RS-04-160, Request for Amendment to Technical Specifications to Eliminate Requirements to Provide Monthly Operating Reports and Annual Occupational Radiation Exposure Reports

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Request for Amendment to Technical Specifications to Eliminate Requirements to Provide Monthly Operating Reports and Annual Occupational Radiation Exposure Reports
ML042990134
Person / Time
Site: Dresden, Peach Bottom, Oyster Creek, Byron, Three Mile Island, Braidwood, Limerick, Clinton, Quad Cities, Zion, LaSalle
Issue date: 10/21/2004
From: Jamie Benjamin
AmerGen Energy Co, Exelon Nuclear
To:
Document Control Desk, NRC/FSME
References
-RFPFR, RS-04-160
Download: ML042990134 (95)
v • d • e


Text

www .exeloncorp .com C

AmerGen Energy Company, LLC Exelon Generation 4300 MUM Road Wunna, IL 60555 4300 VAnfeld Road WunmMt 1 6055 10 CFR 50.90 RS-04-160 October 21, 2004 U. S . Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Braidwood Station, Units 1 and 2 Facility Operating License Nos. NPF-72 and NPF-77 NRC Docket Nos. STN 50-456 and STN 50-457 Byron Station, Units 1 and 2 Facility Operating License Nos. NPF-37 and NPF-66 NRC Docket Nos. STN 50-454 and STN 50-455 Clinton Power Station Facility Operating License No. NPF-62 NRC Docket No . 50-461 Dresden Nuclear Power Station, Units 2 and 3 Facility Operating License Nos. DPR-1 9 and DPR-25 NRC Docket Nos. 50-237 and 50-249 LaSalle County Station, Units 1 and 2 Facility Operating License Nos. NPF-1 1 and NPF-1 8 NRC Docket Nos. 50-373 and 50-374 Limerick Generating Station, Units 1 and 2 Facility Operating License Nos. NPF-39 and NPF-85 NRC Docket Nos. 50-352 and 50-353 Oyster Creek Generating Station Facility Operating License No. DPR-16 NRC Docket No. 50-219 Peach Bottom Atomic Power Station, Units 2 and 3 Facility Operating License Nos. DPR-44 and DPR-56 NRC Docket Nos. 50-277 and 50-278 Three Mile Island Station, Unit 1 Facility Operating License No . DPR-50 NRC Docket No. 50-289

October 21, 2004 U. S. Nuclear Regulatory Commission Page 2 Quad (lies Nuclear Power Station, Units 1 and 2 Facility Operating License Nos. DPR-29 and DPR-30 NRC Docket Nos . 50-254 and 50-265 Zion Nuclear Power Station, Units 1 and 2 Facility Operating License Nos . DPR-39 and DPR-48 NRC Docket Nos. 50-295 and 50-304

Subject:

Request for Amendment to Technical Specifications to Eliminate Requirements to Provide Monthly Operating Reports and Annual Occupational Radiation Exposure Reports In accordance with 10 CFR 50.90, "Application for amendment of license or construction permit," Exelon Generation Company, LLC (EGC) and AmerGen Energy Company, LLC (AmerGen) are requesting an amendment to Appendix A, Technical Specifications (TS) of the Facility Operating Licenses listed above. The proposed amendment will delete the TS requirements to submit monthly operating reports and annual occupational radiation exposure reports. The change is consistent with Revision 1 of NRC-approved Industry/Technical Specifications 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 (69 FR 35067) on June 23, 2004, as part of the Consolidated Line Item Improvement Process (CLIIP) .

The attached amendment request is subdivided as shown below.

Attachment 1 provides a description of the proposed changes and confirmation of applicability .

Attachments 2A - 2K include the marked-up TS pages for the stations listed above .

Attachments 3A - 3K include the associated typed TS pages with the proposed changes incorporated for the stations listed above .

Attachments 4A - 4J include the regulatory commitments for the stations listed above . Zion Nuclear Power Station does not have any associated regulatory commitments.

EGC and AmerGen request approval of the proposed change by April 29, 2005, with the amendment being implemented within 60 days of issuance .

The proposed amendment has been approved by the Plant Operations Review Committees at each of the stations and reviewed by the Chairman of the Nuclear Safety Review Board in accordance with the requirements of the EGC and AmerGen Quality Assurance Programs .

EGC and AmerGen are notifying the States of Illinois and New Jersey and the Commonwealth of Pennsylvania of this application for a change to the TS by sending a copy of this letter and its

October 21, 2004 U. S . Nuclear Regulatory Commission Page 3 attachments to the designated Officials in accordance with 10 CFR 50.91, "Notice for public comment ; State consultation ."

Should you have any questions concerning this letter, please contact Ms. Alison M. Mackellar at (630) 657-2817 .

I declare under penalty of perjury that the foregoing is true and correct.

Executed on 0& ot-bbAll A/Way-4 en Licensing and Regulatory Affairs Exelon Generation Company, LLC AmerGen Energy Company, LLC  : Evaluation of Proposed Changes Attachments 2A-2K : Markup of Proposed Technical Specifications Changes Attachments 3A-3K: Typed TS Pages with Proposed Changes Incorporated Attachments 4A-4J : Regulatory Commitments

ATTACHMENT 1 EVALUATION OF PROPOSED CHANGE INDEX 1 .0 INTRODUCTION 2 .0 DESCRIPTION OF PROPOSED AMENDMENT 3 .0 BACKGROUND 4 .0 REGULATORY REQUIREMENTS AND GUIDANCE 5 .0 TECHNICAL ANALYSIS 6 .0 REGULATORY ANALYSIS 6 .1 Verification and Commitments 7 .0 NO SIGNIFICANT HAZARDS CONSIDERATION 8.0 ENVIRONMENTAL EVALUATION 9.0 PRECEDENT

10.0 REFERENCES

1 .0 INTRODUCTION In accordance with 10 CFR 50.90, "Application for amendment of license or construction permit," Exelon Generation Company, LLC (EGC) and AmerGen Energy Company, LLC (AmerGen) are requesting an amendment to Appendix A, Technical Specifications (TS) for the following operating licenses .

Facility Operating Plant License Nos .

Braidwood Station, Units 1 and 2 NPF-72 and NPF-77 Byron Station, Units 1 and 2 NPF-37 and NPF-66 Clinton Power Station, Unit 1 NPF-62 Dresden Nuclear Power Station, Units 2 and 3 DPR-19 and DPR-25 LaSalle County Station, Units 1 and 2 NPF-1 1 and NPF-1 8 Limerick Generating Station, Units 1 and 2 NPF-39 and NPF-85 Oyster Creek Generating Station DPR-1 6 Peach Bottom Atomic Power Station, Units 2 and 3 DPR-44 and DPR-56 Three Mile Island Station, Unit 1 DPR-50 Quad Cities Nuclear Power Station, Units 1 and 2 DPR-29 and DPR-30 Zion Nuclear Power Station, Units 1 and 2 DPR-39 and DPR-48 The proposed amendment deletes the requirements in Technical Specifications (TS) for an annual report on occupational radiation exposures and for a monthly report of operating statistics and shutdown experience .

The proposed change is consistent with NRC-approved Industry/Technical Specifications Task Force (TSTF) Standard Technical Specification Change Traveler, TSTF-369, Revision 1, "Removal of Monthly Operating Report and Occupational Radiation Exposure Report ." The availability of this TS improvement through the Consolidated Line Item Improvement Process (CLIIP) was announced in the Federal Register on June 23, 2004 (69 FR 35067).

2.0 DESCRIPTION

OF PROPOSED AMENDMENT Consistent with the NRC-approved Revision 1 of TSTF-369, the proposed TS changes include the following.

Braidwood Station, Units 1 and 2 TS Section 5.6 .1 Occupational Radiation Exposure Report Deleted TS Section 5 .6 .4 Monthly Operating Reports Deleted Byron Station, Units and 2 TS Section 5.6 .1 Occupational Radiation Exposure Report Deleted TS Section 5.6.4 Monthly Operating Reports Deleted

Clinton Power Station TS Section 5.6.1 Occupational Radiation Exposure Report Deleted TS Section 5.6.4 Monthly Operating Reports Deleted Dresden Nuclear Power Station, Units 2 and 3 TS Section 5.6.1 Occupational Radiation Exposure Report Deleted TS Section 5.6.4 Monthly Operating Reports Deleted LaSalle County Station, Units I and 2 TS Section 5.6.1 Occupational Radiation Exposure Report Deleted TS Section 5.6.4 Monthly Operating Reports Deleted Limerick Generating Station, Units 1 and 2 TS Section 6.9 .1 .5.a Annual Occupational Radiation Exposure Deleted Report TS Section 6.9 .1 .6 Monthly Operating Reports Deleted Oyster Creek Generating Station TS Section 6.9 .1 .b Annual Exposure Data Report Deleted TS Section 6.9.1 .c Monthly Operating Report Deleted Peach Bottom Atomic Power Station, Units 2 and 3 TS Section 5.6.1 Occupational Radiation Exposure Report Deleted TS Section 5.6.4 Monthly Operating Reports Deleted Three Mile Island Station, Unit 1 TS Section 3.2.4 Reactor Vessel Water Level Revised reporting Instrumentation method for inoperable channels TS Section 6.9.1 .13.1 Annual Reports Deleted TS Section 6.9.1 .C I Monthly Operating Reports Deleted Quad Cities Nuclear Power Station, Units I and 2 TS Section 5.6.1 1 Occupational Radiation Exposure Report I Deleted TS Section 5.6.4 1 Monthly Operating Reports I Deleted Zion Nuclear Power Station, Units 1 and 2 TS Section 5.7.1 Occupational Radiation Exposure Report Deleted 1

As addressed in the safety evaluation published in the Notice of Availability for TSTF-369, EGC and AmerGen are proposing to adopt a part of NRC-approved Revision 4 to TSTF-258,

"Changes to Section 5.0, Administrative Controls." Specifically, the TS include a requirement to include in the monthly operating reports any challenges to pressurizer power operated relief valves or pressurizer safety valves (for pressurized water reactors) or safety/relief valves (for boiling water reactors) . The NRC model safety evaluation addressed the removal of requirements to submit monthly operating reports in those cases where the TS include a requirement to address challenges to relief and safety valves (i.e., if a licensee had not yet adopted the associated pat of TST4258) . The proposed change is consistent with the option described in the Notice of Availability published on June 23, 2004 (69 FR 35067) and the related documentation for both TSTF-369 and the limited portion of TSTF-258 included in this application . Removal of this requirement to address challenges to relief and safety valves is applicable to Braidwood, Byron, Clinton, Dresden, LaSalle, Limerick and Quad Cities .

As addressed in the safety evaluation published in the Notice of Availability for TSTF-369, the removal of the Monthly Operating Report and Annual Occupational Radiation Exposure Report TS Sections resulted in various editorial and formatting changes and do not revise technical or administrative requirements .

This application involves for sites with both operating and shutdown reactors . As addressed in the Notice of Availability TSTF4369, EGC and AmerGen have included in this application a regulatory commitment to support the NRC need to apportion radiation doses reported under 10 CFR Part 20 to the different categories of reactors at these sites.

Zion Nuclear Power Station, Units 1 and 2 are both permanently shutdown . Therefore, EGC is requesting only a deletion of the Occupational Radiation Exposure Report from the Zion Permanently Defueled Technical Specifications,

3.0 BACKGROUND

The background for this application is adequately addressed by the NRC Notice of Availability published on June 23, 2004 (69 FR 35067) and TSTF-369 .

4.0 REGULATORY REQUIREMENTS AND GUIDANCE The applicable regulatory requirements and guidance associated with this application are adequately addressed by the NRC Notice of Availability published on June 23, 2004 (69 FR 35067) and TSTF-369 .

5.0 TECHNICAL ANALYSIS

EGC and AmerGen have reviewed the the safety evaluation (SE) published on June 23, 2004, (69 FR 35067), as part of CLIIP Notice of Availability . This verification included a review of the NRC's SE, and the supporting information provided to support TSTF-369 . EGC and AmerGen have concluded that the justifications presented in the TSTF proposal and the safety evaluation prepared by the NRC are applicable to the Braidwood, Byron, Clinton, Dresden, LaSalle, Limerick, Oyster Creek, Peach Bottom, Three Mile Island (TMI) Unit 1, Quad Cities and Zion stations and justify this amendment for the incorporation of the changes to the applicable TS .

The Limerick, Oyster Creek, and TMI Unit 1 TS are in a custom format that does not coincide with the industry Standard Technical Specifications (STS). The Limerick Generating Station TS Index reference to the Monthly Operating Report will be deleted in addition to the applicable TS Sections. Limerick, Oyster Creek and TMI Unit 1 Monthly Operating Reports and Occupational Exposure Reports are located in Section 6.0 compared to Section 5.0 for STS.

Page 4 of 6

The Three Mile Island Unit 1 TS include a requirement in Section 3 .24, "Reactor Vessel Water Level Indication," to provide the details of reactor vessel water level instrumentation system channel inoperability in the Monthly Operating Report . This requirement is being revised to require submittal of a special report to the NRC providing the details of the inoperability within 14 days of one channel being inoperable for greater than 30 days, or both channels being inoperable for greater than 7 days.

Zion Nuclear Power Station, Units 1 and 2 are both permanently shutdown . Therefore, the Occupational Radiation Exposure Report will be deleted from the Defueled Technical Specifications .

6 .0 REGULATORY ANALYSIS A description of these proposed changes and the relationship to applicable regulatory requirements and guidance was provided in the NRC Notice of Availability published on June 23, 2004 (69 FR 35067) and 'TSTF4369.

6 .1 Verification and Commitments As discussed in the model SE published in the Federal Register on June 23, 2004, (69 FR 35067) for this TS improvement, EGC and AmerGen are making the following regulatory commitments.

1 . EGC and AmerGen are making a regulatory commitment to provide to the NRC using an industry database 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 regulatory commitment will be based on 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)).

Zion Nuclear Power Station is permanently shutdown and is not required to provide a monthly operating report .

2. Dresden and Peach Bottom have both operating and shutdown units. EGC is making a regulatory commitment to provide information to the NRC annually (e.g., with the annual submittal in accordance with 10 CFR 20 .2206) to support the apportionment of station radiation doses to differentiate between operating and shutdown units. The data will provide the summary distribution of annual whole body doses as presented in Appendix B of NUREG-0713, "Occupational Radiation Dose at Commercial Nuclear Power Reactors and Other Facilities," for each operating and shutdown unit.

Braidwood, Byron, Clinton, LaSalle, Limerick, Oyster Creek, Quad Cities and Zion do not have different reactor types or both operating and shutdown reactors .

7.0 NO SIGNIFICANT HAZARDS CONSIDERATION Exelon Generation Company, LLC (EGC) and AmerGen Energy Company, LLC (AmerGen) have reviewed the proposed no significant hazards consideration determination published on June 23, 2004 (69 FR 35067) as part of the CLIIP. EGC and AmerGen have concluded that the proposed determination presented in the notice is applicable to Braidwood, Byron, Clinton, Dresden, LaSalle, Limerick, Oyster Creek, Peach Bottom, TMI Unit 1, Quad Cities and Zion stations and the determination is hereby incorporated by reference to satisfy the requirements of 10 CF R 50.91 (a).

8.0 ENVIRONMENTAL EVALUATION EGC and AmerGen have reviewed the environmental evaluation included in the model SE published on June 23, 2004 (69 FR 35067) as part of the CLIIP . EGC and AmerGen have concluded that the NRC's findings presented in that evaluation are applicable to Braidwood, Byron, Clinton, Dresden, LaSalle, Limerick, Oyster Creek, Peach Bottom, TMI Unit 1, Quad Cities and Zion stations and the evaluation is hereby incorporated by reference for this application.

9.0 PRECEDENT This application is being made in accordance with the CLAP . EGC and AmerGen are not proposing variations or deviations from the TS changes described in TSTF-369, Revision 1 and the limited portion of TSTF-258, Revision 4, or the NRC's model SE published on June 23, 2004 (69 FR 35067).

10.0 REFERENCES

1 . Technical Specifications Task Force (TSTF) Standard Technical Specification Change Traveler, TSTF-369, Revision 1, "Removal of Monthly Operating Report and Occupational Radiation Exposure Report"

2. Federal Register, Volume 69, Number 120, "Notice of Availability of Model Application Concerning Technical Specifications Improvement to Eliminate Requirements to Provide Monthly Operating Reports and Occupational Radiation Exposure Reports Using the Consolidated Line Item Improvement Process," dated June 23, 2004
3. Technical Specifications Task Force (TSTF) Standard Technical Specification Change Traveler, TSTF-258, Revision 4, "Changes to Section 5 .0, Administrative Controls"

ATTACHMENT 2-A Markup of Proposed Technical Specifications Page Changes BRAIDWOOD STATION REVISED TS PAGES 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

NOTE --------------------------

As e submittal may be made for the facility . The subm should mbine sections common to both units .

.1 n annual basis of the number 0 station, utility,

. " " (including contractors), °or whom monitoring 9 annual deep d equivalent > 100 mrem tive deep dos quivalent (reported in k and jo functions (e .g ., reactor se ce inspection, routine (describe maintenance), waste I " " " lation supplements the

-" i ' e se assignments to various 2 a, ocket ionization r electronic dosimeter, alling < 20% of counted for . In

. "" quivalent rom extern sources s ou e ass~gne to ecific o'rk functions . The report covering the previous lendar shall be submitted by April 30 of each year .

BRAIDWOOD - UNITS 1 & 2 5 .6 - 1 Amendment °90°

Reporting Requirements 5 .6 5 .6 Reporting Requirements 5 .6 .2 Annual Radiological Environmental Operating R

NOTE -------------------------------

A single submittal may be made for the facility . The submittal should combine sections common to both units .

The Annual Radiological Environmental Operating Report covering the operation of the facility 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 .

5 .6 .3 Radioactive Effluent Release Report

NOTE -------------------------------

A single submittal may be made for the facility . The submittal shall combine sections common to both units .

The Radioactive Effluent Release Report covering the operation of the facility during the previous year shall be submitted prior to May 1 of each year in accordance with 10 CFR 50 .36a . The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the facility .

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 1,Section IV .B .1 .

5 .6 .4 0 s of operating statistics and shutdown ex ncluding d5- c of all challenges to rizer power operated relief valves 0 y valves, shall be submitted on a mont b of each month fol 1 owi 6'n

- dar month covered by the report .

BRAIDWOOD - UNITS 1 & 2 5 .6 - 2 Amendment

ATTACHMENT 2-13 Markup of Proposed Technical Specifications Page Changes BYRON STATION REVISED TS PAGES a6-1 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

_______________________NOTE-_____________________

total may be made for the facility . The sections common to both units .

a A tabulation on an ual basis of the numb of station, utility, and other personnel ( uding contractor, , for whom monitoring was performed, receiving annual dee ose equivalent > 100 mrem and the associated collectiV deep equivalent (reported in person-rem) according to work A A functions (e .g ., reactor operations and surveillance, i Pe inspection, routine maintenance, special mainte ce (de ibe maintenance), waste processing, and refueling This tabu ion I supplements the requirements of 10 CFR .2206 . The dose signments to various duty functions may estimated based on poc ionization chamber, thermol escence dosimeter (TAD), el tropic dosimeter, or film badge ts . Small exposures tota Q < 20% of the individu deep dose equivalent need not be acco ed for . In the aggre e, at least 80% of the total deep dose equi recei v from external sources should be assigned to speci maj ork functions . The report covering the previous cal en y shall be submitted by April 30 of each year .

BYRON - UNITS 1 & 2 5 .6 - 1 Amendment

Reporting Requirements 5 .6 5 .6 Reporting Requirements 5 .6 .2 Annual Radiological Environmental Operating Report

NOTE -------------------------------

A single submittal may be made for the facility . The submittal should combine sections common to both units .

The Annual Radiological Environmental Operating Report covering the operation of the facility 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 .

5 .6 .3 Radioactive Effluent Release Report

NOTE -------------------------------

A single submittal may be made for the facility . The submittal shall combine sections common to both units .

The Radioactive Effluent Release Report covering the operation of the facility during the previous year shall be submitted prior to May 1 of each year in accordance with 10 CFR 50 .36a . The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the facility .

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 is o operating statistics and shutdown expyrie including documen Ilenges to th operated relief valves or pressu submitted on a mon 6 later than the 15th o foll indar month covered by the report .

BYRON - UNITS 1 & 2 5 .6 - 2 Amendment

ATTACHMENT 2-C Markup of Proposed Technical Specifications Page Changes CLINTON POWER STATION REVISED TS PAGES 5 .0-17 51-18 5.0-19

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 .

A tabu on an annual basis of the number of station ti 1ity, and other sonnet (including contractors), for who onitoring was required, ceiving exposures > 100 mrem/yr a their associated man re xposure according to work job functions (e .g ., reactor opera ns and surveillance rnservice inspection, routine maintenance, spe al maintenan describe maintenance),

waste processing, and refued ng) . tabulation supplements the requirements of 10 CFR 20 .220 e dose assignments to various duty functions may be estima b d on pocket dosimeter, thermoluminescent dosimet (TLD), o ilm badge measurements .

Small exposures total g < 20% of the i ividual total dose need not be accounted ' In the aggregate, at east 80% of the total whole body dos eceived from external sources ould be assigned to specific jor work functions . The Occupation Radiation Exposur eport covering the activities of the unit the previ calendar year shall be submitted by March 31 ach 5 .6 .2 Annual Radiological Environmental Operating Re port The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted by May 1 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 .

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 (continued)

CLINTON 5 . 0-17 Amendment No .

Reporting Requirements 5 .6 5 .6 Reporting Requirements 5 .6 .2 Annual Radiological Environmental Operating Report (continued) 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 The Radioactive Effluent Release Report covering the operation of the unit during the previous calendar year shall be submitted by May 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 50, Appendix I, Section W .B .I .

5 .6 .4 Routine reports - o utdown experience, including documentation o nges to the main steam safety/relief valves on a monthly basis no later than calendar month co v 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. LCO 3 .2 .1, Average Planar Linear Heat Generation Rate (APLHGR),
2. LCO 3 .2 .2, Minimum Critical Power Ratio (MCPR),
3. LCO 3 .2 .3, Linear Heat Generation Rate (LHGR), and
4. LCO 3 .3 .1 .1, RPS Instrumentation (SR 3 .3 .1 .1 .14) .

(continued)

CLINTON 5 .0-18 Amendment No .

Reporting Requirements 5 .6 5 .6 Reporting Requirements 5 .6 .5 CORE OPERATING LIMITS REPORT (COLR) (continued)

The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC in General Electric Standard Application for Reactor Fuel (GESTAR), NEDE-24011-P-A .

The core operating limits shall be determined such that all applicable limits (e .g ., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met .

d. The COLR, including any midcycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC .

CLINTON 5 .0-19 Amendment No .

ATTACHMENT 2-D Markup of Proposed Technical Specifications Page Changes DRESDEN NUCLEAR POWER STATION REVISED TS PAGES 51-1 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

NOTE ----------------

ittal may be made for a multiple unit stat uld combine sections common to all units A tabulation on an a °r of station, utility, and other personnel (inc ), for whom monitoring was performed, receiving a dose equivalent > 100 mrem and the associated collective ose equivalent (reported in man-rem) according to work and J unctions (e .g ., reactor operations and surveillance, ser inspection, routine maintenance, special maint ance (dese De maintenance), waste processing, and refuelin This tabula supplements the requirements of 10 CF 0 .2206 . The dose a ignments to various duty functions may estimated based on pocke ionization chamber, thermol escence dosimeter (TLD), or ctronic dosimeter mea ements . Small exposures totaling 0% of the individual al dose need not be accounted for .

aggrega at least 80% of the total deep dose equivalen from e ernal sources should be assigned to specific major fun ions . The report covering the previous calendar year submitted by April 30 of each year .

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 (continued)

Dresden 2 and 3 5 .6-1 Amendment No . TOJ7

Reporting Requirements 5 .6 5 .6 Reporting Requirements 5 .6 .2 Annual Radiological Environmental Operating Report (continued)

(ODCM), and in 10 CFR 50, Appendix I, Sections IV .B .2, IV .B .3, and IV .C .

5 .6 .3 Radioactive Effluent Release 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 ; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit .

The Radioactive Effluent Release Report covering the operation of the unit shall be submitted prior to May 1 of each year in accordance with 10 CFR 50 .36a . 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 the Process Control Program and in conformance with 10 CFR 50 .36a and 10 CFR 50, Appendix I, Section IV .B .1 .

5 .6 .4 Routine reports o and shutdown experience, including documentation o es to the safety and relief valves, shall ed on a monthly b ater than the 15th following the calendar month cove the 5 .6 .5 CORE OPERATING LIMITS REPORT (COLR)

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 :

l . The APLNGR for Specification 3 .2 .1 .

2. The MCPR for Specification 3 .2 .2 .

(continued)

Dresden 2 and 3 5 .6-2 Amendment No .

ATTACHMENT 2-E Markup of Proposed Technical Specifications Page Changes LASALLE COUNTY STATION REVISED TS PAGES 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 .

___________________________NOTE-_______________________

e submittal may be made for a multiple unit stat The should combine sections common to all units gt the A tabulation on an 6 of station, utility, and other personnel ( I for whom monitoring was performed, receiving a dose equivalent > 100 mrem and the associated collective ge equivalent (reported in man-rem) according to work and ctions (e .g ., reactor operations and surveillance, i e inspection, routine maintenance, special mainteq e Wesc maintenance}, waste processing, and refueli is tabulatio pplements the requirements of 10 CFR .2206 . The dose assig ents to various duty functions may mated based on pocket ti on chamber, thermolu scence dosimeter (TLD), electro dosimeter, or film badge M ts . Small exposures totaling < of the individual 1 dose need not be accounted for . In the aggregate least 80% of the total deep dose equivalent from ex al sources should be assigned to specific major fund 6ns . The report covering the previous calendar year be Amitted by April 30 of each year .

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 (continued)

LaSalle 1 and 2 5 .6-1 Amendment No .

Reporting Requirements 5 .6 5 .6 Reporting Requirements 5 .6 .2 Annual Radiological Environmental Operating Report (continued)

(ODCM), and in 10 CFR 50, Appendix I, Sections IV .B .2, IV .B .3, and IV .C .

5 .6 .3 Radioactive Effluent Release 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 Radioactive Effluent Release Report covering the operation of the unit shall be submitted prior to May 1 of each year in accordance with 10 CFR 50 .36a . 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 the Process Control Program and in conformance with 10 CFR 50 .36a and 10 CFR 50, Appendix I, Section IV .B .1 .

Routine reports of o including documentation of a valves, shall be sub 15th of eac e

5 .6 .5 CORE OPERATING LIMITS REPORT (COLR)

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 :

l. The APLHGR for Specification 3 .2 .1 .
2. The MCPR for Specification 3 .2 .2 .
3. The LHGR for Specification 3 .2 .3 .

(continued)

LaSalle 1 and 2 5 .6-2 Amendment No .-I~~

ATTACHMENT 2-F Markup of Proposed Technical Specifications Page Changes LIMERICK GENERATING STATION - UNIT 1 REVISED TS PAGES 6-15 6-16 LIMERICK GENERATING STATION - UNIT 2 REVISED TS PAGES 6-15 6-16

ADMINISTRATIVE CONTROLS 6-9 . REPORTING REQUI REMENTS ROUTINE REPORTS 6 .9 .1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the Regional Administrator of the Regional Office of the NRC unless otherwise noted .

STARTUP REPORT 6 .9 .1 .1 A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an Operating License, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or'hydraulic performance of the unit .

6 .9 .1 .2 The startup report shall address each of the tests identified in Sub-section 14 .2 .12 of the Final Safety Analysis Report and shall include a descrip-tion of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications . Any corrective actions that were required to obtain satisfactory operation shall also be described . Any additional specific details required in license conditions based on other commitments shall be included in this report .

6.9 .1 .3 Startup reports shall be submitted within (1) 90 days following comple-tion of the startup test program, (2) 90 days following resumption or commence-ment 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 operation) supplementary reports shall be submitted at least every 3 months until all three events have been completed .

ANNUAL REPORTS_*_

6 .9 .1 .4 Annual reports covering the activities of the unit as described below for the previous calendar year shall be submitted prior to March. 1 of each year unless otherwise noted .

6 .9 .1 .5 Reports required on an annual basis shall include:

Occu ational Radiation Ex osure Report tabulat annual basis of the number of station and other personae lading contractors) rec exposures

>100 mrem/yr and their a d man-re "sure according to work and job functions (e .g ., r erations and surveillance, inservice inspection, rou aintenance, ial maintenance (describe mainten waste processing, and refuu - This tabulatio ements the requirements of 10CFR20 .2206 .

nts to various duty functions may be estimated based on po

  • A single submittal may be made for a multiple unit station .

JUN 2 2 1999 LIMERICK - NIT 1 6- 1 5 Amndmt No .

ADMIN?STRATIVE CONTRO LS_

ANNUAL REPORTS (Continued) dosi ments . Small e`x dose need not be accounted of the total whole-bo received be assigned is major work functions .

by April 30 of each year .

(Deleted)

C. Any other unit unique reports required on an annual basis .

d. The results of specific activity analysis in which the primary coolant exceeded the limits of Specification 3 .4 .5 . The following information shall be included : (1) Reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded ;

(2) Results of the last isotopic analysis for radioiodine performed prior to exceeding the limit, results of analysis while limit was exceeded and results of one analysis after the radioiodine activity was reduced to less than limit . Each result should include date and time of sampling and the radioiodine concentrations ; (3) Cleanup system flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded ; (4) Graph of the I-131 concentration and one other radioiodine isotope concentration in microcuries per gram as a function of time for the duration of the specific activity above the steady-state level ; and (5) The time duration when the specific activity of the primary coolant exceeded the radioiodine limit .

6 .9 .1 .6 r'(Rou s - of operating statistics and shutdown experien ing documentation of a s to the main steam systi,m-_~y relief valves, shall be submitted on a mont . Nuclear Regulatory Commission, ATTN : Document Control ..II:e sfiingto-Ifi, 555, with a copy to the Regional Admini, .~a-tor5 the Regional Office of the than the 15th~tf_.ea nth following the calendar month covered by the report.

AN NUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT*

6 .9 .1 .1 The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted before May 1 of each year . The report shall include summaries, interpreta-tions, analysis 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 (1) the ODCM and (2) Sections IV .B .2, IV .B .3, and IV .C of Appendix I to 10 CFR Part 50 .

  • A single submittal may be made for a multiple unit station .

LIMERICK - UNIT 1 6-16 Amendment No . tt, 46, AA,13M, MAR 1 4 2000

ADMINISTRATIVE CONTROLS 6 .9 REPORTING REQIREMENTS ROUTINE REPORTS 6 .9 .1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the Regional Administrator of the Regional Office of the NRC unless otherwise noted .

STARTU P REPORT 6 .9 .1 .1 A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an Operating License, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the unit .

6 .9 .1 .2 The startup report shall address each of the tests identified in Sub-section 14 .2 .12 of the Final Safety Analysis Report and shall include a descrip-tion of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications . Any corrective actions that were required to obtain satisfactory operation shall also be described . Any additional specific details required in license conditions based on other commitments shall be included in this report .

6 .9 .1 .3 Startup reports shall be submitted within (1) 90 days following comple-tion of the startup test program, (2) 90 days following resumption or commence-ment 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 operation) supplementary reports shall be submitted at least every 3 months until all three events have been completed.

ANNUAL REPORTS*

6 .9 .1 .4 Annual reports covering the activities of the unit as described below for the previous calendar year shall be submitted prior to March 1 of each year unless otherwise noted .

6 .9 .1 .5 _Reports required on n annual basis shall include :

Annua ational Radi ation Exaosure Report ~

A tabulation annual basis of the number of sta utility, and other personnel rsonnel ding contractors) r ' ing exposures

>100 mrem/yr and their assacfiat~ma~xposure according to work and job functionsons (e .g ., rations and surveillance, in inspection, r e maintenance, 'al maintenance (describe ma int waste processing, and refu 7his tabulati pplements the requirements of IOCFR20 .2206 . ose nments to various duty functions may be esti mated based on'p

  • A single submittal may be made for a multiple unit station .

JUN 2 2 1999 LIMERICK - UNIT 2 6-15 kwckrerrt No . 100

.ARWIS TRAT ANNUAL, REPORTS (Continued) do's t e uminescent dosimeter (TLD), or film bad is . Smal s al l i ng <20% of the total dose need not be accounte n egate, at least 80%

of the total whole-body _d iv ternaT sources should be assigned t o .,s~eci°fT"c major work functions . shat 1 be subm t-ed'6'"Y April 30 of each year .

b. (Deleted)
c. Any other unit unique reports required on an annual basis .
d. The results of specific activity analysis in which the primary coolant exceeded the limits of Specification 3 .4 .5 . The following information shall be included : (1) Reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded ;

(2) Results of the last isotopic analysis for radioiodine performed prior to exceeding the limit, results of analysis while limit was exceeded and results of one analysis after the radioiodine activity was reduced to less than limit . Each result should include date and time of sampling and the radioiodine concentrations ; {3} Cleanup system flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded ; (4) Graph of the I-131 concentration and one other radioiodine isotope concentration in microcuries per gram as a function of time for the duration of the specific activity above the steady-state level ; and (5) The time duration when the specific activity of the primary coolant exceeded the radioiodine limit .

MORTTHL P RAT N PORTS* T& o 6 .9 .1 .6 Ro r_ts of operating statistics and shutdown ex e r' ~;tcl ud-ing ocumentation a es to the main ste am iiear~s el i of valves, shall be submitted on a mon e U .S . Nuclear Regulatory Commission, ATTN : Documen slt, Washing 0555, with a copy to the Regi n rator of the Regional Offic e of the Nthan t each month following the calendar month covered the re ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT*

6 .9 .1 .7 The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted before May 1 of each year. The initial report shall be submitted prior to May 1 of the year following initial criticality . The report shall include summaries, interpretations, analysis of trends of the results of the Radiological Environmental Monitoring Program far the reporting period . The material provided shah be consistent with the objectives outlined in (1) the ODCM and (2) Sections IV.B.2, IV .B .3, and IV.C of Appendix I to 10 CfR Part 50 .

  • A single submittal may be made for a multiple unit station .

LIMERICK - UNIT 2 6-16 Amendment Na . xx, 100, 102 MAtt 1 4 20

ATTACHMENT 2-G Markup of Proposed Technical Specifications Page Changes OYSTER CREEK GENERATING STATION REVISED TS PAGES 6-13

6 .9 REPORTING REQUIREMENTS In addition to the applicable reporting requirements of 10 CFR, the following identified reports shall be submitted to the Administrator of the NRC Region 1 office unless otherwise noted 6.9 .1 ROUTINE REPORTS Startup Report . A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant. The report shall address each of the tests identified in the FSAR and shall in general include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications . Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specified details required in license conditions based on other commitments shall be included in this report .

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.

al Exvosur Data Report . Routine exposure data reports cov operatio f the facility during the previous calendar year shall be tted prior to Apri 0 of each year . Reports shall contain a tabulat bn an annual basis of the nu of station, utility, and other personne ficluding contractors) for wham pnitoring is required receive' sures greater than 100 mRernlyr . and the sociated man exposure according to work and job functions (this tab on s ements the requirements of Section 20 .2206 of 10 CFR Part 20 reactor operations and surveillance, inservice inspection, routine enance, ial maintenance (describe maintenance), waste pro ing, and refueling. c dose assignment to various duty functio ay be estimated based on p dosimeter, TZ .D, or film badge 'ernents. Small exposures totalling less 11 20% of the individu al dose need not be accounted for. In the aggrega at least 80% the total whole body dose received from external sources s igned to specific major work functions.

tine Re ort Routine reports of operating statistic shutdown expe hall be submitted on a monthl ich will include a narrative of operating ex _

o star, Office of Management and Program Control, ear Re Conunission, with a copy to the Regional no later than the 15th of each mo' wing the month covered by the report .

OYSTER CREEK 6-13 Amendment No. : 69, 78, 84, 108, 125, 134, 166,183, 191

ATTACHMENT 2-H Markup of Proposed Technical Specifications Page Changes PEACH BOTTOM ATOMIC POWER STATION UNIT 2 REVISED TS PAGES 5.0-19 5.0-20 PEACH BOTTOM ATOMIC POWER STATION UNIT 3 REVISED TS PAGES 5.0-19 5.0-20

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 .

Radiation Exposure ReD rt

NOTE--__--_---------_-_----__

A single bmittal may be made for a multiple unit statio submittal s d combine sections common to all units station .

A tabulation on an ann of station, utility, and other personnel (inc receiving an annual deep dose equivalent > 100 m associated collective deep dose equivalent (reported in pd em) according to work and job functions (e .g ., reactor operati and surveillance, inservice inspection, routine mainten spec i. .l maintenance (describe maintenance), waste proce hg, and ref ling) . This tabulation supplements the requir s of 10 CFR 20 . 06 . The dose assignments to vario duty functions may be timated based on pocket dosimeter, ermoluminescence dosimeter D), or film badge measurem s . Small exposures totalling < 2 the individual al dose need not be accounted for . In aggregat at least 80% of the total deep dose equivalen from e ernal sources should be assigned to specific major fun ions . The report shall be submitted by March 31 of each 5 .6 .2 Annual Radioloqical 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 Rauiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted by May 31 of each year . The report shall include summaries, interpretations, and analyses of trends of the results of the radiological environmental monitoring activities 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 1, Sections IV .B .2, IV .B .3, and IV .C .

(continued)

PBAPS UNIT 2 5 .0-19 Amendment No . A.

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 OOCM, 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 should combine sections common to all units at the station .

The Radioactive Effluent Release Report covering the operation of the unit during the previous year shall be submitted prior to May 1 of each year in accordance with 10 CFR 50 .36a . 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 OOCM and Process Control Program and in conformance with 10 CFR 50 .36a and 10 CFR 50, Appendix I, Section W .B .I .

5 .6 . Monthl Re orts nd shutdown experience he 15th of I I "1 - .011 oil I r J110 (continued)

PBAPS UNIT 2 5 . 0-20 Amendment No .

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 .

A singl~ubmittal may be made for a multiple unit statio The submittal 3^hpuld combine sections common to all units the A tabulation on an ann 1 basis o f the numb of station, utility, and other personnel (inc ing co ntractor receiving an annual deep dose equivalent > 100 ma nd associated collective deep dose equivalent (reported in pi o 2e m) according to work and job functions (e .g ., reactor operati and surveillance, inservice inspection, routine maintena spec 1 maintenance (describe maintenance), waste proces hg, and refu ing) . This tabulation supplements the requi hts of 1 0 CFR 20 . 6 . The dose assignments to vari duty funct ions may be e imated based on pocket dosimeter ermoluminescence dosimeter ( , or film badge measurem Small exposu res totallin g < 20 f the individual al dose need not be accounted for . In t aggregat at least 80% of the total deep dose equivalent eived from rnal sources should be assigned to specific major fu The report shall be submitted by March 31 of each 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 31 of each year . The report shall include summaries, interpretations, and analyses of trends of the results of the radiological environmental monitoring activities far 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 .8 .3, and N .C .

(continued)

PBAPS UNIT 3 5 . 0-19 Amendment No . 214 2i9

Reporting Requirements 5 .6 5 .6 Reporting Requirements 5 .6 .2 Annual Radiological Environmental Operating Resort (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 OOCM, 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 should combine sections common to all units at the station .

The Radioactive Effluent Release Report covering the operation of the unit during the previous year shall be submitted prior to May 1 of each year in accordance with 10 CFR 50 .36x . 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 OOCM and Process Control Program and in conformance with 10 CFR 50 .36a and 10 CFR 50, Appendix I, Section IV .B .1 .

5 .6 .4 Routine reports of operatin . . .-

shall be submitt~~ . . . . . .. all- t each . . - .

(continued)

PBAPS UNIT 3 5 . 0-20 Amendment No . 't142I9

ATTACHMENT 2-1 Markup of Proposed Technical Specifications Page Changes THREE MILE ISLAND STATION UNIT 1 REVISED TS PAGES 3-128 6-12 6-12a 6-13 6-14

1i 3 .24 Reactor Vessel Water Level Indication Applic abili ty Applies to the operability requirements for the Reactor Vessel Water Level Indication when the reactor is critical .

Objectives To assure operability of the Reactor Vessel Water Level instrumentation U which may be useful in diagnosing situations which could represent or lead to inadequate core_ cooling .

721 Soecification 0

a Two channels of the Reactor Vessel Water Level Instrumentation System U shall be OPERABLE .

w z

If one channel becomes INOPERABLE that channel shall be returned to If OPERABLE within 30 days . , the channel is not_ restored within 30 days, nclude cause, action being taken and projected date for BLE status .

With no channels OPERABLE, one channel shall be restored to OPERABLE status within 7 days . If at least one channel is not restored within 1 L_ a "tails <h>11 include cause, action being taken and projected date for return to OPERABLE status .

Bases The Reactor Vessel Water Level Indication (Reference 1) provides indication of the trend in water inventory in the hot legs and reactor vessel during the approach to inadequate core cooling (ICC) . In this manner additional information may be available to the operator to diagnose the approach of ICC and to assess the adequacy of responses taken to restore core cooling .

Each Reactor Vessel Water Level channel is comprised of a hot leg level indication and a reactor vessel level indication .

The system is required to be operable (as defined previously) when the plant is critical .

The system is an information system to aid the operator during the approach to inadequate core cooling . There is no regulatory limit for this system .

Inoperability of the system removes the availability of an information system . Other useful instrumentation for inadequate core cooling will be available . The Subcooling Margin Indication System is relied upon to determine subcooling margin when the reactor coolant pumps are operating or when natural circulation can be verified . When natural or forced circulation cannot be verified, the margin to saturation is determined by manual calculation, based on reactor coolant temperature (incore thermocouples) and pressure indications available in the control room and steam tables . See Tech . Spec . 3 .5 .5 .

3-128 Amendment No . 7¢j, 15~,

6 .9 REPORTIN G REQUIR EMENTS In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following identified reports shall be submitted to the Administrator of the NRC Region 1 Office unless otherwise noted .

6 .9 .1 Routine Reports A . Startup Report . A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have signi-ficantly altered the nuclear, thermal, or hydraulic performance of the plant . The report shall address each of the tests identified in the UFSAR, Chapter 13 and shall in general include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications . Any corrective actions that were required to obtain satisfactory operation shall also be described .

Any additional specific details required in license conditions based on other commitments shall be included in this report .

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 .

B . Annual Reports . Annual reports covering the activities of the unit as described below during the previous calendar year shall be submitted prior to March 1 of each year . (A single submittal may be made for the station . The submittal should combine those sections that are common to both units at the station .)

6-12 Amendment No . X2, 37, 77,

abulation on an annual basis of the number of station uti and other personnel (including contractors) whom mon ring was required, receiving exposures eater than 100 mr'e r and their associated man rem osure according to wo job functions, (e . e actor operations and sure lance, inservice pection, routine maintenance, special ma ance ibe maintenance),

waste processing, and refue' 9 The dose assignment to various duty functions may b imates based on pocket dosimeter, TLD, or film !rs. ge meas ments . Small exposures totaling le han 20% of t individual total dose need not be ounted for . In the a @.gate, at least 80% of the tot whole body dose received fro xternal sources sh be assigned to specific major work ctions .

(This blation supplements the requirements of Sec 20 . 6 of 10 CFR Part 20 .)

6-12a Amendment No . d'o,

2. The following information on aircraft movements at the Harrisburg International Airport :
a. The total number of aircraft movements (takeoffs and landings) at the Harrisburg International Airport for the previous twelve-month period .
b. The total number of movements of aircraft larger than 200,000 pounds at the Harrisburg International Airport for the previous twelve-month period, broken down into scheduled and non-scheduled (including military) takeoffs and landings, based on a current estimate provided by the airport manager or his designee .
3. The following information from the periodic Leak Reduction Program tests shall be reported :
a. Results of leakage measurements,
b. Results of visual inspections, and
c. Maintenance undertaken as a result of Leakage Reduction Program tests or inspections .
4. The following information regarding pressurizer power operated relief valve and pressurizer safety valve challenges shall be reported :
a. Date and time of incident,
b. Description of occurrence, and
c. Corrective measures taken if incident resulted from an equipment failure .
5. The following information regarding the results of specfic activity analysis in which the primary coolant exceeded limits of Technical Specification 3 .1 .4 .1 shall be reported :
a. Reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded ;

Results of the last isotopic analysis for radioiodine performed prior to exceeding the limit, results of analysis while limit was exceeded and results of one analysis after the radioiodine activity was reduced to less than limit. Each result should include date and time of sampling and the radioiodine concentrations ;

c. Cleanup system flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded ;
d. Graph of the I-131 concentration and one other radioiodine isotope concentration in microcuries per gram as a function of time for the duration of the specific activity above the steady-state level ; and
e. The time duration when the specific activity of the primary coolant exceeded the radioiodine limit .

6-13 Amendment No .

" ti ics and y basis to the U . S .

ater ifteenth of each month 6 .9 .2 DELETED 6-14 (Pages 6-15 and 6-16 deleted)

Amendment No . ,-° ,

ATTACHMENT 2-J Markup of Proposed Technical Specifications Page Changes QUAD CITIES NUCLEAR STATION REVISED TS PAGES 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

NOTE------------------------

A single ubmittal may be made for a multiple unit stati . The submittal ould combine sections common to all units t the station .

A tabulation on an of station, utility, and other personnel (in ), for whom monitoring was performed, receiving dose equivalent > 100 mrem and the associated collectiv e equivalent (reported in man-rem) according to work and unctions (e .g ., reactor operations and surveillance, se inspection, routine maintenance, special mainte nce (de ibe maintenance), waste processing, and refuelin This tabu ion supplements the requirements of 10 0 .2206 . The dose ssignments to various duty functions may stimated based on po ionization chamber, thermol nescence dosimeter (TLD), ectronic dosimeter ements . Small exposures totaling 20% of the individua dose need not be accounted for . In e aggre east 80% of the total deep dose equiva from ernal sources should be assigned to specific maj6 fun ons . The report covering the previous calendar yea submitted by April 30 of each year .

5 .6 .2 Annual Radiological Environmental Operating Regort

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 (continued)

Quad Cities 1 and 2 5 .6-1 Amendment No .

Reporting Requirements 5 .6 5 .6 Reporting Requirements 5 .6 .2 Annual Radiological Environmental Operating_ Report (continued)

(ODCM), and in 10 CFR 50, Appendix 1, Sections IV .B .2, IV .B .3, and IV .C .

5 .6 .3 Radioactive Effluent Release 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 ; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit .

The Radioactive Effluent Release Report covering the operation of the unit shall be submitted prior to May 1 of each year in accordance with 10 CFR 50 .36a . 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 the Process Control Program and in conformance with 10 CFR 50 .36a and 10 CFR 50, Appendix I, Section IV .B .1 .

Routine reports of o including documentation of a valves, shall be submi 15th o 0

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. The APLNGR for Specification 3 .2 .1 .
2. The MCPR for Specification 3 .2 .2 .

(continued)

Quad Cities 1 and 2 5 .6-2 Amendment No .

ATTACHMENT 2-K Markup of Proposed Technical Specifications Page Changes ZION NUCLEAR POWER STATION REVISED TS PAGES 5-14

Reporting Requirements 5.7 5 .0 Administrative Controls 5 .7 Reporting Requirements The following reports shall be submitted in accordance with 10 CFR 50.4.

5.7.1

_______________________________NOTE-__________________

A single su al may be made for a multiple unit station .

should combine ctions common to all units at the station A tabulation covering the 0 ious calendar yq shall be submitted prior to April 30 of each year on t tuber of ion utility, and other personnel (including contras beiving exposures greater than 100 mrem/year and their associat rem exposure according to work and job functions (e .g., fuel h mg, su ance, routine maintenance, special maintenance (des e maintenance), waste processing).

This tabulation supple nts the requirements o CFR 20.2206 . The dose assignments various duty functions may be 6 ates based on pocket dosi ir', TLD, or film badge measurements . S I exposures totaling le han 20% of the individual total dose need not b ccounted for. I aggregate, at least 80% of the total whole body dose eived fr external sources shall be assigned to specific major work functIi S .

5 .7 .2 Annual Radiological ...Environmental Operating Report

_____________NOTE-_______________ ----------------------------

A single submittal may be made for a multiple unit station.

The Annual Radiological Environmental Operating Report covering unit activities during the previous calendar year shall be submitted before May 15 of each year . The report shall include summaries, interpretations, and analysis 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 (1) the ODCM and (2)

Sections IV .B .2, IV .13.3, and lV .C of Appendix I of 10 CFR Part 50.

(continued)

Zion Station 5-14 Amendment Nos . 4-86 ~-7

ATTACHMENT 3-A Typed Pages for Technical Specifications Changes BRAIDWOOD STATION REVISED TS PAGES 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)

BRAIDWOOD - UNITS 1 & 2 5 .6 - 1 Amendment

Reporting Requirements 5 .6 5 .6 Reporting Requirements 5 .6 .2 Annual Radiological Environmental Operating R

NOTE -------------------------------

A single submittal may be made for the facility . The submittal should combine sections common to both units .

The Annual Radiological Environmental Operating Report covering the operation of the facility 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 Off site Dose Calculation Manual (ODCM), and in 10 CFR 50, Appendix I, Sections IV .B .2, IV .B .3, and IV .C .

5 .6 .3 Radioactive Effluent Release Report

NOTE -------------------------------

A single submittal may be made for the facility . The submittal shall combine sections common to both units .

The Radioactive Effluent Release Report covering the operation of the facility during the previous year shall be submitted prior to May 1 of each year in accordance with 10 CFR 50 .36a . The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the facility .

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)

BRAIDWOOD - UNITS 1 & 2 5 .6 - 2 Amendment

ATTACHMENT 3-13 Typed Pages for Technical Specifications Changes BYRON STATION REVISED TS PAGES 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)

BYRON - UNITS 1 & 2 5 .6 - 1 Amendment

Reporting Requirements 5 .6 5 .6 Reporting Requirements 5 .6 .2 Annual Radiological Environmental Operating Report

NOTE -------------------------------

A single submittal may be made for the facility . The submittal should combine sections common to both units .

The Annual Radiological Environmental Operating Report covering the operation of the facility 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 .

5 .6 .3 Radioactive Effluent Release Report

NOTE -------------------------------

A single submittal may be made for the facility . The submittal shall combine sections common to both units .

The Radioactive Effluent Release Report covering the operation of the facility during the previous year shall be submitted prior to May 1 of each year in accordance with 10 CFR 50 .36a . The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the facility .

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)

BYRON -- UNITS 1 & 2 5 .6 - 2 Amendment

ATTACHMENT 3-C Typed Pages for Technical Specifications Changes CLINTON POWER STATION REVISED TS PAGES aO-17 51-18 ao-19

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 The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted by May 1 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 .

The Annual Radiological Environmental Operating Report 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 tabulate 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 The Radioactive Effluent Release Report covering the operation of the unit during the previous calendar year shall be submitted by May 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 50, Appendix I, Section IV .B .1 .

5 .6 .4 Deleted (continued)

CLINTON 5 .0-17 Amendment No .

Reporting Requirements 5 .6 5 .6 Reporting Requirements 5 .6 .5 CORE OPERATING LIMITS REPORT (COLR)

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. LCO 3 .2 .1, Average Planar Linear Heat Generation Rate (APLHGR),
2. LCO 3 .2 .2, Minimum Critical Power Ratio (MCPR),
3. LCO 3 .2 .3, Linear Heat Generation Rate (LHGR), and
4. LCO 3 .3 .1 .1, RPS Instrumentation (SR 3 .3 .1 .1 .14) .
b. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC in General Electric Standard Application for Reactor Fuel (GESTAR), NEDE-24011-P-A .
c. The core operating limits shall be determined such that all applicable limits (e .g ., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met .
d. The COLR, ng any midcycle revisions or supplements, shall be prov ed upon issuance for each reload cycle to the NRC .

(continued)

CLINTON 5 .0-18 Amendment No .

Reporting Requ ents 5 .6 This page intentionally left blank CLINTON 5 .0- 1 9 Amendment No .

ATTACHMENT 3-D Typed Pages for Technical Specifications Changes DRESDEN NUCLEAR POWER STATION REVISED TS PAGES a6-1 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 Raaar P=t

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 (continued)

Dresden 2 and 3 5 .6- 1 Amendment No .

Reporting Requirements 5 .6 5 .6 Reporting Requirements 5 .6 .2 Annual Radiological Environmental Operating Report (continued)

(ODCM), and in 10 CFR 50, Appendix I, Sections IV .B .2, IV .B .3, and H .C .

5 .6 .3 Radioactive Effluent Release 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 ; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit .

The Radioactive Effluent Release Report covering the operation of the unit shall be submitted prior to May 1 of each year in accordance with 10 CFR 50 .36a . 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 the Process Control Program and in conformance with 10 CFR 50 .36a and 10 CFR 50, Appendix I, Section H .B .I .

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 . The APLNGR for Specification 3 .2 .1 .

2. The MCPR for Specification 3 .2 .2 .

(continued)

Dresden 2 and 3 5 .6-2 Amendment No .

ATTACHMENT 3-E Typed Pages for Technical Specifications Changes LASALLE COUNTY STATION REVISED TS PAGES 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 (continued)

LaSalle 1 and 2 5 .6-1 Amendment No .

Reporting Requirements 5 .6 5 .6 Reporting Requirements 5 .6 .2 Annual Radiological Environmental Operating Report (continued)

(ODCM), and in 10 CFR 50, Appendix 1, Sections IV .B .2, IV .B .3, and IV .C .

5 .6 .3 Radioactive Effluent Release jaL- 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 Radioactive Effluent Release Report covering the operation of the unit shall be submitted prior to May 1 of each year in accordance with 10 CFR 50 .36a . 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 the Process Control Program and in conformance with 10 CFR 50 .36a and 10 CFR 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. The APLHGR for Specification 3 .2 .1 .
2. The MCPR for Specification 3 .2 .2 .
3. The LHGR for Specification 3 .2 .3 .

(continued)

LaSalle 1 and 2 5 .6-2 Amendment No .

ATTACHMENT 3-F Typed Pages for Technical Specifications Changes LIMERICK GENERATING STATION - UNIT 1 REVISED TS PAGES 6-15 6-16 LIMERICK GENERATING STATION - UNIT 2 REVISED TS PAGES 6-15 6-16

ADM_ZftiI TRAT_I_V]~-_C.ON?. R0 LS 6 .9 REPORTING REnl1I REME NJ -

ROUTINE REPORTS 6 .9 .1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the Regional Administrator of the Regional Of`ice of the NRC unless otherwise noted .

STARTUP REPORT 5 .9 .1 .1 A summary report of plan- startup and power escalation testing shall be submitted following (1) receipt of an Operating License, (2) amendment to the license involvirg a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuc-leer, thermal, or hydraulic performance of the unit .

6 .9 .1 .2 The startup report shall address each of the tests .identified in Sub-section 14 .2 .12 of the Final Safety Analysis Report and shall include a descrip-tion of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications . Any corrective actions that were required to obtain satisfactory operation shall also be described . Any additional specific details required in license conditions based on other commitments shall be included in this report .

5 .9 .1 .3 Startup reports shall be submitted within (1) 90 days following comp'e-tion of the startup test program, (2) 90 days following resumption or commence-rne"it; of commercial power operation, or (3) 9 months following initial critica - ity, 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 operation) supplementary reports shall be submitted at least every 3 months until a -- three events have been completed .

ANNUAL RE2DRT~*

5 .9 .1 .4 Annual reports covering the activities of the unit as described below for the previous calerdar year shall be submitted prior to March 1 of each year unless otherwise noted .

6 .9 .1 .5 Reports required on an annual basis shall include :

a. Deleted
  • !? single submittal may be made =or a multiple unit station .

LIMERICK - UNIT 1 6-15 Amendnent No . 4_4~,

ADM I Nj $IF~T T `:, E_ __ _0_NT P r)! S ANNUAL REPORT-a (Continued) b {Deleted) c Any other unit unique reports required on an annual basis .

d The results of specific activity analysis in which the primary coolant exceeded the limits of Specification 3 .4 .5 . The following information shall be included : (1) Reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prio- to the first sample in which the limit was exceeded ;

A) Results of the last isotopic analysis for radioiodine performed prior to exceeding the limit, results of analysis while limit was exceeded and esults of one analysis after the radioiodine activity was reduced to less than limit . Each result should include date and time of sampling and the radioiodine concentrations ; (3) Cleanup system flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded ; (4) Graph of the :-131 concentration and one other radioiodine isotope ccrcentration rn microcu-ies per gram as a function of time for the duration of the specific activity above the steady state level ; and (5) The time duration when the specific activity of the primary coolant exceeded the radioiodine limit .

MONTHLY OPERATING REPORTS*

6 . 9 . i .6 De eted ANNUAL-RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT*

6 .9 .1 .7 The Annual Radiologica - Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted before May I of each year . The repor -- shall include summaries, interpreta-tions, analysis 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 (1) the ODCM and (2) Sections IV .B .2, IV .B .3, and IV .C of Appendix I to 10 CFR --, art 50 .

single submittal may be made for a multiple unit station .

LIMERICK - UNIT 1 6-16 Amendment No . 9, 4-G, 48- 1

ADMJ .N1 __T_MT 1 V E CANT I 6 .9 REPORTING RKLI-FEMENTS ROUTINE REPORTS 6 .9 .1 In addition to the appl'cable reporting re .: jirements of Title 10, Code of Federal Regulations, the fo' - ow 4 ng reports shall be submitted to the Regional Administrator oF the <:eqional Offce o' the NRC unless otherwise notec .

STARTJP REPORT 6 .9 .1 .1 A summary report of plant startup and power, escalation testing shall be :submitted following (1) receipt of an Operating License, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have signifiCdritly altered the ruclear, thermal, or hydraulic performance of the uni -, .

6 .9 .1 .2 The startup report shall address each of the tests identified in Sub-section 14 .2 .12 of the Final Safety Ana - ysis Report and shall include a descrip-

- ion of the measured values of the operatng conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications . Any corrective actions that were required to obtain satisfactory operation shall also be described . Any additional specific de -

-ails required in license conditions based on other commitments shall be included in this report .

6 .9 .1 .3 Startup reports shall be submitted within (1) 90 days following comple-

,ion of the startup test prcgram, (2 .. 90 days Yellowing resumption or commerce-ment 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 operation) supplementary reDorts shall be submitted a -- least every 3 months until all three events have been completed .

ANNUA_ R-- - ?DRTS*

6 .9 .1 .4 Annual reports covering the activites of the unit as described below for the previous calendar year shall be submitted prior to March 1 of each year unless otherwise noted .

6,9 .1 .5 Reports requiced or an annual basis shall include :

d . Deleted

  • A single submittal may be made for a mule -*p - e unit station .

-IM-- RICK - UNIT 2 6-15 Amendment No . 4-0-G,

ADM_I.NISTRA,T IVE-_-CONTROLS ANNU AL RE PORTS (Cont-nued)

b. (Deleted)

Any other uni- uniq ;ja reports required on an annua-! basis .

d. The results o= specific activity analysis in which the primary coolant exceeded the limits of Specification 3 .4 .5 . The 'ollowing information shall be included : (1) Reactor power history s`larting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior -o the first _ sample in which the limit was exceeded ;

(2) Results of she last isotopic analysis for radioiod-ne performed prior to exceeding the limit, results of analysis while limit was exceeded and results of one analysis after the radioiodine activity was reduced to less than limit . Each result should include da-e and time of samp - ; ng and the radioiodine concentrations ; (3) Cleanup system flow h~story sta^ting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the lint was exceeded ; (4) Graph of the 1-131 concentration and one other rad-oiodine isotope concentration in microcuries per gram as a function of time for the duration of the specific activity above the steady-state level ; and (5) The time duration when the specific activity of the primary coolant exceeded the radioiodine 1 -i n -it .

MO NTHLY OPERATING REPORT*

6 9 .1 .6 Deleted ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT*

6 .9 .1 .7 The Annual Radiological Env - ronmental Dperating Report covering the operation of the urit during the previous calendar year shall be submitted before Hay 1 of each year . The init ;.al report shall be submitted prior to May 1 of the year following initial criticality . The report shall include summaries, interpretatiors, analysis of trends of the results of the Radiological Environmental Monitoring Program for the reporting period . the be consistent with the objectives outlined in (1) the material provided shall and Sections IV .B .2, IV .B .3, and I'V .C of Appendix I to 10 CFR Part 50 .

ODCM (2)

  • A single submittal may be made for a mul'--iple .)nit station .

',LIMERICK - UNIT 2 6-16 Amencment No . 44, -'_440, ,

ATTACHMENT 3-G Typed Pages for Technical Specifications Changes OYSTER CREEK GENERATING STATION REVISED TS PAGES 6-13

6.9 REPORTING REQUIREMENTS In addition to the applicable reporting requirements of 10 CFR, the following identified reports shall be submitted to the Administrator of the NRC Region I office unless otherwise noted.

6.9.1 ROUTINE REPORTS

a. Startup Report . A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant. The report shall address each of the tests identified in the FSAR and shall in general include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications . Any corrective actions that were required to obtain satisfactory operation shall also be described . Any additional specified details required in license conditions based on other commitments shall be included in this report .

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.

DELETED

c. DELETED OYSTER CREEK 6-13 Amendment -No. : ,

134, 166, 183, 1,91,

ATTACHMENT 3-H Typed Pages for Technical Specifications Change PEACH BOTTOM ATOMIC POWER STATION UNIT 2 REVISED TS PAGES 5.0-19 5.0-20 PEACH BOTTOM ATOMIC POWER STATION UNIT 3 REVISED TS PAGES 5 .0-19 5 .0-20

Reporting Requirements 5 .6 5 .0 ADMINISTRATIVE CONTROLS 5 .6 Report - ng Requirements The following reports shall be submitted 'n 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 . 7h submittal shou7d combine sections common to a7l units at the station .

The Annual Rad 4 ological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted by May 31 of each year . The report shall include summaries, interpretations, and analyses of trends if the results of the radiological environmental monitoring activities for the reporting period . The material provided shall be consistent with the objectives outlined in the Offsite Dose Ca7culation Manua -

(ODCM), and in 10 DER 60, Appendix 1, Sections IV .B .2, IV .8 .3, and P .C .

Coontinued)

PBAPS LNIT 2 52-19 Amendment No .

Reporting Requiremen-s 5 .6 5 .6 Reporting Requirements 5 .6 .2 Annual Radiological Environmertal Operating Resort (~ontinued ;)

The Annual Radiological Environmental Operating Report shall include the results of analyses of all radiological environmental samples and of al - environmental radiation measurerrrents taker 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 tab-e in the Radiological Assessment Branch Technical Position, Revision 1, November 1979 . In the event that some individual results are net available for inclusion with the report, the report shall be submitted notirg and explainira the reasons for the missing results . The missing da` a shall be submitted in a supplementary report as soon as possible .

5 .6 .3 Radioacti ve Effluent Rele ase Rep ort

-__NOTE -______________________________

A single submittal may be made for a m:Altiple unit station . The submittal should combine sections common to all units at the station .

The Radioactive Effluent Release Report covering the operaticr of the unit during the previous year shall be submitted prior Lc May 1 of each year in accordance w ;:th 13 CFR 50 .36a . The report sha-1 include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste releasec from the unit . The material provided shall be consisten -~ with the objectives outlined in the ODCM and Process Control Program and it conformance with 10 CFR 53 .36a and 10 CFR 50, Appendix I, Section .V .B .1 .

5 .6 .4 Deleted

(.continued)

PBAPS UNIT 2 5 . 0-20 Amendment

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 Radiologica7 Environmental

- e r dL i -n g Report u-

NOTE -----------------------------

A single submittal may b e made for a multiple unit station . The submittal should combine sections common to all unin at the station .

The Annual Radjolog : cal Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted by May al of each year . The report shall include' summaries, interpreta~ions, and ana7yses of trends of the results of the radiological environmental monitoring activiiies for Lhe reporting period . The material provided shall be consistent with the objectives outYned in the Offs 4 te Dose Calculaoioi Manual (ODCM), and in 10 CFR 50, Appendix :, Sections W .B .2, W .B .3, and P .C .

(continued )

PBADS UNIT 3 5 .0-19 Amendm No .

Reporting Requirements 5 .6 5 .6 Reporting Requirement.

5 .6 .2 Annual Radiological =nvironmenta' Operating_ Report (continued ;

The Annual Radiological Environmental Operating Report shall include the results of analyses oi - all radiological environmental samples and of al' environmental radiation measurements taken during the period pu^scant Lc the locations specified in the table and "igares in the ODCM, as well as sumrnarizeC grid tabulated results of these analyses and measurements in the format of the table in the Radiological Assessmen- Branch Technical Position, Revision 1, November 1979 . In the event that some individ'ual 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 submi`-tal should combine sections common to all un ; ts at the station .

The Radioactive Effluent Release Report coverirg the operatic:r of the unit during the previous year shall be submitted prior tc May 1 of each year in accordance w-th 13 CFR 50 .36a . The report shall include a summary of the quantities of radioactive liqu - iu and gaseous: effluents and solid waste released from the unit . The material proviced shall be consistent with the objectives outlined in the ODCM anc Process Control Program and in conformance with 10 CFR 50 .36a and 10 CFR 50, Appendix I, Section IV .B .1 .

5 .6 .4 De - e_-ed

(.continued_)

PBAPS UNIT 3 5 .0-20 Amendment No .

ATTACHMENT 3-I Typed Pages for Technical Specifications Changes THREE MILE ISLAND STATION UNIT 1 REVISED TS PAGES 3-128 6-12 6-13 LETED TS PAGES 6-12a 6-14

3 .24 Reactor Vessel Water Level Indication Applicability Applies to the operability requirements for the Reactor Vessel Water Level Indication when the reactor is critical .

Objectives To assure operability of the Reactor Vessel Water Level instrumentation which may be useful in diagnosing situations which could represent or lead to inadequate core cooling .

Specification Two channels of the Reactor Vessel Water Level Instrumentation System shall be OPERABLE .

If one channel becomes INOPERABLE that channel shall be returned to OPERABLE within 30 days . If the channel is not restored within 30 days, within 14 days, submit a special report to the NRC providing the details of the inoperability, to include cause, action being taken and projected date for return to OPERABLE status .

With no channels OPERABLE, one channel shall be restored to OPERABLE status within 7 days . If at least one channel is not restored within 7 days, within 14 days, submit a special report to the NRC providing the details of the inoperability, to include cause, action being taken and projected date for return to OPERABLE status .

Bases The Reactor Vessel Water Level Indication (Reference 1) provides indication of the trend in water inventory in the hot legs and reactor vessel during the approach to inadequate core cooling (ICC) . In this manner additional information may be available to the operator to diagnose the approach of ICC and to assess the adequacy of responses taken to restore core cooling .

Each Reactor Vessel Water Level channel is comprised of a hot leg level indication and a reactor vessel level indication .

The system is required to be operable (as defined previously) when the plant is critical .

The system is an information system to aid the operator during the approach to inadequate core cooling . There is not regulatory limit for this system .

Inoperability of the system removes the availability of an information system . Other useful instrumentation for inadequate core cooling will be available . The Subcooling Margin Indication System is relied upon to determine subcooling margin when the reactor coolant pumps are operating or when natural circulation can be verified . When natural or forced circulation cannot be verified, the margin to saturation is determined by manual calculation, based on reactor coolant temperature (moose thermocouples) and pressure indications available in the control room and steam tables . See Tech . Spec . 3 .5 .5 .

3-128 Amendment No .

6 .9 REPORTING REQUIREMENTS In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following identified reports shall be submitted to the Administrator of the NRC Region 1 Office unless otherwise noted .

6.9 .1 Routine Reports A. Startup Report . A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating license, (2) amendmen-T to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant. The report shall address each of the tests identified in the UFSAR, Chapter 13 and shall in general include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications . Any corrective actions that were required to obtain satisfactory operation shall also be described .

Any additional specific details required in license conditions based on other commitments shall be included in this report .

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.

B. Annual Reports. Annual reports covering the activities of the unit as described below during the previous calendar year shall be submitted prior to March 1 of each year . (A single submittal maybe made for the station. The submittal should combine those sections that are common to both units at the station .)

DELETED

2. The following information on aircraft movements at the Harrisburg International Airport:

a . The total number of aircraft's movements (takeoffs and landings) at the Harrisburg International Airport for the previous twelve-month period .

b. The total number of movements of aircraft larger than 200,000 pounds at the Harrisburg International Airport for the previous twelve-month period, broken down into scheduled and non-scheduled (including military) takeoffs and landings, based on a current estimate provided by-the airport manager or his designee .

6- 1 2 Amendment No.

The following information from the periodic Leak Reduction Program tests shall be reported :

a. Results of leakage measurements,
b. Results of visual inspections, and
c. Maintenance undertaken as a result of Leakage Reduction Program tests or inspections.
4. The following information regarding pressurizer power operated relief valve and pressurizer safety valve challenges shall be reported :
a. Date and time of incident,
b. Description of occurrence, and
c. Corrective measures taken if incident resulted from an equipment failure.
5. The following information regarding the results of specific activity analysis in which the primary coolant exceeded limits of Technical Specifications 3.1 .4.1 shall be reported :
a. Reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded ;
b. Results of the last isotopic analysis for radioiodine performed prior to exceeding the limit, results of analysis while limit was exceeded and results of one analysis after the radioiodine activity was reduced to less than limit. Each result should include date and time of sampling and the radioiodine activity was reduced to less than limit.

Each result should include date and time of sampling and the radioiodine concentrations ;

c. Cleanup system flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded ;

Graph of the 1-131 concentration and one other radioiodine isotope concentration in microcuries per gram as a function of time for the duration of the specific activity above the steady-state level ; and

e. The time duration when the specific activity of the primary coolant exceeded the radioiodine limit.

C. DELETED 6.9 .2 DELETED 6-13 (Pages 6-14, 6-15, and 6-16 deleted)

Amendment No.

ATTACHMENT 3-J Typed Pages for Technical Specifications Changes QUAD CITIES NUCLEAR POWER STATION REVISED TS PAGES 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 (continued)

Quad Cities 1 and 2 5 .6-1 Amendment No .

Reporting Requirements 5 .6 5 .6 Reporting Requirements 5 .6 .2 Annual Radiological Environmental Operating R (continued)

(ODCM), and in 10 CFR 50, Appendix 1, Sections IV .B .2, IV .B .3, and IV .C .

5 .6 .3 Radioactive Effluent Release - 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 ; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit .

The Radioactive Effluent Release Report covering the operation of the unit shall be submitted prior to May 1 of each year in accordance with 10 CFR 50 .36a . 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 the Process Control Program and in conformance with 10 CFR 50 .36a and 10 CFR 50, Appendix 1,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. The APLHGR for Specification 3 .2 .1 .
2. The MCPR for Specification 3 .2 .2 .

(continued)

Quad Cities 1 and 2 5 .6-2 Amendment No .

ATTACHMENT 3-K Typed Pages for Technical Specifications Changes ZION NUCLEAR POWER STATION REVISED TS PAGES 5-14

Reporting Requirements 5.7 5 .0 Administrative Controls 5 .7 Reporting Requirements The following reports shall be submitted in accordance with 10 CFR 50.4.

5 .7.1 (Deleted) 5 .7.2 Annual Radiological Environmental Operating Report

NOTE ----------------------------------------------

A single submittal may be made for a multiple unit station.

The Annual Radiological Environmental Operating Report covering unit activities during the previous calendar year shall be submitted before May 15 of each year. The report shall include summaries, interpretations, and analysis 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 (1) the ODCM and (2)

Sections IV .13 .2, IV.B .3, and IV .C of Appendix I of 10 CFR Part 50 .

(continued)

Zion Station 5-14 Amendment Nos .

ATTACHMENT 4-A REGULATORY COMMITMENTS FOR BRAIDWOOD STATION The following table identifies those actions committed to by Exelon Generation Company, LLC (EGC) in this document. Any other statements in this submittal are provided for information purposes and are not considered to be regulatory commitments . Please direct questions regarding these commitments to Alison Mackellar at (630) 657-2817 .

Regulatory Commitments Due Date / Event Exelon Generation Company, LLC (EGC) is making a Implemented by TS Amendment regulatory commitment to provide to the NRC using an implementation date.

industry database 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 regulatory commitment will be based on 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)) .

ATTACHMENT 4-B REGULATORY COMMITMENTS FOR BYRON STATION The following table identifies those actions committed to by Exelon Generation Company, LLC (EGC) in this document. Any other statements in this submittal are provided for information purposes and are not considered to be regulatory commitments . Please direct questions regarding these commitments to Alison Mackellar at (630) 657-2817 .

Regulatory Commitments Due Date / Event Exelon Generation Company, LLC (EGC) is making a Implemented by TS Amendment regulatory commitment to provide to the NRC using an implementation date.

industry database 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 regulatory commitment will be based on 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)).

ATTACHMENT 4-C REGULATORY COMMITMENTS FOR CLINTON POWER STATION The following table identifies those actions committed to by AmerGen Energy Company, PLC (AmerGen) in this document . Any other statements in this submittal are provided for information purposes and are not considered to be regulatory commitments . Please direct questions regarding these commitments to Alison Mackellar at (630) 657-2817 .

Regulatory Commitments Due Date / Event AmerGen Energy Company, PLC is making a regulatory Implemented by TS Amendment commitment to provide to the NRC using an industry implementation date.

database 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 regulatory commitment will be based on 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)).

ATTACHMENT 4-D REGULATORY COMMITMENTS FOR DRESDEN NUCLEAR POWER STATION The following table identifies those actions committed to by Exelon Generation Company, LLC (EGC) in this document. Any other statements in this submittal are provided for information purposes and are not considered to be regulatory commitments. Please direct questions regarding these commitments to Alison Mackellar at (630) 657-2817 .

Regulatory Commitments Due Date / Event Exelon Generation Company, LLC (EGC) is making a Implemented by TS Amendment regulatory commitment to provide to the NRC using an implementation date.

industry database 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 regulatory commitment will be based on 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)).

EGC is making a regulatory commitment to provide Implemented by TS Amendment information to the NRC annually (e.g., with the annual implementation date .

submittal in accordance with 10 CFR 20.2206) to support the apportionment of station radiation doses to differentiate between operating and shutdown units. The data will provide the summary distribution of annual whole body doses as presented in Appendix B of NUREG-0713, "Occupational Radiation Dose at Commercial Nuclear Power Reactors and Other Facilities," for each operating and shutdown unit .

ATTACHMENT 4-E REGULATORY COMMITMENTS FOR LASALLE COUNTY STATION The following table identifies those actions committed to by Exelon Generation Company, LLC (EGC) in this document. Any other statements in this submittal are provided for information purposes and are not considered to be regulatory commitments . Please direct questions regarding these commitments to Alison Mackellar at (630) 657-2817 .

Regulatory Commitments Due Date / Event Exelon Generation Company, LLC (EGC) is making a Implemented by TS Amendment regulatory commitment to provide to the NRC using an implementation date.

industry database 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 regulatory commitment will be based on 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)).

ATTACHMENT 4-F REGULATORY COMMITMENTS FOR LIMERICK GENERATING STATION The following table identifies those actions committed to by Exelon Generation Company, LLC (EGC) in this document. Any other statements in this submittal are provided for information purposes and are not considered to be regulatory commitments. Please direct questions regarding these commitments to Alison Mackellar at (630) 657-2817 .

Regulatory Commitments Due Date / Event Exelon Generation Company, LLC (EGC) is making a Implemented by TS Amendment regulatory commitment to provide to the NRC using an implementation date.

industry database 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 regulatory commitment will be based on 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)).

ATTACHMENT 4-G REGULATORY COMMITMENTS FOR OYSTER CREEK GENERATING STATION The following table identifies those actions committed to by AmerGen Energy Company, LLC (AmerGen) in this document . Any other statements in this submittal are provided for information purposes and are not considered to be regulatory commitments . Please direct questions regarding these commitments to Alison Mackellar at (630) 657-2817 .

Regulatory Commitments Due Date / Event AmerGen Energy Company, LLC is making a regulatory Implemented by TS Amendment commitment to provide to the NRC using an industry implementation date.

database 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 regulatory commitment will be based on 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)) .

ATTACHMENT 4-H REGULATORY COMMITMENTS FOR PEACH BOTTOM ATOMIC POWER STATION The following table identifies those actions committed to by Exelon Generation Company, LLC (EGC) in this document. Any other statements in this submittal are provided for information purposes and are not considered to be regulatory commitments . Please direct questions regarding these commitments to Alison Mackellar at (630) 657-2817 .

Regulatory Commitments Due Date / Event Exelon Generation Company, LLC (EGC) is making a Implemented by TS Amendment regulatory commitment to provide to the NRC using an implementation date.

industry database 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 regulatory commitment will be based on 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)).

EGC is making a regulatory commitment to provide Implemented by TS Amendment information to the NRC annually (e.g ., with the annual implementation date.

submittal in accordance with 10 CFR 20.2206) to support the apportionment of station radiation doses to differentiate between operating and shutdown units. The data will provide the summary distribution of annual whole body doses as presented in Appendix B of NUREG-0713, "Occupational Radiation Dose at Commercial Nuclear Power Reactors and Other Facilities," for each operating and shutdown unit.

ATTACHMENT 4-1 REGULATORY COMMITMENTS FOR THREE MILE ISLAND, UNIT 1 The following table identifies those actions committed to by AmerGen Energy Company, LLC (AmerGen) in this document . Any other statements in this submittal are provided for information purposes and are not considered to be regulatory commitments. Please direct questions regarding these commitments to Alison Mackellar at (630) 657-2817 .

Regulatory Commitments Due Date / Event AmerGen Energy Company, LLC is making a regulatory Implemented by TS Amendment commitment to provide to the NRC using an industry implementation date .

database 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 regulatory of commitment will be based on use 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)).

ATTACHMENT 4-J REGULATORY COMMITMENTS FOR QUAD CITIES NUCLEAR POWER STATION The following table identifies those actions committed to by Exelon Generation Company, LLC (EGC) in this document. Any other statements in this submittal are provided for information purposes and are not considered to be regulatory commitments . Please direct questions regarding these commitments to Alison Mackellar at (630) 657-2817 .

Regulatory Commitments Due Date I Event Exelon Generation Company, LLC (EGC) is making a Implemented by TS Amendment regulatory commitment to provide to the NRC using an implementation date.

industry database 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 regulatory commitment will be based on 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)).

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