ML20091K565
| ML20091K565 | |
| Person / Time | |
|---|---|
| Site: | 05000000, Pilgrim |
| Issue date: | 05/27/1976 |
| From: | Norian P Office of Nuclear Reactor Regulation |
| To: | Ziemann D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17139C189 | List:
|
| References | |
| FOIA-84-105 NUDOCS 8406070136 | |
| Download: ML20091K565 (2) | |
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UNITED STAT'ES VUCLEAR REGULATORY COMMISSION.
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WASHINGTON, D. C. 20555 k*****
'iAy 2 71976
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Docket No. 50-293
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Dennis L. Ziemann, Chief, erating Reactors Branch #2, DPM THRU: Zoltan R. Rosztoczy, Chief, Analysis Branch, DSS i
REQUEST FOR ADDITIONAL INFORMATION - PILGRIM UNIT 1 Document Name:- Pilgrim Unit 1 l
Docket No.: 50-293 Licensing Stage: Post OL Milestone No.: 5 Additional Information Requests Responsible Branch and Project Manager:
LWR-2, P. O'Connor Technical Review Branch Involved: Analysis Branch Descript!.on of Review: Supplemental Questions Requested Completion Date: N/S Review Status: Additional Information Requested
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-To assist completion of our review of the proposed single loop
'i operation for the Pilgrim Unit 1 plant,.the additicnal information requested I
in the anclosure will be needed.
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Paul E. Norian, Section Leader
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Systems Analysis Section Analysis Branch Division of Systems Safety cc:
D. Ross T. Novak M onnor R. Frahm R. Audette p
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8406070136'840319' PDR FOIA-BELL 84-105 PDR.
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w BOSTON EDISON COMPANY PILGRIM UNIT 1 DOCKET No. 50-293
.s REVIE'4 0F SINGLE LOOP OPERATION
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REQUEST FOR ADDITIONAL INFORMATION
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- 1. Furnish, in graphical form, the results of a complete DBA LOCA calculation for Pilgrim when operating in the single recirenlation
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loop mode. Also, provide the resulcs of a co=plete break spectrum s
.analysis-to demonstrate that the DBA is the limiting. case. The
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paraceters of interest are as follows:
Peak Clad Temperature (ruptured and unruptured nodes)
Reactor Vessel Pressure
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Water Level Inside the Shroud Thercal Power Heat Transfer Coefficients.
- 2. ' Pr5 vide a set of calculations as a function of core life for l
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l Pilgrim to justify selection of the MAPLHGR curve.
The above l
. parameters should be provided in graphical form.
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~7 JUN 8 1962 Docket No. 50-298 MEHORANDUM FOR:
Thomas N. I!cvak, Assistant Director for Operating Reacters, D1 FRCM:
Themi; P. Speis, Assist?.nt Direcfor for Reactor Safety, DSI
SUBJECT:
COOPER UUCLEAR STATION SINGLE LOOP OPERATION, NEBRASPA PUBLIC POWER DISTRICT Plant Name:
Cooper Nuclear Station Docket Number:
50-298 f;SSS Supplier:
General Electric Responsible Branch: ORB-2 Projectfianager; B. L. Siegel Review Status:
Complete TAC tiumber:
42418 Cooper SER for Single Loop Operation (SLO) with power operation limited to 50%
was issued on December 10, 1931. The following requirements were among tne conditions for SLO. a) APRM flux noise will be measured once per shift and the recirculation pump speed will be reduced if the flux noise exceeds 5-percent peak to peak. b) The core plate delta noise be measured once ter shift and the recirculation pump speed will be reduced if the noise exceeds 1 psi peak to peak.
The staff requires that the licensee perform daily surveillance on the jet pumps to ensure that the pressure drop for one jet pump in a loop does not vary frca the mean of all jet punps in that loop by more than 5%.
The above requirements were imposed based on SLO experience of other EURs especially Browns Ferry-l.
Butthelicensee(NebraskaPublicPowerDistrict) during a tele-conference on February 11, 1982 has indicated that the operating margins we imposed for APRH flux noise and core plate delta noise are too stringent and too difficult to conform during SLO. The licensee requested relief from the 5% margin we specified. The licensee proposed that they will monitor the noises at about 40% of power for a reasonable time period of 1/2 hour to I hour and the operating margin they get will be increased by a maximu? of 50% to get the allowable margin at 50% power.
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The noise levels at Cooper during SLO may not be same as other BWRs, and it may. vary during different power and flow conditions. He believe the proposed method to determine the operating margir.s for the flux nosie and core plate delta noise during SLO give sufficient conservatism to satisfy our BF-1 corcerns hence is acceptable. The licensee may be informed accordingly.
MEinal Signed By Thee.s p,sp,j, Thenis P. Speis, Assistant Director for Reactor Safety, DSI cc:
B. Siegel D. Vassallo R. Clark C. Berlinger RSB Section Leaders RSB Section B Members G. Thomas Distribution Docket File RSB n/F RSB Plant File:
Cooper GThomas R/F TSpeis BSheron GThomas
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