ML20148R639
| ML20148R639 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 01/25/1988 |
| From: | George Thomas PUBLIC SERVICE CO. OF NEW HAMPSHIRE |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NYN-88009, NUDOCS 8802020247 | |
| Download: ML20148R639 (10) | |
Text
1 George S. Thomas vu mesoent. Nuclear hoovenon Put2c SeMee of New HompeNro N;w Hampshire Yankee Division NYN-88009 January 25, 1988 United States N'iclear Regulatory Commission Washington, DC 20555 Attention:
Document Control Desk
References:
(a)
Facility Operating License No. NPF-56, Docket No. 50-443 (b)
PSNH Letter (SBN-1086), dated June 4, 1986, "Inservice Testing (IST) of Pumps and Valves (SER Outstanding Issue No. 4)," G. S. Thomas to V. S. Noonan (c)
PSNH Lecter (SBN-1136), dated June 23, 1986, "Inservice Testing (IST) of Pumps and Valves (SER Outstanding Issue No. 4)," G. S. Thomas to V. S. Noonan (d)
PSNH Letter (SBN-1144), dated June 25, 1986, ' Inservice Testing (IST) of Pumps and Valves (SER Outstanding Issue No. 4) Relief Request No. 46 "
G. S. Thomas to V. S. Noonan (e)
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
Subject:
Inservice Testing (IST) of Pumps and Valves (Changes to Revision 1)
Gentlemen:
Reference (e) provided changes to Revision 1 of the Seabrook Station Inservice Testing (IST) Program for pumps and valves.
These changes were reviewed by the NRC Staff and their contractor, EG&G. On December 18, 1987, members of the NRC Staff, EGLG, and New Hampshire Yankee (NHY) discussed, by telephone, several concerns that were identified during the review.
The enclosed material provides the changes to the IST program that are necessary to resolve the Staff concerns.
OfCK 05099443 47 800125 P
PDR fb P.O. Box 300. Seabrook, NH 03874. Telephone (603) 474-9574
/
United States Nuclear Regulatory Commission January 25, 1988 Attention:
Document Control' Desk Page 2 Should you have any further questions regarding this matter, please contact our Bethesda office (Mr. R. E. Sweeney) at 301-656-6100.
Very truly yours,
-d< fjf s
~
~ d'eorge I Thomas Enclosure cci Mr. William T. Russell Regional Administrator Region I United States Nuclear Regulatory Commission 4
425 Allendale Road King of Prussia. PA 19406 Mr. Victor Nerses, Project Manager-i Project Directorate I-3 Division of Reactor Projects United States Nuclear Regulatory Commission Washington, DC 20555 Mr. Antone C. Cerne NRC Senior Resident Inspector i
Seabrook Station
(
Seabrook, NH 03874 i
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Page 1 of 2 Relief Request:
P-3 P umps :
CC-P-l l A, CC-P-ll B, CC-P-llc, CC-P-ll D, RH-P-8 A, RH-P-8 B, SW-P-41 A, SW-P-41 B, SW-P-41C, SW-P-41D, SW-P-110 A 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 with an emergency power source.
Test Requirements:
Table IWP-3100-2 specifies the allowable ranges of inser-vice test quantities in relation to reference values.
This table limits the acceptable performance of the dif-ferential pressure ( 21 P) for each pump to 103 percent (1,0343Pr).
If the differential pressure of any pump exceeds this limit, the pump shall be declared inoperable and not returned to service until the cause of the deviation has been determined and the condition corrected.
Basis for Relief:
The requirement to declare a pump iroperative when pump performance exceeds the reference value by 3 percent is impractical and is not clearly indicative of pump degrada-tion for the following reasons:
a.
The 3 percent limitation is overly restrictive when compared to the total accuracy of the ins t r ume n t a t ion used to gather the test data.
In order to con-sistently remain below the 3 percent limitation, extremely lower instrument loop accuracies than those required by Table IWP-4110-1 would have to be established. This is particularly evident when testing pumps that have high flow rates and low discharge head characteristics such as the pumps listed above, b.
Power plant operating systems were not designed to provide laboratory type conditions required to meet the 3 percent limitation. The primary component cooling water (CC) and service water (SW) systems require the use of large butterfly valves using remote manual control to throttle large volumes of water to the reference flow rate.
Normally flow rates can only be established to + 100 gpm of the specified reference flow.
A deviation of flow of 200 gpm can signifi-cantly affect measured test quantities.
Rev. 1
Page 2 of 2 Basis for Relief:
(continued) c.
Reference values are specific sets of values deter-mined by measuring or observing pump performance when a specific pump is known to be performing its required function acceptably. Merely 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.
d.
For the pumps listed, the difference between the dif-ferential pressure reference value and 103 percent required action value have been in the range from 1.7 to 5.7 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 allowed range by less than 0.5 psid.
Further evaluation of these conditions has shown there has been no pump degradation.
Further-more, since an actual increase in pump differential pressure is not indicative of degraded pump perfor-mance, it is not necessary to maintain such a strict upper limit, e.
Relief from the 3 percent limitation will provide an acceptable level of quality and safety and will not endanger the public.
Alternate Testinl[*
Pumps shall be tested in accordance with Subsection IWP with the following exceptions:
a.
The Required Action Range (High) will be a value greater than 1.10 /1 Pr.
b.
The Alert Range (High) will be a value greater than 1.05 21 Pr.
Rev. I
Relief Request:
P-4 Pumps:
SW-P-110A, SW-P-110B, SW-P-41 A, SW-P-41 B, SW-P-41C and SW-P-41D Code Class:
3 Function:
Pumps required to perform a function in shutting down the reactor or in mitigating the consequences of an accident, and are provided with an emergency power source.
Test Requirements:
IWP-4200 requires direct pressure measurements.
Table IWP-4110-1 acceptable instrument accuracy for pressure measurement.
Basis for Relief:
a) The above listed pumps are vertical turbine pumps with no direct means to obtain the inlet pressure measurements as required by IWP-4200.
b) Plant installed level instrumentation is accurate to +
0.5%whichiswithintherequirementsofTableIWP-4110-17 but total loop accuracy is + 2.5% which exceeds the requirement of Table IWP-4110-1.
Alternate Testing:
The inlet pressure shall be calculated based on the water level above the pump inlet using existing plant in s t rume n-tation to measure pump suction pressure.
Relief Request:
V-48 Valves:
FW-V99, FW-V216, FW-V357 and Co-V-340 Category:
C Code Class:
3 and NNS Function:
Active Test Requirements:
1WV-3530 (3 months)
Basis for Relief:
Full flow through these normally closed check valves quar-terly during power operations would require establishing emergency feedwater flow to the steam generators and would unnecessarily introduce cold water into the steam genera-tors causing thermal shock to the feed nozzles. This is the only full flow path for these valves. Thermal shocking of the feed nozzles could lead to their premature failure. Also, 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 Testing:
All of these valves shall be full stroke exercised during cold shutdowns. Co-V-340 shall be partially stroked on a quarterly basis.
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