ML20027D923
| ML20027D923 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 11/08/1982 |
| From: | Devincentis J PUBLIC SERVICE CO. OF NEW HAMPSHIRE, YANKEE ATOMIC ELECTRIC CO. |
| To: | Knighton G Office of Nuclear Reactor Regulation |
| References | |
| SBN-355, NUDOCS 8211100396 | |
| Download: ML20027D923 (12) | |
Text
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SEABM SMM IPUE5LIC SERVICE v.;..
- ., on.
Companyof Nea *Aampshre 1671 Worcester Road Framinoham, Massachusetts 01701 (617) - 872 - 8100 November 8, 1982 SBN 355 T.F. B7.1.2 United States Nuclear Regulatory Commission Washington, D. C. 20555 Attention:
Mr. George W. Knighton, Chief Licensing Branch 3 Division of Licensing
References:
(a) Construction Permits CPPR-135 and CPPR-136, Docket Nos. 50-443 and 50-444 (b) USNRC Letter, dated February 12, 1982, " Request for Additional Information," F. J. Miraglia to W. C. Tallman (c) USNRC tetter, dated March 12, 1982, " Response to 440 Series RAIs; (Reactor Systems Branch)," J. DeVincentis to F. J. Miraglia
Subject:
Revised Response to 440 Series RAIs; (Reactor Systems Branch)
Dear Sir:
We have enclosed revised responses to the following Requests for Additional Information (RAIs) which were forwarded in Reference (b):
440.5, 440.6, 440.8, 440.25, 440.39 Responses or revised responses to the 440 Series RAIs will be included in Amendment 48..
Very truly yours, YANKEE ATOMIC ELECTRIC COMPANY
/
g J. DeVincentis Project Manager ALL/fsf 8211100396 821108 DR ADOCK 05000443 PDR
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440.5
RESPONSE
A new analysis is being performed to demonstrate that the sizing criteria employed in the design of the Seabrook safety valves is as conservative as that recommended in SRP 5.2.2.
The results of this analysis will be provided when they are available.
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RESPONSE
The assumed instrument and control errors are provided in Section 15.0.3.2 of the FSAR. They are as follows:
2% Power l
5.80 Temperature 30 psi Pressure i
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bI r /2[fg SB 1 & 2 FSAR RAI 440.8 (5.2.2)
Provide assurance that loading due to water relief has been considered in the support analysis, including the passage of a water slug and ef fects of water hammer. What liquid water relief rates were assumed in the loading analysis? Are these values consistent with experimental results obtained from similar valves?
RESPONSE
The redesign of the pressurizer safety and relief valve piping has elimi-nated the water seals from the safety valve piping. The new piping configu-ration has been analyzed through the use of the RELAP-5 computer program to determine the loadings to which the piping will be subjected under steam discharge and also water discharge. The associated effects are then factored into the piping and support analysis.
The liquid water relief rates used in the analysis were:
344,644 #/hr for the PORVs and 481,500 #/hr for the safety valves.
These values were extracted from the EPRI reports as typical values for this application.
y
440.25 Provide or reference a discussion on methods utilized to prevent freezing of the RWST and RWST vent line.
RESPONSE
FSAR Subsection 6.2.2.3 will be updated to provide additional information, demonstrating that freezing temperatures will not occur. See RAI Response to 440.//A for Section 6.2.2.3.
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440.39 Provide a discussion of NPSH requirements for all ECCS pumps.
Include in this discussion NPSH as required by pump warranty, estimated variability between pumps, and testing inaccuracies.
Also provide the assumptions and calculations used to establish available NPSH.
RESPONSE
A discussion of the calculational method used to determine the NPSH for the ECCS pumps is given in Seabrook FSAR Section 6.3.2.2.
For RHR pumps, see also Section 5.4.7.
The required and available NPSH values are given in Table 6.3-1.
Pump curves for RHR, HHSI/CH, SI pumps are attached.
For the RHR pumps, the NPSH evaluation is based on one RHR pump discharging flow to two RCS loops and both SI and HHSI/CH pump suctions. The limiting single failure is the second RHR pump, with the corresponding NPSH requirement based on the runout flow resulting from this most limiting failure.
For the SI and HHSI/CH pumps, the limiting single failure is the second SI or HHSI/CH pumps, respectively.
The corresponding NPSH requirement is based on the runout flow resulting from this most limiting single failure. Prioperational full flow tests are also performed on the systems to verify calculated maximum runout conditions. This serves as a final assurance of acceptable system performance.
ECCS puup specifications include a specified maximum required NPSH which t ie pump is required to meet. Pump vendors have verified that the required NPSH for the pumps was less than the maximum required NPSH through testing in accordance with the criteria established by the Hydraulic Institute Standards. Further, from the pump h9ad/ flow and NPSH required characteristic curves that are derived from the testing, Westinghouse subsequently confirmed that adequate NPSH is available based on the actual system piping layouts, and conservatively calculated maximum pump runout verified by preoperational testing.
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