ML19337A818
| ML19337A818 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 09/09/1980 |
| From: | Counsil W NORTHEAST UTILITIES |
| To: | Crutchfield D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19337A819 | List: |
| References | |
| NUDOCS 8009300297 | |
| Download: ML19337A818 (5) | |
Text
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NORTHEAST UTIEJTIES 1
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e September 9, 1980 Docket No. 50-245 B10067 Director of Nuclear Reactor Regulation Attn:
Mr. Dennis M..Crutchfield, Chief Operating Reactors Branch #5 U. S. Nuclear Regulatory Commission Washington, D.C.
20555 Gentlemen:
Millstone Nuclear Power Station, Unit No.1 Provisional Operating License No. DPR-21 Reload #7 License Amendment Submittal Pursuant to 10CFR50.90, the holders of Provisional Operating License, DPR-21, hereby propose a change in the next refueled core as described in Attachment 1,
" Reload 7, Supplemental Reload Licensing Submittal", Y1003J01A09, June, 1980.
The new reload fuel consists of 128 General Electric P8DRB282 bundles and 40 General Electric P8DRB26511 bundles which are described in the "GE/BWR Generic Reload Fuel Application", NEDE-240ll-P-A-1, July, 1979.
All 168 new bundles will have drilled lower tie plates and finger springs to regulate bypass flow.
A reanalysis of the plant LOCA is provided in Attachment 2, " Loss of Coolant Accident Analysis Report", NEDO-24085-1, July,1980, to demonstrate conformance with the ECCS acceptance criteria of 10CFR50.46. contains proposed Technical Specification changes for this refueling, along with the technical descriptions and bases for such changes.
The off-site Nuclear Review Board has reviewed and approved these proposed changes, which have been found to not constitute any unreviewed safety questions pursuant to 10CFR50.59. The changes would constitute a license amendment which we have assessed pursuant to 10CFR170, with the conclusion that they would constitute a Class IV type of amendment. Accordingly, enclosed herewith is the appropriate fee payment in the amount of $12,300 (twelve thousand three hundred dollars). We wish to point out that there are several more Technical Specification changes that are necessary for this refueling outage, but are not included in Attachment 3.
These additional 1
changes will be submitted under a separate transmittal letter, as a supplement 80093009. g
e to this license amendment application, and are, therefore, covered by the enclosed Class IV amendment fee.
l The additional changes include, as a minimum, the following subjects and are planned for submittal by September 30, 1980.
(1) Containment Integrated Leak Rate.
(2) Spiral Pattern for Complete Core Off-Loading.
(3) Bases for Standby Liquid Control Suberitical Requirement.
Also included as part of this license amendment application is NEDE-20592-5P, "STR Bundle Submittal, Millstone-1 Segmented Test Rod Bundle, Supplement 5",
June, 1980. This document updates the original report which was submitted October 3, 1974, as part of the Reload 2 license amendment submittal, and which was also updated for Reloads 3, 4, 5, and 6.
The report describes proposed changes to be made to the test bundle composition during the upcoming outage. We have been informed by the General Electric Company that this report is considered proprietary by them, and as such, it is being forwarded under separate cover.
The present refueling outage schedule calls for plant shutdown on October 4, 1980, with an anticipated ten-week outage duration. Thus, we request that the enclosed proposed Technical Specification changes be approved no later than December 4, 1980.
Should you have any questions, please contact us as soon as possible.
Very truly yours, NORTHEASTNUCLEARENERGYJ0MPANY
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W.' ti. Counsil I
Senior Vice President Attachments
STATE OF CONNFCTICUT )
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Berlin COUNTY OF HARTFORD
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Then personally appeared before me W. G. Counsil, who being duly sworn, did state that he is Senior Vice President of Northeast Nucl' ear Energy Company, a Licensee herein, that he is authorized to execute and file the foregoing information in the name and on behalf of the Licensees herein and that the statements contained in said information are true and correct to the best of his knowledge and belief.
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PROPOSED TECHNICAL SPECIFICATION CHANGES FOR MILLSTONE UNIT NO. 1. RELOAD 7, TABLE OF CONTEtiTS_
Description of Changes and Proposed Technical Specification Safety Evaluation Summary Pages Affected' l.
MAPLHGR Limits 3/4 11-1 through 3/4 11-7b, B 3/4 11-1 2.
New Multiplier for APRM l-3, Rod Block Monitor Setting 2-3 through 2-6, B 2-2 B 2-6, B 2-7 3.
Acoustic Monitoring for 3/4 6-5, Safety / Relief Valves 3/4 6-6, B 3/4 6-4 4.
MCPR Limita 3/4 11-10 5.
Four ADS Valves 3/4 5-7 B 3/4 5-3 6.
Jet Pump Baseline Data 3/4 6-10 1
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Primary Containment Isolation Valves 3/4 7-15 1
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Reactor Protection System Response Time 3/4 1-1 l
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Surveillance Testing of 3/4 4-2, ECCS and SLC Equipment 3/4 5-1 through 3/4 5-7, 3/4 5-8, 3/4 5-9, 3/4 13-1, B 3/4 4-1, B 3/4 5-1 through B 3/4 5-3, B 3/4 5-6 10.
3/4 3-5 11.
Test and Calibration 3/4 2-6, Frequency for Core Cooling -
3/4 2-7 Instrumentation
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.2 - Description of Changes and Proposed Technical Specification Safety Evaluation Summary Pages Affected 12.
Personnel Air-Lock Door 3/4 7-8, Leak Test B 3/4 7-9
'13 Rod Worth Minimizer Diagnostic Test 3/4 3 14.
Housekeeping Changes B 2-8, 3/4 2-2, 3/4 2-4, 3/4 2-8, i
3/4 3-2, 3/4 3-3, 3/4 3-4, 3/4 6-10, 3/4 7-14, 3/4 7-15, 3/4 7-17, 3/4 9-2, 3/4 9-3, 3/4 11-1, 3/4 12-4, B 3/4 1-2, B 3/4 1-8, B 3/4 2-2, B 3/4 3-1, B 3/4 4-1, B 3/4 5-4, B 3/4 6-4, B 3/4 7-3, B 3/4 7-8, B 3/4 7-9, B 3/4 7-10, B 3/4 9-1, 5-1 L
> DOCKET No. 50-245 ATTACHMENT 1
" SUPPLEMENTAL RELOAD LICENSING SUBMITTAL FOR MILLSTONE UNIT 1, RELOAD 7,"
Y1003J01A09, JUNE, 1980
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l SEPTEMBER, 1980