RS-08-012, Amergen Company, Request for Amendment to Administrative Controls Section of Technical Specifications

Amergen Company, Request for Amendment to Administrative Controls Section of Technical Specifications

ML080730054
Person / Time
Site:	Dresden, Peach Bottom, Oyster Creek, Byron, Three Mile Island, Braidwood, Limerick, Clinton, Quad Cities, LaSalle
Issue date:	02/28/2008
From:	Benyak D AmerGen Energy Co, Exelon Nuclear
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
RS-08-012, TSTF-306-A, Rev 1
Download: ML080730054 (48)

Text

erG _ Exelono, An Exelon Company ArnerGen Fnergy Company, LLC www.exeloncorp.com Nuclear 4300 Winfield Road Exelon Generation Warrer~ville, I(_ 60555 4300 Winfield Road Warrenville, IL 60555 10 CFR 50.90 RS-08-012 February 28, 2008 U . S. Nuclear Regulatory Commission ATTN : Document Control Desk Washington, D. C . 20555 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, Unit 1 Facility Operating License No. NPF-62 NRC Docket No. 50-461 Dresden Nuclear Power Station, Units 1, 2 and 3 Facility Operating License No. DPR-2 and Renewed Facility Operating License Nos . DPR-19 and DPR-25 NRC Docket Nos.50-010 50-237, and 50-249 LaSalle County Station, Units 1 and 2 Facility Operating License Nos . NPF-11 and NPF-18 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 Nuclear Generating Station Facility Operating License No . DPR-16 NRC Docket No. 50-219 Peach Bottom Atomic Power Station, Units 2 and 3 Renewed Facility Operating License Nos. DPR-44 and DPR-56 NRC Docket Nos . 50-277 and 50-278

February 28, 2008 U . S. Nuclear Regulatory Commission Page 2 Quad Cities Nuclear Power Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-29 and DPR-30 NRC Docket Nos. 50-254 and 50-265 Three Mile Island Nuclear Station, Unit 1 Facility Operating License No. DPR-50 NRC Docket No. 50-289

Subject:

Request For Amendment to Administrative Controls Section of Technical Specifications

Reference:

TSTF-308-A, Revision 1, "Determination of Cumulative and Projected Dose Contributions in RECP," dated July 6, 2000 Pursuant to 10 CFR 50 .90, Exelon Generation Company, LLC, (EGC) and AmerGen Energy Company, LLC (AmerGen) hereby request the following amendment to Appendix A, Technical Specifications (TS), to the Facility Operating Licenses listed above. Specifically, the proposed changes will enhance the Administrative Controls Section of TS to clarify the existing wording for the Radioactive Effluent Controls Program (RECP) in accordance with the referenced NRC-approved Technical Specification Task Force (TSTF) traveler TSTF-308-A, Revision 1 .

As part of that program, licensees are required to determine both cumulative and projected dose contributions from radioactive effluents. The proposed change will clarify the wording of the RECP Administrative TS to not require dose projections for a calendar quarter and a calendar year every 31 days .

Dresden Nuclear Power Station (DNPS), Unit 1, Limerick Generating Station (LGS), Units 1 and 2, Three Mile Island (TMI), Unit 1, and Oyster Creek Nuclear Generating Station (OCNGS) have not implemented the Improved Standard Technical Specifications (ITS) . While the referenced traveler is written in an ITS format, the proposed changes for DNPS Unit 1, LGS Units 1 and 2, TMI 1 and OCNGS are consistent with the intent of TSTF-308-A as discussed above .

The attached amendment request is subdivided as shown below:

Attachment 1 provides an evaluation of the proposed changes .

Attachments 2A - 2J include the marked-up TS pages with the proposed changes indicated .

EGC and AmerGen request approval of the proposed changes by February 27, 2009 in order to meet corporate business needs. Once approved, the amendment shall be implemented within 60 days .

The proposed changes have been reviewed by the Plant Operations Review Committees at each of the stations and approved by their respective Nuclear Safety Review Boards in accordance with the requirements of the EGC and AmerGen Quality Assurance Programs .

February 28, 2008 U . S. Nuclear Regulatory Commission Page 3 In accordance with 10 CFR 50.91, "Notice for public comment ; State consultation," EGC and AmerGen are notifying the States of Illinois, Iowa, New Jersey (Bureau of Nuclear Engineering), and the Commonwealth of Pennsylvania of this application for changes to the TS by transmitting a copy of this letter and its attachments to the designated State Official .

There are no regulatory commitments contained in this letter . Should you have any questions concerning this letter, please contact Mr. Mitchel Mathews at (630) 657-2819.

I declare under penalty of perjury that the foregoing is true and correct . Executed on the 28 th day of February 2008.

Respectfully, Darin M. Benyak '

Director - Licensing and Regulatory Affairs Exelon Generation Company, LLC AmerGen Energy Company, LLC

February 28, 2008 U . S . Nuclear Regulatory Commission Page 4  : Evaluation of the Proposed Changes A: Mark-up of Proposed Technical Specification Changes for Braidwood Station 13 : Mark-up of Proposed Technical Specification Changes for Byron Station C: Mark-up of Proposed Technical Specification Changes for Clinton Power Station D: Mark-up of Proposed Technical Specification Changes for Dresden Nuclear Power Station E: Mark-up of Proposed Technical Specification Changes for LaSalle County Station F: Mark-up of Proposed Technical Specification Changes for Limerick Generating Station G: Mark-up of Proposed Technical Specification Changes for Oyster Creek Nuclear Generating Station H : Mark-up of Proposed Technical Specification Changes for Peach Bottom Atomic Power Station 1 : Mark-up of Proposed Technical Specification Changes for Quad Cities Nuclear Power Station J : Mark-up of Proposed Technical Specification Changes for Three Mile Island Nuclear Station

cc: NRC Project Manager, NRR - Braidwood Station NRC Project Manager, NRR - Byron Station NRC Project Manager, NRR - Clinton Power Station NRC Project Manager, NRR - Dresden Nuclear Power Station NRC Project Manager, NRR - Limerick Generating Station NRC Project Manager, NRR - LaSalle County Station NRC Project Manager, NRR - Oyster Creek Generating Station NRC Project Manager, NRR - Peach Bottom Atomic Power Station NRC Project Manager, NRR - Quad Cities Nuclear Power Station NRC Project Manager, NRR - Three Mile Island Nuclear Station Unit 1 Illinois Emergency Management Agency - Division of Nuclear Safety Iowa Emergency Management Division Director, Bureau of Radiation Protection - Pennsylvania Department of Environmental Resources Director, Bureau of Nuclear Engineering, New Jersey Department of Environmental Protection Chairman, Board of County Commissioners of Dauphin County, PA Chairman, Board of Supervisors of Londonderry Township, PA Mayor of Lacey Township, Forked River, NJ R . I. McLean, State of Maryland R . R. Janati, Commonwealth of Pennsylvania

ATTACHMENT 1 EVALUATION OF PROPOSED CHANGES

Subject:

Request For Amendment to Administrative Controls Section of Technical Specifications 1 .0 DESCRIPTION 2 .0 PROPOSED CHANGE

3.0 BACKGROUND

4 .0 TECHNICAL ANALYSIS

5.0 REGULATORY ANALYSIS

5.1 No Significant Hazards Consideration 5.2 Applicable Regulatory Requirements/Criteria 6.0 ENVIRONMENTAL EVALUATION 7.0 PRECEDENTS

8.0 REFERENCES

ATTACHMENT 1 EVALUATION OF PROPOSED CHANGES 1 .0 DESCRIPTION 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) request an amendment to Appendix A, Technical Specifications (TS), for the following Operating Licenses .

EGC Braidwood Station, Units 1 and 2 Facility Operating License Nos. NPF-72 and NPF-77 Byron Station, Units 1 and 2 Facility Operating License Nos. NPF-37 and NPF-66 Facility Operating License No. DPR-2 Dresden Nuclear Power Station, Units 1, 2, and 3 and Renewed Facility Operating License Nos. DPR-19 and DPR-25 LaSalle County Station, Units 1 and 2 Facility Operating License Nos. NPF-11 and NPF-18 Limerick Generating Station, Units 1 and 2 Facility Operating License Nos. NPF-39 and NPF-85 Peach Bottom Atomic Power Station, Units 2 and 3 Renewed Facility Operating License Nos . DPR-44 and DPR-56 Quad Cities Nuclear Power Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-29 and DPR-30 AmerGen Clinton Power Station, Unit 1 Facility Operating License No. NPF-62 Oyster Creek Nuclear Generating Station Facility Operating License No. DPR-16 Three Mile Island Nuclear Station, Unit 1 Facility Operating License No. DPR-50 Specifically, the proposed changes will revise the Administrative Controls Section of TS to clarify the existing wording for the Radioactive Effluent Controls Program (RECP) in accordance with the NRC-approved Technical Specification Task Force (TSTF) Traveler TSTF-308-A, Revision 1, "Determination of Cumulative and Projected Dose Contributions in RECP," (Reference 1). The proposed change is consistent with Reference 1, with the only exception being the TS section affected by the change at the associated station. Dresden Nuclear Power Station (DNPS), Unit 1, Limerick Generating Station (LGS), Units 1 and 2, Three Mile Island, Unit 1 (TMI 1), and Oyster Creek Nuclear Generating Station (OCNGS) have not implemented Improved Technical Specifications (ITS). Therefore, the TS Sections for DNPS Unit 1, LGS, TMI 1, and OCNGS impacted by the proposed change do not correspond to the ITS sections . The change however, is consistent with the NRC-approved TSTF-308-A .

Page 2 of 10

ATTACHMENT 1 EVALUATION OF PROPOSED CHANGES

2.0 PROPOSED CHANGE

EGC and AmerGen propose to clarify the existing wording in the Radioactive Effluent Controls Program TS to reflect the intent of Generic Letter (GL) 89-01, "Implementation of Programmatic and Procedural Controls for Radiological Effluent Technical Specifications (RETS) in the Administrative Controls Section of the Technical Specifications and the relocation of Procedural Details of RETS to the Offsite Dose Calculation Manual or to the Process Control Program," concerning the determination requirements for cumulative and projected dose contributions. The methodology and parameters for the determination of cumulative and projected dose contributions are defined in the Offsite Dose Calculation Manual (ODCM). The proposed change clarifies the wording in the RECP to not require dose projections for a calendar quarter and a calendar year every 31 days . This is specifically accomplished by replacing the existing wording with the following statement to the appropriate section of the administrative controls section of TS.

"Determination of cumulative dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days. Determination of projected dose contributions from radioactive effluents in accordance with the methodology in the ODCM at least every 31 days ."

The applicable TS sections impacted by the proposed change for each facility are listed below.

Braidwood Station, Units 1 and 2 TS 5.5 .4 "Radioactive Effluent Controls Program," paragraph e Byron Station, Units 1 and 2 TS 5 .5 .4 "Radioactive Effluent Controls Program," paragraph e Clinton Power Station, Unit 1 TS 5.5.4 "Radioactive Effluent Controls Program," paragraph e Dresden Nuclear Power Station, Unit 1 TS 6.8 .D.4 "Radioactive Effluent Controls Program," paragraph e Page 3 of 10

ATTACHMENT 1 EVALUATION OF PROPOSED CHANGES Dresden Nuclear Power Station, Unit 2 and Unit 3 TS 5.5.4 "Radioactive Effluent Controls Program," paragraph e LaSalle County Station, Units 1 and 2 TS 5.5.4 "Radioactive Effluent Controls Program," paragraph e Limerick Generating Station, Units 1 and 2 TS 6 .8 .4.d "Radioactive Effluent Controls Program," paragraph 5 Oyster Creek Nuclear Generating Station TS 6.8.4.a "Radioactive Effluent Controls Program," paragraph 5 Peach Bottom Atomic Power Station, Units 2 and 3 TS 5.5.4 "Radioactive Effluent Controls Program," paragraph e Quad Cities Nuclear Power Station, units 1 and 2 TS 5 .5 .4 "Radioactive Effluent Controls Program," paragraph e Three Mile Island Nuclear Station, Unit 1 TS 6.8.4.b "Radioactive Effluent Controls Program," paragraph 5 The revised TS with changes indicated are presented in Attachments 2A through 2J.

3.0 BACKGROUND

The NRC issued GL 89-01 to provide guidance in support of implementing programmatic controls in TS for radioactive effluents and for radiological environmental monitoring that conforms to the applicable regulatory requirements . This guidance was intended to allow the relocation of existing procedural details from the Radiological Effluent Technical Specifications (RETS) to the Offsite Dose Calculation Manual (ODCM) .

As stated in TSTF-308-A, GL 89-01 combined two surveillance requirements into one program element. The wording in the GL 89-01 guidance combined the cumulative and projected dose determinations into a single requirement. In combining these requirements, the new program element can be interpreted to require determining projected dose contributions for the calendar quarter and current calendar year every 31 days . This was not consistent with the original surveillance . Therefore, TSTF-308-A was developed and subsequently approved by the NRC to not require dose projections for a calendar quarter and a calendar year every 31 days (i.e., to describe the actual intent of the dose projections) .

Page 4 of 10

ATTACHMENT 1 EVALUATION OF PROPOSED CHANGES

4.0 TECHNICAL ANALYSIS

As noted above, EGC and AmerGen stations are required under currently approved TS to determine both cumulative and projected offsite dose contributions from radioactive effluents every 31 days. These requirements were derived from previous TS and combined into one requirement and incorporated in the currently approved TS under the guidance of GL 89-01 . Implementation of the proposed change is administrative and does not modify the original requirement. The proposed change simply enhances the Administrative Controls Section of TS by clarifying the wording of this program element to be consistent with the original intent of the need for dose projections . The proposed change is consistent with the NRC-approved TSTF-308-A (Reference 1) and the justification provided is applicable to the EGC and AmerGen stations included in this amendment request.

5.0 REGULATORY ANALYSIS

5.1 No Significant Hazards Consideration 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) request an amendment to Appendix A, Technical Specifications (TS), for the following operating licenses .

EGC Braidwood Station, Units 1 and 2 Facility Operating License Nos. NPF-72 and NPF-77 Byron Station, Units 1 and 2 Facility Operating License Nos. NPF-37 and NPF-66 Dresden Nuclear Power Station, Units 1, 2, and 3 Facility Operating License No . DPR-2 and Renewed Facility Operating License Nos.

DPR-19 and DPR-25 LaSalle County Station, Units 1 and 2 Facility Operating License Nos. NPF-11 and NPF-18 Limerick Generating Station, Units 1 and 2 Facility Operating License Nos . NPF-39 and NPF-85 Peach Bottom Atomic Power Station, Units 2 and 3 Renewed Facility Operating License Nos .

DPR-44 and DPR-56 Quad Cities Nuclear Power Station, Units 1 and 2 Renewed Facility Operating License Nos.

DPR-29 and DPR-30 AmerGen Clinton Power Station, Unit 1 Facility Operating License No . NPF-62 Oyster Creek Nuclear Generating Station Facility Operating License No. DPR-16 Three Mile Island Nuclear Station, Unit 1 Facility Operating License No . DPR-50 Page 5 of 10

ATTACHMENT 1 EVALUATION OF PROPOSED CHANGES Specifically, the proposed changes will revise the Administrative Controls Section of TS to clarify the existing wording for the Radioactive Effluent Controls Program (RECP) in accordance with the NRC-approved Technical Specification Task Force (TSTF) Traveler TSTF-308-A, "Determination of Cumulative and Projected Dose Contributions in RECP,"

Revision 1 . The proposed change is consistent with TSTF-308, with the only exception being the TS section affected by the change at the associated station. Dresden Nuclear Power Station (DNPS), Unit 1, Limerick Generating Station (LGS), Units 1 and 2, Three Mile Island, Unit 1 (TMI 1) and Oyster Creek Nuclear Generating Station (OCNGS) have not implemented Improved Technical Specifications (ITS). Therefore, the TS Sections for DNPS Unit 1, LGS, TMI 1, and OCNGS impacted by the proposed change do not correspond to the ITS sections . The change, however, is consistent with the NRC-approved TSTF-308-A .

According to 10 CFR 50.92, "Issuance of amendment," paragraph (c), a proposed amendment to an operating license involves no significant hazards consideration if operation of the facility in accordance with the proposed amendment would not:

Involve a significant increase in the probability or consequences of an accident previously evaluated ; or (2) Create the possibility of a new or different kind of accident from any accident previously evaluated ; or Involve a significant reduction in a margin of safety .

In support of this determination, EGC and AmerGen have evaluated whether or not a significant hazards consideration is involved with the proposed amendment by focusing on the three criteria set forth in 10 CFR 50.92 as discussed below.

1 . Does the change involve a significant increase in the probability or consequences of an accident previously evaluated?

Response : No The proposed change revises the applicable TS Section to conform to TSTF-308-A, Revision 1 .

The proposed change is administrative and simply provides enhanced clarity of current requirements . Therefore, this change does not affect any accident initiators, does not affect the ability to successfully respond to previously evaluated accidents, and does not affect radiological assumptions used in the evaluations . This change will not alter the operation of process variables, structures, systems, or components as described in the affected stations' Updated Final Safety Analysis Report (UFSAR). As such, the probability of occurrence for a previously evaluated accident is not increased .

The consequences of a previously analyzed event are dependent on the initial conditions assumed in the analysis, the availability and successful functioning of equipment assumed to operate in response to the analyzed event, and the Page 6 of 10

ATTACHMENT 1 EVALUATION OF PROPOSED CHANGES setpoints at which these actions are initiated . The consequences of a previously evaluated accident are not increased by the proposed change . The proposed change does not affect the performance of any equipment credited to mitigate the radiological consequences of an accident .

Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated .

2. Does the change create the possibility of a new or different kind of accident from any accident previously evaluated?

Response : No The proposed change does not involve a physical alteration of the plant (i.e., no new or different type of equipment will be installed) or changes in methods governing normal plant operation . No system or component setpoints will be changed, and the proposed change will not impose any new or eliminate any old requirements . There are no new accident initiators or equipment failure modes resulting from the proposed changes . The proposed changes are administrative in nature and support the implementation of common programs .

Thus, this proposed change does not create the possibility of a new or different kind of accident from any previously evaluated .

3. Does the change involve a significant reduction in a margin of safety?

Response : No The proposed change revises the applicable TS Section for the affected EGC and AmerGen stations to provide clarity concerning the determination requirements for cumulative and projected dose contributions.

The proposed change is administrative in nature and does not modify the safety limits or setpoints at which protective actions are initiated, and does not change the requirements governing operation or availability of safety equipment assumed to operate to preserve the margin of safety . In addition, there are no changes proposed to equipment operability requirements, setpoints, or limiting parameters specified in the stations' Technical Specifications.

Therefore, the proposed change does not involve a significant reduction in a margin of safety .

Based on the above, EGC and AmerGen conclude that the proposed amendment presents no significant hazards consideration under the standards set forth in 10 CFR 50 .92(c), and, accordingly, a finding of "no significant hazards consideration" is justified.

Page 7 of 10

ATTACHMENT 1 EVALUATION OF PROPOSED CHANGES 5 .2 Applicable Regulatory Requirements/Criteria According to 10 CFR 20.1302, "Compliance with dose limits for individual members of the public," paragraph (b), a licensee shall show compliance with the annual dose limit in 10 CFR 20 .1301, "Dose limits for individual members of the public," by demonstrating by measurement or calculation that the total effective dose equivalent to the individual likely to receive the highest dose from the licensed operation does not exceed the annual dose limit.

To comply with the above requirements, 10 CFR 50.36a, "Technical specifications on effluents from nuclear power reactors," states that in order to keep releases of radioactive materials to unrestricted areas during normal conditions, including expected occurrences, as low as reasonably achievable, each licensee of a nuclear power reactor will include technical specifications that, in addition to requiring compliance with applicable provisions of 10 CFR 20.1301, require each licensee to submit a report to the NRC that will allow an estimation of the maximum potential annual radiation doses to the public resulting from effluent releases .

The RECP, which was based on the guidance of GL 89-01, is a section in the Administrative Controls section of TS common to all EGC and AmerGen sites . This program conforms to 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to members of the public from radioactive effluents as low as reasonably achievable . The program is contained in the site's ODCM, is implemented by procedures, and includes remedial actions to be taken whenever the program limits are exceeded .

The proposed change is an administrative change that simply enhances the verbiage used to ensure compliance with the determination of offsite dose caused by the release of radioactive effluents from the above listed nuclear stations in the event that the Liquid and/or Gaseous Radwaste Treatment Systems are not being fully utilized . No processes or procedures will be altered due to this change.

In addition to the above, the proposed change does not affect the EGC and AmerGen compliance with General Design Criterion (GDC) 60, "Control of releases of radioactive materials to the environment," GDC 64, "Monitoring radioactivity releases," or 10 CFR 50, Appendix I, "Numerical Guides for Design Objectives and Limiting Conditions for Operation to Meet the Criterion 'As Low As Reasonably Achievable' for Radioactive Material in Light-Water-Cooled Nuclear Power Reactor Effluents."

In conclusion, based on the considerations discussed above, (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the NRC's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public .

Page 8 of 10

ATTACHMENT 1 EVALUATION OF PROPOSED CHANGES 6.0 ENVIRONMENTAL EVALUATION A review has determined that the proposed amendment would change a requirement with respect to installation or use of a facility component located within the restricted area, as defined in 10 CFR 20, "Standards for Protection Against Radiation," or would change an inspection or surveillance requirement. However, the proposed amendment does not involve : (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluent that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure .

Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51 .22(c)(9), "Criterion for categorical exclusion; identification of licensing and regulatory actions eligible for categorical exclusion or otherwise not requiring environmental review ." Therefore, pursuant to 10 CFR 51 .22(b),

no environmental impact statement or environmental assessment need be prepared in connection with the proposed amendment.

7.0 PRECEDENTS The NRC has previously approved similar amendments for the Calvert Cliffs Nuclear Power Plant (Reference 2), the Susquehanna Steam Electric Station (Reference 3), the Kewaunee Power Station (Reference 4), the Turkey Point Plant (Reference 5), the St.

Lucie Plant (Reference 6), the Pilgrim Nuclear Power Station (Reference 7), and the Indian Point Nuclear Generating Station (Reference 8) . The subject license amendment request proposes to adopt TSTF-308-A changes similar to those addressed in the previously approved amendments .

Page 9 of 10

ATTACHMENT EVALUATION OF PROPOSED CHANGES

8.0 REFERENCES

1 . TSTF-308-A, Revision 1, "Determination of Cumulative and Projected Dose Contributions in RECP," dated July 6, 2000

2. Letter from U . S . NRC to Mr. P . E. Katz (Calvert Cliffs Nuclear Power Plant, Inc.),

"Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2 - Amendment Re:

Revision to the Administrative Controls Section of the Technical Specifications (TAC Nos . MB5416 and MB5417)," dated July 16, 2003

3. Letter from U . S . NRC to Mr. B. L. Shriver (PPL Susquehanna, LLC),

"Susquehanna Steam Electric Station, Units 1 and 2 - Issuance of Amendment Re : Adoption of Generic Changes to Improved Technical Specifications (TAC Nos. MB3269 and MB3270)," dated February 25, 2003 4 . Letter from U . S. NRC to Mr. D . A. Christian (Nuclear Management Company, LLC), "Kewaunee Power Station - Issuance of Amendment Re : Technical Specification Changes for Radioactive Effluents Control Program and Off-Site Dose Calculation Manual (TAC No. MC5900)," dated October 4, 2005

5. Letter from U. S. NRC to Mr. J . A. Stall (Florida Power and Light Company),

"Turkey Point Units 3 and 4 - Issuance of Amendments Regarding Adoption of Technical Specification Task Force Travelers (TAC Nos . MC5840, MC5841 and MC6027 through MC6040)," dated May 26, 2006

6. Letter from U. S. NRC to Mr. J . A. Stall (Florida Power and Light Company), "St.

Lucie Units 1 and 2 - Issuance of Amendments Regarding Adoption of Selected Standard Technical Specifications Requirements (TAC Nos. MC6858, MC6859, MC6861 through MC6873)," dated June 19, 2006

7. Letter from U . S . NRC to Mr. M. Kansler (Entergy Nuclear Operations, Inc.),

"Pilgrim Nuclear Power Station - Issuance of Amendment Re: Administrative Changes and Relocation of Certain Technical Specification Responsibilities (TAC No. MC5419)," dated August 9, 2006

8. Letter from U . S . NRC to Mr. M. R . Kansler (Entergy Nuclear Operations, Inc.),

"Indian Point Nuclear Generating Unit Nos. 2 and 3 - Issuance of Amendments Re: Technical Specification Changes - Adoption of TSTF-258, TSTF-308, and Related Administrative Control Changes Based on NUREG-1431 (TAC Nos .

MC9475 and MC9476)," dated December 13, 2006 Page 10 of 10

ATTACHMENT 2A BRAIDWOOD STATION UNITS 1 and 2 Facility Operating License Nos. NPF-72 and NPF-77 Markup of Proposed Technical Specifications Page Changes REVISED TS PAGES 5 .5-3

ATTACHMENT ZA Insert A Determination of cumulative dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days. Determination of projected dose contributions from radioactive effluents in accordance with the methodology in the ODCM at least every 31. days.

Programs and Manuals 5 .5 5 .5 Programs and Manuals 5 .5 .4 Radioactiv e Effluent Controls Proqram This program conforms to 10 CFR 50 .36a for the control of radioactive effluents and for maintaining the doses to members of the public from radioactive effluents as low as reasonably achievable . The program shall be contained in the ODCM, shall be implemented by procedures, and shall include remedial actions to be taken whenever the program limits are exceeded . The program shall include the following elements :

a. Limitations on the functional capability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM ;

b. Limitations on the concentrations of radioactive material released in liquid effluents to unrestricted areas, conforming to 10 times the concentrations stated in 10 CFR 20, Appendix B, Table 2, Column 2 (to paragraphs 20 .1001 - 20 .2402) ;

c. Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20 .1302 and with the methodology and parameters in the ODCM ;

d. Limitations on the annual and quarterly doses or dose commitment to a member of the public from radioactive materials in liquid effluents released from each unit to unrestricted areas, conforming to 10 CFR 50, Appendix I ;

d o ~- con nt alend Insert A h the

y. ~ I d BRAIDWOOD - UNITS 1 & 2 5 .5 - 3 Amendmen

ATTACHMENT 2B BYRON STATION UNITS 1 and 2 Facility Operating License Nos. NPF-37 and NPF-66 Markup of Proposed Technical Specifications Page Changes REVISED TS PAGES 5.5-3

ATTACHMENT 2B Insert A Determination of cumulative dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days. Determination of projected dose contributions from radioactive effluents in accordance with the methodology in the ODCIVI at least every 31 days .

Programs and Manuals 5 .5 5 .5 Programs and Manuals 5 .5 .4 Radioactive Effluent Controls Progr am This program conforms to 10 CFR 50 .36a for the control of radioactive effluents and for maintaining the doses to members of the public from radioactive effluents as low as reasonably achievable . The program shall be contained in the ODCM, shall be implemented by procedures, and shall include remedial actions to be taken whenever the program limits are exceeded . The program shall include the following elements :

a. Limitations on the functional capability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM ;

b. Limitations on the concentrations of radioactive material released in liquid effluents to unrestricted areas, conforming to 10 times the concentrations stated in 10 CFR 20, Appendix B, Table 2, Column 2 (to paragraphs 20 .1001 - 20 .2402) ;

c. Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20 .1302 and with the methodology and parameters in the ODCM ;

d. Limitations on the annual and quarterly doses or dose commitment to a member of the public from radioactive materials in liquid effluents released from each unit to unrestricted areas, conforming to 10 CFR 50, Appendix I ;

e. ed 0 Insert A J

BYRON - UNITS 1 & 2 5 .5 - 3 Amendment

ATTACI IMENT 2C CLINTON POWER STATION UNIT 1 Facility Operating License No . NPF-62 Markup of Proposed Technical Specifications Page Changes REVISED TS PAGES

5. 0-10

ATTACHMENT 2C Insert A Determination of cumulative dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days. Determination of projected dose contributions from radioactive effluents in accordance with the methodology in the ODCM at least every 31 days.

Programs and Manuals 5 .5 5 .5 Programs and Manuals 5 .5 .4 Radioactive Effluen t Cont rols Program (continued)

e. r~xtt iriatio of cum'1 ative 'a proje~ ed - los cons radio tive e luents or the w~r rent alenda Insert A curr t cal ar year n acco ance w th the par meters ;'n the OAM at l~_, aspi

. st evek 31 davs ;

f. Limitations on the functional capability and use of the liquid and gaseous effluent treatment systems to ensure that appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a period of 31 days would exceed 2% of the guidelines for the annual dose or dose commitment, conforming to 10 CFR 50, Appendix I ;

g. Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the site boundary as follows :

1. For noble gases : <_ 500 mrem/yr to the total body and

<_ 3000 mrem/yr to the skin, and 2 . For iodine-131, iodine-133, tritium, and all radio-nuclides in particulate form with half-lives > 8 days :

<_ 1500 mrem/yr to any organ ;

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

i. Limitations on the annual and quarterly doses to a member of the public from iodine-131, iodine-133 ; tritium, and all radionuclides in particulate form with half lives > 8 days in gaseous effluents released from the unit to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I ; and j Limitations on the annual dose or dose commitment to any member of the public due to releases of radioactivity and to radiation from uranium fuel cycle sources, conforming to 40 CFR 190 .

(continued)

CLINTON 5 .0-10 Amendment No .

ATTACHMENT 2D DRESDEN NUCLEAR POWER STATION UNITS 1, 2, and 3 Facility Operating License No. DPR-2 and Renewed Facility Operating License Nos .

DPR-19 and DPR-25 Markup of Proposed Technical Specifications Page Changes UNIT 1 REVISED TS PAGES 6-6 UNITS 2 AND 3 REVISED TS PAGES 5 .5-3

ATTACHMENT 2D Insert A Determination of cumulative dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days. Determination of projected dose contributions from radioactive effluents in accordance with the methodology in the ODCM at least every 31 days.

Radioactive Effluent Control Program 6 .8 .D .4 ADMINISTRATIVECONTROLS

4. Radioactive Effluent Controls Program A program shall be provided conforming with 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to members of the public from radioactive effluents as low as reasonably achievable . The program (1) shall be contained in the ODCM, (2) shall be implemented by station procedures, and (3) shall include remedial actions to be taken whenever the program limits are exceeded . The program shall include the following elements:

a. Limitations on the operability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and set-point determination in accordance with the methodology in the ODCM,

b. Limitations on the instantaneous concentrations of radioactive material released ir. ;iq,;id effluents to unrestricted areas conforming to ten (10) times the concentration values in 10 CFR Part 20, Appendix B, Table 2, Column 2 to 10 CFR Part 20 .1001

-20 .2402,

c. Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20 .1302 and with the methodology and parameters in the ODCM,

d. Limitations on the annual and quarterly doses to a member of the public from radioactive materials in liquid effluents released from Insert A -,1` . each Unit conforming to Appendix I to 10 CFR Part 50, rojecte urrent with t ry 31

f. Limitations on the operability and use of the liquid and gaseous effluent treatment systems to ensure that the appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a 31-day period would exceed 2 per-cent of the guidelines for the annual dose conforming to Appendix I to 10 CFR Part 50, DRESDEN - UNIT 1 6-6 Amendment No

Programs and Manuals 5 .5 5 .5 Programs and Manuals 5 .5 .4 Radioactive Effluent _ Controls_ Program This program conforms to 10 CFR 50 .36a for the control of radioactive effluents and for maintaining the doses to members of the public from radioactive effluents as low as reasonably achievable . The program shall be contained in the ODCM, shall be implemented by procedures, and shall include remedial actions to be taken whenever the program limits are exceeded . The program shall include the following elements :

a. Limitations on the functional capability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM ;

b. Limitations on the concentrations of radioactive material released in liquid effluents to unrestricted areas, conforming to ten times the concentration values in Appendix B, Table 2, Column 2 to 10 CFR 20 .1001-20 .2402 ;

c. Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20 .1302 and with the methodology and parameters in the ODCM ;

d. Limitations on the annual and quarterly doses or dose commitment to a member of the public from radioactive materials in liquid effluents released from each unit to unrestricted areas, conforming to 10 CFR 50, Appendix I ;

e. e er natio cum ag ue a fro radio of vents a .d curr t ar year anq Ipa r~et~ n the Limitations on the functional capability and use of the liquid and gaseous effluent treatment systems to ensure that appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a period of 31 days would exceed 2% of the guidelines for the annual dose or dose commitment, conforming to 10 CFR 50, Appendix I ;

g. Limitations on the dose rate resulting from radioactive material released in gaseous effluents from the site to areas at or beyond the site boundary shall be in accordance with the following :

(continued)

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

ATTACHMENT 2E LASALLE COUNTY STATION UNITS 1 and 2 Facility Operating License Nos. NPF-11 and NPF-18 Markup of Proposed Technical Specifications Page Changes REVISED TS PAGES 5 .5-3

ATTACHMENT 2E Insert A Determination of cumulative dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCIVI at least every 31 days. Determination of projected dose contributions from radioactive effluents in accordance with the methodology in the ODCM at least every 31 days.

Programs and Manuals 5 .5 5 .5 Programs and Manuals 5 .5 .4 Radioact ive_ Effluent Controls Program This program conforms to 10 CFR 50 .36a for the control of radioactive effluents and for maintaining the doses to members of the public from radioactive effluents as low as reasonably achievable . The program shall be contained in the ODCM, shall be implemented by procedures, and shall include remedial actions to be taken whenever the program limits are exceeded . The program shall include the following elements :

a. Limitations on the functional capability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM ;

b. Limitations on the concentrations of radioactive material released in liquid effluents to unrestricted areas, conforming to ten times the concentration values in Appendix B, Table 2, Column 2 to 10 CFR 20 .1001-20 .2402 ;

c. Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20 .1302 and with the methodology and parameters in the ODCM ;

d. Limitations on the annual and quarterly doses or dose commitment to a member of the public from radioactive materials in liquid effluents released from each unit to unrestricted areas, conforming to 10 CFR 50, Appendix I ;

e. Deter 'nati`o'5/6 f 'c U fro . radio tive of Insert A a d curr ~i t cale a and par meters n t

f. Limitations on the functional capability and use of the liquid and gaseous effluent treatment systems to ensure that appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a period of 31 days would exceed 2% of the guidelines for the annual dose or dose commitment, conforming to 10 CFR 50, Appendix 1 ;

g Limitations on the dose rate resulting from radioactive material released in gaseous effluents from the site to (continued)

LaSalle 1 and 2 5 .5-3 Amendment No .

ATTACHMENT 2F LIMERICK GENERATING STATION UNITS 1 and 2 Facility Operating License Nos. NPF-39 and NPF-85 Markup of Proposed Technical Specifications Page Changes REVISED TS PAGES UNIT 1 6-14a UNIT 2 6-14a

ATTACHMENT 2F Insert A Determination of cumulative dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days. Determination of projected dose contributions from radioactive effluents in accordance with the methodology in the ODCM at least every 31 days.

ADMINISTRATIVE-CONTROLS PROCEDURES AND PROGRAMS (Continued)

d. Radioactive Effluent Controls Program A program shall be provided conforming with 10 CFR 50 .3ba for the control of radioactive effluents and for maintaining the doses to MEMBERS OF THE PUBLIC from radioactive effluents as low as reasonably achievable . The program (1) shall be contained in the ODCM, (2) shall be implemented by operating procedures, and (3) shall include remedial actions to be taken whenever the program limits are exceeded . The program shall include the following elements :

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

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

3) Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20 .1302 and with the methodology and parameters in the ODCM,

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

5) of ~umul~ ti v- and roj cted ose ont ibut ons \

ve ffl m nts or t e cu rent cale dar uart r an ar y~ar i a cc rdan e wi h th met odol~gy a d M.MOM t u.~CM lea Ft e ry da ,

6) Limitations on the operability and use of the liquid and gaseous effluent treatment systems to ensure that the appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a 31-day period would exceed 2 percent of the guidelines far the annual dose or dose commitment conforming to Appendix I to 10 CFR Part 50,

7) Limitations on the dose rate resulting from radioactive material released in gaseous effluents from the site to areas at or beyond the SITE BOUNDARY shall be limited to the following :

a . For noble gases : less than or equal to 500 mrem/yr to the total body and less than or equal to 3000 mremlyr to the skin, and b . For iodine-132, iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days : less than or equal to 1500 mrem/yr to any organ .

LIMERICK - UNIT 1 6-14a Amendment No .

PROCFD-URES AND PROGRAMS (Continued)

d. Radioactive Effluent Controls Program A program shall be provided conforming with 10 CFR 50 .36a for the control of radioactive effluents and for maintaining the doses to MEMBERS OF THE PUBLIC from radioactive effluents as low as reasonably achievable . The program (1) shall be contained in the ODCM, (2) shall be implemented by operating procedures, and (3) shall include remedial actions to be taken whenever the program limits are exceeded . The program shall include the following elements :

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

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

3) Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20 .1302 and with the methodology and parameters in the ODCM,

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

5) e roi 1- cted F o nt i but on s a

!F e cu rent calendar uart an wi ~h t h , met odology d ry 1 da_

6} Limitations an the operability and use of the liquid and gaseous effluent treatment systems to ensure that the appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a 31-day period would exceed 2 percent of the guidelines far the annual dose or dose commitment conforming to Appendix I to 10 CFR Part 50,

7) Limitations on the dose rate resulting from radioactive material released in gaseous effluents from the site to areas at or beyond the SITE BOUNDARY shall be limited to the following :

a. For noble gases : less than or equal to 500 mrem/yr to the total body and less than or equal to 3000 mrem/yr to the skin, and b . For iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days : less than or equal to 1500 mrem/yr to any organ .

LIMERICK - UNIT 2 6-14a Amendment No .

ATTACHMENT 2G OYSTER CREEK NUCLEAR GENERATING STATION Facility Operating License No. DPR-16 Markup of Proposed Technical Specifications Page Changes REVISED TS PAGES 6-11

ATTACHMENT 2G Insert A Determination of cumulative dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days . Determination of projected dose contributions from radioactive effluents in accordance with the methodology in the ODCM at least every 31 days.

6 .8 4 The following programs shall be established, implemented and maintained :

a. Radioactive Effluent Controls Program A program shall be provided conforming with 10 CFR 50.36a for the control of radioactive effluent and for maintaining the doses to MEMBERS OF THE PUBLIC from radioactive effluent as low as reasonably achievable . The program (1) shall be contained in the ODCM, (2) shall be implemented by operating procedures, and (3) shall include remedial actions to be taken whenever the program limits are exceeded . The program shall include the following elements :

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

2. Limitations on the concentrations of radioactive material released in liquid effluent to the UNRESTRICTED AREA conforming to less than the concentration values in Appendix B, Table 2, Column 2 to 10 CFR 20.1001-20 .2402 .

Monitoring, sampling, and analysis of radioactive liquid and gaseous effluent in accordance with 10 CFR 20.1302 and with the methodology and parameters in the ODCM.

4. Limitations on the annual and quarterly doses and dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluent released to the UNRESTRICTED AREA conforming to Appendix I of 10 CFR 50, Limitations on the operability and use of the liquid and gaseous effluent treatment systems to ensure that the appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in the 31 day period would exceed 2 percent of the guidelines for the annual dose or dose commitment conforming to Appendix 1 to 10 CFR 50,

7. Limitations on the dose rate resulting from radioactive materials released in gaseous effluents from the site to the UNRESTRICTED AREA shall be limited to the following :

rrrre n

a. For noble gases: Less than or equal to a dose rate of 5 'yr to the total body and less than or equal to a dose rate of 3 yr to the skin, and

b. For iodine-131, iodine -133, tritium, and or radionuclides in particulate form with half-lives greater then 8 days: Less then or equal tog dose rate of 1500

~~ to any organ.

Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents to the UNRESTRICTED AREA conforming to Appendix I of 10 CFR 50, OYSTER CREEK 6-11 Amendment No.

ATTACHMENT 2H PEACH BOTTOM ATOMIC POWER STATION UNITS 2 and 3 Renewed Facility Operating License Nos. DPR-44 and DPR-56 Markup of Proposed Technical Specifications Page Changes REVISED TS PAGES UNIT 2 5 .0-9 UNIT 3 5.0-9

ATTACHMENT 2H Insert A Determination of cumulative dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days . Determination of projected dose contributions from radioactive effluents in accordance with the methodology in the ODCM at least every 31 days .

Programs and Manuals 5 .5 5 .5 Programs and Manuals (continued) 5 .5 .4 Radioactive Effluent Controls Program This program conforms to 10 CFR 50 .36a for the control of radioactive effluents and for maintaining the doses to members of the public from radioactive effluents as low as reasonably achievable . The program shall be contained in the ODCM, shall be implemented by procedures, and shall include remedial actions to be taken whenever the program limits are exceeded . The program shall include the following elements :

a. Limitations on the functional capability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance' with the methodology in the ODCM ;

b. Limitations on the concentrations of radioactive material released in liquid effluents to unrestricted areas, conforming to 10 times the concentration values in Appendix B, Table 2, Column 2 to 10 CFR 20 .1001-20 .2402 ;

c. Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20 .1302 and with the methodology and parameters in the ODCM ;

d. Limitations on the annual and quarterly doses or dose commitment to a member of the public from radioactive materials in liquid effluents released from each unit to unrestricted areas, conforming to 10 CFR 50, Appendix I ;

-_ _Irrr-r

e. Deter- {nation 6f cumu tive anf projec ed dose contribution fro liquid adio ac ve effl .fents and/deter nation c Y6ulativ dose c tributi ns from~;aseous r adioac ,ve ffluen S for t curre calend guar r and c -rent calen r year in acco ance wi the thod olo,, and r eters X1"1 the O M at leapt ve 3,1 day,

f. Limitations on the functional capability and use of the liquid effluent treatment systems to ensure that appropriate portions of these systems are used to reduce releases of radioactivity when projected doses averaged over one month would exceed 0 .12 mrem to the total body or 0 .4 mrem to any organ (combined total from the two reactors at the site) ;

g. Limitations to ensure gaseous effluents shall be processed, prior to release, through the appropriate gaseous effluent treatment systems as described in the ODCM ;

(continued)

PBAPS UNIT 2 5 .0-9 Amendment No .

Programs and Manuals 5 .5 5 .5 Programs and Manuals (continued) 5 .5 .4 Radioactive Effluent Controls Program This program conforms to 10 CFR 50 .3fia for the control of radioactive effluents and for maintaining the doses to members of the public from radioactive effluents as low as reasonably achievable . The program shall be contained in the ODCM, shall be implemented by procedures, and shall include remedial actions to be taken whenever the program limits are exceeded . The program shall include the following elements :

a. Limitations on the functional capability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM ;

b. Limitations on the concentrations of radioactive material released in liquid effluents to unrestricted areas, conforming to 10 times the concentration values in Appendix B, Table 2, Column 2 to 10 CFR 20 .1001-20 .2402 ;

c. Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20 .1302 and with the methodology and parameters in the ODCM ;

d. Limitations on the annual and quarterly doses or dose commitment to a member of the public from radioactive materials in liquid effluents released from each unit to unrestricted areas, conforming to 10 CFR 50, Appendix I ;

¬ nsert A

e. D term in tion o' cumina~ ive an proje ted do e cont i butiohs r ~m i i qu d mad active ffluen s and etermi ation f cum lativ e dose c tribu ions f gase pus ra oacti effl ents f r the 5

calen ar yea , in ac rdanc with ~

rent cal end quar r and urren e met dolog and pArame er s in the 0 M at 1 ast ev ry . 31. y5 ;

f. Limitations on the functional capability and use of the liquid effluent treatment systems to ensure that appropriate portions of these systems are used to reduce releases of radioactivity when projected doses averaged over one month would exceed 0 .12 mrem to the total body or 0 .4 mrem to any organ (combined total from the two reactors at the site) ;

g. Limitations to ensure gaseous effluents shall be processed, prior to release, through the appropriate gaseous effluent treatment systems as described in the ODCM ;

(continued),

PBAPS UNIT 3 5 . 0-9 Amendment No

ATTACHMENT 21 QUAD CITIES NUCLEAR POWER STATION UNITS 1 and 2 Renewed Facility Operating License Nos . DPR-29 and DPR-30 Markup of Proposed Technical Specifications Page Changes REVISED TS PAGES 5.5-3

. ATTACHMENT 21 Insert A Determination of cumulative dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days. Determination of projected dose contributions from radioactive effluents in accordance with the methodology in the ODCM at least every 31 days .

Programs and Manuals 5 .5 5 .5 Programs and Manuals 5 .5 .4 Radioactive Effluent Controls Program This program conforms to 10 CFR 50 .36a for the control of radioactive effluents and for maintaining the doses to members of the public from radioactive effluents as low as reasonably achievable . The program shall be contained in the ODCM, shall be implemented by procedures, and shall include remedial actions to be taken whenever the program limits are exceeded . The program shall include the following elements :

a . Limitations on the functional capability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM ;

b. Limitations on the concentrations of radioactive material released in liquid effluents to unrestricted areas, conforming to ten times the concentration values in Appendix B, Table 2, Column 2 to 10 CFR 20 .1001-20 .2402 ;

c. Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20 .1302 and with the methodology and parameters in the ODCM ;

d. Limitations on the annual and quarterly doses or dose commitment to a member of the public from radioactive materials in liquid effluents released from each unit to unrestricted areas, conforming to 10 CFR 50, Appendix 1 ;

e. Det`e'r inat o 0 cu e~ e -Kvos p cod fro radio tive e wGrrent alenda Insert A aAd cu41 t cale nce ~" th the v FRE"'dI '

p, a ~~~ mete

, , e v P.rw 31 da

f. Limitations on the functional capability and use of the liquid and gaseous effluent treatment systems to ensure that appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a period of 31 days would exceed 2% of the guidelines for the annual dose or dose commitment, conforming to 10 CFR 50, Appendix I ;

9- Limitations on the dose rate resulting from radioactive material released in gaseous effluents from the site to areas at or beyond the site boundary shall be in accordance with the following :

(continued)

Quad Cities 1 and 2 5 .5-3 Amendment No .

ATTACHMENT 2J THREE MILE ISLAND UNIT 1 Facility Operating License No. DPR-50 Markup of Proposed Technical Specifications and Bases Page Changes REVISED TS PAGES 6-11 b

ATTACHMENT 2J Insert A Determination of cumulative dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days. Determination of projected dose contributions from radioactive effluents in accordance with the methodology in the ODCM at least every 31 days.

b. Radioactive Effluent Controls Program (continued)

(4) Limitations on the annual and quarterly doses or dose commitment to a'MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released from the unit to the site boundary conforming to Appendix I to 10 CFR-Part 50, Y~

erminati n tribution dar quay h the metho ry 31 days, (6) Limitations on the operability-and use of the liquid and gaseous effluent treatment systems to ensure that the appropriate portions of these systems are used to reduce' releases of radioactivity when the projected doses in a 31-day period would exceed 2 percent of the guidelines for the annual dose or dose commitment conforming to Appendii I to 10 CFR Part 50, (7) Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas at, or beyond, the site boundary . The limits are as follows :

(a) For noble gases : less than or equal to 500 mrem/yr to the total body and less than or equal to 3000 mrem/yr to the skin, and (b) ,-For I-131, I-133, tritium and all radionuclides in .

particulate form with half lives greater than 8 days :

less than or equal to 1500 mrem/yr to any organ .

(8) Limitations on the annual and quarterly air doses resulting from noble.gases -released in gaseous effluents from the unit to areas beyond the site boundary conforming to Appendix I to 10 CFR Part 50, (9) Limitations on the annual quarterly doses to a MEMBER OF THE PUBLIC from Iodine-131, Iodine-133, tritium, and . all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from -the unit to areas teyond the site boundary conforming to Appendix I. to 10 CFR Part 50, and (10) Limitations on the annual dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources conforming to 40 CFR Part 190 .

6-llb Amendment No.