ML20154P290
| ML20154P290 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 09/26/1988 |
| From: | George Thomas PUBLIC SERVICE CO. OF NEW HAMPSHIRE |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NYN-88129, NUDOCS 8810030010 | |
| Download: ML20154P290 (26) | |
Text
{{#Wiki_filter:. _ _ _. I George S. Thomas W.e he64end Nvclect hoducMon NYN. 88129 Putsc Servios of New HampeNro September 26. 1988 N3r Harnpshire Yankee DMsion j United States Nuclear Regulatory Comission Vashington, D.C. 20555 { Attention: Document Control Desk j
References:
(a) Facility operating License No. NFF.56. Docket No. 50 443 (b) PSNH Letter (NYN.87081). dated June 17, 1987 ' Inservice Testing (IST) of Pumps and Valves (Changes to Revision 1 of the Inservice Testing Program).' G. S. Thomas to NRC (c) PSNH Letter (NYN.88009) dated January 25, 1988 ' Inservice Testing (IST) of Pumps and Valves (Changes to Revision 1).' l 1 G. S. Thomas to NRC
Subject:
Inservice Testing (IST) of Pumps and Valves (Changes to Revision 1) i Gwntlemen Reference (b) provided changes to Revision 1 of the Seabrook Station Inservice Testing (IST) Program for pumps and valves. These changes were t i reviewed by the NRC Staff and their contractor. EGLG. On December 18, 1987, f l members of the NRC Staff. EGLG and New Hampshire Yankee (NNY) discussed. by l l telephone. several concerns that were identified during the review. These ( concerns were incorporated and submitted to the NRC in Reference (c). After 3 reviewing Reference (c). further coments by the NRC Staff were discussed with l NHY on March 25. 1988 and Kay 9. 1988. I Following these telephone conferences. NNY performed technical analyses i to identif y the minimum design flow and head requirements for each of the operating modes of the Service Water system and to determine the current operating conditions. These analyses demonstrate that there is a wide margin t between the required and actual system characteristics. (Ref: Relief Request [ P.3 attached). 1 similar worst case minimum design performance requirements will be i l M i N identified by NHY for all IST program pumps. The lower limit for all i 4 monitored performance parameters will be adjusted as necessary to ensure that ( the specified value satisfies the code requirement, as well as the minimm I J design requirements. 0 The enclosed material provides changes to the IST Program to resolve the l a 0 Staff concerns. Additionally. trends of total developed head observed to i M4 date, as well as vendor supplied performance characteristic curves for all f 4 l b pumps covered by Relief Request P.3 are provided in Attachment 1 to illustrate 8 actual fluctuations in test data as well as the extre=ely narrow performance i g band before the upper linit is exceeded. @9 ,moom.seamoo - m.1e,e one 3,m..m
United States Nuclear Regulatory Commission Septenbsr 26, 1988 . At t en' tion: Document Control Desk Page 2 Furthermore, a New Hampshire Yankee position is provided in Attachment 2, which assures the service Water system minimum design performance parameters are well below the current reference flow conditions. As illustrated by these numerical values, the pump performance is above the design requirements when dorated to the minimum allowable per ASHE Section XI. A pump failure while operating at this derated performance value has been reviewed by the pump vendor with regatd to degradation below the minimum design conditions without an associated rise in component vibrations. This evaluation shows that since there is such a large available margin for the Service Vater System pumps above the minimum design requirements, quarterly pump vibration monitoring will easily detect any developing pump failures. Should you have any further questions regarding this matter, please contact Mr Robert A. Gwinn at (603) 474 9574, extension 4056. l i Very truly yours. 4 8 ;rc 5 George S. Thomas Inclosure cci Mr. William T. Russell Regional Administrator Region ! United States Nuclear Regulatory Commission 475 Allendale Road King of Prussia. PA 19406 Mr. Victor Nerses. Project Manager Project Directorate 1 3 Division of Reactor Projects United $tates Nuclear Regulatory Commission Vashington, DC 20555 David G. Ruscitto Senior Resident Inspector P.O. Box 1149 Seabrook NH 03874
i l i ' G a I { e i P I t ENCLOSURE TO NYN I I t ( i I I: b d l b i 9 9 s f 4 4 4 s v 4 l s e d
Page 1 of 2 Relief Recuest: P-3 Pumps: SW-P-41A, SW-P-41B, SW-P-41C, SW-P-41D. SW-P-110A and SW-P-110B Code Class: 2 and 3 Function: Pumps required to perform a function in shutting down the reactor or in mitigating the consequences of an accident, and are provided witt. an emergency power source. Test Requirements: Table IWP-3100-2 specifies the allowable ranges of inservice test quantities in relation to reference values. This table limits the acceptable performance of the differential pressure (o P) for each pump to 103 percent (1.03 dPr). If the differential pressure of any pump exceeds this limit, the pump shall be declared ir. operable and not returned to service until the cause of the deviation has been determined and the condition corrected. Basis for Relief: The requirement to decla6e a pump inoperstive whea pump performance exceeds the reference value by 3 percent is i impractical and is not clearly indicative of pump degradation for the following reasons: a. The 3 percent linitation is overly restrictive when comparod to the total securacy of the instrumentation used to gather the test data. In order to consistently romain below the 3 percent limitation, extremely lower instrument loop accuracies than those required by Table IWP.tkio-1 wcuid have to be l estsblished. This is particularly evi6ent when testing p2mps that have high flow rates and low discharge head characteristic 6 suC/. as the pumps listed above. t b. Power piant operating systems were not design 9d to provide laboratorf type conditions required to meet the 3 percent limitatic,n. The se.vice water (SV) systems require the use of large butterfly valves using renote manual conttol to throttle large voluaer of water to the reference flow rar.e. NormTily f7.ow rates can only be established to i 100 spn of the specified reference flow, c. Reference values are specific sets of data determined by measuring or observing pump performance when a specific pump is known to be performing its required function acceptably. Herely exceeding the 3 percent limitation is not a clear signal of pump degradation. It may signify that the reference value is at the lower side of the statistical scatter of the test data in comparison with other periodic test data.
Page 2 of 2 Basis for Reliefs d. For the pumps listed, the difference between the (continued) differential pressure reference value and 103 percent required action value is approximately 2.0 psid. This is extremely restrictive and is easily exceeded by any combination of statistical scatter, instrument inaccuracy and minor flow variations. In the past, these pumps have been declared inoperable due to high differential pressure readings exceeding the 1 range by less than 0.5 paid. Further evalue of these conditions has shown there has been no pump degradation. Furthermore, since an actual increase in pump differential pressure is not indicative of degraded pump performance, it is not necessary to maintain such a strict upper limit. e. The minimum design flow requirements for the SW system pumps are as follows: 4 Flow Head i Service Water Pumps 8,700 gpm 34.9 psid Cooling Tower Pumps 11.360 gpm 47.1 psid j j These components are currently tested at the following 4 reference corditions: Minimum / Maximum Proposed Flow Head Limits Limit (0.90/1.03 x 4P ref) (.93/1.10 x 4 P ref) SW-P-41n 11,500 gpm 66.3 psid 59.7/68.3 61.2/72.9 SW-P-41B 11,500 gpn 67.1 psid 60.4/69.1 62.4/73.8 SV-P-41C 11,500 spn 65.2 psid 58.7/67.2 60.6/71.7 SV-P-41D 11,500 gpm 66.1 psid 59.5/68.1 61.5/72.7 i SW-P 110A 13,000 gpm 70.4 psid 63.4/72.5 65.5/77.5 1 SV-P-110B 13,000 gpn 69.6 csid 62.6/71.7 64.7/76.6 As can be seen from the above figures, there is a wide i margin between the design flow requirements and the lower limit while the difference between the current upper limit of 103Z and the reference values is very small. The proposed apper limit of 1102 would expand the allowed opsrating band to minimise unnecessarily declaring the pump inoperable due to a slightly high differential pressure. f. Relief from the 3 percent limitation will provide an acceptable level of quality and safety and will not endanger the health and safety of the public. Alternate Testing: The subject pumps shall be tested in accordance with ANSI /ASME CM-6, Table 6100-1. b e- ,w,
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.Relie'f Reauest: P-4 Pumps: SW-P-110A. LW-P-110B, SW-P-41A, SW-P-41B, SW-P-41C and SW-P-41D Code Class: 3 Function: Pumps required to perfonn a function in shutting down the reactor or in mitigating the consequences of an accident, and are provided with an emergency power source. Test Reauirements: IWP-4200 requires direct pressure measurements. Table IWP-4110-1 acceptable instrument accuracy for pressure measurement. Basis for Reliefs a) The above listed pumps are vertical turbine pumps with no direct mesns to obtain the inlet pressure measurements as required by IWP-4200. b) Plant installed level instrumentation is accurate to t 0.5% which is within the requirements of Table IWP-4110-1, but total loop accuracy is i 2.5% which exceeds the requirement of Table IWP-4110-1. Alternate Testina: The inlet pressure shall be calculated based on water level above the pump inlet using existing plant instrumentation to measure pump suction pressure.
' Relief Request: V-48 Valves: FR-V99, FW-V216, FW V357 and CO-V-340 Category: C Code Class: 3 and NNS Function: Active Test ReQuirments: IWV-3530 (3 months) Basis for Relief: Full flow through these normally closed check valves quarterly during power operations would require establishing emergency feedwater flow to the steam generators and would unnecessarily introduce cold water into the steam generators causing thermal shock to the feed nozzles. This is only full flow path for these valves. Thermal shocking of the feed nozzles could lead h to their premature failure. Al s'), introducing the required flow to full-stroke exercise these valves could cause feedwater control problems during operation which could lead to a plant trip. Alternate testina: All of these valves shall be full stroke exercised during cold shutdowns. CO-V-340 shall be partially stroked on a quarterly basis. 4 d 4 4 1 6 1 i e I
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T 1-SW-P-41-C 4 \\ PUMP TREND g t7e p CIA 3RODI G7/2.75011 _o _ DP Differential Presssure (ISID) 72.5 70.0 - -t r !N 67.5 Iligh Alarm = 67.1 \\ / \\ K, ref. Value = 65.1 65.0 - 1 \\' i 62.5 1 i, l '. 60.0 I Low Alarm = 58.7 I Cet ' ~ Jan ' Jul ' ' Oct ' Jan ' ' Apr ' ' Jul ' ' Jan Apr Oct 1986 1987 1983 1989 Time
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i ( -t ATTACHMENT 2 TO NYN i 1 i New Hampshire Yankee ASME XI IWP Position on Service Water Relief Request 4 4 4 4 { j I 4 \\ i i t l L f D ,r-.-- _...,_m_,-..
Page 1 of 2 New Hampshire Yankee Position Detection of Failure of High Volume / Low Head IST Program Pumps to Achieve Minimum Lesign Flow Requirements During a telephone conference call on May 9, 1988, between representatives of NHY and the NRC staff regarding proposed changes to revision 1 of the NHY Inservice Testing Program for Pumps and Valves, a question was raised regarding the potential failure mechanisms for pumps that would be characterized by a degradation in hydraulic performance without an ssociated rise in component vibration identifying the developing failure. Further, the specific concern was whether the possibility existed for a pump to be operating near the lower end of its ASME XI IWP allowed performance band when in fact an imminent failure would render it incapable of delivering the minimum design tiow required in a worst case accident scenario. Engineering evaluation and discussions with the vendor have concluded that due to the large margin available above the minimum design requirements, there is no known hydraulic failure mechanism resulting in a rapid failure of the SW 3 system pumps, rendering them incapable of delivering the minimum design required head and flow, which would not be preceded by symptomatic vibration readings. This evaluation is discussed in greater dotsil below. The relief request in question pertained to raising the upper limit for Total Developed Head for high volume / low head pump 3 in the Primary Component Cooling Water (PCCW) and Service Water (SW) systems. There were a total of ten pumpe affected by this relief request, six of which are two stage, deep draft, vertical line shaft pumps and four of which are single stage, horizontal, centrifugal pumps. The horizontal PCCW pumps have cince been removed from the relief request pending an analysis to det4rmine actual system performance above the design margin. Far the deep draft SW system pumps (including the Cooling Tower Pumps), vibration monitoring is performed at tne driver end cf the pump which As cignificantly removed from the submerged nump impellers. For this ceason, it cannot be assumed that all pump hydraulic degradation for the SW pumps i would initially be detected by vibration monitoring. However, due to the large available margin for the SW system pumps above the minimum design requirements, vibration monitoring will easily detect a developing failure and render the rump inoperable due to high vibration readings well before the pump approaches the design required flow or differential pressure. This is bacause there would have to be extreme degradatior, of pump performance before the design limits would be approached. Therefore, vibration monitoring combined with monitoring the hydraulic performance of these pumps does provide reasonable assurance that they are always capable of supplying at least the minimum required design flow. Surveillance testing demonstrates that there is adequate margin between the test point and the minimum required hydraulic design requirements even when j allowed degradation, test data scatter and cumulative instrument errors are i
~- Page 2 of 2 factored into the calculation. Per Request for Engineering Services, (RES) 88-0186, NHY has determined that the minimum required design performance requirements for the SW system pumps are as follows: Head Flow Service Water Pumps SW-P-41A - D 34.9 psid 8.700 gpm Cooling Tower Pumps SW-P-110A and B 47.1 psid 11.360 gpm These performance requirements were calculated using the following assumptions and informations a) System fouling at the maximum design allowance b) Suction pressure (tide or tower basin level) at minimum c) Simultaneous Loss of Coolant Accident (LOCA) and Loss of Offsite Power (LOOP) d) Design calcuation 4.3.8-72F, a computer program providing an iterative solution of Bernoulli's equation adjusted for actual performance results observed during startup testing. e) Design calcuation 4.3.8-57F identifying the cooling requirements for individual components cooled by the SW system. Calculation 4.3.8-57F, was used to determine the minimum design required flow based on the sum of t'ae individual cooling flow requirements for each ccmponent. Calculation 4.3.8-57F was used co identify the minimum pump head required to deliver this design flow reto aavuming the worst case conditionn identified in (a) through (c) above. Thess components are tested at che following reference conditions: Hesd Flow Service Water Pumps SW-P-41A 66.3 psid 11,500 gpm LV-P-41B 67.1 psid 11,500 gpm SW-P-410 65.2 psid 11,500 gpm SW-P-41D 66.1 psid 11,500 gpm Cccling Tower Pumps SW-P-110A 70.4 pri2 13,000 gym SW-P-1103 69.6 psid 13.000 gpr As c:.n be seea from tha above figures, the worst case minimum operating parameters are signiiicently above the design requirements even when 7! pump wear, test data acatter and cumulative instrument errors are considered. Based on these margins, there is no failure mechanism which would cause degradation in the hydraulic performance of the SW pumps in question which could result in a pump satisfactorily passing all surveillance requirements while being unable to achieve minimum design flow requirements. This evaluation has been reviewed with }!r. Ron Lov of Johnston Pumpa (1-800-227 2601) on July 1, 1988 and he has concurred with the conclusions reached.}}