ML20063F081
ML20063F081 | |
Person / Time | |
---|---|
Site: | Sequoyah |
Issue date: | 02/02/1994 |
From: | Fenech R TENNESSEE VALLEY AUTHORITY |
To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
References | |
NUDOCS 9402140083 | |
Download: ML20063F081 (18) | |
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Tennessee VaBefAuthorny. PoM 0%e Bos 2000. hadrDa'sy, Tennewee 37379-2000 -
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Robert A. Fenech Vice Wesident. 5eavoyah Nackar P? ant i
February 2, 1994 ;
i U.S. Nuclear Regulatory Commission +
ATTN: Document Control Desk Washington, D.C. 20555 Centlemen: f In the Matter of ) Docket No. 50-328 .i Tennessee Valley Authority ) {
.i SEQUOYAH NUCLEAR PLANT (SQN) - UNIT 2 CENTRIFUGAL CHARGING. PUMP (CCP) 2B-B- i POSTMAINTENANCE TESTING SUITABILITY i i
t On January 7,1994, the 2B-B CCP shaf t broke as a result of an event i initiated by a high-cycle fatigue failure. .A matched spare element was-utilized to repair the 2B-B pump; and a subsequent American Society of. i Mechanical Engineers,Section XI, pump test was performed to' validate the l pump head and establish a baseline. As requested by NRC'during a January 10, 1994, telecon, Enclosure 1 provides the basis for TVA's position that a modification to the emergency core cooling system (ECCS), :
subsystem flow characteristics has not occurred. Based on Enclosure 1, . l' the ECCS flow tests specified by Technical Specification (TS)~ Surveillance' Requirement (SR) 4.5.2.h will not be required. 'However, a flow verification test will be performed es scheduled during the upcoming Unit 2 Cycle 6 refueling outage.
It should be pointed out that performance of a system flow test, as specified by TS SR 4.5.2.h, is normally performed.each refueling outage .
with the reactor vessel head removed and the reactor ~ coolant pumps jacked' '
up. Performance of1the system flow test in other than this configuration L
unnecessarily challenges the cold overpressure protection system and has ;
been a suspected source of seal degradation if seal injection is being ,
maintained during the-test. In addition, performance of the full flow I test in the current plant configuration is estimated to delay plant .i restart two to three days. l l
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PDR. ADDCK 05000328L g P. PDR. E ]fs ( !
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- U.S. Nuclear Regulatory Commission Page 2 ,
February 2, 1994 ,
Enclosure - 2 contains the commitmen"; provided in this submittal.
Please direct questions concerning this issue to J. D. Smith at '
(615) 843-6672.
Sincerely, ,
h$ $ Y~A Robert A. Fenech Enclosures cc (Enclosures):
Mr. D. E. LaBarge, Project Manager i U.S. Nuclear Regulatory Commission One White Flint. North 11555 Rockville Pike Rockville, Maryland.20852-2739 NRC Resident inspector Sequoyah Nuclear Plant 2600 Igou Ferry Road Soddy-Daisy, Tennessee 37379-3624 Regional Administrator U.S. Nuclear Regulatory Commission Region II ,
101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323-2711 l
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mk w a- I s ENCLOSURE 1 S57 940108 880 ACCEPTANCE OF INSTALLING THE SPARE ELEMENT S/N 36532C-SPARE II INTO THE CCP 2B-B PUMP LOCATION AND PMT REQUIREMENTS r
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k ACCEPTANCE OF INSTALLING THE SPARE ELEMENT INTO THE 2B-B CCP LOCATION WITHOUT PERFORMING A FULL FLOW TEST.
Tech Specs section 3/4.5.2 surveillance requirements requires the sum of the injection flow rates, excluding the highest flow -
rate must be greater or equal to 309 gpm (commonly referred to as the N minus 1 criteria or number of loops minus one) and the total pump flow must be less than or equal to 555 gpm. AS described in Tech Specs this requirement applies when modifications are performed to the ECCS subsystems that alter the flow characteristics. Though not addressed in Tech Specs there.is also- ;
a design requirement that the pumps not be allowed to degrade below '
a minimum ECCS performance curve. This minimum ECCS performance r curve insures that the system resistance is not reduced to '
compensate for weak pumps. Not all design base accidents will result in RCS pressure stabilizing immediately at ambient i conditions where the flow balance is performed. Having a lower >
resistance than assumed in the analysis would result in more flow ,
being lost thru the assumed break (in the lowest resistance branch.
line) when the RCS pressure is higher than those during the actual balance. From graph 1 it can be seen both the original and spare elements are well above the Min ECCS performance curve and add ;
margin to the analysis.
From graph 1 and table I it can also be seen all 3-pump performance curves have very similar characteristics with-the spare ;
curve being between the 2A-A and 2B-B at the critical area or- I maximum flow. Near the low flow area of the curve the spare element has a slightly higher head which is a desirable characteristic yet insignificant.
From table I and graph II it can be seen the old 2B-B pump ,
has shown negligible degradation since its original installation'in
'983 with all flow balance points shown. Although field discharge pressure test data has not agreed with the vendor certified curve performed on an ideal test loop it is a known fact the-specific- l plant piping layout includes a short run of discharge piping (3 ft) '
leaving a nonconcentric discharge nozzle with a ninety degree elbow-immediately followed by the miniflow tee. In the middle of these components is the discharge pressure tap. It should be'noted SNP has never been able to achieve test data as high as the vendor ,
certified curve and the plant test data has always been in the ;
conservative direction in relation to the Min ECCS performance curve. As seen on graph II a direct correlation does exist. The ;
latest flow balances are seen on graphs IV and V.
A review was also conducted on the ten years of Section XI l test data. (Ref Table III and Graph III) This shows at miniflow conditions the average head loss for the 2B-B pump was 18 psig over a 10 year period. Using the conversion of 4.3 lbs of pressure increase yeilds an increase of 1 gpm and applied uniformly across the pump performance curve only a 4 gpm increase in flow would be ;
expected at the max flow conditions. The 2B-B' pump flow was left "
at 538.24 gpm during the 1992 flow balance or 16.8 gpm from runout.
Thus enough margin is available to absorb the additional flow. -
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t Westinghouse -(see attached memo)' has also reviewed and -j discussed the following areas with TVA which include:
NORMAL CHARGING l TESTING FLOW BALANCING I PUMP RUNOUT .
t NPSH REQUIREMENTS RPM i HORSEPOWER ,
CONCLUSION: THE. SPARE ELEMENT 36532C-SPARE II CAN BE i INSTALLED AND VERIFIED ACCEPTABLE WITHOUT A FULL FLOW TEST. A :
SECTION XI TEST IS REQU' IRED TO BASELINE THE PUMP. A FULL FLOW TEST !
WILL BE PERFORMED NEXT REFUELING OUTAGE IN ACCORDANCE WITH i SEQUOYAH'S NORMAL SCHEDULE.
vd / 7/3 NSSS YS M EN INEER 8
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PUMP VENDOR DATA 2A-A FLOW 2B-B TEST SPARE MINIMUM HD HD DATA HD ECCS CURVE 1769 550 3250 455 1 4499 359 5281 277 5855 166 5892 107 5944 0 5988 84 5907 --,
164 5826 284 5098 370 4331 454 3326 550 1836 551 1774 458 3232 355 4581 262 5440 150 6047 .
66 6124 ,
0 6129 5410 ,
50 5400 100 5300 150 5110 200 4875 250 4575 '.
300 4175 ;
350 3675 400 3085 450 2200' 500 1140 525 500 '
549 1235 1990 548 1237 1986 538 1320 1992 -3 536 1327 1983 ;
533 1261 1989-
- PAS 7 TEST ****************
9/24/83 1327 536
- YEAR 10/16/86 1237 549 *j 2/07/89- 1261 533
- 10/12/90 1235 549
- 3/24/92 1320 538 *
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HEAD FT FLOW
- i TOTAL
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UNIT 2 CCP PERFORMANCE -
CURVES 4
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O- 2A-A' VEND PERF CURV -+- 28-B VEND PERF: CURV .o SPARE VEND PERF CUR ,
A. MINIMUN CURVE- ' .
X TEST'83,86,89,90,92 w-r t me + - w e+-ee w ey -wt em -i- 11---eew m- +k-t++w+r w =M-+--wn aem e *e-be,-w-4,e--re<re- *+-7 m + 4 ws- 1 ' s e e e
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~~========== ================ =========== FOR HEAD FLOW HEAD, FLOW HEAD FLOW TEST (FEET) (GPM) (FEET)' (GPM) (FEET) (GPM) DATA t
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- 5110 150 2214.78 491.5 5281 277 X^3= --0.00018 4875 200 2618.94 454.6 4499 359 X'4= 1.SE-07 4575 250 .3046.19 431.7 3250 455 4175 300 3541.57 392 1769 550 3675 350 4188.22 343.4 3085 400 4811.78 270.6 2200 450 5181 29 214 1140 500 5504.62 114.2
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A GEAPH Y 28-B CCP TEST DATA ECCS MINIMUM U2C5RC VENDOR CURVE FIT ;
PERFORMANCE DATA DATA COEFFICIENTS
===------------- -------~~~- FOR HEAD FLOW HEAD FLOW HEAD FLOW TEST (FEET) (GPM) (FEET) (GPM) (FEET) (GPM) DATA 5410 0 1319.63 538.24 5988 0 C- 6247.455 5400 50 1675.06 520.6 5907 84 X- -9.70844 5300 100 2298.38 458.1 5826 164 X^2- 0.058383 ,
5110 150 3028.18 411.6 5098 284 X"3- -0.00021 ,
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- 3085 400 5275.29 202.9 -
2200 450 5536.26 137.9 1140 500 500 525 CCP 2B-B PERFORMANCE CURVE +
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FSE/FSDA-94-2386 .
From: Fluid Systems Engineering WIN: 284-5917 Date: January 7,1994
Subject:
CCP Failure Evaluation To: J. Steinmetz cc: L Walker j M.P. Osborne ,
K.N. Garner File : Sequoyah Operating Plant The Sequoyah Nuclear Station Unit 2 experienced a failure of the 2-BB Centrifugal Charging Pump (CCP) on Janua2y 7,1994. Sequoyah Engineering requested ,
Westinghouse to evaluate the replacement element impact on the system performance. ;
Westinghouse (Auxiliary Equipment Group and Fluid Systems) evaluated the following .;
4
$;s:en performance areas:
- Normal Charging Function
- Safety Injection Function
- Flow Balancing
- Pump Runout Issue. ,
- ECCS Minimum Performane. *
' Brake Horse Power
- NPSH Requirements ,
" RPM Comparison ,
- Testing 1 General Comment : ,
The replacement rotating element, as shown in the attached Table, is very similar to _
CCP 2BB. The replacement element head is slightly higher ( 50 to 100 ft) from 0 to 300 l GPM, the same at 400 and 500 gpm and 50 ft, lower at the pump runout of 550 gpm. :
'Also, the replacement vender curve data falls in between the installed 2AA and the j failed 2BB vender curves, i
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2AA 36532C Revised 2BB 36532D -
Spare 36532C-Spare II
- Normal Charging Fimetion :
P Tne replacement element will meet the normal charging functions. .
- Safety Injection Function
- Flow Balancing :
L The failed element, CCP 2BB, was installed and the system balanced in ,
9/83. The spare / replacement element pump characteristics are very similar
( See attached Table) to that of the 2BB vender data. In fact, the ;
replacement element vender curve data lies between the 2AA and 2BB test t performance curves.
Conclusion : Based on the pumps characteristics being very similar and the system not being rebalanced since the initial installation of elements' 2AA :
and 2BB, the system need not be rebalanced with the installation of the i spare element. Tne system resistance has not been significantly changed. .
i
- Pep Ru=ut Issu : Not an issue since the spare element runout head is less, !
sc that d 2BB.
- ECCS Minimum Performance : Not a issue since the replacement pump performance is similar to 2BB and slightly higher than 2AA ( See Attached .
Table). The system configuration / resistance has not been significantly changed,' .
therefore there is not an impact to the Sequoyah ECCS model. .
- Brake Horse Power : Not an issue since they are the similar.
Spare BHP is 670 and 2BB BHP is 680.
" NPSH Requirements :Not an issue since the NPSH requirements for the ..
1 replacement element (NPSHR @ 550 is 16.5) is less than that of 2BB (NPSHR @
.i 550 is 18).
a RPM Comparison : Not an issue. The speed requirements are slightly less than !
the originalinstalled element. Tne effect to pump head is negligible.
k 1
.. . . ~ - -. - _ . - -. .- . . . . --.
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- Testing :
i Westinghouse Recommendation :
Initial Installation : Test Data at Mini-flow and or at the maximum flowrate the plant ;
can achieve during plant operating conditions. Evaluate the replacement element data ;
against that of 2BB. y Next Plant Shutdown : Perform a pump test curve. Evaluate the replacement element data against that of 2BB. ,
Verified By -
D. F. Dudek, Engineer J.G. Dudiak, Engineer :
Fluid System Design and Analysis Auxiliary Equipment Group ,
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1 Sequoyah U 2 CCP Shaft Failure Evaluation Flow 00 100 200 300 400 500 550 (GPM) .
2AA 5950 5900 5700 5100 4000 2550 1750 Head '
(FT)
Vender Curve 36532C ;
2AA 114 gpm 214 gpm 392 gpm 505 gpm 552 Head 5504 ft 5181 ft 3541 ft 1972 ft gpm Test 1395 ft (FT) 2BB 6000 5900 5700 5000 4000 2650 1850 Head (FT)
Vender ,
, Cun'c '
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'l 36532D j j l- l b l
l 27 7 202 gpm 300 gpm 411 gpm 538 H .d 5275 ft 4454 ft 3028 ft gpm .
Test 1319 ft l (PT)
Spare o100 6050 5800 5050 4000 2650 1800 i Head :
(FT)
Vender ;
Curve i 36532C-Spare II i
O' ENCLOSURE 2 l Commitment The full flow tests described in Technical Specification 4'.5.2.h that involve flow from the 2B-B centrifugal charging pump will be performed ,
during Unit 2 Cycle 6 refueling outage. l 2
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