ML20039F075

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Forwards Amend 18 to B-SAR-205,in Response to NRC 770830 Questions.Amend Clarifies hot-shutdown Requirements for Auxiliary Feedwater Sources & Provides Info Re Burnable Poison Rod Assemblies
ML20039F075
Person / Time
Site: 05000561
Issue date: 09/26/1977
From: Taylor J
BABCOCK & WILCOX CO.
To: Boyd R
Office of Nuclear Reactor Regulation
Shared Package
ML111090060 List: ... further results
References
FOIA-80-515, FOIA-80-555 NUDOCS 8201110820
Download: ML20039F075 (6)


Text

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Babcock &Wilcox Power Gecerat:en Group P.o. Box 1260. Lyncnourg, Va. 24505 Teleenone: (80.t) 384-5111 September 26, 1977 g E' 4',

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DOCKET STN 50-561 0 ~ %/ Ij A T.

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Office of Nuclear Reactor Regulation Division of Project Management

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Mr., Roger S. Boyd, Director N #'*4 U.S. Nuclear Regulatory Commission

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Subject:

B-SAR-205 Transmittal of Amendment 18

References:

1)

Report to the Advisory Committee on Reactor Safeguards by the Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, in the matter of Babcock 5 Wilcox Company l

Reference Safety Analysis Report, B-SAR-205, l

Docket No. STN 50-561, July 9,1977 1

2)

Olan D. Parr to J. H. Taylor, "B-SAR-205 Outstanding Issues," August 30, 1977

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Dear Mr. Boyd:

The Babcock 5 Wilcox Company herewith submits sixty copies of B-SAR-205 Amendment 18 for review.

This amendment is being submitted to provide responses to

.NRC questions 212.236 through 212.240 which were transmitted to B5W with Reference 2, and to provide certain other information as follows:

(1)

As requested by the Staff, Section 10.5 9.1 has been revised to clarify the hot-shutdown requiremehts for auxiliary feedwater sources.

(2)

As requested by the Staff, Table 1.3-1 has been expanded to include information concerning Burnable Poison Rod Assemblies (BPRA's).

Poison length and cladding thickness of Control Rod Assemblies (CRA's) has also been corrected in this table.

(3)

Figure 6.3.7a has been modified to delete connections from the sump lines to the containment spray pumps, since spray system interfaces are not required to support the NSSS function and will be described in the Applicant's SAR.

In addition, valves DHV14A and 14B have been changed from pneumatic to EMO consistent with our response to open 7

8201110920 810403 PDR FOIA The Baececk & waccx corncany / Estachshed 1867 MADDEN 80-515 PDR

ibcock&Wilcox Mr. Roger S. Boyd Page 2 September 26, 1977 item number (7) (question number 212.223) submitted in Amendment 17, and check valves MU-V131A, B, C and D in the HPI injection lines, which were inadvertently omitted in earlier amendments, have been included.

To be con-sistent, these changes have also been made to related figures 6.3-7b and 6.3-7c.

(4)

Figure 6.3-7 is redundant to figures 6.3-7a, b and c and is being deleted with this amendment.

(5)

As requested by an AE with whom we are working, Section 6.2.1.2.1 has been expanded to provide additional subcompartment mass and energy release data tables for 2.5 ft breaks.

(6)

The response to NRC request 122.9 has been revised.

The purpose of the revision is to allow B6W greater flexibility in applying the ASME Code based upon recommendations established by the Joint Task Group for Delta Ferrite Testing.

(7)

Figure 10.1-1 has been revised to include changes as listed in the attachment to this letter.

The only safety related change is the revision to the arrangement of the check valves in the main feedwater lines.

The revised I

check valve arrangement shown in this amendment limits the maximum break size to the value used in the analysis of a feedwater line break as discussed in Section 15.1.8 of the B-SAR.

Consistent with this change, Section 10.5.5.2(2) item c has also been revised to further clarify the basis used for the feedwater line break analysis.

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. Ve truly y.ours, N

James H. Taylor Manager, Licensi g JHT:dsf Attachments s

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ATTACHMENT D

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CHANGES TO BSAR FIGURE 10.1-1, SHEET 2 CHANGE REASON FOR CHANGE Change 7 ' main FP! lines to 24",

These changes in typical line size change 6' S/V FW lines to 8".

reflect current A/E design philosophy on B6W 205FA plants.

Change the location of the main This change is necessary to limit FW check valves from the common the maximum possible feed water 24" line to one check valve in line break to a size that is each 14" line feeding the-IE0TSG.

compatible with safety analysis performed for this accident.

By putting the check valves in the IE0TSG noz 1c feeder lines, the maximum break size is limited to the nozzle size (18" I. D. )

assumed in the feedwater line break analysis.

Add 2" bypass valve around MV4A These bypass valves will allow 2nd MV4C.

the applicant the option of warm-ing up part of the main feedwater lines.

During plant startup by biceding hot water back from the IEOTSG.

Add position switches These ' witches are shown on other s

6A6B and 14A6B to the modulating valves in this system and were atmosphere dump valves and main inadvertently omitted on these feed control valves.

four valves.

Delete redundant ESFAS signals to Only one signal is supplied to main steam isolation valves.

each valve.

Show ESFAS signals to customer This is being included to provide turbine protection system.

visual representation of para-graph 10.5.7.3 of the BSAR.

Delete 4" carbon steel drain These lines are only necessary if lines from main steam lines to a solid water heatup of the drain system.

secondary side of the IEOTSG is used.

The standard approach is tc use a vacuum heatup method.

Thess drain lines are therefore superfluous.

'}Combineandgeneralizenotes This revision is made to allow 8 and 9.

greater flexibility to applicants.

1 ibcock&Wilcox Mr. Roger S. Boyd Page 3 September 26, 1977 cc:

R. B. Borsum (B4W)(2) 4 U.S. Nuclear Regulatory Commission (1)

Office of Inspection and Enforcemen.t - Region IV 611 Ryan Plaza Drive - Suite 1000 Arlington, Texas 76012 Mr. Neil Thomasson (3)

Attn:

Loretta Long Office of Radiation Programs Environmental Protection Agency Room 647A East Tower Waterside Mall 401 M Street, S.W.

Washington, D.C.

20460 Mr. A. J. Oswald (1)

EG6G Idaho, Inc.

P. O. Box 1625 Idaho Falls, Idaho 83401 1

ibco(.k&Wilcox t

STATE OF VIRGINIA)

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SS. Lynchburg CITY OF LYNCHBURG)

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James H. Taylor, being first duly s sorn, deposes, and says:

That he is the Manager of the Licensing Section of the Nuclear Power Generation Division, THE BABCOCK 4 WILCOX COMPANY, the applicant herein; that he is authorized to submit tne foregoing on behalf of said applicant; that he has read the foregoing and knows the contents hereof; and believes the same to be true to the best of his knowledge.

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h o.A Dated: t-./.C # [6 /f/#

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James H. Tay Subscribed and sworn to before me, this 404 day of September, 1977.

atY) J Nd Notdry Public in and for the State of Virginia, City of Lynchburg My Commission expires

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QATE CP CCCUMENT FRCM: Babcock C Wilcox R S Boyd 9-26-77

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Lynchburg, va CATE *ECEIVED l

J H Taylor 10-4-77 i

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ItCMcQINAL QMC(Agglpi g g 3 S I/,eJ G O Cc Pv OEsCmtPTION ENCLOSu ME I

j notarized 9-?6-77....trans the following:

Amdt #18 to BSAR-205: Consisting of revised I

& addl pgs, tables, figs & miscellaneous text revisions in response to NRC staff questions........ 1/2 inch

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