ML19350E592

Forwards Response to 810515 Request for Addl Info Re Health Physics Program for Facility.Onsite Coverage in Event of Absence of Site Health Physicist Will Be Provided by Health Physics Supervisor

ML19350E592
Person / Time
Site:	Wolf Creek
Issue date:	06/15/1981
From:	Koester G KANSAS GAS & ELECTRIC CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
References
KMLNRC-81-085, KMLNRC-81-85, NUDOCS 8106230315
Download: ML19350E592 (7)

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KANSAS GAS AND ELECTRIC COMPANY T>4E ELECTsaC COM88ANY 4LENN L. etOE57Ea v<a ,masicam, esuctaan June 15, 1981 s.

Mr. Harold R. Denton, Director  %

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U.S. Nuclear Regulatory Commission ~ ,

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KMLNRC 81-085 'O Re: Docket No. STN 50-482 /

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Ref: NRC Letter dated 5/15/81 from RLTedesco N

to GLKoester, KGE Subj: Response to Request for Additional Information on the Wolf Creek Generati ng Station Unit No.1 Health Physics Program

Dear Mr. Denton:

Attar'.ed please find our response to Mr. Tedesco's request for additional information on the Wolf Creek Generating Station Unit No. 1 Health Physics Program.

This set of questions and responses will be included in the next revision to the Wolf Creek Generating S?.ation FSAR Addendum.

This information is hereby incorporated into the Wolf Creek Generating Station Operating License Application.

Yours very truly,

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,ff) A GLK:bb Attach cc: Dr. G.E. Edison (2)

Tom Vandel I

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e' OATH OF AFFIRMATION

. STATE OF KANSAS )

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COUNTY OF SEDGWICK )

I,' Glenn L. Koester, of lawful age, being duly sworn upon oath, do depose, state and affim that I am Vice President - Nuclear of Kansas Gas and Electric Company, Wichita, Kansas, that I have signed the foregoing letter of transmittal, know the contents thereof, and that all ' statements contained therein are true.

KANSAS GAS AND ELECTRIC COMPANY A'ITEST:

., By ffjy' , >

Glenn L. Koestei-Vice President - Nuclear W.B. Walker, Secretary STATE OF KANSAS )

) SS:

COUNTY OF SEDGWICK )

BE IT REMEMBERED that on this 15th day of June, 1981 , before me, Evelyn L. Fry, a Notary, personally appeared Glenn L. Koester, Vice President - Nuclear of Kansas Gas and Electric Company, Wichita, Kansas, who is personaJly known to he and who ' executed the foregoing instrument, and he duly acknowledged the execation of the same for and on behalf of and as the act and dead of said corporation.

Nb d# IN WITNESS WHEREOF, I have hereunto set my hand and affixed my saal the d year above written.

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E elyn L. ff, Notary

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• ..... .My ';Comission expires on August 15, 1981.

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SNUPPS-WC 471. Owc RADIOLOGI' CAL ASSESSMENT BRANCH Q471.1we' Please describe your plan to provide onsite backup.

coverage in the event of the absence of the site Health Physicist and _- outline the qualifications

'(or make reference to them in the aporopriate sec-tion of the FSAR) of the individual who will act as the backup. It is our position that this individual have a B .S. degree' in science or engi-neering, and two years health physics experience, i one year of which should be nuclear power plant expe rience, with six months of this experience being onsite. It is our position that this expe-rience be health physics experience.

R471.iwc Onsite backup coverage _in the event of the absence of the site Health Physicist will be - provided by designating one-of the Health Physics Supervisors.

Minimum qualification requirements for the Health Physics Supervisors will be a B.S. degree in science or engineering, and two years health phy-sics experience, one year of which should be nuclear power plant experience, with six months of this experience being onsite as specified in draft ANS 3.1-1981 Section 4.4.4.d.

Q471.2wc Section 13.1.2.3 " Shift crew Composition" states that this area will be addressed in the Technical Specification. The staff requires that an H.P.

technician will be onsite at all times, in eccord-ance with NUREG-0654 " Criteria for Preparation

' and Evaluation sf Radiological Emergency Responso Plans and Preparation in Support of Nuclear Power Plants", after the reactor is at power. Please state your intentions for having your technical specification. include a H.P. tecnnician as part of the shift crew. The qualifications of the H.P.

technician are described in ANSI 18.1.

R471.2wc The WCGS Technical Specifications section 6.0 will i include the following statement, " Qualified Health Physics personnel shall be onsite when fuel is in

, the reactor."

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1 0471.3wc In accordance with 12.5.3 several ' procedures in-cluding' respiratory protection, decontamination, glove bexes, tents, etc. will be used to reduce possibility of. personnel exposure to . airborne activity. Please discuss your radiation protec-tion provision for installation of temporary flex-ible ducting and monitoring equipment at the site of maintenance operations and repair activities, if .a high potential for airborne radioactivity exists, to assure that 10 CFR Part 20.103 limits are not excluded, that 10 CFR 20.103(b) actions are taken, and that exposure are maintained ALARA during the operation.

R471.3wc As discussed in Section 12.5.3, ALARA Regulatory Guides 8.8 and 8.10 are an integral part of the WCGS Health Physics procedures.

t Airborne radioactivity will normally be controlled through the use of engineering controls, cuch as installed ventilation systems or installed IIEPA and activated charcoal filters, or if needed, portable containment and ventilation. Respiratory protection, glove boxes and tents attached through flexible ducting to HEPA and activated charcoal filters, or decontamination will be used when engineering controls are not practical. Contin-uous Air-Monitors (CAMS) and grab samples will be used to monitor the concentrations of the airborne '

radioactivity in the atmosphere to assure that 10 CFR Part 20.103 limits are not exceeded.

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SNUPPS-IC Q471.4we Table 12.5-2 " Portable Health Physics Equipment" show -quantities of instrumentation not adequate to meet the anticipated needs of a radiation pro-tection program for a nuclear power plant. The staff- position is that sufficient numbe rs of instrumentation be available in operating condi-tion to accommodate the need to monitor such large numbers of operations that may be required in radiation areas and high radiation areas through-out the plant during major maintenance and refuel-ing outages and/or accidents. In arriving at a total number, consideration should also be given to the survey instruments that may be in a cali-bration, maintenance or inope rative-on-the-shel.f status during the outage and/or accidents. Addi-tionally, the inventory should include the re-quirements .for selected ranges, sensitivities, types of radiation to be monitored, accuracy re-quired, and types of monitoring to be pe -"- :.ned .

Ten instruments that read-out in the R/hr range of measurements, as shown in Table 12.5.2, would probably not satisfy the above criteria based on the findings at operating nuclear power p la nts .

Therefore, the table should be revised to reflect these criteria in orde r to provide the radiation protection instrumentation inventory requirements of the plant.

R471.4wc See revised Table 12.5-2. -

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.. uf lable 12.5-2 ' Sheet 1 of 2)

Portable Ikalth Physics Equipment ,

Types of .-

Inst runent Ra3istion Sensitivities R.srqe Accuracy ' Monitor 1rq Number location Remarks 44 'iurvey Meter Deta, Gansna 45% eff. 0.54 0-50,000 CPM 120% Fbil Scale Contamination 30 llealth Physics With standard or

' Office . pancake probe GM Survey Meter Deta. Gamma 15% eff. 0-1 R/llR 120% Ebll Scale Working Area 15 Hea e Physics With Internal l

.31-1.33 MeV Railation- Off1 2 -Iktector l GH Survey Meter Deta, Gununa 15% ef f. 0-1000 R/tiR 420% Ebil Scale Working Area 12 tiealth Ihysics With iblescoptrg 0.1-3.0 Mev Radiation Office Probe Survey ieter Deta, Gamma 15% eff. 30 Kev 0-10,000 R/HR 120% tbli Scale Workiry Area . 6 tiealth Physics With extendirg 1.2 Mev Radiation Office Probe or Cable Survey Meter Peta, Gamma 15% ef f . 0-5 R/HR 120% Pull Scale Workiry Area 15 tiealth Physics lonization Chamber j 0.b-2 Mev Radiation Office with beta shield i Servcy N ter beta, Gamma 15% ef f. 0-50 R/HR 120% Pull Scale Workirq Area 10 llealth Physics Ionization Chamber -l 0.8-2 Mev Radiation Office with beta Shield I ,

t..utron REM rkutron 15% eff. 0-5 REM /hr 120% Eb11 Scale Worktry Area 5 llealth Physics PNR-4 Meter 'Ihernal-10 Mev Raliation Office '

Yeutron RPM Neutron 15% ef f . 0-50 REM /hr 120% Tbll Scale Working Area 3- Health Physics PNR-4 '

Meter 1hermal-10 Mev Raiiation Office' l

Scintillation Alpha -NA- 0-50,000 CPM 120% Eb11 Scale Cc tamination- 4 ilealth Phy.91cs Alpha Scintillation T Counter Office . Crystal with a  ;

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fortal lon. tor Deta, Gamma 20% eff. Variable range 420% Full' Scale Personnel 6 Personnel exits Eauurus3 with I O atdible alano,

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80 Kev-1.2 Mev Switch Contienir ation at se writy l house and frun Gas propnrtional g controlla$ access or scintillation

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Table 12.5-2 (Sheet 2 of 2)

Portable tiealth Physics Equipment Types of Accuracy Hmitorirn Mantwr tocation Remarks 4nsitivities Range In st nament Radiat_ ions 0-994 mR Injividual 25 tiealth Physics A udible alana Individual Ekta, Gansna 30% eff. 120% (10R/ttr) Office response propor--

60 Kev -1.25 Mew Exposure Personnel taonal to dase '

• Monitor -rate-0-200 mR +15% Ebli Scale Initvidual 2000 Health Physics Intergrat t ry, i'

Pocket Gansna 15% etf. 80 Kev Office direct reajing 1.2 Nev Exposure

, Dosimeter '

0-1 R Inlividual '100 llealth Physics Intergrating, Focket Gamma 15% eff. 80 Kev 115% tb11 Scale Office direct reading 1.2 "r- Exposure Dosimeter Pocket Gamma 15% eff. 80 Kev tiealth Physics Intergrating, 1.2 nev 0-5 R 115% tb11 Scale In31vidual 50 l Ibstmeter Exposure Cffice .darect reading i individual 20 ticalth Physics Intergrating,.

Pocket Ganma 15% eff. 80 Kev 0-10 R 115% Eb11 Scale direct readirq Exposure Oftice tbsimeter 1.276

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