ML20216E342

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Summary of 970826 Meeting W/Gpu in Rockville,Md Re Possibility of Decommissioning of Plant.Agenda,Meeting Handouts & Primarily Centered Activities Associated W/Decommissioning Plant in Yr 2000 Encl
ML20216E342
Person / Time
Site: Oyster Creek
Issue date: 09/03/1997
From: Eaton R
NRC (Affiliation Not Assigned)
To:
NRC (Affiliation Not Assigned)
References
NUDOCS 9709100154
Download: ML20216E342 (17)


Text

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September 3, 1997 LICENSEE: GPU Huclear Corporation FACILITY: Oyster Creek Nuclear Generating Station

SUBJECT:

MEETING WITH GFU NUCLEAR CORPORATION REGARDING THE POSSIBILITY OF DECOMMISSIONING THE OYSTER CREEK NUCLEAR GENERATING STATION At the request of GPU I:;eclear (GPU or licensee), a public meeting was held on August 26, 1997, in the Nuclear Regulatory Comission (NRC) offices at Rockville, Maryland. The licensee made a presentation regarding its options to shut down, sell, or continue to operate the Oyster Creek Nuclear Generating Station (OCNGS). The presentation followed the enclosed agenda and meeting handouts and primarily centered on the activities associated with decomissioning OCNGS in the year 2000.

As noted in the handouts, the licensee is considering deferral of a number of commitments pending its final decision which is expected in late 1997 or early 1998. The NRC informed.the licensee that any requested change in its -

commitments should be submitted on the docket with adequate jnstification and risk assessment to allow the NRC staff to evaluate the requests.

Original signed by Ronald B. Eaton, Senior Project Manager Project Directorate I-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket No. S0-219

Enclosure:

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DISTRIBUTION j

HARD COPY E-MAIL Docket File SCollins/FMiraglia (SJC1)(FJM)

PUBLIC R. Zimmerman (RPZ) PEselgroth (PSE)

PDI-3 Rdg. B. Boger (BAB2)

OGC S. Bajwa (SSB1)

ACRS C. Jamerson (CAJ1)

REaton B. Sheron (BWS)

B. McCabe (BCM)

S. Weiss (SH2)

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GPU Nuclear Corporation Oyster Creek Nuclear Generating Station CC:

Ernest L. Blake, Jr., Esquire Shaw, Pittman, Potts & Trowbridge 2300 N Street, W Washington, DC 20037 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406-1415 BWR Licensing Manager GPU Nuclear Corporation 1 Upper Pond Road Parsippany, NJ 07054 Mayor Lacey Township 818 West Lacey Road Forked River, NJ 08731 Licensing Manager Oyster Creek Nuclear Generating Station Mail Stop: Site Emergency Bldg.

P.O. Box 388 Forked River, NJ 08731 Resident Inspector c/o U.S. Nuclear Regulatory Commission P.O. Box 445 Forked River, NJ 08731 Kent Tosch, Chief New Jersey Department of Environmental Protection Bureau of Nuclear Enginearing CN 415 Trenton, NJ 08625 Mr. Michael B. Roche Vice President and Director GPU Nuclear Corporation Oyster Creek Nuclear Generating Station P. O. Box 388 Forked River, NJ 08731

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Background & Purpose

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+ On April 10,1997, GPU, Inc. announced that in addition to continued operation, it was exploring the additional options of sale or early shutdown of the Oyster Creek Nuclear Generating Station (OCNGS). . .

+ The purpose of today's meeting is to describe the planning efforts initiated in response to the announcement to assure continued safe operation of OCNGS and to prepare for early shutdown and decommissioning.

+ Five Planning Teams were formed to address:

+ Decommissioning

+ Sale of Oyster Creek

+ Personnel Retention

+ Projects / Regulatory Commitments

+ Communications -

e Background & Purpose (cont'd)

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+ The primary focus of today's discussion will be the results of three of these planning teams.

+ Personnel Retention Team .

+ Projects / Regulatory Commitments Team 4 Revise regulatory commitments which pose an acceptable individusi and integrated safety risk

+ Submit requests for deferrals as a package 4

+ Decommissioning Team

+ GPU, Inc. decision is expected by the end of 1997 O

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Staff Retention Strategy meanewma?L waggg;tyd;imsi%gCriermswy,,e

+ As expected, staff attrition rate since the announcement .

has been higherthan normal.

+ Retention strategy developed to ensure a qualified staff to safely operate, maintain and support Oyster Creek.

+ Utilize in-house staff to work on decdmmissioning activities.

+ Enhanced education and training opportunities.

+ Outplacement services.

+ Potential alliances with suppliers.

+ Enhanced retirement packages.

+ Lump-sum monetary payments.

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+ Other personnel issues to be addressed including transition of work force to decommissioning.

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+ Review Process .

+ Review team formed to assess the benefits of all existing projects and regulatory commitments.

+ Initial review criteria:

+ safety / risk

+ radiological dose savings

+ technical justification

+ economic payback / cost savings

+ operational significance

+ benefits decommissioning

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& Significant number of projects / regulatory commitments .

reviewed.

+ Projects / regulatory commitments placed into three categories:

+ Implement as originally committed.

+ Defer now, before final plant decision is made.

+ Regulatory commitments to be addressed in accordance with the Section 2.C.6 of Oyster Creek operating license " integrated schedule"

+ Cancel if early retirement decision is made.

+ Additional changes to integrated living schedule -

+ Exemption request -

+ Tech Spec Change Request

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PROJECTS REVIEW l ALL PROJECTS CANCEL ~AFTER DECISION - . at .

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DEFER BEFORE DECISidN 18 PROJEC. TS

. I NRC Regulatory Commitments

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1 Implement as Committed 2KMD ? M&. q y g g g g g g g g Q f'f j y ?g: : % g:g g g g g gg, Commitment Regulatory Approach Generic Letter 88 Air operated valve testing Not Applicable Biennial Procedure Review (Operational QA Plan - Section 3.1.2) Not Applicable Generic Letter 89 Motor Operated Valves 17R Modifications - Not Applicable Motor Operated Valves (BA #400001) -

MSIV Leakage / Control Room Thyroid Dose (BA #328368) Not Applicable ESW Delamination - LAR 85206.09 Not Applicable Complete 5 remaining DBDs - 50.54f commitment- LAR 96107.07 Not Applicable Marathon Test Control Rod Inspection - LAR 93010.02 Not Applicable ThermoLag Fire Barrier Modifications to 460V rooms (BA #403042) Not Applicable ECCS Suction Strainers - NRC, Owners Group and Individual Not Applicable Commitments (BA #403048)

Top Guide, Shroud, Core Spray Sparger In-Vessel Inspection 17R (BA Not Applicable

  1. 32XAHD, BA #320005)

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NRC Regulatory Commitments Defer Before Final Plant Decision  !

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Commitme.at Regulatory Approach Generic Letter 96-06 Modifications - Pressure concerns for piping penetrations Integrated Schedule (BA #31G690, BA #320011) Update SQUG - Seismic Qualification Modifications. NOTE: Significant number of Integrated Schedule modifications have been completed. (BA #403092) Update Contro1 Room Human Factors Design Review- Repaint, refurbish, and relabel Integrated Schedule control room panel IR through 10R, 6XR,11XR,12R,12XR,14R,14XR,16R, Update 11F,9XR and 11R, NUREG 0737, Supplement 1 (BA #328030)

Anticipatory Scram Logic Modification LER 95-05 (BA #400018) Integrated Schedule Update Severe Accident Management Program Generic Letter 88-20 " Individual Plant Integrated Schedule Examination for Severe Accident Vulnerabilities" Update ,

Thermolag Fire Barrier Modifications 16 and 17R. NOTE: Modifications to Integrated Schedule 460V rooms will not be deferred. (BA #403042) Update Reactor Water Clean Up - Provide an automatic RWCU system isolation on a Integrated Schedule line break - SIL 604 - LER 96-015. (BA #40G294, BA #400017). Update e

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NRC Regulatory Commitments Cancel if Early Retirement Decision is Made -

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Commitment Regulatory Approach

  • Containment Integrated Leak Rate Test Exemption Request Generic Letter 89 Motor Operated Valves 18R Integrated Schedule Modifications - Motor Operated Valves (BA #400001) Update Hydrogen Injection Water Chemistry. NOTE: Integrated Schedule Additional technical evaluation required for a complete Update safety assessment. -

IGSCC Weld Inspections in the Drywell. NOTE: Technical Specification Additional technical evaluation rquired for a complete 4.3.1 (NRC Generic Letter safety-assessment. (BA #320003) 88-01)

ISIInspections (BA #320003) Reschedule in accordance with ISIInspdction

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One time FSAR review - 50.54f commitment Integrated Schedule Update SWSOPI commitment - Perform DBD on intake Integrated Schedule structure Update

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+ Next step is to perform a more in-depth individual and .

integrated risk assessment of regulatory commitments.

+ Four step process used to evaluate safety / risk impact:

+ Evaluate the projects within the framework of the risk analysis studies performed for Oyster Creek.

+ Evaluate the safety or risk impact:

+ Quantitative, if supported by existing or easily developed risk analyses, or

+ Qualitative .

+ Categorize all safety / risk impacts as either.high, medium or low.

+ Integrate results of above steps. Use weighting factors for qualitative information.

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. Regulatory Commitments Risk Assessment '

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+ Examples:

+ Containment integrated leak rate test. Risk is low based on quantification of risk model. Quantitative evaluation uses the Level 2 OCPRA.

+ Intake structure-DBD (SWSOPI commitment). Qualitative evaluation since project does not significantly affect quantitative plant risk. Risk is low based on judgment.

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6 Decommissioning Information armtwm m:gg%gMggmgnBit=waupmgg

+ Decommissioning organization established to perform preliminary .

planning pending early retirement decision.

+ Post Shutdown Decommissioning Activities Report (PSDAR) -i plan for submittal December,1998.

+ Decommissioning technical specification amendment and revised UFSAR - plan for submittal early 1999.

+ Dr. Michael.Masnik, Decommissioning Project Directorate (NRR),

apprised of Oyster Creek early retirement option..

+ NJ State officials briefed on 7/22/97 regarding early retirement option and retention plan. -

+ If shutdown decision announced, community advisory committee to be established.

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+ GPU Nuclear will maintain its strong commitment to plant .

operations during this transition period.

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+ Personnel retention strategy is our near-term focus and will continue to be a long-term issue.

+ Utilized PRA/ Risk Assessment methodology for deferrals.

Request NRC staff review our proposed deferments in a similar fashion.

+ GPU Nuclear will submit updated integrated schedule to NRC in September of 1997 with individual and integrated risk assessment.

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+ GPU Nuclear will continue to maintain active and open communications with NRC staff.

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GPU NEETING TO PRESENT POSSIBLE OYSTER CREEK SCENARIOS AUGUST 26, 1997 1

llamt Office l

Ronald Eaton NRC/PDI-3 Bonnie Williamson Nucleonics Week Ray Ng Bechtel Power Corp, Singh Bajwa NRC Art Rone GPUN Pete Eselgroth NRC Nike Laggart GPU Nuclear Ken Canavan GPU Nuclear Richard Pinney NJ - Dep Adrian Heymer NEC Bruce Boger NRC Nichael Roche GPUN