ML052220266

Application for Technical Specification Improvement to Eliminate Requirements to Provide Monthly Operating Reports and Occupational Radiation Exposure Reports

ML052220266
Person / Time
Site:	Cook   (DPR-058, DPR-074)
Issue date:	07/29/2005
From:	Jensen J Indiana Michigan Power Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
AEP:NRC:5090, TAC MC2629, TAC MC2630, TAC MC2653, TAC MC2687, TAC MC2690, TAC MC2691, TAC MC2692, TAC MC2693, TAC MC2694, TAC MC2695, TAC MC3152, TAC MC3153, TAC MC3154, TAC MC3155, TAC MC3156, TAC MC3157, TAC MC3432, TAC MC3453
Download: ML052220266 (33)

Text

INDIANA MICHIGAN POWER*

A unit of American Electric Power Indiana Michigan Power Cook Nuclear Plant One Cook Place Bridgman.MI 49106 AERcom July 29, 2005 AEP:NRC:5090 10 CFR 50.90 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop O-P1-17 Washington, DC 20555-0001

Reference:

Donald C. Cook Nuclear Plant Units 1 and 2 Docket Nos. 50-315 and 50-316 Application for Technical Specification Improvement to Eliminate Requirements to Provide Monthly Operating Reports and Occupational Radiation Exposure Reports Letter from J. Donohew, Nuclear Regulatory Commission, to M. K. Nazar, Indiana Michigan Power Company, "D. C. Cook Nuclear Plant, Units 1 and 2 - Issuance of Amendments for the Conversion to the Improved Technical Specifications with Beyond Scope Issues (TAC Nos. MC2629, MC2630, MC2653 through MC2687, MC2690 through MC2695, MC3152 through MC3157, MC3432 through MC3453),"

Accession Number ML050620034, dated June 1, 2005.

Dear Sir or Madam:

In accordance with the provisions of Section 50.90 of Title 10 of the Code of Federal Regulations, Indiana Michigan Power Company (I&M), the licensee for the Donald C. Cook Nuclear Plant (CNP), Units 1 and 2, is submitting a request for an amendment to the technical specifications (TS).

The proposed amendment would delete the TS requirements to submit monthly operating reports and occupational radiation exposure reports.

The change is consistent with Nuclear Regulatory Commission (NRC)-approved Revision 1 to Industry/Technical Specification Task Force (TSTF)

Standard Technical Specification Change Traveler, TSTF-369, "Removal of Monthly Operating Report and Occupational Radiation Exposure Report." The availability of this TS improvement was announced in the Federal Register on June 23, 2004 (69 FR 35067) as part of the consolidated line item improvement process.

By the referenced letter, the NRC approved the conversion of the CNP Current Technical Specifications (CTS) to the Improved Technical Specifications (ITS) specified in NUREG-1431, "Standard Technical Specifications - Westinghouse Plants," Revision 2. However, the ITS have not yet been implemented. I&M has therefore provided copies of both the CTS and the current draft ITS

U. S. Nuclear Regulatory Commission AEP:NRC:5090 Page 2 pages that are affected by this proposed amendment. I&M will coordinate with the NRC Project Manager to ensure that the appropriate pages are issued.

The enclosure to this letter provides an affirmation pertaining to the statements made in this correspondence. Attachment 1 provides a description of the proposed change and confirmation of applicability. Attachments 2a and 2b provide the Unit I and Unit 2 CTS pages marked to show the proposed changes. Attachments 3a and 3b provide the Unit 1 and Unit 2 ITS pages marked to show the proposed changes. Attachments 4a and 4b provide the proposed Unit 1 and Unit 2 CTS pages.

Attachments 5a and 5b provide the proposed Unit 1 and Unit 2 ITS pages. Attachment 6 provides I&M's regulatory commitment to provide operating data to the NRC using an industry database.

1&M requests NRC review and approval in accordance with normal NRC review schedules for this type of request. I&M requests a 45-day implementation period following approval.

Should you have any questions, please contact Mr. John A. Zwolinski, Safety Assurance Director at (269) 466-2428.

Sincerely, Joseph N. Jensen Site Vice President RGV/rdw

Enclosure:

Affirmation Attachments:

1. Description and Assessment 2a. Unit I Current Technical Specification Pages Marked to Show Proposed Changes 2b. Unit 2 Current Technical Specification Pages Marked to Show Proposed Changes 3a. Unit 1 Improved Technical Specification Pages Marked to Show Proposed Changes 3b. Unit 2 Improved Technical Specification Pages Marked to Show Proposed Changes 4a. Unit 1 Proposed Current Technical Specification Pages 4b. Unit 2 Proposed Current Technical Specification Pages 5a. Unit 1 Proposed Improved Technical Specification Pages Sb. Unit 2 Proposed Improved Technical Specification Pages

6. Commitment

U. S. Nuclear Regulatory Commission AEP:NRC:5090 Page 3 C:

J. L. Caldwell, NRC Region III K. D. Curry, Ft. Wayne AEP, w/o enclosure/attachments J. T. King, MPSC, w/o enclosure/attachments C. F. Lyon, NRC Washington, DC MDEQ - WHMD/IHWRPS, w/o enclosure/attachments NRC Resident Inspector

Enclosure to AEP:NRC:5090 AFFIRMATION 1, Joseph N. Jensen, being duly sworn, state that I am Site Vice President of Indiana Michigan Power Company (I&M), that I am authorized to sign and file this request with the Nuclear Regulatory Commission on behalf of I&M, and that the statements made and the matters set forth herein pertaining to I&M are true and correct to the best of my knowledge, information, and belief.

Indiana Michigan Power Company Joseph N. Jensen Site Vice President SWORN TO AND SUBSCRIBED BEFORE ME THIS _q2bDAY OF JLAI

, 2005 k--~

U Try kblic My Commission Expires L

° ( Lc>0\\

Attachment I to AEP:NRC:5090 Description and Assessment

1.0 INTRODUCTION

In Reference 1, the Nuclear Regulatory Commission (NRC) approved the conversion of the Donald C. Cook Nuclear Plant (CNP) Current Technical Specifications (CTS) to the Improved Technical Specifications (ITS) specified in NUREG-1431, "Standard Technical Specifications -

Westinghouse Plants," Revision 2. However, the ITS have not yet been implemented. Indiana Michigan Power Company (I&M) has therefore provided copies of both the CTS and the current draft ITS pages that are affected by this proposed amendment.

The proposed license amendment deletes the requirements in Unit 1 and Unit 2 CTS 6.9.1.5.a for an annual report on occupational radiation exposures and Unit 1 and Unit 2 CTS 6.9.1.8 for a monthly report of operating statistics and shutdown experience.

The corresponding ITS requirements are 5.6.1 and 5.6.4.

The changes are consistent with NRC approved Industry/Technical Specification Task Force (TSTF) Standard Technical Specification Change Traveler, TSTF-369, "Removal of Monthly Operating Report and Occupational Radiation Exposure Report," Revision 1. The availability of this technical specification (TS) improvement was announced in Reference 2 as part of the consolidated line item improvement process (CLIIP).

2.0 DESCRIPTION

OF PROPOSED AMENDMENT Consistent with the NRC-approved Revision I of TSTF-369, the proposed TS changes include:

CTS 6.9.1.5.a (ITS 5.6.1)

Occupational Radiation Exposure Report Deleted CTS 6.9.1.8 (ITS 5.6.4)

Monthly Operating Reports Deleted As addressed in the safety evaluation (SE) published in the Notice of Availability for TSTF-369, I&M is proposing to adopt a part of NRC-approved Revision 4 to TSTF-258, 'Changes to Section 5.0, Administrative Controls."

Specifically, CTS 6.9.1.8 includes a requirement to include in the monthly operating reports any challenges to pressurizer power operated relief valves or pressurizer safety valves (ITS 5.6.4 does not have this provision). The NRC model safety evaluation addressed the removal of requirements to submit monthly operating reports in those cases where the TS includes a requirement to address challenges to relief and safety valves (i.e., if a licensee had not yet adopted the associated part of TSTF-258). The proposed change is consistent with the option described in the Reference 2 Notice of Availability, and the related documentation for both TSTF-369 and the limited portion of TSTF-258 included in this application.

to AEP:NRC:5090 Page 2

3.0 BACKGROUND

The background for this application is adequately addressed by the Reference 2 Notice of Availability and TSTF-369.

4.0 REGULATORY REQUIREMENTS AND GUIDANCE The applicable regulatory requirements and guidance associated with this application are adequately addressed by the Reference 2 Notice of Availability and TSTF-369.

5.0 TECHNICAL ANALYSIS

I&M has reviewed the Reference 2 SE as part of the CLIIP Notice of Availability.

This verification included a review of the NRC staff's SE and the supporting information provided to support TSTF-369. I&M has concluded that the justifications presented in the TSTF proposal and the SE prepared by NRC staff are applicable to CNP, Units 1 and 2 and justify this amendment for the incorporation of the changes to the CNP technical specifications.

6.0 REGULATORY ANALYSIS

A description of this proposed change and its relationship to applicable regulatory requirements and guidance was provided in the Reference 2 Notice of Availability and TSTF-369.

6.1 VERIFICATION AND COMMITMENT As discussed in the model Reference 2 SE for TS improvement, I&M is making the following regulatory commitment:

Using an industry database, I&M will provide the NRC the operating data (for each calendar month) that is described in Generic Letter 97-02 "Revised Contents of the Monthly Operating Report," by the last day of the month following the end of each calendar quarter. The commitment is based on the use of an industry database (e.g., the industry's Consolidated Data Entry (CDE) program, currently being developed and maintained by the Institute of Nuclear Power Operations). This regulatory commitment will be implemented to prevent any gaps in the monthly operating statistics and shutdown experience provided to the NRC (i.e., data for all months will be provided using one or both systems (monthly operating reports and CDE)).

CNP does not have different reactor types or both operating and shutdown reactors. Thus, no commitment regarding apportionment of station doses between different reactor types or between operating and shutdown units is required.

to AEP:NRC:5090 Page 3 7.0 NO SIGNIFICANT HAZARDS CONSIDERATION I&M has reviewed the Reference 2 proposed no significant hazards consideration determination as part of the CLIIP. I&M has concluded that the proposed determination presented in the notice is applicable to CNP and the determination is hereby incorporated by reference to satisfy the requirements of 10 CFR 50.9 1(a).

8.0 ENVIRONMENTAL EVALUATION I&M has reviewed the environmental evaluation included in the Reference 2 model SE as part of the CLIIP. I&M has concluded that the NRC staff's findings presented in that evaluation are applicable to CNP and the evaluation is hereby incorporated by reference for this application.

9.0 PRECEDENTS This application is being made in accordance with the CLIIP. I&M is not proposing variations or deviations from the TS changes described in TSTF-369 and the limited portion of TSTF-258 or the Reference 2 model SE.

Similar amendments have previously been approved for Brunswick Units 1 and 2, Reference 3, and Crystal River Unit 3, Reference 4.

10.

REFERENCES

1. Letter from J. Donohew, Nuclear Regulatory Commission, to M. K. Nazar, Indiana Michigan Power Company, "D. C. Cook Nuclear Plant, Units 1 and 2 - Issuance of Amendments for the Conversion to the Improved Technical Specifications with Beyond Scope Issues (TAC Nos. MC2629, MC2630, MC2653 through MC2687, MC2690 through MC2695, MC3152 through MC3157, MC3432 through MC3453),"

Accession Number ML050620034, dated June 1,2005.

2. Federal Register Notice: Notice of Availability of Model Application Concerning Technical Specification Improvement to Eliminate Requirements to Provide Monthly Operating Reports and Occupational Radiation Exposure Reports Using the Consolidated Line Item Improvement

Process, published June 23, 2004 (69 FR 35067).

3. Letter from Brenda L. Mozafari, NRC, to C. J. Gannon, Brunswick Steam Electric Plant, 'Brunswick Steam Electric Plant, Units 1 and 2 - Issuance of Amendments on Elimination of Requirements to Provide Monthly Operating Reports and Annual Occupational Radiation Exposure Reports (TAC Nos. MC5125 and MC5126)," dated April 19, 2005.

to AEP:NRC:5090 Page 4

4. Letter from Brenda L. Mozafari, NRC, to Dale E. Young, Crystal River Nuclear Plant, "Crystal River Unit 3 -

Issuance of Amendment on Elimination of Requirements to Provide Monthly Operating Reports and Annual Occupational Radiation Exposure Reports (TAC No. MC5127)," dated April, 19 2005.

a to AEP:NRC:5090 Unit I Current Technical Specification Pages Marked to Show Proposed Changes Revised Pages Unit 1 6-10 6-12

6.0 ADMINISTRATINTE CONTROLS 6.9 STARTUP REPORT (Continued) 6.9.1.3 ANNUAL REPO Startup reports shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest. If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or commencement of commercial power operation), supplementary reports shall be submitted at least every three months until all three events have been completed.

,RTS' Annual reports covering the activities of the unit as described below for the previous calendar year shall be submitted prior to March I of each year. The initial report shall be submitted prior to March 1 of the year following initial criticality.

Reports required on an annual basis shall include:

6.9.1.4 6.9.1.5 a.

A4abtatiourratin-nnuaali&of4h-n F ofsttio, tifta d-e rpef_

1 (insuding-eetntraet0FS)-eeeiving-annual-eaposures-gfeate u-l40mreaeeordin-4e weorlztnd-ob-unet eg.er-eper-ations--and-suwieilianeKM;ni on routineaintenance, SpeoW--maintenancee(desrbe-mmtenanen),Baste-proeessing-and refueling. Also ine4uded4&-a-tabu~tn-of4hetta-pefson-.remexpes4 sta utilityr-and--ether--personnel-assoeiated--witlI ca

rl ndmjeb-fanetien.-The-delosee assiment-to var t

tenimates-base&-en-poeket desimeter; eleenie-dosrimeter, TLD, om-fit-badge-measirement.-Smral-exposures-totaling-ess than40%,of!4hesd

-otb ntef ea te-,atleast 8go" of dosetreei-tv ae-

_assigned to specife-4mjer-work-funeonDEETE I

b.

The complete results of steam generator tube in-service inspections performed during the report period (reference Specification 4.4.5.5.b).

c.

Documentation of all challenges to the pressurizer power operated relief valves (PORVs) or safety valves.

d.

Information regarding any instances when the 1-131 specific activity limit was exceeded.

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.

2 Tlistabulatfim-supplements-the r ements of20.2206 cf 10 CFR Partp ELETED I

COOK NUCLEAR PLANT-UNIT 1 Page 6-10 AMENDMENT 89, 44, 454, I9, 26, 245

6.0 ADMINISTRATIVE CONTROLS MONTIHLY REACGTOR-PF1;LING-REPOR 6.9.1.8 Reutine-p otperatinsties-and-siutdoe-perixneerneuidoe tatien-f ehalenges-4o-the-P-OVs-or safey valves-slial-besubmited-on--monrithUy-basi.-he--U.&

NtweaR atorytn"Dmiment rol Desk), Washingi

, D.C. 20555, %rith-a eopy-to4 heeater-than.

.45the--eho nth-oRo,4ng-4he-caiendarF-month covered) y thepM E

CORE OPERATING LIMITS REPORT 6.9.1.9.1 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.

6.9.1.9.2 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),

b.

WCAP-8385, "Power Distribution Control and Load Following Procedures - Topical Report," September 1974 (Westinghouse Proprietary),

c.

WCAP-10216-P-A, Revision IA, "Relaxation of Constant Axial Offset Control/FQ Surveillance Technical Specification," February 1994 (Westinghouse Proprietary),

d.

WCAP-10266-P-A Rev. 2, "The 1981 Version of Westinghouse Evaluation Mode Using BASH Code," March 1987 (Westinghouse Proprietary).

e.

WCAP-12610-P-A, "VANTAGE+ Fuel Assembly Reference Core Report," July 1991 (Westinghouse Proprietary).

COOK NUCLEAR PLANT-UNIT I Page 6-12 AMIENDMfENT 69,4-54, 4-74, 49,206 26,279

- b to AEP:NRC:5090 Unit 2 Current Technical Specification Pages Marked to Show Proposed Changes Revised Pages Unit 2 6-10 6-12

6.0 ADMINISTRATIVE CONTROLS STARTUP REPORT (Continued) 6.9.1.3 ANNUAL REPC Startup reports shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest. If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or commencement of commercial power operation), supplementary reports shall be submitted at least every three months until all three events have been completed.

IRTS' Annual reports covering the activities of the unit as described below for the previous calendar year shall be submitted prior to March I of each year. The initial report shall be submitted prior to March I of the year following initial criticality.

Reports required on an annual basis shall include:

6.9.1.4 6.9.1.5 a.

A-4abttatioann at-basis of th-number-o--stat.i.n,--utlityi nd-eatber-pefsne (ineluding-eentraetrs) eeiving-annual-exposures greater'-than 400 rnrem-ee-eor-ding-to work-end-job-funein e

reeo-prtions and-survellanee-4n-srie-npeeh foutine-maintena ee,,-speeial-imintenanee_-deseibe.-maintenance),--Anstep esng-and refuelng.--Also-e-inkde~sa-tabutation-i4he-4etaI-erene es fosr-ea-o-n utilivy;-and--other--per-sonel asseeiated-with-eaeh--workand-job--funetie--The-dose essignment-o--v Fious-duyf~uneten--ay0eesimates-based-np oktdsimeter-el~ee4Fonie-<osimeFTeLD, or-4fi-bae-mreasurements.--&Dll-e~psres-totaling-less than,-2/,-o4he-indivduaetaI ose need-net-unted4h-fo naggregat-ate-atleast 8O%-.of--te--ctl A-e sce received sha~llbe--assigned--4 -speeifle -- ae-wr funetionst)ELETEDjt I

b.

The complete results of steam generator tube in-service inspections performed during the report period (reference Specification 4.4.5.5.b).

c.

Documentation of all challenges to the pressurizer power operated relief valves (PORVs) or safety valves.

d.

Information regarding any instances when the 1-131 specific activity limit was exceeded.

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.

2 This~bulatien-suppkemets-the-requreme ts of 20.2206 of 10 CPR P A20O. ELETEj~_

I COOK NUCLEAR PLANT-UNIT 2 Page 6-1 0 AMENDMENT 73, 449, 4-75, 0, 226

6.0 ADMINISTRATIVE CONTROLS MONTHLY REACTOR-OPERATING REPORT 6.9.1.8 Routinefeports ofopatiegatistitsnces ahutd-ex iOVA.e ing-deetimentation-of-all cm-egelsbe4o-hePRV5 oF safety ^ ahvs,-hallb-sub rmtet~hoybsi-4heJU.S.-Nueear Regula

-so e rment Control--esk}), Washilgton, D.C. 20555, With--eeepy4o-e Regienal-3friee-i4ater4han4he 15th-of-each-monthl-felowng4le-ecalendar-onth -eovered-bythe fepert4)ELETED CORE OPERATING LIMITS REPORT 6.9.1.9.1 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 3/4.1.3.4,

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, and

h.

Allowable Power Level for Specification 3/4.2.6.

6.9.1.9.2 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),

b.

WCAP-8385, "Power Distribution Control and Load Following Procedures - Topical Report,"

September 1974 (Westinghouse Proprietary),

c.

WCAP-10216-P-A, Revision IA, "Relaxation of Constant Axial Offset ControlIFQ Surveillance Technical Specification," February 1994 (Westinghouse Proprietary),

d.

WCAP-10266-P-A Rev. 2, "The 1981 Version of Westinghouse Evaluation Mode Using BASH Code," March 1987 (Westinghouse Proprietary).

e.

WCAP-12610-P-A, "VANTAGE+

Fuel Assembly Reference Core Report,"

July 1991 (Westinghouse Proprietary).

COOK NUCLEAR PLANT-UNIT 2 Page 6-12 AMENDMENT -54, 48, 457, 4-5, 90, 24, 261 a to AEP:NRC:5090 Unit 1 Improved Technical Specification Pages Marked to Show Proposed Changes Revised Pages Unit 1 5.6-1 5.6-2

Reporting Requirements 5.6 5.0 ADMINISTRATIVE CONTROLS 5.6 Reporting Requirements The following reports shall be submitted in accordance with 10 CFR 50.4.

5.6.1 OcGUnatieanal Radiation Exno

Renrt, NOTE A ringc submittal may be made for a multiple unit rtation. The submittal should combine sections common to all units at the station.

A tabulation on an annual basis of the number of station, utility, and other personnel (including contractors), for whom monitoring was pceormed, rereiving an annual deep dose equivalent > 100 mrems and the associated collective deep dose equivalent (reported in person rem) according to work and job functions (e.g., reactor operations and surveillance, inservice inspection, utine maintenance, specia! maintenance (describe maintenance), waste processing, and refueliRg). This tabulation supplements the requiremRets ot 10 CFR 20.2206. The dose assignments to various duty funGtions may be estimated based on pocket ionization chamber, thermoluminescence dosimeter

-TLD), electronie dosimeter, or film badge measurements. Small exposures totaling 2 20 percent of the individual total dose need not be accounted for. In the aggregate, at least 80 percent of the total deep dose equivalent received from external sources should be assigned to specific major worlk functions. The report covering the previous calendar year shall be submitted by April 30 of each DEETED 5.6.2 Annual Radiological Environmental Operating Report NOTES-A single submittal may be made for a multiple unit station. The submittal should combine sections common to all units at the station.

The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted by May 15 of each year. The report shall include summaries, interpretations, and analyses of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in the Offsite Dose Calculation Manual (ODCM), and in 10 CFR 50, Appendix I, Sections IV.B.2, IV.B.3, and IV.C.

Cook Nuclear Plant Unit 1 5.6-1 Amendment No. 287

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.2 Annual Radiological Environmental Operating Report (continued)

The Annual Radiological Environmental Operating Report shall include the results of analyses of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the table and figures in the ODCM, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual 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 in a supplementary report as soon as possible.

5.6.3 Radioactive Effluent Release Report NOTE--

A single submittal may be made for a multiple unit station. The submittal shall combine sections common to all units at the station.

The Radioactive Effluent Release Report covering the operation of the unit in the previous year shall be submitted within 90 days of January 1 of each year. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be consistent with the objectives outlined in the ODCM and Process Control Program and in conformance with 10 CFR 50.36a and 10 CFR Part 50, Appendix I,Section IV.B.1.

5.6.4 Monthly Operatinq Reports Routine reports of operating statistics and phutdown experience shall be submitted on a monthly basis no later than the 1 5th of each month following the calendar month covered by the report. ELETED 5.6.5 CORE OPERATING LIMITS REPORT (COLR)

a.

Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following:

1. SL 2.1.1, "Reactor Core Safety Limits";

2.

LCO 3.1.1, "SHUTDOWN MARGIN (SDM)";

3.

LCO 3.1.3, "Moderator Temperature Coefficient (MTC)";

4.

LCO 3.1.5, "Shutdown Bank Insertion Limits";

Cook Nuclear Plant Unit 1 5.6-2 Amendment No. 287 b to AEP:NRC:5090 Unit 2 Improved Technical Specification Pages Marked to Show Proposed Changes Revised Pages Unit 2 5.6-1 5.6-2

Reporting Requirements 5.6 5.0 ADMINISTRATIVE CONTROLS 5.6 Reporting Requirements The following reports shall be submitted in accordance with 10 CFR 50.4.

5.6.1 QGG~r.

patig a

RadiatiGR CExpes,re-DRenr NOTE A single submittal may be made for a multiple unit station. The submittal should comnbine rectionrs ommnO to all units at the station.

A tabulation on an annual basis of the number of station, utility, and other personnel (including Gontractors), for whom monitoring was performed, receiving an aRnual deep doee equivalent 100 rems aRd the associ cltie deep dose equivalent (reported in person rem) according to work and job functions (e.g., reactor operations and sur!eillancc, inservice inspection, routine maintenance special maintenae r

aintenance), waste processing, and refueling). This tabulation supplements the requirements of 10 CFR 20.2206. The dose assignments to various dut' functioRS maynbe estimated based on pocket ionization chamber, thermoluminecsence dosimeter (TLD), electronic dosimeter, or film badge measurements. Small exposures totaling - 20 percent of the indi'idual total dose need not be accounted for. In the aggregate, at least 80 percent of the total deep dose equivalent received fromn eoernal sources should be assigRed to specific major work fuRntionr. The report -covring the previous calendar year shall be submitted by Aprl 30 of each year-7 ELT l 5.6.2 Annual Radiological Environmental Operating Report k I

%Ivrr, IFJI t-A single submittal may be made for a multiple unit station. The submittal should combine sections common to all units at the station.

The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted by May 15 of each year. The report shall include summaries, interpretations, and analyses of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in the Offsite Dose Calculation Manual (ODCM), and in 10 CFR 50, Appendix I, Sections IV.B.2, IV.B.3, and IV.C.

Cook Nuclear Plant Unit 2 5.6-1 Amendment No. 269 Cook Nuclear Plant Unit 2 5.6-1 Amendment No. 269

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.2 Annual Radiological Environmental Operating Report (continued)

The Annual Radiological Environmental Operating Report shall include the results of analyses of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the table and figures in the ODCM, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual 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 in a supplementary report as soon as possible.

5.6.3 Radioactive Effluent Release Report

~NOTES A single submittal may be made for a multiple unit station. The submittal shall combine sections common to all units at the station.

The Radioactive Effluent Release Report covering the operation of the unit in the previous year shall be submitted within 90 days of January 1 of each year. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be consistent with the objectives outlined in the ODCM and Process Control Program and in conformance with 10 CFR 50.36a and 10 CFR Part 50, Appendix I,Section IV.B.1.

5.6.4 Month!Y OpeatiRIn RePorts Routine reports of operating statistics and shutdown cxperix nce shall be submitted on a monthly basis no later than the 1 5th of each month following the Galendar mon-th co'ered by the rporGtJ. E D

5.6.5 CORE OPERATING LIMITS REPORT (COLR)

a.

Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following:

1. SL 2.1.1, "Reactor Core Safety Limits";

2.

LCO 3.1.1, "SHUTDOWN MARGIN (SDM)";

3.

LCO 3.1.3, "ModeratorTemperature Coefficient (MTC)";

4.

LCO 3.1.5, "Shutdown Bank Insertion Limits";

Cook Nuclear Plant Unit 2 5.6-2 Amendment No. 269 Cook Nuclear Plant Unit 2 5.6-2 Amendment No. 269 a to AEP:NRC:5090 Unit 1 Proposed Current Technical Specification Pages Revised Pages Unit 1 6-10 6-12

6.0 ADMINISTRATIVE CONTROLS 6.9 STARTUP REPORT (Continued) 6.9.1.3 Startup reports shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest. If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or commencement of commercial power operation), supplementary reports shall be submitted at least every three months until all three events have been completed.

ANNUAL REPORTS' 6.9.1.4 6.9.1.5 Annual reports covering the activities of the unit as described below for the previous calendar year shall be submitted prior to March I of each year. The initial report shall be submitted prior to March I of the year following initial criticality.

Reports required on an annual basis shall include:

a.

DELETED2

b.

The complete results of steam generator tube in-service inspections performed during the report period (reference Specification 4.4.5.5.b).

c.

Documentation of all challenges to the pressurizer power operated relief valves (PORVs) or safety valves.

d.

Information regarding any instances when the 1-131 specific activity limit was exceeded.

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.

2 DELETED I

I COOK NUCLEAR PLANT-UNIT 1 Page 6-10 AIMENDMIENT 87, 44, 4-54, 489, 6,

245,

6.0 ADMINISTRATIVE CONTROLS 6.9.1.8 DELETED CORE OPERATING LIMITS REPORT 6.9.1.9.1 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.

Allowvable Power Level for Specification 3/4.2.6.

6.9.1.9.2 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),

b.

WCAP-8385, "Power Distribution Control and Load Following Procedures - Topical Report," September 1974 (Westinghouse Proprietary),

c.

WCAP-10216-P-A, Revision IA, "Relaxation of Constant Axial Offset Control/FQ Surveillance Technical Specification," February 1994 (Westinghouse Proprietary),

d.

WCAP-10266-P-A Rev. 2, "The 1981 Version of Westinghouse Evaluation Mode Using BASH Code," March 1987 (Westinghouse Proprietary).

e.

WCAP-12610-P-A, "VANTAGE+ Fuel Assembly Reference Core Report," July 1991 (Westinghouse Proprietary).

COOK NUCLEAR PLANT-UNIT I Page 6-12 AM1ENDNMENT 69,-54,4-74, 489,206 226, M, b to AEP:NRC:5090 Unit 2 Proposed Current Technical Specification Pages Revised Pages Unit 2 6-10 6-12

6.0 ADMINISTRATIVE CONTROLS STARTUP REPORT (Continued) 6.9.1.3 Startup reports shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest. If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or commencement of commercial power operation), supplementary reports shall be submitted at least every three months until all three events have been completed.

ANNUAL REPORTS' 6.9.1.4 6.9.1.5 Annual reports covering the activities of the unit as described below for the previous calendar year shall be submitted prior to March I of each year. The initial report shall be submitted prior to March I of the year following initial criticality.

Reports required on an annual basis shall include:

a.

DELETED2 I

b.

The complete results of steam generator tube in-service inspections performed during the report period (reference Specification 4.4.5.5.b).

c.

Documentation of all challenges to the pressurizer power operated relief valves (PORVs) or safety valves.

d.

Information regarding any instances wvhen the 1-131 specific activity limit was exceeded.

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.

2 DELETED I

COOK NUCLEAR PLANT-UNIT 2 Page 6-10 AMENDMENT q3,44-9,4-7-5,240, 26,

6.0 ADMINISTRATIVE CONTROLS 6.9.1.8 DELETED CORE OPERATING LIMITS REPORT 6.9.1.9.1 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 3/4.1.3.4,

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, and

h.

Allowable Power Level for Specification 3/4.2.6.

6.9.1.9.2 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),

b.

WCAP-8385, "Power Distribution Control and Load Following Procedures - Topical Report,"

September 1974 (Westinghouse Proprietary),

c.

WCAP-10216-P-A, Revision IA, "Relaxation of Constant Axial Offset Control/FQ Surveillance Technical Specification," February 1994 (Westinghouse Proprietary),

d.

WCAP-10266-P-A Rev. 2, "The 1981 Version of Westinghouse Evaluation Mode Using BASH Code," March 1987 (Westinghouse Proprietary).

e.

WCAP-12610-P-A, "VANTAGE+ Fuel Assembly Reference Core Report,"

July 1991 (Westinghouse Proprietary).

COOK NUCLEAR PLANT-UNIT 2 Page 6-12 ANMENDMIENT N1, 4-,

4-P, 4-75,490, 20,261.,

a to AEP:NRC:5090 Unit 1 Proposed Improved Technical Specification Pages Revised Pages Unit 1 5.6-1 5.6-2

Reporting Requirements 5.6 5.0 ADMINISTRATIVE CONTROLS 5.6 Reporting Requirements The following reports shall be submitted in accordance with 10 CFR 50.4.

5.6.1 DELETED 5.6.2 Annual Radiological Environmental Operating Report NOTENOT E-A single submittal may be made for a multiple unit station. The submittal should combine sections common to all units at the station.

The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted by May 15 of each year. The report shall include summaries, interpretations, and analyses of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in the Offsite Dose Calculation Manual (ODCM), and in 10 CFR 50, Appendix I, Sections IV.B.2, IV.B.3, and IV.C.

Cook Nuclear Plant Unit 1 5.6-1 Amendment No. 2897,

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.2 Annual Radiological Environmental Operating Report (continued)

The Annual Radiological Environmental Operating Report shall include the results of analyses of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the table and figures in the ODCM, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual 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 in a supplementary report as soon as possible.

5.6.3 Radioactive Effluent Release Report NOTED A single submittal may be made for a multiple unit station. The submittal shall combine sections common to all units at the station.

The Radioactive Effluent Release Report covering the operation of the unit in the previous year shall be submitted within 90 days of January 1 of each year. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be consistent with the objectives outlined in the ODCM and Process Control Program and in conformance with 10 CFR 50.36a and 10 CFR Part 50, Appendix I,Section IV.B.1.

5.6.4 DELETED 5.6.5 CORE OPERATING LIMITS REPORT (COLR)

a.

Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following:

1. SL 2.1.1, "Reactor Core Safety Limits";

2.

LCO 3.1.1, "SHUTDOWN MARGIN (SDM)";

3.

LCO 3.1.3, "Moderator Temperature Coefficient (MTC)";

4.

LCO 3.1.5, "Shutdown Bank Insertion Limits";

Cook Nuclear Plant Unit I 5.6-2 Amendment No. 28-7, Cook Nuclear Plant Unit 1 5.6-2 Amendment No. 2I8, b to AEP:NRC:5090 Unit 2 Proposed Improved Technical Specification Pages Revised Pages Unit 2 5.6-1 5.6-2

Reporting Requirements 5.6 5.0 ADMINISTRATIVE CONTROLS 5.6 Reporting Requirements The following reports shall be submitted in accordance with 10 CFR 50.4.

5.6.1 DELETED 5.6.2 Annual Radiological Environmental Operating Report NOTE A single submittal may be made for a multiple unit station. The submittal should combine sections common to all units at the station.

The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted by May 15 of each year. The report shall include summaries, interpretations, and analyses of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in the Offsite Dose Calculation Manual (ODCM), and in 10 CFR 50, Appendix I, Sections IV.B.2, IV.B.3, and IV.C.

Cook Nuclear Plant Unit 2 5.6-1 Amendment No. 269, Cook Nuclear Plant Unit 2 5.6-1 Amendment No. 269,

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.2 Annual Radiological Environmental Operating Report (continued)

The Annual Radiological Environmental Operating Report shall include the results of analyses of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the table and figures in the ODCM, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual 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 in a supplementary report as soon as possible.

5.6.3 Radioactive Effluent Release Report NOTE-A single submittal may be made for a multiple unit station. The submittal shall combine sections common to all units at the station.

The Radioactive Effluent Release Report covering the operation of the unit in the previous year shall be submitted within 90 days of January 1 of each year. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be consistent with the objectives outlined in the ODCM and Process Control Program and in conformance with 10 CFR 50.36a and 10 CFR Part 50, Appendix I,Section IV.B.1.

5.6.4 DELETED 5.6.5 CORE OPERATING LIMITS REPORT (COLR)

a.

Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following:

1. SL 2.1.1, "Reactor Core Safety Limits";

2.

LCO 3.1.1, "SHUTDOWN MARGIN (SDM)";

3.

LCO 3.1.3, "Moderator Temperature Coefficient (MTC)";

4.

LCO 3.1.5, "Shutdown Bank Insertion Limits";

Cook Nuclear Plant Unit 2 5.6-2 Amendment No. 269, Cook Nuclear Plant Unit 2 5.6-2 Amendment No. 269, to AEP:NRC:5090 Commitment The following table identifies those actions committed to by Indiana Michigan Power Company (I&M) in this document.

Any other actions discussed in this submittal represent intended or planned actions by I&M. They are described to the Nuclear Regulatory Commission (NRC) for the NRC's information and are not regulatory commitments.

Commitment Due Date Using an industry database, I&M will provide the NRC the operating data (for each calendar month) that is described in Generic Letter 97-02 "Revised Contents of the Monthly Operating Report," by the last day of the month following the end of each calendar quarter. The commitment will be based on the Ongoing use of an industry database (e.g., the industry's Consolidated Data Entry (CDE) program, currently being developed and maintained by the Institute of Nuclear Power Operations). This regulatory commitment will be implemented to prevent any gaps in the monthly operating statistics and shutdown experience provided to the NRC (i.e., data for all months will be provided using one or both systems (monthly operating reports and CDE)).