ML20033B208
| ML20033B208 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 11/02/1981 |
| From: | Houston M Office of Nuclear Reactor Regulation |
| To: | Davidson D CLEVELAND ELECTRIC ILLUMINATING CO. |
| References | |
| NUDOCS 8112010032 | |
| Download: ML20033B208 (4) | |
Text
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DISTRIBUTION Docket NRC PDR NOV 2 1981 Local PDR TERA NISC TIC Docket Nos. 50-440 ACRS(16) and 50-441 LB#2 Reading ASchwencer MService Mr. Dalwyn R. Davidson Vice President - Engineering GThomas' DSI:RSB
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e The Cleveland Electric Illuminating
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Cleveland, Ohio 44101 i
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Dear Mr. Davidson:
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Subject:
Request for Additional Information - Reactor iSystett os Perry Nuclear Power Plant, Units 1 & 2 In the performance of the Perry licensing review, the staff has identified w
additional concerns in regard to reactor ;syste' ms The inforr.lition that we-require is identified in the enclosure. We plan to d*scuss these concerns with Bill Coleman of your staff during the week of November 9,1981.,
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We request that you provide the information not later than November'20, 1981.
If you require any clarification of this request, please contact me
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at (301) 492-8430.
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Sincerely, A
Origimi agned by
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e, M. Dean Houston, Project Manaher -
Licensing Branch flo. 2
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Division of Licensing
Enclosure:
Request for Additional Information cc w/ encl:
See next page
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Mr. Dalwyn' R. Davidson Vice President, Engineering The Cleveland Electric Illuminating Company P. O. Box 5000 Cleveland, Ohio 44101, cc: Gerald Charnoff, Esq.
Shaw, Pittman, Potts & Trowbridge 1800 M Street, N. W.
Washington, D. C. 20006 -
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Donald H. Hauser, Esq.
The Cleveland Electric Illuminating Company P. O. Box 5000 Cleveland, Ohio 44101 Resident Inspector's Office U.S.N.R.C.
Parmly at Center Road Perry, Ohio _4,4081 Donald T. Ezzone; Esq.
Assistant Prosecuting Attorney
. _10.5 Main Street _
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- - Lake County Admini_stration-Center
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Pair.esville, Ohio 44077 Tod J. Kdnney 228 South College', Apt. A Bowling Green, Ohio 43402 Daniel-D. Wilt Wegman, Hesiler & Vanderberg 7301 Chipp~ewa Road, Suite 102
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Brecksvijle, Ohio 44141 Robert Alexander OCRE Interim Representative 2030 Portsmouth Street Suite 2 Houston Texas 77098-.
Terry Lodge, Esq.
7 915 Spitzer Building Toledo, Ohio 43604 J
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ENCLOSURE 440.21 "Section 5.4.7.1.5 of the Perry FSAR considered alternate shutdown (5.4.7.1)
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cool.ing methods in the event the residual heat removal (RHR) system in the suction line may not be used. bec5use of valve failure.
Valves in the aytomatic depressurization system (ADS) are used to transfer fluid (steam, water or a combination of these) from the reactor vessel to the suppression pool. The RHR system removes the added heat by cooling water remove'd from the suppression pool and injecting it into the reactor vessel.
We require t, hat you cite test results or submit analysis to demon-strate that the ADS valves _can discharge the fluid flow under the most limiting c::nditions when the fluid is all water. Show that this alternate ethod is a viable means of shutdown cooling by c'om-
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Paring the system hydraulic losses with the av.ailable pump head.
Hy-draulic losses should be provided for each system component and, where-
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ever. possible, should be derived from experi; mental results."
How much time is required to achieve cold shutdown by this alternating method assuming one RHR train only is available fo'r pool cooling?
440.22 Operation of the RHR system in the steam condensing mode involves (5.4.7) partial drainin; of one or both RHR heat exchangers and introduction of reactor stear into initially cold lines and heat exchangers.
De-scribe the methcds (e.g., valve operation, air introduction, etc.) and provisions.to be used to prevent occurrence of water hammer during the initiation of o;eration in this mode, and the change to the pool cool-ing mode.
When the RHR is used in the steam condensing mode with one
or' both heat exchangers, can the jockey pump system fill the lines to the injection valve'in the core spray and RHR lines? If not, what procedures would be used to prevent water hammer following startup of the core spray or RHR pumps?
Pressure relief valves and lines designed to prevent overpressurization of '.he RHR system are routed outside containment before being returned to the suppression pool.
Discuss design provisions made to mitigate possible water hammer in there lines.
440.23 Discuss the procedures for minimizing the potential for exceeding the (5.4.7) allowable cooldown rate (greater tr.an ~100 degrees Fahrenheit / hour) of the RHR and the reactor coolant systen when placing the plant in-a shut-down cooling mode following planned normal conditions or an emergency.
.440.24. Discuss the RHR pump reliability fer long-term operation.
Long-term (5.4.7) reliability should be deronstrated by either operational experience or testing.
If previous operational experience should be cited as the basis for qualifying the pumps, state any pump design differences and conditions of previous pump operations.
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