ML20086S012
| ML20086S012 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 12/20/1991 |
| From: | Zeringue O TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9201030003 | |
| Download: ML20086S012 (33) | |
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December 20, 1991 O J %e'7enngue va mnunswuecer,op w n U.S. Nuclear Regulatory Commission ATTN Document Control Desk Washington, D.C.
20555 Centlement in the Matter of
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Docket No. 50-260 Tenneuce Vality Authority
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BROWNS PERRY NUCLEAR PLANT (BFN) - UNIT 2 - REQUEST FOR 10 CFR 50, APPENDIX J SCHEDULAR EXEMPTION In accordance with 10 CFR 50.12, TVA requests a one-time eFemption from the schedular requirements of 10 CFR 50 Appendix J. Sections II.D.2(a) and III.D.3.
Section II.D.2(a) and Section III.D.3 require Type B tests, except tests for air locks, and Type C tests to be performed at intervals no greater than two years during reat.ar shutdown for refuellug. We are requesting a one-time exemption to allow the performance of LLkT testing during the Cycle 6 refueling outage schedule to begin January 29, 1993.
This exemption request has been reviewed by the Plant Operations Revlev Committee an/. the Nuclear Steam Supply System Vendor.
During the Cycle 5 outage, LLRT testing was accomplished as the associated systems were being returned to service.
Siibsequent delays in the restart of Unit 2 resulted in a number of these tests being performed significantly in advance of the May 24, 1991 restart of Unit 2.
Therefore, the expiration of the test interval for some Type B and Type C testa vill necessitate a plant shutdown of as much as 30 days for testing prior to the Cycle 6 refueling outage. While the earliest expiration of the test interval is July 1992, load supply. planning considerations may require Unit 2 to shutdown sooner for LLRT testing. Approval of this one time exemption is requested to permit the realigtunent of the LLRT program with the BFN refueling outage schedule. Approval of this request vill alsc benefit the BFN ALARA program by eliminating the additional.
personnel exposure which would accrue during the performance of these tests prior to the Cycle 6 refueling outage.
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9201030003 911220
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o-2 O.S. Nuclear Regulatory Commission December 20, 1991 BrH han and will continue to make every effort to satisfy the Appendix J test requirements during the current test intsrval.
During two recent forced outages local leak rate tests were performed on_30 components for which the test interval vould have expired prior to the Cycle 6 refueling outage. Additional LLRT testing vill be performed during any forced outage of sufficient duration should one occur prior to the Cycle 6 refueling outage.
BFN's exemption request is contained on Enclosure 1.
summarizes the commitment made in thio letter.
If you have any questions, pidase contact Raul R. Baron at (205) 729-7566.
-Sincerely,
/
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/fup-n O. J. Zeringue i
Enclosure cc (Enclosure):
NRC Resident Inspector Browns Ferry Nuclear Plant Route 12, Box 637 Athens, Alabama 35611 Mr. Thierry M. Ross, Project Manager U.S. Nuclear Regulatory Commissicn One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852
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Mr. B. A. Wilson, Project Chief U.S. Nuclear-Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 P
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ENCLOSURE 1 REQUEST FOR A SCIIEDUIAR EXEh11"flON FROh! 10 CFR 50, APPENDIX J HROWNS FERRY NUCl. EAR PLANT UNIT 2 INTRODUCTION 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 Ill.D.2.(a) and Ill.D 3 for Browns Ferry Nuclear Plant Unit 2. Section Ill.D.2.(a) and Section Ill.D.3 require h'pe B tests, except fus for airlockr., and T)pe C tests to be performed at intervals no greater than two years during reactor shutdown for refueling. Browns Ferry Unit 2 was in cold shutdown from September 1984 until startup on hiay 24,1991. As left local leak rate test (LLRT) performance began July 30,1990 in preparation for Unit 2 startup, Due to a longer than expected return to power sequence, the as left LLRT program extended into hiny 1991. Since the next refueling outage for Unit 2 is not scheduled to begin until early 1993, the expiration of the time interval for some Type U t.nd Type C tests would force the plant to shutdown in July 1992 to perform Appendix J testing. TVA rescheduled the next planned outage from mid hiarch 1992 to January 29,1993. This schedule avoids extension of components that have demonstrated poor leak performance in the past. Type B and C tests were performed during two recent forced outages to aduce the number of components that would require an interval extension. TVA plans to continue to perform Type B and C testing during unplanned outages as conditions permit.
Tha amponents affected by this request are listed in Table 1. These components represent approximuely 44% of the LLRT program, hiost of the components affected are Type B tests or Type C tests on closed loop seismic class 1 and water sealed isolation valves that either account for an extremely small percentage of total Type B and C leakage or are not included in the Type B and C leakage total. Th: remainder of the components are air tested isolation valves.
The tests listed in Table 1 will be reperformed during the next refueling outage. This outage is scheduled to begin less than six months after the time interval for the first LLRT performed expires. This relatively small increase in test interval (25% which is permissible for other types of surveillances) does not significantly increase the risk to the public health and safety based on the expected performance of the subject components.
An analysis of past component performance indicates the incremental increase in leakage due to the extension is not a significant contributor to the tetalType B and C leakage limit. The components included in this request that have experienced significant degradation over the past operating cycle have been repaired or replaced. The cost of doubling radiation exposure to plant test personnel when compared to the minimal gain in assurance that the affected components have not rignificantly degraded is unnecessary based upon the present test results and anticipated incremental increases in component leak rates. The requested exemption would reduce both personnel radiological exposure and resources expended to cornply with the regulation without undue risk to the public health and safety.
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l Page 2 of 31 If Unit 2 is required to shutdown and de inert primary containment to perform local leak rate tests, a minimum of thirty days may be needed to perform various surveillance instructions. A heatup and cooldown cycle would be added increasing the probability of evens more like!y to occur during such evolutions. The length of a testing outage is heavily dependent on the rate of decay heat removal, since shutdown cooling must be removed from service to be tested. Eliminating a shutdown fc perform testing mid cycle and continuing operation until the next scheduled outage would result in a savings of approximately $8 million.
DESCRilrrION The first Cycle 5 as left LLRT on Unit 2 was performed July 30,1990; therefore, the maximum extension of the two year interval is 182 days. Prior to two forced outage that began October 18 and December 9,1991, local leak rate tests on 158 components i
performed between July 30,1990 and January 29,1991 required time interval extension.
ilowever, during these two outages which resulted in Unit 2 being shutdown for approximately 5 days,30 components were tested reducing the number of components i
requiring extension to 121. The listing below provides a breakdown of the number and types of components included in the requested extension. Components tested after January 29,1991 are not affected by this request.
Air Tested Components (Subject to 0.6La 1.cakage Limit)
Expansion Bellows 28 Electrical Penetrations 15 Bonnet / Packing 5
Isolation Valves 35 Flanges 7
Water Scaled Components (Subject to 28.65 CFil Technical Specification Limit)
Isolation Valves 5
Closed Loop Seismic Class 1 Components isolation Valves 26 I
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Page 3 of 31 The following chart shows the distribution of LLRT performance for Unit 2 Cycle 6 restart. The maximum required extension for each component is tabulated in Table 1.
LLRT Performance Comt ot4 pts Tested 60 51 -
$1 so 40
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30
.y.
19
. 19 co D -I~=-=~~--
O 12 ll 10 1
0 9
10 11 12 1
2 3
4 5
f, 7
l 90 l
91 1
TECIINICAL 13 ASIS 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) all light water reactors were on a nominal annual refueling cycle with relatively short refueling outages. Today most light water reactors are on an 18 month or two year refueling cycle with extended refueling outages. The intent of the regulation is for isolatica valves to be tested during refueling outages, not to require the unit to be shutdowm solely for local leak rate testing.
Performing local leak rate tests during refueling outages lowers radiation caposure to plant personnel and is consistent with the purpose of 10 CFR Part 20. During the October 18,1991 forced outage, conditions inside containment reduced the speed at which tests could be performed and involved significant heat stress and radiological hazards not normally present during refueling outages. A shutdown solely to perform leak tests is not consistent with the intent of either Appendix J or 10 CFR Part 20 and would result in at least doubFng the radiological exposure and the risks associated with the affected tests. Since the tests will be reperformed during the next refueling outage, the cost to personnel 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 remainder of the Unit 2, Cycle 6 operating cycle.
Page 4 of 31 During the extended outage, the Browns Ferry Appendix J program was reviewed and audited on several occasions. Various components were identified that were not being tested in accordance with Appendix J. Prior to restart, numerous actions were taken to upgr2dc the Appendix J program. The following is a summary of actions taken to upgrade the program:
. Block valves, test connections, and vent valves to enable isolation valves a be i
tested in the accident direction were added.
. Black valves and test connections to facilitate testing of bonnet and packing seals were added.
Valves were reoriented to allow packing and bonnet seah o be tested during the t
normal Type C test.
. Lines no longer used were capped to remove potential leak path.
. Changes in valve type were made io improve leakage characteristics.
Stainless steel overlays were added to ventilation valves to improve leakage characteristics.
. Various repairs, replacements, and modifications of historical problem valves to improve leakage performance were conducted during the cycle 5 outage.
As a result of these upgrades, modifications, and improved maintenance practices, the l
possibility of significant degradation of containment components is reduced.
The projected incremental increase in the total Type B and Type C Wak rate due to the extension is estimated in Table 2 utilizing historical local leak rate data from Unit 2, Cycles 4 and 5. Based on the past performance of the affected components, there is rear.onable assurance that no significant degradation would occur during the extension interval. The condition of the components is, therefore, not expected to change significantly over the extension period of approximately 25-percent of the two year interval specified in Appendix J. Furthermore, the two-year interval specified for Type B and Type C tests was based on two years of exposure to service conditions. For the months prior to startup, these components were not exposed to service conditions. This I
should further reduce any potential degradation of these components.
Many of the components associated with this extension request cannot be tested at power due to their intended function and location. The specific reason why testing at power is impracticable is provided for each component in the notes to Table 1. BFN has and will continue to make every effort to satisfy the Appendix J requirements during the current test interval. Additional LLRT testing will be performed during any forced l
outage of sufficient duration should one occur prior to the Cycle 6 refueling outage. The current prioritization for forced outage leak rate testing is provided in Table 5.
l 1,nclosure 1 Page 5 of 31 Air Tested Components ine:uded in the extension request are the following types of air tested components flanges, expansion bellows, electriuol penetrations, bonnets and packing, and isohth n valves. Flanges, expansion bellows, electrical penetrations, and bonnets and, Jacking leakage account for only a very small fraction of Type li and C leakage. llased on 3
historical data lor these components, leak rates did not increase significantly over the last operating cycle. These results provide assurance that say 'ncremental increase in leakage occurring during the extension period would not result in unacceptable camponent leakage rates. Isolation valves included in the extension have generally met the reference leak rates assigned based on valve size lleference leak rates are administratively assigned to cuch component to help maintain leakage below associated allowable limits. A comparison of measured leakage to the reference leak rate for the particular component aides in determining if repain are necessary and provides a means for identifying potential problern valves. Efforts are made to maintain leak rates below the reference values to ensare significant degradation of containment components does not occur. Of the 35 air tested isolnlon valves included in this extension request,10 valves failed to men assigned reference leak rates when cycle 5 as found tests were performed. These components viere repaired (2 69 579,2 IICV-73 23,2 73-603, 2 FCV-71-2,2 FCV 713), modified (2 3 554), or replaced with a different type of valve (2-68-508,2-68-550,2 68 555,2 FCV 73-45). Subsequent leak tests on these components were acceptable and well within established reference leak rates. The current total Type B and C leakage is less than 17% af the 0.612i limit (655.9 scfh).
Water Scaled Isolation Valves Four of the five water sealed isolation valves included in this extension have not experienced any signi'icant degradation in the past and account for only a small fraction of the Technical Specification allowable limit of 28.65 cf1L There is no contribution to total Type B and C leakage due to these components. These results provide assurane that any incremental increase in leakage due to the extension would not result in any significant leakage through any valve. The remaining water scaled isolation valve was added to the Appendix J program this ouuge. The current total water sealed leakage is less than 1.5% of the Technical Specification limit.
Closed Looo Seismic Class 1 ' solation Valves Closed Imop Seismic Class I components of the Residual licat Removal System and
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Core Spray System are water filled post accident and are required to be tested, but are not included in the 0.612 leakage limit. There is no contribution to total Type B and C leakage due to these components. Of the 26 valves of this type, only 3 vaives failed to meet the assigned reference leak rate. These valves (2 FCV-74 57 and 2 FCV-74-58 tested simultaneously and 2-FCV 75 26) have been repaired and subsequent tests were completed satisfactorily. Based on past performance and recent test results any incremental increase in leakage due to an extension would not result in unacceptable leakage through these valves, b
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Page 6 of 31 Mw Components As a result of Appendix J program upgrades,6 air tested components, I water scaled component, and 8 closed loop scismic class I components were added to the prol', ram.
No historical data are available for these components; however, the integrity of the 6 air tested components was demonstrated during the Type A test perlormed in March 1991.
The 8 closed loop seismic class 1 components added to the program were tested upon completion of modifications to make these valves testable and at other times throughout the extended outage. No significant problems Live been experienced with these valves since they were included in the Appendix J program. During an October 18,1991 forced outage, these valves were tested to demonstrate valve closure for ASME Section XI. No leakage through these valves was identified.
JUSTIFICATION 10 CFR 50.12 states that the commission may grant exemptions from the requirements of 7
the regulations contained in 10 CFR 50 provided that
.The exemption is authorized by law;
.The exemption does not present an undue risk to the public health and safety;
.The requested exemption will not endanger the common defense and seci rity; Special circumstances are present as defined in 10 CFR 50,'.2 (a)(2).
q
- 1. The Requested Exemption is Authorized by Law The Commission is rmthorized by law to grant this exemption, s
- 11. The Requested Exemption Does Not Present an Unduc Risk to the Public Ilenith and Safety The intent of sections Ill.D.2.(a) and Ill.D.3 of Appendix J is to ensure containment integrity is maintained. Based on the following information, the exemption requested vill not significantly affect the ability of the individual primary contaimnent components to perform their safety functions.
- 1. The valves and components for which the extension of the two year interval is beiir, requested are considered to be leak tight and in good condition. The leak tight condition of these components has been verified by Type B and C local leak rate tests and again for most by the Type A test conducted on unit 2 in March 1991, Based on the present containment leak rate that accounts for less than 17%
of the 0.6-percent 12 limit, TVA believes the remaining margin is sufficient to ensure any incremental increases in leakage due to the extension will not result in unacceptable as found test results.
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_ _ _ _ _ _ ~. _ _ _ _ - _ _ _. _ _._
Page 7 of 31
- 2. Ilased on historical data, any incremental increase in leakage due to the extension will be small (less than 18% of 0.612). Improved maintenance practices implemented during the unit 2 cycle 5 outage, including motor operator testing (hiOVATS) of containment isolation valves, provides increased assurance that these components will perform their safety function.
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- 3. Significant changes and improvements were made to the Browns Periy LLRT l
program since the unit was shutdown in 1984. Numerous components previously untested were added to the program as a result of program reviews. Individual LLRT procedures were upgraded and detailed valve line ups, isometries, and draining and venting instructions were added.
- 4. hiaintenance and modification of components with poor leak performance history was performed to improve subsequent performance of these components.
Post modification and post maintenance tests were completed satisfactorily.
- 5. hiany of the components for which the exemption is requested were included in the 'Iype A test performed in hiarch 1991. This test indicated a containment leak rate of 0.24% per day, which is we" below the 1.5% per day limit.
Ill. The Requested Exemption Will Not Endanger the Common Defense and Security The common defense and security are not affected by this request for exemption.
IV. Special Circumstances are Present Which Necessitate the Request for an Exemption to the Regulations of 10 CFR 50, Appendix J, Sections III.D.2.(a) and Ill.D.3.
Per 10 CFR 50.12(a)(2), the following special ciremastances are present-
- 1. Application of the regulation in the particular circumstances present would not serve the intent of the regulation. The intent of the regulation is to assure l
containment integrity tarough component performance. The expected incremental increases in component leakage due to the extension are small (less than 18% of 0.6 La). Assignment of the projected increase in total leakage due to the extension to the as left leakage total reduces the margin between as left leakage and 0.6 La by less than 22 percent. Since operation would be allowed for two years with less margin than is present even with the additional leakage due to the extension added to the ns left total, the requested _ exemption does not conflict with the intent of the regulation. Thus, the exemption to defer testing of the subject components until the next scheduled refueling is appropriate.
- 2. Compliance with the regulation would result in undue hardship or other costs that are significantly in excess of those contemplated when the regubtion was adopted. De 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 L
Page 8 of 31 were not provided; thus increasing the likelihood of a plant shutdown to perform LLRTs. llowever,it was not the intent of the regulation to force a shutdown solely to perform Type B and C testing. A requirement to shutdown to perform LLRTr, even though the projected incremental increase in leakage due to extension of the test interval to the next scheduled refueling outage is minimal, would represent undue hardship and excessive costs in the form of increase personnel radiological exposure, lost revenues, and higher costs associated with two outages instead of one. Eliminating a shutdown to perform testlug would also result in a nving of approximately $8 million. Furthermore, a heatup and cooldown cycle is eliminated by increasing the test interval and would reduce the probability of events that are more likely to occur during such evolutions.
- 3. The exemption would provide only temporary relief from the regulation and TVA has made a good faith effort to strictly comply with the regulation. This exemption is being requested as a one time schedular exemption to allow Unit 2 te operate until the next refueling outage scheduled to begin January 29,1993.
This request is a result of a longer than anticipated return to power sequence, in addition, by performing LLRT testing during forced outages, TVA has made a good faith effort to comply with the regulation.
SAFETY IMPACT The extension of the LLRT test interval does not impact the probability of occurrence of any accident.
The present containment leakrate represents less than 17% of the maximum Type D and C leakage rate of 0.60 La allowed by TS. Thus a severe 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. 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 ability to perform its intended function will be maintained, no new accident precursors are generated, and therefore no new or different kind of accident scenarios are created.
The present margin between the most recent as left total leakrate and the 0.60 La limit is sufficient to allow for the additional projected leakage due to the extension. Therefore, extending the LLRT test interval will not result in a significant reduction in the mari;in of safety.
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Page 9 of 31 CONCLUSION The valves and components for which the extension of the two year interval is being requested are considered to be leak tight and in good condition. The leak tight condition of these components has been verified by 'Iype B and C local leak rate tests and again for most by the Type A test conducted on unit 2 in March 1991. Based on the i
present containment leak rate that accounts for less than 17% of the 0.61.a limit, TVA believes the remaining margin is sufficient to ensure any incremental increases in leakage due to the extension will not result in unacceptable as found test results.
Based on historical data, any incremental increase in leakage due to the extension will be small (less than 18% of 0.6 La). Improved maintenance practices implemented during the unit 2 cycle 5 outage, including motor operator testing (MOVA13) of containment isolation valves, provides increased assurance that these components will perform their safety function.
On the average, as left leak rates are less than 25% of the established reference leak rates for the components listed in Table 1. Since the maximum extension requested is relatively short in comparison to the two year test interval (approximately 25%), it is unlikely that substantial degradation of containment components leading to failure of the containment to perform its safety function would occur.
Based on the discussion above, TVA concludes that the extension of the two year interval for the components listed in Table 1 will not impair valve operability or significantly degrade the integrity of primary containment and would not significantly increase the risk to the health and safety of the public.
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Page 10 of 31 1.lSTING OF TAllLES l
Tabl e 1................................
Components Requielng Extenslon l
Ta bl e 2................................
Projeeted Type il and C Ixak Rates Tabl e 3................................
Projected Type C Seismie Class 1 Leak Rates Ta bl e 4................................
Unit 2 Cycle 5 As.Found/As len Test Results Tabl e 5................................
Unit 2 Forced Outage Testing Priority I
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Umlosule 1 l' age l'2 of 31 i
i TABLE 1 COMPONENTS HEQUIRING EXTENSION
'ITPE B TI:51f'D COMPONF.S1f COMPONI:NT s1NI?!RATXtN DPSCRD'110N i:XP.DA1E
$l#
IX11NilON Days / Notes 101JIMS X.7 A trilmarilic lows M3 thw A 1/2/93 g 4"lle 27/I It!!J OWs X 7A Outteard Bellows ha Line A 1/2/93 27/t 11111Im3 X.7tl Intxwd Bolkm: M5 Lire il 1/19/43 10/l e
IU1 Jim 3 X 78 OutboarJ Bellows M5 (Jne B 1/19/93 10/1 lullim3 X 7C Intuard Itellowa MS the C 1/I9/91 10/1 lulIIm3 X.7C Outtuard llellose MA 1.ine C 1/29/93 10/1 lullins X 7D inbosed Bellowa M3 Line D 1/l_9/93 10/I ntIJr#3 X 7D Outtuerd Belkiws M!i IJns D 1/19/93 10/l lu1Jims X.8 Intmatd Bellows MS Drula 1/2/93 27/l fuljIm3 X.8 Outtmard BeJiews MS IEsin 1/2/93 27/l lu!Jims X.9 A Inboard fiellows l*W l.tte A 10/10/92 1Il/l 1011I 2 3 X 9A Outboard Itellous IV IJew A
!0/10/92 111/l fulJims X.9B inbond Bellows FW Line B 10/10/92 III/1 1011I 2 3 X 911 Outboard Bellows IW IJne B 10/10/92 11I/1 Iuljim3 X.10 Intowd Bellows RCIC Steva 10/1/92 120/l fullims X 10 Outtmed Bellows RCIC Stewn 10/1/92 120/1 lutIIm3 X ll Inbowd llantows IIPCI Steam 1/20/93 9/I lullims X.Il Outboard Bellous itPCI Stews i/20/93 9/1 lu1]Im3 X.I2 Inboard Bellows 3DC Saction 12/I#192 42/l fu1Jims X 12 Outboard !! allows SDC suction 12/18/91 42/l IMIJim3 X.13A Inboard Bellows RilR Dischtge 12/18/92 42/1 IMIIIm3 X.13 A Outboard Bellows RilR Discharge 12/18/92 42/1 l
1111Jims X.13 B tr& erd Bellows Rl!R Discharp 12/16/92 42/1 IVIJimi X.1 s p Os card llellows RilR Dicharg;e 12/19/92 42/1 IPflim3 X 16 A Inhoard Bellows CS Discharge 12/18/92 42/1 IUllims X.16 A Outboard Bellows C$ Discharge 1.1/18/92 42/1 141 Jim'S X 16B Inhoard Belloe CS Dis harge 12/I8192 42/1 lu111m3 X.16B Outboard Bellows C3 Discharge 12/11/92 42/1 Ikl1Wi!!KATION X.1008 Neutron Moultoring 9/16/92 g 2/ Fin 133/2 Ein1f! RATION X.100C Neutron Monitoring 9/18/92 133/2 EliWITRA110N X.100D Neutron Monitorin6 9/18/92 133/2 1
EI1NLTRA110N X.100E Neutron Monitoring 9/18/92 133/2 EI1' NIT! RATION X.100P Neviron Monitoring 9/10/91!
131/2 Ikli:NITIRATION X.1000 Neutron Monitoring 9/16/92 135/2 IkPlWl?fRATION X.103 CRD Position Indication 9/18/92 133/2 ILl1NiflRATION X.104 D Therrnocouples 9/l$/92 133/2 El%3?lRAT10N X 104E Indication A Control 9/1R/92 133/2 Ekl1NI?iRATION X.104F Indication & Control
-9/18/P2 133/2 1kPlWl? IRA 110N X.10$ A Power 12/11/92 49/2 E11NLTRATION X 1088 CRD Position Indication 9/18/92 133/2 IkF"Wl?!KATION X.110 A Pow er 9/20/92 111/2 IklYN!?! RATION X llDil '
CRD Position Indication 9/1B/92 133/2 Ikl1NITIRAT10N X 219 PSC Vacuum Breakers 9/20/92 13U2 l
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Pap 12 of 31 3
'INillE 1. (CONTINUED COMPONENTS ItEQUll(ING EXTENSION 1)PE B 11311:p COMPOSINlis 1
COMP 03 LNT Pl:NLTRATION D13CRWI10N IXP. DA'n-:
5W IN1N5lON 3
Days /Nc te s 11ANE N/A shcas 1.9g Attess Cover 0*
1/17/93 g 2/llla 12/4 11NK21 N/A
$ heat 1.ug Actuse Cover 43' I/17/93 12/4 11ANG N/A Shear 1.93 Access Covw 90' l/16/9J l3/4 II ANT N/A hv Lug Access Cover 135' t/16/9s 13/4 11N G:
N/A War Lug Aness Cover 270*
1/11/93 12/4 11Nn:
N/A Ww leg Aurs: Coser 313' I/17/93 12/4 DONN!!!!l'ACMLNG X.218 2.f CV 71.$9/601 1/20/9,1 g 4Tilb 9/3 IIONN1'1/PACbNO X.220 2.):CV 73 64/642 1/20/9) 9/3 110NN13!i' ACKING 71-32 RCIC Vanit.m Purnp Distharge 11/26/92 6 3/71 e 64/3 IlONTETACKNO 73 24 IIPCI TurNne !!thaust Disin 8/25/92 g. J /7.le 167/3 IlONS).T 73 23 l!PCl T6atnw 1:thaust I/13/93 g-)/7.4h 16/6 II. ant 37 64 19 Coritairituena Ventilaticm 1/26/93 g-3/646 3/7 t
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Page 13 of 31 TAllt.E 1, (CONTINUED)
COMPONENTS REQUIRING EXTENSION TYit C TI'.511:11 COMPONi:Ni s COMPONIWT 11NI'!kA110N iaWCRWDON IXP. D ATE
$18 IXMW$lON Days /Notts 2 2+1381 X 20 Demiseralized Water 7/31/92 g 3/2 182/4 2 2 1192 X.20 DoenJnerahted Water 7/31/92 g 3/2 182/4 23554
?. 9A Reactat Feedwates A l/15/93 g.33a 14/4 2 3.$$4 X 9A Rescu liedwsw.A I/15/93 8 3/3a 14/4 2-ICV 13 45 X 9A UDCl Injection 1/15/93 g 3/la 14/4 2 +3 112 X 9B Rsacw Feeduster 14 9/14/92 g.3/3b 137/4 2 3-568 X 914 Reactor Feedwater A 9/14/92 g.3/3b 137/4 2 69 579 X-9H MWCU Raurn 9/14/92 3.)/3b 137/4 2.FCV 7140 X 9B RCIC ldersion 9/14/92 g.3/3b I37/4 2 85 376 X.9H CRD Rewrn 9/14/92 g.3/36 137/4 2 32 336 X 22 Drywell Ceuol Ak Surp)y 8/5/92 3 3/32b 177/4 2 32 2163 X 22 Drywell Control Air 56:yty 8/20/92 g 3/112b 162/4 2 84 617 X.22 C AD!/X'A Tis in 8/5/92 g.3/32b 177/4 2 63 125 X 42 Standby 1.gl4 Control 8/7/92 g 3/63 175/4 243 526 X 42 starwih3 uguld Control 8/7/92 g.3/63 17$/4 2 69 301 X 37C RCP 5 cal Wwer 1/5/93 g 3/6ta 24/4 2 68 350 X 37C RC9 &ul Waer 1/5/93 g.3/6Ba 24/4 2 68 523 X 38C kCP&ealW ar 8/4r92 3 3/65b 178/4 but.$5$
X StC RCP Seat Wee 3/4/92 g.3/68b s*/8/4 2 lCV49.1 X 14 RWG1 Suction 9/5/92 g.3/69 146/4 2 FCV.to 2 X 14 kWCU $vctbo 9fS/92 g.3/69 146/4 2JCV 70 47 X 23 ABCOV Wwn 12/3/92 3 3/70
$5/4 2 70 506 X.24 RitCCW 59Wy 8/$/92 g.3/70 177/4 21 CV.11 2/3 X 10 RCIC $uan $'4t y 1/24/93 3 3/71e 5/4 l
2IICV 13 23A03 X 214 tiPCI Turtbe Eahrut 1/13/93 g 3/73b 16/3 2fCV.*84 47 X 12 RIIR $hudown Coohng 10/30/92 g.3/7 4 g.
91/4 2 FCV.74-41 X 12 kHR Shs; dawn Coutmg 10/10/92 g.3/74g 91/4 2 14 661/662 X 12 Ri!R Shytdown Coohng 10/30/92 3 3/74g 91/4 2-FCV 7MA X 18 Dtywell Iloor DratA My 11/30/92 g.3/77a 60/4 2 l>CV.77 28 X 18 Drya' ell hw Draire Smp -
11/30/92
- g. 3 /7 7 a 60/4 2-FCV 7715 A X 19 Dr)well Eqelpment Dram Sump '
11/30/92 g 3/77b 60/4 2 FCV.1715h X.19 Drywell Eqdpment Disin Sump 11/30/92 g 3/77b 60/4 s
e linclosure 1 l' age 14 of 31 TAllt.E 1, (CONTINUED)
COMI'ONENTS REQUIRING EXTENSION T Yl'l: C TI'hil:ll COMI'ONi:N18 (W All:R El:All:D)
COMIONi'.NT 11WirillATION DISCRIF110N IXP.DA111
$14 IXil:NslON Days / Notes 211CV 7132/$92 X 221 RCIC Yaruum Pump Discharge 11/26/92
- g. 3 /71 e 64/2 2.llCV.73 24/609 X 722 IIPCI Turtee I:thaust theiti 8/13/92 g.3 /7 3c 167/3 2 ICV-71 15 X 227A RLIC Pump sucthei 1/23/93 g.3/71d 6/3
_ - - -. - ~ _ - _. -.
r Page 15 of 31 TAlli.E 1, (CONTINUEl))
COMI'ONENTS REQUIRING EXTENSION f
TYPI: C TP.5TI.D COMPONrNT8 (El:lkMIC CLA55 I)
COMPONILNT IENI.TRA110N D13CRIP!10N IXP, DAlU
$18 IXil:N$10N Days / Notes 2 ICV 74 53 X 13 A RIIR Return 11/3/92 g. 3 /7 4 a 87/4 2 ICV.74 54 X.13A RilR Retuti 11/3/92 3 3 Dea 87/4 2.l CV.74 57/$ 8 X.2tl A RilR Containment $ptay 11/5/92 g.3/74b 85/5 2 FCV-l4 60 X 39B Rilk Contatament $ pray 11/2/92 3 3/74c 08/5 2.l CV.74 61 X.39B RilR Containment $ pray 11/2/92 3
- 3 /74c 88/5 2.f CV.74 67 X.13tl kilR Return 11/1/92 s.3/7 4d 89/4 2 FCV 74 68 X 13B Rilk Return 11/9/92 g.3/7 4d 81/4 2 lCV 74 71/72 X.21111 kilR Containment spay 11/13/92 3 3/74e 75/5 2 FCV.74 74 X.39A RilR Containment $ pray 11/1/92 3 3/74f 89/5 2 ICV 74 75 X 39A RilR Containment $ptay 11/1/92 g 3/74f 89/5 2 74 792 N/A RilR PSC llend Tars Tie-in 9/8/92 3 3/741 143/5 2 74 804 N/A RilR PSC llend Tara Tie in 9/8/92 g.3ndi 143/5 2 74 802 N/A kilR PSC llcad Tank Tie in 10/24/92 s.3/74]
97/5 2 14 803 N/A RilR PSC licad Tank Tle-in 10/24/92 g.3/74J 97/5 2 FCV.75 25 X 16 A Core Spey injection 8/9/92 g.3n$a 173/4 2 3 CV.73 26 X.16 A Core Spey injection 8/9/92 g.3/75a 173/4 2.FCV.75 53 X.1611 Core Spey injection 8/10/92 s.3D5b 172/4 2 FCV.75 54 X 16B Core Spey injection 8/23/92 3 3M5b 157/4 2 FCV.73 57/58 X.227A P$C 14 vel C<mtrol 9/4/92 g.3D5e 147/5 2 75 609 N/A PSC llend Tank Tie in 4/29/92
- g. 3/75 d 153/5 2 75 610 N/A PSC Ilead Tank Tie-in I/29/92 g.3/75d 153/5 2 75 606 N/A PSC llead Tank Tie-in 8/28/92 3 3/75e 154/5 2-75 607 N/A PSC llend Tank Tie.in 8/28/92 g.3D$e 154/5 4
i l
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l Page 16 of 31 TAlllE 1, (CONTINUED)
I COMPONENTS REQUIRING EXTENSION Notes:
- 1. Expansion bellows cannot be tested at power due to heat and radiological conditions.
- 2. Electrical penetrations can be tested at power, but may unnecessarily increase the potential for challenges to safety systems.
- 3. These components cannot be tested at power because it would require entering a Limiting Condition for Operation in order to perform the tests, in addition, other Surveillance Instructions must be performed in order to demonstrate operability.
Performance of these Surveillance Instructions in order to accomodate leak rate testing represents unnecessary challenges to safety systems.
- 4. Testing of these components requires drywell entry; therefore, these components cannot be tested at power.
- 5. Cannot be tested at power due to system alignments required for testing.
- 6. Can be tested at power, but requires scaffolding to be crected in the IIPCI room.
- 7. Can be tested at power.
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..,;3 Page 19 of 31 kh@'S':@
TAllLE 2, (CONTINUED) 4 MOJECTED 'lYPE 11 AND C LEAK RATES M
%, ~ i,Y i
.40TES
- 1. A new seat was installed in 2-69-579 during Cycle 5. Subsequent testing was satisfactory.
- 2. 2-ee 15,2-68 523,2 68 550,and 2-66 508 were cut out and replaced to improve leakage performance. Subsequent testing was satisfactory.
3.23554 was modified d ving ti.. @cle 5 outage to impron leakage performance.
- 4. 2 FCV-7M5 u as replaced with a different type of valve during Cycle 5 to improve leakage performance.
- 5. 2-IICV-73 23/603 required extensive maintenance to meet air test acceptance criteria.
6,2 FCV-71.2/3 failed ttle cycle 5 as-fount it due to a large packh g leak. Packing has been modified and is now live load type. Subsequent testing was satisfactory.
The following general notes am, applicable ti a 2 in its entirety:
e
- 1. The average length of extension requested is 115 days (16% extension).
- 2. In accordance with ANSI 56.8, measured leak rates that are below the calculated test error are reported as the test error.
- 3. The extended interval between as-found and as-left tests was due to the extended Cycle 5 ou: age.
=
a TABLE 3 PROJECTED T Pi' C f EISMIC CLASS 1 LEAK RATES Page 20 of 31 c us 5 c,c.e 5 A.-L.n cyee 4 r
Ct34U(NT AsLeft tR As Lou Date As Found LR As Found Date A
No. of Days Alcay Days EA1erried As. Lee LR As Lou Date Prejucted LR A Mar PLA Re erence LR % Reference LA 8
Sestric Ctans i Cornpanems 2 74-53 0.0198 1G0/83 0.0477 12/8/84 0.0279 688 0.0000 87 0.009 11/3/90 0.0421 1.2 0.75 %
2-74-54 0.5085 9/2/82 0.27 12/8/84
-0.2385 828 0.0000 87 0.549 11/3/90 0.5490 0.0000 1.2 4F.75%
2-74 57/58 0.4 A 1 12/31/82 48.6106 10/28/94 48.1784 667 0 0722 85 0.396 11/5/99 592647 6.1397 0.9 86.00 %
)
2-78-60/61 0.01 :.
10/5/82 0.0144 12/9/94
-0 D036 796 0.0000 88 0.3375 11 r2/GO 0 3375 0.0000 06 56.25 %
2-74-67 0.072 9/2/82 0 2286 11/2/84 0.1566 792 0.0002 89 0.2565 11/1/90 0.4184 1.2 21.38%
27468 0.108 9'2/82 0.243 11/2/84 0.135 792 0.0002 81 0.426 11/9 r90 0.5742 0.0139 1.2 36.33 %
2 74-71/72 0.1149 10/6/82 0.3555
- 0/28184 0.2.36 753 0.0003 75 0.576 11/15/90 0.8332 0 024.0 06 96.00 %
2-74 74/75 0.135 9/2/F2 0.0036 6/23/85 1.1314 1025 0.0000 89 0.6075 11/1/90 0 6075 0.0000 06 101.25%
j 2-74 792 N/A N/A N/A NIA N/A N/A N/A 143 0.0056 9/8/90 0.1000 0.fc00 0.1 5.60 %
l 2 74-804 N/A N/A N/A N/A N/A NI#.
NfA 143 0.0036 9/8/90 0.1000 0.1 3 60 %
j 2-74.802 N/A N/A N/A N/A N/A N/A N/A
.97 0.0036 10/24/90 0.1000 0.7000 0.1 3 60 %
2-74-803 N'A N/A N/A N/A N/A NA N/A 97 0.0036 10/24/90 0.1000 0.1 3 60 %
2 75-25 0
9/4/82 0.0063 6/23/85 0.0063 1023 0.0000 173 0.135 810/90 0.1406 0.6 22.50%
2-75-29 0.0225 9!4/92 2.t M 6/23/S5 2.1105 1023 0.0021 173 0.0225 8'9/90 1.8854 0.3569 06 3.75 %
2-75-53 0.0225 9/4/82 0.0M 4 2/10/e 5 0 0162 890 0 0000 172 0.1125 8/10/90 0.1125 0.6 18 75%
2 75-54 0.405 9/4/82 0.1278 2/10/85 0.2772 890 0.0000 157 0.198 8/25/90 0.1980 0.0000 09 33.00 %
2 75 57/58 0.261,
'3/4/82 0.0063 3/16!85
-0 2547 924 0.0000 147 0.009 9/4/90 0.0090 0.0000 0.15 6.00 %
I 2 75-609 N/A N/A N/A-N/A N/A N/A N/A 153 0.009 8/29f90 0.1000 0.f0C0 0.1 9 00 %
2 75-610 N/A N/A N/A N/A N/A N/A N/A 153 0.0036 8/29/90 0.1000 0.1 3.60 %
2 75 606 N/A N/A N/A N/A N/A N/A N/A 154 0.0056 8/28/90 0.1000 0.fcco 0.1 5.60 %
2-75 607 N/A N/A N/A N/A N/A N/A N/A 154 0.0027 8/28/90 0.1000 01 2.70 %
g,g3ee Searnic Class iPath h 25.95%
Average % of Reference LR (A>Left) 4;-
~
Ei.dosure 1 Page 21 of 31 4
PROJECTION METilODOLOGY UTILIZED FOR TAllLES 2 AND 3 The following methodology was used to determine the projected leak rates (Ill).
- 1. Unit 2 c,5 cle 4 as left data and cyie 5 as-found data were used to obtain the increase in leak rate over the operating cycle (D).
- 2. The !? crease in leak rate was then divided by the number of days between the as-left end avfound dates (D/ day).
- 3. The D/ day for each component was multiplied by the number of days of the requested extension plus the two-year interval to obtain the projected LR.
[
- 4. The increase in the total maximum path leak rate (D Max PLR) was then determined u',ing plant instructions for guidance.
The following conventions were used in calculating the total maximum path leakage rate increase and projected component leak rates.
- 1. All D less than zero were considered to be zero for the purposes of these calculations.
- 2. Twelve valves included in the extension were added to the Appendix J program in cycle 5; therefore, no historical information was available. The projected leak rate for these components was considered to be the reference leak rate.
- 3. Expansion bellows, flanges, and electrical penetrations were not considered as T;
individual components. Historical information indicates no significant increases in f
as found leak rates. Total as-found and as-left leak rates for all electrical pen Q
penetrations, flanges, and all bellows penetrations were used in the calculations, y
C
- 4. The bonnet and packing tests performed an 2-HCV-71-32 and 2-IICV 73-24 were added to 111e Appendix J program in cycle 5. No historical information is available.
However, since resilient seals that were part of the Appendix J program have not been a problem in the past, no significant increase in leakage for these components is anticipated.
E mi
Page 22 of 31 PROJECI'lON METilODOLOGY UI'lLIZED FOR TAllLES 2 AND 3,(CONTINUED)
- 5. Projected leak rates for Seismic class I components that are water filled or in service during a design basis accident were calculated; however leakage through these components has no impact on the Type Il and C leakage limit.
- 6. 2 IICV-73 23/603 were previously tested with water instead of air. Ilistorical data with air as a test medium are not available. The projected leak rate for these components was considered to be the reference leak rate.
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Page 31 of 31 TAllLE 5, (CONTINUED) UNIT 2 FORCED OUTAGE TESTING PRIORITY Notes: Y
- 1. Electrical penetretions will be tested as the outage schedule permits as filler work.
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- 2. Expansion bellows will be tested as the outage schedule permits as filler work after all electricel penetrations are tested.
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- 3. Shear lugs are located at the top of the drywell. IIigh temperature and radiation conditions at this location present a significant risk to personnel.
- 4. High coolant and component temperatures may adversely affect test results and 4
_ personnel safety,
- 5. RCP pump seat water :s isoir.'ed to perform this test. System fill and venting is required prior to system return to service.
- 6. Requires disassembl:' of sump pump discharge piping. High dose rates, high contamination levels, and heat stress conditions may be present.
l
ENCLOSURE 2
SUMMARY
OF T11E COMMITMENT MADE IN Tills LETTER Additional LLRT testing will be performed during any forced outage of sufficient duration should one occur prior to the Unit 2, Cycl:: 6 refueling outage. i l l l I}}