ML20049A683
| ML20049A683 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 09/16/1981 |
| From: | Houston M Office of Nuclear Reactor Regulation |
| To: | Davidson D CLEVELAND ELECTRIC ILLUMINATING CO. |
| References | |
| NUDOCS 8110010405 | |
| Download: ML20049A683 (5) | |
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4 SEP l 6 ggg, Docket tios. 50-440 s
and 50-441
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.,9 Mr. Dalwyn R. Davidson d
Vic.e President Engineering
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'S The Cleveland Electric Illuminating Company
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P. O. Box 5000 O
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s Cleveland, Ohio 44101
Dear Mr. Davidson:
Subject:
Request For Additional Information-Reactor Systens In the performance of the Perry licensing review, the staff has identified concerns in regard to reactor systems. The information that we require is identified in the enclosure and was discussed with Bill Coleman on September 11, 1981.
We request that you provide the information not later than October 30, 1981.
If you require any clarification of this request, pleaso contact me at (301) 492-8593.
Sincerely,
. H. Dean Houston, Project Manager Licensing Branch No. 2
~ Division of Licensing
Enclosure:
Distribution:
bcc Request for Additional Docket File NRC PDR Information LB#2 Local PDR DEisenhut/RPurple NSIC cc w/ enclosure:
RTedesco TERA See next page ASchwencer TIC DHouston ACR3 (16)
Mervice I&E (3) 8110010405 810916 PDR ADOCK 05000440 PDR h
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s Mr. Dalwyn R. DIvidstn Vice President, Engineering The Cleveland Electric Illuminating Company P. O. Box 5000 Cleveland, Ohio 44101 cc: G+.rald Charnoff, Esq.
Shaw, Pittman, Potts & Trowbridge 1800 M Street, N. W.
Washington, D. C. 20006 Donald H. Hauser, Esq.
The Cleveland Electric Illuminating Company P. O. Box 5000 Cleveland, Ohio 44101 l
Resident Inspector's Office U.S.N.R.C.
Parmly at Center Road Perry, Ohio 44081 Donald T. Ezzone, Esq.
Assistant Prosecuting Attorney 105 Main Street Lake County Adninistration Center Painesville, Ohio 44077 Tod J. Kenney 228 South College, Apt. A Bowling Green, Ohio 43402 Daniel D. Wilt Wegman, Hesiler & Vanderberg 7301 Chippewa Road, Suite 102 Brecksville, Ohio 44141 Robert Alexander OCRE Interim Representative 2030 Portsmouth Street Suite 2 Houston Texas 77098 Terry Lodge, Esq.
915 Spitzer Building Toledo, Ohio 43604
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I ENCLOSURE 440.11 BWR operating experience has shown that the HPCI and RCIC systems (5.4.6) have been rendered inoperable because of inadvertent leak detection isolations caused by equipment room area high differential tempera-ture signal. The events occurred when there was a relatively sharp drop in outside temperature. As noted in Section 5.4.6.1.1.1 and Table 5.2.8, Perry incorporates this type of RCIC and RHR (steam) isolation.
Provide a discussion of the modifications that have bden or will be made to prevent inadvertent isolations of this type which affect the availability and reliability of the RCIC and the RHR systems.
Secondly, provide the trip settings for isolation of the RHR and RCIC systems due to high area temperature in terms of degrees above ambient temperature.
Also, discuss the method of specification that would be applied.
Show that the setting could not be set too low and cause inadvertent isolation when the system is needed.
440.12 Describe the provisions used for protection of the RCIC and the RHR (5.4.6) systems from cold weather in order to assure satisfactory operational performance. Also, in the assessment include the standby liquid control and the control rod drive hydraulic systems and sources of water (e.g., CST standby service water) for all the above systems.
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t 440.13 It appears that it is possible for some steam condtnsate to remain (5.4.b) in the lines leading to the RCIC steam turbine.
(This occurs when the steam isolation valves would be temporar.ily closed for main-tenance.)
Discuss whether the amount of liquid can cause damage to the RCIC turbine so that the system is incapable of delivering water to the reactor vessel as required.
440.14 Identify the most limiting operating condition with regard to NPSH (5.4.6) requirements and specify the NPSH margin under this condition.
440.15 Confirm that the RCIC electro-hydraulic system integrated with the (5.4.6) turbine governing valve is of a safety-grade design (e.g., seismic Category I).
440.16 Describe and provide a drawing for the sparger in the RCIC turbine (5.4.6) exhaust line.
440.17 We require.that the technical specifications include provision for:
(5.4.6) a) periodic high point venting of ECCS and RCIC discharge lines, b) flow and functional tests of the RCIC.
440.18 Turbine exhaust vacuum breaker valves are identified as E514:077 (5.4.6) and E51-F078 in Figure 5-4.9 of the FSAR.
But, in page 5-4.26 (Section 5.4.6.2.1.g), they are identified as E51-F080 and E51-F086.
Please clarify.
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440.19 Response to the following TMI action items are required tc com-
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(5.4.6) plete the review of Section 5.4.6.
(a)
TMI Item II.K.l.22 - Auxiliary Heat Removal A plant specific response describing Perry design provisions is re-quired. References to BWR Owners' position and NED0-25224 are not sufficient.
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(b)
TMI Item II.K.3.13 We request that the applicant submit an acceptable response to the requirements included in Action Plan item II.K.3.13, possible need for separation of RCIC and HPCS initiation levels and restart capa-bility of RCIC on low water level (NUREG-0737).
(c)
TMI Item II.K.3.15 We request that the applicant submit an acceptable response for Item II.K.3.15, provisions for preventing inadvertent RCIC system isolation or trip.
440.20 Isometric drawings, incl _uding slope a,nd elevation; for the RHR system, (5.4.6)
~ including the steamline from the RCIC supply line to the RHR heat exchangers.
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