ML20147C070

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Forwards Latest Schedule for C-E Sys 80+ Project 675 & Identification of Numbers to Be Used for Info Request.Many Reviewers of 870918 Amend 12,Chapter 1 Have Not Submitted Requests for Addl Info by 871215 Due Date
ML20147C070
Person / Time
Issue date: 01/11/1988
From: Vissing G
Office of Nuclear Reactor Regulation
To: Cheng C, Hum M, Marsh T
NRC
References
PROJECT-675A NUDOCS 8801190065
Download: ML20147C070 (9)


Text

January 11, 1987 NOTE FOR:

Distribution (See attached list)

FROM:

Guy S, Vissing, Project Manager Standardization and Non-Power Reactor Project Directorate Division of Reactor Projects III, IV, V and Special Projects, NRR

SUBJECT:

COMBUSTION ENGINEERING SYSTEM 80+ PROJECT N0. 675 Attached is the latest schedule of the subject project. Also attached is the identification of numbers to be used by the review branches for request for information.

You are reminded that we have received the following submittals that should be in your hands for review:

1.

9/18/87 Amendment 12, Chapter 1 2.

11/30/87 Amendment 12, Chapter 10, Steam and Pcwer Conversion System and Chapter 17, Quality Assurance You.are reminded that Requests for Addition Information for 1 above were due December 15, 1987. Many reviewers have not yet responded.

For those that have not provided RAIs, please indicate yot* intentions. Also those reviewers of 2 above are reminded that our schedule calls for RAIs for 2 above are due by February 28, 1988.

If you have any problems in receiving copies of the submittals please call ine at X28208.

5 "VissEjfNojectManager Standardizat'on and Non-Power Reactor Project Directorate Division of Reactor Project III, IV, V and Special Projects, NRR

Enclosures:

As stated

_ DISTRIBUTION:

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8801190065 880111 675 PDR

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January 11, 1988 NOTE FOR:

Distribution (See attached list)

FROM:

Guy S Vissing, Project Mattager Standardization and Non-Power Reactor Project Directorate Division of Reactor Projects III, IV, V and Special Projects, NRR

SUBJECT:

COMBUSTION ENGINEERING SYSTEM 80+ PROJECT NO. 675 Attached is the latest schedule of the subject project. Also attached is the identification of numbers to be used by the review branches for request for information. You are reminded that we have received the following submittals that should be in your hands for review:

1.

9/18/87 Amendment 12, Chapter 1 2.

11/30/87 Amendment 12, Chapter 10, Steam and Power Conversion System and Chapter 17, Quality Assurance You are reminded that Requests for Addition Information for 1 above were due December 15, 1987. Many reviewers have not yet responded. For '. hose that have not provided RAls, please indicate your intentions. Also those reviewers of 2 above are reminded that our schedule calls for RAIs for 2 above are due by February 28, 1988.

If you have any problems in receiving copies of the submittals please call me at X28208.

k S. Vissing, Pro t Manager Standardization an Non-Power Reactor Project Directorate Division of Reactor Project III, IV, Y and Special Projects, NRR

Enclosures:

As stated

DISTRIBUTION Tad Marsh James Knight Robert Erickson C. Y. Cheng John Craig Barry Mendelsohn Martin Hum Janak Raval Ed Butcher.

J. Rajan Jerry Wermiel Bob Giardina Horace shaw Wayn Hodges Arthur Beech Conrad McCracken Larry Kopp Jack Spraul Frank Witt Tim Collins Bill Regan G. Bagchi Dave ffathews George Lapinsky N. Romney Richard Yan Niel S. Wiess Dave Jeng Rich Barrett Joe Murphy Jerry Mauck Glen Kelly Harold Vandermolen James Stewart A. El-Bassoni E. Chelliah Faust Rosa L. Cunningham O. Chopra T. Essig

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Identification Numbers Used By NRR Branches for Review Questions Question ID Number Review Area Branch Applicable SRP Sections 100 miscellaneous Responsible Project Directorate This question number has been deleted.

110 systems 112 implementation This question number has been deleted.

210 mechanical engineering EMEB 3.2.1, 3.2.2, 3.6.2, 8TP MEB 3-1, 3.9.1, 3.9.2, 3.9.3, 3.9.4, 3.9.5, 3.9.6, 5.2.1.1, 5.2.1.2 i

220 structural engineering ESGB 3.3.1, 3.3.2, 3.4.2, 3.5.3, 3.7.1, 3.7.2, 3.7.3, 3.7.4, 3.8.1, 3.8.2, 3.8.3, 3.8.4, i

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230 seismology ESGB 2.5.E 231 geology-ESGB 2.5.1, 2.5.3 240 hydrologic engineering ESGB 2.4.1, 2.4.2, 2.4.3, 2.4.4, 2.4.5, 2.4.6, 2.4.7, 2.4.8, 2.4.9, 2.4.10, 2.4.11, 2.4.12, BTP HGEB-1, 2.4.13, 12.4.14 241 geotechnical engineering ESGB 2.5.4, 2.5.5 250 inservice inspection EMTB 5.2.4, 5.4.2.2, 6.6, 10.2.3 251 component integrity EMTB 3.5.1.3, 5.3.1, 5.3.2, BTP MTEB 5-2, 5.4.1.1, 6.2.7 252 materials application EMTB 4.5.1, 4.5.2, 5.2.3, BTP MTEB 5-7, 5.4.2.1, 6.1.1, 10.3.6 260 quality assurance LQAB 17.1, 17.2

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environmental SPLB 3.11 270 qualification P*

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271 seismic and dynamic EMEB 3.10 f

load qualification 280 fire protection CCEB 9.5.1, BTP CMEB 9.7.1 281 chemical technology ECEB BTP CMEB 5-3, 5.4.8, BTP MTEB 6-1, 6.1.2, i

9.3.2, 9.3.4. 9.5.1, BTP CMEB 9.5.1, 10.4.6, 10.4.8 290 environmental engineering Environmental Report 310 regional impact analysis m3GB Environmental Report 311 site analysis ESGB 2.1.1, 2.1.2, 2.1.3, l

2.2.1-2,2.2, 2.2.3 3.5.1.5, 3.5.1.6 1

320 antitrust and economic PTSB None analysis 410 auxiliary s,'tstems SPLB 3.4.1, 3.5.1.1, I

l 3.5.1.2, 3.5.1.4, 3.5.2, 3.6.1, BTP ASB 3-1, Q

5.2.5, 5.4.11, 6.7.

9.1.1, 9.1.2, 9.1.4, BTP i

ASB 9-1, 9.1.5, 9.2.1, j

9.2.2, 9.2.3, 9.2.4, j

9.2.5, BTP ASB 9-2, i

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SPLB/ECEB 9.1.3 420 instrumentetion and SICB 7.1, 7.2, 7.3, 7.4. 7.5, control systems 7.6, 7.7

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430 power systems SELB 8.1, 8.2, 8.3.1, 8.3.2, 9.5.3 SICB 9.5.2 SPLB 9.5.4, 9.5.5, 9.5.6, l

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440 reactor systems SRXB 5.2.2, BTP RSB 5-2, 5.4.6, 5.4.7, BTP RSB 5-1, 5.4.12, 6.3, BTP RSB 6-1, 15.1.1-15.1.4, 15.1.5, 15.2.1-15.2.5, 15.2.6, 15.2.7, 15.2.8, 15.3.1-15.3.2, 15.3.3-15.3.4, 15.4.4-15.4.5, 15.4.6, 15.5.1-15.5.2, 15.6.1, 15.6.5, 15.8 450

ccident evaluation SPLB 6.4, 6.5.2, 6.5.3, 6.5.4 PRPB App. A to 15.1.5, App. A to 15.4.8, App. A to 15.4.9 15.6.2, 15.6.3, 15.6.4, App. A to 15.6.5, App. B to 15.6.5, App. C to 15.6.5, App. D to 15.6.5, 15.7.4, 15.7.5 451 meteorology PRP8 2.3.1, 2.3.2, 2.3.3, 2.3.4, 2.3.5 O

460 effluent treatment SPLB 6.5.1, 10.4.2, 10.4.3, 11.1, 11.2, 11.3, 11.4, BTP ETSB 11-3, 15.7.3 PRPB BTP ETSB 11-5, 11.5 470 radiological impact PRPB Environmental Report 471 radiation protection PRPB 12.1, 12.2, 12.3-12.4, 12.5 480 containment systems SPLB 6.2.1, 6.2.1.1.A.

6.2.1.1.B. 6.2.1.1.C.

6.2.1.2, 6.2.1.3, 6.2.1.4, 6.2.1.5, BTP CSB 6-1, 6.2.2, 6.2.3, BTP CSB 6-3, 6.2.4, BTP CSB 6.4, 6.2.5, BTP CSB 6-2,6.2.6 490 fuels SRXB 4.2 491 physics SRXB 4.3, BTP CPB 4.3-1, 15.4.1, 15.4.2, 15.4.3, 15.4.7, 15.4.8, 15.4.9

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492 thermal-hydraulics SRXB 4.4 0

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610 operator licensing LHFB 13.2.1 620 human factors LHFB 18, 18.1, 18.2 engineering 630 licensee qualifications LPEB 13.1.1, 13.1.2-13.1.3, 13.4, 13.5.1 LHFB 13.2.2 640 procedures ar.d systems LHFB 13.5.2, 14.2 review 720 reliability and risk PRPB Kane assessment 730 generic issues None 760 Clinch River Breeder This question number has been deleted.

Reactor 810 emergency planning PEPB 13.3 910 safeguards RSGB 13.6

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Abbreviations ECEB Chemical Engineering Branch EMEB Mechanical Engineering Branch EMTB Materials Engineering Branch ESGB Structural and Geosciences Branch LHFB Human Factors Assesswent Branch LPEB Performance Evaluation Branch LQAB Quality Assurance Branch PEPB Emergency Preparedness Branch PRPB Radiation Protection Branch PTSB Policy Development and Technical Support Branch O

RSGB Safeguards Branch SELB Electrical Systems Branch SICB Instrumentation and Control Systems Branch SPLB Plant Systems Branch SRXB Reactor Systems Branch 4

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