ML20155E323

Proposed Tech Specs Revising Various Sections of 6.0, Administrative Controls, Including Relocation of 6.11 Contents to Plant Ufsar,Per NUREG-1430,Rev 1

ML20155E323
Person / Time
Site:	Davis Besse
Issue date:	10/28/1998
From:	CENTERIOR ENERGY
To:
Shared Package
ML20155E308	List: ML20155E303 ML20155E318 ML20155E323
References
RTR-NUREG-1430 NUDOCS 9811050007
Download: ML20155E323 (13)

Text

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1;AR 97-0015 - INDEX Page 13 AL)MINISTRATIVE CONTROLS

. SECTION PAGE Mee ti ng Frequency. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-9 Quorum..................................................... 6-9 Review..................................................... 6-10 Audits...................................................... 6-11 A u t h o ri ty . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-12 Re c o rd s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-12 6.5.3 Technical Review and Control. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-12 6.6 REPORTABLE EVENT ACTION. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-12a 6.7 SAFETY LIMIT VIOLATION OR PROTECTIVE LIMIT VIOLATION. . . . 6-13 6.8 PROCEDURES AND PROGRAMS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-13 6.9 REPORTINO REOUIREMENTS 6.9.1 Rou ti ne R e ports. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-14c 6.9.2 S pec i al Re po rts . . . . . . . . . . , . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-18 6.10 RECORD RETENTION. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-18 6.11 DELETED R ADIATION PROTECTION PROGR AM . . . . . . . . . . . . . . . -64&

6.12_ HIG H R ADI ATION ARE A . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-20 6.13 ENVIRONMENTAL OUALIFICATION . . . . . . . . . . . . . . . . . . . . . . . . . 6-21 6.14 PROCESS CONTROL PROGRAM (PCP) . . . . . . . . . . . . . . . . . . . . . . . . . 6-22

6. I 5 OFFSITE DOSE CALCULATION M ANUAL (ODCM) . . . . . . . . . . . . . . 6-22 DAVIS-BESSE, UNIT 1 XVI Amendment No. 38,135,170,189, 9811050007 DR 981028 "'

ADOCK 05000344 PDR

LAR 97-0015 Page 14 ADMINISTRATIVE CONTROLS COMPOSITION l

6. 5.1. 2 The Station Review Board (SRB) shall be composed of at least six members of the Davis-Besse onsite management organization. The members shall be as a minimum, managers or individuals reporting directly to managers from each of the following disciplines: plant operations, maintenance, planning, radiological controls, engineering, and quality assurance. The members shall meet the requirements of ANSI N18.1-1971, Sections 4.2,' 4.4, or 4.6 for applicable required experience.

The SRB Chairman shall be drawn from the SRB members and designated in writing by the Plant Manager.

ALTERNATES

6. 5.1. 3 All alternate members shall be appointed in writing by the SRB Chairman; however, no more than two alternates shall participate as voting members in SRB activities at any one time.

MEETING FREQUENCY 6.5.1.4 The SRB shall meet at least once per calendar month and as convened by the SRB Chairman or his designee.

QUORUM

6. 5.1. 5 A quorum of the SRB shall consist of the Chairman or his designee and four members including alternates.

RESPONSIBILITIES

6. 5.1. 6 The Station Review Board shall be responsible for:

a. Review of plant administrative procedures and changes thereto.

b. Review of the safety evaluation for 1) procedures, 2) changes to procedures, equipment or systems, and 3) tests or experiments completed under the provisions of 10 CFR.50.59, to verify that such actions do not constitute an unreviewed safety question,

c. Review of proposed procedures and changes to procedures and equipment determined to involve an unreviewed safety question as defined in 10 CFR 50.59. _,

INFORMATION ONI.Y DAVIS-BESSE, UNIT 1 6-6 Amendment No. 12,76,98.J09,J38,J39, JA2,169

'llR 97-0015 Pdge 15' ADMINISTRATIVE CONTROLS i

d. Review of proposed tests or experiments determined to involve an unreviewed safety question as defined in 10 CFR 50.59.

e. Review of reports of violations of codes, regulations, orders, Technical Specifications, or Operating License requirements having nuclear safety significance or reports of abnormal degradation of systems designed to contain radioactive material.

f. Review of all proposed changes to the Technical Specifications or the Operating License.

g. Deleted

h. Review of reports of significant operating abnormalities or deviations from normal and expected performance of plant equipment that affect plant safety,

i. Review of chances to the Industrial Security Plan, the Security Training and Qualification Plan, and the Security Contingency Plan,ycnd changes therete J. Review of phDESSJ2.the Davis-Besse Emergency Plan, and changes thwete l k. Review of items which may constitute potential nuclear safety hazards as identified during review of facility operations.

1. Investigations or analyses of special subjects as requested by the Company Nuclear Review Board.

m. Review of all REPORTABLE EVENTS.

n. Review of all Safety 1.imit Violation Reports and Protective Limit Violation Reports (Section 6.7).

o. Review of any unplanned, accidental or uncontrolled radioactive releases, evaluation of the event, ensurance that remedial action is identified to prevent recurrence, review of a report covering the evaluation and forwarding of the report to the Plant Manager and to the CNRB.

p. Review of the changes to the OFFSITE DOSE CALCULATION MANUAL.

q. Review of the changes to the PROCESS CONTROL PROGRAM.

r. Review of the Annual Radiological Environmental Operating Report.

s. Review of the Radioactive Effluent Release Report.

t. Review of chame3_Lo_the Fire Protection Program, and+hanges-therete DAVIS-BESSE, UNIT 1 6-7 Amendment No. 27,86,93,98,109, 139,174,184,189,

l- L^ 3 ADMINISTRATIVE CONTROLS INFORMATION ONLYI l

l 6.8 PROCEDURES AND PROGRAMS (Continued) i

c. Surveillance and test activities of safety related equipment.

I d.. Industrial Security Plant implementation. l

e. Davis-Besse Emergency Plan implementation.

f. Fire Protection Program implementation.

g. The radiological environmental monitoring program,

h. The Process Control Program.

1. Offsite Dose Calculation Manual implementation.

6.8'2 Each procedure of 6.8.1 above, and changes thereto, shall be reviewed and approved prior to implementation as set forth in 6.5.3 above.

6.8.3 (deleted) 6.8.4 The following programs shall be established, implemented and maintained:

"- a. Primary Coolant Sources Outside Containment A program to reduce leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to as low as practical levels. The systems include makeup, letdown, seal injection, seal return, low pressure injection, containment spray, high pressure injection, waste gas, primary sampling and reactor coolant drain systems. The program shall include the following:

(i) Preventive maintenance and/or periodic visual inspection requirements, and

-(ii) Integrated leak test requirements for each system at refueling cycle intervals or less.

b. Jn-Plant Radiation Monitoring A program which will ensure the capability to accurately determine the airborne iodine concentration in vital areas under accident conditions. This program shall include the following:

(i) Training of personnel, (ii) Procedures for monitoring, and l (iii) Provisions for maintenance of sampling and analysis l equipment.

DAVIS-BESSE, UNIT 1 6-14 Amendment No. B, l

,12, EJ , 98,109,189

LAR 97-0015 ADMINISTRATIVE CONTROLS pg g7 6.8.4 (Continued)

I s. Post-Accident Sampline A program which will ensure the capability to obtain and analyse reactor coolant, radioactive iodines and particulates in plant gaseous effluents, and containment atmosphere samples under accident conditions. The program shall include the following:

L (i) Training of personnel, 1

(ii) Procedures for sampling and analysis, j 1

(iii) Provisions for maintenance of sampling and analysis equipment.

d. Radioactive Effluent Controls Program A program shall be provided conforming with 10 CFR 50.36a for the control of l radioactive effluents and for maintaining the doses to MEMBERS OF THE l PUBLIC from radioactive effluents as low as reasonably achievable. The program (1) shall be contained .in the ODCM, (2) shall be implemented by operating

]

procedures, and (3) shall include rernedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements:

1) Limitations on the operability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM.

2) Limitations on the concentrations of radioactive material released in liquid effluents to UNRESTRICTED AREAS conforming to 10 CFR Part 20, Appendix B, Tablel41, Column 2,

3) Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.MQ1,406 and with the methodology and parameters in the ODCM.

4) Limitations on the annual and quarterly doses or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released from each unit to UNRESTRICTED AREAS conforming to Appendix I to 10 CFR Part 50, l

5) Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar year l

in accordance with the methodology and parameters in the ODCM at least l every 31 days.

DAVIS-DESSE, UNIT I 614a Amendment No. 37,84,93,170,

1 lag 97-0015 ADMINISTRATIVE CONTROLS Page13 6.8.4 (Continued)

.d. Radioactive Ef0uent Controls Program (Continued)

6) Limitations on the operability and use of the liquid and gaseous effluent treatment rystems to ensure that the appropriate portions of these systems are used to reduce l

releases of radioactivity when the projected doses in a 31-day period would exceed 2 '

percent of the guidelines for the annual dose or dose commitment conforming to i Appendix ! to 10 CFR Part 50, l

7) Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the SITE BOUNDARY conforming to the doses associated with 10 CFR Part 20, Appendix B, Tablel-H, Column 1,

{

8) Limitations on the annual and quarterly air doses resulting from noble gases  ;

released in gaseous effluents from each unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50,

9) 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 greater than 8 days in gaseous effluents released from each unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50,

10) 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 Part 190.

c. Radiological Environmental Monitoring Procram A program shall be provided to monitor the radiation and radionuclides in the environs of the plant. The program shall provide (1) representative measurements I of radioactivity in the highest potential exposure pathways, and (2) verification of the accuracy of the effluent monitoring program and modeling of environmental exposure pathways. The program shall (1) be contained in the ODCM, (2) conform to the guidance of Appendix I to 10 CFR Part 50, and (3) include the following:

1) Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with tlw methodology and parameters in the ODCM,

2) A Land Use Census to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the monitoring program are made if required by the results of this census, and DAVIS-BESSE, UNIT 1 6-14b Amendment No.170,

ua 9>='s INFORMATION ONLY Page 19 ADMINISTRATIVE CONTROLS

• SPECIAL REP 6RTS 6.9.2 Special reports shall be submitted to the U.S. Nuclear Regulatory Cosmission in accordance with 10 CFR 50.4 within the time period specified for each report. These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable reference specifications:

a. ECCS Actuation, Specifications 3.5.2 and 3.543.

b. Deleted l

c. Deleted l

d. Deleted l

e. Deleted

f. Deleted

g. Inoperable Remote Shutdown System control circuit s or transfer switch (es) required for a serious control room or(ca)ble spreading room fire, Specification 3.3.3.5.2.

6.10 RECORD RETENTION 6.10.1 The following records shall be retained for at least five years:

a. Records and logs of facility operation covering time interval at each power level.

b. Records and logs of principal maintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety,

c. All REPORTABLE EVENTS.

d. Records of surveillance activities, inspections and calibrations required by these Technical Specifications.

e. Records of changes made to Operating Procedures.

, f. Records of radioactive shipments.

g. Records of sealed source and fission detector leak tests and results.

h. Records of annual physical inventory of all sealed source material of record.

DAVIS-BESSE, UNIT 1 6-18 Amendment 9,12,55,06,105, 135,170,174,107, 201

. Page 20 ADMINISTRATIVE CONTROLS 6.10.2 The following records shall be retained for the duration of the Facility Operating License:

a. Records and drawing changes reflecting facDity design modifications made to systems and equipment described in the Final Safety Analysis Report.

b. Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories, i i

c. Records of radiation exposure for all individuals entering radiation control areas.

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d. Records of gaseous and liquid radioactive material released to the environs.

e. Records of transient gnef-operational cycles for those facility components  !

I identified in 11SAR_ Table _5J-8444.

f. Records of reactor tests and experiments. i

g. Records of training and qualification for current members of the plant staff,

b. Records of in-service inspections performed pursuant to these Technical

- Specifications.

i. Records of Quality Assurance activit es i required by the QA Manual.

j. Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.

k. Records of meetings of the SRB and the CNRB.  ;

1. Records for Environmental Qualification which are covered under the provisions of paragraph 6.13.

m. Records of analyses required by the radiological environmental monitoring program that would permit evaluation of the accuracy of the analyses at a later date. This should include procedures effective at specified times and QA records showing that these procedures were followed.

7

o. Records of the service lives of all safety related hydraulic and mechanical snubbers including the date at which the service life commences and associated installation and maintenance records.

- p. Records of reviews performed for changes made to the OFFSITE DOSE CALCULATION MANUAL and the PROCESS CONTROL PROGRAM.

DAVIS-BESSE, UNIT 1 6-19 Amendment No. 8,12,86,94,170, Order dated Oct. 24,1980

LAR 97-0015 1

Page 2l ADMINISTRATIVE CONTROLS '

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l 6.12 IIIGH RADIATION AREA 4

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l As nrovided in naracranh 20.160l(c) of 10 CFR Part 20. the followine controls shall be annlied ighinh radiation areas in niace of the controls reagired by naracranh 201601(a) and (b) of 10 CFR Part 20: 1 1

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1 1he radiation source or from any surface nenetrated by the radiation:

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. - _ _ . - - - .. - . - - - - - - ~ . _ _ . - --- - - . ---- -

LAR 97-0015 - l Page R ADMINISTRATIVE CONTROLS 6.12.1 (continued)

)

a. Each entry way to such an area shall be barricaded and consnippously nostedas_a i hich radiation area. Such barricades may be onened_as necessaryjo ocrmit entry l

or exit of nersonnel or cauinment. i

b. Access to. and activities in. each such area shall be controlled by means of a Radiation Work Permit (RWP) or couivalent that includes snecification of radiation dose rates in the immediate work areafs) and other annronriate radiation proicction cauinment and measures,

c. Individuals cualified in radiation omtection nJocedures (e.e.. health nhysics 3

nersonnell and nersonnel continuousiv escorted by such individuals may be exemnted from the reauirement for a RWP or couivalent while nerformine their assiened duties nrovided that they are followine olant radiation nrotection procedures for entry to. exit from. and work in such areas.

d. EaclLindividual (whether alone or in a crouc) enterine such an area shall nossess:

1. A radiation monitorine device that continuousiv disnlavs radiation dose rates in the area: or i 2 A radiation monitorine device that continuousiv inteerates the radiation dnse rates in the area and_ alarms when the device's dose alarm setnoint is  ;

mached. with2n annronriate alarm setnoint. or j 3. A radiation monitorine device that continuously transmits dose rate and cumulatirellose_information to alemoteleceive_Lmonitored by radiation nrotection nersonnel resnonsible for controlline nersonnel radiation pJoosure within thcarcaar

4. A self-readine dosimeter (e.e.. nocket ionization chamber or electronic dosimeter) and be under the surveillance. as snecified in the RWP or cauivalent. while in the area. by means of closed circuit television. by nersonnel aualified in radiation nrotection orocedures resnonsible for controlline nersonnel radiation exnosure in the area,

c. Excent for individuals aualified inladiation nrotection nrocedures. entry into such areas shall be made only after dose rates in the area have been determined and entry nersonnel are knowledeeable of them, 6.12.2 Locked hich radiation areas with dose rates creater than 1.0 rem / hour at 30 centimeters from the radiation source or from any surface nenetrated by the radiation. but less than 500 rads / hour at 1 meter from the_ radiation source or from any surface nenetrated by the radiation:

DAVIS-BESSE, UNIT I 6-20a

LAR 97-0015 Page 23 ADMINISTRATIVE CONTROLS 6.12.2 (continued)

'.il

• Each entryway to such an area shall be consni uousiv nosted as a high radiation

treg_and shall be orovided with a locked door. eate. or other barrier that orevents unauthorized entry. and. in addition

1. All keys to such doors. cates. or other barriers shall be maintained under the administl ative control of theshiftsupervisor. radiation protection manacer. or his or her desience.

2. Doors. cates. or other barriers shall remain locked excent durine nsriods of personnel or eaninment entry or exit.

b. Access to. and activities in. each such area shall be controlled by means of an RWP or cauivalent that includes snecification of radiation dose rates in the immediate work area (s) and other annropriats_ radiation orotection enu_inment and measures.

c. IndividunLssiualified in radiation nrotection orocedures may be exemnted from the Ignuirement for a RWP or enuivalent while_nerformine radiation surveys in such areas nrovided that they are followine ojnnt radiation orotection orocedures for entry to. exit from. and work in such areg

d. Each individual (whether alone or in a crogn) enterine such an area shallpossess:

J. A radiation monitorine device that continuously intetrates theladiation glossaales in the area and alarms when the device's dose alarm setnoint is reached. with an apurontiate alarm setnniakor

2. A radiation monitorine device that continuousiv transmits dose rate _and pJJmulative dose infonnation to a remote receiver. monitored by radiation protection nersonnel responsible for controlline personnel radiatiom CXnossure within the area with the means to communicate with and control every individualinJhe_ar_ea or L_ A scEreadinLdosimeter (e.e.. nocket ionization chamber or electronic l dosimeter) and, (i) Be under the surveillance. as specified in the RWP or eauivalent.

while in the area. by an individuaLoualified in radiation orotectio_u nmcedures. equipped with a radiation monitorine device that continuousltdisnktyslastiation dose rates in the_arca: who is resnonsible for controlline nersonnel exoosure within the arcild2I i

I DAVIS-BESSE, UNIT 1 6-20b l

LAR 97-0015 E"EC ADMINISTRATIVE CONTROLS 1

l l

6.12.2 (continued) I 1

(ii) Be under the surveillance as soccified in the RWP or cauivalent.

while in the area. by means of closed circuit television. by personnel gualified in radjation orotection orocedures responsible for controllintnersonnel radiation exposure in the area and with the j means to communicate with and control every individual in the area. '

GI

4. In those cases whng options (2) and (3). above. me imoractical or determined to be inconsistent with the "As Low As is Reasonably Achievable" orincjnle. a radiation monitorine device that continuottsly l

@olavs radiation dose rates in the area.

1

e. Except for an individual cualified in ra@Jion protection orocedures. entry into I sucitarcas shall be madtonlLafierdose rates _ituhe_arenliave been determined and entrv oersonnel are knowledccable of thenn

f. Such individuaLateas thature within a larner_arcidhaLis controlled as a hich radialinrtarea. where no enclosure exists for the ontoose of lockine and where no enclosyre can reasonably be construcleil arouniihe individual area. need not be controlled by a locked door or catelut shall be barricadedand consoicuous. and_a clearly visible flashine licht shtdLbc_ activated at thtarea as a warnine device.

DAVIS-BESSE, UNIT 1 6-20c

LAR 97 0015

. Page ~25 ADMINISTRATIVE CONTROLS 6.14 PROdESS CONTROL PROGRAM (PCP)

Changes to the PCP:

a. Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.2.p. This documentation shall contain:

1) Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s), and

2) A determination that the change will maintain the overall conformance of the  !

solidified waste product to existing requirements of Federal, State, or other applicable regulations.

b. Shall become effective after resiew and acceptance by the SRB and the approval of the Plant Manager.

6.15 OFFSITE DOSE CALCULAllO_N_. MANUAL (ODCM) i l

Changes to the ODCM:

a. Shall be documented and records of reviews performed shall be retained as l required by Specification 6.10.2.p. This documentation shall contain:

1

1) Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s), and

2) A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.1LO2_406,40 CFR Part 190,10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose or setpoint calculations.

b. Shall become effective after review and acceptance by the SRB and the approval of the Plant Manager.

c. Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as part of or concurrent with the Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made.

Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month / year) the change was implemented.

DAVIS-BESSE, UNIT 1 6-22 Amendment No. 86,170,184