ML20203B249

Forwards Info Supplied by Ies Utilities Inc.Info Provided Subsequent to Discussions About Conversion from Current to Improved TS at Duane Arnold Energy Center

ML20203B249
Person / Time
Site:	Duane Arnold
Issue date:	12/03/1997
From:	Kelly G NRC (Affiliation Not Assigned)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9712120385
Download: ML20203B249 (9)

Text

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3'o _ 3 3 j December 3,1997 NOTE TO: Information and Records Management Branch Office ofinformation Resources Management i a , .4 ,, l A'

FROM:

Glenn B. Kelly, Project Directorate Senior 3 3. DRPW, NRR p Project que ,Manager 4 4- 'y'([) l

SUBJECT:

INFORMATION TO DE PLACED ON Tile DUANE ARNOLD E$ERGY CENTER (DAEC) DOCKET (50-331)

The enclosed infonnation was supplied to me by IES Utilities Inc. This information was provided subsequent to discussions about the conversion from current to improved Technical j i

Specifications at DAEC. Please place the enclosed infonaation on the DAEC docket.

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swrw Emju wtarDUEFVRE) tw t018Wud!Es $00u008 Procedures 5.4

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5.0 ADMINISTRATIVE CONTROLS 5.4 Procedures 5.4.1 Written procedures shall be established. implemented, and maintained covering the following activities:

a. The applicable procedures recommended in Regulatory Guide 1.33. Revision 2, Appendix A. February 1978:

b. The emergency operating procedures required to implement the requirements of NUREG 0737 and to NUREG-0737. Supplement 1.

as stated in Generic Letter 82-33: ,

c. Quality assurance for effluent and environmental monitoring:

d. Fire Protection Program implementation: and

e. All programs specified in Specification 5.5.

DAEC 5.0-S Revision A

uun avv 6avuu upa r m s vuuo arru m a mu w j

, , i Programs and Manuals

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5.5 -

5.0 ADMINISTRATIVE CONTROLS 5.5 Programs and Manuals The following programs shall be established implemented and maintained.

5.5.1 Offsite Osse Assessment Manual (00AM)

a. The ODAM shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm and trip setpoints, and in the conduct of the radiological environmental monitoring program: and

b. The ODAM shall also contain the radioactive effluent controls and radiological environmental monitoring activities and descriptions of the information that should be included in the Annual Radiological Environmental Operating Report and Radioactive Material Release Report required by Specification 5.6.2 and Specification 5.6.3.

c. Licensee initiated changes to the ODAM:

1. Shall be documented and records of reviews performed-shall be retained. This documentation shall contain:

a. Sufficient information to support the change (s) together with the appropriate analyses or

, evaluations justifying the change (s). and

b. A determination that the change (s) maintain the levels of radioactive effluent control required by 10 CFR 20.1302. 40 CFR 190. 10 CFR 50.36a and 10 CFR 50. Appendix 1. and not adversely impact the accuracy or reliability of effluent. dose. or setpoint calculations:

2. Shall become effective after review and acceptance by the Operations Committee and the approval of the plant manager: and

3. Shall be submitted to the NRC in the form of a complete. legible copy of the entire ODAM as a part of or concurrent with the Radioactive Material Release Report for the period of the report in which any change in the ODAM was made. Each change shall be identified by (continued)

DAEC 5.0-6 Revision A

Programs and Manuals i

5.5 f'

5.5 Programs and Manuals 5.5.1 offsite 00se calculatien Manual f 00Am (continued) markings in the margin of the affected pages. clearly indicating the area of the page that was changed, and shall indicate the date (i.e. month and year) the change was implementad.

5.5.2 Primary coolant sourcee outside contaim This program provides controls to miniinize leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to levels as low as practicable. The systems include Core Spray.

High Pressure Coolant Injection, Residual Heat Removal. Reactor Core Isolation Cooling. Reactor Water Cleanup (only to second isolation valve). Post Accident Sampling. Containment Atmos r

Monitoring. Control Rod Drive (scram discharge volume and only)pheric Liquid Radwaste (only Reactor Building Floor and Equipment Drain G' M';i sumph).punos, piping, tanks T1e program shalland tanks include the up to and including collector following: ,

a. Preventive maintenance and periodic visual inspection -

requirements: and

b. System leak test requirements for each system at refueling cycle intervals or less, 5.5.3 Post Accident Saanlino This progrt.,provides controls that ensure the capability to obtain and analyze reactor coolant, radioactive gases, and particulates in plant gaseous effluents and containment atmosphere samples under accident conditions. The program shall include the following:

a. Training of personnel:

b .' Procedures for sampling and analysis; and

c. Provisions for maintenance of sampling and analysis equipment.

(cont nued)

DAEC 5.0-7 Reti sion A

12/02/97 Ig 'u319 6517193 IEs INDL'sTRIEs @00s/006

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Programs and Manuals 5.5 i

5.5 Programs a'd Manuals (continued) 5.5.4 Radioactive Effluent Controls Proaram This program. ccnforming to 10 CFR 50.36a provides for the control of radioactive effluents and for maintaining the doses to members of the public from radioactive effluents as low as

- reasonably achicvable. The program shall be contained in the ODAM, shall be implemented by procedures, and shall include remedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements:

a. Limitations on the functional capability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and sotpoint determination in accordance with the methodology in the 00AM:

b. Limitations on the concentrations of radioactive material released in liquid effluents from the site to unrestricted areas. conforming to ten times (10x) the concentrations listed in Appendix B. Table 2. Column 2 to 10CFR20.100}-20.2402:

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c. Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents pursuant to 10 CFR 20.1302 and with the methodology and parameters in the 00AM: -

d. Limitations on the annual and quarterly doses or dose commitment to a member of the public from radioactive materials in liquid effluents released to urrestric'ted areas. ccnforming to 10 CFR 50. Appendix I:

e. Determination of cumulative and arojected dose contributions from radioactive effluents for tie current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODAM at least every 31 days:

f. Limitations on the functional capability and use of the liquid and gaseous ef fluent treatment systems to ensure that the ar.propriate portions of tnese systens which were used to establish compliance with the design objectives in 10 CFR

50. Appendix 1.Section II be used when specified to provide reasonable assurance that releases of radioactive material in liquid and gaseous effluents be kept as low as reasonably achievable:

(continued)

DAEC 5.0-8 Revision A

nD709/0V 14:00 G 310 801 V193 IEs INDUSTRIES @ o06/008 1 1

Programs and Manuals 5.5 I

5.5 Program and Manuals 5.5.4 Radioactive Fffluent controit Procram (continued) 9 Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the site boundary shall be limited to the following:

1. For noble gases: less than or ecual to a dose rate of 500 mrem /yr to the total body anc less than or equal to a dose rate of 3000 mrem /yr to the skin and

2. For iodine-131. iodine-133, tritium, and for all radionuclides in particulate form with half lives > 8 1 days: less than or equal to a dose rate of 1500 mrem /yr to any organ:

h. Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents to areas beyond the site boundary, conforming to 10 CFR 50.

Appendix I;

i. Limitations on the annual and quarterly doses to a member of the public from iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half lives > 8 days in gaseous effluents released to areas beyond the site boundary, conforming to 10 CFR 50. Appendix 1: and

j. Limitations on the annual dose or dose commitment to any member of the public due to releases of radioactivity and to radiation from uranium fuel cycle sources, conforming to 40 CFR 190.

5.5.5 tornonent cyclic or Transient umit This program provi' des controls to track the UFSAR Section 5.3.3.

cyclic and transient occurrences to ensure that components are maintained within the design limits.

(continued)

DAEC 5.0-9 Revision A l

N i h io 001 9193 IES INDUSTRIES @ 007/008

10. Program to ensure that capability to accurately determine the airtem iodine concentration in vital areas under accident conditions, including training of personnel, procedures for monitoring and provisions for maintenance of sa;6pling and analysis equipment.

11< Administrative procedures for shift overtime for Operations personnel 404es wit com 15,1 pol t2 i ion's J ste m . l ne p

ime ed b d staff rs ormi ty to df ll imite co led in gadance the Polic tate - rki ru(Go e Lette,r 87.,_12). - 4 A S S p u= c o >= s G D IN Yse ndo cial Spase, ,c t an-re cas.

l0* 40 c.i s's Cottmat t aygam ,

17.2 A-12 Revision 19 to be determined e

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( approved in the NRC Safety Evaluation Report, BWROG EPG, Revision 4, September 1988.

8.14 The following procedures and changes thereto, shall be myiewed by ther Operations Committee as indicated in Section 6.4 above and approved by the Plant Manager, Nuclear or designee prior to implementation, except as provided in Section 6.7 above:

1. Normal st&rtup, operation, and shutdown of systerns arH axnpunents of the facility.

2. Refueling operation.

3. Actions to be taken to correct spcific and foreseen potential matfunctions of systerr.s or components, including responses to alarms, suspected primary system leaks, and abnormal reactivity changes.

4. Emergency and off-normal condition procedures. The emergency operating procedures required to imp;ement the requirements of NUREG-0737 and to NUREG-0737, Supplement 1, as stated in Generic Leiter 82-33.

5. Preventive and corrective maintenance operations which could have an effect on the nuclear safety of the facility.

6. Surveillance and testing requirements of equipment that could have an effect on the

( nuclear safety of the facility.

7. Operation of radioactive waste systems.

8. Fire Protection Program implemantation.

9. A preventive maintenance and periodic visual examination program to reduce leakage from systems outside containment that would or could contain highty radioactive fluids during a serious transient to as low as practicallevels. This program shall also. include provisions for performance of_ periodic systems leak tests of each system once per OPERATING CYCLEfThis prog provides prols to minimi akage r nom mose rtions of systeths outsid ntainment at could conta'. hty .

radios e fluids duri se.rious nsient or a ' ent to levels as pra ' e, ystems inci Core S , High Pres Coolant In' on, Residu t /

emoval, R or Co ation Coolin , eactor W ieanup ( second i Ive), P accident Sam 3, Contain Atmosphe onit Rod ' s (scram disce volume o and Uqui e uilding r and EquipmmtIDrain sum iping, a ka up to including Reactor /

col r tanks). The ram shalli the f ng

a. Preventiv aintenancegperiodic alinspecti equireme ,and b.Sysj ak test reggit(ments for ch system uelingp intervals or 17.2 A-11 Revision 19 te be determined

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