ML20082U173
| ML20082U173 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 09/13/1991 |
| From: | Schuster T COMMONWEALTH EDISON CO. |
| To: | Murley T NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9109200040 | |
| Download: ML20082U173 (36) | |
Text
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( C Downers Grove. Illinois 60515 V
September 13,1991 Dr. Thomas E. Murley, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commissic a Washington, D.C. 20555 Attn: Document Control Desk
Subject:
Byron Station Units 1 and 2 Inservice Testing Program for Pumps and Valves, Revision 9a and 10c respectively NBCRochetNos<50 45tand_50-A55
References:
(a) May 23,1991 letter to Dr. T.E. Murley submitting a new Inservice Testing (IST)
Program Plan for Pumps and Valvcs, Revision 9 and 10/10a.
(b) August 8,1991 and August 29,1991 Teleconferences between the NRC Staff, Byron Station and Nuclear Licensing Department Personnel.
Dear Dr. Murley:
Attached is a revision to the IST Program Plan for Valve Relief Request VR 19 and Pump Relief Requests PR 1 and PR 7 which is being submitted for NRC Staff review. These relief requests wore originally submitted for NRC Staff review in Reference (a) and have been subsequently revised to address NRC Staff comments ex:)ressed during the teleconferences of Reference (b). Revision lines in the right hanc margins identify each change. Please direct any questions you may have regarding this request to this office.
Respectfully, Yuffll.h/ha tW G.
Terence K. Schuster Nuclear Licensing Administrator Attachments A. Hsia, Project Manager - NRR cc:
W. Kropp, Senior Resident Ins 3ector - Byron A. Bert Davis, Regional Admin strator - Rill s, :A m omo-, mm ZNLD/1165/12 PDR ADoc K 050004'54 100013 P
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September 13,1991 ATTACHMENT Content (34 pages)
- 1) Valve Rollef Request VR-19
- 2) Pump Relief Roquest PR-1
- 3) Pump Relief Riquest PR-7 ZNLD/1165/13
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R3v. 10c REL11L_1EQlJEST VR-12
-1.
Ealye Numbergt 1Ar001A 2AF001A 1AT0018 2AF001B 2.
Rumber of Valvagt 4
[
t 3.
ASNE_Codelategory:
AC and C 4..
ASME Code, Eggtlon II Requitamants Esercise check valves to the position required to fulfill their function (open a Cts closed = Bt), unless such operation 16 not practical during plant operation, per IWV-3522.
l 5.
Basis for 131131 Adequate closure capab111tles of these valves can not be verified by' performing a back pressure test due to the multiple boundary isolation points.
This configuration makes it impossible to tesign any observed leakage to any individual component.
- 6.
AlttInste Tsatingi The A train and B train valves are of the same design (manuf acturer, sise-model number, and materials construction) and have the same service conditions, including orientation, therefore they form a sample disassembly group Y
,_,,,,.Qtgup 1 0roup 2 1Ar001A 2AT001A 1Ar0018 2Ar001B One valveLfrom each group, on a per-unit basis, will be tested each refueling outage.
If the disassembled valve is not capable of being full-stroke esercised or-if there is binding or failure of valve internals,-the remaining valve on the affected unit will be inspected.
7.
Justificatlog Performing a pressure' test to verify closure is impractical due to the system configuration.
To' perform this test it would be necessary to attach a pump to a test connection and pressurise the line containing the
[
valve.
Ilowever, this line also contains many potential leakage paths (valves, pump seal, and instrument lines).. It is impossible to assign a leakage value to any specific path.
1 L
-(0095D/0035D/051791) 4.6 -'page 30 of 39
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Rov. 10c ELiff_.RCdjI!iT VR-1]l Cont.
7.
Justifications (cont)
The alternate test frequency is justifiable in that removal of these valves requires that the system be taken out of service for an estended period of time. Due to Safety System Performance, Probabilistic Risk Assessment (FRA), and availability concerns involving the Aus111ary feedwater system these valves cannot be removed on a quarterly f requency without impacting plant safety. Maintenance history and previous inspections of these valves at Byron and Braidwood stations has shown no evidence of degradation or impairment.
Industry esperience, as documented in NPRDS, showed no history of problems with these valves.
A company wide check valve evaluation addressing the "EPRI Applications Guidelines for Check Valves in Nuclear Power Plants: revealed that the location, orientation and application of these valves are not conducive to the type of wear or degra6stion correlated with SOER 86-03 type problems.
- However, they still required some level of monitoring to detect hidden problems.
The alternate test method is sufficient to insure operability of these valves and is consistent with Generic Letter 89-04.
Although these valves will be stroke tested per the ASME Section ); code requirements for cold shutdown valves, they also have an additional Technical Specification requirement.
Per note 12 these valves are full stroke tested during cold shutdown in accordance with Technical Specification 4.7.1.2.2 which insures the operability of the Aus111ary reedwater flow path to each steam generator by verifying flow to each steam generator following each cold shutdown of 30 days prior to entering Mode 2.
Testing at this frequency is sufficient to insure operability of this system and forms the basis of this Technical Specification.
8.
Applicable _ Time Per. igd:
This relief is requested once per quarter during the first inspection interval.
9.
Approval status:
a.
delief gr anted per NRC Generic Letter 89-04.
b.
Revised to include more detail on only AF valves in reponse to 5/7/91 NRC teleconference; relief granted per Generic Letter 89-04.
(0095D/0035D/051791) 4.f - page 31 of 39 l
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a DRATT REVISION OF RELIEF REQUEST NO. PR-1 1.
EUMPRTJt All pumps in the program plan.
2.
NUMBER Of ITEMSt 42 pumps.
3.
ASME CQDE CLASS:
2 f. 3
.4.
AEME CODE. SECTICal XI REQUIRE!(ENTS:
In reference to Table IWP-3100-0, " Allowable Ranges of Test Quantities". pump vibration is to be measured in and compared to values given in mila displacement.
i
. 5.
BAgis ron nrtIEri The measuremeht of pump vibration is required so that developing problems can be detected and repairs initiated prior to a pump becoming inoperable. Measurement of vibration only in displacement quantities, as required by the ASME Code, does not take into account i
frequency which is also an important factor in determining the severity of the vibration.
6.
ALTERNATE TESTINQ:
The ASME Code minimum. standards require measurement of the vibration amplitude in mils (displacement).. Byron Station proposes an alternate program of measuring vibration velocity (inches per second)
L which is more comprehensive than that required by Section KI.
This technique is an industry-accepted method which is much more meaningful and sensitive to small changes that are indicative.cf developing mechanical problems. These velocity measurements detect not only high amplitude vibration, that indicates a major mechanical problem such as misalignment or unbalance, but also the equally harmful low amplitude, high frequency vibration due to bearing wear that usually goes undetected by simple displacement measurements.
The allowable ranges of vibration-and their associated action levels will_be patterned after the guidelines established in ANSI /ASME OMb-1989, Part 6, Table.3 and Table 3a.
These ranges will be used in whole to assess equipment operational readiness for all components
-except the Essential Service Water Make-up Pumps OSX02PA & B (see PR-7),
e i
F (0091D/0034D/090591) 3.5 - page 11 of 17
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a DRATT REVISION Or i
RELIET REQUEST NO. PR-1 The acceptable performance range for all components (escept the Essential Service Water Hake Up Pumps OSX02PA & B) will be as follows:
Acceptance Alert Required Action Range Range Range (in/sec)
(in/sec)
(in/sec) i V12.5Vr 2.5Vr<V16.0Vr V > 6. 0V r and or or V10.325 0.325<V10.700 V>0.700 Tor all pumps, evaluation of data, to assign equipment to the Alert or Required.Actiun ranges, will be done immediately per the l
requirements of NRC Generic Letter 89-C;, Attachment le position 8.
1 This will be done using industry accepted vibration analysis equi pment, such as a full spectrum analyse *.
Vibration measurements for all pumps will be obtained and recorded _in velocity, anches per second, and will be broadband unfiltered (filtered-out (IRD) or total (TEC Smart meter)) Peak measurements.
The monitored locations for vibration analysis will be marked so as r.o petmit subsequent duplication in both location and plane.
The frequency response range of the vibration transducers and their readout system shall be capable of frequency responses from one-third i
minimum pump shaf t rotational speed to at least one thousand herts.
t The Centrifugal Pumps in the program will have vibration-measurements taken in a plane approximately perpendicular to the rotating shaft in two orthogonal directions on each accessible pump bearing housing and in the axial direction on each accessible pump thrust bearing housing.
t 7.
J111IIUCAT10til Measurements of vibration in alls displacement are not sensitive to small. changes that are indicative of developing mechanical problems.
Therefore, the proposed alternate method of-measuring vibration amplitude in inches /second (in conjunction with the use of_the allowable vibration ranges and limits as established in ANSI /ASME OMb-1989, Part 6) provides added assurance of the continued operability of the pumps, f
8.
AEELICARLE TIME PEkIOD This relief is requested once per quarter during the first inspection' interval.
9.
APPROVAL STATUSI L This tellef request is a proposed-change to the approved PR-1 and is NQT approved for use. Formal written approval from-the NRC is required prior to changing the vibration monitoring points on the vertical line shaf t pumps in the program.
(1/2RH01PA,-
1/2RH01PB, 1/2CS01PA, 1/2CS01PB).
Expedited review and approval is requerted.
(0091D/0034D/090591) 3.5 - page 12 of 17
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DRATT RELIEF REQUEST PD. PR-7 w
1.
PUMP NUMBERt OSX02PA, 5 pumps 2.
NUMBER OF ITEMR8 2 pumps.
3.
ASME CODE CLASS:
2&3 4.
ASME CODE. SECTION 11,1EQLillEMENTS:
ANSI /ASME OKb-1989, Part 6 states "If deviations fall within the alert range of Table 3, the frequency of testing specified in paragraph 5.1 shall be doubled until the I
cause of the deviation is determined and the condition corrected.
If deviations fall within the required action range of Table 3, the pump shall be declared inoperable until the cause of the deviation has been determined and the condition corrected.
k:
When a test shows deviations outside the acceptable range of table 3, the instruments involved may be recalibrated and the test terun."
TABLE 3 Pume Pwne feet Accessante Alset Reisuered Ivee
$esed Paranweeg Ranee lance Action Range
>L$ V,to e v,ot
> 6 V, or Centneveal ano
< boo rom Vg or V, s 2.$ V, verticas 6.ne
> 101 mus
> 22 mais shan # Note ibt 4
I Centtousas ano a 600 tom V, or Va s 2.5 Vr
>2.3 Vrto 6 Vror
> 6 V, ot
-e v+mcas une
>9.323inssec
> 010 6n.<sec shaft INote ibt 7 6 V.-
f Rectorocatine Vd ot v, s 2.3 Ve
>2.3 Vrto e vr t
1 I
5.
BASIS FOR RELfi{t The Essential Service Water Pumps OSX02PA & B are of a very unique design (see Tig. 1).
The pump is attached to a horizontal die e1 driver via a right angle gear drive, and the gear drive is located approsimately 39 feet above the pump.
This configuration assures pump oper~ ability during the design basis floocing of the Rock River.' As would be espected, this estreme configuration results in vibration characteristics which are different from pumps of a more conventional design.
The vibration i
levels for these pumps are consistently higher than the commonly espected values. These pumps exhibited higher than usual vibration levels at the time of their installation (approximately 0.4 - 0.45 in/sec for the gear box and approximately 0.20 - 0.25 in/sec for the-2 i
Pump), at which time they were verified by the vendor to be operating Properly, and have continued to display high vibration levels throughout their service life.
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(00911s/0034D/090591) 3.5 - pa'ge 15 of 17 e
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DRATT RELIEF REQUEST HO. PR-7 6.
ALTERNATE TESTINGt Also characteristic of these pumps ja the fact that the gear bon vibration levels are consistently higher than the pump vibration levels. We propose that, in order to properly monitor this uniquely designed pump, separate acceptan'ce ranges be used for the gear box and the pump. The vibration levels for the pump, though consistently higher than those for conventional pumps, display no significant upward trend over a period of approximately sis years.
This is significant evidence that these vibration levels are characteristic of this unique design and do not indicate pump degradation.
However, we propose that tighter acceptance criteria be used for the pump than for the gear 90s in order to detect any degradation that may occur in the future.
Based on performance data, Byron Station proposes that the following ranges be utilised to monitor vibration levels for OSX02PA & B (where V e the vibration amplitude (in inches per second) and Vr = the reference vibration amplitude (in inches per second] established when the pump was known to be operating acceptably):
OSX02PA & B Acceptance Alert Required Action Location Range Range Range fin /sec) fin /sec) fin /ngg1_.
fin /ste)
Pump Shaft V12.5Vr
- 2. 5V r < V16. 0V r V>6.0Vr and or or V10.325 0.325tV10.700 V>0.700 Gearbos V12.5Vr 2.5Vr<vi6.0Vr v>6.0Vr and or or V 0.600 0.600(V10.900 V>0.900 1
Additions 11y, although it is obvious that this pump has unusual charatteristics and understandably high vibration levels, we plan to maintain conservatism in our maintenance practices and replace the gear assembly when parts are available to re-verify that the high.
vibration levels are characteristic of this pump design.
7 JUSTIriCATICH - A review of past performance parameters for the SX Hake-up pumps has been completed.
Attached are graphs of flowrate and vibration data over the last 2.5 years of operation.
Prior to 1989 i
only the matimum peak vibretion values were recorded with associated
(
orientation thtrefore, the prior data catuot be directly compared to i
recent data. From the atta: bed plett.(gee attachments A ard B) and l
tables (soe table 1 and i) it ct.n be seen that the vibration flucturtes dramnticaliy but showed no overall upward trend over a 2.5 year period.
1 (0091D/0034D/090591) 3.5 - page 16 of 17
Rsv. 00 DRAfl IET REQUEST
.t..
PR-7 7.
JUSTIFICATIONt(cont)
Also, Commonwealth Edison System Material Analysis Department (SMAD) measured vibration levels at the points shown in figure 2 and compared the results to available data on vibration amplitudes for similar gear drive arrangements throughout the company. These were diesel driven fire punip units at Braidwood, Zion, and Dresden stations.
Regardless of vendor, these four units all exhibited high vibration amplitudes on the gear drive consistent with the elevated vibratloa levolu recorded on the SX Make-up pumps at Byron Station (see figure 3).
The OH-6 limit on the alert range for vibration is either 2.5 times the reference value or 0.325 (whichever is less) and the code limit on the required action range is 6.0 times the reference value or 0.700 (whichever is less).
Based on engineering judgement, an alert range value of 0.600 and a required action value of 0.900 were s-lected as conservative limits in comparison to the OH-6 limits.
OM-6 limits allow an increase of 140% between the alert limit and the required action limid (for 2.5 times reference to 6.0 times reference) or an increase of 115% (for the 0.325 to 0.700).
The alert limit being proposed here is 0.600 (a limit recognized as a reasonable limit in the secent 7/15/91 NRC conference call) and the required action range is 0.900.
The proposed range here is 0.50%
increase from alert to required action. This is a much more conservative increase than the OH-6 requirement.
By using acceptance ranges which are reflective of the intrinsic characteristics of the pump, performance can be monitored more effectively and unnecessary and excessive testing of nroperly functioning equipment can be avoided.
8.
APPLICABLE TIME PERIOD:
This relief is requested quarterly, during each inservice pump test, during the first inspection interval.
9.
APPROVAL STATUS:
a.
November '90: SX Make-up Pump vibration limit relief request moved from SELIEF REQUEST NO. PR-1 to RELIET REQUEST NO. PR-7 for clarification.
b.
March '91: Additional information plus sepatate pump Shaft and Gearbox limits proposed based on NRC request for additional information.
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c.
August '91: Additional information on operating history and elevated vibration levels on similar pumps added based on NRC l
request for additional information.
Relief pending per Approval from the NRC is required PRIOR to use of this relief request.
Expedited review and approval is requeste'.
(0091D/0034D/090591) 3 3 - page 17 of 17
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.800-
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- 750 -
.- 7 2 5 -
- 100 - - - - - - - - - - - - ~ ~ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ~ ~ - - - - - - - - -
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.625-
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.450-
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.400-
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L
.150 -
125-c-
j' 100-
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.050-
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.850 -
825 -
.800 -
775-
. 7 5 0 '-
.725-
.700-
------------- ---------------------------------~~----------
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{
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100 -
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.050-
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.000----~~~-------------------,----,---------...........................................
i 12/05/87 04/18/89 08/31/90 01/13/92 TEST 0 ATE
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anaennan a page 3 of 10 OSN g?ON OSX02PA PUMP UNE SHAFT VIBRATION (RAD E-W)(IN/SEC)
VPLSHE-
.900-E75-
,850-
.625-500-
,775-
.750-725-
,700- ----------~~--------------------------------------------------------~~-------------
,675-
.650-
- 625-
.600-
.575-550-525-500-
.475-
.450-
. '42 5 -
.-400 -
375-
.350-325- ----------------------- -------- --- ----------------- ----- ------- -------------
.100-275-
.250-
,225-
.200-
,t75-
.150-125-
.100-J075-
.050-
.025-
.000....................................................................................
i 12/05/57 04/18/89 06/31/90 01/13/92 TESTDATE
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page 4 of to poS OSN' OSX02PA UPPER GEAR BOX VIBRATION (VERT) (IN/SEC)
VUGBV
.900- ---------------------------~~------- ------------------------------------~~----------
.875-
.850-
.825 2
.800-
.775 -
.750-
.725-
.700-
.675-
.650-
.625 2
.600- ----------------------------------~~-------------------------------------------------
.575-
.550-
,525-
.500 -
.' 4 7 5 -
.450-
.425-
,400 2
.375-
.350-
.325-
.300-
.275-
.250-
.225-
.200-
.175-15 0 ~-
,125-100-
.075-
.050-r
.025-
.000---------,--------,-------------------------------------------------------------------;
12/05/57 04/16/69 08/31/90 01/13/92 TESTDATE
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.875-
.850 -
.'8 2 5 -
.800-775-730-725-
.700-
.e75-
.650-
.625-
.600- ---------~~----------- -~~------------------------------ --------------------------
575-
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.500-
. 475 -
.450-425-
.400-
.? ?5 -
1150-325-300-275-
.250-
.225-
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. ISO -
125 -
100 -
- 075 -
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.025 -
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.12/05/87 04/18/89
' 08/31/90 01/13/92 TESTDATE
01/3 ATTACHMENT A page 6 of to OSd i
gy0 N OSX02PA UPPER GEAR BOX VIBRATION (RAD E-W) (IN/SEC)
VUGBRE
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.675-
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.550-
.525-
.500 -
.475-
.450-
.425 -
.400-
.375-
.350-
.325-
.600-
.275-
.250-
.225-
'200-175-
.150 -
125 -
100 -
.075
.050 -
.025 -
.000---------.--.--.-.-.--.----.--.--.-.--.--.--.-.--.--.----.--.--.-.--.--.----------i 12/05/67 04/16/89 08/31/90 01/13/92 TESTDATE
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VLGBV
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.875-
.850-
.825-
.800-
.775-
.750-
.725-
,700-
.675-
.630-
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VLGBE
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9 01 / 3 ATTACHMENT A Page 10 of to j OSd N
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