ML19312C790
| ML19312C790 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 04/17/1967 |
| From: | Grimes B US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Boyd R US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 7912191008 | |
| Download: ML19312C790 (3) | |
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SUPPLEMENTAL
.o att enoV UNITED STATES GOVERNMENT FILI. UUri Memorandum AES 1I lbb7 To Roger S. Boyd, A/D-RPB, DRL DATE:
THRU: Charles G. Iong, Chief Reactor Project Branch No. 3, DRL FROM B. Grimes, Reactor Project Branch No. 3 Division or Reactor Licensing
SUBJECT:
DUKE PCWER CCMPANY MEETDiG APRIL 4,1967 - DOCKET NCS. 50-269/270 On April 4, 1967, a brief meeting between representatives of Duke Power Company and the regulatory staff was held to discuss revisions to the safeguards report and partial ansvers to cur questions dated March 23 which were received the same day. The engineered safeguaztis have been entirely revised, with separation of the safeguards now proposed rather than sharing between units. Core flooding tanks (accumulators) are also proposed.
" Master" copies of the other replacement pages were also sub-mitted informally with the revisions underlined. These are available for reference when inserting replacement pages. The replacement pages should be inserted beform errata rM nges are made. A list of the sub-jects covered in the replaced pages is attached.
Our future schedule was discussed in light of the Duke's estimate that the remainder of the questions would be answered about April 19 We indi-cated that a meeting April 27 or 28 vould be desirable to discuss the answers and to orally indicate which areas would be covered in a second question list. A site visit was tentatively scheduled for early May.
(Cn the basis of recent conversations with the ACRS, a tentative date of May 2 has been set.)
Several technical areas of interest to us were indicated to the applicant, including:
(t) the need to speak to the points in the ACES letter on TVA, (2) snalysis et the earthen dams, (3) isolation valves en the secondary system and (h) engineered safeguartis systems. These vill be discussed at the April 27 or 28 meeting.
Duke indicated that an attempt would be made to justify the ommission of secondary system isclation valves and noted that this was the first PWR with a G. E. turbine.
(Westinghouse turbines require a cross-connection between steam lines before the stop valves whereas the G. E. cross-connee-tion is after the stop valves.)
e Buy U.S. Savings Bonds Regularly on the Payroll Savings Plan 79'1219100 8
R I 7 G67 2-Roger s. Boyd Duke also indicated that the scram on low pressure coincident with low pressurizer level was being changed to a scram on~ low pressure only.
Attachment:
As stated above Distribution:
Suppl. f y-DRL Reading RPB #3 Reading P. A. Morris D. J. Skovholt S. Levine D. R. Muller R. L. Tedesco C. G. Icug R. E. Ireland R. C. DeYcung M. Rosen V. A. Moore J. F. Newell N. Davison J. Hard F. Kelly B. Grimes n
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m DUKE POWER COMPANY AMENDMENT NO. 1 1
DOCKET NOS. 50-269/270 The replacement pages in Amendment No. 1 resulted from the following system and instrumentation changes:
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SYSTEMS miminated shared engineered safeguards equipment Revision to Reactor Building sump piping Increase in borated water storage tank capacity New Icop volume end Bingham pumps Reactor Buildin6 sump pump Component drain pump -
Core flooding tanks Reactor Building coolers to tube type and on low pressure service water Reduced component cooling pumps 3 to 2 Deleted Reactor Building spray coolers Revised isolation valves Relocated decay heat line to reactor outlet line Chan6ed core flooding nozzle to discharge into bottom of reactor vessel INSTRUME!iTATION Engineered safeguards protective system from energized to de-energized Control rod drive bus Nuclear instrumentation Pressurizer low level scram eliminated l
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