Text

TSTF-446, Revision 3, Risk Informed Evaluation of Extensions to Containment Isolation Valve Completion Times (WCAP-15791).
	ML080510164
Person / Time
Site:	Technical Specifications Task Force
Issue date:	02/19/2008
From:	David Bice, Gambrell R, Joseph Messina, Yates B; BWR Owners Group, PWR Owners Group, Technical Specifications Task Force
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	TSTF-08-04, TSTF-446, Rev 3, WCAP-15791
	Download: ML080510164 (40)
	v • d • e

TECHNICAL SPECIFICATIONS TASK FORCE TSTF A JOINT OWNERS GROUP ACTIVITY February 19, 2008 TSTF-08-04 PROJ0753 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001

SUBJECT:

TSTF-446, Revision 3, "Risk Informed Evaluation of Extensions to Containment Isolation Valve Completion Times (WCAP-15791)"

Dear Sir or Madam:

Enclosed for NRC review is Revision 3 of TSTF-446, "Risk Informed Evaluation of Extensions to Containment Isolation Valve Completion Times (WCAP-15791)." TSTF-446 is revised to reflect submittal of Revision 2 of the supporting Topical Report (WCAP-15791) and changes requested by the NRC during a teleconference. A description of the changes is found in the section entitled, "TSTF Revision 3, Revision Description."

We request that NRC review of TSTF-446 continue to be granted a fee waiver pursuant to the provisions of 10 CFR 170.11. Specifically, the request is to support NRC generic regulatory improvements (risk management technical specifications), in accordance with 10 CFR 170.11(a)(1)(iii). This request is consistent with the NRC letter to A. R. Pietrangelo on this subject dated January 10, 2003 and the NRCs review of previous revisions of this Traveler.

The TSTF requests that the Traveler be made available under the Consolidated Line Item Improvement Process.

11921 Rockville Pike, Suite 100, Rockville, MD 20852 Phone: 301-984-4400, Fax: 301-984-7600 Email: tstf@excelservices.com Administered by EXCEL Services Corporation

TSTF 08-04 February 19, 2008 Page 2 Should you have any questions, please do not hesitate to contact us.

Bert Yates (PWROG/W) John Messina (BWROG)

David Bice (PWROG/CE) Reene' Gambrell (PWROG/B&W)

Enclosure cc: Gerald Waig, Technical Specifications Branch, NRC Matthew Hamm, Technical Specifications Branch, NRC

WOG-167, Rev. 0 TSTF-446, Rev. 3 Technical Specification Task Force Improved Standard Technical Specifications Change Traveler Risk Informed Evaluation of Extensions to Containment Isolation Valve Completion Times (WCAP-15791)

NUREGs Affected: 1430 1431 1432 1433 1434 Classification: 1) Technical Change Recommended for CLIIP?: Yes Correction or Improvement: Improvement NRC Fee Status: Exempt Benefit: Provides Longer Completion Time Industry

Contact:

Bert Yates, (314) 554-3573, gyates@ameren.com See attached justification.

Revision History OG Revision 0 Revision Status: Closed Revision Proposed by: WOG Revision

Description:

Original Issue Owners Group Review Information Date Originated by OG: 17-Jul-02 Owners Group Comments (No Comments)

Owners Group Resolution: Approved Date: 17-Jul-02 TSTF Review Information TSTF Received Date: 27-Sep-02 Date Distributed for Review 04-Oct-02 OG Review Completed: BWOG WOG CEOG BWROG TSTF Comments:

(No Comments)

TSTF Resolution: Approved Date: 18-Oct-02 NRC Review Information NRC Received Date: 25-Oct-02 Final Resolution: Superceded by Revision TSTF Revision 1 Revision Status: Closed 19-Feb-08 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.

WOG-167, Rev. 0 TSTF-446, Rev. 3 TSTF Revision 1 Revision Status: Closed Revision Proposed by: WOG Revision

Description:

TSTF-446, Rev. 0 is revised to address responses to NRC RAI's on WCAP-15791 as follows.

1. Condition A references to Conditions D and E in Condition A are changed to Conditions E and F.

2. Condition B references to Conditions D and E in Condition B are changed to Conditions E and F.

3. A new Condition D is added for two or more penetration flow paths with one containment isolation valve inoperable.

4. Existing Conditions D, E, and F are revised to Conditions E, F, and G.

5. A new Bases discussion is added for new Required Action D.1. A Reviewer's Note is also added to the new Bases discussion for new Condition D that discusses the WCAP-15791 analysis, and the provision for a plant specific analysis, and associated revision to new Condition D to reflect the plant specific analysis.

6. The Bases for Required Actions D.1, E.1, and F.1 are revised to E.1, F.1, and G.1.

7. Reference 4 in the References of the Bases is revised to WCAP-15791, Rev. 1, May 2004.

In addition, the revised pages were marked on Revision 3 of NUREG-1431. This resulted in no alteration of the proposed changes.

Owners Group Review Information Date Originated by OG: 11-Mar-04 Owners Group Comments (No Comments)

Owners Group Resolution: Approved Date: 27-Jul-04 TSTF Review Information TSTF Received Date: 15-Oct-04 Date Distributed for Review 02-Nov-04 OG Review Completed: BWOG WOG CEOG BWROG TSTF Comments:

(No Comments)

TSTF Resolution: Approved Date: 29-Jan-05 NRC Review Information NRC Received Date: 31-Jan-05 NRC Comments:

On 5/19/07, the NRC stopped review of the Traveler pending submittal by Westinghouse of a revised Topical Report.

Final Resolution: Superceded by Revision 19-Feb-08 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.

WOG-167, Rev. 0 TSTF-446, Rev. 3 TSTF Revision 2 Revision Status: Closed Revision Proposed by: WOG Revision

Description:

Insert 4 and Insert 5 are revised to reflect the correct Table in WCAP-15791, Revision 1. Insert 8 is revised to provide additional clarifying Bases wording for subsequent CIV inoperabilities.

The NRC issued the final Safety Evaluation for WCAP-15791, Revision 1, "Risk-Informed Evaluation of Extension to Containment Isolation Valve Completion Times," on March 10, 2006. The lead plant amendment was issued on September 28, 2006, to Wolf Creek Nuclear Operating Company.

Owners Group Review Information Date Originated by OG: 02-Jan-06 Owners Group Comments (No Comments)

Owners Group Resolution: Date:

TSTF Review Information TSTF Received Date: 10-Jan-07 Date Distributed for Review 10-Jan-07 OG Review Completed: BWOG WOG CEOG BWROG TSTF Comments:

(No Comments)

TSTF Resolution: Approved Date: 11-Jan-07 NRC Review Information NRC Received Date: 11-Jan-07 Final Resolution: Superceded by Revision TSTF Revision 3 Revision Status: Active Revision Proposed by: NRC Revision

Description:

TSTF-446 is revised to address NRC comments:

1) The justification is revised to reflect submittal of WCAP-15791, Revision 2, on November 1, 2007.

2) The Tier 1 discussion is revised to clarify that licensees can use plant-specific input parameters and develop plant-specific Completion Times.

3) The discussion of Tier 3 requirements is expanded.

4) A new section on Performance Monitoring is added.

19-Feb-08 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.

WOG-167, Rev. 0 TSTF-446, Rev. 3 TSTF Revision 3 Revision Status: Active The Specifications are unaffected. The References section of the Bases was revised to reference Revision 2 instead of Revision 1 of WCAP-15791.

Owners Group Review Information Date Originated by OG: 15-Feb-08 Owners Group Comments (No Comments)

Owners Group Resolution: Approved Date: 19-Feb-08 TSTF Review Information TSTF Received Date: 15-Feb-08 Date Distributed for Review 29-Feb-08 OG Review Completed: BWOG WOG CEOG BWROG TSTF Comments:

(No Comments)

TSTF Resolution: Approved Date: 19-Feb-08 NRC Review Information NRC Received Date: 19-Feb-08 Affected Technical Specifications LCO 3.6.3 Containment Isolation Valves (Atmospheric, Subatmospheric, Ice Condenser, and Dual)

Ref. 3.6.3 Bases Containment Isolation Valves (Atmospheric, Subatmospheric, Ice Condenser, and Dual)

Action 3.6.3.A Containment Isolation Valves (Atmospheric, Subatmospheric, Ice Condenser, and Dual)

Action 3.6.3.A Bases Containment Isolation Valves (Atmospheric, Subatmospheric, Ice Condenser, and Dual)

Action 3.6.3.B Containment Isolation Valves (Atmospheric, Subatmospheric, Ice Condenser, and Dual)

Change

Description:

New Action 3.6.3.B Containment Isolation Valves (Atmospheric, Subatmospheric, Ice Condenser, and Dual)

Change

Description:

Renamed C 19-Feb-08 Traveler Rev. 3. Copyright (C) 2006, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.

1.0 DESCRIPTION

WCAP-15791, Rev. 1 provides the technical justification for extending the Completion Time, also referred to as the allowed outage time (AOT), from 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months to 168 hours0.00194 days 0.0467 hours 2.777778e-4 weeks 6.3924e-5 months (7 days) (for isolation valves that cannot demonstrate acceptable results for 168 hours0.00194 days 0.0467 hours 2.777778e-4 weeks 6.3924e-5 months , shorter times are considered and evaluated), for Technical Specification (TS) 3.6.3, "Containment Isolation Valves (Atmospheric, Subatmospheric, Ice Condenser, and Dual)." The current Completion Times are generally insufficient to respond to containment isolation valve inoperability and perform preventative maintenance activities at power.

The TS Bases for TS 3.6.3 are modified for consistency with the changes to the Technical Specifications.

Letter OG-02-022, dated June, 6, 2002, transmitted WCAP-15791-P, Rev. 0 (Proprietary) and WCAP-15791-NP, Rev. 0 (Non-Proprietary), both entitled "Risk-Informed Evaluation of Extensions to Containment Isolation Valve Completion Times," to the NRC for review and approval.

Letter WOG-04-234, dated May 6, 2004, transmitted WCAP-15791-P, Rev. 1 (Proprietary) and WCAP-15971-NP, Rev. 1 (Non-Proprietary), both entitled "Risk-Informed Evaluation of Extensions to Containment Isolation Valve Completion Times," to the NRC. WCAP-15791, Rev.

0 was revised in response to an NRC Request for Additional Information.

The NRC issued a revised final Safety Evaluation for WCAP-15791, Revision 2 on November 1, 2007. The lead plant amendment was issued on September 28, 2006, to Wolf Creek Nuclear Operating Company. The final, "-A" version of the Topical Report has not yet been issued. The date of the final version will be added to the References section of the Bases for Specification 3.6.3 during incorporation of this Traveler into the ISTS NUREGs.

2.0 PROPOSED CHANGE

WCAP-15791, Rev. 2 provides the justification for the following changes to TS 3.6.3, "Containment Isolation Valves (Atmospheric, Subatmospheric, Ice Condenser, and Dual)," of NUREG-1431, Westinghouse Standard Technical Specifications:

Condition A is revised to delete the NOTE, and to be applicable when the containment isolation valve pressure boundary is intact.

The Completion Time for Required Action A.1 is revised to allow a Completion Time from 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months up to a Completion Time of 7 days with the containment isolation valve pressure boundary intact.

A new Condition B is added for one or more penetration flow paths with one containment isolation valve inoperable and the containment isolation valve pressure boundary not intact.

Existing Condition B is revised to Condition C.

Existing Condition C for penetration flow paths with only one containment isolation valve and a closed system is deleted.

A new Condition D is added for two or more penetration flow paths with one containment Page 1 of 12

TSTF-446, Rev. 3 isolation valve inoperable. Existing Conditions D, E, and F are revised to Conditions E, F, and G.

3.0 BACKGROUND

The containment isolation valves are used to isolate containment penetration flow paths.

Typically, there is one containment isolation valve inside and one containment isolation valve outside each penetration that performs this function. Depending on the purpose of the system, the containment isolation valves may be normally open or closed. Systems can be closed or open inside and outside of containment. An open system inside containment is one that is directly connected to the containment atmosphere. An open system outside containment is one that is directly connected to the outside environment. A closed system inside containment is one that is not directly connected to the containment atmosphere and may consist of only a run of pipe inside containment. A closed system outside containment has no direct connection to the outside environment. Closed systems, either inside or outside containment, may not have an associated containment isolation valve.

The containment isolation valves form part of the containment pressure boundary and provide a means for fluid penetrations not serving accident consequence limiting systems to be provided with two isolation barriers that are closed on a containment isolation signal. The isolation devices are either passive or active (automatic). Manual valves, de-activated automatic valves secured in their closed position (including check valves with flow through the valve secured),

blind flanges, and closed systems are considered passive devices. Check valves, or other automatic valves designed to close without operator action following an accident, are considered active devices. Two barriers in series are provided for each penetration so that no single credible failure or malfunction of an active component can result in a loss of isolation or leakage that exceeds limits assumed in the safety analyses. One of these barriers may be a closed system. These barriers (typically containment isolation valves) make up the Containment Isolation System.

Automatic isolation signals are produced during accident conditions. Containment Phase "A" isolation occurs upon receipt of a safety injection signal. The Phase "A" isolation signal isolates nonessential process lines in order to minimize leakage of fission product radioactivity.

Containment Phase "B" isolation occurs upon receipt of a containment pressure high signal and isolates the remaining process lines, except systems required for accident mitigation. In addition to the isolation signals listed above, the purge and exhaust valves receive an isolation signal on a containment high radiation condition. As a result, the containment isolation valves (and blind flanges) help ensure that the containment atmosphere will be isolated from the environment in the event of a release of fission product radioactivity to the containment atmosphere as a result of a Design Basis Accident (DBA).

The OPERABILITY requirements for containment isolation valves help ensure that containment is isolated within the time limits assumed in the safety analysis. Therefore, the OPERABILITY requirements provide assurance that the containment function assumed in the safety analysis will be maintained.

The containment isolation valve Limiting Condition for Operation (LCO) was derived from the assumptions related to minimizing the loss of reactor coolant inventory and establishing the containment boundary during major accidents. As part of the containment boundary, containment isolation valve OPERABILITY supports leak tightness of the containment.

Page 2 of 12

TSTF-446, Rev. 3 Therefore, the safety analysis of any event requiring isolation of containment is applicable to this LCO.

The DBAs that result in a release of radioactive material within containment are a loss of coolant accident and a rod ejection accident. In the analysis for each of these accidents, it is assumed that containment isolation valves are either closed or function to close within the required isolation time following event initiation. This ensures that potential paths to the environment through containment isolation valves are minimized.

As discussed in Regulatory Guide 1.177, "An Approach for Plant-Specific, Risk-Informed Decision-Making: Technical Specifications," acceptable reasons for requesting Technical Specification changes fall into one or more of the following categories:

Improvement to operational safety: A change to the TSs can be made due to reductions in the plant risk or a reduction in the occupational exposure of plant personnel in complying with the TS requirements.

Consistency with risk basis in regulatory requirements: TS requirements can be changed to reflect improved design features in a plant or to reflect equipment reliability improvements that make a previous requirement unnecessarily stringent or ineffective.

TSs may be changed to establish consistently based requirements across the industry or across an industry group.

Reduce unnecessary burdens: The change may be requested to reduce unnecessary burdens in complying with current TS requirements, based on operating history of the plant or the industry in general. This includes extending Completion Times 1) that are too short to complete repairs when components fail with the plant at-power, 2) to complete additional maintenance activities at-power to reduce plant down time, and 3) to provide increased flexibility to plant operators.

The Completion Time extensions in WCAP-15791, Rev. 2 are requested primarily to provide an improvement to operational safety, reduce unnecessary burden and provide a more consistent risk basis in regulatory requirements. In addition, the assumption that shutting the plant down is the safest course of action is not always valid and depending on the component or system of interest, it may be safer to complete component repairs at power. During shutdown, the transfer from auxiliary feedwater (AFW) to the residual heat removal (RHR) system represents an increased risk level due to system alignment changes that could lead to loss of inventory events. This transition can be avoided by completing the repair at-power. Potential risks associated with plant shutdown need to be considered when determining an appropriate course of action. Extended Completion Times enable this shutdown risk to be averted.

With regard to the regulatory basis consistency, containment isolation valves are typically not as risk significant as many other plant safety systems and components. Often these other systems more important to risk have Completion Times that are longer than the Completion Times for containment isolation valves. Shorter Completion Times should be imposed on systems or components that are considered to be of higher risk significance. Containment penetrations do not rely on single valves to perform their isolation function, but are designed with multiple isolation valves or involve a closed system. A 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Completion Time is too restrictive and potentially forces plant operators to focus on containment isolation valve inoperability ahead of other inoperabilities that may be more risk significant, but have longer Completion Times.

Page 3 of 12

TSTF-446, Rev. 3

4.0 TECHNICAL ANALYSIS

4.1 Impact on Defense-in-Depth and Safety Margins In addition to discussing the impact of the changes on plant risk, the traditional engineering considerations need to be addressed. These include defense-in-depth and safety margins.

The fundamental safety principles on which the plant design is based cannot be compromised.

Design basis accidents are used to develop the plant design. These are a combination of postulated challenges and failure events that are used in the plant design to demonstrate safe plant response. Defense-in-depth, the single failure criterion, and adequate safety margins may be impacted by the proposed change and consideration needs to be given to these elements.

Impact on Defense-in Depth The proposed change needs to meet the defense-in-depth principle which consists of a number of elements. These elements and the impact of the proposed change on each follow:

A reasonable balance among prevention of core damage, prevention of containment failure, and consequence mitigation is preserved.

The containment isolation valves are part of the plant design to primarily ensure containment integrity following an accident. By closing the containment isolation valves, inventory required to cool the core is also maintained. The containment isolation valves are not included in the plant design for consequence mitigation. Therefore, the proposed Completion Time change for the containment isolation valves has a negligible impact on Core Damage Frequency (CDF), no direct impact on consequence mitigation, and only a small impact on Large Early Release Frequency (LERF). This change does not significantly degrade the ability of one barrier to fission product release and compensates with an improvement of another barrier. The balance between prevention of core damage and prevention of containment failure and consequence mitigation is maintained. Furthermore, no new accidents or transients are introduced with the requested change and the likelihood of an accident or transient is not impacted.

Over-reliance on programmatic activities to compensate for weaknesses in plant design.

The plant design will not be modified with this proposed change. All safety systems, including the containment isolation valves, will still function in the same manner with the same reliability, and there will be no additional reliance on additional systems, procedures, or operator actions. The calculated risk increase for the Completion Time changes is very small and additional control processes are not required to be put into place to compensate for any risk increase.

System redundancy, independence, and diversity are maintained commensurate with the expected frequency and consequences of challenges to the system.

There is no impact on the redundancy, independence, or diversity of the containment isolation valves or on the ability of the plant to isolate containment penetrations with diverse systems. The redundant and diverse containment isolation designs will not be changed.

Page 4 of 12

TSTF-446, Rev. 3 The containment isolation valves are reliable components and will remain reliable after these proposed changes.

Defenses against potential common cause failures are maintained and the potential for introduction of new common cause failure mechanisms is assessed.

Defenses against common cause failures are maintained. The completion time extensions requested are not significantly increased such that any new common cause failure mechanisms would occur. In addition, the operating environment for these components remains the same, therefore, new common cause failures modes are not expected. The number, design, and types of valves used for containment isolation remain the same with these changes so the containment isolation system maintains the potential against common cause failures.

Independence of barriers is not degraded.

The barriers protecting the public and the independence of these barriers are maintained. It is not expected that multiple systems will be out of service simultaneously during the extended Completion Times that could lead to degradation of these barriers, and an increase in risk to the public. In addition, the extended Completion Times do not provide a mechanism that degrades the independence of the barriers; fuel cladding, Reactor Coolant System, and containment.

Defenses against human errors are maintained.

No new operator actions related to the Completion Time extensions are required to maintain plant safety. No changes to current operating, maintenance, or test procedures are required due to these changes. The increase in Completion Times provides additional time to complete troubleshooting, and test and repair activities which will lead to improved operator and maintenance personnel performance, resulting in reduced system re-alignment and restoration errors.

Impact on Safety Margins The safety analysis acceptance criteria as stated in the FSAR are not impacted by this change.

Redundant and diverse containment isolation valves, where applicable, and closed systems, will be maintained. The proposed changes will not allow plant operation in a configuration outside the design basis. Isolation of all containment penetrations will remain single failure proof.

Containment isolation valve operation and testing requirements and containment leakage requirements are not impacted by this change. There is no impact on safety margins.

4.2 Generic Assessment of Impact on Risk This section presents the analysis and assumptions used to determine the impact on plant risk of increasing the Completion Times specified in Section 2.0. This section addresses the three tiered approach to the evaluation of risk-informed TS changes. The three tiered approach is defined in Regulatory Guide 1.177. The first tier addresses Probabilistic Risk Assessment (PRA) insights and includes the risk analyses to support the Completion Time change. The second tier addresses avoidance of risk-significant plant configurations. The third tier, which Page 5 of 12

TSTF-446, Rev. 3 addresses risk-informed plant configuration control and management, is covered by each utilitys Maintenance Rule Program.

Tier 1: Approach to the Evaluation The Tier 1 analysis provides the impact of the Completion Time changes on the incremental conditional large early release probability (ICLERP) and LERF. Since the containment isolation valves are used to maintain containment integrity, any change to their availability will directly impact releases from containment following a core damage event. The impact of these changes on CDF, and as measured by the change in CDF and incremental conditional core damage probability (ICCDP) values, is not important since this impact would be a secondary effect related to a long-term loss of inventory for core cooling or are associated with releases from containment bypass sequences. With regard to containment bypass sequences, the LERF guidelines are more limiting than the CDF guidelines, therefore, if the LERF guidelines are met for containment bypass sequences, then the CDF guidelines are also met.

The approach used in this program applies both deterministic and probabilistic evaluations. A deterministic approach is used to determine the containment hole size that could result in a large release. Based on previous industry analyses, a containment hole size of 2 inches or less will not result in a large release from the containment atmosphere. The 2 inch containment hole size is applicable to large dry, subatmospheric, and ice condenser containment types.

Therefore, penetration flow paths connected to the containment atmosphere less than or equal to 2 inches are allowed a Completion Time of 7 days. All other penetrations are evaluated on a probabilistic basis to demonstrate if a Completion Time of 7 days is acceptable or to determine an appropriate lesser Completion Time. The probabilistic evaluation is consistent with the Nuclear Regulatory Commissions (NRC's) approach for using PRA in RI decisions on plant-specific changes to the current licensing basis. This approach is discussed in Regulatory Guide 1.174, "An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis," and Regulatory Guide 1.177.

The probabilistic analyses was completed on a generic basis. Input parameters used in the analyses were chosen based on the most conservative plant parameters available, that is, the set of parameters that results in the most conservative results (shortest Completion Time).

Application of the generic analysis on a plant specific basis requires each utility implementing this change to demonstrate that their plant is within the bounds of the analysis. As an alternative, licensees can use plant specific input parameters, re-quantify the Completion Time calculations, and develop plant specific Completion Times.

The following types of containment penetration flow paths are evaluated:

Penetration flow paths connected to the containment atmosphere

Penetration flow paths connected to the Reactor Coolant System

Penetration flow paths connected to the Steam Generators Probabilistic Evaluation of the Containment Penetrations The probabilistic evaluation involves the calculation of the ICLERP and LERF for each type of containment isolation valve penetration. Through finding acceptable ICLERP and LERF values per Regulatory Guides 1.177 and 1.174 (less than 5.0E-08 and 1.0E-07, respectively),

Page 6 of 12

TSTF-446, Rev. 3 the maximum Completion Times were determined. For those penetrations that could not be justified to the target 7 day Completion Time, shorter Completion Times were evaluated at 72, 48, 24, 12, and 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

The ICLERP is defined in Regulatory Guide 1.177 as:

ICLERP = [(conditional LERF with the subject equipment out of service) - (baseline LERF with nominal expected equipment unavailabilities)] x duration of a single CT under consideration The ICLERP was found for each penetration with the assumption that one containment isolation valve within the penetration is in maintenance. If there was more than one containment isolation valve within the penetration, the calculation was performed as many times as there are valves because any one of those valves could be in maintenance.

For the LERF calculations, a fault tree analysis was performed to evaluate all combinations of non-isolated penetration possibilities for each penetration. Non-isolations can be a result of valve failure as well as a valve being in maintenance. This was done for the current 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Completion Time and the proposed 168 hour0.00194 days 0.0467 hours 2.777778e-4 weeks 6.3924e-5 months Completion Time or lesser times as necessary to meet the 1.0E-07/yr LERF criterion. The increase in the probability of failing to isolate the penetration was then multiplied by the CDF to find the final LERF.

The specific calculations for the ICLERPs and LERFs for the containment isolation valves vary from penetration to penetration. The variations are dependent upon the conditions and configurations of the penetration.

For generic applicability, a large variety of possible containment penetration flow paths were identified, including connections to containment atmosphere, the Reactor Coolant System and the Steam Generators. Different valve types (solenoid-operated valves, motor-operated valves, air-operated valves, check valves, and safety relief valves) and valve positioning (normally open or normally closed) were taken into account for each penetration type. The common cause failure of valves within a flow path being of the same valve type and performing a similar function was also included. In addition, unavailability due to maintenance of the containment isolation valves was included in the analysis.

Deterministic Evaluation used for Containment Hole Sizes Less than or Equal to 2 Inches A containment hole size less than or equal to 2 inches will not result in a large release.

Penetration flow paths connected to the containment atmosphere (this excludes all Reactor Coolant System and Steam Generator connections) that have piping diameters less than or equal to this 2 inch threshold value are not large enough to result in a large release. This is consistent with previous industry analyses that use a 2 inch containment hole size for screening in the development of containment isolation PRA models, and was agreed to by the NRC as discussed in the response to RAI 2.c as discussed in letter WOG-04-077, dated February 13, 2004. These penetrations automatically default to the 7 day Completion Time and no detailed probabilistic analysis is required.

Page 7 of 12

TSTF-446, Rev. 3 Tier 2: Avoidance of Risk-Significant Plant Conditions The objective of the second tier, which is applicable to Completion Time extensions, is to provide reasonable assurance that risk-significant plant equipment outage configurations will not occur when equipment is out of service. If risk-significant configurations do occur, then enhancements to Technical Specifications or procedures, such as limiting unavailability of backup systems, increased surveillance frequencies, or upgrading procedures or training, can be made that avoid, limit, or lessen the importance of these configurations.

The containment isolation valves form part of the containment barrier limiting releases to the environment. Other containment systems, such as the containment cooling system and containment spray system, also function to mitigate releases to the environment, but by different mechanisms. These other systems typically are used to preserve containment integrity by limiting containment pressure increase or to remove radioactive material from the containment atmosphere. The containment cooling and containment spray systems are generally not considered backup to the containment isolation function. Given that containment isolation has failed, releases from containment are independent of the success or failure of containment cooling. The containment is already breached and containment pressure limitation is no longer an issue. On the other hand, if containment isolation has failed, then containment sprays could be a factor in limiting releases via their scrubbing effect. This would be of limited benefit, because a large portion of the core damage sequences in which containment spray was functional at the time of the initiating event do not have effective scrubbing by sprays at the time of fission product release to the containment. Thus, efforts taken to assure the availability of containment spray when containment isolation may be impaired, do little to assure that containment spray will be effective in reducing releases if a core damage accident occurs. Also, when analyzed on a realistic basis, only a small fraction of the core damage sequences with containment isolation failures would result in fission product releases that are risk significant.

Therefore, no Tier 2 limitations need to be imposed.

Tier 3: Risk-Informed Plant Configuration Control and Management The objective of the third-tier is to ensure that the risk impact of out-of-service equipment is evaluated prior to performing any maintenance activity. As stated in RG-1.174, "a viable program would be one that is able to uncover risk-significant plant equipment outage configurations as they evolve during real-time, normal plant operation." The third-tier requirement is an extension of the second-tier requirement, but addresses the limitation of not being able to identify all possible risk-significant plant configurations in the second-tier evaluation.

Tier 3 requirements will be addressed by each licensee's Maintenance Rule Program (10 CFR 50.65(a)(4)). Plant specific Maintenance Rule evaluations will consider the CIVs with diameters greater than 2 inches. This can be done in one of the following two ways:

Model each CIV greater than 2 inches in diameter and the associated containment penetration in the PRA model used for the Maintenance Rule evaluations.

Model a representative number of CIVs greater than 2 inches in diameter and associated containment penetrations in the PRA model used for the Maintenance Rule evaluations. The representative modeled CIVs can be used as surrogates for the CIVs not explicitly modeled.

Page 8 of 12

TSTF-446, Rev. 3 4.3 Performance Monitoring Element 3 (Define Implementation and Monitoring Program) of the risk-informed process defined in Regulatory Guide 1.174 addresses performance monitoring. The primary goal of performance monitoring is to ensure that no adverse safety degradation occurs because of the proposed changes. The performance monitoring program should ensure that the engineering evaluation remains applicable. The key analysis parameters in the extension of the CIV Completion Times is the unavailability of the CIVs. Therefore, the program can monitor the unavailability of the CIVs to ensure they remain within the analysis assumptions. One method to do this is by CIV Category with the Category defined by a common Completion Time. Each CIV greater than 2 inches in diameter can be assigned to Categories 2 through 7. It is not necessary to monitor Category 1, since this Category is the original 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months CIV Completion Time. It is also not necessary to monitor CIVs less than or equal 2 inches in diameter, since they cannot provide a large release. The average unavailability for each Category can be compared to the analysis assumptions to demonstrate consistency.

5.0 REGULATORY ANALYSIS

5.1 No Significant Hazards Consideration The proposed changes to the Improved Standard Technical Specifications (ISTS) will revise Technical Specifications 3.6.3 to extend selected Completion Times.

In accordance with the criteria set forth in 10 CFR 50.92, the proposed changes to NUREG-1431 have been evaluated and it has been determined that they do not represent a significant hazards consideration. The following is provided in support of this conclusion:

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

Response: No The proposed changes to the Completion Times do not change the response of the plant to any accidents and have no impact on the reliability of the containment isolation valves, and an insignificant impact on the availability of the containment isolation valves. The containment isolation valves will remain highly reliable and the proposed changes will not result in a significant increase in the risk of plant operation. This is demonstrated by showing that the impact on plant safety as measured by core damage frequency (CDF) and large early release frequency (LERF) is acceptable. In addition, for the Completion Time change, the incremental conditional core damage probabilities (ICCDP) and incremental conditional large early release probabilities (ICLERP) are also acceptable. These changes are consistent with the acceptance criteria in Regulatory Guides 1.174 and 1.177. Therefore, since the containment isolation valves will continue to perform their functions with high reliability as originally assumed, and the increase in risk as measured by CDF, LERF, ICCDP, ICLERP is acceptable, there will not be a significant increase in the consequences of any accidents.

The proposed changes do not adversely affect accident initiators or precursors nor alter the design assumptions, conditions, or configuration of the facility or the manner in which the plant Page 9 of 12

TSTF-446, Rev. 3 is operated and maintained. The proposed changes do not alter or prevent the ability of structures, systems, and components (SSCs) from performing their intended function to mitigate the consequences of an initiating event within the assumed acceptance limits. The proposed changes do not affect the source term, containment isolation, or radiological release assumptions used in evaluating the radiological consequences of an accident previously evaluated. Further, the proposed changes do not increase the types or amounts of radioactive effluent that may be released offsite, nor significantly increase individual or cumulative occupational/public radiation exposures. The proposed changes are consistent with the safety analysis assumptions and resultant consequences.

Therefore, it is concluded that this change does not significantly increase the probability of an accident previously evaluated.

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

Response: No The proposed changes do not result in a change in the manner in which the containment isolation valves provide plant protection. There are no design changes associated with the proposed changes. The changes to Completion Times do not change any existing accident scenarios, nor create any new or different accident scenarios.

The changes do not involve a physical alteration of the plant (i.e., no new or different type of equipment will be installed) or a change in the methods governing normal plant operation. In addition, the changes do not impose any new or different requirements or eliminate any existing requirements. The changes do not alter assumptions made in the safety analysis. The proposed changes are consistent with the safety analysis assumptions and current plant operating practice.

Therefore, the possibility of a new or different kind of accident from any accident previously evaluated is not created.

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

Response: No The proposed changes do not alter the manner in which safety limits, limiting safety system settings or limiting conditions for operation are determined. The safety analysis acceptance criteria are not impacted by these changes. The proposed changes will not result in plant operation in a configuration outside the design basis. The calculated impact on risk is insignificant and is consistent with the acceptance criteria contained in Regulatory Guides 1.174 and 1.177.

Therefore, it is concluded that this change does not involve a significant reduction in a margin of safety.

5.2 Applicable Regulatory Requirements/Criteria General Design Criteria 54 - Piping Systems Penetrating Containment Page 10 of 12

TSTF-446, Rev. 3 Piping Systems penetrating the primary reactor containment shall be provided with leak detection, isolation, and containment capabilities having redundancy, reliability, and performance capabilities which reflect the importance to safety of isolating these piping systems. Such piping systems shall be designed with a capability to test periodically the operability of the isolation valves and associated apparatus and to determine if valve leakage is within acceptable limits.

General Design Criteria 55 - Reactor Coolant Pressure Boundary Penetrating Containment Each line that is part of the reactor coolant pressure boundary and that penetrates primary reactor containment shall be provided with containment isolation valves as follows, unless it can be demonstrated that the containment isolation provisions for a specific class of lines, such as instrument lines, are acceptable on some other defined basis:

(1) One locked closed isolation valve inside and one locked closed isolation valve outside containment; or (2) One automatic isolation valve inside and one locked closed isolation valve outside containment; or (3) One locked closed isolation valve inside and one automatic isolation valve outside containment. A simple check valve may not be used as the automatic isolation valve outside containment; or (4) One automatic isolation valve inside and one automatic isolation valve outside containment. A simple check valve may not be used as the automatic isolation valve outside containment.

Isolation valves outside containment shall be located as close to containment as practical and upon loss of actuating power, automatic isolation valves shall be designed to take the position that provides greater safety.

Other appropriate requirements to minimize the probability or consequences of an accidental rupture of those lines or of lines connected to them shall be provided as necessary to assure adequate safety. Determination of the appropriateness of these requirements, such as higher quality in design, fabrication and testing, additional provisions for inservice inspection, protection against more severe natural phenomena, and additional isolation valves and containment, shall include consideration of the population density, use characteristics, and physical characteristics of the site environs.

General Design Criteria 56 - Primary Containment Isolation Each line that connects directly to the containment atmosphere and penetrates primary reactor containment shall be provided with containment isolation valves as follows, unless it can be demonstrated that the containment isolation provisions for a specific class of lines, such as instrument lines, are acceptable on some other defined basis:

(1) One locked closed isolation valve inside and one locked closed isolation valve outside containment; or (2) One automatic isolation valve inside and one locked closed isolation valve outside containment; or Page 11 of 12

TSTF-446, Rev. 3 (3) One locked closed isolation valve inside and one automatic isolation valve outside containment. A simple check valve may not be used as the automatic isolation valve outside containment; or (4) One automatic isolation valve inside and one automatic isolation valve outside containment. A simple check valve may not be used as the automatic isolation valve outside containment.

Isolation valves outside containment shall be located as close to the containment as practical and upon loss of actuating power, automatic isolation valves shall be designed to take the position that provides greater safety.

General Design Criteria 57 - Closed System Isolation Valves Each line that penetrates the primary reactor containment and is neither part of the reactor coolant pressure boundary nor connected directly to the containment atmosphere shall have at least one containment isolation valve which shall be either automatic, or locked closed, or capable of remote manual operation. This valve shall be outside containment and located as close to the containment as practical. A simple check valve may not be used as the automatic isolation valve.

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

6.0 ENVIRONMENTAL CONSIDERATION

S A review has determined that the proposed change would change a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR 20, or would change an inspection or surveillance requirement. However, the proposed change does not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluents that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure. Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(9). Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed amendment.

7.0 REFERENCES

1. WCAP-15791-P-A, Rev. 2 (Proprietary) and WCAP-15791-NP-A, Rev. 1 (Non-Proprietary), both entitled "Risk-Informed Evaluation of Extensions to Containment Isolation Valve Completion Times."

Page 12 of 12

TSTF-446, Rev. 3 Containment Isolation Valves (Atmospheric, Subatmospheric, Ice Condenser, and Dual) 3.6.3 3.6 CONTAINMENT SYSTEMS 3.6.3 Containment Isolation Valves (Atmospheric, Subatmospheric, Ice Condenser, and Dual)

LCO 3.6.3 Each containment isolation valve (CIV) shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS

NOTES----------------------------------------------------------

1. Penetration flow path(s) [except for [42] inch purge valve flow paths] may be unisolated intermittently under administrative controls.

2. Separate Condition entry is allowed for each penetration flow path.

3. Enter applicable Conditions and Required Actions for systems made inoperable by containment isolation valves.

4. Enter applicable Conditions and Required Actions of LCO 3.6.1, "Containment," when isolation valve leakage results in exceeding the overall containment leakage rate acceptance criteria.

CONDITION REQUIRED ACTION COMPLETION TIME A. ------------NOTE------------ A.1 Isolate the affected 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for Category Only applicable to penetration flow path by 1 CIVs penetration flow paths use of at least one closed with two [or more] and de-activated automatic AND containment isolation valve, closed manual valve, valves. blind flange, or check valve 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months for Category

with flow through the valve 2 CIVs secured.

[ One or more AND penetration flow paths AND with one containment 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for Category isolation valve 3 CIVs inoperable [for reasons other than Condition[s] D AND E [and EF)).

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for Category AND 4 CIVs Containment isolation AND WOG STS 3.6.3-1 Rev. 3.0, 03/31/04

TSTF-446, Rev. 3 Containment Isolation Valves (Atmospheric, Subatmospheric, Ice Condenser, and Dual) 3.6.3 CONDITION REQUIRED ACTION COMPLETION TIME valve pressure boundary intact. ] 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months for Category 5 CIVs AND 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months for Category 6 CIVs AND 7 days for Category 7 CIVs4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months WOG STS 3.6.3-2 Rev. 3.0, 03/31/04

TSTF-446, Rev. 3 Containment Isolation Valves (Atmospheric, Subatmospheric, Ice Condenser, and Dual) 3.6.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME A.2 -------------NOTES-------------

1. Isolation devices in high radiation areas may be verified by use of administrative means.

2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means.

Verify the affected Once per 31 days for penetration flow path is isolation devices isolated. outside containment AND Prior to entering MODE 4 from MODE 5 if not performed within the previous 92 days for isolation devices inside containment ]

WOG STS 3.6.3-3 Rev. 3.0, 03/31/04

TSTF-446, Rev. 3 Containment Isolation Valves (Atmospheric, Subatmospheric, Ice Condenser, and Dual) 3.6.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. [One or more penetration B.1 Isolate the affected 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for flow paths with one penetration flow path by Category 8 CIVs containment isolation valve use of at least one closed inoperable [for reasons and de-activated AND other than Condition[s] E automatic valve, closed

[and F)). manual valve, blind 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months for flange, or check valve with Category 9 CIVs AND flow through the valve Containment isolation secured. AND valve pressure boundary not intact. AND 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for Category 10 CIVs AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for Category 11 CIVs AND 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months for Category 12 CIVs AND 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months for Category 13 CIVs AND 7 days for Category 14 CIVs WOG STS 3.6.3-4 Rev. 3.0, 03/31/04

TSTF-446, Rev. 3 Containment Isolation Valves (Atmospheric, Subatmospheric, Ice Condenser, and Dual) 3.6.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.2 -------------- NOTES ---------

1. Isolation devices in high radiation areas may be verified by use of administrative means.

2. Isolation devices that are locked, sealed, or otherwise secured may be verified by administrative means.

Verify the affected Once per 31 days penetration flow path is for isolation isolated. devices outside containment AND Prior to entering MODE 4 from MODE 5 if not performed within the previous 92 days for isolation devices inside containment]

WOG STS 3.6.3-5 Rev. 3.0, 03/31/04

TSTF-446, Rev. 3 Containment Isolation Valves (Atmospheric, Subatmospheric, Ice Condenser, and Dual) 3.6.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME BC. ------------NOTE------------ BC.1 Isolate the affected 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Only applicable to penetration flow path by penetration flow paths use of at least one closed with two [or more] and de-activated automatic containment isolation valve, closed manual valve, valves. or blind flange.

One or more penetration flow paths with two [or more] containment isolation valves inoperable [for reasons other than Condition[s] D E [and EF)).

C. ------------NOTE------------ C.1 Isolate the affected 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Only applicable to penetration flow path by penetration flow paths use of at least one closed with only one and de-activated automatic containment isolation valve, closed manual valve, valve and a closed or blind flange.

system.

AND One or more penetration flow paths with one containment isolation valve inoperable.

WOG STS 3.6.3-6 Rev. 3.0, 03/31/04

TSTF-446, Rev. 3 Containment Isolation Valves (Atmospheric, Subatmospheric, Ice Condenser, and Dual) 3.6.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C.2 -------------NOTES-------------

1. Isolation devices in high radiation areas may be verified by use of administrative means.

2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means.

Verify the affected Once per 31 days penetration flow path is isolated.

D. Two or more penetration D.1 Isolate all but one 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months flow paths with one penetration flow path by containment isolation use of at least one closed valve inoperable [for and de-activated automatic reasons other than valve, closed manual valve, Condition[s] E [and F)). or blind flange.

DE. [ One or more shield DE.1 Restore leakage within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for shield building bypass leakage limit. building bypass

[or purge valve leakage] leakage not within limit.

AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for purge valve leakage ]

EF. [ One or more EF.1 Isolate the affected 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months penetration flow paths penetration flow path by with one or more use of at least one [closed containment purge and de-activated automatic valves not within purge valve, closed manual valve, valve leakage limits. or blind flange].

AND WOG STS 3.6.3-7 Rev. 3.0, 03/31/04

TSTF-446, Rev. 3 Containment Isolation Valves (Atmospheric, Subatmospheric, Ice Condenser, and Dual) 3.6.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME EF.2 -------------NOTES-------------

1. Isolation devices in high radiation areas may be verified by use of administrative means.

2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means.

Verify the affected Once per 31 days for penetration flow path is isolation devices isolated. outside containment AND Prior to entering MODE 4 from MODE 5 if not performed within the previous 92 days for isolation devices inside containment AND EF.3 Perform SR 3.6.3.7 for the Once per [92] days ]

resilient seal purge valves closed to comply with Required Action EF.1.

FG. Required Action and FG.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND FG.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months WOG STS 3.6.3-8 Rev. 3.0, 03/31/04

TSTF-446, Rev. 3 Containment Isolation Valves (Atmosperic, Subatmospheric, Ice Condenser, and Dual)

B 3.6.3 BASES ACTIONS (continued)

A second Note has been added to provide clarification that, for this LCO, separate Condition entry is allowed for each penetration flow path. This is acceptable, since the Required Actions for each Condition provide appropriate compensatory actions for each inoperable containment isolation valve. Complying with the Required Actions may allow for continued operation, and subsequent inoperable containment isolation valves are governed by subsequent Condition entry and application of associated Required Actions.

The ACTIONS are further modified by a third Note, which ensures appropriate remedial actions are taken, if necessary, if the affected systems are rendered inoperable by an inoperable containment isolation valve.

In the event the isolation valve leakage results in exceeding the overall containment leakage rate, Note 4 directs entry into the applicable Conditions and Required Actions of LCO 3.6.1.

REVIEWERS NOTE ------------------------------------

Conditions A and B may be combined into one Condition that addresses both the containment isolation valve pressure boundary intact and containment isolation valve pressure boundary not intact by specifying the limiting Completion Time for each configuration identified in Tables D-1, D-2, and D-3 of Reference 4.

[ A.1 and A.2 Condition A is applicable to penetration flow paths with two [or more]

containment isolation valves, and penetration flow paths with only one containment isolation valve and a closed system. The closed system must meet the requirements of Reference 3.

In the event one containment isolation valve in one or more penetration flow paths is inoperable, [except for purge valve or shield building bypass leakage not within limit], and the containment isolation valve pressure boundary is intact, the affected penetration flow path must be isolated.

The containment isolation valve pressure boundary is considered to be intact when the inoperable containment isolation valve is capable of maintaining the boundary between the contained fluid and the containment or outside atmosphere. An example of when a containment isolation valve would be inoperable and the pressure boundary is considered to be intact is when work is being performed on a valve actuator. The method of isolation must include the use of at least one isolation barrier that cannot be adversely affected by a single active WOG STS B 3.6.3-5 Rev. 3.0, 03/31/04

TSTF-446, Rev. 3 Containment Isolation Valves (Atmosperic, Subatmospheric, Ice Condenser, and Dual)

B 3.6.3 failure. Isolation barriers that meet this criterion are a closed and de-activated automatic containment isolation valve, a closed manual valve, a blind flange, and a check valve with flow through the valve secured. For a penetration flow path isolated in accordance with Required Action A.1, the device used to isolate the penetration should be the closest available one to containment. Required Action A.1 must be completed within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . The 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Completion Time is reasonable, considering the time required to isolate the penetration and the relative importance of supporting containment OPERABILITY during MODES 1, 2, 3, and 4. the Completion Time specified for each Category of containment isolation valve identified in [a licensee controlled document]. The Completion Time is justified in Reference 4.

REVIEWERS NOTE ------------------------------------

Conditions A and B may be combined into one Condition that addresses both the containment isolation valve pressure boundary intact and containment isolation valve pressure boundary not intact by specifying the limiting Completion Time for each configuration identified in Tables D-1, D-2, and D-3 of Reference 4.

The plant specific determination of the containment isolation valve Completion Time categories is performed by comparing the plant specific penetration types to the generic penetration types evaluated that are identified in Tables D-1, D-2, and D-3 of Reference 4.

The plant specific application of the generic analysis that justified the generic Completion Time categories is discussed in Section 9.0 of Reference 4.

Plant specific Completion Time categories may also be calculated in lieu of the generic Completion Time categories. This approach is discussed in Section 10.0 of Reference 4.

For plants not adopting the risk-informed extended Completion Time for containment isolation valves, a Completion Time of 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months is maintained.

The 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Completion Time is reasonable, considering the time required to isolate the penetration and the relative importance of supporting containment OPERABILITY during MODES 1, 2, 3, and 4. A Condition for one or more penetration flow paths with one containment isolation valve inoperable for penetrations with one containment isolation valve and a closed system would be required.

For affected penetration flow paths that cannot be restored to OPERABLE status within the 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months specified Completion Time and that have been isolated in accordance with Required Action A.1, the affected penetration flow paths must be verified to be isolated on a periodic basis.

This is necessary to ensure that containment penetrations required to be isolated following an accident and no longer capable of being automatically WOG STS B 3.6.3-6 Rev. 3.0, 03/31/04

TSTF-446, Rev. 3 Containment Isolation Valves (Atmosperic, Subatmospheric, Ice Condenser, and Dual)

B 3.6.3 BASES ACTIONS (continued) isolated will be in the isolation position should an event occur. This Required Action does not require any testing or device manipulation.

Rather, it involves verification that those isolation devices outside containment and capable of being mispositioned are in the correct position. The Completion Time of "once per 31 days for isolation devices outside containment" is appropriate considering the fact that the devices are operated under administrative controls and the probability of their misalignment is low. For the isolation devices inside containment, the time period specified as "prior to entering MODE 4 from MODE 5 if not performed within the previous 92 days" is based on engineering judgment and is considered reasonable in view of the inaccessibility of the isolation devices and other administrative controls that will ensure that isolation device misalignment is an unlikely possibility.

Condition A has been modified by a Note indicating that this Condition is only applicable to those penetration flow paths with two [or more]

containment isolation valves. For penetration flow paths with only one containment isolation valve and a closed system, Condition C provides the appropriate actions.

Required Action A.2 is modified by two Notes. Note 1 applies to isolation devices located in high radiation areas and allows these devices to be verified closed by use of administrative means. Allowing verification by administrative means is considered acceptable, since access to these areas is typically restricted. Note 2 applies to isolation devices that are locked, sealed, or otherwise secured in position and allows these devices to be verified closed by use of administrative means. Allowing verification by administrative means is considered acceptable, since the function of locking, sealing, or securing components is to ensure that these devices are not inadvertently repositioned. Therefore, the probability of misalignment of these devices once they have been verified to be in the proper position, is small. ]

[ B.1 and B.2 Condition B is applicable to penetration flow paths with two [or more]

containment isolation valves, and penetration flow paths with only one containment isolation valve and a closed system. The closed system must meet the requirements of Reference 3.

In the event one containment isolation valve in one or more penetration flow paths is inoperable, [except for purge valve or shield building bypass leakage not within limit,] and the containment isolation valve pressure boundary is not intact, the affected penetration flow path must be isolated.

The containment isolation valve pressure boundary is considered not to be intact when the inoperable containment isolation valve is not capable WOG STS B 3.6.3-7 Rev. 3.0, 03/31/04

TSTF-446, Rev. 3 Containment Isolation Valves (Atmosperic, Subatmospheric, Ice Condenser, and Dual)

B 3.6.3 of maintaining the boundary between the contained fluid and the containment or outside atmosphere. The method of isolation must include the use of at least one isolation barrier that cannot be adversely affected by a single active failure. Isolation barriers that meet this criterion are a closed and de-activated automatic containment isolation valve, a closed manual valve, a blind flange, and a check valve with flow through the valve secured. For a penetration flow path isolated in accordance with Required Action B.1, the device used to isolate the penetration should be the closest available one to containment. Required Action B.1 must be completed within [the Completion Time specified for each Category of containment isolation valve identified in [a licensee controlled document]. The Completion Time is justified in Reference 4.

REVIEWERS NOTE ------------------------------------

Conditions A and B may be combined into one Condition that addresses both the containment isolation valve pressure boundary intact and containment isolation valve pressure boundary not intact by specifying the limiting Completion Time for each configuration identified in Tables D-1, D-2, and D-3 of Reference 4.

The plant specific determination of the containment isolation valve Completion Time categories is performed by comparing the plant specific penetration types to the generic penetration types evaluated that are identified in Tables D-1, D-2, and D-3 of Reference 4.

The plant specific application of the generic analysis that justified the generic Completion Time categories is discussed in Section 9.0 of Reference 4.

Plant specific Completion Time categories may also be calculated in lieu of the generic Completion Time categories. This approach is discussed in Section 10.0 of Reference 4.

For plants not adopting the risk-informed extended Completion Time for containment isolation valves, a Completion Time of 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months is maintained.

The 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Completion Time is reasonable, considering the time required to isolate the penetration and the relative importance of supporting containment OPERABILITY during MODES 1, 2, 3, and 4. A Condition for one or more penetration flow paths with one containment isolation valve inoperable for penetrations with one containment isolation valve and a closed system would be required.

For affected penetration flow paths that cannot be restored to OPERABLE status within the specified Completion Time and that have been isolated in accordance with Required Action B.1, the affected penetration flow paths must be verified to be isolated on a periodic basis.

This is necessary to ensure that containment penetrations required to be isolated following an accident and no longer capable of being automatically isolated, will be in an isolated position should an event WOG STS B 3.6.3-8 Rev. 3.0, 03/31/04

TSTF-446, Rev. 3 Containment Isolation Valves (Atmosperic, Subatmospheric, Ice Condenser, and Dual)

B 3.6.3 occur. This Required Action does not require any testing or device manipulation. Rather, it involves verification that those isolation devices outside containment and capable of being mispositioned, are in the correct position. The Completion Time of "once per 31 days for isolation devices outside containment" is appropriate considering the fact that the devices are operated under administrative controls and the probability of their misalignment is low. For isolation devices inside containment, the time period specified as "prior to entering MODE 4 from MODE 5 if not performed within the previous 92 days" is based on engineering judgment, and is considered reasonable in view of the inaccessibility of the isolation devices and other administrative controls that will ensure that isolation device misalignment is an unlikely possibility.

Required Action B.2 is modified by two Notes. Note 1 applies to isolation devices located in high radiation areas and allows these devices to be verified closed by use of administrative means. Allowing verification by administrative means is considered acceptable, since access to these areas is typically restricted. Note 2 applies to isolation devices that are locked, sealed, or otherwise secured in position and allows these devices to be verified closed by use of administrative means. Allowing verification by administrative means is considered acceptable, since the function of locking, sealing, or securing components is to ensure that the devices are not inadvertently repositioned. Therefore, the probability of misalignment of these devices once they have been verified to be in the proper position is small. ]

BC.1 With two [or more] containment isolation valves in one or more penetration flow paths inoperable, [except for purge valve or shield building bypass leakage not within limit,] the affected penetration flow path must be isolated within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . The method of isolation must include the use of at least one isolation barrier that cannot be adversely affected by a single active failure. Isolation barriers that meet this criterion are a WOG STS B 3.6.3-9 Rev. 3.0, 03/31/04

TSTF-446, Rev. 3 Containment Isolation Valves (Atmosperic, Subatmospheric, Ice Condenser, and Dual)

B 3.6.3 BASES ACTIONS (continued) closed and de-activated automatic valve, a closed manual valve, and a blind flange. The 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Completion Time is consistent with the ACTIONS of LCO 3.6.1. In the event the affected penetration is isolated in accordance with Required Action B.1C.1, the affected penetration must be verified to be isolated on a periodic basis per Required Action A.2 or B.2, which remains in effect. This periodic verification is necessary to assure leak tightness of containment and that penetrations requiring isolation following an accident are isolated. The Completion Time of once per 31 days for verifying each affected penetration flow path is isolated is appropriate considering the fact that the valves are operated under administrative control and the probability of their misalignment is low.

Condition CB is modified by a Note indicating this Condition is only applicable to penetration flow paths with two [or more] containment isolation valves. Condition A of this LCO addresses the condition of one containment isolation valve inoperable in this type of penetration flow path.

C.1 and C.2 With one or more penetration flow paths with one containment isolation valve inoperable, the inoperable valve flow path must be restored to OPERABLE status or the affected penetration flow path must be isolated.

The method of isolation must include the use of at least one isolation barrier that cannot be adversely affected by a single active failure.

Isolation barriers that meet this criterion are a closed and de-activated automatic valve, a closed manual valve, and a blind flange. A check valve may not be used to isolate the affected penetration flow path.

Required Action C.1 must be completed within the 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Completion Time. The specified time period is reasonable considering the relative stability of the closed system (hence, reliability) to act as a penetration isolation boundary and the relative importance of maintaining containment integrity during MODES 1, 2, 3, and 4. In the event the affected penetration flow path is isolated in accordance with Required Action C.1, the affected penetration flow path must be verified to be isolated on a periodic basis. This periodic verification is necessary to assure leak tightness of containment and that containment penetrations requiring isolation following an accident are isolated. The Completion Time of once per 31 days for verifying that each affected penetration flow path is isolated is appropriate because the valves are operated under administrative controls and the probability of their misalignment is low.

WOG STS B 3.6.3-10 Rev. 3.0, 03/31/04

TSTF-446, Rev. 3 Containment Isolation Valves (Atmosperic, Subatmospheric, Ice Condenser, and Dual)

B 3.6.3 BASES ACTIONS (continued)

Condition C is modified by a Note indicating that this Condition is only applicable to those penetration flow paths with only one containment isolation valve and a closed system. The closed system must meet the requirements of Ref. 3. This Note is necessary since this Condition is written to specifically address those penetration flow paths in a closed system.

Required Action C.2 is modified by two Notes. Note 1 applies to valves and blind flanges located in high radiation areas and allows these devices to be verified closed by use of administrative means. Allowing verification by administrative means is considered acceptable, since access to these areas is typically restricted. Note 2 applies to isolation devices that are locked, sealed, or otherwise secured in position and allows these devices to be verified closed by use of administrative means. Allowing verification by administrative means is considered acceptable, since the function of locking, sealing, or securing components is to ensure that these devices are not inadvertently repositioned. Therefore, the probability of misalignment of these valves, once they have been verified to be in the proper position, is small.

D.1

REVIEWERS NOTE ------------------------------------

The analysis in Reference 4 evaluated each CIV in each penetration individually and determines an acceptable Completion Time based on the ICLERP and LERF for each CIV. It is assumed that only a single CIV is inoperable in one penetration flow path. If plant specific analyses are performed to evaluate multiple inoperable CIVs in separate penetration flow paths, Condition D should be revised to reflect the plant specific analyses.

In the event one containment isolation valve in two or more penetration flow paths is inoperable [except for purge valve or shield building bypass leakage not within limit], all but one of the affected penetration flow path(s) must be isolated. The method of isolation must include the use of at least one isolation barrier that cannot be adversely affected by a single active failure. Isolation barriers that meet this criterion are a closed and de-activated automatic containment isolation valve, a closed manual valve, a blind flange, and a check valve with flow through the valve secured. For a penetration flow path isolated in accordance with Required Action D.1, the device used to isolate the penetration should be the closest available one to containment. Required Action D.1 must be completed within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . For subsequent containment isolation valve inoperabilities, the Required Action and Completion Time continue to apply to each additional containment isolation valve inoperability, with the Completion Time based on each subsequent entry into the Condition WOG STS B 3.6.3-11 Rev. 3.0, 03/31/04

TSTF-446, Rev. 3 Containment Isolation Valves (Atmosperic, Subatmospheric, Ice Condenser, and Dual)

B 3.6.3 consistent with Note 2 to the ACTIONS Table (e.g., for each entry into the Condition). Each containment isolation valve(s) that is (are) declared inoperable for subsequent Condition D entries shall meet the Required Action and Completion Time. For the penetration flow paths isolated in accordance with Required Action D.1, the affected penetration(s) must be verified to be isolated on a periodic basis per Required Action A.2 [or B.2], which remains in effect. This periodic verification is necessary to assure that the penetrations requiring isolation following an accident are isolated. The 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Completion Time is reasonable, considering the time required to isolate the penetration and the relative importance of supporting Containment OPERABILITY during MODES 1, 2, 3, and 4.

[ DE.1 With the shield building bypass leakage rate (SR 3.6.3.11) [or purge valve leakage rate (SR 3.6.3.7)] not within limit, the assumptions of the safety analyses are not met. Therefore, the leakage must be restored to within limit. Restoration can be accomplished by isolating the penetration(s) that caused the limit to be exceeded by use of one closed and de-activated automatic valve, closed manual valve, or blind flange. When a penetration is isolated the leakage rate for the isolated penetration is assumed to be the actual pathway leakage through the isolation device.

If two isolation devices are used to isolate the penetration, the leakage rate is assumed to be the lesser actual pathway leakage of the two devices. The 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Completion Time for shield building bypass leakage is reasonable considering the time required to restore the leakage by isolating the penetration(s) and the relative importance of secondary containment bypass leakage to the overall containment function. [The 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Completion time for purge valve leakage is acceptable considering the purge valves remain closed so that a gross breach of the containment does not exist.]

WOG STS B 3.6.3-12 Rev. 3.0, 03/31/04

TSTF-446, Rev. 3 Containment Isolation Valves (Atmosperic, Subatmospheric, Ice Condenser, and Dual)

B 3.6.3 BASES ACTIONS (continued)

REVIEWERS NOTE-----------------------------------

[The bracketed options provided in ACTION D E reflect options in plant design and options in adopting the associated leakage rate Surveillances.

The options (in both ACTION D E and ACTION EF) for purge valve leakage, are based primarily on the design - if leakage rates can be measured separately for each purge valve, ACTION E F is intended to apply. This would be required to be able to implement Required Action EF.3. Should the design allow only for leak testing both purge valves simultaneously, then the Completion Time for ACTION D E should include the "24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for purge valve leakage" and ACTION E F should be eliminated.] ]

[ EF.1, EF.2, and EF.3 In the event one or more containment purge valves in one or more penetration flow paths are not within the purge valve leakage limits, purge valve leakage must be restored to within limits, or the affected penetration flow path must be isolated. The method of isolation must be by the use of at least one isolation barrier that cannot be adversely affected by a single active failure. Isolation barriers that meet this criterion are a [closed and de-activated automatic valve, closed manual valve, or blind flange]. A purge valve with resilient seals utilized to satisfy Required Action EF.1 must have been demonstrated to meet the leakage requirements of SR 3.6.3.7. The specified Completion Time is reasonable, considering that one containment purge valve remains closed so that a gross breach of containment does not exist.

In accordance with Required Action EF.2, this penetration flow path must be verified to be isolated on a periodic basis. The periodic verification is necessary to ensure that containment penetrations required to be isolated following an accident, which are no longer capable of being automatically isolated, will be in the isolation position should an event occur. This Required Action does not require any testing or valve manipulation.

Rather, it involves verification that those isolation devices outside containment capable of being mispositioned are in the correct position.

For the isolation devices inside containment, the time period specified as "prior to entering MODE 4 from MODE 5 if not performed within the previous 92 days" is based on engineering judgment and is considered reasonable in view of the inaccessibility of the isolation devices and other administrative controls that will ensure that isolation device misalignment is an unlikely possibility.

WOG STS B 3.6.3-13 Rev. 3.0, 03/31/04

TSTF-446, Rev. 3 Containment Isolation Valves (Atmosperic, Subatmospheric, Ice Condenser, and Dual)

B 3.6.3 BASES ACTIONS (continued)

For the containment purge valve with resilient seal that is isolated in accordance with Required Action EF.1, SR 3.6.3.7 must be performed at least once every [92] days. This assures that degradation of the resilient seal is detected and confirms that the leakage rate of the containment purge valve does not increase during the time the penetration is isolated.

The normal Frequency for SR 3.6.3.7, 184 days, is based on an NRC initiative, Generic Issue B-20 (Ref. 45). Since more reliance is placed on a single valve while in this Condition, it is prudent to perform the SR more often. Therefore, a Frequency of once per [92] days was chosen and has been shown to be acceptable based on operating experience.

Required Action EF.2 is modified by two Notes. Note 1 applies to isolation devices located in high radiation areas and allows these devices to be verified closed by use of administrative means. Allowing verification by administrative means is considered acceptable, since access to these areas is typically restricted. Note 2 applies to isolation devices that are locked, sealed, or otherwise secured in position and allows these devices to be verified closed by use of administrative means. Allowing verification by administrative means is considered acceptable, since the function of locking, sealing, or securing components is to ensure that these devices are not inadvertently repositioned. ]

FG.1 and FG.2 If the Required Actions and associated Completion Times are not met, the plant must be brought to a MODE in which the LCO does not apply.

To achieve this status, the plant must be brought to at least MODE 3 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and to MODE 5 within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . The allowed Completion Times are reasonable, based on operating experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant systems.

SURVEILLANCE [ SR 3.6.3.1 REQUIREMENTS Each [42] inch containment purge valve is required to be verified sealed closed at 31 day intervals. This Surveillance is designed to ensure that a gross breach of containment is not caused by an inadvertent or spurious opening of a containment purge valve. Detailed analysis of the purge valves failed to conclusively demonstrate their ability to close during a LOCA in time to limit offsite doses. Therefore, these valves are required to be in the sealed closed position during MODES 1, 2, 3, and 4. A WOG STS B 3.6.3-14 Rev. 3.0, 03/31/04

TSTF-446, Rev. 3 Containment Isolation Valves (Atmosperic, Subatmospheric, Ice Condenser, and Dual)

B 3.6.3 BASES SURVEILLANCE REQUIREMENTS (continued) containment purge valve that is sealed closed must have motive power to the valve operator removed. This can be accomplished by de-energizing the source of electric power or by removing the air supply to the valve operator. In this application, the term "sealed" has no connotation of leak tightness. The Frequency is a result of an NRC initiative, Generic Issue B-24 (Ref. 56), related to containment purge valve use during plant operations. In the event purge valve leakage requires entry into Condition E, the Surveillance permits opening one purge valve in a penetration flow path to perform repairs. ]

[ SR 3.6.3.2 This SR ensures that the minipurge valves are closed as required or, if open, open for an allowable reason. If a purge valve is open in violation of this SR, the valve is considered inoperable. If the inoperable valve is not otherwise known to have excessive leakage when closed, it is not considered to have leakage outside of limits. The SR is not required to be met when the minipurge valves are open for the reasons stated. The valves may be opened for pressure control, ALARA or air quality considerations for personnel entry, or for Surveillances that require the valves to be open. The minipurge valves are capable of closing in the environment following a LOCA. Therefore, these valves are allowed to be open for limited periods of time. The 31 day Frequency is consistent with other containment isolation valve requirements discussed in SR 3.6.3.3. ]

SR 3.6.3.3 This SR requires verification that each containment isolation manual valve and blind flange located outside containment and not locked, sealed, or otherwise secured and required to be closed during accident conditions is closed. The SR helps to ensure that post accident leakage of radioactive fluids or gases outside of the containment boundary is within design limits. This SR does not require any testing or valve manipulation. Rather, it involves verification that those containment isolation valves outside containment and capable of being mispositioned are in the correct position. Since verification of valve position for containment isolation valves outside containment is relatively easy, WOG STS B 3.6.3-15 Rev. 3.0, 03/31/04

TSTF-446, Rev. 3 Containment Isolation Valves (Atmosperic, Subatmospheric, Ice Condenser, and Dual)

B 3.6.3 BASES SURVEILLANCE REQUIREMENTS (continued)

SR 3.6.3.5 Verifying that the isolation time of each automatic power operated containment isolation valve is within limits is required to demonstrate OPERABILITY. The isolation time test ensures the valve will isolate in a time period less than or equal to that assumed in the safety analyses.

[The isolation time and Frequency of this SR are in accordance with the Inservice Testing Program or 92 days.]

[ SR 3.6.3.6 In subatmospheric containments, the check valves that serve a containment isolation function are weight or spring loaded to provide positive closure in the direction of flow. This ensures that these check valves will remain closed when the inside containment atmosphere returns to subatmospheric conditions following a DBA. SR 3.6.3.6 requires verification of the operation of the check valves that are testable during unit operation. The Frequency of 92 days is consistent with the Inservice Testing Program requirement for valve testing on a 92 day Frequency. ]

[ SR 3.6.3.7 For containment purge valves with resilient seals, additional leakage rate testing beyond the test requirements of 10 CFR 50, Appendix J, Option

[A][B], is required to ensure OPERABILITY. Operating experience has demonstrated that this type of seal has the potential to degrade in a shorter time period than do other seal types. Based on this observation and the importance of maintaining this penetration leak tight (due to the direct path between containment and the environment), a Frequency of 184 days was established as part of the NRC resolution of Generic Issue B-20, "Containment Leakage Due to Seal Deterioration" (Ref. 45).

Additionally, this SR must be performed within 92 days after opening the valve. The 92 day Frequency was chosen recognizing that cycling the valve could introduce additional seal degradation (beyond that occurring to a valve that has not been opened). Thus, decreasing the interval (from 184 days) is a prudent measure after a valve has been opened. ]

WOG STS B 3.6.3-17 Rev. 3.0, 03/31/04

TSTF-446, Rev. 3 Containment Isolation Valves (Atmosperic, Subatmospheric, Ice Condenser, and Dual)

B 3.6.3 BASES REFERENCES 1. FSAR, Section [15].

2. FSAR, Section [6.2].

3. Standard Review Plan 6.2.4.

4. WCAP-15791-A, Rev. 2, "Risk-Informed Evaluation of Exensions to Containment Isolation Valve Completion Times," [Date to be supplied later].

45. Generic Issue B-20, "Containment Leakage Due to Seal Deterioration."

56. Generic Issue B-24.

WOG STS B 3.6.3-20 Rev. 3.0, 03/31/04

TSTF-08-04, TSTF-446, Revision 3, Risk Informed Evaluation of Extensions to Containment Isolation Valve Completion Times (WCAP-15791).

Contents

Text

SUBJECT:

Dear Sir or Madam:

Contact:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

1.0 DESCRIPTION

2.0 PROPOSED CHANGE

3.0 BACKGROUND

4.0 TECHNICAL ANALYSIS

5.0 REGULATORY ANALYSIS

6.0 ENVIRONMENTAL CONSIDERATION

7.0 REFERENCES

Navigation menu

TSTF-08-04, TSTF-446, Revision 3, Risk Informed Evaluation of Extensions to Containment Isolation Valve Completion Times (WCAP-15791).

Text

SUBJECT:

Dear Sir or Madam:

Contact:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

1.0 DESCRIPTION

2.0 PROPOSED CHANGE

3.0 BACKGROUND

4.0 TECHNICAL ANALYSIS

5.0 REGULATORY ANALYSIS

6.0 ENVIRONMENTAL CONSIDERATION

7.0 REFERENCES

Navigation menu

Search