3F0595-02, Requests one-time Schedular Exemption from Requirements of 10CFR50,App J, Primary Reactor Containment Leakage Testing for Water Cooled Power Reactors, Re ILRT
| ML20083R585 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 05/19/1995 |
| From: | Beard P FLORIDA POWER CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 3F0595-02, 3F595-2, NUDOCS 9505300084 | |
| Download: ML20083R585 (14) | |
Text
_ _ _ _ _
l Florida l
Power CORPORATION NWA 1
f I
May 19, 1995 3F0595-02 l
U. S. Nuclear Regulatory Commission l
Attn:
Document Control Desk l
Washington, D.C. 20555 I
Subject:
One-Time Schedular Exemption Request from 10 CFR 50, Appendix J l
Reference:
A. FPC to NRC, 3F0388-16, letter dated March 21, 1988 i
B. FPC to NRC, 3F0192-16, letter dated January 29, 1992
Dear Sir:
Florida Power Corporation (FPC) is hereby submitting a one-time schedular exemption request from the requirements of 10 CFR 50, Appendix J,
" Primary Reactor Containment Leakage Testing for Water Cooled Power Reactors," regarding Integrated Leak Rate Testing (ILRT) testing frequency for Crystal River Unit 3 (CR-3). The proposed exemption would allow CR-3 to perform the next ILRT during our Refueling Outage 11 (Rll) currently scheduled for Spring of 1998.
The attachment includes a description of the proposed exemption request, the reason for the request and its basis. The basis provided in the attachment provides a regulatory review section that evaluates the applicability of 10 CFR 50.12 to the request, the evaluation concludes this proposed exemption meets the requirements of 10 CFR 50.12; provides CR-3's Types A, B and C testing history which justifies the proposed reduction of ILRTs during the current 10-year service per.od; describes the structural capabilities of the CR-3 containment and provides a probabilistic safety assessment.
{
{
i 9505300084 950519 PDR ADOCK 05000302 p
PDR CR.STAL n!VER ENEJKlY COMPLIx. 15760 W. Power uno Street. Crys.nl FWer. Florida 344284708. (904) 7954486
'l A Fhmda Progress Company
.(
I i
)
i 1
a
)
'i ;
-U. S.' Nuclear.RGgulatory Commission
' ~
.3F0595-02~
>r Page 2 i
a FPC.has recently adopted the. Improved Technical Specifications (ITS). The ITS requirements for Type A testing are to follow the requirements of Appendix J with approved exemptions. Therefore, no license amendment is required.
. Sincerely, t
b
. M. Beard, Jr.
Senior Vice President Nuclear Operations PMB/LVC-Attachment xc: Regional Administrator, Region II Senior Resident Inspector NRR Project Manager 1
-1 I
k 1
?
5 1
i
U. S.* Nuclear Regulatory Commission Attachment 3F0595-02 Page 3 10 CFR 50.55, APPENDIX J EXEMPTION REQUEST CRYSTAL RIVER UNIT 3 DESCRIPTION OF THE PROPOSED EXEMPTION REQUEST Title 10 of the Code of Federal Regulations, Part 50.55, Appendix J,Section III.D.1, " Primary Containment Overall Integrated Leakage Rate Periodic Testing r
(
(ILRT)" requires "a set of three Type A (Integrated Leak Rate Tests) tests shall be performed, at approximately equal intervals during each 10-year service period".
The third test of each set shall be conducted when the plant is shutdown for the 10-year plant inservice inspections.
Florida Power Corporation (FPC) in accordance with the provisions of 10 CFR 50.12 is requesting a one-time schedular exemption from those requirements for CR-3.
Specifically, FPC is requesting a deferral of our next ILRT until Spring 1998 (CR-3's Refueling Outage 11).
The technical analyses s"nporting this request, indicates that this one-time exemption does not add any significant risk to public health and safety.
FPC has recently adopted the Improved Technical Specifications (ITS). The ITS requirements for Type A testing are to follow the requirements of Appendix J with approved exemptions. Therefore, no license amendment is required.
REASON FOR THE REQUEST The current ISI/IST service period for CR-3 s*arted in March 1987 (Second 10-year service period) and ends in March 1997. CR ' ias performed one ILRT during this service period in November 7,1991. FPC perfo.med a prior test in November 1987.
However, FPC counted the 1987 test as the third test of the first 10-year interval (10 CFR 50.55a establishes the requirements for inspections by referencing to the ASME Code,Section XI which allows the extension of the 10-year interval to coincide with a refueling outage).
Therefore, FPC can only "take credit" for the November 1991 test for the current interval. The next ILRT j
for the interval was originally scheduled for Refuel 9 (April 1994).
- However, l
FPC re-scheduled the test until the then planned next mid-cycle outage due 1
l schedular impact upon Refuel 9.
That mid-cycle outage (Spring.")5) was not I
conducted due to the inproved system and equipment performance during this cycle.
The next available opportunity for performing the ILRT would be in Spring 1996 (Refuel 10).
However, if our request for exemption is approved, FPC would be able to save over two million dollars and would produce a reduction in personnel I
radiation exposure. Therefore, we propose scheduling the next ILRT in Refuel 11 (1998).
l l
I
U. S. Nuclear Regulatory Commission Attachment 3F0595-02 Page 4 BASES FOR THE EXEMPTION REQUEST Regulatory Review The provisions of 10 CFR 50.12 (a)(1) apply in that the proposed exemption is authorized by law, will not present an undue risk to the public health and safety and is consistent with the common defense and security.
The Special Circumstances required by 10 CFR 50.12 (a)(2)(ii) " Application of the regulation in the particular circumstances is not necessary to achieve the underlying purpose of the rule", apply to this situation.
A one-time schedular exemption from the Type A testing frequency of Appendix J is requested on the following basis.
The exemption request meets the underlying purpose of the regulation. Appendix J states that the purpose of Type A tests is to assure, by periodic verification tests, the leak tight integrity of the primary reactor containment.
The following discussion contains information pertaining to Types A, B and C testing history, structural capability, and risk assessment. The discussion establishes that CR-3 has shown acceptable containment leakage rates which are confirmed by satisfactory local leak rates (LLRTs) performed on penetrations and containment isolation valves; that structural integrity is assured; and, that the risk in changing the Type A testing frequency is negligible.
This exemption request does not affect the periodic schedule for Type B and C.
The performance of Types B and C testing demonstrate the leak-tightness of the penetrations and associated components. Thus, providing a high degree of confidence that the containment will not significantly degrade while this exemption is in effect.
This confidence is supported by:
a)
The two most recent Type A test data which shows the 95% Upper Confidence Limit (UCL) leakage rates to be 0.097 weight % per day and 0.0958 weight %
per day for the 1987 and 1991 ILRTs respectively.
These values when corrected for maintenance penalties were within the acceptance limit of.75 L, (.1875 weight % per day). Additionally, combined Types B and C leakage tests results have been significantly below the acceptance criteria of Appendix J (0.6 L,) as shown in Table A.
b)
There have been no modifications to the containment structure, liner or penetrations since the last Type A test that could adversely affect the Type A test results.
c)
No modifications that require a Type A test are planned prior to the 1998 refueling outage, d)
There have been no pressure or temperature excursions since the last Type A test in the containment which could have adversely affected containment integrity.
Operating experience demonstrates that essentially all containment leakage can be detected by LLRTs (Type B and C). As noted in draft NUREG-1493, out of 180 ILRT reports which covered 110 individual reactors and approximately 770 years of operating history, only 5 ILRT failures were found which local leak rate testing could not detect. Therefore, it is unlikely that this one-time exemption for the performance of Type A testing at CR-3 would result in significant degradation of the overall containment integrity. As a result the application of the regulation's stated frequency in this particular circumstance is not necessary to achieve the underlying purpose of the rule.
. U. S. Nuclear Regulatory Commission Attachment 3F0595-02 Page 5 BASES FOR THE EXEMPTION REQUEST (continued)
Type A Testing History The CR-3 testing history provides justification for the proposed reduction of the number of ILRTs during the current service period. Two ILRTs have been performed during the last seven years with successful results (all previous tests have also been successful). The results of the last two tests are significant to show that this request is also consistent with the recommended performance criteria for establishing Type A test intervals given in the draft industry guidelines for implementing performance-based option of the proposed 10 CFR Part 50, Appendix J Rule. The following summaries provide the results of the 1987 and 1991 ILRTs.
November 13-15. 1987 The test was performed using the Absolute Method of leakage rate determination.
The test data analysis was done by the Total Time Method as described in ANSI N45.4-1972 and by the Mass Point Method described in ANS 56.8-81.
The 95 % UCL leakage rate was.097 % wt/ day.
The total reported leakage value by the Total Time method, after corrections for pre-test valve repairs and in-test valve lineups was 0.137 weight % per day.
This value is less than the Appendix J acceptance criteria value of 0.1875 weight % per day (.75L A detailed discussion of the results was provided to the NRC in Reference,)A.
i November 7. 1991 This periodic type A test was performed using the Absolute Method of leakage determination as described in ANSI /ANS 56.8-1987, " Containment System Leakage Testing Requirements". The 95 % UCL leakage rate was.0958 % wt/ day. The total leakage value after corrections by the Total Time Analysis Method was 0.0986 weight % per day and by the Mass Point Analysis after corrections for pre-tests valve repairs and in-test valve lineups was 0.1014 weight % per day. those values are lower than the allowable (0.75 L = 0.1875) weight % per day.
The complete reportwasprovidedtotheNRCinReferenceB.
4 Types B and C Testing History FPC has a good record of leak tight containment as summarized below and as shown in Table A (immediately follows) which contain the minimum path LLRT results for each penetration that is in the LLRT program. The tables show that the overall combined as-found leakage in each campaign (from 1983 to 1994) was less than the allowed combined Type B and C leakage rate of 0.6 L (266,431 SCCM) at the calculat~d maximum peak containment pressure as specifled in Appendix J.
I i
I The as-left leakage was also significantly under the allowable.
As Table A shows, the results of LLRTs have always been acceptable.
Furthermore, those results have continuously improved and as could be seen in the table, the combined Types B and C tests resulting leakage has trend down since the 1987 campaign.
This shows FPC's commitment to fix those components that may not perform to the expected criteria.
FPC imposes administrative limits based on valve opening size. When valves fail to meet those administrative limits, the valves are repaired or replaced and re-tested. Corrective measures are taken in accordance with the CR-3's Inservice Testing and Repair and Replacement Programs.
Table B shows in detail, the maximum path, LLRT leakage rate results for the CR-3 last refueling outage (1994).
This table provides the as-found and as-left leakage rates for electrical penetrations and containment isolation valves. It could be seen from
..U. S. Nuclear Regulatory Commission Attachment 3F0595-02 Page '6 1
BASES FOR THE EXEMPTION REQUEST (continued) the values on the as-left column in that table, that containment isolation valves which presented leakage rates higher than allowed by FPC's administrative limits were repaired and re tested.
The downward leakage trend shown in Table A, has been confirmed by the ILRT results which have also shown acceptable results and show overall improved results for the 1991 ILRT thus confirming a down trend of overall containment leakage.
Structural Capability of the Containment The CR-3 containment is a reinforced concrete structure with a cylindrical wall, a flat foundation mat, and a shallow dome roof. The cylinder wall is prestressed with a post tensioning system in the vertical and horizontal directions.
The dome roof is prestressed using a three way post. tensioning system. The inside surface of the containment has a carbon steel liner to ensure a high degree of leak tightness during operating and accident conditions. The liner plate nominal thickness is 3/8 inch for the cylinder and dome and 1/4 inch for the base. The liner is anchored to the concrete as to ensure composite action with the concrete shell.
Piping penetrations have been designed to ensure that the liner will not be breached due to the rupture of any proce;s pipe.
Risk Impact Assessment The purpose of containment leak testing is to detect containment leakage which could be the result of failures (active or passive) before an accident occurs.
Containment leakage caused by degradation of sealing material within containment penetrations and containment isolation components will continue being effectively measured by the Type B and C testing programs. The only potential failures not covered by types B and C testing are failures of the containment due to structural deterioration because of parameters such as pressure or temperature.
However, under normal conditions there is no significant environmental or operational stress which could contribute to thi degradation of the containment structure to allow leakage. Such passive failures of the containment resulting in containment leakage have never occurred at CR-3.
The proposed one-time change in Type A leakage test frequency only affects the length of time that the containment could be in an undetected failed state as a result of a failure.
However, the Types B and C testing which will continue being performed each refueling outage will identify the majority of potential leakage paths.
Draft NUREG-1493 includes the results of a sensitivity study performed to explore the risk impact of several alternate leak rate testing schedules.
The draft NUREG concludes that the impact on risk due to the relaxation of Type A testing is very low. The NUREG also concludes that a decrease of ILRT frequency to once per 20 years would not have a significant increase in risk.
FPC believes the proposed one-time exemption request is bounded by the analyses for draft NUREG-1493. FPC also believes that the information contained in NUREG-1493 reinforces our conclusion that the risk increase due to the reduction of the number of ILRTs for this service period is not significant.
U. S Nuclear Regulatory Comission Attachment 3F0595-02 TABLE A Minimum Type C Type C TypeC Type C Type C Type C Penetration Leakage leakage Leakage Leak.u,e Leakage Leaksga Path 1983 1987 1990 1991 1992 1994 329 2.80 20.00 20.00 20.00 464.00 458.00 SCCM 439 2,108.00 1,096.00 60.00 60.00 220.40 88.70 SCCM 425 1 2.00 20.00 30.00 30.00 77.80 49.40 SCCM 425 2 2.00 20.00 250.00 250.00 20.00 20.00 SCCM
_40 3.60 230.00 225.00 313.00 380.00 244.00 SCCM 4
441 2.00 20.00 976.00 360.00 528.00 20.00 SCCM 206 838.00 775.00 82.00 82.00 1,368.00 390.00 SCCM 207 4,460.00 12.00 15.00 15.00 45.50 4,450.00 SCCM 366 2.50 2.00 15.00 15.00 10.00 28.00 SCCM 367 122.50 85.00 650.00 650.00 369.00 18.40 SCCM 1,040.00 327.00 2.00 2.00 271.00 176.00 SCCM 117 333 459.00 95.00 1,978.00 1,903.80 345.00 522.00 SCCM 377 2.00 145.00 291.10 564.00 1,049.00 80.00 SCCM 339 2.00 1,405.00 152.40 152.40 54.40 20.00 SCCM 349 2.00 59.20 227.00 234.00 20.00 20.00 SCCM 354 21.20 3,440.00 1,130.00 227.00 2.50 2.00 SCCM 374 2.00 78.80 20.00 20.00 20.00 154.00 SCCM 315 70.00 20.00 73.30 73.30 20.00 20.00 SCCM 332 52.40 20.00 7.76 7.76 20.00 28.00 SCCM 356 106.00 80.00 62.48 62.48 80.00 80.00 SCCM 123 350.00 20.00 13.00 13.00 171.40 167.00 SCCM 373 314.00 20.00 190.40 190.40 179.40 350.00 SCCM 124 1,178.00 1,152.00 20.00 20.00 261.00 297.00 SCCM 350 157.60 1,095.00 172.00 172.00 412.00 340.00 SCCM 351 6.30 20.00 431.00 431.00 20.00 20.00 SCCM 352 4.70 40.00 640.00 20.00 20.00 20.00 SCCM 355 150.30 133.00 1,670.00 1,670.00 42.20 1,775.00 SCCM y
372 l
24.80 43.80 37.00 37.00 28.50 12.17 SCCM 317 517.00 231.00 750.00 750.00 4.40 119.80 SCCM 110 1,000.00 124.00 98.90 98.90 168.70 383.00 SCCM 111 89.50 79.00 20.00 20.00 229.00 4?.20l SCCM 112
]
594.00 125.00 49.20 49.20 20.00 8.23 SCCM 347
[
12,340.00 15,940.00 13.60 13.60 387.00 118.00 SCCM 430 l
25.00 61.10 1,400.00 1,400.00 30.00 820.00 SCCM
~
316 100.00 20.00 5.00 5.00 20.00 2.00 SCCM 320 132.00 1,201.00 1,015.00 1,015.00 1,040.00 1,029.00 SCCM Page1
'" U. 'S. Nuclear Regulatory Connission Attachment 3F0595-02
- 4 TABLE A 318 2.50 20.00 20.00 20.00 872.00 20.00 SCCM 314 1,740.00 7,210.00 12,050.00 2,100.00 70.00 1,255.00 SCCM 427 189.00 7,560.00 200.00 200.00 543.00 130.00 SCCM 428 27.60 237.00 345.00 345.00 630.00 617.00 SCCM 306 21.05 60.00 48.75 48.75 60.00 60.00 SCCM 376 4.00 40.00 15.10 15.10 40.00 40.00 SCCM 113 1,000.00 4,800.00 657.00 1,185.00 568.00 620.00 SCCM 357 690.00 20.00 1,003.00 866.00 570.00 1,369.00 SCCM 121 195.30 278.00 655.00 459.70 338.00 1,312.00 SCCM 122 89.60 29.50 252.80 20.00 112.50 106.10 SCCM 125 202.00 783.00 720.00 752.00 1,228.70 814.00 SCCM 116 2.50 75.80 2.00 2.00 107.00 211.00 SCCM 305 9.80 2.00 30.00 30.00 20.00 20.00 SCCM 306 2.00 1,093.00 59.80 57.70 20.00 20.00 SCCM 202 20.00 20.00 20.20 69.60 51.50 28.00 SCCM i
31,084.55 50,481.20 28,868.79 19,108.69 15,618.90 20,966.00 SCCM TypeB 100.10 108.80 191.98 492.97 496.03 451.47 SCCM Hatches 12,550.00 1,474.00 9,620.00 18,580.00 17,600.00 1,822.00 SCCM I
Total B + C 43,734.65 52,064.00 38,880.77l 38,181.66 33,714.93 23,239.47 SCCM Test Press.
49.6 PSIG <
53.9 PSIG 53.9 PSIG 54.2 PSIG Allowed SCCM' 414,471 i 414,471 442,189-442,189 442,189 >
444,099 SCCM
% of aRowed 10.55%
12.58%
B.75%
l 8.83%.
' 7.82% : l 5.23%
SCCM
,1 Converted to 1983 1987 1990 1991 1992 1994 Pounds Mass 167.16 198.995 147.84 145.93 128.86 88.82 LBM B+C Wt Per Day l 0.028 l
0.032 l
0.022 l
0.022 l
0.019 0.013 0 -
r 9
s l
Page 2
,,,U..t. Nuclear Regulatory Commission Attachment 3F0595-02 TABLE B 1094 As left
% of To Allowed As Found
% of..
Pen #
Description SCCM Date l Valuel Allowed Date i Valuel Allowed as found 101 Elec 100 04/07/94 54.60 54.60 %
04!07/94 54.60 54.60 %
0.00 102 Elec 100 04/27/94 12.34 12.34 %
04/27/94 12.34 12.34 %
0.00 103 Elec 100 04/27194 3.70 3.70 %
04/27/94 3.70 3.70 %
0.00 104 Elec 100 04/07/94 20.00 20.00 %
04/07/94 20.00 20.00 %
0.00 120 Elec 100 04/27/94 6.80 6.80%
04/27194 6.80 6.80 %
0.00 127 Elec 100 04/27/94 7.70 7.70%
04/27/94 7.70 7.70 %
0.00 120 Elec 100 04/07/94 20.00 20.00 %
04/07/94 20.00 20.00 %
0.00 120 Elec 100 04/07/94 21.30 21.30%
04/07/94 21.30 21.30 %
0.00 130 Elec 100 04!07/94 22.70 22.70%
04/07/94 22.70 22.70 %
0.00 132 Elec 100 04/07/94 20.00 20.00 %
05I16/94 2.00 2.00 %
18.00 133 Elec 100 04/07/94 23.20 23.20%
04/07/94 23.20 23.20 %
0.00 134 Elec 100 04/11/94 2.00 2.00%
04/11/94 2.00 2.00 %
0.00 135 Elec 100 04/11/94 6.50 6.50%
04/11/94 6.50 6.50 %
0.00 200 Elec 100 04/08/94 9.50 9.50%
04/08/94 9.50 9.50 %
0.00 209 Elec 100 04/08/94 7.30 7.30%
04/08/94 7.30 7.30%
0.00 210 Elec 100 04/08/94 2.50 2.50%
04/08/94 2.50 2.50%
0.00 211 Elec 100 04/08/94 12.90 12.90%
04!08194 12.90 12.90 %
0.00 212 Elec 100 04/11/94 9.70 9.70 %
05/05/94 7.10 7.10 %
2.60 213 Elec 100 04/08/94 6.20 6.20 %
04/08!94 6.20 6.20 %
0.00 214 Elec 100 04/11/94 2.00 2.00 %
04/11/94 2.00 2.00 %
0.00 215 Elec 100 04I11/94 6.20 6.20%
04I11/94 6.20 6.20%
0.00 301 Elec 100 04/08/94 3.90 3.90%
04/08/94 3.90 3.90 %
0.00 302 Elec 100 04/08194 2.00 2.00 %
04/08/94 2.00 2.00 %
0.00 303 Elec 100 04/08/94 4.50 4.50%
04/08/94 4.50 4.50%
0.00 304 Elec 100 04/08/94 3.40 3.40%
04/08/94 3.40 3.40 %
0.00 307 Elec 100 04/08/94 5.00 5.00%
04/08/94 5.00 5.00%
0.00 300 Elec 100 04/08/94 2.00 2.00%
04/08/94 2.00 2.00 %
0.00 309 Elec 100 04/08/94 5.50 5.50%
04!08/94 5.50 5.50%
0.00 401 Elec 100 04/27194 7.85 7.85 %
04/27/94 7.85 7.85%
0.00 402 Elu 100 04/27/94 6.75 6.75 %
04/27/94 6.75 6.75%
0.00 483 Elec 100 04/27/94 5.16 5.16%
C4/27/94 5.16 5.16%
0.00 404 Elec 100 04/27194 2.00 2.00%
04/17/94 2.00 2.00%
0.00
_ 405 Elec 100 04/27/94 11.60 11.60 %
04/27/94 11.60 11.60 %
0.00 400 Elec 100 04/27194 44.60 44.60 %
04/27/94 44.60 44.60 %
0.00 407 Elec 100 04/26!94 9.37 9.37%
04/26/94 9.37 9.37%
0.00 400 Elec 100 04/26i34 18.53 18.53%
04/26/94 18.53 18.53%
0.00 409 Elw 100 04/26194 2.00 2.00%
04/26!94 2.00 2.00%
0.00 4101 Elec 100 04/26/94 7.74 7.74 %
04/26/94 7.74 7.74 %
0.00 411 Elec 100 04/27194 3.90 3.90%
04/27/94 3.90 3.90 %
0.00 412 Elec 100 04/27/94 6.50 6.50 %
04/27194 6.50 6.50 %
0.00 413 Elec l 100 04/27/94 2.00 2.00%
04/27/94 2.00 2.00 %
0.00 I
l Total Electrical J
l 431.44 21.57%
410.84 20.54%
20.60 Allowed Electrical I
}
^
{2.000 ]scem i
i i
l Page1 i
l U. S.. Nuclear Regulatory Commission Attachment 3F0595-02 TABLE B a
1994 Allowed As Found
% of As left
% of To Pen #
Description SCCM Date Valuel Allowed Date l Value!
Allowed as found 219 T. POWER 10G 05/23/94 2.00 2.00%
05/23/94 2.00 2.00 %
0.00 217 T-POWER 100 05/23/94 2.00 2.00%
05/23/94 2.00 2.00 %
0.00 344 SS/LXFER 100 04/07/94 4.40 4.40%
05/23/94 20.00 20.00 %
15.60 439 SSFLXFER 100 1 04/07/94 2.48 2.48%
05I23/94 20.00 20.00 %
17.52 119 CG FL 100 l 04/07/94 2.00 2.00%
05I23/94 2.00 2.00%
0.00 I 129 CG FL 100 04/07/94 2.00 2.00 %
05/18194 20.00 20.00 %
18.00 999 RAX 3 500 04/07/94 5.15 1.03%
05/27/94 20.00 4.00 %
14.85 1
i Eles, & Other Type "B" Tetsis 447.47 15.43%
496.84 17.13%
49.37 Allowed Other & Elec. Type "B" 2,900 seem i
113 AHV.1Cl10 2500 04/07/94 620.00 24.80 %
05/25I94 804.00 32.16%
184.0_0, 367. AHV 1 A11B.
2500 04/07/94 1,369.00 54.76%
05/28194 829.00 33.16%
540.00 997 RAX1 21500 05/28,'94 772.00 3.59%
05/28/94 772.00 3.59%
0.00 999 RAX 2 21500 05/27/94 1,050.00 4.88 %
05/27/94 1,050.00 4.88 %
0.00 ALL Type "B" Tetnis 4,258.47 8.37%
3,951.84 7.76%
306.63 Allowed Type 'B' I 50.900 seem i
i l
l 5
Page 2
, U. S.. Nuclear Regulatory Commission Attachment 3F0595-02 TABLE B l
I I
I
~ Measured i Leekage Apeedia J.
Velves TYPE "C" 1994 j AHowed As Found
% of f
As left
% of To Pen #
Osseription!
SCCMI Date l Valuel Allowed l Date i Valuel Allowed as found 110 SAV 24 4788 04/09/94 363.00 7.58%
04/09/94 363.00 7.58%
0.00 111 IAV 28 3192 04/09/94 42.20 1.32 %
04/09/94 42.20 1.32%
0.00 112 lAV 29 3192 04/09/94 8.23 0.26%
04/09/94 8.23 0 26%
0.00
_ 118 LRV45 3192 04/26/94 28.70 0.90%
04I26/94 28.70 0.90%
0.00 III LRV46 1596 04/26/94 211.00 13.22%
04/26/94 211.00 13.22 %
0.00 117 DWV.160 4788 04/11/94 176.00 3.66 %
04/11/94 176.00 3.b8%
0.00 117, DWV.162 4788 04/11/94 635.00 13.26%
04/11/94 635.00 13.26%
0.00 121 LRV.36 12768 04l13194 1,390.00 10.89%
04/13!94 1,390.00 10.89%
0.00 121 LRV 50 12768 04/12/94 1,072.00 8.40%
04/12/94 1,072.00 8.40%
0.00 121 LRV 89 4788 04/13/94 240.00 5.01 %
04/13/94 240.00 5.01%
0.00_
121 LRV 90 4788 04I13/94 250.00 5.22%
04/13/94 250.00 5.22 %
0.00 i
_122 LRV-87 4788 04/13/94 106.10 2.22%
04113/94 106.10 2.22 %
0.00 122 LRV 88 4788 04/13/94 119.50 2.50%
04/13/94 119.50 2.50%
0.00 123 CFV 20 1596 04/23/94 529.00 33.15%
04/23/94 529.00 33.15%
0.00 123 CFV 28 1596 04/25/94 167.00 10.46%
04/25/94 167.00 10.46%
0.00 124 CFV.17 1596 04/25!94 297.00 18.61 %
04/25/94 297.00 18.61 %
0.00 124 CFV 27 1596 04/25/94 402.00 25.19%
04I25/94 402.00 25.19%
0.00 125 LRV1 4788 04/20/94 330.00 6.89%
04/20/94 402.00 8.40%
72.00 125 LRV 92 4788 04/20/94 355.00 7.41 %
04/20/94 355.00 7.41%
0.00 125 LRV 93 4788 04/20/94 484.00 10.11 %
04/20/94 484.00 10.11%
0.00 125 LRV 94 4788 04/20/94 485.00 10.13 %
04/20/94 485.00 10.13 %
0.00 202 LRV44 3192 04/08/94 28.00 0.88 %
04/08/94 28.00 0.88%
0.00
_ 200 CIV41 3990 04/16/94 390.00 9.77%
05/06/94 5.50 0.14%
384.50 207 CIV 40 3990 04/16/94 4,450.00 111.53%
05/19/94 3.445.00 86.34 %
1.005.00 305 } LRV 72 9576 04/12/94 20.00 0.21%
04/12/94 20.00 0.21%
0.00 305 ~
LRV 73 9576 04/12/94 20.00 0.21%
04/12/94 20.00 0.21%
0.00 300 LRV 70,
9576 04/12!94 20.00 0.21%
04/12/94 20.00 0.21%
0.00 308 LRV 71 [
9576 04/12/94 20.00 0.21 %
04/12/94 20.00 0.21%
0.00 l
'CIV40 Operater
. Repaired Prior to An-Left. ITest Page 3
- _,, _. -.., ~,,,,., ~.. -.,.. _,.,., -,,. _
_.,_--u-----__
..U. S.. Nuclear Regulatory Commission Attachment 3f0595-02 TABLE 8 ITYPE "C" I Messered I I Leshage I Apendis 1 J.! Velves I 1994 Allowed As found
%of As left
%of To 306 WSV 26J 798 04/20/94 20.00 2.51%
04/20/94 20.00 _ 2.51 %
0.00 308 WSV.27 798 04/20/94 20.00 2.51 %
04/20/94 20.00 2.51%
0.00 300 WSV 28 798 04/20/94 20.00 2.51 %
04"20/94 20.00 2.51%
0.00 308 WSV 29 798 04/20/94 20.00 2.51%
04/20/94 20.00 2.51%
0.00 306 WSV 32 798 f4/20/94 20.00 2.51%
04/20!94 20.00 2.51%
0.00 300 WSV 33 798 04,?0!94 20.00 2.51%
04/20!94 20.00 2.51%
0.00 314 MSV 146
- 6384, 05/11/94 1,255.00 19.66%
05/11/94 1,255.00 19.66%
0.00 315 WSV4 If,f6~
0C.eI94 51.50 3.23 %
04/26/94 51.50 3.23%
0.00 315 WSV 3 1596
$ddb 20.00 1.25 %
04/ 6/94 20.00 1.25%
0.00 318 MSV.114 2394 C/I22",4 2.00 0.08%
04/22/94 2.00 0.08%
0.00 317 NGV81 2394 04I19/94 119.80 5.00 %_ 04/19194 119.80 5.00%
0.00 310 MSV.128 6J84 04I22/94
?0.00 0.31 %
04/22/94 20.00 0.31%
0.00 320 MSV.132 2394 04/22/94 1,029.00 42.98%
04!22/94 1,029.00 42.98%
0.00 329 DHV-91 3192 04/13/94 458.00 14.35 %
05/03/94 139.00 4.35%
319.00 329 DHV 93 3192 04I13'94 2,260.00 70.80 %
04113/94 2,260.00 70.80%
0.00 332 WSV 5 1596 04I26/94 32.00 2.01%
04/26/94 32.00 2.01%
0.00 332 WSV,6 1506 04/26/94 28.00 1.75%
04/26/94 28.00 1.75 %
0.00 333 MUV40 3990 04/21194 830.00 20.80 %
05/07/34 25.00 0.63 %
805.00 333 MUV41 3990 04/20/94 289.00 7.24 %
05/07/94 146.00 3.66%
143.00 333 MUV49 3990 04/21/94 522.00 13.08%
04/21/94 522.00 13.08%
0.00
~333 MUV 505 4788 04/21194 176.50 3.69 %
05I16/94 151.80 3.17%
24.70 339 WDV3 6384 04116/94 566.00 8.87%
04116/94 566.00 8.87%
0.00
,, 339 WDV4 6384 04I16!94 20.00 0.31%
05/17/94 41.40 0.65 %
21.40 347 SFV.18/19 15960 04I11/94 118.00 0.74 %
05/20/94 20.00 0.13%
98.00
_ 349 WDV 60 3192 04I16/94 20.00 0.63 %
05/04/94 20.00 0.63 %
0.00 349 WDV 61 3192 04/16/94 20.00 0.63 %
05I12/94 280.00 8.77%
260.00 350 CFV.18 1596 04/25194 340.00 21.30%
04/25/94 340.00 21.30%
0.00 350 CFV.26 1596 04/23/94 350.00 21.93%
04/23/94 350.00 21.93%
0.00 351 CFV 15 1596 04/15194 176.10 11.03%
04l28/94 71.00 4.45%
105.10
_ 351 CFV.16 1596 04115/94 20.00 1.25 %
04/28/94 20.00 1.25%
0.00 351 CFV 29 2394 04l15/94 20.00 0.84 %
04115/94 20.00 0.84%
0.00 i
a 1
i 4
Page 4
,.U. S.. Nuclear Regulatory Commission Attachment 3F0595-02 TABLE B ITYPE "C" I Menoured l i Leekage I Apendix I J.1 Velves I 1994 Allowed As Found
% of As left
% of To 362 CFV.11 1596!
04/15/94 20.00 1.25 %
05/05/94 20.00 1.25 %
0.00 362 CFV 12 1596!
04/15l94 20.00 1.25 %
04/28/94 20.00 1.25%
0.00 352 CFV42 15 %
0 411 519 4 20.00 1.25%
04115194 l 20.00 1.25 %
0.00 364 WDV405 23941 04/15/94 2.00 0.08%
05/13/94 '
20.00 0.84 %
18.00 364 TWDV406 2394 04/16/94 76.00 3.17%
05113/94 2,100.00 87.72 %
2,024.00 365 NGV 62 2394 04/19194 1,775.00 74.14 %
04/19194 1,775.00 74.14 %
0.00'
_ 358 WSV.1 1596 04/19I94 20.00 1.25 %
04/19/94 20.00 1.25%
0.00 360 WSV-2 1596 04/19/94 20.00 L 1.25%
04I19/94 20.00 1.25%
0.00 358 WSV 30 798 04/19/94 20.00 2.51%
04!19/94 20.00 2.51%
0.00 368 WSV 31 798 04119/94 20.00 2.51%
04/19194 20.00 2.51%
0.00 358 WSV 34 798 04/19/94 20.00' 2.51%
04/19/94 20.00 2.51%
0.00 355 WSV-35 798 04/19/94 20.00 2.51%
04/19/94 20.00 2.51%
0.00 356 WSV 38 798 04/20/94 20.00 2.51% 1 04/20/94 20.00 2.51%
0.00' 364 WSV 39 798 04/20l94 20.00 2.51 %
04/20194 20.00 2.51%
0.00 360 CIV 34 3990 04/16/94 2.80 0.07%
05/06/94 4.70 0.12 %
1.90 387 CIV 35 3990 04116/94 16.40 0.41%
05!06/94 114.00 2.86%
97.60 372 NGV-82 1596 04/19194 12.17 0.76%
04/19194 12.17 0.76%
0.00 373 CFV.19 1596 04/23/94 554.00 34.71 %
04/23/94 554.00 34.71 %
0.00 3?3 CFV 25 1596 04/23/94 350.00 21.93%
04/23/94 350.00 21.93%
0.00 374 WDV 62 4788 04I18194 154.00 3.22 %
05!10/94 2.00 0.04 %
-151.00 374 WDV94 4788 04118/94 210.00 4.39%
05/04/94 110.00 2.30%
100.00 378 WSV40 798 04/20!94 20.00f 2.51%
04/20/94 20.00 2.51%
0.00 378 WSV41 798 04/20/94 20.00 2.51%
04/20/94 20.00 2.51%
0.00 378 WSV42 798 04/20/94 20.00 2.51%
04/20/94 20.00 2.51 %
0.00 378 WSV43 798 04/20/94 87.70, 10.99%
04/20/94 07.70 10.99%
0.00 377 MUV 253 1596 04/16!94 80.00l 5.01%
04/16/94 80.00 5.01%
0.00 377 MUV 258 1596 04/16/94 20.00l 1.25 %
05/09/94 21.40 1.34 %
1.40 377 MUV-259
_ 1596 04/16/94 20.00j 1.25%
05/09/94 54.00 3.38%
34.00 377 MUV 260 1596 04/16/94 20.00h 1.25%,
05/09/90 20.00 1.25%l 0.00 377 l MUV 261i 1596 04116/94 20.00I 1.25%I 05/09/94 29.30 1.84% l 9.30 Page5
..U. S.. Nuclear Regulatory Commission Attachment 3F0595-02 TABLE B I
ITYPE "C" l.Mesoured l I Leskege ( Apendix l J.I Velves i 1994 Allowed As Found
% of As left
% of To 425 CAV433 598 04/18/94 481.00 80.43%
04/18194 481.00 80.43%
0.00 425 CAV434 598 04/18/94 20.00 3.34 %
0 411 819 4 20.00 3.34 %
0.00 425 CAV435 598 04118/94 49.40 8.26%
04/18/94 49.40 8.26%
0.00
_ 425 CAV436 598 04/18I94 20.00 3.34%
04/18/94 20.00 3.34 %
0.00 427 MSV 130 4788 04/21194 130.00 2.72 %
05/20/94 305.00 6.37%
175.00 428 MSV.148 4788 04/21/94 C17.00 12.89%
04/21/94 617.00 12.89%
0.00 430 FSV.261 6384 04!09/94 820.00 12.84%
04/09/94 820.00 12.84%
0.00 430 { _ FSV.262 6384 04/09/94 830.00 13.00 %
04/09/94 830.00 13.00 %
0.00 439 CAV1 I 598 04/15194 20.00 3.34%
05/02/94 20.00 3.34 %
0.00 439. CAV 2 1596 04/15/94 80.00 5.01%
04/15/94 80.00 5.01%
0.00 439 CAV 3 598 04/15/94 20.00 3.34 %
05/02/94 20.00 3.34 %
0.00 439 CAV.126 598 04/15/94 20.00 3.34 %
05/02/94 20.00 3.34 %
0.00 439 CAV429 598 04/14/94 94.70 15.84 %
04/14/94 94.70 15.84%
0.00 439 CAV430 598 04/14/94 160.00 26.76%
04/14/94 160.00 26.76%
0.00 439 CAV 431 598 04/15/94 6.70 1.12 %
04/15!94 6.70 1.12 %
0.00 439 CAY 432 598 04/15/94 2.00 0.33%
04I15/94 2.00 0.33 %
0.00 440 CAV4 598 04/12/94 249.00 41.64 %
05/02/94 364.00 60.87 %
115.00 440 CAV-6 1596 04/12/94 244.00 15.29%
04I12/94 244.00 15.29%
0.00 441 CAV5 598 04/12/94 20.00 3.34 %
04/28/94 20.00 3.34 %
0.00 441 CAV.7 1596 04/12/94 831.00 52.07%
04/12/94 831.00 52.07%
0.00 7
I Page 6 1
i
__