ML041740723

Technical Specification (TS) Amendment to Section 3.6.3, Containment Isolation Valves and the Associated Bases Section

ML041740723
Person / Time
Site:	Catawba
Issue date:	06/10/2004
From:	Jamil D Duke Power Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML041740723 (24)

Text

Duke D.M. JAMIL A Power, Vice President A Duke Energy Company Duke Power Catawba Nuclear Station 4800 Concord Rd. / CNOI VP York, SC 29745-9635 803 831 4251 803 831 3221 fax June 10, 2004 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555

Subject:

Duke Energy Corporation Catawba Nuclear Station (CNS), Units 1 and 2 Docket Numbers 50-413 and 50-414 Technical Specification (TS) Amendment to Section 3.6.3, "Containment Isolation Valves" and the associated Bases section.

Pursuant to 10 CFR 50.90, Duke is requesting amendments to Technical Specifications (TS) Section 3.6.3, "Containment Isolation Valves". This amendment change will revise Surveillance Requirement (SR) 3.6.3.6 and the associated Bases section to allow the required frequency of the SR to be specified in the Containment Leak Rate Testing Program.

This license amendment request was developed based on information listed on Attachment 5 of this document. This attachment contains the results of past leak rate tests for the valves controlled by this SR. These test results show no adverse leakage results have occurred since 1999 for the Hydrogen Purge (VY)

System and Containment Air Release and Addition (VQ) System valves and since 1998 for the Containment Purge (VP) System valves.

This license amendment is similar to the December 7, 2001 McGuire submittal, which was approved as amendments 207/188. Pages in the McGuire submittal.noted a .deviation from the March 1, 2001 Catawba submittal. These pages, concerning-SR 3.6.3.6, are being revised in this Catawba submittal to be consistent with the NRC-approved McGuire submittal.

This license amendment is consistent with the guidance contained in Technical Specification Task Force (TSTF)-52, Revision 3.

I Co0 www. duke-energy. corn

U.S. Nuclear Regulatory Commission Page 2 June 10, 2004 Duke is requesting that the NRC review and approve the enclosed license amendment request no later than December 2004 to reduce the testing work load on the site.

Implementation of this amendment will not impact the Catawba Updated Final Safety Analysis Reports (UFSAR).

Duke Energy Corporation has determined that a 30-day implementation period would be acceptable in order to revise surveillances with minimum impact on scheduling.

In accordance with Duke administrative procedures and the Quality Assurance Program Topical Report, the proposed amendment has been previously reviewed and approved by the CNS Plant Operations Review Committee and on an overall basis by the Duke Nuclear Safety Review Board.

The contents of this amendment request package are as follows:

1. Attachment 1 provides marked copies of the affected TS and TS Bases pages for Catawba showing the proposed changes.

2. Attachment 2 provides a description of the proposed changes and technical justification.

3. Pursuant to 10 CFR 50.92, Attachment 3 documents the determination that the amendments contain No Significant Hazards Considerations.

4. Pursuant to 10 CFR 51.22(c)(9), Attachment 4 provides the basis for the categorical exclusion from performing an Environmental Assessment/Impact Statement.

5.Attachment 5 provides data for the Catawba Unit 1 and Unit 2 Containment Purge (VP) System, Hydrogen Purge (VY) System, and Containment Air Release and Addition System (VQ) Valve Leakage.

Pursuant to 10 CFR 50.91, copies of this proposed amendment are being sent to the appropriate state officials.

There are no regulatory commitments contained in this letter or its attachments.

U.S. Nuclear Regulatory Commission Page 3 June 10, 2004 Inquiries on this matter should be directed to A.P Jackson at (803) 831-3742.

Very truly yours, Dhiaa M. Jamil Site Vice President Catawba Nuclear Station APJ/apj Attachments

U.S. Nuclear Regulatory Commission Page 4 June 10, 2004 Dhiaa M. Jamil affirms that he is the person who subscribed his name to the foregoing statement, and that all the matters and facts set forth herein are true and correct to the best of his knowledge.

Dhiaa M. Jamil, Site Vice President, Catawba Nuclear Station Subscribed and sworn to me:

Date Notary Public MY COMMISSION EXPIRES My commission expires: MARCH 27, 2008 Date SEAL

U.S. Nuclear Regulatory Commission Page 5 June 10, 2004 xc (with attachments):

W.D. Travers U.S. Nuclear Regulatory Commission Regional Administrator, Region II Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, GA 30303 E.F. Guthrie Senior Resident Inspector (CNS)

U.S. Nuclear Regulatory Commission Catawba Nuclear Station S. E. Peters NRC Project Manager (CNS)

U. S. Nuclear Regulatory Commission Mail Stop 0-8 G9 Washington, DC 20555-0001 H. J. Porter, Director Division of Radioactive Waste Management Bureau of Land and Waste Management Department of Health and Environmental Control 2600 Bull St.

Columbia, SC 29201

ATTACHMENT 1 MARKED-UP TS AND TS BASES PAGES FOR CATAWBA

INSERTS Insert 1 for TS 3.6.3, (SR 3.6.3.6):

In accordance with the Containment Leakage Rate Testing Program.

Insert 2 for Bases 3.6.3 For the Containment Purge (VP) System valves with resilient seals, additional leakage rate testing beyond the test requirements of 10 CFR 50, Appendix J, Option B is required to ensure operability. The measured leakage rate for the containment purge valves must be < 0.05 La when pressurized to Pa. Operating experience has demonstrated that this type of seal has the potential to degrade in a shorter time period than 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), these valves will not be placed on the maximum extended test interval, but tested on the nominal test interval in accordance with the Containment Leakage Rate Testing Program.

The Containment Air Release and Addition (VQ) System and the Hydrogen Purge (VY) System valves have a demonstrated history of acceptable leakage. The measured leakage rate for containment air release and addition valves must be < 0.01 La when pressurized to Pa. The measured leakage rate for hydrogen purge valves must be < 0.05 La when pressurized to Pa. These valves will be tested in accordance with 10CFR50, Appendix J, Option B.

If at any time the leakage deteriorates to unacceptable levels, the frequency will be reduced until acceptable leakage performance is demonstrated and extended interval testing can resume.

Containment Isolation Valves 3.6.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.3.4 - -- -------------- NOTE------------------------------------

Valves and blind flanges in high radiation areas may be verified by use of administrative means.

Verify each containment isolation manual valve and blind Prior to entering flange that is located inside containment or annulus and MODE 4 from not locked, sealed, or otherwise secured and required to MODE 5 if not be closed during accident conditions is closed, except for performed within containment isolation valves that are open under the previous 92 days administrative controls.

SR 3.6.3.5 Verify the isolation time of automatic power operated In accordance with containment isolation valve is within limits. the Inservice Testing Program SR 3.6.3.6 Perform leakage rate testing for Containment Purge I B days System, Hydrogen Purge System, and Containment Air Release and Addition System valves with resilient seals. AND within op daya afte op1i Delete and valen_

SR 3.6.3.7 Verify each automatic containment isolation valve that is 18 months not locked, sealed or otherwise secured in position, actuates to the isolation position on an actual or simulated actuation signal.

(continued)

Catawba Units 1 and 2 3.6.3-6 Amendment Nos. 1 -73116

Containment Isolation Valves 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 is specified in the UFSAR and the Frequency of this SR is in accordance with the Inservice Testing Program.

SR 3.6.3.6 For valvS with resilient sealS, additional Icakage rate testing beyond the teSt requirements of 10 CFR 50, AppeRndix J, Option B, is requred to encure OPERABILITY. The measured leakagc rate for Containment PuFge System and Hydrogon Purgc System valves must be 5 0.05 La wheR prcsrurrizod to P. The measured akage rate fr nt-net Air Release and Addition valves must be ! 0.01 6 when presrized to P2 Operating experionce has demonstrated that this typo of seal has the potential to degrado in a shorter time period than do other seal typcs.

Based oR this obserpation and the impeortaRe of manrta-RinR thir penetration leak tight (due to the direct path betwecn Gontainmcnt and the eRVironmeRt), a Frequency of 181 days was established.

Delete and Insert 2 The Containment Air Release and Addition System valves may be used during normal operation, therefore, in ad-dition to the 181 day Frequency, this SR must be peformed every 02 days after opening the valves. The 02 day F=requeny was rognizing that cycGiRn the valve could introduce additional seal degradation (beyond that occurring to a valve thdat has net been opened). Thus, deesn the inter'.al (4from 181 days) ie a prudont measure after a valve has been opened. The CoRtainment Purge and Hydrogen Purge System valves remain closed during normal operation and this SR is only performcd overy 184 days for these valve.

SR 3.6.3.7 Automatic containment isolation valves close on a containment isolation signal to prevent leakage of radioactive material from containment following a DBA. This SR ensures that each automatic containment isolation valve will actuate to its isolation position on a containment Catawba Units 1 and 2 B 3.6.3-1 3 Revision No. H

ATTACHMENT 2 DESCRIPTION OF PROPOSED CHANGES AND TECHNICAL JUSTIFICATION

DESCRIPTION OF PROPOSED CHANGES AND TECHNICAL JUSTIFICATION Background Information:

In March 2001 Catawba Nuclear Station submitted an amendment to allow implementation of 10CFR50, Appendix J, Option B, which governs performance based containment leakage testing requirements for Types B and C testing. In December of 2001 the McGuire Nuclear Station issued a similar amendment based on 1'OCFR50, Appendix J, Option B. It was understood for both of these amendments that for certain containment valves with resilient seals, additional leakage rate testing beyond the test requirements of 10CFR50, Appendix J, Option B would be required to ensure operability. At that time Catawba did not wish to change the surveillance interval for these valves with resilient seals as specified in SR 3.6.3.6. However, McGuire's submittal did revise SR 3.6.3.6 to allow the interval to be "specified in accordance with the Containment Leakage Rate Testing Program."

Subsequently, the test results at Catawba have demonstrated that the test interval of 184 days is conservative.

Therefore, Catawba is proposing a revision of SR 3.6.3.6 to specify that the test interval be: "In accordance with the Containment Leakage Rate Testing Program."

Description of Proposed Changes:

Duke Energy Corporation is proposing to revise Technical Specification Surveillance Requirement (SR) 3.6.3.6 and the associated Bases section. The following acronyms defined here will be used below: La (Design Leakage Rate)'and Pa (Design Containment Pressure).

The specific revision is as follows:

SR 3.6.3.6 currently states:

"Perform leakage rate testing for Containment Purge System, Hydrogen Purge System, and Containment Air Release and Addition System valves with resilient seals."

This has a frequency of once every "184 days and within 92 days after opening the valve."

This amendment would change the frequency to read:

"In accordance with the Containment Leakage Rate Testing Program.

ATTACHMENT 2 Page 1 of 4

The Bases for SR 3.6.3.6 will be deleted and replaced with the following paragraphs:

For the Containment Purge (VP) System valves with resilient seals, additional leakage rate testing beyond the test requirements of 10 CFR 50, Appendix J, Option B is required to ensure operability. The measured leakage rate for the containment purge valves must be < 0.05 La when pressurized to Pa. Operating experience has demonstrated that this type of seal has the potential to degrade in a shorter time period than 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), these valves will not be placed on the maximum extended test interval, but tested on the nominal test interval in accordance with the Containment Leakage Rate Testing Program.

The Containment Air Release and Addition (VQ) System and the Hydrogen Purge (VY) System valves have a demonstrated history of acceptable leakage. The measured leakage rate for containment air release and addition valves must be <

0.01 La when pressurized to Pa. The measured leakage rate for hydrogen purge valves must be < 0.05 La when pressurized to Pa. These valves will be tested in accordance with 10CFR50, Appendix J, Option B. If at any time the leakage deteriorates to unacceptable levels, the frequency will be reduced until acceptable leakage performance is demonstrated and extended interval testing can resume.

Regulatory Requirements and General Discussion Technical Justification:

Each Unit 1 and 2 Containment Purge Ventilation (VP) System contains nine containment penetrations (M456, M432, M357, M434, M368, M433, M119, M213, and M140). Each penetration contains redundant containment isolation valves. The valves are pneumatic operated butterfly valves with resilient seals. During normal plant operations, these valves are administratively locked closed by de-energizing their solenoid valves (SR 3.6.3.1). The valves are only opened during cold shutdown and refueling activities. During core alterations or movement of irradiated fuel assemblies within containment, these penetrations can only be open if they are ATTACHMENT 2 Page 2 of 4

exhausting through an operable Containment Purge Exhaust System (Technical Specification 3.9.3).

Each Unit 1 and 2 Hydrogen Purge (VY) System contains two containment penetrations (M332 and M346). Each penetration contains redundant containment isolation valves. Three of these valves are motor operated gate valves with soft seats and one is a passive check valve. During normal plant operations, the motor operated gate valves are administratively locked closed by de-energizing their actuators (SR 3.6.3.1). The passive check valve located inside the containment maintains a closed position since the blower is not placed in operation. The Hydrogen Purge System containment isolation valves are only opened during cold shutdown or no mode activities. The Hydrogen Purge System containment isolation valves are maintained in a closed position during core alterations or movement of irradiated fuel assemblies within the containment (Technical Specification 3.9.3).

Each Unit 1 and Unit 2 Containment Air Release and Addition (VQ) System contains two penetrations (M204 and M386). Each penetration contains redundant containment isolation valves.

These are gate and diaphragm valves. The VQ System is designed to provide a means of controlling the containment pressure between 0.3 psig and -0.1 psig during normal plant operations including start-up and shutdown transients.

Containment pressure fluctuations due to postulated accidents are mitigated by safety related systems, rather than the Containment Air Release and Addition System. The Containment isolation valves will automatically shut upon receipt of a Phase "Am containment isolation to prevent containment air from being purged to the atmosphere during a Design Basis Event. Technical Specification 3.3.6 discusses the isolation instrumentation for this system.

The surveillance interval extensions being sought are supported by the leakage history. Attachment 5 is a leakage summary for the VP, VQ, and VY Systems.

The administrative leakage limits for the VP valves are 420 standard cubic centimeters per minute (sccm) for the 12 inch diameter valves and 840 sccm for the 24 inch diameter valves. These administrative limits were not challenged during the period reviewed. Acceptable leakage is confirmed prior to entry into mode 4. In modes 1-4, the VP valves are closed with power removed per Technical Specification SR 3.6.3.1. Degradation from valve operation is a major mechanism which contributes to resilient seal degradation.

By limiting valve manipulation in modes 1 through 4, ATTACHMENT 2 Page 3 of 4

susceptibility to this mechanistic failure mode has been limited. A test interval of 18 months would be acceptable for the VP valves based upon the operational limits imposed by the Technical Specifications and historical leakage data.

Leakage history for the VY System valves with resilient seals supports interval extension. These are 4 inch check and gate valves that have exhibited minimal leakage as indicated in Attachment 5. The administrative leakage limit is 1200 sccm for gate valves and 2400 sccm for check valves.

In modes 1-4, the VY valves are closed with power removed per Technical Specification SR 3.6.3.1. Degradation from valve operation is a major mechanism which contributes to resilient seal degradation. By limiting valve manipulation in modes 1 through 4, susceptibility to this mechanistic failure mode has been limited. As shown on Attachment 5, these valves have an excellent leakage history; therefore extending the test interval beyond the current limit is justified. These valves will be evaluated for extended test intervals using the Containment Leakage Rate Testing Program, which is based on 10CFR50, Appendix J, Option B.

Leakage history for the VQ System valves with resilient seals also supports interval extension. These are 4 inch diameter diaphragm valves that have exhibited minimal leakage as indicated in Attachment 5. The administrative leakage limit for the VQ power operated diaphragm valves is 690 sccm. As shown on Attachment 5, these valves have an excellent leakage history; therefore extending the test interval beyond the current limit is justified. These valves will be evaluated for extended test intervals using the Containment Leakage Rate Testing Program, which is based on 10CFR50, Appendix J, Option B.

ATTACHMENT 2 Page 4 of 4

ATTACHMENT 3 NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION

NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION Requested Change:

Revision of Technical Specification (TS) Section 3.6.3, "Containment Isolation Valves" and Associated Bases No Significant Hazards Determination:

The following discussion is a summary of the evaluation of the changes contained in these proposed amendments against the 10 CFR 50.92(c) requirements to demonstrate that all three standards are satisfied. A no significant hazards consideration is indicated if operation of the facility in accordance with the proposed amendments would not:

1. Involve a significant increase in the probability or consequences of an accident previously evaluated, or

2. Create the possibility of a new or different kind of accident from any accident previously evaluated, or

3. Involve a significant reduction in a margin of safety.

First Standard Does the change involve a significant increase in the probability or consequences of an accident previously evaluated?

No.

This amendment will not change any previously evaluated accidents such as the postulated "Fuel Handling Accident (FHA) in Containment". No credit is assumed for VP containment isolation in the FHA within containment. The Containment Purge (VP) System and Hydrogen Purge (VY) System containment isolation valves are sealed closed during modes 1 through 4. The Containment Air Release and Addition (VQ)

System containment isolation valves are designed to close within 5 seconds of a containment phase "Am isolation signal. The prevention and mitigation of these accidents is not affected by this change.

Test data demonstrates that the likelihood of a malfunction of a resilient seal in one of the VP, VY, or VQ valves is not increased by this change in the surveillances. The systems will continue to be able to perform their design functions of isolating containment during the evaluated accidents. Test procedures will continue to monitor the ATTACHMENT 3 Page 1 of 2

leakage of these valves to ensure the design function will continue to be met. There is no impact on previously evaluated accidents since the valves will continue to close and seal or remain closed as originally assumed in the accident scenarios.

Therefore, the changes do not involve a significant increase in the probability or consequences of an accident previously evaluated.

Second Standard Does the change create the possibility of a new or different kind of accident from any accident previously evaluated?

No.

This change does not involve a physical alteration to the plant (i.e., no new or different type of equipment will be installed) or a change in the methods governing any normal plant operation. The change does not alter assumptions made in the safety analyses or licensing basis. This change will not affect or degrade the ability of the Containment Purge System, Hydrogen Purge System, or Containment Air Release and Addition System valves to perform their specified safety functions. Therefore, the change does not create the possibility of a new or different kind of credible accident from any accident previously evaluated.

Third Standard Does the proposed change involve a significant reduction in a margin of safety?

No.

SR 3.6.3.6 currently states: "The measured leakage rate for Containment Purge System and Hydrogen Purge System valves must be < 0.05 La (Design Leakage Rate) when pressurized to Pa (Design Containment Pressure). The measured leakage rate for Containment Air Release and Addition valves must be <

0.01 La when pressurized to Pa. These required maximum leak rates will not be changed by this amendment. Testing of these valves to measure leakage through the valve seats will continue, only at a different frequency based on past test results. This will be a nominal frequency of 18 months for the VP System and in accordance with 10CFR50, Appendix J, Option B for the VQ and VY Systems. Therefore, the proposed changes listed above do not involve a significant reduction in a margin of safety.

ATTACHMENT 3 Page 2 of 2

ATTACHMENT 4 ENVIRONMENTAL IMPACT STATEMENT CONSIDERATION

ENVIRONMENTAL IMPA&T STATEMENT CONSIDERATION Pursuant to 10 CFR 51.22(b), an evaluation of this license amendment request has been performed to determine whether or not it meets the criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9) of the regulations.

This amendment revises Technical Specification (TS)

Section 3.6.3, Containment Isolation Valves. The change revises the required frequency of Surveillance Requirement (SR) 3.6.3.6 for the Containment Purge System, Hydrogen Purge System, and Containment Air Release and Addition System valves with resilient seals from "184 days and within 92 days after opening the valve" to be a frequency specified in accordance with the Containment Leakage Rate Testing Program. The amount of allowable leakage from these valves is not altered by this change.

Implementation of this amendment will have no adverse impact upon the Catawba units; neither will it contribute to any additional quantity or type of effluent being available for adverse environmental impact or personnel exposure.

It has been determined there is:

1. No significant hazards consideration,

2. No significant change in the types, or significant increase in the amounts, of any effluents that may be released offsite, and

3. No significant increase in individual or cumulative occupational radiation exposures involved.

Therefore, this amendment to the Catawba Technical Specifications and associated bases meets the criteria of 10 CFR 51.22(c)(9) for categorical exclusion from an environmental impact statement.

ATTACHMENT 4 Page 1 of 1

ATTACHMENT 5 Catawba Unit 1 and Unit 2 Containment Purge (VP) System, Hydrogen Purge (VY) System, and Containment Air Release and Addition (VQ) System Valve Leakage

Catawba Unit 1 VO & VY Leakage History (All valves are 4" Diameter)

Units a standard cubic centimeters per minute of leakage (scom)

Penetration 1M204 1M386 IM332 1IM346 CIV VOl 6A VO2A W16 Wi 5B VY1 7A VY1 8B Date/Leakage 3/17/04 2/16/04 214/04 2/4/04 (19) 4/27/04 (0) 2/4/04 (12)

...19 L (27) (17) _ _ _ _ _ _ _ _ _ _ _ _ _

11/20/03 11/23/03 8/15/03 8/15/03 (6) 11/29/03 (0) 8/15/03 (12) 10(/1)03 9/4/03 2/24/03 2/2/4/03 (3) 5/21/03 (7) 2/24/03 (0) 7/29/03 6/3/03 9/10/02 9/10/02 (25) 12/3/02 (0) 9/10/02 (3) 5/7/)03 11/19/02 5/1/02 5/13/02 (25) 6/18/02 (17) 6/18/02 (29) 5/7/03 12/17/02 3/25/02 3/25/02 (20) 1/2/02 (0) 3/25/02 (0)

39) ( 2 )J (_ _ _ _ _ _ _ _ _ _ _ _ _

2/11/03 9/25/02 11/6/01 11/6/01 (38) 7/17/01 (0) 11/6/01 (118)

(0) (70) 11/29/02 7/1/02 4/24/01 4/24/01 (2) 1/30/01 (0) 11/16/00 (0) 8/27/02 5/7/02 11/2/00 11/2/00 (27) 11/16/00 (1) 5/23/00 (140)

(15) (0) 6/4/02 4/9/02 5/23/00 10/21/00 (16) 8/15/00 (0) 1217/99 (39) 5/7/02 11/15/02 12/7/99 5/23/00 (0) 2/29/00 (10) 6/22/99 (30)

(8 (4 (14) 3/12/02 10/24/01 6/22/99 12/7/99 (50) 9/14/99 (6) 9/24/01 7/30/01 1/6/99 6/22/99 (8)

_______ (29) (9) (43) 7/2/01 5/7/01 3/31/99 (0)

__ __ _ __ _ _ _ _ ) (20) _ _ _ _ _ _ _

4/9/01 11/3/00 2/19/01 8/28/00 1/22/01 6/5/00

_ __ __ _ _ A L (1 0) 10/21/00 4/11/00

____ ____ (1 9) ( 7 _ _ _ _ _ _ _ _

8/7/00 12/30/99 (20) (6) .

5/15/00 9/27/99 (19) A8) 2/21/00 7/6/99 11/30/99 517/99

_ __ _ __ _ _ _ _ (43) 11 L.7_ _ _ _ _ _

9/8/99 6/14/99 5/8/99

_ _ __ __ _ _ _ _ (1 2) _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ Page l of 4

Catawba Unit 1 VP Leakage History Units = standard cubic centimeters per minute of leakage (sccm)

Penetration IM119 1M140 1M213 1M357 1M368 1M432 1M433 1M434 1M456 Inside CIV VP15A VP19A VP17A VP7A VP1OA VP4A VP12A VP9A VP1B Outside CIV VP16B VP20B VP18B VP6B VP11B VP3B VP138 VP8B VP2A Valve Diameter 24" 12" 12" 24" 24" 24" 24" 24" 24" 12/8/2003 322 87 140 230 113 230 99 103 340 7/8/2003 350 32 10 28 12 150 30 16 220 1/21/2003 370 47 28 76 180 235 185 184 218 8/6/2002 205 27 10 0 35 75 210 0 95 5/12/2002 430 59 25 1 102 5 190 140 125 285 2/19/2002 378 60 25 45 225 110 200 110 255 9/4/2001 0 50 0 0 0 160 135 5 190 6/13/2001 33 10 21 276 146 108 170 190 190 3/20/2001 405 92 38 20 60 234 140 17 255 11/11/2000 210 56 37 465 12 200 55 15 405 4/18/2000 195 18 17 160 22 145 149 195 160 11/3/1999 220 33 20 170 150 188 160 146 120 5/16/1999 203 20 58 130 2 350 166 350 315 12/30/1998 82 2 12 2 53 265 288 325 180 10/7/1998 220 24 2 219 43 236 218 310 219 6/1/1998 144 2.4 5 18 32 213 182 210 275 ATTACHMENT 5 Page 2 of 4

Catawba Unit 2 VO & VY Leakage History (All valves are 4" diameter)

Units

• standard cubic centimeters per minute of leakage (sccm)

Penetration 2M204 2M386 2M332 2M346 CIV VO16A VQ2A VY16 VY15B VY17A VY1 8B Date/Leakage 3/17/04 (122) 2/17/04 (86) 3/9/04 (37) 3/9/04 (0) 12/17/03 (0) 3/9/04 (0) 12/22/03 (139) 12/03/03 (7) 9/23/03 (26) 9/23/03 (17) 6/30/03 (0) 9/23/03 (0) 10/1/03 (145) 9/3/03 (5) 4/8/03 (13) 4/8/03 (13) 4/8/03 (0) 4/08/03 (9) 7/29/03 (141) 6/3/03 (1) 10/21/02 (1) 10/21/02 (4) 1/14/03 (8) 10/21/02 (0) 5/7/03 (154) 5/7/03 (13) 5/8/02 (1) 5/8/02 (133) 7/23/02 (16) 4/27/02 (0) 3/12103 (178) 12/17/02 (4) 10/16/01 (0) 10/16/01,(35) 1/29/02 (28) 10/16/01 (0) 2/11/03 (10) 9/25/02 (0) 6/5/01 (0) 6/5/01 (135) 10/16/01(0) 6/5/01 (0) 5/7/02 (8) 7/1/02 (0) 12/20/00 (0) 12/20/00 (0) 3/13/01 (6) 12/20/00 (0) 3/12102 (178) 4/9/02 (13) 7/5/00 (0) 7/5/00 (0) 9/26/00 (21) 7/5/00 (0) 10/3/01 (3) 10/17/01 (6) 4/4/00 (8) 4/4/00 (0) 4/4100 (27) 4/4/00 4) 7/2/01 (122) 7/30/01 (0) 1/18/00 (5) 1/18/00 (3) 10/27/99 (0) 1/18/00 (4) 4/9/01 (60) 5/7/01 (2) 8/5/99 (0) 8/5/99 (23) 5/12/99 (0) 8/5/99 (28) 10/31/00 (88) 11/18/00 (14) 2/17/99 (0) 2/17/99 (0) 2/17/99 (0) 8/7/00 (85) 8/28/00 (17) 5115/00 (80) 6/5/00 (0) 4/5/00 (88) 3/25/00 (2) 2/21/00 (130) 12/29/99 (32) 11/30/99 (108) 9/27/99 (0) 9/8/99 (108) 7/6/99 (2) 6/17/99 (107) 4/12/99 (12) 3/22/99 (125) _

ATTACHMENT 5 Page 3 of 4

Catawba Unit 2 VP Leakage History Units = standard cubic centimeters per minute of leakage (sccm)

Penetration 2M119 2M140 2M213 2M357 2M368 2M432 2M433 2M434 2M456 Inside CIV VP15A VP19A VP17A VP7A VP10A VP4A VP12A VP9A VP1B Outside CIV VP16B VP20B VP18B VP6B VP11 B VP3B VP13B VP8B VP2A Valve Diameter 24" 12" 12" 24" 24" 24" 24" 24" 24" 3116/2004 24 64 24 20 72 36 30 47 61 9/30/2003 226 22 59 8 116 55 3 36 199 3/21/2003 128 10 152 10 104 158 18 73 239 10/30/2002 83 30 25 240 10 19 29 90 68 5/22/2002 8 10 41 355 88 36 51 128 41 10/14/2001 64 10 152 380 54 76 153 196 114 9/4/2001 10 50 10 10 10 160 135 10 190 6/13/2001 33 10 21 276 146 108 170 190 190 3/20/2001 405 92 38 20 60 234 140 17 255 12/27/2000 138 13.6 31 312 166 23 260 182 127 7/11/2000 100 4.5 38 333 46 50 242 224 89 4/4/2000 125 10 49 260 161 125 222 205 118 1/24/2000 15 15 47 215 280 65 166 180 7 8/10/1999 198 J14 35 375 53 42 280 212 42 2/24/1999 46 10 37 329 72 38 189 138 97 1219/1998 41 2 34 325 60 38 97 177 70 10/14/1998 102 6 41 70 115 15 220 400 75 ATTACHMENT 5 Page 4 of 4