NL-11-110, Amendment Update to the Final Safety Analysis Report (Fsar), Revision 04

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Amendment Update to the Final Safety Analysis Report (Fsar), Revision 04
ML16106A095
Person / Time
Site: Indian Point Entergy icon.png
Issue date: 10/08/2011
From: Joseph E Pollock
Entergy Nuclear Operations
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-11-110
Download: ML16106A095 (6)


Text

Indian Point Energy Center 450 Broadway, GSB P.O. Box249

--- Entergx Buchanan, N.Y. 10511-0249 Tel (914) 734-6700 NL-11-110 October 8, 2011 Document Control Desk U.S. Nuclear Regulatory Commission Mail Stop O-P1-17 Washington, D.C. 20555-0001 J.E. Pollock Site Vice President Admininstration

Subject:

Indian Point 3 Nuclear Power Plant 2011 Amendment Update to the Fimd Safety Analysis Report (FSAR)! Revision 04 Indian Point Unit No. 3 Docket No. 50-286 License No. DPR-64

References:

1)
2)

Dear Sir or Madam:

NEI 98-03, "Guidelines for Updating Final Safety Analysis Reports", Revision 1, June 1999 NEI 99-04, "Guidelines for Managing NRC Commitments",

Revision 0, December 1995 Entergy Nuclear Operations, Inc. (Entergy), in accordance with 10 CFR 50.71(e) hereby transmits the most re~nt update to the Updated Final Safety Analysis Report (UFSAR) for Indian Point Unit 3 (IP3). This submittal incorporates applicable Changes made to the IP3 facility since the last UFSAR update on April 15, 2009, through the information available as of April 8, 2011, the com:pletion of the last refueling outage.

Entergy is submitting one copy of the entire IP3 UFSAR, Technical Specification Bases, and Technical Requirements Manual (TRM) in the electronic medium of Adobe PDF on CD-ROM in accordance with the guidance contained in NRC, "General (Non-Adjudicatory) Electronic Submission Instructional Guide, June 11, 2009, Revision 4.

UFSAR changes to the text and tables since the last revision are indicated by gray highlighted background rather than a revision bar next to the line containing the change.

This update to the FSAR also contains information that has been classified as "Historical" information according to the NEI 98-03 definition (Reference 1 ), and is no longer subject to updating. Material designated as "Historical" information in the UFSAR is indicated by a green highlighted background.

Any UFSAR figures that have been revised since the last revision contain "Rev. 04" in the figure title block.

A-05"°~

,JrtLR

Docket No. 50-286 NL-11-110 Page 2 of 3 Indian Point 3 Technical Specification 5.5.13, "Technical Specification Bases Control Program" requires that changes to the Bases implemented without prior NRC approval be provided to the NRC on a frequency consistent with 10 CFR 50.71 (e). The required information is listed in Attachment 1, Revisions to the IP3 Technical Specification Bases, and the entire document is provided on the enclosed CD-ROM. to this letter, Revisions to IP3 Docketed Commitments, submits a summary update of all changes made to the Unit 3 docketed commitments using the NEI 99-04 guidance, (Reference 2), for determination of commitments which do not have either a safety or regulatory significance, which may be changed Without prior interaction with the NRC staff and which require periodic NRG staff notification either annually or along with the FSAR updates as required by 10 CFR 50.71(e).

The Technical Requirements Manual (TRM) under NEI 98-03 (Reference 1) is controlled in a manner consistent with procedures fully or partially described in the UFSAR. Under this approach, the TRM document is subject to the change control requirements of 10CFR50.59 and the update/reporting requirements of 10CFR50.71 ( e). Attachment 3 of this letter, submits the summary list of changes to the Unit 3 TRM for the same time period as the Unit 3* FSAR update and the entire document is provided on the enclosed CD-ROM.

Entergy is making.no new commitments in this letter.

Should you or your staff have any questions regarding this submittai, please contact Mr.

Robert Walpole, Manager, Licensing, Indian Point Energy Center at (914) 734-6710.

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

Executed~\\,t.r-4/ J.\\-Q'-U<.\\(_ lfJ/1 l / \\\\

Date Sincerely, JEP/as Attachments: 1)

2)
3)

Revisions to the Indian Point 3 Technical Specification Bases Revisions to Indian Point 3 Docketed Commitments Revisions to the Indian Point 3 Technical Requirements Manual

cc (w/o enclosure or attachments):

Docket No. 50-286 NL-11-110 Page 3 of 3 Mr. John P. Boska, Senior ProjectManager, NRG NRR DORL Mr. William Dean, Regional Administrator, Region 1 Mr. Paul Eddy, New York State Dept. of Public Service Mr. Francis J. Murray, Jr., President & CEO, NYSERDA NRC Resident Inspector's Office

ATTACHMENT 2 TO NL-11-110 REVISIONS TO INDIAN POINT 3 DOCKETED COMMITMENTS ENTERGY NUCLEAR OPERATIONS, INC.

INDIAN POINT UNIT 3 DOCKET NO. 50-286 OPR-64

COMMITMENT CURRENT NUMBER STATUS P-7740 Open IPN-90-004 COM-90-03535 INDIAN POINT 3 2009/2011 NL-11-110 Page 1of5 COMMITMENT CHANGE

SUMMARY

REPORT CHANGED DESCRIPTION DATE 12/28/10 Original text:

THE AUTHORITY PROPOSES TO INSPECT THE SERVICE WATER INTAKE BAY DURING THE 1990 REFUELING OUTAGE AND EVERY REFUELING OUTAGE THEREAFTER. IF THE INSPECTION REVEALS EVIDENCE OF BIOFOULING WHICH COULD HINDER FLOW DURING THE SUBSEQUENT CYCLE, THE AREA WILL BE CLEANED AND ACCUMULATIONS DISCHARGED IN ACCORDANCE WITH NEW YORK STATE ENVIRONMENTAL REGULATIONS.

Revised text:

THE STATION USES THE PREVENTATIVE MAINTENANCE PROGRAM TO IMPLEMENT THE REQUIRED GL 89-13 INSPECTIONS OF THE UNIT 1, 2, AND 3 INTAKE BAYS AND STRUCTURES. THESE PMS CURRENTLY CONSIST OF THE FOLLOWING TASKS ON SET FREQUENCIES:

= SILT MONITORING AND MAPPING

=FULL DESILTING, AND TRASH/DEBRIS REMOVAL FROM THE SW BAYS

=TRASH RACK CLEANING VISUAL INSPECTIONS MAY BE INCLUDED AS PART OF THESE PM TASKS. VISUAL INSPECTIONS BY DIVERS, 1

A-4075 Open 03/15/11 RA-99-111-C01 NL-11-110 Page 2 of 5 HOWEVER, PRESENT PERSONAL SAFETY CONCERNS WHEN DIVERS ENTER THE SW PUMP BAYS WITH PUMPS RUNNING AND HAVE BEEN FOUND TO BE EXTREMELY LIMITED IN THEIR USEFULNESS IN DETERMINING OVERALL BAY CONDITIONS DUE TO WATER TURBIDITY & MURKINESS IN THE SW PUMP BAYS. BASED ON THE PM RESULTS, ENTERGY WILL TAKE THE REQUIRED MITIGATING ACTIONS WHEN UNACCEPTABLE BIOLOGICAL FOULING, SEDIMENTATION, AND/OR CORROSION CONDITIONS ARE IDENTIFIED.

Summary of justification:

Revise NRC Commitments A-2098 {IP2) &. P-7740 (IP3) to make clear that. "visu~I" inspections may be, but are not necessarily, performed. The original PM's to visually inspect the intake structures at IP2 and IP3 were deactivated due to safety concerns of having divers entering the SW pump bays with pumps running.

Additionally, based on completed dive,r inspections, water turbidity

& murkiness in the SW Pump Bays made diver visual inspections extremely limited in their usefulness in determining overall bay conditions.

The station uses the Preventative Maintenance Program to implement the required GL 89-13 inspe,ctions of the Unit 1, 2, and

  • 3 Intake Bays and Structures. These PMs currently consist of:
  • Silt monitoring and mapping
  • Full desilting, and trash/debris removal from the SW Bays
  • Trash rack cleaninQ Original text:

CONED WILL PERFORM EVALUATION OF VALVES AS REQUIRED BY GL 95-07, PRESSURE LOCKING AND 2

Indian Point Energy Center 450 Broadway, GSB P.O. Box249

--- Entergx Buchanan, N.Y. 10511-0249 Tel (914) 734-6700 NL-11-110 October 8, 2011 Document Control Desk U.S. Nuclear Regulatory Commission Mail Stop O-P1-17 Washington, D.C. 20555-0001 J.E. Pollock Site Vice President Admininstration

Subject:

Indian Point 3 Nuclear Power Plant 2011 Amendment Update to the Fimd Safety Analysis Report (FSAR)! Revision 04 Indian Point Unit No. 3 Docket No. 50-286 License No. DPR-64

References:

1)
2)

Dear Sir or Madam:

NEI 98-03, "Guidelines for Updating Final Safety Analysis Reports", Revision 1, June 1999 NEI 99-04, "Guidelines for Managing NRC Commitments",

Revision 0, December 1995 Entergy Nuclear Operations, Inc. (Entergy), in accordance with 10 CFR 50.71(e) hereby transmits the most re~nt update to the Updated Final Safety Analysis Report (UFSAR) for Indian Point Unit 3 (IP3). This submittal incorporates applicable Changes made to the IP3 facility since the last UFSAR update on April 15, 2009, through the information available as of April 8, 2011, the com:pletion of the last refueling outage.

Entergy is submitting one copy of the entire IP3 UFSAR, Technical Specification Bases, and Technical Requirements Manual (TRM) in the electronic medium of Adobe PDF on CD-ROM in accordance with the guidance contained in NRC, "General (Non-Adjudicatory) Electronic Submission Instructional Guide, June 11, 2009, Revision 4.

UFSAR changes to the text and tables since the last revision are indicated by gray highlighted background rather than a revision bar next to the line containing the change.

This update to the FSAR also contains information that has been classified as "Historical" information according to the NEI 98-03 definition (Reference 1 ), and is no longer subject to updating. Material designated as "Historical" information in the UFSAR is indicated by a green highlighted background.

Any UFSAR figures that have been revised since the last revision contain "Rev. 04" in the figure title block.

A-05"°~

,JrtLR

Docket No. 50-286 NL-11-110 Page 2 of 3 Indian Point 3 Technical Specification 5.5.13, "Technical Specification Bases Control Program" requires that changes to the Bases implemented without prior NRC approval be provided to the NRC on a frequency consistent with 10 CFR 50.71 (e). The required information is listed in Attachment 1, Revisions to the IP3 Technical Specification Bases, and the entire document is provided on the enclosed CD-ROM. to this letter, Revisions to IP3 Docketed Commitments, submits a summary update of all changes made to the Unit 3 docketed commitments using the NEI 99-04 guidance, (Reference 2), for determination of commitments which do not have either a safety or regulatory significance, which may be changed Without prior interaction with the NRC staff and which require periodic NRG staff notification either annually or along with the FSAR updates as required by 10 CFR 50.71(e).

The Technical Requirements Manual (TRM) under NEI 98-03 (Reference 1) is controlled in a manner consistent with procedures fully or partially described in the UFSAR. Under this approach, the TRM document is subject to the change control requirements of 10CFR50.59 and the update/reporting requirements of 10CFR50.71 ( e). Attachment 3 of this letter, submits the summary list of changes to the Unit 3 TRM for the same time period as the Unit 3* FSAR update and the entire document is provided on the enclosed CD-ROM.

Entergy is making.no new commitments in this letter.

Should you or your staff have any questions regarding this submittai, please contact Mr.

Robert Walpole, Manager, Licensing, Indian Point Energy Center at (914) 734-6710.

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

Executed~\\,t.r-4/ J.\\-Q'-U<.\\(_ lfJ/1 l / \\\\

Date Sincerely, JEP/as Attachments: 1)

2)
3)

Revisions to the Indian Point 3 Technical Specification Bases Revisions to Indian Point 3 Docketed Commitments Revisions to the Indian Point 3 Technical Requirements Manual

cc (w/o enclosure or attachments):

Docket No. 50-286 NL-11-110 Page 3 of 3 Mr. John P. Boska, Senior ProjectManager, NRG NRR DORL Mr. William Dean, Regional Administrator, Region 1 Mr. Paul Eddy, New York State Dept. of Public Service Mr. Francis J. Murray, Jr., President & CEO, NYSERDA NRC Resident Inspector's Office

ATTACHMENT 2 TO NL-11-110 REVISIONS TO INDIAN POINT 3 DOCKETED COMMITMENTS ENTERGY NUCLEAR OPERATIONS, INC.

INDIAN POINT UNIT 3 DOCKET NO. 50-286 OPR-64

COMMITMENT CURRENT NUMBER STATUS P-7740 Open IPN-90-004 COM-90-03535 INDIAN POINT 3 2009/2011 NL-11-110 Page 1of5 COMMITMENT CHANGE

SUMMARY

REPORT CHANGED DESCRIPTION DATE 12/28/10 Original text:

THE AUTHORITY PROPOSES TO INSPECT THE SERVICE WATER INTAKE BAY DURING THE 1990 REFUELING OUTAGE AND EVERY REFUELING OUTAGE THEREAFTER. IF THE INSPECTION REVEALS EVIDENCE OF BIOFOULING WHICH COULD HINDER FLOW DURING THE SUBSEQUENT CYCLE, THE AREA WILL BE CLEANED AND ACCUMULATIONS DISCHARGED IN ACCORDANCE WITH NEW YORK STATE ENVIRONMENTAL REGULATIONS.

Revised text:

THE STATION USES THE PREVENTATIVE MAINTENANCE PROGRAM TO IMPLEMENT THE REQUIRED GL 89-13 INSPECTIONS OF THE UNIT 1, 2, AND 3 INTAKE BAYS AND STRUCTURES. THESE PMS CURRENTLY CONSIST OF THE FOLLOWING TASKS ON SET FREQUENCIES:

= SILT MONITORING AND MAPPING

=FULL DESILTING, AND TRASH/DEBRIS REMOVAL FROM THE SW BAYS

=TRASH RACK CLEANING VISUAL INSPECTIONS MAY BE INCLUDED AS PART OF THESE PM TASKS. VISUAL INSPECTIONS BY DIVERS, 1

A-4075 Open 03/15/11 RA-99-111-C01 NL-11-110 Page 2 of 5 HOWEVER, PRESENT PERSONAL SAFETY CONCERNS WHEN DIVERS ENTER THE SW PUMP BAYS WITH PUMPS RUNNING AND HAVE BEEN FOUND TO BE EXTREMELY LIMITED IN THEIR USEFULNESS IN DETERMINING OVERALL BAY CONDITIONS DUE TO WATER TURBIDITY & MURKINESS IN THE SW PUMP BAYS. BASED ON THE PM RESULTS, ENTERGY WILL TAKE THE REQUIRED MITIGATING ACTIONS WHEN UNACCEPTABLE BIOLOGICAL FOULING, SEDIMENTATION, AND/OR CORROSION CONDITIONS ARE IDENTIFIED.

Summary of justification:

Revise NRC Commitments A-2098 {IP2) &. P-7740 (IP3) to make clear that. "visu~I" inspections may be, but are not necessarily, performed. The original PM's to visually inspect the intake structures at IP2 and IP3 were deactivated due to safety concerns of having divers entering the SW pump bays with pumps running.

Additionally, based on completed dive,r inspections, water turbidity

& murkiness in the SW Pump Bays made diver visual inspections extremely limited in their usefulness in determining overall bay conditions.

The station uses the Preventative Maintenance Program to implement the required GL 89-13 inspe,ctions of the Unit 1, 2, and

  • 3 Intake Bays and Structures. These PMs currently consist of:
  • Silt monitoring and mapping
  • Full desilting, and trash/debris removal from the SW Bays
  • Trash rack cleaninQ Original text:

CONED WILL PERFORM EVALUATION OF VALVES AS REQUIRED BY GL 95-07, PRESSURE LOCKING AND 2