ML20063E951
| ML20063E951 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 02/04/1994 |
| From: | Fenech R TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9402140039 | |
| Download: ML20063E951 (18) | |
Text
{{#Wiki_filter:_. _ _. ~. A -[ v e 4 _ I y Tonnessee Vafey Autnor4y Post Othee Box 20txl SacMcDaisy. Tennessee 37379 2000 t i 'i Robert A Fenech vice Prescent. seauoyan Neuar Plant f February 4, 1994 U.S. Nuclear Regulatory Commission ATTN: ' Document Control Desk Washington, D.C. 20555 Gentlemen: 3 v In the Matter of ) Docket No. 50-328 Tennessee Valley Authority ) SEQUOYAll NUCLEAR PLANT (SQN) - UNIT 2 - REQUEST FOR 10 CFR 50, APPENDIX J SCIIEDULAR EXEMPTION i
References:
1. TVA letter to NRC dated September 27, 1993 f 2. NRC letter to TVA dated December 16, 1993, " Exemption to Appendix J of 10 CFR Part 50, Schedular Requirements for 4 Type B and C Local Leak Rate Tests Sequoyah Nuclear-Plant Unit 2 (TAC No. M87802)" In accordance with 10 CFR 50.12, TVA-requests a one-time exemption from, the test-interval requirements of 10 CFR 50, Appendix J, _3 Sections III.D.2(a) and III.D.3, for SQN Unit 2. This' exemption request supersedes TVA's exemption request submitted in Reference 1. The extension to the previous exemption is the result of a change in the schedule for the-Unit 2 Cycle 6 refueling outage.- The basis for TVA's' proposed exemption remains unchanged. t On March 15, 1992 SQN Unit 2 entered Mode 5 for its Cycle 5 refueling ll . outage. During the refueling, outage (late March to late April 1992), all- ~ Types B and C tests were performed. SQN Unit 2 returned to service from the Cycle 5 refueling outage on May 17, 1992. On March-1, 1993, Unit 2 i was shut down because of an extraction steam. leak. This forced outage lasted approximately eight months and Unit 2 resumed power operation on- +. October 22, 1993. Because of the, forced outage duration and the need to optimize fuel burnup, an exemption from the test-interval requirements of i
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4 U.S. Nuclear Regulatory Commission l Page 2 February 4, 1994 Appendix J was requested (Reference 1) and subsequently granted by NRC in Reference 2. This exemption allowed for continued operation until i April 2, 1994. However, since that time, Unit 2 has had several forced outages. To allow for fuel and outage preparation optimization, TVA has rescheduled the Unit 2 Cycle 6 refueling outage to begin on or. before July 3, 1994. Since Unit 2 operation is desired past April 2, 1994, TVA' requests.that the Types B and C tests be deferred until the Unit 2 Cycle 6 refueling .i outage. To allow for outage scheduling flexibility, TVA requests that July 15, 1994, be established as the date after which TVA-must either have started Types B and C testing or have entered Mode 5. Approval of TVA's one-time exemption is requested before April 2, 1994, to permit the realignment of the local leak-rate test program with the SQN refueling _ outage schedule. The approval of this request will also benefit the SQN As Low As Reasonably Achievable Program by eliminating the additional personnel e:.3osure that would accrue during the performance of these tents before the Unit 2 Cycle 6 refueling outage. contains the exemption request. Enclosure 2 contains a tabular performance listing of the impacted components. Enclosure 3 contains a listing of the commitments contained within this submittal. i Please direct questions concerning this issue to D. V. Goodin at (615) 843-7734. 4 Sincerely, hfYf Robert A. Fenech Enclesures cc;. See page 3 i T h
i._ + 9 e U.S. Nuclear Regulatory Commission 1: Page'3 February _4.-1994 e Enclosures cc (Enclosures): Mr. D. ~ E LaBarge, Project Manager l U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike -Rockv111e, Maryland-20852-2739 NRC Resident Inspector Sequoyah Nuclear Plant 2600 Igou Ferry Road Soddy-Daisy, Tennessee _ 37379-3624 f Regional Administrator U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323-2711 .l t i ? 6 l i i q i 1
1 1 ) ENCLOSURE 1 REQUEST FOR A SCHEDULAR EXEMPTION FROM 10 CFR 50, APPENDIX J SEQUOYAH NUCLEAR PIANT UNIT 2 i I s 4 4 0 l n i
Introduc. tion In accordance with 10 CFR 50.12, TVA is requesting a one-time exemption from the test-interval requirements of 10 CFR 50, Appendix J, Sections III.D.2(a) and III.D,3, for SQN Unit 2. Sections III.D.2(a) and III.D.3 require Types B and C tests to be performed at intervals no greater than two years during reactor shutdown for refueling. The SQN Unit 2 Cycle 5 refueling outage began in March 1992 and lasted through mid-May 1992. Local leak-rate test (LLRT) performance during the Cycle 5 refueling outage started in March 1992 and ended ir. April 1992. All Types B and C tests were performed during the Cycle 5 *:efueling outage. SQN Unit 2 returned to service from the Cycle 5 refueling outage on May 17, 1992. On March 1, 1993, Unit 2 was taken offline because of an extraction steam leak. Unit 2 entered Mode 5 and remained in Mode 5 (cold shutdown) until October 1993 when it returned to service. Since October 1993, Unit 2 has encountered several forced shutdowns. Unit 2 returned to continued service Januury 12, 1994. Unit 2 is not scheduled to begin shutdown for refueling until July 3, 1994. The expiration of the two-year time interval f or some Types B and C tests would force the plant to shut down in April 1994 to perform Appendix J testing. Accordingly, TVA is requesting a one-time exemption from the two-year test interval of 10 CFR 50 Appendix J for Types B and C testing. The components affected by this request are listed in Enclosure 2. These components represent approximately 88 percent of the LLRT program. This compares with 53 percent of the LLRT program that was previously approved by the NRC letter to TVA dated December 16, 1993. The components affected consist of Type B penetrations and Type C valves. The components listed in the table will be tested during the Unit 2 Cycle 6 refueling outage. This outage is scheduled to begin less than four months after the two-year time interval expires for the first LLRT performed during the Cycle 5 refueling outage (March 15, 1994). This increase in the test interval continues to provide an adequate safety margin such that there is.no undue risk to the public health and safety based on the expected performance of the subject components. A review of past component performance indicates that any incremental increase in leakage that may result from the extensien would not significantly contribute to the total Types B and C leakage limits. The components included in this request that have experienced degradation over the past operating cycle have been repaired or replaced. The cost associated.with radiation exposure to plant test personnel when compared with the minimal gain to ensure that the affected components have not significantly degraded is considered unnecessary based upon the present test results - and the small potential for incremental increases in component leak rates. The requested exemption would reduce personnel radiological exposure and the expenditure of resources that would be required to comply with the regulation without undue risk to the public health and safety. In addition, to further ensure safe plant operation, two components (2-FCV-67-87 and 2-VLV-67-575A) will be leak-rate tested in the event Unit 2 experiences a forced shutdown to Mode 5. These are the only components that have any appreciable amounts of leakage from the Unit 2 Cycle 4 and Unit 2 Cycle 5 refueling outages. Dearriplinn The first LLRT on Unit 2 that was conducted during the Cycle 5 refueling outage was performed on March 15, 1992. Components tested during the Unit 2 forced outages between October 1993 and January 1994 are not affected by this request. Accordingly, the maximum time extension. beyond the two-year interval that is requested is four months. The listing below provides a breakdown of the number and types of components included in the requested extension. r Air tested components (subject to 0.6 maximum allowable leakage rate {La)) Bellow Penetrations 39 Electrical Penetrations 47 Isolation Valves 196* Flanges 11 Hydrogen Analyzer (A Train) 1 RHR Spray Header Valves (Water Tested) 10
- Eight of these 196 valves experienced American Society of Mechanical Engineers (ASME) Section XI leak testing following the Unit 2 shutdown on March 1, 1993, and were found to be acceptable under ASME Section XI leak-test criteria.
Inshnical Basis t The two-year interval specified in Appendix J is intended to be frequent. enough to prevent significant degradation from occurring and long enough to permit LLRTs to be performed during refueling outages. At the time-Appendix J was published (February 14, 1973), light-water reactors were nominally on annual refueling cycles with relatively short refueling outages. Today, most light water reactors are on an 18-month or 2-year refueling cycle with extended refueling outages. The intent of the regulation is for isolation valves to be tested during refueling outages, not to require the unit to be shut down solely for LLRT testing. A shutdown solely to perform leak tests is not consistent with the intent i of Appendix J and would result in increased radiological exposure to test personnel. Since testing will be performed during the Unit 2 Cycle 6 refueling outage. the cost to personnel for performing tests'during a. forced outage (in terms of radiological exposure and personnel safety) is greater than the minimal increase in assurance that the' components will not significantly degrade'during the remaining Unit 2 Cycle 6 operating -) cycle. l 1 The enclosed table represents the historical local leak-rate data from Onit 2 Cycles 4 and 5 for the components affected by tyls extension. l j
Based on the past performance of the affected components, there is reasonable assurance that no' significant degradation would occur during the extension interval. The condition of the components is therefore not expected to change.significcntly over the extension period of four - months. Furthermore,-the two-year interval specified for Types'3 and C tests was based on two years of exposure to service conditions. For the months before Unit 2 restart, most of the subject components were not exposed to service conditions. This would further reduce any potential degradation of these components. Justification 10 CFR 50.12 states that the commission may grant exemptions from the requirements of the regulations contained in 10 CFR 50 provided: I. The Requested Exemption is Authorized by Law The Commission is a'sthorized by law to grant this exemption. II. The Requested Exemption Does Not Present an Undue Risk'to the Public Health and Safety The intent of Sections III.D.2(a) and III.D.3 of Appendix J is to ensure containment integrity is maintained. Based on the following i information, the exemption requested will not significantly affect the ability of the individual primary containment components to perform their safety functions. 1. The valves and components for which the extension of the: two-year interval is being requested are, in general,. considered to be leak tight and in good condition. The leak-tight condition of these components has been verified by Types B and C LLRTs and again by the Type A test conducted on Unit 2 in April 1992. The present Types B and C pathway leak rates account for less than 8.0 percent of the 0.6 percent La limit in the technical specifications (TSs). TVA believes the remaining margin is sufficient to ensure any incremental increase in leakage resulting from the extension would not cause unacceptable as-found test results. l 2. Based on historical data,.any incremental increase in leakage' because of the extension will be small. Improved maintenance practices implemented during the Unit 2 Cycle 5 outage (i.e..- periodic replacement of valve packing, periodic lubrication of valve stems, and MOVATS testing of containment isolation valves) provide increased assurance that these components'will I perform their safety function. 3. Many of the components for which the exemption is requested were included in the Type A test performed in April 1992. This I test indicated a containment leak rate of 0.15 percent per day, which is below the 0.1875 percent per day limit. i i l i l 5
~ III. The Requested Exemption is Consistent With the Common Defense and Security The common defense and security are noL affected by this request for exemption. IV. Special. Circumstances are Present Which Necessitate the Requast for an Exemption to the Regulations of 10 CFR 50,-Appendix J, Sections III.D.2(a) and III.D.3 In accordance with 10 CFR 50.12(a)(2), the following special circumstances are present. 1. The application of the regulation in the particular circumstances present would not serve the intent of the regulation. The intent of the regulation is to ensure containment integrity through component performance. Any incremental increase in component leakage because of the extension is expected to be small. Since the regulation allows-operation for two years with less margin than is currently present, the requested exemption does not conflict with the intent of the regulations. Thus, the exemption to defer testing of the subject components until the next scheduled refueling outage is considered appropriate. i 2. Compliance with the regulation would result in undue hardship i' or other costs that are significantly in excess of those contemplated when the regulation was adopted. The intent of the regulation is that the required testing be performed'during normal refueling outages to ensure containment integrity. When the regulation was adopted, provisions to accommodate an 18-or 24-month fuel cycle-were not provided, thus increasing the likelihood of a plant shutdown to perform LLRTs. However,.it was not the intent of the regulation to force a shutdown' solely to perform LLRTs. A requirement to shut down to perform LLRTs would represent undue hardship and excessive costs in the form of increased personnel radiological exposure, lost revenues,. and higher cost associated with two outains instead of'one. 3. The exemption'would provide only temporary relief from the regulation. This exemption is being requested as a one-time schedular exemption to allow Unit 2 to operate until the next refueling outage scheduled to begin July 3, 1994. Safety Impact The extension of the LLRT interval does not impact the probability of the occurrence of any accident. The-present leak rate for the Types B and C pathways on Unit 2 is 9.731 standard cubic feet per hour (SCFH) while-the 0.6-La TS limit'is j 135.1 SCFH. This leak rate represents less than 8.0 percent of the i i ~
n maximum leakage rate allowed by TSs. Thus, a large amount of additional degradation would have to occur for the TS limit to be exceeded. The potential for a large amount of degradation to occur during the extension period is small. On the average, as-left leak rates are less than 25 percent of'the established reference leak rates for the components listed in the. table. Since the maximum extension requested is relatively short in comparison with the two-year test interval (approximately.17 percent), it is unlikely that substantial degradation of containment components leading-to the failure of the containment to perform its safety function would occur. Since the integrity of the containment boundary is not expected to be substantially diminished during the extension period, it is concluded that the proposed amendment does not involve a significant increase in-the consequences of any accident previously evaluated. Physical modifications are not being made and plant operations are not being changed. Consequently, the containment system's capability to perform its intended function will be maintained; no new accident precursors are generated; therefore, no new or different kind of accident scenarios are created. The present margin between the most recent as-left total leak rate and the 0.60-La limit is sufficient to allow for any additional leakage that might result from the extension. Therefore, extending the LLRT interval will not result in a significant reduction in the margin of safety. Cancinainn i The valves and components for which the extension of the two-year interval is being requested are considered in general to be leak tight and in good condition. The leak-tight condition of these. components has been verified by Types B and C local LLRTs and again by the Type A test ~ conducted on Unit 2 in April 1992. Based on the present leak rate for the Types B and C pathways (accounts for less than 8.0 percent of the 0.6-La 11mit), TVA believes the remaining margin is sufficient to ensure-any incremental increase in leakage because the extension will not result t in unacceptable as-found test results. Based on historical data, any incremental increase in leakage because of_ the extension will be small. Improved maintenance practices implemented-during the Unit-2 Cycle 5 outage provide increased assurance that these t components will perform their safety function. mi the average, as-lef t leak rates are less than 25 percent of the _ established reference leak rates for the components listed in the table. Since the maximum extension-requested is relatively short in comparison with the two-year test interval (approximately 17 percent), it is r unlikely that substantial degradation of containment components leading. to the failure of the containment to perform its safety function would occur. i
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6 f ENCLOSURE 2 i i TABLE 9 COMPONENTS REQUIRING EXTENSION AND HISTORICAL LEAK-RATE DATA i i i 9 F P ~b t i j l 1 .'j
9 TYPE B TESTED COMPONENTS U2C4 U2C5 2 AF/Ap AF/AL Expiration Camponent Penetration SCFH SCFH -Date Electrical X-122E 0.0000/0.0000 0.0000/0.0000 03/31/94 E1cetrical X-132E 0.0000/0.0000 0.0000/0.0000 03/27/94 Electrical X-133E 0.0000/0.0000 0.0799/0.0799 03/28/94 Electrical X-134E 0.0000/0.0000 0.0000/0.0000 03/31/94 Electrical X-136E 0.0000/0.0000 0.0000/0.0000 03/31/94 Electrical X-137E 0.0000/0.0000 0.0000/0.0000 03/31/94 Electrical X-138E 0.0000/0.0000 0.0000/6 0000 03/31/94 Electrical X-140E 0.0000/0.0000 0.0000,?.1000 -03/31/94~ Electrical X-142E 0.0000/0.0000 0.0000/0.0000 03/31/94 Electrical X-143E 0.0085/0.0000 0.0000/0.0000 03/27/94 Electrical X-144E 0.0000/0.0000 0.0000/0.0000 03/27/94 Electrical X-150E 0.0000/0.0000 0.0000/0.0000 04/02/94. Electrical X-154E 0.0000/0.0000 0.0000/0.0000 03/26/94 Electrical X-157E 0.0000/0.0000 0.0000/0.0000 03/26/94 Electrical X-158E 0.0000/0.0000 0.0000/0.0000 03/26/94. L E1cetrical X-159E 0.0000/0.0000 0.0000/0.0000 03/25/94 i Electrical X-161E 0.0000/0.0000 0.0000/0.0000 .03/27/94L Electrical. X-164E 0.0000/0.0000 .0.0000/0.0000 03/27/94 3 Electrical X-165E 0.0000/0.0000 0.0000/0.0000 03/25/94 1 Electrical X-166E 0.0000/0.0000 0.0000/0.0000 03/26/94 Resilient Seal X-108 0.0000/0.0000 0.0000/0.0000 03/17/94 Resilient Seal X-109 0.0000/0.0000 0.0000/0.0000 03/17/94 1. Standard Cubic Feet Per Hour = SCFH 2. As-Found/As-Left = AF/AL { s 'l B f 1 )
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- t TYPE B TESTED COMPONENTS r
U2C4 U2C5 AF/AL AF/AL Expiration CDmponent_ l'entttratinn SCSI SCFlf 'Date . Res111cnt Seal X-1 0.0000/0.0000 0.0000/0.0000 04/26/94 I Resilient Seal X-40D 0.3706/0.0000 0.0000/0.0000 04/06/94 Resilient Seal X-54 0.0000/0.0000 0.0000/0.0000 04/30/94 Resilient Seal X-88 0.0042/0.0000 0.0000/0.0000 04/24/94 Resilient Seal X-111 0.0000/0.0000 0.0000/0.0000 04/06/94 r Resilient Seal X-112 0.0000/0.0000 0.0000/0.0000 04/06/94 Resilient Seal X-113 0.0000/0.0000 0.0000/0.0000 04/06/94 Resilient Seal X-117 0.0015/0.0000 0.0000/0.0000 04/25/94 Resilient Seal X-118 0.0000/0.0000 .0.0000/0.0000 04/30/94 Bellows X-12A 0.0000/0.0000 0.0000/0.0000 04/07/94 Bellows X-123 0.0000/0.0000 0.0000/0.0000 04/08/94 Bellows X-120 0.0000/0.0000 0.0000/0.0000 04/08/94 Bellows X-12D 0.0000/0.0000 0.0000/0.0000 04/07/94 Bellows X-13A 0.0000/0.0000 0.0000/0.0000 04/16/94 Bellows X-13B 0.0267/0.0267 0.0000/0.0000 04/16/94 Bellows X-130 0.0000/0.0000 0.0000/0.0000 04/16/94 Bellows X-13D 0.0000/0.0000 0.0000/0.0000 04/16/94 Bellows X-14A 0.0000/0.0000 0.0000/0.0000 04/07/94 Bellows X-14B 0.0000/0.0000 -0.0000/0.0000 '04/07/94-Bellows X-140 0.0000/0.0000 0.0000/0.0000 04/07/94 Bellows X-14D 0.0000/0.0000 0.0000/0.0000 04/07/94 Bellows X-15 0.0000/0.0000 0.0000/0.0000 04/07/94 Bellows X-17 0.0000/0.0000 0.0000/0.0000-04/09/94 Bellows X-20A-0.0000/0.0000 0.0000/0.0000 04/07/94 Bellows X-20B 0.0000/0.0000 0.0000/0.0000 -04/09/94 Bellows X-21 0.0000/0.0000 0.0000/0.0000 04/07/94 Bellows X-22 0.0000/0.0000 0.0000/0.0000 04/07/94-Bellows X-24 0.0000/0.0000 0.0000/0.0000 04/07/94 Bellows X-30 0.0000/0.0000 0.0000/0.0000 04/08/94-Bellows X-32 0.0000/0.0000 0.0000/0.0000 04/08/94 l Bellows X-33 0.0000/0.0000 0.0000/0.0000 04/08/94 Bellows-X-45 0.0000/0.0000 0.0000/0.0000 04/08/94 - Bellows X-46 0.0000/0.0000 .0.0000/0.0000 04/08/94 Bellows X-47A 0.0000/0.0000 0.0000/0.0000-04/09/94 1 Bellows X-47B 0.0000/0.0000' O.0000/0.0000 04/09/94 Bellows-X-81 0.0000/0.0000 0.0000/0.0000 04/08/94^ j Bellows X-107 0.0000/0.0000 0.0000/0.0000 104/08/94 .l Bellows' X-108 0.0000/0.0000 0.0000/0.0000-04/08/94 Bellows X-109 0.0085/0.0085 0.0000/0.0000 04/09/94 n Electrical X-120E 0.0000/0.0000 0.0000/0.0000 04/04/94' l Electrical X-121E 0.0000/0.0000 0.0000/0.0000 03/31/94 . Electrical X-123E 0.0000/0.0000' O.0000/0;0000 04/03/94 Electrical X-124E 0.0000/0.0000 0.0000/0.0000 04/04/94
- TYPE B TESTED COMPONENTS U2C4 U2C5 AF/AL AF/AL Expiration, Component _
Eeneiration SCfH SCFH Dde ^ Electrical X-126E 0.0000/0.0000 0.0000/0.0000 04/03/94 Electrical X-127E 0.0000/0.0000 0.0000/0.0000 04/16/94 E1cetrical X-128E 0.0000/0.0000 0.0000/0.0000 04/16/94 i Electrical X-129E 0.0000/0.0000 0.0000/0.0000 04/03/94 Electrical X-131E 0.0533/0.0533 0.0000/0.0000 04/03/94 Electrical X-135E 0.0000/0.0000 0.0000/0.0000-04/16/94 Electrical X-139E ~0.0000/0.0000 0.0000/0.0000 04/16/94-Electrical-X-141E 0.0000/0.0000 0.0000/0.0000 04/03/94 Electrical X-145E 0.0000/0.0000 0.0000/0.0000 04/03/94 Electrical X-146E 0.0000/0.0000 0.0000/0.0000 04/03/94 i Electrical X-147E 0.0000/0.0000 0.0000/0.0000 04/03/94 Electrical X-148E 0.0000/0.0000 0.0000/0.0000 04/16/94 Electrical X-149E 0.0000/0.0000 0.0000/0.0000_ 04/03/94 Electrical X-151E 0.0424/0.0000 0.0000/0.0000 04/03/94 Electrical X-152E 0.0000/0.0000-0.0000/0.0000 04/03/94 Electrical X-153E 0.0000/0.0000 0.0000/0.0000 04/16/94 Electrical X-156E 0.0000/0.0000 0.0000/0.0000 04/16/94 Electrical X-160E 0.0000/0.0000 0.0000/0.0000 04/16/94 Electrical X-163E 0.1660/0.1660 0.0946/C.01359 04/16/94 Electrical X-167E 0.0000/0.0000 0.0000/0.0000 04/16/94 Electrical X-168E 3.814/0.0000 0.0000/0.0000 04/03/94 Electrical X-169E 0.0000/0.0000 0.0000/0.0000 -04/16/94 Electrical X-170E 0.0000/0.0000 0.0000/0.0000 04/03/94 s i l
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y TYPE C TESTED COMPONENTS U2C4 U2C5-i AF/AL. AF/AL Expiration ComPDnenL l'_CDmira tion SCFH SCFH Drte Valves 62-72/73/74 X-15 43.9243/0.0000 0.0000/0.0000 03/20/94 i Valve 43-310 X-23 0.0000/0.0000 0.0000/0.0000 03/18/94 Valve 43-2 X-25A 0.0000/0.0000 0.0000/0.0000 03/24/94-Valve 43-3 X-25A 0.0000/0.0000 0.0000/0.0000 '03/24/94 I Valve 30-44X X-25B 0.0000/0.0000 0.0000/0.0000 03/16/94 i Valve 30-44Y X-25B 0.4040/0.4040 0.0000/0.0000 03/16/94 Valve 30-311X X-25B 0.0772/0.0772 0.0000/0.0000 03/16/94 Valve 30-311Y .X-25B 0.1817/0.1817 0.0000/0.0000 03/16/94 Valve 43-11 X-25D 0.0000/0.0624 0.0000/0.0000 03/24/94 Valve 43-12 X-25D 0.0000/0.0000 0.0000/0.0000 03/24/94 Valve 30-43X X-26A 0.1501/0.1501 0.0000/0.0000 03/16/94 Valve 30-43Y X-26A 0.0000/0.0000 0.0000/0.0000 03/16/94-Valve 30-310X X-26A 0.0000/0.0000 0.0000/0.0000 03/16/94 j Valve 30-310Y X-26A 0.0000/0.0000 0.0000/0.0000 03/16/94 Valve 30-30CX X-27A 0.1499/0.1499 0.0000/0.0000 03/16/94 Valve 30-30CY X-27A 0.0971/0.0971 0.0000/0.0000 03/16/94 Valve 30-42Y X-27B 0.0625/0.0625 0.0000/0.0000 03/16/94 Valve 30-42X X-27B 0.0625/0.0625 0.0000/0.0000 03/16/94-Valve 52-504 X-27C 0.0000/0.0000 0.0000/0.0000' 03/17/94 Valve 52-505 X-27C 0.0000/0.0000 0.0000/0.0000 03/17/94 Valves 70-89/698 X-29 0.0000/0.0000 0.0000/0.0000 03/19/94 Valve 70-92 X-29 0.0000/0.0000 0.0000/0.0000 03/19/94 Valve 63-71 X-30 4.8089/0.0000 'O.0000/0.0000 03/27/94 Valves 70-85/143/703 X-35/53 0.0000/0.0000 0.3545/0.~3545 03/19/94 Valve 63-64 X-39A 0.0000/0.0000 0.0000/0.0000 03/20/94 + Valve 77-868 X-39A 0.0000/0.0000 0,0000/0.0000 03/20/94 Valve 77-849 X-39B 0.0000/0.0000 486.42/0.0000 04/02/94 Valve 77-127 X-41 0.0000/0.0000 0.0000/0.0000 03/27/94 Valve-77-128 X-41 0.0000/0.0000 0.0000/0.0000 03/27/94 Valves 32-103/341 X-268 0.0000/0.0000 -0.0000/0.0000 03/23/94-Valve 81-12. X-42 0.0000/0.0000 0.0000/0.0000 03/19/94; Valve 81-502 X-42 0.0000/0.0000 0.0000/0.0000-03/19/94' -Valve 61-191 X-47A 0.0000/0.0000
- 526.6563/0.0000 04/02/94
- Valves 61-192/533 X-47A 0.0000/0.0000 211.1943/0.0000; 04/02/94 Valves 61-194/680 X-47B 0.0000/0.0000-0.0000/0.0000 04/01/94 Valve 26-240 X 7.7436/0.3004 0.1877/0.1877-03/27/94 Valve 70-140-X-52 0.0000/0.0000 0.0000/0.0000' 03/19/94 Valves 70-141/791 X-52 0.0000/0.0000' O.0000/0.0000.
03/19/94 'l Valve 67-83 X-56 0.0000/0.0000 0.0000/0.0000-03/31/94 Valves 67-89/1523D X-56 0.0000/0.0000-10.0000/0.0000 03/31/94 Valves 67-111/575D X-57 0.0000/0.0000 0.0000/0.0000 03/31/94 Valve-67-112 X-57 0.0000/0.0000 0.0000/0.0000 03/31/94 Valve 67-107 X-58 0.0000/0.0000 0.0000/0.0000. l03/24/94 1 Valve 67-88 X-59_ 0.0000/0.0000 0.0000/0.0000 03/23/94 Valve 67-91 X-60 0.0000/0.0000 1.0000/0.0000 '03/31/94 i l i i ~- -
TYPE C TESTED COMPONENTS U2C4 U2C5 AF/AL AF/AL Expiration CompDRent_ Eene1Iatinn SCFH SCEB Date Valves 67-90/1523B X-60 0.0000/0.0000 0.0000/0.0000 03/31/94 Valves 67-103/575B X-61 0.0000/0.0000 0.0000/0.0000 03/31/94 Valve 67-104 X-61 0.0000/0.0000 0.0000/0.0000 03/31/94 Valve 67-99 X-62 0.0000/0.0000 0.0000/0.0000 03/24/94 Valve 67-96 X-63 0.0000/0.0000 0.0000/0.0000 03/25/94 valve 31C-222 X-64 0.0000/0.0000 0.0856/0.0000 04/02/94 Valves 31C-223/752 X-64 0.0000/0.0000 0.0000/0.0000 03/21/94 Valve 31c-224 X-65 0.0000/0.0000 0.0000/0.0000 03/21/94 Valves 31C-225/734 X-65 0.0000/0.0000 0.0000/0.0000 03/21/94 Valve 31C-229 X-66 0.0000/0.0000 0.0000/0.0000 03/26/94 Valves 31C-230/715 X-66 0.0000/0.0000 0.0000/0.0000 03/26/94 Valve 31C-231 X-67 0.0000/0.0000 0.0000/0.0000 03/26/94 Valve 67-141 X-68 0.0000/0.0000 0.0000/0.0000 03/21/94 Valve 67-580D X-68 374.3522/0.0000 0.0000/0.0000 03/21/94 Valve 67-130 X-69 0.0000/0.0000 0.0000/0.0000 03/19/94 Valve 67-139 X-70 0.0000/0.0000 0.0000/0.0000 03/21/94 Valves 67-297/585B X-70 0.0000/0.0000 0.0000/0.0000 03/21/94 Valve 67-134 X-71 0.0000/0.0000 0.0000/0.0000 03/19/94 Valves 67-296/585C X-71 0.0000/0.0000 0.0000/0.0000 03/191 Valve 67-142 X-72 0.0000/0.0000 0.0000/0.0000 03/21 Valves 67-298/585D X-72 0.2644/0.2644 0.0000/0.0000 03/21/>e Valves 67-295/585A X-73 0.0000/0.0000 0.0000/0.0000 03/19/94 Valve 67-138 X-74 0.0000/0.0000 0.0000/0.0000 03/21/94 Valve 67-580B X-74 0.0000/0.0000 0.0000/0.0000 03/21/94 Valve 67-133 X-75 0.0000/0.0000 0.0000/0.0000 03/19/94 Valve 67-5800 X-75 0.0000/0.0000 0.0000/0.0000 03/19/94 Valve 33-722 X-76 0.0000/0.0000 0.0000/0.0000 03/15/94 valve 33-739 X-76 0.0000/0.0000 0.0993/0.0993 03/15/94 Valves 59-522/529 X-77 0.0000/0.0000 0.0000/0.0000 03/15/94 Valve 59-d33 X-77 0.0000/0.0000 0.0000/0.0000 03/15/94 Valve 26-243 X-78 0.0000/0.0000 0.0000/0.0000 03/26/94 Valve 26-1296 X-78 1.8127/0.2933 0.0392/0.0392 03/26/94 Valve 78-561 X-82 0.0000/0.0000 0.0000/0.0000 03/16/94 Valve 78-557 X-83 0.0000/0.0000 0.0000/0.0000 03/16/94 Valve 78-558 X-83 0.0000/0.0000 0.0000/0.0000 03/16/94 Valve 68-307 X-84A 0.0000/0.0000 0.0000/0.0000 03/20/94 Valve 68-308 X-84A 0.0000/0.0000 0.0000/0.0000 03/20/94 Valve 43-75 X-85A 0.0000/0.0000 0.0000/0.0000 03/24/94 Valve 43-77 X-85A 0.0000/0.0000 0.0000/0.0000 03/24/94 Valve 30-45Y X-85B 0.0625/0.0625 0.0000/0.0000 03/17/94 Valve 30-45X X-85B 0.1501/0.1501 0.0000/0.0000 03/17/94-Valve 52-502 X-87A 0.0000/0.0000 0.0000/0.0000 03/16/94 Valve 52-503 X-87A 0.0000/0.0000 0.0000/0.0000 03/16/94 Valve 52-500 X-87D 0.0000/0.0000 0.0000/0.0000 03/16/94 Valve 52-501 X-87D 0.0000/0.0000 0.0000/0.0000 03/16/94 e v
.~ ' + y i V TYPE C TESTED COMPONENTS. U2C4 U2C5 AF/AL AF/AL Expiration Componsnt fsnetration fiREH SCFH Dat.e - e Valves 32-81/353 X-90 0.0547/0.0547 0.0000/0.0000 03/25/94 Valve 32-358 X-90 0.0000/0.0000 0.0000/0.0000-03/25/94 l Valve 43-250 X-91 0.0000/0.0000 0.0000/0.0000 03/17/94-i Valve 43-251 X-91 0.0900/0.0000 0.0000/0.0000 03/17/94 Valve 43-207 X-92A 0.0000/0.0000 0.0390/0.0390 03/25/94 i Valve 43-210A X-92A 0.0000/0.0000 0.0000/0.0000 03/25/94 i Valve 43-2101 X-92A 0.0000/0.0000 0.0000/0.0000 03/25/94 l Valve 43-208 X-928 0.0000/0.0000 0.0390/0.0390 03/25/94 i 8 Valve 43-210A X-92B 0.0000/0.0000 0.0000/0.0000 03/25/94 Valve 43-2101 X-92B 0.0000/0.0000 0.0000/0.0000 03/25/94 i Valve 43-34 X-93 0.0000/0.0000 0.0000/0.0000 03/24/94 i Valve 43-35 X-93 0.0000/O.0000 0.0000/0.0000 03/24/94' Valves 90-107/108/109X-94A/B 0.0000/0.0000 0.0000/0.0000 03/30/94 Valves 90-110/111 X-940 0.0000/0.0000 0.0000/0.0000 03/30/94-Valves 90-114/115 X-95A/B 0.0000/0.0000 0.0000/0.0000- .03/31/94 i Valve 90-113 X-95A/B 0.0000/0.0000 0.0000/0.0000. 03/31/94 Valves 90-116/117 %-950 0.0000/0.0000 0.0000/0.0000 03/31/94 .l Valve 43-22 X-960 0.0000/0.0000 0.0000/0.0000 03/24/94 s Valve 43-23 X-960 0.0000/0.0000 0.0000/0.0000. 03/24/94 Valve 30-134 X-97 0.0000/0.0000 0.0000/0.0000 03/20/94-l Valve 30-135 X-97 0.0000/0.0550 0.0000/0.0000 03/20/94 Valvc 52-506 X-98 0.0000/0.0000 0.0000/0.0000 03/17/94 Valve.52-507 X-98 0.0000/0.000' O.0000/0.0000 03/17/04 Valve 43-202 X-99 0.0000/0.00u 0.0000/0.0000 03/24/94.. -{ Valve 43-200A X-99 .0.0000/0.000( 0.0000/0.0000 03/24/94 j valve 43-2001 X-99 0.0000/0.0000 0.0000/0.0000-03/24/94 Valve 43-201 X-100 0.0000/0.0000 0.0000/0.0000 03/24/94. Valvo 43-200A X-100 'O.0000/0.0000 0.0000/0.0000' 03/24/94: Valve 43-2001 X-100 0.0000/0.0000 0.0000/0.0000 03/24/94 ) Valve 43-318 X-101 0.0544/0.0544 0.0000/0.0000-03/18/94 l Valve 43-319 X-101 0.0544/0.0544 0.0389/0.0389 03/18/94'- l Valves 43-317/341 X-103 0.0000/0.0000 0.0000/0.0000-03/18/94 l Valves 43-325/307 X-106 0.0000/0.0000' O.0000/0.0000 03/18/94 { Valves 30-46/571 X-l h 0.0000/0.0000 0.0000/0.0000 03/17/94 { Valve 30-49Y X-111 0.0000/0.0000 0.0000/0.0000 03/17/94 Valve 30-46AX X-112 0.0000/0.0000 0.0000/0.0000 03/17/94 1 Valve 30-47/572 X-112 0.0000/0.0000 0.0000/0.0000-03/17/94 l Valve 30-47AY X-112 0.0000/0.0000 0.0000/0.0000 03/17/94. Valve 30-47AX X-112 0.0000/0.0000 0.0000/0.0000 03/17/94~ Valves 30-48/573 'X-113 0.0000/0.0000 0.0000/0.0000 03/16/94 Valve'30-48AY X-113 0.0000/0.0000 0.0000/0.0000: 03/16/94- 's Valve 30-48AX X-113 0.0000/0.0000' O.0000/0.0000-03/16/94' Valve 61-110 X-114 0.0000/0.0000-0.0000/0.0000 04/01/94 i Valves 61-122/745 X-114~ 0.0000/0.0000 0.0000/0.0000 04/01/94- ,j .Velve 61-96 X-115-0.0000/0.0000- -0.0000/0.0000 04/01/94 4 5 t 9 m.
~ _7_ TYPE C TESTED COMPONENTS U2C4 U2C5 AF/AL AF/AL Expiration' Component _ Eenetration FCFH SCf]L .Date Valves 61-97/692 x-115 0.3558/0.3558 0.6786/0.0000 04/02/94 Valve 43-287 X-116 0.0000/0.0000 0.0000/0.0000-03/20/94 Valve 43-288 x-116 0.0000/0.0000 0.0000/0.0000 03/20/94 Valves 62-77/662 x-15 0.0000/0.0000-0.5103/0.0000 04/23/94 i Valves 63-84/23/344E x-30 0.3148/0.0000 1.6760/0.0000 04/16/94' Valves 62-61/639 x-44 0.0000/0.1456 0.0000/0.0000 04/15/94-Valve 62-63 x-44 0.0000/0.0000 0.0000/0.0000 04/15/94 valve 77-18 x-45 0.0000/0.0000 0.0000/0.0000 04/20/94 3 Valves 77-19/20 x-45 0.0000/0.0000 0.0748/0.01072 04/21/94 valve 77-9 x-46 0.0000/0.0000 0.0000/0.0000 04/21/94 Valves 77-10/84-511 x-46 0.0000/0.0000 0.0000/0.0000 04/21/94 Valves 70-87/687 x-50A 131.95/0.1751 0.0000/0.0000 04/25/94-Valve 70-90 x-50A 0.0000/0.0e)0 0.0 s0/0.0000 04/25/94 l Valve 26-1260 x-51 0.0000/0.0000 0.0392/0.0016 04/17/94 -l Valves 67-87/575A x-59 533.75/0.0000 84.0349/0.0000 04/10/94 i Valves 67-95/575C x-63 0.0000/0.0000 0.6743/0.0000' 04/10/94~ i Valves 31C-232/697 x-67 0.0000/0.0000 0.0000/0.0000' -03/26/94 Valve 67-131 x-73 0.0000/0.0000 0.0000/0.0000 03/19/94 ~i Valves 32-111/385 X-34 0.0000/0.0000 0.0000/0.0000 04/08/94 Valve 32-387-X-34 0.0000/0.0000 0.0000/0.0000 04/08/94 .I Valves 67-106/1523A x-58 0.0000/0.0000 0.3985/0.0000 04/06/94 valves 67-105/1523C x-62 533.75/0.0000 0.0390/0.0000' 04/06/94 Valves 72-40/215E/ .X-49A Passed Passed / Passed- -04/04/94 .i 215F/216E/216F Valves 72-41/217E/ x-49B Passed Failed / Passe 1 04/09/94 217F/21SE/218F l 2 Analyzer >:, sed Passed 03/28/94 'f A Train H l if I n j
c... . i 4 'I ENCLOSURE 3 f f TVA Commitment In the event that Unit 2 experiences a forced shutdown to Mode 5, components 2-FCV-67-87 and 2-VLV-67-575A will be leak-rate tested. 1 i i - l
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