ML17331A286

Proposed Tech Specs Section 6 Re Radioactive Effluent Reporting & Nuclear Safety & Design Review Committee Membership

ML17331A286
Person / Time
Site:	Cook
Issue date:	04/16/1993
From:	INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:
Shared Package
ML17331A284	List: ML17331A283 ML17331A286
References
NUDOCS 9304220165
Download: ML17331A286 (31)

Text

ATTACHMENT 2 TO AEP:NRC:0659V EXISTING TECHNICAL SPECIFICATIONS PAGES MARKED TO REFLECT PROPOSED CHANGES 9304220ib5 9304ib ere anaCZ Oa0003iS P -- PDR

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ADMINISTRATIVE CONTROLS c, chemistry and xadiochemistzy

d. metallurgy

e. instzumentation and control

f. radiological safety

g. mechanical and electrical engineering

h. quality assurance practices COMPOSITION 6.5.2.2 The NSDRC shall be composed of the follovtng regular membezs:

Group

l. Vice President - Nuclear Operations (NSDRC Chairman)

2. nager, Nuclear Safety ask Licensing+- Nuclear Operations (NSDRC Secretary) 4 MESSt~&

3. Plant Manager - Donald C. Cook Nuclear Plant

4. Executive Assistant to the Pzesidant - Indiana Michigan Povez Company

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Senior Vice President and Chief Engineer V(R ~i~

Vice President - Pzo]ect Management and Construction K8 i+ + E4 dl I cBJ lp Chief lE/uc1d3s- +ieger Assistant Vice President - Civil Engineering (0+. Assistant Vice Pzesident - Design

}) Q. Division Manager - Environmental and Technical Assessment Director - Quality Assurance 94v- ~~~~ ~ay;71~;tl1 +~ pj~g( h Additional members and Vice Chairman may be appointed by the

~d1 CYid.F ALTERNATE MEMBERS iP 2) ('~, ~~z'~ident P~glkllp 6/Kl 6.5.p..3 as he Dasdgmaead shall designate.

alearmaee Zn members shall be appeimeed sammy. or addition, temporary alternate by eha deedeseQ such other pe son members may'be

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appointed by the NSDRC Chairman to serve on an interim basis, as zequized.

Temporary alternate members are empovezed to act on the behalf of the regular or designated alternate members for vhom they substitute.

COOK NUCLEAR PLANT - UNIT 1 6-7 AMENDMENT NO. )7/~

ADMINISTRATIVE CONTROLS The OFFSXTE DOSE CALCUlATION MANUAL and implementing procedures at least once per 24 months.

The PROCESS COHTROL PROCRAM and implementing procedures for solidification of radioactive vastes at least once per 24 months.

The performance of activities required by the Quality Assurance Program to meet the criteria of Regulatory Guide 1.21, Rev. 1, June 1974 and Regulatory Guide 4.1, Rev. 1, AprQ. 1975 at, least once pez 12 months.

Any other azea of facility operation considered appropriate by the NSDRC.

AUTHORITY V(c Pm'sldane N-u~4ar C anions 6.5.2.9 The NSDRC shall report to and advise the

. AEPSC, on those areas of t responsibility specified in Sections 6.5.2.7 and 6.5.2.8.

RECORDS 6.5.2.10 Records of NSDRC activities shall be pzepared, approved and distributed as indicated belov:

ai Minutes of each HSDRC meeting shall be prepared, approved and l5 vithin 14 days folloving each meeting. I Reports of zevievs enco i S5M assed by Section 6.5.2.7 above, shall be prepared, approved and e vithin 14 days follo~ing completion of the raviev, i~uc C~ Audit reports encompassed'y Section 6.5 2.8 above, shall be forvazded to the ice President- s AEPSC, and to the management positions responsible for the areas audited vithin 30 days after completion of the audit.

6.5.3 TECHNICAL RZVIZV AHD CONTROL 6.5.3.1 Activities vhich affect nuclear safety shall be conducted as foilovs:

Proceduzes required by Specification 6.8 and other pzocedures which affect plant nuclear safety, and changes thereto, 'shall be prepared, revieved and approved. Each such procedure or procedure change shall be revieved by a qualified individual/group other than the individual/group vhich prepared the procedure oz procedure change, but vho may be from the same organisation as the individual/group vhich prepared the procedure or procedure .

change. Procedures other than Plant Manager Procedures COOK NUCLEAR PLANT " UNIT 1 6-10 AMENDMENT NO. P~~

3 ANNUAL RADIOLOGLCAL ENVIRONHEHTAL OP~TING REPORT 6,9.1.6 Routine radiological environmental operating reports covering the operation of the uait during the previous calendar year shall be submitted px'ior to Ywy 1 of each year.

6,9,1,7 The annual radiological environmental operating xeports shall incLude summaries, interpretations, and statistical evaluation of the xesults of the radiological environmental suxveillaace activities for the report period, including a compaxison vith preoperational studies, operational controls (as appropriate), and prevfous envtzonmeatal survefllance repox;ts and an assessment of the observed impacts of the plant operation on the environment. The xeports shall also iaclude the results of the land-use census required by Specification 3.12.2. If harmful effects or evidence of ix'reversible damage are detected by the monitoring, the report shall provide an analysis of the problem and a planned course of action to alleviate the pxoblem.

The annual radfological environmental operating reports shall include summarized and tabulated results in the format of 3.12-2 of all radiological environmental samples taken during the report period. In the event that some results are not available for inclusion vith the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as'oon as possible in a supplementary x'aport.

The xeports shaLL also include the foLLovtng: a summazy dcsczfption of the radiological environmental monitoring progzam including sampling methods for each sample type, size, and physical characteristics of each sample type, sampLe prepaxatf.on methods, analytical methods, and measuring equipment used; a map of all sample locations keyed to a table going distances and directions from one reactor; the result of land-use census zcquizad by the Specification 3.12.2; and the results of particfpatfon ia the Iatex'Laboratory Compaxison Progxam xequizcd by Specificatioa 3.12.3.

ANNUAL RADIOACTIVE EPFLUEHT RELEASE REPORT IR 6.9.L.8 Routine radioactive effluent rel'ease report/ covering the operation of the unit duzing the previous months of operation shall be submitted vithin ~

90 days aftez January L Of ~4k QN r 6.9.1.9 The radioactive effluent release report/ shall include a summary of the quantities of radioactive liquf.d and gaseous effluents aad solid vaste released from the uaits as outlined ia Regulatory Guide 1.21, "Zeasuriag, Evaluating and Reporting in Solid Vastes and Releases of Radioactfve 3

A single submittal may be made for a multiple unit statfon. The submittal should combine those sections that are common to all units at the station;hovever, for units vith separate zadvaste systems, tha submittaL shall specify the releases ox xadioactive matexial for each unit.

COOK NUC~~ PLAVZ - UNIT 1 6-15

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~~MIVXS~~. TIVE CO OLS Matezials in Liquid and Gaseous Effluents from Light-Rater Cooled Huclear Pover Plants," vith data summazixed on a quarterly basis folloving the format of hppendix B, thereof.

9o The radioactive effluent release report to be submitted~ days after hourly meteorological data collected duxing the reporting period., This summary may be either in the form of an hour-by-hour Listing of vtnd speed, vtnd direction, atmospheric stability, and precipitation (if measured) on magnetic tape, ox in'the form of ]oint fze'quency distributions 6f vind q 0 speed, vind direction and atmospheric stability. The report submitted 4F days after January 1 shall includ~ an assessment of the radiation doses due to the radioactive liquid and gaseous effluen released from the unit or station. duzing the previous calendaz yeax. repor@ shall include an assessment of the radiation doses from radioactive liquid and gaseous effluents to members of the public due to theix'ctivities inside the site boundary (rigure 5.1-3) dux'ing the reporting period. hLL assumptions used in making these assessments Location) shall be included in (i., specific activity, exposure time and report/. The meteoxological conditions concur ent vith the time of zelease of radioactive material's in gaseous effluents (as determined by sampling frequency and measurement) shall be used for determining the gaseous-pathvay doses. The assessment of radiation doses shall be performed in accordance vith the Offsite Dose Calculation Manual (ODCM) .

Qb The radioactive effLuent release rcport to be submitted %% days after January 1 of each year shall also include an assessment of radiation doses to the LIkely most exposed membez of the public from reactor releases and othez neaxby uranium fuel cycle sources (including doses fzom primary effluent pathvays and dixect radiation) foz the previous 12 consecutive months to shov conformance vith 40 CFR 190, Environmental Radiation Protection Standards for Nuclear Povez Operation. hcceptable methods for calculating the dose contribution from liquid and gaseous effluents axe given in Regulatory Cuide 1.109, Rev. l.

The zadioac ive effluent release report shall include the follovtng informatioa for each type of solid vaste shipped offsite during the report period:

a~ Volume (cubic meters),

b. Total curie quantity (specify vhether determined by measurement or estimate),

Principal radionuclides (specify vhether determined by measurement ox estimate),

COOK HUC~~ PLun' tmIT 1 6-16 hMEHDMEHT HO PP g54-

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p hDMZNZSTRATZVE CONTROLS

d. Type of waste (e.g., spent resin, compacted dry waste, evapozator bottoms),

e. Type of container (e.g., LSA, Type A, Type B, Large ~ntity), and

f. Solidification agent (e.g., cement).

The zadioactive effluent release report shall include unplanned releases

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fzom the site to unrestricted areas of radioactive materials in gaseous and liquid effluent on a quarterly basis.

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The radioactive effluent release report)( shall include any change to the PROCESS CONTROL PROGRhH (PCP) and the OFFSITE DOSE CALC~TZON HhHUhL (ODCM) made duzing the repozting period.

MONTHLY RZhCTOR OP~TING REPORT 6.9.1.10 Routine zepozts of operating statistics and shutdown experience, including documentation of all challenges to the PORVs or safety valves, shall be submitted on a monthly basis to the U.S. Nuclear Regulatory Commission (httn: Document Control Desk), Vashington, D.C. 20555, with a copy to the Regional Office no latez than the 15th of each month following the calendar month covered by the report.

CORE OPKUlTZNG LIMITS REPORT P

6.9.1.11.1 Core operating 1&its shall be established and documented in the CORE OP~TING LZMXTS REPORT before each reload cycle or any remaining part of a reload cycle for the following:

a. Moderator Temperature Coefficient Limits for Specification 3/4.1.1.4,

b. Rod Drop Time Limits for Specification 3/4.1.3.3, c; Shutdown Rod'Insertion Limits for Specification 3/4.1.3.4,

d. Contxol Rod Insertion Limits for Specification 3/4.1.3.5,

e. hxial Flux Difference for Specification 3/4,2.1, Heat Flux Hot Channel Factor for Specification 3/4.2.2,

g. Nuclear Enthalpy Rise Hot Channel Factor for Specification 3/4.2.3, and

h. allowable Power Level for Specification 3/4.2.6.

6.9.1.11.2 The analytical methods used to detezmine the core operating limits shall be those previously reviewed and approved by the NRC in:

a. VCR-9272-P-h, "Vestinghouse.Reload Safety Evaluation Methodology,"

July 1985 (Vestinghouse Proprietary),

COOK NUCUDlR PLhHT - UNIT 1 6-17 h2KHDMENT NOPP~~

ADMINISTRATIVE CONTROLS c, chemi.stry and zadiochamistry

d. me tallurgy

e. instrumentation and control radi.ological safety

g. mechanical and electzical engineering

h. quality assurance practices COMPOSITION 6.5.2.2 The NSDRC shall be composed of the folloving regular members:

Sroup

~~

1. Vice President - Nuclear Operations (NSDRC Chairman)

2. n Manager, Nuclear Safety

)

M Licensing+- Nuclear Operationsl hp (NSDRC Secretary)

3. Plant Manager - Donald C. Cook Nuclear Plant

4. Executive Assistant to the President - Indiana Michigan Pover Company Senior Vice President and Chief Engineer I+. Ca7ss Bitt ad Cll'+ gsi '

7P.'i.ca President - Pzo)ect Management and Construction ehieINUduarP im~

gg. Assistant Vice President - Civil Engineering Assistant Vice President - Design

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Division Manager - Environmental and Technical Assessment Director - Quality Assurance Q +., I~I~on-Man~pm m~, Plans ard lhjrans- hI(de 0

members and Vice Chairman may be appointed by the Smear i'dditional

~dan4 ~ERS s

avd Chick Cp.~p Owiccr, 0 ed >'<

ALTERNATE P~(k 6.5.2.3 Daslgnaaacb alaasnasa nanbass shall ba apyainaad by aba '.bsngan"Q niiQQ+

or such other pe son as he shall designate.'n addition, tamporazy alternate members may be appointed by the NSDRC Chairman to sazva on an interim basis, as required.

Temporary alternate members are empovezed to act on the behalf of tha regular .or designated alternate members for, vhom they substitute.

COOK NUCLEAR PLANT - UNIT 2 6-7 AMENDMENT NO. 7)g~

ADMINISTRATIVE CONTROLS The OFFSITE DOSE CALCUIATION MANUAL and implementing procedures at least once per 24 months.

k. The PROCESS CONTROL PROGRAM and implementing procedures for solidification of zadioactive vastas at lease once per"24 months.

The performance of activities requizad by the ~1$ .ty Assurance Pxogram to meet the criteria of Regulatory Guide 1.21, Rav. 1, Jane 1974 and Regulatory Guide 4.1, Rav. 1, hpril 1975 at least once par 12 months.

hny other area of facility operation c'onsidared appropriate'y the NSDRC.

arrBORZTT 6.5.2.9 Th g

NSDRC

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shall report to and advise the Vice Pzesident- AEPSC, on those azeas of responsibility specified in Sections 6.5.2.7 and 6.5.2.S.

RECORDS 6.5.2.10 Records of NSDRC activities shall be prepared, approved and distributed as indicated balov:

a. Minutes of each NSDRC meeting shall be prepared, approved and tSS

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vithin 14 days folloving each meeting.

b. Reports of zeviavs enc ass by Section 6.5.2.7 above, shall be =

prepared, approved and e-Vice vithin 14 days folloving complacion of the raviev.

Ca atdlt reports aocospassad by Sactidk 6.6.2.8 abova, shall. ba ggC+O f}jg for the areas audicad vithin 30 days after completion of the audit.

6.5.3 TECHNICAL REVIEW AND CONTROL 6.5.3.1 hctivities vhich affect nucleaz safety shall be conducted as follovs:

a. Pzocadures required by Specification 6.8 and ocher procedures vhich affect plane nuclaaz safety, and changes thereto, shall be prepared, zaviaved and approved. ,Each such, procedure or procedure change shall be ravieved by a qualified individual/group ocher than cha individual/group vhich prepared the procedure or procedure change, but vho may be from the same organization as the individual/group vhich prepared the procedure or procedure change. Procedures other than Plant Manager Procedures COOK NUCLEAR PLANT - UH:s'.T 2 6-10 AMENDMENT NO. 7P ~~

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'DMINISTRATIVE CONTROLS 3

ANNUAL RADIOLOGICAL EHVIRONMEVZAL OP~TING REPORT 6.9.1.6 Routine radiological environmental operating reports covezing the operation of the unit dux'ing the previous calendaz year shall be submitted prior to May 1 ox each year.

6.9.1.7 The annual radiological envtxonmental operating reports shall include summaries, interpretations, and statistical evaluation of the results of the radiological environmental surveillance activities for the report period, including a comparison vith preoperational studies, operational controls (as appropriate), and previous environmental suxveillance reports and an assessment of the observed impacts of the plant operation on the environment. The reports shall also include the zesults of the land-use census required by Specification 3.12.2. If harmful effects or evidence of irreversible damage are detected by the monitoring. the report shall provide an analysis of the pzoblem and a planned couzse of action to alleviate the problem.

The annual radiological envixoamental operating reports shall include summazi ed and tabulated results in the format of 3.12-2 of all zadiological environmental samples taken during the report period. In the event that some results are not available for inclusion vith the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary x epoxt.

The reports shall also include the foilovtng: a summary descziption of the radiological environmental monitoring program including sampling methods for each sample type, si=e, and physical chaxactezistics of each sample type, sample prepaxation methods, analytical methods, and measuring equipment used; a map of all sample locations keyed to a table giving distances and directions from one xeactoz; the result of land-use census required by the Specification 3.12.2; and the results of participation in the Interlaboratory Comparison Progzam required by Specification 3,12.3.

4$ $~ANNUAL RADIOACTIVE EFFLUENT RE~~E REPORT 19 6.9.1,8 Routine radioactive effluent release report)( co~ering the operation of the unit dux'ing the px'eviou months of operation shall be submitted vithin k0'ays after Januazy 1 a~uk~ of each yeaz.

9a 6.9.1.9 The radioactive effluent zelease report)f shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid vaste released from the units as outlined in Regulatory Guide 1.21, "Measuring.

Evaluating. and Reporting in Solid Vastes and Releases of Radioactive 3

h single submittal may be made for a multiple unit station. The submittal should combine those sections that aze common to all units at the station; hovever, for units vith sepaxate radvaste systems, the submittal shall specify the releases of radioactive matazial foz each unit.

~mn COOK NUC~~ PLANT - UNIT 2 6-15 No.>y,rgb psSf

h3MZNZSTRATXVE CONTROLS Materials in Liquid and Gaseous Effluents from Light-Pater Cooled Nuclear Povez Plants," vith data summarixed on a quazterly basis folloving the fozmat of hppendix B, thereof.

The radioactive effluent release zeport to be submitted 48'ays after hourly meteorological data collected during the zeporting peziod. This summary may be either in the form of an hour-by-hour listing of vind speed, vtnd direction, atmosphezic stability, and precipitation (if measured) on magnetic tape, or in the fora, of joint frequency distributions of vtnd speed, vtnd direction and atmospheric stability. The report submitted~I>

days after January 1 shall include an'assessment of the radiation doses due to the zadioactive liquid and gaseous effluan eleased from the unit or station duzing the pxavious calendar.yeaz. report/ shall include an assessment of the radiation doses from radioactive liquid and to members of the public due to theiz activities inside the site gaseous'ffluents boundary (Ff.gure 5.1-3) dux'ing the reporting pexiod. All assumptions used in making these assessments (i.~ specific activity, exposure time and

'ocation) shall be included in eiQL4 report(. The meteorological conditions concur ent. vt.th the time of release of radioactive materials in gaseous effluents (as determined by sampling frequency and measurement) shall be used for detezmining the gaseous pathvay doses. The assessment of radiation doses shall be performed in accordance, vith the Offsite Dose Calculation Ywnual (ODCM) .

ge The zadioactive effluent release repox't to be submitted g days of each year shall also include an assessment of zadiation doses aft'anuary' to the likely most exposed membez of the public f om reactor releases and other nearby ux;anium fuel cycle sources (including doses from primary effluent pathvays and direct radiation) for the previous '12 consecutive months to shov conformance vt.th 40 CFR 190, Environmental Radiation Protection Standards for Nucleax'ovez Operation. hcceptable methods for calculating the dose contribution fzom liquid and gaseous effluents are given in Regulatozy Cuide 1.109, Rev. 1.

The radioactive effluent release report shall include the follovtng information for each type of solid vaste shipped offsite dur~mg the zepor" period:

Volume (cubic meters),

b. Total curie quantity (specify vhether determined by measuxement or estimate),

C ~ Principal radionuclides (specify vhether determined by measurement ox'stimate),

COOK NUC~~ PLhHT - UNIT 2 6-16

ADMINISTRATIVE CONTROLS

d. Type of vaste (e.g., spent resin, compacted dry vaste, evaporatox bottoms),

e. Type of container (e.g., LSA, Type A, Type 3, Large Quantity), and

f. Solidification agent (e.g., cement).

The radioactive effluent release report shall include unplanned releases from the site to unrestricted areas of radioactive materials in gaseous and liquid effluent on a quarter3.y basis.

The radioactive effluent release report/ shall include any change to the PROCESS CONTROL PROGRAM (PCP) and the OFFSITE DOSE CALCULATION MANUAL (ODCM) made dux'ing the reporting period.

MONTHLY REACTOR OPERATING REPORT 6.9.1.10 Routine reports of operating statistics and shutdovn experience, including documentation of all challenges to the PORVs or safety valves, shall be submitted on a monthly basis to the U.S. Nuclear Regulatory Commission (Attn: Document Contzol Desk), Vashington, D.C. 20555, vith a copy to the Regional Office no later than the 15th of each month folloving the calendaz month covexed by the report.

CORE OPERATING LIMITS REPORT 6.9,1.11.1 Core operating limits shall-be established and documented in the CORE OPERATING LEES REPORT before each reload cycle oz any remaining pax't of a reload cycle for the follovtng:

a. Moderator Temperatuze Coefficient Limits for Specification 3/4.1.1.4,

b. Rod Drop Time Limits for Speci ication 3/4.1.3.4,

c. Shutdown Rod Insertion Limits foz Specification 3/4.1.3.5,

d. Control Rod Insertion Limits for. Specification 3/4.1.3.6,

e. Axial Flux Difference for Specification 3/4.2.1, Heat Flux Hot Channel Factor for Specification 3/4.2.2,

g. Nuclear Enthalpy'ise Hot Channel Factor for Specification 3/4.2.3, and

h. Allo~able Pover Le~el for Specification 3/4.2.6.

6.9.1.11.2 The analytical methods used to determine the coxe operating limits shall be those previously zevieved and approved by the NRC in:

COOK NUCLEAR PLANT - UNXT 2 6-17 ABER)MENT NO. P$ ~~

ATTACHMENT 3 TO AEP'NRC:0659V PROPOSED REVISED TECHNICAL SPECIFICATIONS PAGES

ADMINISTRATIVE CONTROLS

c. chemistry and radiochemistry

d. metallurgy

e. instrumentation and control

f. radiological safety

g. mechanical and electrical engineering

h. quality assurance practices COMPOSITION

,6.5.2.2 The NSDRC shall be composed of the following regular members:

1. Vice President - Nuclear Operations (NSDRC Chairman)

Group Manager, Nuclear Safety, Licensing & Assessment - Nuclear Operations (NSDRC Secretary)

3. Plant Manager - Donald CD Cook Nuclear Plant 4, Executive Assistant to the President - Indiana Michigan Power Company

5. Senior Vice President and Chief Engineer

6. Vice President and Chief Electrical Engineer

7. Vice President - Project Management and Construction

8. Chief Nuclear Engineer

9. Assistant Vice President - Civil Engineering

10. Assistant Vice President - Design

11. Division Manager - Environmental and Technical Assessment

12. Director - Quality Assurance

13. Manager, Plans and Programs - Nuclear Operations Additional members and Vice Chairman may be appointed by the President and Chief Operating Officer.

ALTERNATE MEMBERS 6.5.2.3 Designated alternate members shall be appointed by the President and Chief Operating Officer or such other person as he shall designate. In addition, temporary alternate members may be appointed by the NSDRC Chairman to serve on an interim basis, as required. Temporary alternate members are empowered to act on the behalf of the regular or designated alternate members for whom they substitute.

COOK NUCLEAR PLANT - UNIT 1 6-7 AMENDMENT NO.

ADMINISTRATIVE CONTROLS j . The OFFSITE DOSE CALCULATION MANUAL and implementing procedures at least once per 24 months.

k. The PROCESS CONTROL PROGRAM and implementing procedures for solidification of radioactive wastes at least once per 24 months.

1. The performance of activities required by the Quality Assurance Program to meet the criteria of Regulatory Guide 1.21, Rev. 1, June 1974 and Regulatory Guide 4.1, Rev. 1, April 1975 at least once per 12 months.

m. Any other area of facility operation considered appropriate by the NSDRC.

AUTHORITY 6.5.2.9 The NSDRC shall report to and advise the Vice President - Nuclear Operations, AEPSC, on those areas of responsibility specified in Sections 6.5.2.7 and 6 '.2.8.

~ECORDS

6. 5.2. 10 Records of NSDRC activities shall be prepared, approved and distributed as indicated below:

a. Minutes of each NSDRC meeting shall be prepared, approved and issued within 14 days following each meeting.

b. Reports of reviews encompassed by Section 6.5.2.7 above, shall be prepared, approved and issued within 14 days following completion of the review.

c ~ Audit reports encompassed by Section 6.5.2.8 above, shall be forwarded to the Vice President - Nuclear Operations, AEPSC, and to the management positions responsible for the areas audited within 30 days after completion of the audit.

6 5 3 TECHNICAL REVIEW AND CONTROL 6.5.3.1 Activities which affect nuclear safety shall be conducted as follows:

a. Procedures required by Specification 6.8 and other procedures which affect plant nuclear safety, and changes thereto, shall be prepared, reviewed and approved. Each such procedure or procedure change shall be reviewed by a qualified individual/group other than the individual/group which prepared the procedure or procedure change, but who may be from the same organization as the individual/group which prepared the procedure or procedure change. Procedures other than Plant Manager Procedures COOK NUCLEAR PLANT - UNIT 1 6-10 AMENDMENT NO.

ADMINISTRATIVE CONTROLS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 6.9.1.6 Routine radiological environmental operating reports covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of each year.

6.9.1.7 The annual radiological environmental operating reports shall include summaries, interpretations, and statistical evaluation of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, operational controls (as appropriate), and previous environmental surveillance reports and an assessment of the observed impacts of the plant operation on the environment. The reports shall also include the results of the land-use census required by Specification 3.12.2. If harmful effects or evidence of irreversible damage are detected by the monitoring, the report shall provide an analysis of the problem and a planned course of action to alleviate the problem.

The annual radiological environmental operating reports shall include summarized and tabulated results in the format of 3.12-2 of all radiological environmental samples taken during the report period. In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.

The reports shall also include the following: a summary description of the radiological environmental monitoring program including sampling methods for each sample type, size, and physical characteristics of each sample type, sample preparation methods, analytical methods, and measuring equipment used; a map of all sample locations keyed to a table giving distances and directions from one reactor; the result of land-use census required by the Specification 3.12.2; and the results of participation in the Interlaboratory Comparison Program required by Specification 3.12.3.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT~

6.9.1.8 Routine, radioactive effluent release report covering the operation of the unit during the previous 12 months of operation shall be submitted within 90 days after January 1 of each year.

6.9.1.9 The radioactive effluent release report shall include a summa'ry of the quantities of radioactive liquid and gaseous effluents and solid waste released from the units as outlined in Regulatory guide 1.21, "Measuring, Evaluating and Reporting in Solid Wastes and Releases of Radioactive 3

A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station;however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material for each unit.

COOK NUCLEAR PLANT - UNIT 1 6-15 AMENDMENT NO. M, 448, ~

ADMINISTRATIVE CONTROLS Materials in Liquid and Gaseous Effluents from Light-Water Cooled Nuclear Power Plants," with data summarized on a quarterly basis following the format of Appendix B, thereof.

The radioactive effluent release report to be submitted 90 days after January 1 of each year shall include a quarterly summary of hourly meteorological data collected during the reporting period. This summary may be either in the form of an hour-by-hour listing of wind speed, wind direction, atmospheric stability, and precipitation (if measured) on magnetic tape, or in the form of joint frequency distributions of wind speed, wind direction and atmospheric stability.

The report submitted 90 days after January 1 shall include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year. This report shall include an assessment of the radiation doses from radioactive liquid and gaseous effluents to members of the public due to their activities inside the site boundary (Figure 5.1-3) during the reporting period. All assumptions used in making these assessments (i.e., specific activity, exposure time and location) shall be included in this report. The meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents (as determined by sampling frequency and measurement) shall be used for determining the gaseous pathway doses. The assessment of radiation doses shall be performed in accordance with the Offsite Dose Calculation Manual (ODCM).

The radioactive effluent release report to be submitted 90 days after January 1 of each year shall also include an assessment of radiation doses to the likely most exposed member of the public from reactor releases and other nearby uranium fuel cycle sources (including doses from primary effluent pathways and direct radiation) for the previous 12 consecutive months to show conformance with 40 CFR 190, Environmental Radiation Protection Standards for Nuclear Power Operation.

Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev. 1.

The radioactive effluent release report shall include the following information for each type of solid waste shipped offsite during the report period:

a. Volume (cubic meters),

b. Total curie quantity (specify whether determined by measurement or estimate),

C. Principal radionuclides (specify whether determined by measurement or estimate),

COOK NUCLEAR PLANT - UNIT"'1 6-16 AMENDMENT NO. 49, ~

DMINISTRATIVE CONTROLS

d. Type of waste (e.g., spent resin, compacted dry waste, evaporator bottoms),

e. Type of container (e.g., LSA, Type A, Type B, Large Quantity), and

f. Solidification agent (e.g., cement:).

The radioactive effluent release report shall include unplanned releases from the site to unrestricted areas of radioactive materials in gaseous and liquid effluent on a quarterly basis.

The radioactive effluent release report shall include any change to the PROCESS CONTROL PROGRAM (PCP) and the OFFSITE DOSE CALCULATION MANUAL (ODCM) made during the reporting period.

ONTHLY REACTOR OPERATING REPORT 6.9.1.10 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the PORVs or safety valves, shall be submitted on a monthly basis to the U.S. Nuclear Regulatory Commission (Attn:

Document Control Desk), Washington, D.C. 20555, with a copy to the Regional Office no later than the 15th of each month following the calendar month covered by the report.

CORE OPERATING LIMITS REPORT 6.9.1.11.1 Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT before each reload cycle or any remaining part of a reload cycle for the following:

a. Moderator Temperature Coefficient Limits for Specification 3/4.1.1.4,

b. Rod Drop Time Limits for Specification 3/4.1.3.3, c ~ Shutdown Rod Insertion Limits for Specification 3/4.1.3.4,

d. Control Rod Insertion Limits for Specification 3/4.1.3.5,

e. Axial Flux Difference for Specification 3/4.2.1,

f. Heat Flux Hot Channel Factor for Specification 3/4.2.2,

g. Nuclear Enthalpy Rise Hot Channel Factor for Specification 3/4.2.3, and

h. Allowable Power Level for Specification 3/4.2.6.

6.9.1.11.2 The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC in:

a. WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology,"

July 1985 (Westinghouse Proprietary),

COOK NUCLEAR PLANT - UNIT 1 6-17 AMENDMENT NO. 69, ~

ADMINISTRATIVE CONTROLS C. chemistry and radiochemistry

d. metallurgy

e. instrumentation and control

f. radiological safety

g. mechanical and electrical engineering

h. quality assurance practices COMPOSITION 6.5.2.2 The NSDRC shall be composed of the following regular members:

1. Vice President - Nuclear Operations (NSDRC Chairman)

2. Group Manager, Nuclear Safety, Licensing & Assessment - Nuclear Operations (NSDRC Secretary)

3. Plant Manager - Donald C. Cook Nuclear Plant

4. Executive Assistant to the President - Indiana Michigan Power Company

5. Senior Vice President and Chief'Engineer

6. Vice President and Chief Electrical Engineer

7. Vice President - Project Management and Construction

8. Chief Nuclear Engineer

9. Assistant Vice President - Civil Engineering

10. Assistant Vice President - Design

11. Division Manager - Environmental and Technical Assessment

12. Director - Quality Assurance

13. Manager, Plans and Programs - Nuclear Operations Additional members and Vice Chairman may,be appointed by the President and Chief Operating Officer.

ALTERNATE MEMBERS 6.5.2.3 Designated alternate members shall be appointed by the President and Chief Operating Officer or such other person as he shall designate. In addition, temporary alternate members may be appointed by the NSDRC Chairman to serve on an interim basis, as required. Temporary alternate members are empowered to act on the behalf of the regular or designated alternate members for whom they substitute.

COOK NUCLEAR PLANT - UNIT 2 6-7 AMENDMENT NO.

Cq ADMINISTRATIVE CONTROLS The OFFSITE DOSE CALCULATION MANUAL and implementing procedures at least once per 24 months.

The PROCESS CONTROL PROGRAM and implementing procedures for solidification of radioactive wastes at least once per 24 months.

The performance of activities required by t'e Quality Assurance Program to meet the criteria of Regulatory Guide 1.21, Rev. 1, June 1974 and Regulatory Guide 4.1, Rev. 1, April 1975 at least once per 12 months.

Any other area of facility operation considered appropriate by the NSDRC.

AUTHORITY 6.5.2.9 The NSDRC shall report to and advise the Vice President - Nuclear Operations, AEPSC, on those areas of responsibility specified in Sections 6.5.2.7 and 6.5.2.8.

RECORDS 6.5.2.10 Records of NSDRC activities shall be prepared, approved and distributed as indicated below:

a. Minutes of each NSDRC meeting shall be prepared, approved and issued within 14 days following each meeting.

b. Reports of reviews encompassed by Section 6.5.2.7 above, shall be prepared, approved and issued within 14 days following completion of the review.

C. Audit reports encompassed by Section 6.5.2.8 above, shall be forwarded to the Vice President - Nuclear Operations, AEPSC, and to the management positions, responsible for the areas audited within 30 days after completion of the audit.

6 5 3 TECHNICAL REVIEW AND CONTROL 6.5.3.1 Activities which affect nuclear safety shall be conducted as follows:

a. Procedures required by Specification 6.8 and other procedures which affect'lant nuclear safety, and changes thereto, shall be prepared, reviewed and approved. Each such procedure or procedure change shall be reviewed by a qualified individual/group other than the individual/group which prepared the procedure or procedure change, but who may be from the same organization as the individual/group which prepared the procedure or procedure change.

Procedures other than Plant Manager Procedures COOK NUCLEAR PLANT - UNIT 2 6-10 AMENDMENT NO.

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qn II

(j ~ I ADMINISTRATIVE CONTROLS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT~

6.9.1.6 Routine radiological environmental operating reports covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of each year.

6.9.1.7 The annual radiological environmental operating reports shall include summaries, interpretations, and statistical evaluation of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, operational controls (as appropriate), and previous environmental surveillance reports and an assessment of the observed impacts of the plant operation on the environment. The reports shall also include the results of the land-use census required by Specification 3.12.2. If harmful effects or evidence of irreversible damage are detected by the monitoring, the report shall provide an analysis of the problem and a planned course of action to alleviate the problem.

The annual radiological environmental operating reports shall include summarized and tabulated results in the format of 3.12-2 of all radiological environmental samples taken during the report period. In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.

The reports shall also include the following: a summary description of the radiological environmental monitoring program including sampling methods for each sample type, size, and physical characteristics of each sample type, sample preparation methods, analytical methods, and measuring equipment used; a map of all sample locations keyed to a table giving distances and directions from one reactor; the result of land-use census required by the Specification 3.12.2; and the results of participation in the Interlaboratory Comparison Program required by Specification 3.12.3.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT~

6.9.1.8 Routine radioactive effluent release report covering the operation of the unit during the previous 12 months of operation shall be submitted within 90 days after January 1 of each year.

6.9.1.9 The radioactive effluent release report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the units as outlined in Regulatory guide 1.21, "Measuring, Evaluating and Reporting in Solid Wastes and Releases of Radioactive 3

A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material for each unit.

COOK NUCLEAR PLANT - UNIT 2 6-15 AMENDMENT NO. 58, kRQ, ~

ADMINISTRATIVE CONTROLS A

Materials in Liquid and Gaseous Effluents from Light-Water Cooled Nuclear Power Plants," with data summarized on a quarterly basis following the format of Appendix B, thereof.

The radioactive effluent release report to be submitted 90 days after January 1 of each year shall include a quarterly summary of hourly meteorological data collected during the reporting period. This summary may be either in the form of an hour-by-hour listing of wind speed, wind direction, atmospheric stability, and precipitation (if measured) on magnetic tape, or in the form of )oint frequency distributions of wind speed, wind direction and atmospheric stability.

The report submitted 90 days after January 1 shall include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year. This report shall include an assessment of the radiation doses from radioactive liquid and gaseous effluents to members of the public due to their activities inside the site boundary (Figure 5.1-3) during the reporting period. All assumptions used in making these assessments (i.e., specific activity, exposure time and location) shall be included in this report. The meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents (as determined by sampling frequency and measurement) shall be used for determining the gaseous pathway doses. The assessment of radiation doses shall be performed in accordance with the Offsite Dose Calculation Manual (ODCM).

The radioactive effluent release report to be submitted 90 days after January 1 of each year shall also include an assessment of radiation doses to the likely most exposed member of the public from reactor releases and other nearby uranium fuel cycle sources (including doses from primary effluent pathways and direct radiation) for the previous 12 consecutive months to show conformance with 40 CFR 190, Environmental Radiation Protection Standards for Nuclear Power Operation.

Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev. l.

The radioactive effluent release report shall include the following information for each type of solid waste shipped offsite during the report period:

a o Volume (cubic meters),

b. Total curie quantity (specify whether determined by measurement or estimate),

c ~ Principal radionuclides (specify whether determined by measurement or estimate),

COOK NUCLEAR PLANT - UNIT 2 6-16 AMENDMENT NO.

l' ~

I' ft

ADMINISTRATIVE CONTROLS

d. Type of waste (e.g., spent resin, compacted dry waste, evaporator bottoms),

e. Type of container (e.g., LSA, Type A, Type B, Large Quantity), and

f. Solidification agent (e.g., cement).

The radioactive effluent release report shall include unplanned releases from the site to unrestricted areas of radioactive materials in gaseous and liquid effluent on a quarterly basis.

The radioactive effluent release report shall include any change to the PROCESS CONTROL PROGRAM (PCP) and the OFFSITE DOSE CALCULATION MANUAL (ODCM) made during the reporting period.

MONTHLY REACTOR OPERATING REPORT 6.9.1.10 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the PORVs or safety valves, shall be submitted on a monthly basis to the U.S. Nuclear Regulatory Commission (Attn:

Document Control Desk), Washington, D.C.'0555, with a copy to the Regional Office no later than the 15th of each month following the calendar month covered by the report.

CORE OPERATING LIMITS REPORT 6.9.1.11.1 Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT before each reload cycle or any remaining part of a reload cycle for the following:

a. Moderator Temperature Coefficient Limits for Specification 3/4.1.1.4, I

b. Rod Drop Time Limits for Specification 3/4.1.3.4,

c. Shutdown Rod Insertion Limits for Specification 3/4.1.3.5,

d. Control Rod Insertion Limits for Specification 3/4.1.3.6,

e. Axial Flux Difference for Specification 3/4.2.1,

f. Heat Flux Hot Channel Factor for Specification 3/4.2.2,

g. Nuclear Enthalpy Rise Hot Channel Factor for Specification 3/4.2.3, GIld

h. Allowable Power Level for Specification 3/4.2.6.

6.9.1.11.2 The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC in:

COOK NUCLEAR PLANT - UNIT 2 6-17 AMENDMENT NO. 54, ~