ML021300342: Difference between revisions

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==Dear Mr. Anderson:==
==Dear Mr. Anderson:==
 
The Commission has issued the enclosed Amendment No. 245 to Facility Operating License No. NPF-6 for Arkansas Nuclear One, Unit No. 2 (ANO-2). This amendment consists of changes to the Technical Specifications (TSs) in response to your application dated May 2, 2001, as supplemented by {{letter dated|date=March 20, 2002|text=letter dated March 20, 2002}}.
The Commission has issued the enclosed Amendment No. 245 to Facility Operating License No. NPF-6 for Arkansas Nuclear One, Unit No. 2 (ANO-2). This amendment consists of changes to the Technical Specifications (TSs) in response to your application dated May 2, 2001, as supplemented by letter dated March 20, 2002.
The amendment relocates the requirements for the containment recirculation system from the TSs to the Technical Requirements Manual.
The amendment relocates the requirements for the containment recirculation system from the TSs to the Technical Requirements Manual.
A copy of our related Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commissions next biweekly Federal Register notice.
A copy of our related Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commissions next biweekly Federal Register notice.
Sincerely,
Sincerely,
                                                    /RA/
/RA/
Thomas W. Alexion, Project Manager, Section 1 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-368
Thomas W. Alexion, Project Manager, Section 1 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-368


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==Dear Mr. Anderson:==
==Dear Mr. Anderson:==
 
The Commission has issued the enclosed Amendment No 245 to Facility Operating License No. NPF-6 for Arkansas Nuclear One, Unit No. 2 (ANO-2). This amendment consists of changes to the Technical Specifications (TSs) in response to your application dated May 2, 2001, as supplemented by {{letter dated|date=March 20, 2002|text=letter dated March 20, 2002}}.
The Commission has issued the enclosed Amendment No 245 to Facility Operating License No. NPF-6 for Arkansas Nuclear One, Unit No. 2 (ANO-2). This amendment consists of changes to the Technical Specifications (TSs) in response to your application dated May 2, 2001, as supplemented by letter dated March 20, 2002.
The amendment relocates the requirements for the containment recirculation system from the TSs to the Technical Requirements Manual.
The amendment relocates the requirements for the containment recirculation system from the TSs to the Technical Requirements Manual.
A copy of our related Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commissions next biweekly Federal Register notice.
A copy of our related Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commissions next biweekly Federal Register notice.
Sincerely,
Sincerely,
                                                    /RA/
/RA/
Thomas W. Alexion, Project Manager, Section 1 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-368                     DISTRIBUTION PUBLIC                             RidsNrrPMTAlexion
Thomas W. Alexion, Project Manager, Section 1 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-368 DISTRIBUTION PUBLIC RidsNrrPMTAlexion


==Enclosures:==
==Enclosures:==
PDIV-1 RF                         RidsNrrLADJohnson
PDIV-1 RF RidsNrrLADJohnson
: 1. Amendment No. 245 to NPF-6         RidsNrrDripRtsb (WBeckner)         RidsRgn4MailCenter(KBrockman)
: 1. Amendment No. 245 to NPF-6 RidsNrrDripRtsb (WBeckner)
: 2. Safety Evaluation                   RidsNrrDlpm(JZwolinski/TMarsh) EBenner RidsNrrDlpmLpdiv(CHolden)         L.Hurley,RIV RidsOgcRp                         D.Bujol,RIV Rids AcrsAcnwMailCenter           G.Hill(2) cc w/encls: See next page             RidsNrrDlpmPdivLpdiv1(RGramm)
RidsRgn4MailCenter(KBrockman)
TS: ML021620013                 PKG: ML021750311 Accession No.: ML021300342           NRR-058           *SE input includes SPLB concurrence OFFICE     PDIV-1/PM     PDIV-1/LA         RORP/TSS/SC*       OGC             PDIV-1/SC NAME       TAlexion:sp   DJohnson         RDennig WDBfor     SBrock         MWebb RGramm DATE       5/17/02       5/15/02           03/27/02           5/22/02         5/31/02 OFFICIAL RECORD COPY
: 2. Safety Evaluation RidsNrrDlpm(JZwolinski/TMarsh)
EBenner RidsNrrDlpmLpdiv(CHolden)
L.Hurley,RIV RidsOgcRp D.Bujol,RIV Rids AcrsAcnwMailCenter G.Hill(2) cc w/encls: See next page RidsNrrDlpmPdivLpdiv1(RGramm)
TS: ML021620013 PKG: ML021750311 Accession No.: ML021300342 NRR-058
*SE input includes SPLB concurrence OFFICE PDIV-1/PM PDIV-1/LA RORP/TSS/SC*
OGC PDIV-1/SC NAME TAlexion:sp DJohnson RDennig WDBfor SBrock MWebb RGramm DATE 5/17/02 5/15/02 03/27/02 5/22/02 5/31/02 OFFICIAL RECORD COPY


ENTERGY OPERATIONS, INC.
ENTERGY OPERATIONS, INC.
DOCKET NO. 50-368 ARKANSAS NUCLEAR ONE, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 245 License No. NPF-6
DOCKET NO. 50-368 ARKANSAS NUCLEAR ONE, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 245 License No. NPF-6 1.
: 1. The Nuclear Regulatory Commission (the Commission) has found that:
The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Entergy Operations, Inc. (the licensee), dated May 2, 2001, as supplemented by letter dated March 20, 2002, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations 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 Commissions regulations; D. The issuance of this license 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 Commissions regulations and all applicable requirements have been satisfied.
A.
: 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-6 is hereby amended to read as follows:
The application for amendment by Entergy Operations, Inc. (the licensee), dated May 2, 2001, as supplemented by {{letter dated|date=March 20, 2002|text=letter dated March 20, 2002}}, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter I; B.
(2)     Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 245, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
: 3. The license amendment is effective as of its date of issuance and shall be implemented within 60 days from the date of issuance.
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 Commissions regulations; D.
The issuance of this license 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 Commissions regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-6 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 245, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
The license amendment is effective as of its date of issuance and shall be implemented within 60 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
FOR THE NUCLEAR REGULATORY COMMISSION
                                                      /RA by M Webb for/
/RA by M Webb for/
Robert A. Gramm, Chief, Section 1 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation
Robert A. Gramm, Chief, Section 1 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation


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ATTACHMENT TO LICENSE AMENDMENT NO. 245 FACILITY OPERATING LICENSE NO. NPF-6 DOCKET NO. 50-368 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
ATTACHMENT TO LICENSE AMENDMENT NO. 245 FACILITY OPERATING LICENSE NO. NPF-6 DOCKET NO. 50-368 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove                                   Insert VII                                     VII 3/4 6-20                                 ---
Remove Insert VII VII 3/4 6-20 B 3/4 6-3 B 3/4 6-3 B 3/4 6-5 B 3/4 6-5 B 3/4 6-6 B 3/4 6-6
B 3/4 6-3                               B 3/4 6-3 B 3/4 6-5                               B 3/4 6-5 B 3/4 6-6                               B 3/4 6-6


SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 245 TO FACILITY OPERATING LICENSE NO. NPF-6 ENTERGY OPERATIONS, INC.
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 245 TO FACILITY OPERATING LICENSE NO. NPF-6 ENTERGY OPERATIONS, INC.
ARKANSAS NUCLEAR ONE, UNIT NO. 2 DOCKET NO. 50-368
ARKANSAS NUCLEAR ONE, UNIT NO. 2 DOCKET NO. 50-368


==1.0     INTRODUCTION==
==1.0 INTRODUCTION==
 
By {{letter dated|date=May 2, 2001|text=letter dated May 2, 2001}}, as supplemented by {{letter dated|date=March 20, 2002|text=letter dated March 20, 2002}}, Entergy Operations, Inc. (the licensee), submitted a request for changes to the Arkansas Nuclear One, Unit No. 2 (ANO-2), Technical Specifications (TSs). The requested changes would relocate the requirements for the containment recirculation system from the TSs to the Technical Requirements Manual (TRM).
By letter dated May 2, 2001, as supplemented by letter dated March 20, 2002, Entergy Operations, Inc. (the licensee), submitted a request for changes to the Arkansas Nuclear One, Unit No. 2 (ANO-2), Technical Specifications (TSs). The requested changes would relocate the requirements for the containment recirculation system from the TSs to the Technical Requirements Manual (TRM).
The March 20, 2002, supplemental letter provided clarifying information that did not change the scope of the original Federal Register notice (66 FR 29352, May 30, 2001) or the original no significant hazards consideration determination.  
The March 20, 2002, supplemental letter provided clarifying information that did not change the scope of the original Federal Register notice (66 FR 29352, May 30, 2001) or the original no significant hazards consideration determination.
 
==2.0      BACKGROUND==


==2.0 BACKGROUND==
The Commissions regulatory requirements related to the content of TSs are set forth in 10 CFR 50.36. This regulation requires that the TSs include items in five specific categories. These categories include 1) safety limits, limiting safety system settings and limiting control settings;
The Commissions regulatory requirements related to the content of TSs are set forth in 10 CFR 50.36. This regulation requires that the TSs 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 (LCOs); 3) surveillance requirements; 4) design features; and 5) administrative controls. However, the regulation does not specify the particular TSs to be included in a plants license.
: 2) limiting conditions for operation (LCOs); 3) surveillance requirements; 4) design features; and 5) administrative controls. However, the regulation does not specify the particular TSs to be included in a plants license.
Additionally, 10 CFR 50.36(c)(2)(ii) sets forth four criteria to be used in determining whether a LCO is required to be included in the TSs. These criteria are as follows:
Additionally, 10 CFR 50.36(c)(2)(ii) sets forth four criteria to be used in determining whether a LCO is required to be included in the TSs. These criteria are as follows:
: 1. Installed instrumentation that is used to detect, and indicate in the control room, a significant abnormal degradation of the reactor coolant pressure boundary.
1.
: 2. A process variable, design feature, or operating restriction that is an initial condition of a design basis accident or transient analysis that either assumes the failure of or presents a challenge to the integrity of a fission product barrier.
Installed instrumentation that is used to detect, and indicate in the control room, a significant abnormal degradation of the reactor coolant pressure boundary.
: 3. A structure, system, or component that is part of the primary success path and which functions or actuates to mitigate a design basis accident or transient that
2.
 
A process variable, design feature, or operating restriction that is an initial condition of a design basis accident or transient analysis that either assumes the failure of or presents a challenge to the integrity of a fission product barrier.
either assumes the failure of or presents a challenge to the integrity of a fission product barrier.
3.
: 4.     A structure, system or component which operating experience or probabilistic risk assessment has shown to be significant to public health and safety.
A structure, system, or component that is part of the primary success path and which functions or actuates to mitigate a design basis accident or transient that either assumes the failure of or presents a challenge to the integrity of a fission product barrier.
4.
A structure, system or component which operating experience or probabilistic risk assessment has shown to be significant to public health and safety.
Existing LCOs and related surveillances included as TS requirements which satisfy any of the criteria stated above must be retained in the TSs. Those TS requirements which do not satisfy these criteria may be relocated to other, licensee-controlled documents.
Existing LCOs and related surveillances included as TS requirements which satisfy any of the criteria stated above must be retained in the TSs. Those TS requirements which do not satisfy these criteria may be relocated to other, licensee-controlled documents.
3.0     EVALUATION ANO-2 TS 3/4.6.4.3, containment recirculation system, is proposed to be relocated to the TRM.
3.0 EVALUATION ANO-2 TS 3/4.6.4.3, containment recirculation system, is proposed to be relocated to the TRM.
In the staffs safety evaluation for ANO-2 Amendment 3, dated October 4, 1987, the staff stated:
In the staffs safety evaluation for ANO-2 Amendment 3, dated October 4, 1987, the staff stated:
One of the provisions of Standard Review Plan 6.2.5 is that a system be provided to mix the combustible gases within the containment following a loss-of-coolant accident (LOCA). This may be accomplished through the use of a recirculation fan system, fan-cooler system, or containment spray system. We have found that each of these systems acting alone is an acceptable means for providing adequate recirculation of the containment atmosphere. In addition to any of the above systems, natural convection forces would also contribute to mixing the containment atmosphere.
One of the provisions of Standard Review Plan 6.2.5 is that a system be provided to mix the combustible gases within the containment following a loss-of-coolant accident (LOCA). This may be accomplished through the use of a recirculation fan system, fan-cooler system, or containment spray system. We have found that each of these systems acting alone is an acceptable means for providing adequate recirculation of the containment atmosphere. In addition to any of the above systems, natural convection forces would also contribute to mixing the containment atmosphere.
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The containment recirculation fans do not challenge the integrity of containment. If an increase in hydrogen concentration were to occur in containment post-LOCA, adequate mixing of the containment atmosphere is available through use of the safety-related containment cooling units and containment spray system. Therefore, this specification does not meet Criterion 2.
The containment recirculation fans do not challenge the integrity of containment. If an increase in hydrogen concentration were to occur in containment post-LOCA, adequate mixing of the containment atmosphere is available through use of the safety-related containment cooling units and containment spray system. Therefore, this specification does not meet Criterion 2.
Based on a review of the ANO-2 Safety Analysis Report (SAR) Chapter 15 events, the containment recirculation fans were not credited in any design basis accident or transient analysis. Therefore, this specification does not meet Criterion 3.
Based on a review of the ANO-2 Safety Analysis Report (SAR) Chapter 15 events, the containment recirculation fans were not credited in any design basis accident or transient analysis. Therefore, this specification does not meet Criterion 3.
The containment recirculation system is not credited in the ANO-2 probabilistic risk assessment for accomplishing the hydrogen mixing function. The containment cooling units and/or the containment spray pumps, which are credited, provide the mixing of the containment atmosphere. The containment recirculation system is judged to be non-risk significant as a means of providing containment atmosphere mixing. Therefore, this specification does not meet Criterion 4.
The containment recirculation system is not credited in the ANO-2 probabilistic risk assessment for accomplishing the hydrogen mixing function. The containment cooling units and/or the containment spray pumps, which are credited, provide the mixing of the containment atmosphere. The containment recirculation system is judged to be non-risk significant as a means of providing containment atmosphere mixing. Therefore, this specification does not meet Criterion 4.
The specifications proposed for relocation from the ANO-2 current TSs, discussed above, are not required to be in the TSs because they do not fall within the criteria for mandatory inclusion in the TSs as stated in 10 CFR 50.36(c)(2)(ii). These specifications are not needed to obviate the possibility that an abnormal situation or event will give rise to an immediate threat to the public health and safety. Therefore, they may be removed from the TSs.
The specifications proposed for relocation from the ANO-2 current TSs, discussed above, are not required to be in the TSs because they do not fall within the criteria for mandatory inclusion in the TSs as stated in 10 CFR 50.36(c)(2)(ii). These specifications are not needed to obviate the possibility that an abnormal situation or event will give rise to an immediate threat to the public health and safety. Therefore, they may be removed from the TSs.
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Also associated with the relocation of the containment recirculation system TSs discussed above, the licensee proposed to also revise the TS Bases for combustible gas control, the containment spray system, and the containment cooling system, to indicate that adequate mixing of the containment following a LOCA is provided by the containment spray system and containment cooling system. These changes are also appropriate.
Also associated with the relocation of the containment recirculation system TSs discussed above, the licensee proposed to also revise the TS Bases for combustible gas control, the containment spray system, and the containment cooling system, to indicate that adequate mixing of the containment following a LOCA is provided by the containment spray system and containment cooling system. These changes are also appropriate.


==4.0     STATE CONSULTATION==
==4.0 STATE CONSULTATION==
 
In accordance with the Commissions regulations, the Arkansas State official was notified of the proposed issuance of the amendment. The State official had no comments.
In accordance with the Commissions regulations, the Arkansas State official was notified of the proposed issuance of the amendment. The State official had no comments.


==5.0     ENVIRONMENTAL CONSIDERATION==
==5.0 ENVIRONMENTAL CONSIDERATION==
 
The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and changes surveillance requirements. The NRC staff has determined that the amendment involves 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 amendment involves no significant hazards consideration, and there has been no public comment on such finding (66 FR 29352, dated May 30, 2001). Accordingly, the amendment meets 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 amendment.
The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and changes surveillance requirements. The NRC staff has determined that the amendment involves 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 amendment involves no significant hazards consideration, and there has been no public comment on such finding (66 FR 29352, dated May 30, 2001). Accordingly, the amendment meets 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 amendment.
 
==6.0    CONCLUSION==


==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 Commissions 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.
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 Commissions 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.
Principal Contributor: E. Benner Date: May 31, 2002
Principal Contributor: E. Benner Date: May 31, 2002


Arkansas Nuclear One cc:
March 2001 Arkansas Nuclear One cc:
Executive Vice President           Vice President, Operations Support
Executive Vice President  
  & Chief Operating Officer         Entergy Operations, Inc.
  & Chief Operating Officer Entergy Operations, Inc.
Entergy Operations, Inc.          P. O. Box 31995 P. O. Box 31995                    Jackson, MS 39286-1995 Jackson, MS 39286-1995 Wise, Carter, Child & Caraway Director, Division of Radiation   P. O. Box 651 Control and Emergency Management Jackson, MS 39205 Arkansas Department of Health 4815 West Markham Street, Slot 30 Little Rock, AR 72205-3867 Winston & Strawn 1400 L Street, N.W.
P. O. Box 31995 Jackson, MS 39286-1995 Director, Division of Radiation Control and Emergency Management Arkansas Department of Health 4815 West Markham Street, Slot 30 Little Rock, AR 72205-3867 Winston & Strawn 1400 L Street, N.W.
Washington, DC 20005-3502 Mike Schoppman Framatome ANP, Richland, Inc.
Washington, DC 20005-3502 Mike Schoppman Framatome ANP, Richland, Inc.
Suite 705 1911 North Fort Myer Drive Rosslyn, VA 22209 Senior Resident Inspector U.S. Nuclear Regulatory Commission P. O. Box 310 London, AR 72847 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 County Judge of Pope County Pope County Courthouse Russellville, AR 72801 March 2001}}
Suite 705 1911 North Fort Myer Drive Rosslyn, VA 22209 Senior Resident Inspector U.S. Nuclear Regulatory Commission P. O. Box 310 London, AR 72847 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 County Judge of Pope County Pope County Courthouse Russellville, AR 72801 Vice President, Operations Support Entergy Operations, Inc.
P. O. Box 31995 Jackson, MS 39286-1995 Wise, Carter, Child & Caraway P. O. Box 651 Jackson, MS 39205}}

Latest revision as of 18:31, 16 January 2025

ANO2, License Amendment No. 245 Relocation of Containment Recirculation System
ML021300342
Person / Time
Site: Arkansas Nuclear Entergy icon.png
Issue date: 05/31/2002
From: Alexion T
NRC/NRR/DLPM
To: Anderson C
Entergy Operations
References
Download: ML021300342 (10)


Text

May 31, 2002 Mr. Craig G. Anderson Vice President, Operations ANO Entergy Operations, Inc.

1448 S. R. 333 Russellville, AR 72801

SUBJECT:

ARKANSAS NUCLEAR ONE, UNIT NO. 2 - ISSUANCE OF AMENDMENT RE: RELOCATION OF CONTAINMENT RECIRCULATION SYSTEM (TAC NO. MB1842)

Dear Mr. Anderson:

The Commission has issued the enclosed Amendment No. 245 to Facility Operating License No. NPF-6 for Arkansas Nuclear One, Unit No. 2 (ANO-2). This amendment consists of changes to the Technical Specifications (TSs) in response to your application dated May 2, 2001, as supplemented by letter dated March 20, 2002.

The amendment relocates the requirements for the containment recirculation system from the TSs to the Technical Requirements Manual.

A copy of our related Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commissions next biweekly Federal Register notice.

Sincerely,

/RA/

Thomas W. Alexion, Project Manager, Section 1 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-368

Enclosures:

1. Amendment No. 245 to NPF-6
2. Safety Evaluation cc w/encls: See next page

May 31, 2002 Mr. Craig G. Anderson Vice President, Operations ANO Entergy Operations, Inc.

1448 S. R. 333 Russellville, AR 72801

SUBJECT:

ARKANSAS NUCLEAR ONE, UNIT NO. 2 - ISSUANCE OF AMENDMENT RE: RELOCATION OF CONTAINMENT RECIRCULATION SYSTEM (TAC NO. MB1842)

Dear Mr. Anderson:

The Commission has issued the enclosed Amendment No 245 to Facility Operating License No. NPF-6 for Arkansas Nuclear One, Unit No. 2 (ANO-2). This amendment consists of changes to the Technical Specifications (TSs) in response to your application dated May 2, 2001, as supplemented by letter dated March 20, 2002.

The amendment relocates the requirements for the containment recirculation system from the TSs to the Technical Requirements Manual.

A copy of our related Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commissions next biweekly Federal Register notice.

Sincerely,

/RA/

Thomas W. Alexion, Project Manager, Section 1 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-368 DISTRIBUTION PUBLIC RidsNrrPMTAlexion

Enclosures:

PDIV-1 RF RidsNrrLADJohnson

1. Amendment No. 245 to NPF-6 RidsNrrDripRtsb (WBeckner)

RidsRgn4MailCenter(KBrockman)

2. Safety Evaluation RidsNrrDlpm(JZwolinski/TMarsh)

EBenner RidsNrrDlpmLpdiv(CHolden)

L.Hurley,RIV RidsOgcRp D.Bujol,RIV Rids AcrsAcnwMailCenter G.Hill(2) cc w/encls: See next page RidsNrrDlpmPdivLpdiv1(RGramm)

TS: ML021620013 PKG: ML021750311 Accession No.: ML021300342 NRR-058

  • SE input includes SPLB concurrence OFFICE PDIV-1/PM PDIV-1/LA RORP/TSS/SC*

OGC PDIV-1/SC NAME TAlexion:sp DJohnson RDennig WDBfor SBrock MWebb RGramm DATE 5/17/02 5/15/02 03/27/02 5/22/02 5/31/02 OFFICIAL RECORD COPY

ENTERGY OPERATIONS, INC.

DOCKET NO. 50-368 ARKANSAS NUCLEAR ONE, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 245 License No. NPF-6 1.

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

A.

The application for amendment by Entergy Operations, Inc. (the licensee), dated May 2, 2001, as supplemented by letter dated March 20, 2002, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations 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 Commissions regulations; D.

The issuance of this license 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 Commissions regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-6 is hereby amended to read as follows:

(2)

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 245, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

The license amendment is effective as of its date of issuance and shall be implemented within 60 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

/RA by M Webb for/

Robert A. Gramm, Chief, Section 1 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: May 31, 2002

ATTACHMENT TO LICENSE AMENDMENT NO. 245 FACILITY OPERATING LICENSE NO. NPF-6 DOCKET NO. 50-368 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove Insert VII VII 3/4 6-20 B 3/4 6-3 B 3/4 6-3 B 3/4 6-5 B 3/4 6-5 B 3/4 6-6 B 3/4 6-6

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 245 TO FACILITY OPERATING LICENSE NO. NPF-6 ENTERGY OPERATIONS, INC.

ARKANSAS NUCLEAR ONE, UNIT NO. 2 DOCKET NO. 50-368

1.0 INTRODUCTION

By letter dated May 2, 2001, as supplemented by letter dated March 20, 2002, Entergy Operations, Inc. (the licensee), submitted a request for changes to the Arkansas Nuclear One, Unit No. 2 (ANO-2), Technical Specifications (TSs). The requested changes would relocate the requirements for the containment recirculation system from the TSs to the Technical Requirements Manual (TRM).

The March 20, 2002, supplemental letter provided clarifying information that did not change the scope of the original Federal Register notice (66 FR 29352, May 30, 2001) or the original no significant hazards consideration determination.

2.0 BACKGROUND

The Commissions regulatory requirements related to the content of TSs are set forth in 10 CFR 50.36. This regulation requires that the TSs 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 (LCOs); 3) surveillance requirements; 4) design features; and 5) administrative controls. However, the regulation does not specify the particular TSs to be included in a plants license.

Additionally, 10 CFR 50.36(c)(2)(ii) sets forth four criteria to be used in determining whether a LCO is required to be included in the TSs. These criteria are as follows:

1.

Installed instrumentation that is used to detect, and indicate in the control room, a significant abnormal degradation of the reactor coolant pressure boundary.

2.

A process variable, design feature, or operating restriction that is an initial condition of a design basis accident or transient analysis that either assumes the failure of or presents a challenge to the integrity of a fission product barrier.

3.

A structure, system, or component that is part of the primary success path and which functions or actuates to mitigate a design basis accident or transient that either assumes the failure of or presents a challenge to the integrity of a fission product barrier.

4.

A structure, system or component which operating experience or probabilistic risk assessment has shown to be significant to public health and safety.

Existing LCOs and related surveillances included as TS requirements which satisfy any of the criteria stated above must be retained in the TSs. Those TS requirements which do not satisfy these criteria may be relocated to other, licensee-controlled documents.

3.0 EVALUATION ANO-2 TS 3/4.6.4.3, containment recirculation system, is proposed to be relocated to the TRM.

In the staffs safety evaluation for ANO-2 Amendment 3, dated October 4, 1987, the staff stated:

One of the provisions of Standard Review Plan 6.2.5 is that a system be provided to mix the combustible gases within the containment following a loss-of-coolant accident (LOCA). This may be accomplished through the use of a recirculation fan system, fan-cooler system, or containment spray system. We have found that each of these systems acting alone is an acceptable means for providing adequate recirculation of the containment atmosphere. In addition to any of the above systems, natural convection forces would also contribute to mixing the containment atmosphere.

The containment cooling units (i.e., fan-coolers, covered by TS 3/4.6.2.3) and the containment spray system (covered by TS 3/4.6.2.1) are both safety-related systems, whereas the containment recirculation fans are not. As stated above, any one of these systems is adequate to mix the combustible gases in the containment atmosphere following a LOCA. The two safety systems are adequate to perform the atmosphere mixing function, and the containment recirculation fans are not needed.

LCOs and associated requirements that do not satisfy or fall within any of the four specified criteria presently contained in 10 CFR 50.36 may be relocated from existing TSs (an NRC-controlled document) to appropriate licensee-controlled documents. The staff has reviewed the containment recirculation system specification proposed for relocation from the ANO-2 current TSs against these criteria, as described below.

The containment recirculation fans are not used in the detection of a significant degradation of the reactor coolant pressure boundary. Therefore, this specification does not meet Criterion 1.

The containment recirculation fans do not challenge the integrity of containment. If an increase in hydrogen concentration were to occur in containment post-LOCA, adequate mixing of the containment atmosphere is available through use of the safety-related containment cooling units and containment spray system. Therefore, this specification does not meet Criterion 2.

Based on a review of the ANO-2 Safety Analysis Report (SAR) Chapter 15 events, the containment recirculation fans were not credited in any design basis accident or transient analysis. Therefore, this specification does not meet Criterion 3.

The containment recirculation system is not credited in the ANO-2 probabilistic risk assessment for accomplishing the hydrogen mixing function. The containment cooling units and/or the containment spray pumps, which are credited, provide the mixing of the containment atmosphere. The containment recirculation system is judged to be non-risk significant as a means of providing containment atmosphere mixing. Therefore, this specification does not meet Criterion 4.

The specifications proposed for relocation from the ANO-2 current TSs, discussed above, are not required to be in the TSs because they do not fall within the criteria for mandatory inclusion in the TSs as stated in 10 CFR 50.36(c)(2)(ii). These specifications are not needed to obviate the possibility that an abnormal situation or event will give rise to an immediate threat to the public health and safety. Therefore, they may be removed from the TSs.

The licensee indicated that the containment recirculation system specifications contained in TS 3/4.6.4.3, with their LCOs and surveillance requirements, will be relocated to the TRM following NRC approval of their amendment request. The licensee further indicated that no changes to these specifications, other than the relocation, are proposed in their request.

The ANO-2 SAR, Section 13.8.2, states that the TRM is administered as part of the SAR, changes to the TRM are subject to the criteria of 10 CFR 50.59, and administrative controls for processing TRM changes are included in the site procedures. Therefore, the staff finds that sufficient regulatory controls exist for the TRM.

Accordingly, the staff has concluded that the requirements associated with the containment recirculation system in TS 3/4.6.4.3 may be relocated outside the TSs because (1) the 10 CFR 50.36 TS inclusion criteria are not applicable, (2) these requirements will be appropriately relocated to the licensees TRM, and (3) sufficient regulatory controls exist for the TRM.

Associated with the above changes are an appropriate revision to TS index page VII. This page change is administrative and acceptable.

Also associated with the relocation of the containment recirculation system TSs discussed above, the licensee proposed to also revise the TS Bases for combustible gas control, the containment spray system, and the containment cooling system, to indicate that adequate mixing of the containment following a LOCA is provided by the containment spray system and containment cooling system. These changes are also appropriate.

4.0 STATE CONSULTATION

In accordance with the Commissions regulations, the Arkansas State official was notified of the proposed issuance of the amendment. The State official had no comments.

5.0 ENVIRONMENTAL CONSIDERATION

The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and changes surveillance requirements. The NRC staff has determined that the amendment involves 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 amendment involves no significant hazards consideration, and there has been no public comment on such finding (66 FR 29352, dated May 30, 2001). Accordingly, the amendment meets 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 amendment.

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 Commissions 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.

Principal Contributor: E. Benner Date: May 31, 2002

March 2001 Arkansas Nuclear One cc:

Executive Vice President

& Chief Operating Officer Entergy Operations, Inc.

P. O. Box 31995 Jackson, MS 39286-1995 Director, Division of Radiation Control and Emergency Management Arkansas Department of Health 4815 West Markham Street, Slot 30 Little Rock, AR 72205-3867 Winston & Strawn 1400 L Street, N.W.

Washington, DC 20005-3502 Mike Schoppman Framatome ANP, Richland, Inc.

Suite 705 1911 North Fort Myer Drive Rosslyn, VA 22209 Senior Resident Inspector U.S. Nuclear Regulatory Commission P. O. Box 310 London, AR 72847 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 County Judge of Pope County Pope County Courthouse Russellville, AR 72801 Vice President, Operations Support Entergy Operations, Inc.

P. O. Box 31995 Jackson, MS 39286-1995 Wise, Carter, Child & Caraway P. O. Box 651 Jackson, MS 39205