ML20077M296

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Forwards Response to NRC Request for Addl Info to Enable NRC to Review 870817 Application for Amends to Licenses DPR-71 & DPR-62,extending OL Expiration Dates Until 40 Yrs from Date of OL Issuance
ML20077M296
Person / Time
Site: Brunswick  Duke energy icon.png
Issue date: 08/08/1991
From: Vaughn G
CAROLINA POWER & LIGHT CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NLS-91-156, TAC-66082, TAC-66083, NUDOCS 9108130282
Download: ML20077M296 (7)


Text

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Carolina Power & Light Company P o Boa 1651 e Raleigh N C 77602 AUG 0 81391 SERIAL: NLS 91-156 10 CFR 50.90 G E VAUGHN vin rews.,i waar s.r.cei omo.ni United States Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, DC 20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 DOCKET NOS. 50-325 & 50-324/ LICENSE NOS. DPR-71 & DPR-62 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION EXTENSION OF OPERATING LICENSE (NRC TAC NOS. 66082 AND 66083)

Gentlemen:

On August 17,1987 (Serial: NLS-87-111), Carolina Power & Light Company (CP&L) submitted a licenso amendment request to extend the expiration date for the operating licensos for the Brunswick Steam Electric Plant, Units 1 and 2 to 40 years from tho dato the operating licenses were issued. The existing operating licenso expiration dates are based on 40 years from the date the construction permits were issued.

The NRC Staff cor,tacted CP&L to request information needed to complete the Staff's review of the Company's license amendment request. The Staff's questions, along with CP&L's responses, are provided in Enclosuro 1.

Please refer any questions regarding this submittal to Mr. W. R. Murray at (919) 546-4661.

Yours very truly,

' o G.E.Vaughn WRM/wrm (\wp\olext4b.wpf)

Enclosures

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Document Control Desk NLS-91 156 / Page 2 cc: Mr. Dayne H. Brown Mr. S. D. Ebneter Mr. N. B. Le Mr. R. L. Prevatte G. E. Vaughn, havino been first duly sworn, did deposo and say that the information contained heroin is true and correct to the best of his information, knowledge anJ belief; and the sources of his information are officers, employees, contractors, and agents of Carolina Power & Light Company. l nn- T aufL f_

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l ENCLOSURE 1 BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 NRC DOCKETS 50 325 & 50 324 OPERATING LICENSES DPR-71 & DPR 62 RESPONSE TO REQUES' FOR ADDITIONAL INFORMATION EXTENSION OF OPERATING LICENSE (NRC TAC NOS. 66082 AND 66083)

NRC REQUEST NO.1:

Provido a copy of the Doso Reduction Program detailing plans to reduce Brunswick's annual collectivo dose over the next few years to a lovel more comparable to the industry averago euring the period of the extension, CP&L RESPONSE:

The CP&L Doso Roduction Plan was approved in September 1990. The Plan consists of pro-activo recommendations that the Company's three nuclear plants and their support departments can imptomont to lower personnel radiation exposures.

Carolina Power & Light Company has completed a review of the Company Doso Roduction Plan and identified the following Brunswick Nuclear Project doso goals (two units) and supporting actions to be appropriate for the 1991 through 1996 planning period:

yrat Goal (Man-rem) 1991 1100 1992 600 1993 570 1994 870' 1995 500 1996 530

'Roprosents two refueling outages occurring in 1994.

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l To support achlovement of these dose goals, the Brunswick Nuclear Project Doso l

Reduction Plan includes a number of action items currently underway to reduco personnel radiation exposure. The following is a brief description and status of action items:

l Outaao Plannino: Plant procedure BSP-35, Pre outago Planning, has boon devo!oped

! to minimize planned outage longths by improving outogo planning and thereby minimize collective radiation exposure.

Recirculation System Decontamination: The Brunswick Plant has an aggressivo chemical decontamination program. During the last Unit 1 and Unit 2 refueling outages, the recirculation systems were decontaminated using a throo stop Citrox  ;

process prior to the partial pipe replacement. During the Fall 1991 Unit 2 refueling l outage, the recirculation system and reactor vessel annulus (af ter being vacuumed) i are scheduled to be chemically decontaminated using the LOMI process.

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! Radiation Control Area Access: A single point access control program has boon implomonted to contralize access to the Radiation Control Area and to provido better Radiation Work Permit accountability and evaluation of what are the major i exposure contributors. This will assist management in determining where to place ,

emphasis on personnel exposure reduction.

Valve Maintenance Cleanliness: Maintenance procedures have boon revisod to include prevention and clean up stops to minimize cobalt intrusion into piping.

CRD Blade Pin and Roller Removal: Company efforts are underway to participate in the EPRI pin and roller replacement tailored collabpration, in addition, there are plans to accelerato the replacement of control rod drive blados containing stoliito material.

Additional actions are underway at the Brunswick Nuclear Project to further reduce personnel exposure and include the following:

1. A surrogato video tour that will be accessible to plant personnelis nearing completion. The ability to "see" a plant area without actually going into the Radiation Control Area will be used in job planning for both outago and routine operation
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2. ALARA incenti ses .iave been included in appropriate contracts.
3. An ALARA cuOgsstion program has been improved.
4. An ALARA Teamwork Incentivo program that offers cash awards to personnel for successfully meeting exposure goals has been implemented.

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5. The use of mock ups in At. ARA training is emphasized.
6. A Rowork Tracking Program that allows plant personnel to bonofit from lessons learned has boon implemented.

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7. For the fall 1991 Unit 2 rotuo'ing outago, time has boon providad in tho l outage schedule to allow the annulus to ba vacuumed prior to the chemical l decontamination Vacuuming will remove some of the accumulated crud m l the vessel, as well as increasing the oflectivonocs of the chemical j decontamination of the suction side of the recirculation system. Present J plans includo having the same proceduto performed on Unit 1 during the 1992 refueling outago,in addition to the chemical decontamination of the residual heat removal and reactor water cleanup systems.
8. The Company is a participant in an ongoing research offort to ovaluato the feasibility of a full system decontamination.
9. Extensivo uso is made of video cameras to reduce personnel radiation exposure.
10. Extensivo uso of reactor vossol nozzlo flushing has boon modo to reduco personnel radiation exposure during outages.
11. The spent fuel shipping cask basket has boon rodosigned to permit shipping of spent fuel bundles without the nood for removing the fuel channel prior to shipment.
12. The Company has a program in place for minimizing plant contaminated areas.
13. A team is working on ways to maximizo the uso of temporary sh;olding during outages in the plant while ensuring nuclear safety.
14. An Elevated Exposuro Rato Task Force has been pro activo in pursuing remedios for the ureanticipated clovated recirculation system doso rates soon due to hydrogen water chemistry.

Each year, the dose reduction actions are reviewed as part of the Company's periodic re-evaluation and establishment of now long-term doso goals.

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NRC REQUFJT NO. 2:

Either provido a summary of Brunswick Plant's occupational dosos for 1990 or reference to where the information has boon previously submitted.

CEE RESPONSE:

Carolina Power & Lir,ht Compeny has previoasiy submitted two letters to the NRC i pmvidinD 1990 Brunswick Nuclear Project personnel exposure information. On January 8, 1991 (Serial: BSEP/91-0008), CP&L submitted the 1990 Statistical Radiation Exposuro Report in accordance with 10 CFR 20.407(a)(1). This report providos statistical _

information on the number of personnel exposed and the who10 body exposuro ran00s involved. Also, on January 8,1991 (Serial: BSEP/91-0009), CP&L submitted the Annual Radiation Exposura R0 port in accordance with Brunswick Technical Specification 6.9.1.5.

The Annual Radiation Exposure Report providos exposure data for CP&L personnel based on work and job function. Copios of those submittals are provided in Enclosuro 2.

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. 1 ENCLOSURE 2 BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 l NRC DOCKETS 50 325 & 50 324 OPERATING LICENSES DPR 71 & DPR 62 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION EXTENSION OF OPERATING LICENSE (NRC TAC NOS. 66082 AND 66083)

.CP&L CORRESPONDENCE DATED JANUARY 8,1991 l

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