mr. Jack N. Donohew, Jr.
- U.S. Nuclear Regulatory Comission 7920 Norfolk Avenue, Phillips Bldg.
Bethesda, MD 20014 ,N,r&j~1 ~3<n/ D
Mail Stop No. 314 NRC Resident Inspector 0/ ster Creek Nuclear Generating Station GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation
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r ATTACHMENT I
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' Revised Response to NRC 16E Bulletin 79-19 i
Item 1 Maintain a current set of DOT and NRC regulations concerning the transfer, packaging, and t ransport of low-level radioactive waste material .
Response A current set of Department of Transportation (49 CFR) and Nuclear Regulatory Commission (10 CFR) regulations concerning the transfer, packaging, and transport of low-level radioactive waste material is maintained at the Oyster Creek Station in the Radwaste Shipping Department.
Item 2 Maintain a current set of requirements (license) placed on the waste burial firm by the Agreement State of Nevada, South Carolina, or Washington before packaging low-level radioactive waste material for transfer and shipment to the Agreement State licensee. If a waste collection contractor is used, obtain the appropriate requi rement s from the contractor.
Response A current set of requirements (license) placed on the burial site operators by their respective states are maintained on site in the Radwaste Shipping Department.
Items 3 Designate, in writing, people in your organization who are responsible for the safe transfer, packaging, and transport of low-level radioactive material.
Response Personnel in the Oyster Creek Station organization who are responsible for the safe transfer, packaging, and transport of the low-level radioactive material and those personnel qualified and authorized to sign shipping papers for transportation of radioactive waste have been designated in writing.
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Revised Response to NRC I6E Page 2
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Bulletin 79-19 Item 4 Provide management-approved, detailed inst ructions and operat ing procedures to all personnel involved in the transfer, packaging, and transport of low-level radioacti ve mat erial . Special attention should be given to controls on the chemical and physical fom of the low-level radioactive material and on the containment integrity of the packaging..
Response Management-approved operating procedures which are used in operations and in the transfer, packaging, and transport of radioactive material are provided.
Item 5 Provide training and periodic retraining in the DOT and NRC regulatory requi rements, the waste burial license requirements, and in your instructions and operating procedures for all personnel involved in the transfer, packaging, and t ransport of radioactive material . Maintain a record of t raining dates, attendees, and subject material for future inspections by NRC personnel.
Response Training and periodic retraining in the DOT and NRC regulatory requirements are presently provided to Radwaste Operators, Rad Con Technicians, Station Services, and Radwaste Shipping Supervisors.
The present Operations t raining program provides training and retraining on minimizing radioactive waste by those processes which
> generate wastes. A training program is administered for radwaste facility operators which covers Radwaste Operations including transfer, packaging, and shipping of radioactive material in the DOT, NRC, and waste burial requirements thereto. Personnel packaging DAW are bargaining unit personnel who are trained in the operations of the packaging as well as transfer and storage procedures. They are under the direct supervision of the Radwaste Shipping Supervisors who are training in all applicable regulatory criteria.
Item 6 Provide t raining and periodic ret raini ng to Radwaste Operators who operate the processes which generate waste to assure that the volume
, of low-level radioactive waste is minimized and that such waste is
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processed into acceptable chemical and physical fom for transfer and shipment to a low-level radioactive waste burial facility.
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Revised Response to NRC I6E Page 3
Item '
Establish and implement a management-controlled andit function of all transfer, packaging, and transport activities to provide assurance that personnel, instructions and procedures, and process and transport equipment are functioning to ensure safety and compliance with regulatory recuirements.
Response A management-controlled audit function for the transfer, packaging, and transport of radioactive materials has been established and has been implemented. This function is provided by the Quality Assurance Department through the QA program development and audit sections.
Item 8 Perform, within 60 days of the date of this bulletin, a management-controlled audit of your activities associated with the t ransfer, packaging, and transport of low-level radioactive waste.
Maintain a record of all audits for future inspections by NRC or DOT inspections. (Note: If you have an established audit function arx!
have performed such an audit of all activities in items 1-6 within the past six months, this audit requirement is satisfied.)
Response A management controlled audit of Radwaste Operations was conducted on March 7, 1979 (Audit No. 79-04) and have been conducted on an annual basis since the issuance of the 16E bulletin. In addition to annual audits conducted by the QC QA site audit section, routine inspections / monitoring of regular waste shipments are conducted by Operations QA monitors.
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Revised Response to NPC I6E Page 4
Bulletin 79-19 Item 9 Provide answers for 1978 and for the first six months of 1979 to the following questions:
1. How many low-level radioactive waste shipments did you make?
What was the volume of low-level radioactive waste shipped?
(Power reactor licensees who _ report this information in accordance with Technical Specifications do not need to respond to this question.)
2. What was the quantity (curies) of low-level radioactive waste shipped? What were the major isotopes in the low-level radioactive waste?
(Power reactor licensees who report this information in accordance with Technical Specifications do not need to respond to this question.)
3. Did you generate liquid low-level radioactive waste? If the answer is "yes", what process was used to solidify the liquid waste?
Response 1. Reported in Semiannual Reports for the years since 1978,
" Radioactive Effluent Releases."
2. Same as No. I above.
3. Liauld low-level radioactive waste is generated. A process using line and cement is presently used to solidify filter sludge and evaporator bottoms.
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