ML12339A461
| ML12339A461 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 07/05/2011 |
| From: | Entergy Nuclear Operations |
| To: | Atomic Safety and Licensing Board Panel |
| SECY RAS | |
| References | |
| RAS 22150, 50-247-LR, 50-286-LR, ASLBP 07-858-03-LR-BD01 | |
| Download: ML12339A461 (6) | |
Text
United States Nuclear Regulatory Commission Official Hearing Exhibit In the Matter of:
Entergy Nuclear Operations, Inc.
(Indian Point Nuclear Generating Units 2 and 3)
ASLBP #: 07-858-03-LR-BD01 Docket #: 05000247 l 05000286 Exhibit #:
Identified:
Admitted:
Withdrawn:
Rejected:
Stricken:
Other:
ENT000384-00-BD01 10/15/2012 10/15/2012 Indian Point 2 ENT000384 Submitted: March 30, 2012 Revision 0 PROGRAM SECTION No. SEp*lP2* IST*2 Revision No. 0 Page I of 146 INDIAN POINT 2 FOURTH TEN* YEAR INTERVAL INSERVICE TESTING PROGRAM PLAN ENTERGY NUCLEAR ENGINEERING PROGRAMS APPLICABLE SITES All Sites: 0 Specific Sites: ANO 0 GGNS 0 IPEe ~ lAP 0 PLP 0 PNPS 0 RBS 0 Vy 0 w3D HQN 0 Safety Related:
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No Program Section Revision Summary Current Description of Change Revision 0
This Site Engineering Program (SEP) supercedes the previolls 1ST Program Plan, IP-RPT-07-000 I g
REVIEW AND CONCURRENCE SHEET Program Section No.: SEP-IP2-IST-2 Revision No.:
0 Program Section
Title:
Indian Point 2 Fourth Ten-Year Intervallnservice Testing Program Plan Prepared By: ____
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Indian Point 2 Revision 0 SECTION 1 Inservice Testing Program Introduction The Inservice Testing Program described herein has been developed as required by Section SO.SSa of 10 CFR Part SO to implement the requirements of AS.ME OM CODE-200 I (Revision of AS.ME OM Code-1998) through 2003 Addenda. The safe shutdown condition for IP2 is Hot Shutdown.
Applicability Consistent with Section SO.SSa of 10 CFR Part SO, this program is applicable to the inservice testing of in-scope AS.ME Code Class I, 2 and 3 components for the unit's fourth ten-year interval. An Inservice Testing Program for AS.ME Code Class I, 2 and 3 components is identified in IP2 Technical Specification S.5.6 and IP2 Technical Requirements Manual S.S.F. An inservice testing program for non-AS.ME Code Class I, 2 and 3 pumps and valves has been updated concurrently, is not a part of this required submittal, and is available for review at the plant site or upon request.
Applicable Codes In accordance with Section SO.S5a of 10 CFR Part 50, the applicable code is 1995 Edition through the 2003 Addenda. For IP2 this is specifically AS.ME OM CODE-2001 (Revision of ASME OM Code-1998) with the following Addenda: AS.ME OMa Code-2002 and AS.ME OMb Code-2003. This is referred to as the Code in the remaining text.
Program Description The list on the following page identifies the Indian Point Unit No.2 AS.ME Code Class I, 2 and 3 plant specific systems subject to the inservice testing requirements of the Code. The subject systems are derived from the latest IP2 Code Boundary drawings.
Sections 2 and 3 identify the AS.ME Code Class I, 2 and 3 pumps and valves to be tested in accordance with the Code. The pumps and valves are listed followed by both general and specific relief requests where it has been found that the testing requirements for that pump or valve are impractical, as applicable. In such instances, appropriate alternative testing provisions have been identified. General relief requests are used when the impracticality of a particular test requirement applies to more than one pump or more than one valve. Specific relief requests are unique to a particular pump or val ves.
The testing program outlined in Sections 2 and 3 has been developed following a design review. Should certain Code requirements prove to be impractical due to unforeseen circumstances, subsequent relief from that requirement will be requested.
Justifications Cold shutdown/refueling justifications are provided for those components where test frequency varies within Code allowances. NUREG-1482 "Guidelines for Inservice Testing at Nuclear Power Plants", was used in developing these justifications.
Relief Requests Relief requests are written in accordance with IOCFRSO.5Sa when specific requirements for inservice testing are considered impractical or pose an undue burden on the licensee. The enclosed relief requests, if any, are subject to change throughout the inspection interval. If requirements are determined to be impractical, or result in hardship or unusual difficulty without a compensating increase in the level of quality and safety, during the course of the interval, additional or moditied relief requests will be submitted in accordance with IOCFRSO.5Sa.
NUREG-1482 "Guidelines for Inservice Testing at Nuclear Power Plants", is used in developing justification for the basis of the relief requests.
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Indian Point 2 Revision 0 List of Systems Subject to Inservice Testing I. The following list relates specific plant systems and drawings to a list of typical systems and components for pressurized water reactors patterned after Table 2.1 ofNUREG-1482 "Guidelines for Inservice Testing at Nuclear Power Plants".
- 2.
Drawings are listed once and only against the most applicable system characteristic.
SYSTEM TYPICAL COMPONENTS IP2 DRAWINGS Reactor coolant Power-operated relief valves and associated block valves 9321-2738 system and Reactor high point and head vents 208168 flowpaths for Primary system safety and relief valves (pressurizer Code safety establishing valves) natural Pressure boundary isolation valves circulation Valves in lines to pressurizer relief/quench tank Main steam Main steam isolation valves (MSIV's) 9321-2017 system Main steam non-return valves (if applicable) 9321-2041 Secondary system safety and relief valves 9321-2729 Atmospheric dump valves Auxiliary feedwater turbine steam supply vlaves Steam generator blowdown isolation valves High pressure High-pressure injection pumps and discharge check valves 9321-F-2735 safety injection Injection valves in injection flow path 235296 and Isolation Valves containment Valves for the refueling water storage tank (RWST) spray systems Containment spray pumps and suction/discharge check valves Valves in flow path to spray header Chemical and Charging or makeup pumps and suction/discharge check valves 9321-2736 volume control Injection valves in charging/makeup flow path system Boric acid transfer pumps and suction/discharge check valves Valves in emergency boration flow paths Relief valves Low pressure Low pressure injection pumps and suction/discharge check valves 251783 safety injection Valves associated with safety injection accumulators system and Recirculation flow path valves, including containment sump shutdown isolation valves cooling/
Isolation valves (high-low pressure interface) res idual heat Relief valves removal system Main and Main feed water check valves 932 1-2019 auxiliary Auxiliary feed water pumps and suction/discharge check valves 9321-2018 feed water Valves in auxiliary path to steam generator system Valves in auxiliary suction lines Relief and isolation valves 1-2
Indian Point 2 Revision 0 SYSTEM TYPICAL COMPONENTS IP2 DRAWINGS Primary Containment isolation valves (various systems)
(Various) containment Sampling lines penetrating containment 9321-2745 system Containment isolation seal water system 9321-2746 Penetration protection relief valves (GL 96-06)
Component Component cooling water pumps and suction/discharge check 9321-F-2720 cooling water valves 227781 system Auxiliary component cooling water pumps and suction/discharge check valves Relief Valves Service water Service water pumps and discharge check valves 9321-F-2722 system Valves in flow path to containment cooling 209762 including Valves in flow path to emergency diesel cooling cooling to Valves in flow path to component cooling heat removal containment Isolation and cross-tie valves and emergency diesel generators 1-3
Indian Point 2 Revision 0 SECTION 2 Inservice Test Program - ASME Code Class I, 2 and 3 Pumps 1.0 ASME CODE CLASS I, 2 AND 3 PUMPS SUBJECT TO THE TESTING REQUIREMENTS OF SUBSECTON ISTB:
Safety Injection Pumps 21, 22, and 23 Containment Spray Pumps 21 and 22 Recirculation Pumps 21 and 22 Service Water Pumps 21, 22, 23, 24, 25 and 26 Residual Heat Removal Pumps 21 and 22 Component Cooling Pumps 21, 22, and 23 Auxiliary Feedwater Pumps 21, 22, and 23 Boric Acid Transfer Pumps 21 and 22 Charging Pumps 21, 22, and 23 Safety Injection Circulating Water Pumps 21, 22, and 23 Auxiliary Component Cooling Water Pumps 21 and 22 2.0 PROGRAM DESCRIPTION The following tabulation lists the pump identification, diagram number, quality group, parameters required to be measured or observed, pump group, and the test frequency. Requests for relief (R-R) numbers have been noted in the appropriate parameter columns, if applicable.
The detailed description of the requests for relief, containing the basis for a relief and alternate testing, follows the program tabulation, if applicable.
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