ML101820028

License Amendment, Issuance of Amendments Regarding Changing the Channel Calibration Frequency for the Low-Temperature Overpressure Protection System

ML101820028
Person / Time
Site:	Oconee
Issue date:	07/21/2010
From:	Stang J Plant Licensing Branch II
To:	Baxter D Duke Energy Carolinas
Stang J, NRR/DORL, 415-1345
References
TAC ME2141, TAC ME2142, TAC ME2143
Download: ML101820028 (16)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 21, 2010 Mr. Dave Baxter Vice President, Oconee Site Duke Energy Carolinas, LLC 7800 Rochester Highway Seneca, SC 29672

SUBJECT:

OCONEE NUCLEAR STATION, UNITS 1,2, AND 3, ISSUANCE OF AMENDMENTS REGARDING CHANGING THE CHANNEL CALIBRATION FREQUENCY FOR THE LOW-TEMPERATURE OVERPRESSURE PROTECTION SYSTEM (TAC NOS. ME2141, ME2142, AND ME2143)

Dear Mr. Baxter:

The Nuclear Regulatory Commission has issued the enclosed Amendment Nos. 368, 370, and 369 to Renewed Facility Operating Licenses DPR-38, DPR-47, and DPR-55, for the Oconee Nuclear Station, Units 1, 2, and 3, respectively. The amendments consist of changes to the Technical Specifications (TSs) in response to your application dated August 6,2009, supplemented by letter dated February 23, 2010.

These amendments revise the TSs by changing the surveillance requirement frequency for TS 3.4.12, "Low-Temperature Overpressure Protection System," from 6 months to 18 months.

A copy of the related Safety Evaluation is also enclosed. A Notice of Issuance will be included in the Commission's biweekly Federal Register notice.

If you have any questions, please call me at 301-415-1345.

sincerelYi

~ng, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-269, 50-270, and 50-287

Enclosures:

1. Amendment No. 368 to DPR-38

2. Amendment No. 370 to DPR-47

3. Amendment No. 369 to DPR-55

4. Safety Evaluation cc w/encls: Distribution via Listserv

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 DUKE ENERGY CAROLINAS, LLC DOCKET NO. 50-269 OCONEE NUCLEAR STATION, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 368 Renewed License No. DPR-38

1. The Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment to the Oconee Nuclear Station, Unit 1 (the facility),

Renewed Facility Operating License No. DPR-38 filed by the Duke Energy Carolinas, LLC (the licensee), dated August 6,2009, and supplemented by letter dated February 23,2010, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

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2. Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment and Paragraph 3.B of Renewed Facility Operating License No. DPR-38 is hereby amended to read as follows:

B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 368 , are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3. This license amendment is effective as of its date of issuance and shall be implemented within 30 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Gloria Kulesa, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to Renewed Facility Operating License No. DPR-38 and the Technical Specifications Date of Issuance: Jul y 21, 2010

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 DUKE ENERGY CAROLINAS, LLC DOCKET NO. 50-270 OCONEE NUCLEAR STATION, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 370 Renewed License No. DPR-47

1. The Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment to the Oconee Nuclear Station, Unit 2 (the facility),

Renewed Facility Operating License No. DPR-47 filed by the Duke Energy Carolinas, LLC (the licensee), dated August 6,2009, and supplemented by letter dated February 23, 2010, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

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2. Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment and Paragraph 3.B of Renewed Facility Operating License No. DPR-47 is hereby amended to read as follows:

B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 370 , are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3. This license amendment is effective as of its date of issuance and shall be implemented within 30 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION G(~

Gloria Kulesa, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to Renewed Facility Operating License No. DPR-47 and the Technical Specifications Date of Issuance: July 21,2010

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 DUKE ENERGY CAROLINAS, LLC DOCKET NO. 50-287 OCONEE NUCLEAR STATION, UNIT 3 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 369 Renewed License No. DPR-55

1. The Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment to the Oconee Nuclear Station, Unit 3 (the facility),

Renewed Facility Operating License No. DPR-55 filed by the Duke Energy Carolinas, LLC (the licensee), dated August 6,2009, and supplemented by letter dated February 23, 2010, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

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2. Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment and Paragraph 3.B of Renewed Facility Operating License No. DPR-55 is hereby amended to read as follows:

B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 369 , are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3. This license amendment is effective as of its date of issuance and shall be implemented within 30 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

(~- (e...--.. . . - - -

Gloria Kulesa, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to Renewed Facility Operating License No. DPR-55 and the Technical Specifications Date of Issuance: Jul y 21, 2010

ATTACHMENT TO LICENSE AMENDMENT NO. 368 RENEWED FACILITY OPERATING LICENSE NO. DPR-38 DOCKET NO. 50-269 AND TO LICENSE AMENDMENT NO. 370 RENEWED FACILITY OPERATING LICENSE NO. DPR-47 DOCKET NO. 50-270 AND TO LICENSE AMENDMENT NO. 369 RENEWED FACILITY OPERATING LICENSE NO. DPR-55 DOCKET NO. 50-287 Replace the following pages of the Licenses and the Appendix A Technical Specifications (TSs) with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove Pages Insert Pages Licenses Licenses License No. DPR-38, page 3 License No. DPR-38, page 3 License No. DPR-47, page 3 License No. DPR-47, page 3 License No. DPR-55, page 3 License No. DPR-55, page 3 3.4.12-5 3.4.12-5

-3.

Part 70; is &ubject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subjeCt to the additlonar conditions specified or Incorporated below:

A. Maximum Power lever The licensee is authorized to operate the facility at steady state reactor core power levels not in excess of 2568 megawatts thermal. . .

B. Technical Seecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 368 are hereby Incorporated in the license. The licensee shall J

• operate the facility In tlccordance with the Technicar Specifications.

C. This license Is' subject to the following antitrust conditions:

Applicant makes the commitments contained herein, recognizing that bulk power supply arrangements between nelghbor1ng entities normally tend to serve the public interest. In addition, where there are net benefrts to all participants, such arrangements also serve the best Interests of each of the participants. Among the beneflts of such transactions are Increased electric system reliability, B reduction in the cost of electric power, and minimization of the enVironmental effects of the production and sale of electricity.

Any particular bulk power supply transaction may afford greater benefits to one participant than.to another. The benefIts* realized by a small system may be proportionately greater than those realized by a larger system. The relative benefits to be derived by the parties from a proposed transaction, however, should not be controlling upon a decision with respect to the desirability of participating in the transaction. Accordingly, applicant will enter into proposed bulk power transactions of th~ types hereinafter describedwhich, on balance, provide net benefits to applicant. There are nel benefits in a transaction if applicant recovers the cost of the transaction (as defined In ~1 (d) hereof) and there is no demonstrable net detriment to applicant arising from that transaction.

1. As used herein:

(a) "Bulk Power" means electrIc power and any attendant energy, supplied or made available at transmission or sub-transmission voltage by one electric system to another.

(b) "Neighboring Entity" means a private or public: corporation, a govemmental agency or authority, a municipality, a cooperative, or a lawfUl association of any of the foregoing owning or operating, or Renewed License No DPR*38 Amendment No. 368

-3 Part 70; Is sUbject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additiona', c;:(mditions specified or inc;orporated below:

A. Maximum Power Level The licensee is authorized to operate the facility at steady stale reactor core power levels not in excess of 2568 megawatts thermal.

B. Technical Specifications The Tp.r.hnical Specifications contained in Appen~ix A, as revised through Amendment No. 370 lire hereby incorporated in the license. The licensee shall operate the facility in accoruance with the Technical SpeCifications.

C. This license is subject to the following antitrust conditions:

Applicant makes the commitments contained herein:. recognizing that bulk power supply arrangements between neighboring enti1ies normally tend to serve the public interest. In addition, where there are net benefits to all participants, such arrangements also serve the best Interests of each of the partk:ipants. Among the benefits of soch transactions are increased electric system reliability, a reduction In the cost of electric power, and or minimization of the environmental effects of the production and sale electricity.

Any particular bulk power supply transaction may afford greater benefits to one participant than to another. The benefits realized by a small'system may be proportionately greater than those realized by a.larger system. The relative benefits to be derived by the parties from a p.roposed transaction, however, should not be controlling upon a decision with respect to the desirability of participating in the transaction. Accordingly, applicant will-enter Into proposed bulk power transactions of the types hereinafter described which, on balance, provide net benefits to applicant.

There are net benefits in a transaction If applicant recovers the cost of the transaction (as defined in ~1 (d) hereof) and Ihere is no demonstrable net detriment to applicant Bnsing from that transaction.

1. As used herein:

(a) ftBulk Power" means electric power and any attendant oner9Y, supplied or made available at transmission or sub-transmission voltage by one electric system to another.

(b) -Neighboring Entity" means a prIvate or publiC corporation, a governmental a

agency or authority, a municipality. a cooperative, or lawful aSsociation of 0'

any the foregoing owning or operating. or Renewed Licemie No. DPR-47 Amendment No. 370

• 3 Part 70; Is subject to all'applicable provisions of the Act antt to the rules, regulations, antt orders of. the Commission now or hereafter In effect; and is subject to the additional conditions speclfiett or incorporated below:

A. Maximum Power Level The licensee is authorized to operate the facility at steady state reactor core power levels nof in excess of 2568 megawatts thermal.

B. Technical" Specifications The Technical SpJ'pifications contained in Appendix A, as revised through Amendment No. j09 are hereby incorporated in the license. 'The licensee shall operate* the faCility in accordance with the Technical SpecIfications.

C. This license is subject to the following antitrust conditions:

Applicant makes the commitments contained herein, r'e~gnjzjng that bulk power

. supply arrangements between neighboring entities normally tend to serve the public interest. In addition. where there are net benefits to all participants. such arrangements also serve the best interests of each of the participants. Among the benefits of such transactions are increased electric system reliability, a reduction in the cost of electric power, and minimization of the environmental effects of the production and sale of electricity.

Any particular bulk power supply transaction may afford greater benefits to one participant than to another. The benefits realized by a small system may be proportlE>nately greater than those realized by a larger system. The relative benefits to be derived by the parties from a proposed transaction, however, should not be controlling upon a decision with respect to the desirability of participating in the transaction. Accordingly, applicant will enter Into proposed bulk power transactions of the types hereinafter described Which, on balance. provide net benefits to.

applicant. There are net benefits in a transaction If applicant recovers the cost of the transaction (as defined in ~1 (d) hereof) and there is no demonstrable net detriment to applicant arising from that transaction.

1. As used herein:

(a) "Bulk Power" means electric power and any attendant energy, supplied or made available at transmission or sub-transmission voltage by one electric system to *another.

(b) "Neighboring Entity" means a private or public corporation, a governmental agency or authority, a municipality, a cooperative, or a lawful association of any of the foregoing owning or operating, or Renewed License No. DPR-55 Amendment No. 369

LTOP System 3.4.12 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.4.12.6 Verify Administrative Controls, other than 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> limits for pressurizer level, that assure ~ 10 minutes are available for operator action to mitigate an LTOP event are implemented for the following:

a. RCS pressure when RCS temperature is < 325°F;

b. Makeup flow rate;

c. Alarms;

d. High pressure Nitrogen System; and

e. Verify pressurizer heater bank 3 or 4 is deactivated SR 3.4.12.7 Perform CHANNEL CALIBRATION for PORV. 18 months OCONEE UNITS 1, 2, & 3 3.4.12-5 Amendment Nos. 368 , 370, 369

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 368 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-38 AMENDMENT NO. 370 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-47 AND AMENDMENT NO. 369 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-55 DUKE ENERGY CAROLINAS. LLC OCONEE NUCLEAR STATION. UNITS 1, 2. AND 3 DOCKET NOS. 50-269, 50-270. AND 50-287

1.0 INTRODUCTION

By application dated August 6, 2009 (Agencywide Documents Access and Management System (ADAMS), Accession No. ML092250468), as supplemented by letter dated February 23, 2010 (ADAMS Accession No. ML100890374), Duke Energy Carolinas, LLC (Duke, the licensee),

submitted a license amendment request (LAR) to change the Technical Specifications (TSs) for the Oconee Nuclear Station, Units 1,2, and 3 (Oconee 1/2/3). The supplement dated February 23, 2010, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the staffs original proposed no significant hazards consideration determination as published in the Federal Register (FR) on March 9, 2010 (75 FR 10827).

The proposed changes would revise the TSs by changing the surveillance requirement (SR) frequency for TS 3.4.12. "Low Temperature Overpressure Protection (LTOP) System,"

specifically TS SR 3.4.12.7. TS SR 3.4.12.7 currently requires the performance of a channel calibration every 6 months. The proposed amendments request a change of the TS SR frequency from 6 months to 18 months.

2.0 REGULATORY EVALUATION

The LTOP system protects the reactor vessel from excessive pressure at low-temperature conditions and ensures that the integrity of the reactor coolant pressure boundary is not compromised by violating the pressure and temperature (PIT) requirements of Appendix G, "Fracture Toughness Requirements," to Title 10 of the Code of Federal Regulations (10 CFR),

Part 50.

-2 The TS requires the LTOP system to be operable with the high-pressure injection deactivated and the core flood tanks isolated and an operable pressurizer power-operated relief valve (PORV) with a lift setpoint based on the low-temperature overpressure limits. In addition, the TS requires operator action, assisted by administrative controls and alarms, to mitigate an LTOP event.

TS 3.4.12 requires reactor coolant system (RCS) overpressure protection in Mode 3 when any RCS cold leg temperature is less than 325 degrees Fahrenheit and in Modes 4, 5, and 6 when an RCS vent path capable of mitigating the most limiting LTOP event is not open. Therefore, the TS PIT limits provide the allowable combinations for operational PfT during cooldown, shutdown, and heatup to keep from violating the limits in Appendix G to 10 CFR Part 50.

The Commission's regulatory requirements related to the content of the TS appear in 10 CFR 50.36, Technical Specifications." This regulation requires that the TS include items in five specific categories. These categories include (1) safety limits, limiting safety system settings, and limiting control settings, (2) limiting conditions for operation, (3) surveillance requirements, (4) design features, and (5) administrative controls.

In particular, 10 CFR 50.36(c)(3), which sets forth the criteria for SRs in the TS, states, "Surveillance requirements are requirements relating to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions for operation will be met."

3.0 TECHNICAL EVALUATION

Currently, TS SR 3.4.12.7 requires the performance of a channel calibration for the PORV every 6 months. The current TS SR of a 6-month test frequency is necessary because of the type of existing instrumentation and the supporting calculation values. The licensee has recently upgraded this instrumentation to be more reliable and accurate and the LAR proposes to change the current TS freq uency from 6 months to 18 months.

In the February 23, 2010, supplement, the licensee states that the LTOP system upgrade will modify the existing Train "A" of the low range RCS pressure instrument loop, and will also add a new redundant Train "B" instrument loop. Modifications to Train "A" will include a replacement pressure transmitter, power supply, current alarm module, current transmitter module, and control board indicators. A safety-related Train "B" will be created using the same components.

The LAR states that the analysis for the new pressure transmitter shows minimal drift over a 30-month period. For the old LTOP pressure transmitter (Rosemount 1151 GP9E22B2), the specified drift was 0.25-percent upper range limit (URL) for 6 months, and the transmitter was qualified for normal operating conditions only. The upgraded LTOP pressure transmitter is a Rosemount 1154SH9RB, and the specified drift is 0.2-percent URL for 30 months. The pressure transmitter is calibrated at 0-600 pound-force per-square-inch gauge but is exposed to 2,150 pound-force per-square-inch gauge for extended periods of time up to 30 months. The LTOP pressure transmitters are located outside the secondary shield wall in the reactor building with mild environmental conditions. In addition, the licensee states that the upgraded LTOP pressure transmitter is environmentally qualified to both normal and accident conditions so that it can be used during normal conditions.

-3 In the February 23,2010, supplement, the licensee provided a calculation of total loop uncertainty for the new instrumentation and provided the vendor's information to support the specified drift statement. After reviewing the uncertainty calculation and the vendor's drift information, the Nuclear Regulatory Commission (NRC) staff found that the upgraded LTOP pressure transmitter has the specified drift of 0.2-percent URL for 30 months and that the values of total loop uncertainties for both the operator aid computer and the control room low-range RCS indicators are smaller than those of the previous channel indications under normal conditions. Therefore, the new values of total loop uncertainties with 30-month drift are more conservative than the old values with 6-month drift.

On the basis of the above review, the NRC staff concludes that the proposed change of the TS SR frequency from 6 months to 18 months is acceptable.

4.0 STATE CONSULTATION

In accordance with the Commission's regulations, the South Carolina State official was notified of the proposed issuance of the amendments. The State official had no comments.

5.0 ENVIRONMENTAL CONSIDERATION

The amendments change a requirement with respect to the installation or use of facility components located within the restricted area as defined in 10 CFR Part 20 and change surveillance requirements. The NRC staff has determined that the amendments involve no significant increase in the amounts and no significant change in the types of any effluents that may be released offsite and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration, and there has been no public comment on such finding published in the FR on March 9, 2010 (75 FR 10827). Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).

Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.

6.0 CONCLUSION

The Commission has concluded, based on the considerations discussed above, that: (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 Commission's regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.

Principal Contributor: P. Chung Date: July 21,2010

July 21, 2010 Mr. Dave Baxter Vice President, Oconee Site Duke Energy Carolinas, LLC 7800 Rochester Highway Seneca, SC 29672

SUBJECT:

OCONEE NUCLEAR STATION, UNITS 1,2, AND 3, ISSUANCE OF AMENDMENTS REGARDING CHANGING THE CHANNEL CALIBRATION FREQUENCY FOR THE LOW-TEMPERATURE OVERPRESSURE PROTECTION SYSTEM (TAC NOS. ME2141, ME2142, AND ME2143)

Dear Mr. Baxter:

The Nuclear Regulatory Commission has issued the enclosed Amendment Nos. 368, 370, and 369 to Renewed Facility Operating Licenses DPR-38, DPR-47, and DPR-55, for the Oconee Nuclear Station, Units 1, 2, and 3, respectively. The amendments consist of changes to the Technical Specifications (TSs) in response to your application dated August 6, 2009, supplemented by letter dated February 23, 2010.

These amendments revise the TSs by changing the surveillance requirement frequency for TS 3.4.12, Low-Temperature Overpressure Protection System," from 6 months to 18 months.

II A copy of the related Safety Evaluation is also enclosed. A Notice of Issuance will be included in the Commission's biweekly Federal Register notice.

If you have any questions, please call me at 301-415-1345.

Sincerely, IRA!

John Stang, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-269, 50-270, and 50-287

Enclosures:

1. Amendment No. 368 to DPR-38

2. Amendment No. 370 to DPR-47

3. Amendment No. 369 to DPR-55

4. Safety Evaluation cc w/encls: Distribution via Listserv DISTRIBUTION:

PUBLIC LPLlI-1 RtF RidsAcrsAcnw_MailCTR Resource RidsNrrDirsltsb Resource RidsNrrDorlDpr Resource RidsNrrDorlLp2-1 Resource RidsNrrEicb Resource RidsNrrLAMOBrien Resource (hard copy) RidsOgcRp Resource RidsRgn2MailCenter Resource RidsNrrPMOconee Resource (hard copy) PChung, Nrr ADAMSAccesslon No. ML101820028 *b memo d ae t d OFFICE NRRlLPL2-1/PM NRR/LPL2-1/LA DIRS/ITSB/BC NRR/EICB/BC OGC/NLO NRR/LPL2-1/BC NRRlLPL2-1/PM LSubin GKulesa NAME JStang MO'Brien RElliott WKemper* wi comment wi comments JStang DATE 07107/10 07107/10 07/16/10 04/29/10 07109/10 07/20/10 07/21/10 OFFICIAL RECORD COPY