JPN-88-012, Application for Amend to License DPR-59,requesting Exemption from Containment Integrated Leak Rate Test - Retest Schedule.Exemption Request,Corrective Action Plan & Plant Drawings Identifying Valve Location Encl.Fee Paid
| ML20151G038 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 04/08/1988 |
| From: | Brons J POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| JPN-88-012, JPN-88-12, NUDOCS 8804190161 | |
| Download: ML20151G038 (46) | |
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4# Authority t= COP" April 8, 1988 JPN-88-012 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555
SUBJECT:
James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 Request for Exemption from Containment Intearated Leak Rate Test - Retest Schedule
REFERENCE:
NYPA letter, R.J. Converse to the Director of Nuclear Reactor Regulation, dated August 21, 1985 (JAFP-85-0675).
Dear Sir:
10 CFR 50 Appendix J requires that a Type A Primary Containment Integrated Leak Rate Test (PCILRT) be conducted three times during each 10-year service period. Should two consecutive Type A tests fail to meet the applicable acceptance criteria, a retest must be performed during subsequent refueling outages until two consecutive tests meet the acceptance criteria. Reference 1 provided the results of the PCILRT conducted at FitzPatrick in May 1985. Although the test successfully demonstrated a leak tight contajnment, the test had to be considered a failure in the "as found" condition due to the penalty incurred for the Type B and C Local Leak Rate Tests (LLRTs) conducted during the outage. Valve leakage found during the LLRTs were r3 paired during the outage. The Authority then reviewed the results of the 1982 PCILRT and determined that it also had failed in the "as-found" condition due to LLRT results. This test was performed in accordance with the standard industry practice of that time and did not determine an "as-found" condition. Therefore, the Authority conducted a PCILRT in April 1987, during the first refueling outage after 1985. This test also failed the "as-found" condition due to local leakage. Since increased testing alone will not improve valve leakage, an aggressive valve replacement program is being implemented at an estimated cost of over three million dollars. The Authority proposes a corrective Action Plan featuring this valve replacement program in lieu of an increased test frequency q to maintain a high degree of containment integrity, o i s.c) r804190161 88040Et g,p N GS 'i~O bd W he0 PDR ADOCK 05000333 P DCD pgg .
i i Attachment I to this letter contains an exemption request to restore the retest schedule of Appendix J Section III.D(a) and exempt the FitzPatrick Plant from the requirements of Section III.A.6(b). This exemption is submitted in acordance with the provisions of 10 CFR 50.12. Attachment II contains the FitzPatrick Corrective Action Plan as technical justification for the exemption request. Attachment III contains plant drawings identifying the location of the valves in the replacement program. Because Section III.A.6(b) requires a retest at each refueling shutdown or approximately every 18 months, whichever occurs first, the next test is due in approximately October 1988 (18 months from the last test). The next refueling outage is scheduled to begin in August 1988. The Authority requests that the NRC respond to this exemption request by August 28, 1988, so that preparations for a PCILRT, should this exemption request be denied, can proceed in an orderly manner. In accordance with 10 CFR 170.12, a check in the amount of
$150.00 is enclosed as payment of the application fee for the review of the exemption request.
Should you or your staff have any questions regarding this matter, please contact Mr. J. A. Gray, Jr. of my staff. Very truly yours, 3 w John C. Brons 3xecutive Vice President iuclear Generation cc: U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Office of the Resident Inspector U.S. Nuclear Regulatory Commiscion P.O. Box 136 Lycoming, NY 13093 Mr. Harvey Abelson Project Directorate I-1 Division of Reactor Projects - I/II U.S. Nuclear Regulatory Commission 11555 Rockville Pike Rockville, MD 20852
i- .. ATTACHMENT I TO JPN-88-012
-~ EXEMPTION REQUEST CONTAINMENT lNTEGRATED LEAK RATE TEST RETEST SCHEDULE New York Power Authority JAMES A. FITZPATRICK NUCLEAR POWER PLANT Docket No. 50-333 DPR-59
JAMES A. FIT 3 PATRICK NUCLEAR POWER PLANT EXEMPTION REQUEST CONTAINNENT INTEGRATED LEAK RATE TEST - RETEST SCHEDULE In accordance with 10 CFR 50.12 (a) (2) (ii) , the New York Power Authority requests an exemption from 10 CFR SO Appendix J, Section III.A.6(b) which states, "If two consecutive periodic Type A tests fail to meet the applicable acceptance criteria on III.A.5(b), notwithstanding the periodic retest schedule of III.D, a Type A test shall be performed at each plant shutdown for refueling or approximately every 18 months whichever occurs first, until two consecutive Type A tests meet the acceptance criteria in III.A.5(b) after which time the retest schedule specified in III.D may be resumed." This exemption request is made so that the Type A retest schedule of Section III.D may be resumed at the FitzPatrick plant. Type A tests performed in 1982, 1985, and 1987 did not meet the newly defined acceptance criteria, and therefore the retest requirements of Section III.A.6(b) are applicable. The Authority requests an exemption from the requirement to perform a Type A Integrated Leakage Rate Test during the 1988 refueling outage. This will permit resumption of the normal retest schedule beginning with the 1990 refueling outage. 10 CFR 50 Appendix J establishes two types of tests utilizing separate acceptance criteria. The local leak rate tests (LLRT) (Type B and C) are performed during each refueling outage while the primary containment integrated leak rate test (PCILRT) (Type A) is performed three times in each 10 year inservice inspection (ISI) interval (approximately every 3 to 4 years). The LLRT provide periodic surveillance of components such as isolation valves and air lock seals. The PCILRT is a measurement of the overall integrated leakage rate of the containment. It includes testing of passive and structural components and verifies the adequacy of the LLRT program. Exceeding the allowable leakage rate during the PCILRT indicates that either a passive or structural component is leaking or that there may be an inadequacy in the LLRT program. For leaking passive or structural components, the only test that could determine that the leak exists or had been corrected would be the PCILRT. In the case of LLRT program deficiency, the PCILRT would serve as a means of verification of the LLRT program results. The failures of the FitzPatrick 1982, 1985, and 1987 "as-1 found" PCILRTs were the direct result of Type B and C penalty additions and not the failure of a passive or structural component. The cause of the failure (valve leakage) was repaired l
and tested prior to the PCILRT. The Type A PCILRT successfully met its leakage criteria. Performing the PCILRT more frequently due to LLRT failures, as required by Section III.A.6(b), has no benefit. Containment isolation valve leakage is identified and corrected during each refueling outage in the existing LLRT program. Performing additional PCILRTs merely results in increased outage length, increases radiation exposure, and provides no benefit to the health and safety of the general public. NRC IE Information Notice 85-71 dated August 22, 1985, states in part, "if Type B and C leakage rates constitute an identified contributor to this failure of the "as-found" condition for the CILRT, the general purpose of maintaining a high degree of containment integrity might be better served through an improved maintenance and testing program for containment penetration boundaries and isolation valves. In this situation, the licensee nay submit a Corrective Action Plan with an alternative leakage test program proposal as an exemption request for NRC review." The Authority is addressing the concern of excessive leakage observed during Type B and C testing through a Corrective Action Plan using the guidance contained in Information Notice 85-71. The Corrective Action Plan addresses:
- 1. Identification of "problem" valves.
- 2. Determination of appropriate action.
- 3. Implement short and long term corrective action.
10 CFR 50.12(a) indicates that the Commission may grant exemptions if special circumstances are present. One of the special circumstances presented in 50.12 (a) (2) (ii) is, "application of the regulation in the particular circumstances would not serve the underlying purpose of the rule or is not necessary to achieve the underlying purpose of the rule." The underlying purpose of 10 CFR 50 Appendix J, Section III.A.6(b) is to ensure that unacceptable containment leakage is identified and corrected. Implementation of the corrective Action Plan will ensure this underlying purpose is met through an aggressive program to identify and correct containment isolation valve leakage. Therefore, the provisions in 10 CFR 50.12 (a) (2) (ii) for application for an exemption have been met.
ATTACilMENT 11 TO JPN-88-012 CORRECTIVE ACTION PLAN New York Power Authority JAMES A. FITZPATRICK NUCLEAR POWER PLANT Docket No. 50-333 DPR-59 l i
9 JANES A. FIT 5 PATRICK NUCLEAR POWER PLANT LOCAL LEAK RATE TESTING (LLRT) CORRECTIVE ACTION PLAN I. Problems: A. FitzPatrick has consistantly demonstrated its containment to be essentially leak tight through succesful performance of Type A PCILRT tests. However, the 1982, 1985, and 1987 tests had to be considered failed in the "as-found" condition due to excessive penalty addition from Type B and C testing. B. FitzPatrick LLRT leakage consistently exceeds 0.6 La before repair. II. Root Cause of Problem: A. Containment isolation valve leakage. Specific valves have a history of repeated LLRT failures. B. Inability to trend individual valve performance on penetrations where two or more valves are subjected to a combined LLRT test. III. Objectives of Corrective Action Plan: A. Determine through historical review which valves have contributed an excessive amount of leakage during performance of LLRT. B. Determine through historical review which valves have shown a history of minimal or no leakage. C. Develop LLRT trending to track penetration / valve performance. IV. Corrective Action - LLRT Procram: A. Improve Valve Maintenance Practices
- 1. Purchase main steam isolation valve (MSIV) seat maintenance tool.
- 2. For penetrations where multiple containment isolation valves are tested in combination (i.e. by testing between valves in series), perform LLRT retest after maintenance is performed on a single valve.
i
]
l Combined testing of. valves in series results in an , overly conservative indication of penetration leakage .1 because this technique measures the sum of the , individual valve leakages. Actual penetration leakage is the minimum leakage through any valve in the penetration. By performining maintenance on only one valve followed by an LLRT retest, the leakage rate , for the unrepaired valve can be more accurately determined.
- 3. Improve the quality of valve repairs.
B. Identification of Valve Type / Manufacturer
- 1. Using historical data, identify the typta/ manufacturer of valves which have contributed an excessive amount :
- of leakage during the performance of LLRTs. L
- 2. Using historical data, identify the type / manufacturer of velves which have shown a history of minimal or no ,
leakage during the performance of LLETs. - C. Correction of Problem Penetrations: i lj Recommend / implement effective repair or replacement , methods on containment isolation valven identified as t historically poor performers (excessive leakage). D. Augmented LLRT Program In accordance with Appendix J, LLRT (Type B and C ,
~
testing) of containment penetrations is performed during s each refueling outage. As part of this corrective action plan, valve replacement and a detailed leakage trending , program are being implemented. Following completion of ' i the currently scheduled valve replacements, consideration will be given to an augmented LLRT program if expected LLRT leakage reductions do not occur. 1 It should be noted that the FitzPatrick Inservice Testing l t Program for Pumps and Valves addresses valve leakage. > It requires the LLRT test frequency to be doubled for individual CIVs which exceed specified leak rates. This program has been inspected by the NRC (Inspection No. 50-333/87-08) which found that the individual valve leakage criteria and accelerated testing "represent an initiative by the licensee above the requirements" of Appendix J. It has been the practice at the plant to repair valves in lieu of increased testing. Repairing , a valve better serves the purpose of maintaining a leak-tight containment than performing a retest 6 to 9 months later. '
~
4 V. Actions Comoleted To Date: A review of LLRT data from all refueling outages conducted from 1977 through 1987 has been completed. A listing of all valves which have failed LLRT during this 10 year period has been compiled. A MSIV seat maintenance tool was purchased from the MSIV valve manufacturer. Use of this tool has greatly improved , the quality of valve seat repairs. The results are seen as an improvement in the long term leakage characteristics of the MSIVs. Maintenance practices have changed such that whenever practical, only one containment isolation valve located in a combined valve test configuration receives maintenance prior to LLRT retest. Plant mechanics have received special training from valve ! vendors in conducting leak repairs. An INPO certified apprenticeship program for mechanics has been implemented at ; FitzPatrick which includes job training and qualification. Greater control of valve repair is also obtained by having all valve repairs performed or directly supervised by Authority personnel. Thirty-three containment isolation valves are currently scheduled for replacement during the 1988 and 1990 refueling outages. These valves will be replaced with valves that have better leakage characteristics and are easier to maintain. Current plans are to replace approximately twenty-one of the valves during the 1988 refueling outage, and the remainder in 1990. These valves are being replaced as a result of unsatisfactory LLRT performance and/or Reg. Guide 1.97 requirements. The valves are listed in Section VII and are shown in Attachment III. The "as-found" condition of the containment system is determined by subtracting the post-repair LLRT leakage from the pre-repair leakages for each penetration. The net equivalent leakage is equivalent to the leakage improvement obtained by repairs to the valves. The net equivalvent leakages for all penetrations and the ILRT measured leakage rate are then added together to determine the "as-found" containment leakage rate. The net equivalent leakage of the 33 valves scheduled for replacement was determined using data from the most recent (1987) PCILRT and LLRT. These penetrations, having a total "as-found" leakage rate of 19,500 scfd, contributed to over two-thirds of the total containment "as-found" leakage. Of the remaining 9,247 scfd leakage, over 90% can be attributed to a single penetration.
Tl.e two valves in the penetration mentioned above were tasted in a combined test. Maintenance was performed on both valves, therefore, an accurate determination of the penetration leakage characteristics was not possible. The
; net equivalent leakage of this penetration conservatively assumed that the measured leakage was evenly divided between the two valves. If one of the valves in this penetration was actually leak tight, then there would not have been an "as-found" leakage penalty for this penetration. Resolution of Item IV.A.2 will allow a better quantification of individual valve leakags and avoid taking unnecessary leakage penalties.
VI. Comoletion Schedule for Corrective Action Plan: Iten Title Comoletion Date III.C LLRT trending July 31, 1988 IV.B.1,2 Identify Valve type / July 31, 1988 manufacturer The Authority will submit a report to the commission (along 1 with the PCILRT report) following completion of the valve replacement program. In this report the Authority will discuss the effectiveness of this program and the need (if any) for further actions after the 1990 refueling outage such as an accelerated LLRT schedule. VII. Valve Replacement Schedule Valves to be Replaced in 1988: Valy.e Penetration Service Type C test results (note 1) 13-MOV-15 X-10 RCIC Steam Supply failed 3 LLRTs 12-MOV-15 X-14 RWCU supply failed 4 LLRTs 27-SOV-135A X-31Ad Cont. Rad. Monitor failed 2 LLRTs (note 2) 27-SOV-135B X-31Ad Cont. Rad. Monitor failed 5 LLRTs (note 2) 10-MOV-26A X-39A RHR Cont. Spray failed 2 LLRTs 10-MOV-31A X-39A RHR Cont. Spray failed 1 LLRT 10-MOV-26B X-39B RHR Cont. Spray failed 5 LLRTs 10-MOV-31B X-39B RHR Cont. Spray failed 2 LLRTs 02-2-AOV-39 X-41 Rx. Water Sample failed 1 LLRT (note 2) 02-2-AC7-40 X-41 Rx. Water Sample failed 0 LLRTs (note 2) 27-SOV-125A X-55B Cont. Rad. Monitor failed 0 LLRTs (note 2) 27-SOV-125B X-SSB Cont. Rad. Monitor failed 4 LLRTs (note 2) e-
27-SOV-124E1 X-203B Cont. Atm. Monitor failed 0 LLRTs (note 2) 27-SOV-124E2 X-203B Cont. Atm. Monitor failed 0 LLRTs (note 2) 13-RCIC-4 X-212 RCIC Exhaust Check failed 7 LLRTs 13-RCIC-5 X-212 RCIC Exhaust Check failed 7 LLRTs 23-HPI-11 X-214 HPCI Manual Iso. (note 3) 23-HPI-12 X-214 HPCI Exhaust Check failed 4 LLRTs 23-HPI-65 X-214 HPCI Exhaust check failed 7 LLRTo 13-RCIC-7 X-221 RCIC Cond. Return failed 4 LLRTs 13-RCIC-8 X-221 RCIC Cond. Return failed 2 LLRTs Note 1: Results are based on seven tests conducted over the past ten years. ! Note 2: This valve is being replaced due to the requirements of ! Reg. Guide 1.97. Note 3: Not a containment isolation valve. However, this valve forms part of the LLRT test boundary and its leakage is attributed to the CIV under test. l Valves to be Replaced in 1990: Valve Penetration Service Tvoe C test results (note 11 29-MOV-74 X-8 MSIV drain failed 3 LLRTs 34-NRV-111A X-9A Feedwater Check failed 2 LLRTs 34-NRV-111B X-9B Feedwater Check failed 5 LLRTs 13-MOV-16 X-10 RCIC Steam Supply failed 0 LLRTs 12-MOV-18 X-14 RWCU supply failed 2 LLRTs 20-MOV-94 X-19 Equip. drain sump failed 3 LLRTs 20-AOV-95 X-19 Equip. drain sump failed 2 LLRTs 27-CAD-68 X-25 Cont. Inert. Check failed 7 LLRTs 27-CAD-69 X-25 Cont. Inert. Check failed 1 LLRT 27-CAD-67 X-220 Cont. Inert. Check failed 2 LLRTs 27-CAD-70 X-220 Cont. Inert. Check failed 3 LLRTs 11-SLC-16 X-42 Stby Liquid Check failed 3 LLRTs Note 1: Results are based on seven tests conducted over the past ten years.
, I 1
VIII. Integrated Leak Rate Test A. Guidance provided in NRC IE Information Notice 85-71 ! indicates that an improved maintenance and test program for containment penetration boundaries and isolation valves could be an acceptable alternative to increasing the frequency of Type A tests. In this regard, the aggressive actions listed above will ensure that positive steps are being taken to eliminate the excessive leakage from containment isolation valves found during the LLRT program. B. The Corrective Action Plan will ensure that containment integrity is maintained. The result of the plan will ensure that in the event of an accident, the dose levels do not exceed 10 CFR 100 limits. Therefore, this alternate improved maintenance and testing (Type B and C) plan better meets the intent of 10 CFR 50, Appendix J than increased Type A test frequency. C. The schedule for performing containment leakage tests during the second 10 year ISI interval is as follows: OUTAGE DATE TEST January, 1987 LLRT and ILRT August, 1988 LLRT Spring, 1990 LLRT and ILRT Fall, 1991 LLRT Fall, 1993 LLRT and ILRT
e a ATTACilMENT 111 TO JPN-88-012 PLANT DRAW!NGS .l l New York Power Authority JAMES A. FITZPATRICK NUCLEAR PCWER PLANT Docket No. 50-333 DPR-59
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