ML20246L468
| ML20246L468 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee  |
| Issue date: | 04/30/1989 |
| From: | Devincentis J, Murphy W VERMONT YANKEE NUCLEAR POWER CORP. |
| To: | |
| References | |
| NUDOCS 8907180442 | |
| Download: ML20246L468 (45) | |
Text
{{#Wiki_filter:.-. _. -- - - _ -_ - _ NElkMONT YANKEE NUCLEA'R POWER CORPORATION
~. .
Ferry Road, Brattleboro, VT 05301-7002 BVY 89-64 l REPLY 70 l (V ENGINEERING OFFICE 680 MAIN STREET DOLTON. MA 01740 (508)779-6711 July 7, 1989 U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attention: Document Control Desk
References:
a) License No. DPR-28 (Docket No. 50-271)
Dear Sir:
Subject:
Primary Containment Leak Rate Test Report In accordance with the requirements of Appendix J to 10 CFR 50, we hereby submit a copy of the report entitled, " Vermont Yankee Primary Containment Leak Rate Test 1989." We trust this information is ecceptable to you; however, should you have any questions, please contact us. Very truly yours, VERMONT YANKEE NUCLEAR POWER CORPORATION 4~ Warren P. fM urphy V l Vice President and Manager of Operations
/dm cc: USNRC Resident Inspector, VYNPS USNRC Regional Administrator, Region I i
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. . l VERMONT -Y/ XEE PRIMARY CONTAINMENT LtAKAGE RATE'TESTIkG- ;
a 1 1989 ! TEST COORDINATORS ,
-i James M. DeVincentis i
Gary Cappuccio
' PREPARED BY
-1 James M. DeVincentis ;
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3 Table of Contents-Section page(s) Summary............................................. l' Scope of Report .................................. 1 Summary lof:the. Type A test ........................ 2 e Preparation ......'.......................... 2 Pressurization ............................ 2 Stabilization ............................ 2
-24 hr.-test'............................... 2 1 Verification test ......................... 3 Test Corrections .......................... 4-Conclusions .............................. 4 Summary.of 1987 and 1989 Type B and C testing ..... 5 Types of Tests Performed'................. 5 Acceptance criteria ....................... 5'
' Valves That Exceeded' Acceptance Criteria... 6.to 10 Sum Total Type B and Type C leakage ....... 10 Additional Leak Rate testing that was performed .. 11 Assessment of the As-Found State of Containment ... 12,13 Resolution of NRC Inspection Report 89-02-Issues . 14 to 16 Summary.of Corrective Actions Planned...........,.. 17 References ....................................... 18 Attachments A -- Type A Test Results B - Type B Test Results C - Type C Test Results l
l 1 _m______..___. ._____.__.m._._..__ . _ - . _ . . -
E i "' e i Summary During the 1989 refueling outage (' February to April 1989) Vermont Yankee performed-a successful Integrated Leak Rate test (Type A test) of-the. primary containment system. The results of the previous Type A test were filed with the USNRC in July 1986.. Also, since July of 1986, Local Leak Rate testing (Type B and Type C) was performed on. primary containment penetrations.and valves. This testing
-was performed during both the 1987 outage (August to October 1897) and.the-1989 outage. Required non-outage testing was also performed as necessary.
All testing performed during the period covered in this report satisfied l the requirements of Vermont Yankee's Technical Specifications and 10CFR50 Appendix J. Due to the success of the 1989 ILRT and given the aggressive corrective actions planned for the 1990 outage Vermont Yankee plans to perform the next ILRT during the 1992 refueling outage. Scope of Report l This report includes a summary of; (1) The 1989 Type A test results. (pages 2 to 4 and Attachment A) (2) The'1987 and 1989 Type B and C testing results with an evaluation of those valves that did not meet the acceptance criteria specified in the Technical Specifications. (pages 5 to 10 and Attachments B and C) (3) Additional Leak Rate testing that was performed. (page 11) (4) The evaluation of the as-found state of containment. (pages 12 and 13) (5) Resolutions to leak testing issues raised in NRC Inspection Report 89-02. (pages 14 through 16) (6) A summary of the corrective actions planned. (page 17) page 1 of 18
_Sur nry of 1989 Typa A Tast Results
-Preparation Preparation of the containment for the Type A test included; (1). Performing a general inspection of the accessible interior and exterior surfaces of the containment structures and components No evidence of structural deterioration which could affect containment structural. integrity or leak tightness was discovered.
(2) Closure of the containment isolation valves by normal operation. No preliminary exercising.or adjustments are allowed. (3)Eventing those portions of fluid systems that are part of the reactor coolant pressure boundary and are open directly to the containment atmosphere under post-accident conditions. Pressurization Pressurization for the Type A test commenced on March 29,1989 at 2337 hrs. Containment inspections were performed at 5,15 and 30 psig to attempt to locate any. excessive containment leakage. No significant loaks were identified.-Pressurization continued until the containment pressure was slightly above the peak post accident containment pressure (La) of 44 psig. Pressurization was completed on March- 30,1989 at 0445. On. March 30,1989 at 0600 the containment was repressurized. This was done because temperature stabilization had resulted in a drop in containment pressure. Repressurization was necessary to ensure a starting pressure greater than 44 psig. Repressurization was completed at 0615 hrs. Stabilization The. stabilization period commenced on March 30,1989 at 0615 hrs. The stabilization criteria were satisfied at 1230 hrs. Successful stabilization is. achieved when the temperature change, in both the drywell and torus, is
.less that or equal to 0.5 degrees F/ hour / hour over the last two hours with a minimum stabilization period of four hours.(Note: Stabilization actually occurred earlier. However,due to an initially high torus water to torus air temperature difference,the Test Coordinator used very conservative judgement and extended the stabilization period).
24 hour-Test The 24 hour test commenced on March 30,1989 at 1348 hrs and was completed on March 31,1989 at 1415 after just over 24 hours. On March 31,1989 at 1157 hrs the plant process computer experienced reference voltage variations. j A review of the collected data revealed that the variations effected the i last three hours of data. Prior to experiencing the variations the ; containment leakage rate with 95% confidence converged, with the leakage - rate without statistical confidence at, 0.527 wt%/ day. page 2 of 18 l E__
Vermont Yankee performed off line calculations to vecify the accuracy of the 24 hour test. The start of the test was backed up by approximately three. hours so that the data, effected by the computer, was not within the 24 hour period. The statistical calculations were rerun and the leakage, with 95% confidence was determined to be 0.510 wt%/ day. These data show statistical. equivalence with the results obtained in the initial test. Both sets of data are provided in Attachment A. Vermont Yankee uses the absolute method for the calculation of containment mass and the m0ss point method for the leakage rate calculation. Verification Test vermont Yankee uses the superimposed leak method for the verification test. In this method a leak, equal to La '+/- 25 percent) is imposed out of the containment through a calibrated flow meter. The composite leakage rate (sum of the leakage rate after 24 hr test and the superimposed leak) is compared with the measured superimposed leakage rate. Satisfactory verification is achieved if; l Lam - L'aml < 0.25La where; L'am = Las - Ls Lam = containment leakage rate Las = measured composite leakage rate Ls = superimposed cor. trolled leak rate
- average of the last four hours of the 24 hour test and the last two hours of the verification test L'am - Las-Ls The verification test commenced on March 31,1989 at 1425 hrs and data collection was completed on March 31,1989 at 1923 hrs. The subsequent evaluation of the data revealed that successful verification had been reached after 4 hours. The superimposed flow was determined to be approximately equal to 0.5 La. This was due to the rotometer being calibrated at test pressure (44 psig) and subsequently being vented at atmospheric during the verification test. A procedure change ic planned to address this.
The results of the verification test were as follows; Las = 0.932 wt%/ day Ls = 0.421 wt%/ day L'am - Las - Ls = 0 511 wt%/ day Lam = 0.520 wt%/ day l Lam - L'aml = 0.009 wt%/ day <<<<< 0.25La or 0.2 wt%/ day l page 3 of 18 1 1
' Tost Corrections The following corrections were required for containment penetrations that were not in the normal. post accident position during the test:
Penetration Description Calculated correction * (wt%/ day)
'X Drywell Sumps 0.00181 X-35A TIP Purge 0.00032 X-14 Reactor Water Cleanup 0.00013 X-9A "A" Feedwater Line 0.00019 X-9B "B" Feedwater Line 0.00013 X-50 H202 Monitors 0.00150 Total correction - 0.00408
- based on Minimum Pathway Leakage for the, penetration The final leakage rate, corrected for penetrations not in the standard line-up was 0.527 wt%/ day + 0.004 wt%/ day - 0.531 wt%/ day.
Level changes in both the reactor and the containment sumps were also evaluated and were determined to have an insignificant affect on the calculated leakage. Conclusions Vermont Yankee's Technical Specifications and Appendix J to 10CFR50 require that the containment leakage be below 0.75 La. For Vermont v ankee La - 0.8 wt%/ day and 0.75 La - 0.6 wt%/ day. Based on obtaining a final corrected leakage of 0.531 wt%/ day this criteria was satisfied-cnd the test was successful. t page 4 of 18
Summary of 1987 and 1989 Type B and C Testing During the 1987 and 1989 refueling outages Type B and C primary containment leak rate testing was conducted in accordance with the plant Technical Specifications and 10CFR50 Appendix J. Types of Tests Performed Type B testing was performed on containment penetrations utilizing gasketed seals prior to opening. This is performed to determine the leakage before maintenance / opening. After each containment penetration was-closed a Type B leak test was again performed to provide as-left data. A summary of the Type B testing that was performed during the 1987 and 1989 outages is provided in Attachment B. Type C testing were performed on all containment isolation valves both prior to and after any outage maintenance to provide as-found as well as as-left data. The following four types of test methods were used; (1) The in-leakage test method (2) The pressure drop method (3) The pressure build-up method (4) The water collection method A summary of the Type C testing performed during the 1987 and 1989 outages is provided in Attachment C. Acceptance Criteria Vermont Yankee's Technical Specifications includes a specific limit on the amount of leakage from any one containment isolation valve (VY does not know of any other plant that has this requirement) as well as a limit on the sum total Type B and C Testing. All containment isolation , valves that exceeded the Technical Specification limit were reported to ' the USNRC in Licensee Event Reports LER 87-07 and LER 89-07. The conservative single valve Tech. Spec. limit acts to ensure valves receive maintenance before excessive leakage occurs. Vermont Yankee will selectively perform maintenance on valves that satisfy the single valve acceptance criteria and have the potential to degrade to a point where failure during the next test cycle is possible. l Vermont Yankee calculates the sum total Type B and C using the Maximum Pathway Leakage method with single active failure assumed for all applicable penetrations. The results of this calculation are presented later. l page 5 of 18
. 4 .
- Valves That Exceeded' Acceptance Criteria The following is a summary of the valves that failed to meet the acceptance criteria specified in the Technical Specification (0.522 Lbm/hr for any single valve). For each penetration an evaluation of the root cause, an-cssessment of the significance, and a summary of Vermont Yankees action plan to address,these failures is provided. This information supplements the information in LER 87-07 and LER 89-07. Specific leakage rates are provided in Attachment 7.
F Test Period Containment Containr'nt Description Penetration Isolation Valve 1987 outage X-08 MSD-77 Main steam drain X-18 LRW-83 Drywell floor drain X-19 LEW-94 Drywell equipment drain X-19 LRW-95 Drywell. equipment drain X-25 PCAC Exhaust Drywell atmospheric control X-26 PCAC Supply Drywell atmospheric control 1989 outage X-9B FDW-96A Reactor Feedwater X-18 LRW-83 Drywell floor drain X-19 LRW-94 Drywell equipment drain X-19 LRW-95 Drywell' equipment drain X-22 CA-89C Containment air X-25 PCAC Exhaust Drywell atmospheric control X-26 PCAC Supply Drywell atmospheric control X-08, MSD-77 During the 1987 outage, the out-board main steam drain isolation valve was leak tested and found to have a leakage of 0.525 Lbm/hr. The failure was determined to be due to valve closure on a small object. The seats were ground and lapped and the valve was successfully retested. For this penetration the in-board isolation valve satisfied the acceptance criteria. Both valves were successfully tested during the 1989 outage.
. Vermont Yankee plans no additional action on this penetration.
page 6 of 18 \
l X-98, FDW-96A l During the 1989 outage the outboard Feedwater isolation valve was tested. The leakage could not be measured with available on-site testing equipment. The valve was disassembled and the seats were found to be damaged. Also, the disc swing arm was found to be misaligned. , Vermont Yankee has experienced similar failures of this valve in the l past and has aggressively pursued ways, along with the industry, to improve I the feedwater check valves leak tightness. These improvements have included l replacement of the seats with an improved material and repairing an apparent misalignment problem. Evaluations performed to address reference (k), SOER 86-03, identified a potential root cause of the damage. It is suspected that the the i damage may be occurring during outages when the valve is subject to lower flow conditions. The Reactor Water Cleanup system uses this feedwater line to return water to the reactor vessel. The opposite feedwater line, which does not experience this flow has an excellent leak rate history. For this penetration the in-board isolation valve is exempt from local leak rate testing. Vermont Yankee' believes that additional action is required to improve this penetration's reliability and has scheduled to replace the in-board check valves with new testable check valves during the 1990 refueling outage. Following this replacement VY will perform leak rate testing on both the in-board and out-board check valves. Also, Vermont Yankee will evaluate methods to minimize the effects of the low flow conditions. X-18 and X-19, LRW-83,LRW-94 and LRW-95
,During the 1987 outage, the isolation valves on the drywell equipment and floor drain sump lines were tested and found to have the following leakages; Valve Leakage no. (Lbm/hr)
LRW-83 2.400 LRW-94 0.772 LRW-95 6.000 The root cause of these failures, at that time was determined to be a combination of foreign matter on the valve seats and a misadjustment of the stem shaft coupling. The seats were cleaned, the stem couplings adjusted and the valves successfully tested. The past leak rate tests for all three valves were excellent with no failures in the last five years. page 7 of 18
c =.
, y A s . During.the 1989 outage these' valves'were-found to have the following.
leakages;
, Valve'. Leakage; E' uno. (Lbm/hr) h LRW-83 10.000 l- ;LRW-94 0.856 L LRW-95. 5.330-An investigation into the. repeatLfailure' identified the root cause of the. failures toibeithe. installed orientation of.the operators. The
- operators:are-installed horizontally and over time the wear of the insating surface.resulted in the increased leakage.-The- valve. seating surfaces-were. repaired and the valves were successfully retested.-
'The leak rate test history on these valves, prior.to 1987, was excellent. Vermont Yankee believes that additional action:is required'
.to? improve this penetration's reliability and is selecting from-f lavailable options for improving this penetrations leak' tightness.
X-22, CA-89C aDuring the 1989 outage the in-board Containment Air isolation valve wasLtested. The leakage could not be measured with'available testing equipment. The. root cause of the failure was determined to be dirt-on'the seats. The valve.was disassembled, new-seats were installed and
.successfully retested.
, The containment air valve had experienced a similar failure in
'1984.(refer to LER 84-11) lFor this penetration a second isolation, in each of two potential
. leakage-paths, was available to provide the containment isolation funct[on.
Vermont Yankee does not believe that the leak rate history for this penetration warrants any further action at this time. X-25, PCAC Exhaust During the 1987 outage the Primary Containment Atmospheric-Control (PCAC) system exhaust line was tested and found to have have a total leakage of 10.058 Lbm/hr. The PCAC exhaust is comprised of six valves tasted-as a group. The acceptance criteria used is six times the single
, valve acceptance criteria or 3.132 Lbm/hr.
F page 8 of 18 f
The root cause of the failure was determined to be misalignment of-tha. disc to disc seat on two of the six valves PCAC-6 and PCAC-7. In the closed position the valve disc was approximately 1 1/2 degrees away from full closed. The valves were readjusted and the valve group was successfully rotested with a total leakage of 2.226 Lbm/hr. During the 1989 outage the PCAC exhaust again failed to meet the established acceptance criteria. The total penetration leakage could not be measured with on-site testing equipment. An investigation into the cause of the failures revealed excessive seat leakage, for the PCAC-6A and 6B valves, due to seat damage. Also a packing leak was stopped on PCAC-7A. The investigation into the root cause of the torn seats revealed that the the damage was due to normal wear. The seats for PCAC-6A and PCAC-6B were replaced, PCAC-7A was repacked and the PCAC exhaust successfully retested with a total leakage of 2.77 Lbm/hr. For this penetration a containment isolation valve, in both of the potential leak paths, had leakage less that that allowed. Vermont Yankee plans to develop a preventive maintenance schedule for replacing the seats. X-26, PCAC Supply During the 1987 outage the Primary Containment Atmospheric Control (PCAC) system supply line was tested and found to have have a total leakage of 8.774 Lbm/hr. The PCAC supply is comprised of four valves tested as a group. The acceptance criteria used is four times the single valve acceptance criteria or 2.088 Lbm/hr. l The root cause of the failure was determined to be misalignment of the disc to disc seat on one of the four valves PCAC-8. In the closed position the valve disc was approximately 1 1/2 degrees away from full closed. The valve was readjusted and the valve group was successfully retested with a total leakage of 0.035 Lbm/hr. During the 1989 outage the PCAC supply again failed to meet the i established acceptance criteria. The total penetration leakage was 3.295 Lbm/hr. An investigation into the cause of the failures revealed excessive seat leakage through one of the valves PCAC-8. The investigation into the root cause of the leakage revealed that the seating material was changed. The new material is a synthetic material which is not as soft or pliable as the previously installed seats. This results in a less effective I seal to resist leakage. page 9 of 18 1 m--____-___ _ __ i
r ' 1BEs;dLon'aurocommandDtion from thoxvendor,.a' compression ~ shim was
?cdded" tot the seating 1 arrangement for/PCAC-8 to improve the sealing (surfa'e c contact.-The' seat was,also replaced, with.the available'
! synthetic seats. The PCAC-supply.was~then:successfully retested with F ro s totalcleakage of 0.2351Lbm/hr.
For.this_ penetration a containment l' solation. valve, in'all'of the Lpotential leak' paths, had-leakage.less.than that allowed. Vermont' Yankee plans to access the availability of returning'to
~
the:previously installed seats or developing:a preventive maintenance-
. schedule using the new seats.
' Sum Total-Type B and Type C leakage n .
; Vermont Yankee l Technical Specifications and-Appendix J tof 10CFR50 require 1the. sum total Type:B (penetrations)~and-Type C (valves) leakage'
'to-ime less than or-equal to 0.6 La prior to startup from an outage.
W 1 Vermont Yankee'uses~the Maximum Pathway Leakage method to calculate this tota 141eakage. (0.6 La' equals 14.75 Lbm/hr.). f . The following are the as-left sum totals-for the'1987 and 1989
^
refueling outages..
.F Outage' . Sum Total' Sum Total Maximum Pathway -Minimum Pathway Leakage (Lbm/hr.) Leakage (Lbm/hr.)-
1987 7.329 3.359 1 1989 14.281 5.667 Based on questions raised during NRC Inspection No. 89-02,
. Vermont. Yankee is evaluating alternate methods for calculating ~
the sum. total Type B and C leakage as well as methods for
. calculating minimum and maximum pathway. leakage for valves tested
-asia group. This effort will be completed to support testing performed during the 1990 outage.
i page 10 of 18 1 I
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l ' Additional Leak Rate testing performed l' The following leak rate tests were performed between the 1987 and 1989 refueling outages. Penetration Test Description Measured Leakage (Lbm/hr.) No. Date X-2 10-03-87 Personnel airlock 2.977 X-2 11-10-87 Personnel airlock 2.500 X 12-31-87 Personnel airlock 3.440 X-2 03-19-88 Personnel airlock 0.860 X-2 03-19-88 Personnel airlock 1.075 X-2 06-24-88 Personnel airlock 0.610 X-2 06-30-88 Personnel airlock 4.410 X-2 07-02 Personnel airlock 3.550 X-2 08-23-88 Personnel airlock 1.940 X-2 08-26-88 Personnel airlock 1.380 X-2 08-28-88 Personnel airlock 2.580 ; X-2 08-29-88 Personnel airlock 2.580 X-2 12-28-38 Personnel airlock 4.730 X-2 04-09-89 Personnel airlock 2.320 An evaluation of the historical data on the Personnel Airlock revealed that the penetrations leakage has been trending up. The leakage at the highest measured value, 4.730 Lbm/hr, equates to a containment leakage rate of approximately 0.15 wt%/ day. Vermont Yankee believes that this increased leakage can be attributed to normal wear of the door opening / closure mechanisms. Vermont Yankee believes that overall containment leakage can be significantly reduced by performing maintenance on the Personnel airlock. This maintenance is currently planned for the 1990 refueling outage, page 11 of 18 l
Assessment of the As-found state of containment Integrated Leak. Rate test's are performed on. the Primary Containment system to ensure that containment leakage is within allowable limits. Many utilities, including vermont Yankee, perform this test at the end.of outages.
.The USNRC in' reference (e) expressed the concern that. utilities, parforming the ILRT after work is performed on the containment system (valves and penetrations), were.not correcting the Integrated-Leak Rate Test results for the work performed to determine the.As-Found' state of containment. The need to formulate the.As-Found value was basedionJa USNRC interpretation of paragraph 4.2 of reference (c).
During NRC' Inspection No.85-34, reference (f), the NRC expressed concern because Vermont Yankee had no formal position on' determining the As-Found value. It was Vermont Yankee's position,-documented in reference (g), that our. existing Local Leak Rate Testing Program aggressively limits containment leakage and that formulating an As-Found value is not a requirement of Appendix J. The issue was again raised during NRC Inspection No. 86-14 conducted during the 1986 ILRT. Vermont Yankee's position was discussed with Region 1 .(reference h) and it was agreed that there was no need to formulate the as-found value at that tims. During further discussions, it was agreed that vermont Yankee would provide an assessment of the-As-found state of containment along with the
-results of the 1989 ILRT. This assessment is provided below.
I The following method was used-to determine the As-found containment' leakage. Step 1. Identify all penetrations / valves repaired prior to E conducting the Type A test. Step 2. Identify all cases where.the Minimum Pathway Leakage reduced due to the repair effort. Step 3. Total the difference between the pre-repair and post-repair Minimum Pathway Leakages. Step 4. Convert this leakage to an equivalent weight percent , per day of total containment mass (taken at the j start of the 24 hour test) Step 5. Add the results to the corrected Type A test leakage. Step 6. Compare the results to an acceptance criteria of 0.75 La. page 12 of 18 I N __ _- -_-
.The total correction was determined to be 0.040 wt%/ day. This'rer its in an as-found containment leakage of.0.531 wt%/ day + 0.040 wt%/ day or 0.571 wt%/ day. This is less than 0.'75 La or 0.6 wt%/ day.
Based on this it is concluded that had the Type A test been performed at the start of the refueling outage the acceptance criteria would have baen met. The penetration for the "B" Feedwater line, X-9B, was not included in the formulation of the As-found valu.. This was done for the following reasons;
- This penetration is not isolated during the integrated test to allow for operation of the Reactor Water Cleanup System, which utilizes this line. Because of this leakage through this penetration does not impact the actual test. (a correction using Minimum Pathway Leakage is made to account for this)
- Only one of the two isolation valves is currently locally tested. During the 1989 outage the leakage through the tested valve could not be quantified using evailable test equipment.
Given these two facts determining the Minimum Pathway Leakage for this penetration was not possible.
- Vermont Yankee believes that there is reasonable assurance that this penetration will be water sealed after a design bases accident. Given the physical geometry the piping acts as a loop seal and the water inventory is assured by existing emergency core cooling systems.
- Also, there is reasonable assurance that, with the exception of a feedwater line break (in the same line as FDW-96A) there would be adequate time for the motor operated valves at the discharge of the high pressure feedwater heaters to be closed before there was any escape of containment atmosphere.
Based on the above vermont Yankee believes that the exclusion of this penetration does not invalidate the conclusion that the as-found state of containment satisfied the acceptance criteria. In the future the ability to quantify a correction for this penetration will be enhanced by testing the in-board isolation valves which is planned to be performed during the 1990 outage after the existing valves are replaced with testable valves. l page 13 of 18 i l l
Resolution of NRC' Inspection Report No. 89-02 Issues During NRC Inspection No. 89-02 issues concerning local and integrated-n leak rate testing were identified. This section provides Vermont Yankee's position on these i.nsues and details corrective actions planned to. addressLthese items as required.. Item #1 - Inspection Report 89-02 page 25 paragraph l'- Repeat-failures' and root cause determination Vermont Yankee believes that the process used to determine-the root cause of valve failures is adequate. A description-is provided on pages 7.through 10 detailing.the. specific investigations that went into the determinations.-Vermont Yankee believes'that the past evaluations were comprehensive 6 and utilized data available: at the time. Vermont Yankee also recognizes that new information is often available for repeat 1 failures .that allows for a more comprehensive failt.e analysis. Item #2 - Inspection Report 89-02 page 25 paragraph 2 - Assigning of leakage rates for valves tested in groups. i Vermont Yankee recognizes that testing of valve groups requires that some judgment be made when assigning the total leakage to the individual valves. It is recognized that for a two. valve group, with a combined leakage greater that'the single valve leakage limit, it is not possible to know each valves individual leakage. This condition is especially. difficult to account for when the valve group contains more than two valves. Vermont Yankee believes that having the single valse leakage limit in the Technica3 Specification aids in ensuring that learage is kept to a minimum. Also, current methods for calculation total Type B and C leakage require a single failure to be assumed for each penetration. Vermont Yankee believes that these requirements are adequate to ensure that Technical Specification requirements are satisfied and that current practices are adequate. It should be noted that if subsequent repair of a valve group indicate that a single valve's leakage exceeded the single valve limit that would be considered ! a violation of the Technical Specification requirements. This requirement will be added to the procedure controlling leak rate testing. page 14 of 18
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I
'Itom # Inspection Report 89-02 page 26 paragraph 3 - Volume fraction of temperature elements.
Vermont Yankee is currently committed to ANSI N45.4-1972. Vermont Yankee recognizes that certain enhancements to the leak rate testing program would be needed to upgrade to ANSI /ANS 56.8-1987. Vermont Yankee currently has a in-house commitment item , to assess the impact of the new standard when it becomes a I requirement. Addressing the. volume fraction. requirement is just one of the items that will be involved in thic process. Vermont Yankee does not view this item as a deficiency, as noted in the inspection report, and no additiona l action is planned until adoption of the aforementioned standard. Item # 4 - Inspection Report 89-02 page 26 paragraph 3 - Stabilization criteria. Vermont Yankee recognizes that the stabilization criteria in Bechtel Topical Report BN-TOP-1 is the same as that in the in-house procedure for performing the ILRT. Vermont Yankee also recognizes that the current standard ANSI N45.4 does not include specific stabilization criteria and it is not known if the procedure was developed uning BN-TOP-1 or if the criteria was just the state of the art at the time. Vermont Yankee does not believe that this is a deficiency.as noted in the inspection report and believes the procedure is adequate without the reference to BN-TOP-1. Vermont Yankee believes that adding reference to this topical report, which is for short duration tests, would not improve the procedure. No additional action is planned at this time. Item # 5 - Inspection Report 89-02 page 26 paragraph 3 - Prerequisites not including proper jumpers. Vermont Yankee agrees that the procedure needs to be revised to address this. The root cause and corrective actions, which include a procedure revision, that will be implemented to address l this are detailed in Licensee Event Report (LER) 89-16. l Vermont Yankee believes that this item is resolved upon implementation of the corrective actions detailed in the LER. No additional action is planned Item # 6 - Inspection Report 89- 02 page 26 paragraph 3 - Calculation for required supplemental flow. Vermont Yankee agrees that the procedure requires revision ! to address this item and will institute a procedure revision prior to performing the next Type A test. page 15 of 18 l l E _ --___ - e
W~ - ~ - [ a, . I lit:3 #'7 - Inspaction Report 89-02'page-28 paragraph 4 - Duration.ofEType A test. As; detailed.on page 4 Vermont. Yankee believes that the.
. testing performed satisfies the requirements of the Technical l Specification and 10CFR50 Appendix J. Vermont Yankee performed a full 24~ hour test.and collected data through out the test period.
Local-manual recording ~of containment pressure was conducted and a review'of other control room indication, during the last three hours of the' test, revealed no changes ~ indicative of a change in containment leakage rate. With-the data collected it would be possible to-input corrected data for the last three: hours of the 24 hour test, but this was deemed unnecessary since the actual leakage' rate had-been identified. Based on this the requirements of Appendix J were met in that 24 hours of data were recorded and and available'to determine the-leakage rate. Vermont Yankee' believes that not having the air supply-line fully vented.for a portion of the.three. hours backed into for the off-line evaluation is insignificant based on the following: (1),the local leak tests on the air supply lines out-board isolation valve indicated minimal leakage. The leak &ge measured converts to approximately 0.0077 wtt/dny. (which is insignificant when compared to the final. leakage rate) (2) the data is. factored in with 21 hours of data which had. the line vented. This will also minimize the effect of the leakage. No additional action is planned on'this item. r Item # 8 - Inspection Report 89-02 page 28 pas graph 6 - Calculation of the "as-found" state of containmen< Vermont Yankee's assessment of the "as-found" state of containment is provided on pages 12 and 13. No additional action is planned on this item. , ' Item # 9 - Inspection Report 89-02 page 29 paragraph 1 - effect of local leak rate test results for penetration X-9B on the "as-found" state of containment Vermont Yankee has addressed this item along with the l assessment of the "as-found" state of containment provided )
'to address item # 8 above. This specific assessment is located j on page 13. No additional action is planned at this time. i 1
Item # 10 - Inspection Report 89-02 page 29 paragraph 2.- calculation j of minimum pathway leakage. ; Vermont Yankee recognizes that the. current method used to calculate minimum pathway leakage, for multiple valve penetrations,with more than two valves, needs to be revisited. Vermont Yankee believes that our current method, taken collectively, is conservative. Vermont Yankee will revisit this issue to support testing for the 1990 outage. page 16 of 18 l
6 $ i
- Summary of Corrective Actions Planned The.following is a; summary of the-corrective actions currently planned for implementation during the 1990 refueling outage.
(1) For Feedwater penetrations X-9A and X-9B, Vermont Yankee has scheduled to replace the existing in-board check valves with new testable check valves. (refer to page 7 for additional information on this item) (2).To address / improve check valve performance for Feedwater-check valve V-96A Vermont Yankee will evaluate methods to L minimize the effects of the low flow conditions. (refer to page 7 for~ additional information on this item) l (3) For Liquid Radwaste penetrations X-18 and X-19, Vermont Yankee is selecting from available options for improving the leak tightness of the penetrations. (refer to pages' 7 and 8 for additivnal information on this l'?m) (4) For Containment Atmospheric Control penetrations X-25 and X-26, Vermont Yankee plans to access the availability of returning to the, previous style seats and/or developing a-preventive maintenance schedule using the new seats. (refer to pages 8,9 and 10 for additional information on this item) (5) For the personnel airlock, penetration X-2, Vermont Yankee plans to perform maintenance on potential leak paths to minimize the airlock leakage.~(see page 11 for additional information on this item) (6) Vermont Yankee will revisit the issue of calculating minimum and maximum pathway leakage, for multiple valve groups, to support testing for the 1990_ outage. (refer to pages 10 and 16 for additional information on this item. The-following corrective action is planned to be implemented prior to performing the next Type A test. (7) Vermont Yankee will revise the procedure for performing the Type A test to clarify the requirements for throttling the test flow, at the outlet of the rotometer, to ensure consistency with the calibration requirements. This item will be addressed prior to performing the next Type A test. (refer to pages 3 and 15 for additional information on this item) Vermont Yankee believes that these improvements will significantly , hid in reducing the overall containment leakage. ! page 17 of 18 i l _ _ _ = - - - _ _ _ _ _ _ - _ _ l
1 References (a) License No. DPR-28 (Docket No. 50-271) (b) 10CFR50 Appendix J (c) ANSI N45.4-1972 " Leakage Rate Testing of Containment Structures for Nuclear Reactors" (d) ANSI /ANS 56.8-1987 " Containment Systems Leakage Testing Requirements" (e) IE Information Notice No. 85-71 " Containment' Integrated Leak Rate Tests" (f) Inspection Report No. 50-271/85-34 (g) Memorandum, G.Cappuccio to R.J.Wanczyk, "NRC Information Notice 85-71" (h) Inspection Report No. 50-271/86-14 (i) Letter William T. Russel (USNRC) to Warren P. Murphy (VY)
" Systematic Assessment of Licensee Performance (SALP) Report No. 50-271/85-98", dated June 16, 1987, NVY 87-94.
(j) Inspection Report No. 50-271/89-02 (k) SOER 86-03 " Check Valve Failures or Degradation"
.I l
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page 18 of 18 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - - _ _ _ _ _ _ _ _ _ _ _ _ - - _ - - ._ i
L. * .: e i.
)
i APPENDIX A TYPE A TEST RESULTS Enclosed: Data collected during (1) The 24hr Test. (2) The Off-Line Test. (3) The Verification Test. The Following Graphs: (1) Drywell and Torus Temperature vs Time During Stabilization Period (2) _ Containment Mass vs Time (24hr) (3) Containment Mass vs Time (Off-Line 24hr) (4) Containment Leakage Rate vs Time (24hr) , (5) Containment Leakage Rate vs Time (Off-Line 24hr)
PRIMARY CONTAINMENT LEAKAGE RATE DATA SHEET-24-Hr Test Contain- E Contain-ment Contain-N ment Contain-Absolute' ment I Absolute ment Time
- Contained Pressure Temp.** I Time- Contained Pressure Temp.**
(Min) Mass (pounds) (in. Ha) (*F) R (Min) Mass (pounds) (in. Ha) (*F) 79.6/ D 78.9/ 0 74201.605 119.7 71.5 R 233 74127.493 119.42- 70.8 79.6/ N 78.9/ 10 74202.611 119.7 71.5 8 244 74128.156 119.42 70.8 79.6/ N 78.9/ 20 74202.468 119.7 71.5 8 254 74128.156 119.42 70.8 79.6/ I 78.9/ 30- 74209.376 119.7 71.4 R 264 74135.063 119.42- 70.7 79.6/ N 78.8/ 40 74190.537 119.67 71.4 N 274 74129.764 119.40 70.7 79.7/ H 78.8/ 50 74189.829 119.67 71s3 N 284 74123.327 119.40 70.8 79.6/ H 78.8/ 61 74197.638 119.67 71.3 I 294 74129.903 119.40 70.7 79.5/ I 78.8/
'71 74186.104 119.63 71.2 N 305 74130.562 119.40 70.7 79.6/ I 78.8/
81 74167.056 119.61 71.2 I 315 74111.559 119.37 70.7 79.5/ R 78.8/ 91 74174.337 119.61 71.2 1 325 74111.559 119.37 70.7 79.6/ N 78.8/- 101 74173.298' 119.61 71.1_ B 335 74117.805 119.37 70.6 79.6/ N , 78.8/ 111 74155.646 119.58 71.1 8 345 74118.465 119.37 70.6 79.4/ R 78.8/ 122 74176.453 119.58 71.0 R 355 74093.564 119.33 70.6 79.4/ I 78.8/ 132 74152.242 119.54 71.0 N 366- 74093.235 119.33 70.6 79.3/ H 78.7/ 142 74159.717 119.54 71.0 5 376 74101.373 119.33 70.6 79.4/ B 78.8/ 152 74139.471 119.52 71.0 N 386 74094.222 119.33 70.6 79.3/ N 78.7/ 162 74135.332 119.49 70.9 R 396 74082.173 119.30 70.6 79.1/ I 78.7/ 172 74149.900 119.49 70.9 R 406 74082.503 119.30 70.6 79.1/ N 78.6/ 183 74150.232 119.49 70.9 R 416 74090.311 119.30 70.6 79.0/ H 78.7/ 193 74157.520 119.49 70.9 R 427 74076.954 119.28 70.5 79.0/ H 78.6/ l 203 74145.760 119.46 70.8 R 437 74085.550 119.28 70.5 1 78.9/ N 78.7/ 213 74128.017 119.42 70.8 I 447 74090.062 119.30 70.5 78.9/ N 78.6/ 223 74127.825 119.42 70.8 8 457 74084.432 119.28
~
70.5
- Data collected at ten minute mf.
intervals. Record hours and minutes. Test Asst.'///ld Nff - a, /
** Drywell/ Torus /
VYOPF 4029.04A Date6//d!rW ag 1o Approved 8 / -fy2 N f L L_ _ _ _ - _ _ _ _ _ _ -_
I PRIMARY CONTAINMENT LEAKAGE RATE DATA SHEET l 24-Hr T& t l l Contain- R Contain-ment Contain-R ment Contain-Absolute ment R Absolute ment Time
- Contained Pressure Temp.** I Time Contained Pressure Temp. **
(Min) Mass (pounds) (in. Ha) (*F) R (Min) Mass (pounds) (in. Ha) (*F) 78.6/ R 78.5/ 467 74065.887 119.25 70.5 R 701 74007.507 119.12 70.3 78.6/ I 78.5/ 477 74066.408 119.25 70.5 5 711 74007.507 119.12 70.3 78.6/ B 78.4/ 488 74065.887 119.25 70.5 R 721 74015.246 119.12 70.3 78.6/ R 78.4/ __ 498 74066.215 119.25 70.5 B 732 73996.882 119.09 70.3 78.6/ R 78.4/ 508 74066.215 119.25 70.5 B 742 73996.558 119.09 70.3 78.6/ R 78.4/ 518 74048.207 119.21 70.4 R 752 ' 73996.558 119.09 70.3 78.5/ R 78.5/ 528 74074.156 119.25 70.5 5 762 73995.849 119.09 70.2 78.6/ R 78.5/ 538 74041.828 119.21 70.5 R 772 73989.278 119.09 70.3 78.6/ R 78.4/ 549 74049.187 119.21 70.4 5 782 74003.129 119.09 70.2 78.6/ I 78.4/ 559 74048.861 119.21 70.4 8 793 74003.129 119.09 70.2 ! 78.6/ R 78.5/ 569 74048,861 119.21 70.4 5 803 73976.496 119.07 70.3 78.6/ R 78.4/ 579 74049.045 119.21 70.4 R 813 73990.993 119.07 70.2 78.6/ R 78.4/ 589 74048.861 119.21 70.4 8 823 73984.616 119.07 70.3 78.6/ R 78.4/ 599 74036.080 119.19 70.4 5 833 73990.670 119.07 70.2 78.6/ R 78.4/ 610 74036.406 119.19 70.4 R 843 73990.993 119.07 70.2 78.5/ R 78.4/ 620 74044.340 119.19 70.4 R 854 73990.993 119.07 70.2 78.5/ 8 78.4/ 630 74044.015 119.19 70.4 R 864 73991.317 119.01 70.2 78.5/ 8 78.4/ 640 74043.882 119 19 70.4 8 874 73990.993 119.07 70.2 78.6/ 8 78.4/ 650 74018.049 119.16 70.4 8 884 73990.670 119.07 70.2 78.6/ R 78.4/ 660 74000.360 119.12 70.3 8 894 73972.304 119.04 70.2 78.5/ R 78.5/ 671 74007.314 119.12 70.3 8 904 73983.584 119.07 70.2 78.5/ R 78.5/ 681 74007.639 119.12 70.3 8 915 73940.111 119.00 70.2 78.5/ I 78.5/ 691 74007.832 119.12 70.3 R 925 73965.351 119.04 70.2 __
- Data collected at ten minute ,.f7 / g. /
intervals. Record hours and minutes. Test Asst. ///4/vqfr i _ f'.
**Drywell/ Torus VYOPF 4029.04A Date ' f/// !88
/
g 1o Approved M /f Bf fM w
,49 '
~
PRIMARY CONTAINMENT LEAKAGE RATE DATA SHEET 24-Hr Test
.Contain- E- Cor.cai n-ment Contain-N ment Contain-Absolute ment N Absolute ment Time
- Contained Pressure Temp. **H Time Contained Pressure Temp.**
(Min)~ Mass (pounds) (in. Ha) (*F) I (Min) Mass (pounds) (in. Ha) (SF) 78.5/ N 78.5/ 935 73940.111 119.00 70.2 8 1169 73865.037 118.88 70.2 78.6/ R 78.5/ 945 73932.839 119.00 70.2 N 1179 73865.037 118.88 70.2 78.5/ I 78.5/ 955 73940.111 119.00 70.2 N 1189 73865.361 118.88 70.2 78.5/ I 78.5/ 966 73940.111 119.00 70.2 N 1200 73865.361 110.88 70.2 78.5/ R 78.4/ 976 73940.111 119.00 70.2 N 1210 73860.168 118.86 70.2 78.5/ I 78.4/ 986 73940.111 119.00 70.2 1 1220 73853.610 118.86 70.3 78.5/ I 996 73940.111 119.00 70.2 I 78.5/ I 1006 73940.303 119.00 70.2 R 78.5/ R 1016 73927.329 118.98 70.2 R 78.4/ I 1027 73934.925 118.98 70.2 N 78.5/ I 1037 73927.652 118.98 70.2 .,1 78.5/ I 1047 73927.329 118.98 70.2 8 78.5/ R __{057 73908.965 118.95 70.2 N 78.4/ 1 1067 73915.912 118.95 70.2 I 78.5/ I 1077 73908.965 118.95 ?C.2 N 78.5/ R 1088 73908.967 118.95 70.2 I 78.5/ N 1098 73908.967 118.95 70.2 R 78.5/ R 1108 73908.965 118.95 70.2 N 78.5/ I 1118 73908.965 118.95 70.2 E 78.5/ I 1128 73889.954 118.92 70.2 8 78.4/ R 1138 73897.547 118.92 70.2 R 78.4/ I 1149 73897.547 118.92 70.2 N 78.5/ I 1159 73889.954 118.92 70.2 I
- Data collected at ten minute g f intervals. Record hours and minutes. Test Asst. de /// '~
s, <42
** Drywell/ Torus VYOPF 4029.04A Date ci//6/h9 OP 4029 Rev. 4 Page 1 of 1 Approved 8 // wwT
/
PRIMARY CONTAINMENT LEAKAGE RATE DATA SHEET Off-Lina 24-Hr. Test l. Contain- H Contain-ment Contain-H ment Contain-Absolute ment H Absolute ment-Time
- Contained Pressure Temp.** H Time Contained Pressure Temp.**
(Min) Mass (pounds) (in. Ho) (*F) X (Min) Mass (pounds) (in. Ho) (*F) 79.9/ 79.6/ H 0 74239.077 119.940 72.8 0 234 74208.179 119.700 71.4 l 79.9/ H 79.6/ 10 74227.693 119.510 72.7 H 244 74190.537 119.670 71.4 79.8/ H 79.7/ 20 74235.857 119.910 72.7 0 254 74189.829 119.670 71.3 79.8/ H 79.6/ 31 74223.944 119.870 72.5 0 264 74197.112 119.670 71.3 79.7/ H 79.5/ 41 74219.505 119.840 72.4 H 275 74186.439 119.630 71.2 l- 79.7/ H 79.6/ l 51 74245.034 119.870 72.3 H 285 74179.155 119.630 71.2 1 79.7/ H 79.5/ 61 74225.724 119.840 72.3 0 295 74173.861 119.610 71,2 79.8/ H 79.6/ 71 74213.784 119.820 72.2 H 305 74173.298 119.610 71.1 79.7/ H 79.6/ 81 74220.881 119.820 72.2 H 315 74173.298 119.610 71.1 79.8/ H 79.5/ 92 74202.052 119.790 72.1 X 325 74169.170 119.580 71.0 79.7/ H 79.4/ 102 74215.712 119.790 72.0 H 336 74152.102 119.540 71.0 79.7/ H 79.4/ 112 74216.241 119.790 72.0 H 346 74151.909 119.540 71.0 79.7/ H 79.3/ 122 74222.807 119.790 71.9 H 356 74147.417 119.520 71.0 79.6/ H 79.4/ 132 74231.108 119.790 71.9 H 366 74139.803 119.520 71.0 79.7/ 5 79.3/ 142 74205.007 119.750 71.8 il 376 74135.525 119.490 70.9 79.7/ H 79.1/ 153 74199.485 119.730 71.7 H 386 74149.900 119.490 70.9 79.6/ H 79.1/ 163 74206.435 119.730 71.7 H 397 74130.903 119.460 70.9 79.7/ H 79.0/ 173 74199.821 119.730 71.7 H 407 74139.377 119.460 70.9 79.7/ H 79.0/ 183 74206.727 119.730 71.6 0 417 74120.538 119.420 70.8 79.7/ H 78.9/ 193 74207.062 119.730 71.6 H 427 74153.380 119,460 70.8 79.6/ H 78.9/ 203 74202.276 119.700 71.5 0 437 74153.049 119.460 ' 70.8 79.6/ H 78.9/ 214 74202.611 119.700 71.5 H 447 74153.049 119.460 70.8 79.6/ H 78.9/ 224 74202.468 119.700 71.5 0 458 74,127/82_5 119.420 70.8 df [ // [/['
- Data collected at ten minute intervals. Record hours and minutes. Test Asst. #Aggf// r,$ tsp 2O
//
' ' ~ ~ " -
**Drywell/ Torus j j VYOPF 4029.04A Date d5//[/b?h OP 4029 Rev 4 Page 1 of 1 Approved [/ 8 [ [ 'T5i.
/
.. 0
,. PRIMARY CONTAINMENT LEAKAGE RATE DATA SHEET L Off-Lins 24-Hr. Test Contain- H Contain-ment Contain-H ment Contain-Absolute ment H Absolute ment Time
- Contained Pressure Temp.** H Time Contained Pressure Temp.**
(Min) Mass (pounds) (in. HQ) (*F) 8 (Min) Mass (pounds) (in. Ha) (SF) 78.9/ H 78.6/ 468 74128.486 119.420 70.8 H 702 74066.215 119.250 70.5 78.9/ H 78.6/
-478 74134.732 119.420 70.7 N 712 74066.080 119.250 70.5 78.8/ H 78.6/
, 488 74129.572 119.400 70.7 0 722 74073.310 119.250 70.4 l 78.8/ H 78.5/ 498 74123.327 113.400 70.8 8 732 74048.592 119.210 10. ti 78.8/ H 78.6/ 509 74129.903 119.400 70.7 H 742 74041.635 119.210 70.5 78.8/ H 78.6/ 519 74111.229 119.370 70.7 0 753 74048.535 119.210 70.4 78.8/ H 78.6/ 529 74111.421 119.370 70.'7 H 763 74048.861 119.210 70.4 78.8/ H 78.6/ 539 74111.889 119.370 70.7 H_773 74048.861 119.210 70.4 78.8/ U 78.6/ 549 74118.465 119.370 70.6 0 783 74048.861 119.210 70.4 78.8/ H 78.E/ 559 74093.564 119.330 70.6 H 793 74036.406 119.190 70.4 78.8/ H 78.6/ 570 74093.564 119.330 70.6 H 803 74036.406 119.190 70.4 78.8/ H 78.6/ 580 74093.894 119.330 70.6 H 814 74036.406 119.190 70.4 78.7/ H 78.5/ 590 74082.503 119.300 70.6 H 824 74043.882 119.190 70.4 78.8/ H 78.5/ 600 74093.894 119.330 70.6 H 834 74044.208 119.190 70.4 78.7/ H 78.5/ 610 74082.832 119.300 70.6 H 844 74044.340 119.190 70.4 78.7/ H 78.6/ 620 74082.832 119.300 70.6 H 854 74036.732 119.190 70.4 78.7/ H 78.6/ 63J 74089.735 119.300 70.5 0 864 74025.272 119.160 70.3 78.6/ H 78.5/ 641 74085.550 119.280 70.5 H 875 74032.229 119.160 70.3 78.7/ H 78.5/ 651 74077.282 119.280 70.5 0 885 74032.229 119.160 70.3 78.6/ H 78.5/ 661 74084.896 119.280 70.5 H. 895 74007.639 119.120 70.3 78.6/ H 78.5/ 671 74085.416 119.280 70.5 H 905 74007.314 119.120 10.3 78.6/ H 78.5/ 681 74066.21.5 119.250 70.5 H 915 74007.639 119.120 70.3 78.6/ H 78.4/ 692 74066.542 119.250 70.5 N 925 74015.114 ' 119.120 70.3
- Data collected at ten minute gf ]/)
intervals. Record hours and minutes. Test Asst. #$6 t((/V// ((i X~IA')A
** Drywell/ Torus /
VYOPF 4029.04A Date fi //U./h/ '7 OP 4029 Rev. 4 ? - Pt.ge 1 of 1 Approved . t . - - 1 %-
,f
f _ _ . _ - _ _ _ _ _ _ _ _ _ _ _ _ . _ . _ _ _ _ _ _ . - - __ l
PRIMARY CONTAINMENT LEAKAGE RATE DATA SHEET Off-Lins 24-Hr. Test Contain- H Contain-ment Contain-H ment Contain-Absolute ment H Absolute ment Time
- Contained Pressure Temp.** H Time Contained Pressu"e Temp.**
(Min) Mass (pounds) (in. Hg) (cF) H (Min) Mass (pounds) (in. do) (*F) 78.5/ H 78.6/ 935 74007.639 119 1,22 70.3 H 1169 73932.839 119.000 70.2 __ 78.4/ H 78.5/ 946 73996.751 119.090 70.3 H 1180 73940.434 119.000 70.2 78.4/ H 78.5/ 956 73996.553 119.090 70.3 X 1190 73940.434 319.000 70.2 78.4/ H 78.5/ 966 73996.751 119.090 70.3 H 1200 73939.462 119.000 70.2 78.5/ H 78.5/ 976 73995.849 119.090 70.2 H 1210 73940.303 119.000 70.2 78.5/ H 78.5/ 986 73988.954 119.090 70.3 H 1220 73927.976 118.980 70.2 78.4/ H 78.5/ 997 7,4003.322 119.090 70.2 H 1230 73940.111 119.000 70.2 78.4/ H 78.4/ 1007 73990.538 119.070 70.2 H 1241 73933.952 118.980 70.2 78.5/ H 78.5/ 1017 73977.145 119.070 70.3 H 1251 73927.652 110.980 70.2 78.4/ H 78.5/ 1027 73990.670 119.070 70.2 H 1261 73909.481 118.950 70.2 78.4/ H 78.5/ 1037 73984.423 119.070 70.3 H 1271 73927.521 118.980 70.2 78.4/ H 70.4/ 1047 73991.186 119.070 70.2 H 1281 73915.912 118.950 70.2 78.4/ H 78.5/ 1058 73990.993 119.070 70.2 H 1291 73908.641 118.950 70 3 78.4/ H 8/ 1068 73990.993 119.070 70.2 0 1302 73908.641 118.950 70.2 78.4/ l 78.5/ 1078 73991.317 119.070 70.2 H 1312 73906.641 118.950 70.2 78.4/ H 78.5/ 1068 73991.186 119.070 70.2 0 1322 73908.965 118.950 70.2 78.4/ H 78.5/ 1098 73972.304 119.040 70.2 H 1332 73908.965 118.950 70.2 78.4/ H 78.5/ 1108 73972.304 119.040 70.2 H 1342 73908.965 118.950 70.2 78.5/ H 78.4/
,_1119 73983.907 119.070 70.2 H 1352 73897.416 118.920 70.2 78.5/ H 78.4/
1129 73965.027 119.040 70.2 H 1363 73897.416 118.920 70.2 78.5/ H 78.5/ 1139 73940.111 119.000 70.2 0 1373 73890.277 118.920 70.2 78.5/ H 78.5/ 1149 73940.434 119.000 70.2 H 1383 73865.361 118.880 70.2 78.5/ H 78.5/ 1159 l73940.111 119.000 70.2 H 1393 73S65.361 118,880 70.2
- Data collected at ten minute /? //
intervals. Record hours and minutes. Test Asst. N/k/Vd '/ /-
,gf /
T(N/c,
) /
** Drywell/ Torus / /
VYOPF 4029.04A Date f5/d5/ / 9 Eg 1o Approved '
<'/#
(9'
PRIMARY CONTAINMENT' LEAKAGE RATE DATA SHEET E ~
'Off-Lina 24-Hr. Tast Contain- R -Contain-ment Contain-H ment Contain-Absolute ment R Absolute' ment Time'* LContained Pressure . Temp.** O Time Contained ' Pressure Temp. **-
(Min)' Mass (pounds) (in.'Ho) (*F) B '(Min) Mass (pounds) (in. Ho) -(*F) 78.5/ R 1403 73865.037 118;880 70.2 H 78.5/ H 1413 73865.361 118.880 70.2 H 78.4/ I
'1424 73859.845 118.860~ 70.2 H 78.4/ I 1434- ,73853.286 118.860 70.3' N 78.5/ H 1A44' 73852.579 118.860 70.2 I U
D R R R R R E B ll H n R R R N N R H H H n R H H n l R n H H I U R H H U .. a i n __
- Data collected at ten minute intervals'. Record hours and minutes. Test Asst. g' ', - (L / /,g>'
r/4( ' tv
** Drywell/ Torus
/g,g l- VYOPF 4029.04A Date /D 1 g o 1 Approved I oSh N
PRIMARY CONTAINMENT LEAKAGE RATE DATA SHEET Vsrificatirn Tc3t l Contain- I Contain-ment- Contain-I ment. Contain-Absolute ment ~ I Absolute ment Time
- Contained Pressure Temp.** I -Time . Contained Pressure Temp. **
'(Min) Mass (pounds) (in. Ha) (*F) I (Min) Mass (pounds) (in. Ha) (*F) 77.5/ 8 77.3/
0- 73970.149 118.830 69.3 H 234 73885.711 118.620 69.2 77.4/ E 10 73977.440 118.830 69.3 N 77.4/ N 20 73952.158 118.790- 69.3 R l 77.4/ R 31 73952.477 118.790 69.3 I 77.5/ R 41 73945.188 118.790 69.3 I 77.5/ I 51 73932.069 118.770 69.3 N 77.4/ I 61 73964.864 118.770 69.3 I 77.4/ N 71 72940.630 118.770 69.3 N . 77.5/ R 87 73914.304 118.740 69.3 N l 77.5/ N ;
~~
92 73913.987 118.740 69.3 N 77.5/ I ; 102 73913.668 118.740 69.3 R l 77.4/ I 112 73921.272 118.740 69.3 I 77.4/ I 122 73928.167 118.740 69.2 N 77.4/ I ' 132 73902.549 118.710 69.3 N 77.4/ 5 142 73902.867 118.710 69.3 I 77.4/ I 153 73910.078 118.710 69.2 8 77.4/ N l 163 73884.477 118.670 69.2 5 j 77.4/ R I 173 73909.443 118.710 69.2 5 77.4/ B 183 73878.221 118.670 69.3 E 77.4/ I 193 73864.795 118.670 69.2 N _ 77.3/ R 203 73904.444 118.650 69.2 N _ j, 77.3/ R j 214 73879.912 118.650 69.2 E l 77.4/ R l 224 73897.161 118.650 69.2 N j ) cData collected at ten minute . , I intervals. Record hours and minutes. Test Asst. a a l
** Drywell/ Torus _f f VYOPF 4029.04A Date 6//d/b?9 g 1o Approved #d/ axe d f
I,
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l APPENDIX B TYPE B TEST RESULTS l l l l i l i 1
c APSEMDIX,0 c. Summary Test Results for Type B Testina Page 1 of 4 LEAKAGE (LBM/HR) 1987 1989 PENETRATION INITIAL RETEST INITIAL RETEST NUMBER DESCRIPTION X-2 Personnel Lock O.860 0.000 3.484' 2.90 Bellows Seals X-7A Main Steam Line A 0.000 (1) X-78 Main Steam Line B 0.000 (1) X-7C Main Steam Line C 0.000 (1) X-70 Main Steam Line D 0.000 (1)
-X-9A Feedwater A 0.000 (1)
X-98 Feedwater B 0.000 (1) X-11 HBCI Steam Line 0.000. (1) X-12 RHR Suction 0.000 (1) X-13A RHR Return A 0.000 (1) X-13B RHR Reburn B 0.000 (1) X Cleanup Suction 0.000 (1) X-16A Core Spray A 0.000 (1) X-16B Core Spray B 'O.000 (1) Electrical Penetrations 100A Electrical Penetration 0.001 0.000 0.002 1008 Electrical Penetration 0.001 0.010 100C Electrical Penetration 0.001 0.000 1000 Electrical Penetration 0.000 0.087 101C Electrical Penetration 0.003 0.002 Note (1) Snoop checked during ILRT. No significant leakage noted.
APPENDIX B Summary Test Results for Type B Testina Page 2 of 4 i LEAKAGE (LBM/HR) 1987 1989 PENETRATION INITIAL RETEST INITIAL RETEST NUNBER DESCRIPTION i 101D Electrical Penetration 0.000 0.000 i 102 Electrical Penetration 0.011 0.012 103 Electrical Penetration 0.003 0.000 104A Electrical Penetration 0.000 0.000 104B Electrical Penetration 0.001 0.000 , 104C Electrical Penetration 0.000 0.000 105A Electrical Penetration 0.000 0.001 105B Electrical Penetration 0.000 0.003 105C Electrical Penetration 0.000 0.000 105D Electrical Penetration 0.008 0.100 214 Electrical Penetration 0.000 0.000 Double Gasketed Seals X-1 Equipment Hatch 0.002 0.002 0.002 0.002 X-3 Drywell Head Flange 0.018 0.000 0.126 0.007 X-4 Drywell Head Access Hatch 0.000 0.000 0.000 0.000 X-6 Control Rod Drive Removal 0.000 0.000 0.000 0.000 X-35A TIP Penetration Flange 0.000 0.000 X-35B TIP Penetration Flange 0.000 0.000 X-35C TIP Penetration Flange 0.000 0.000 X-35E TIP Penetration Flange 0.000 0.000 X-200A Torus Access Hatch 0.000 0.000 0.000 0.000
APPENDIX B Summary Test Results for Type B Testina Page 3 of 4 LEAKAGE (LBM/HR) 1987 1989 PENETRATION INITIAL RETEST INITIAL RETEST NUMBER DESCRIPTION X-2008 Torus Access Hatch 0.000 0.000 0.000 0.000 VBC-A Vacuum Breaker Access Cover 0.000 0.000 0.000 0.000 VBC-B Vacuum Breaker Access Cover 0.000 0.000 0.000 0.000 V3C-C Vacuum Breaker Access Cover 0.000 0.000 0.000 VBC-D Vacuum Breaker Access Cover 0.000 0.000 0.000 VBC-E Vacuum Breaker Access Cover 0.000 0.000 0.000 VBC-F Vacuum Breaker Access Cover 0.000 0.000 0.000 VBC-G Vacuum Breaker Access Cover 0.000 0.000 0.000 VBC-H Vacuum Breaker Access Cover 0.000 0.000 0.000 VBC-I Vacuum Breaker Access Cover 0.000 0.000 0.000 VBC-J Vacuum Breaker Access Cover 0.000 0.000 0.001 VBSL-A Vacuum Breaker Shaft Left 0.000 0.000 0.000 0.000
- VBSR-A Vacuum Breaker Shaft Right 0.000 0,000 a .000 0.000
{ VBSL-B Vacuum Breaker Shaft Left 0.000 D.or3 0.000 0.000 VBSR-B Vacuum Breaker Shaft Right 0.000 0.000 0.000 0.000 VBSL-C Vacuum Breaker Shaft Left 0.000 0.000 0.000 VBSR-C Vacuum Breaker Shaft Right 0.000 0.000 0.000 VBSL-D Vacuum Breaker Shaft Left 0.000 0.000 0.000 VBSR-D Vacuum Breaker Shaft Right 0.000 0.000 0.000 VBSL-E Vacuum Breaker Shaft Left 0.000 0.000 0.000 VBSR-E Vacuum Breaker Shaft Right 0.000 0.Ord 0.000
APPENDIX B R Summary Test Results for Type B Testina Page 4 of 4 LEAKAGE (LBM/HR) 1987 1989-PENETRATION INITIAL RETEST INITIALI RETEST NUMBER DESCRIPTION VBSL-F Vacuum Breaker Shaft Left 0.000 0.000 0.000 VBSR-F Vacuum Breaker Shaft Right 0.000 0.000 0.001' VBSL-G Vacuum Breaker Shaft Left 0.000- 0.000 0.000 VBSR-G Vacuum Breaker Shaft Right 0.002 0.000 0.000 VBSL-H Vacuum Breaker Shaft Left 0.000 0.000 0.000 VBSR-H Vacuum Breaker Shaft Right 0.000 0.000 0.000 VBSL-I- Vacuum Breaker Shaft Left 0.000 0.000 0.000 VBSR-I Vacuum Breaker Shaft Right 0.000 0.000 0.000 VBSL-J Vacuum Breaker Shaft Left 0.000 0.000 0.000 VBSR-J Vacuum Breaker Shaft Right 0.000 0.000 0.000 SLH-A Shear Lug Access Cover 0.000 0.000 SLH-B- Shear Lug Access Cover 0.000 0.000. SLH-C Shear Lug Access Cover 0.000 0.001 SLH-D Shear Lug Access Cover 0.000 0.000 SLH-E Shear Lug Access Cover 0.004 0.001 SLH-F Shear Lug Access Cover 0.000 0.000 SLH-G Shear Lug Access Cover 0.)04 0.005 SLH-H Shear Lug Access Cover 0.000 0.000 X-213-A Torus Orain 0.000 0.000 X-213-B Torus Drain 0.000 0.000
--.-n-,-----
9 i p '" '^$' .g, i.- APPENDIX C TYPE C TEST RESULTS f 1 l l
g .-_.,. APPENDIX C Summary Test Results for Type C Testina Page 1 of 4 LEAKAGE (LBM/HR) 1987 ' 1989 PENETRATION VALVE INITIAL RETEST INITIAL RETEST NUMBER TESTED DESCRIPTION X-7A MS80A A Main Steam Line 0.886 0.675 MS86A A Main Steam Line 1.850 4.02 X-7B MS80B B Main Steam Line 0.477 0.501 MS868 8 Main Steam Line 1.130 1.172 X-7C MS80C C Main Steam Line 0.252 0.000 MS86C C Main Steam Lino 0.748 1.075 X-7D MS80D D Main Steam Line 0.072 0.000 MS86D D Main Steam Line 0.500 1.213 X-8 MS-74 Main Steam Drain 0.000 0.321 MS-77 Main Steam Drain 0.525 0.503 0.378 X-9A FDW-27A Feedwater Check Valve 0.000 0.006 X-98 FDW-96A Feedwater Check Valve 0.071 Note (2) 0.004 Page 4/4 RCU-68 Reactor Cleanup 0.034 CRD-181 Control Rod Drive 0.034 X-10 RCIC-15 RCIC Steam Supply 0.000 0.000 RCIC-16 RCIC Steam Supply 0.281 0.210 X-11 HPCI-15 HPCI Steam Supply 0.000 0.000 HPCI-16 Reactor Cleanup 0.003 0.154 X-14 RCU-15 Reactor Cleanup 0.024 0.166 RCU-18 Reactor Cleanup 0.000 0.000 0.004
A'PENDIX C , ) Summary Test Results for Type C Testina Page 2 of 4 LEAKAGE (LBM/HR) 1987 1989 PENETRATION VALVE INITIAL RETEST INITIAL RETEST NUMBER TESTED DESCRIPTION X-16A CS-12A Core Spray Injection 0.0005 0.008 0.004 0.018 CS-11A Core Spray Iniection 0.0005 0.008 0.004 0.018 X-16B CS-12B Core Spray Injection 0.008 0.004 0.020 CS-11B Core Sprav In_iection 0.008 0.004 0.020 X-18 LRW-82 Drywell Floor Drain 0.012 0.014 LRW-83 Drywell Floor Drain 2.400 0.099 10.000 0.011 X-19 LRW-94 Drywell Equipment Drain 0.772 0.373 0.856 0.497 Drywell Equipment Drain 6.000 0.056 LRW-95 O.385 5.333 X-22 CA-89C Cont. Air Compressor 0.046 Note (2) 0.045 Page 4/4 CA-898 Cont. Air Compressor 0.005 0.048 0.000 IA-103 Instrument Air Valve 0.110 0.084 X-25 SB-6, Containment Exhaust 1.681 0.371 Note (3) 0.462 7,6A,6B (Per (Per Page 4/4 (Per 7A and valve) valve) valve) 7B X-25 VG-9A CAD Vent 0.006 0.001 VG-22A CAD Vent 0.032 0.036 0.001 X-26 XB-8,9 Containment Purge 2.194 0.009 0.824 0.059 10, and (Per (Per (Per (Per 23 valver valve) valve) valve) X-26 SB-22B Containment Purge 0.001 0.002 Makeup SB-20 Containment Purge 0.001 0.001 Makeup X-26 NG 13A CAD Injection 0.004 0.004
& 13B NG 11A CAD Injection 0.004 0.004
& 11B L__ _ __ - -
.1 W.
, APPENDIX C l
Summary Test Results for Type C Testina Page 3 of 4 l LEAKAGE (LBM/HR) 1987 1989 PENETRATION VALVE INITIAL RETEST INITIAL RETEST NUMBER TESTED DESCRIPTION X-26 SB-51 PCAC 0.055 0.055 SB-52 PCAC 0.055 0.007 X-31F CRD- Recirc Pump Seal Purge 0.023 0.120 0.102 413A 1 l CRD- Recire Pump Seal Purge 0.000 0.000 l 412A X-32F CRD- Recirc Pump Seal Purge 0.003 0.150 413B CRD- Recirc Pump Seal Purge 0.002 0.068 4138 X-35A N/A Tip Purge PNL Check 0.081 0.068 N/A Tip Purae Check Valve 0.002 0.01 X-35C N/A Tip Ball Valve #1 0.081 0.053 X-35D N/A Tip Ball Va_lve #2 0.439 0.196 X-35E N/A Tip Ball Valve #3 0.001 0.005 0.005 X-41 RV-39 Recire Sample 0.050 0.053 RV-40 Recire Sample 0.050 0.053 X-47 CA-38A Cont. Air Compressor 0.002 0.002 CA-38B Cont. Air Compressor 0.191 0.310 X-205 NG 12A CAD Injection 0.003 0.007
& 12B NG 11A CAD Injection Note (1) (1)
& 118 Page 4/4 X-205 SB-11A Vacuum Relief 0.007 0.86Y 0.276
& 12A (Total) (Total) (Total)
SB-11B Vacuum Relief 0.037 0.158
& 128 (Total) (Total)
c a : =* . APPENDIX C l l! Summary Test Results for Type C Testina Page 4 of 4 LEAKAGE (LBM/HR) 1987 1989 PENETRATION VALVE INITIAL RETEST INITIAL RETEST NUMBER TESTED DESCRIPTION X-205 SB-22A Containment Purge 0.001 0.001 l Makeup SB-20 Containment Purge (1) (1). Makeup SB-22B Containment Purge (1)- (1) Makeup X-216 VG-76A Rad. Mon. Return 0.001 0.001 VG-76B Rad. Mon. Heturn 0.001 0.001 X-218 VG-9B CAG Vent 0.002 0.001 VG-22B CAD Vent 0.001 0.004 0.000 X-220 VG-26 CAD Rad. Mon. Supply 0.000 0.001 VG-23 CAD Rad. Mon. Supply 0.001 0.001 Notes: ; (1) Reported 'Jnder X-26 (2) Could Not Pressurize Valve / Valve Group Utilizing Existing Equipment JMD/thm:ES9044.1/JMD _ _ _ _ _ -_--___--_- -_-_____- __-}}