ML20039F093

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Forwards Amend 16 to B-SAR-205.Includes Stagnation Pressure & Stagnation Enthalpy Bases Used in Computing Discharge Flows,Pressurizer Surge Line Base Data & Revised Section 3.11.W/o Amend
ML20039F093
Person / Time
Site: 05000561
Issue date: 06/28/1977
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 8201110846
Download: ML20039F093 (4)


Text

,

f Babcock &Wilcox

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P.o. Box 1260. Lynchburg. Va. 24505 Telephone: (804) 384-5111 June 28, 1977 DOCKET STN 50-561 Office of Nuclear Reactor Regulation ATTN:

Mr. Roger S.

Boyd, Director Division of Project Management U. S. Nuclear Regulatory Commission Washington, D.C.

20555

Subject:

B-SAR-205 Transmittal of Amendment 16

References:

(1) J. H. Taylor to R. S. Boyd, "B-SAR-205 -

l Revised B6W Positions," June 3, 1977 (2) J. H. Taylor to R. S.

Boyd, "B-SAR-205 -

Revised B6W Position," June 4, 1977

Dear Mr. Boyd:

The Babcock 6 Wilcox Company het?with submits sixty copies of B-SAR-205 Amendment 16 for review.

This amendment includes the following specific items:

(1) In compliance with a request by the Staff, Table 6.2-32 has been revised to show mass and energy discharge rates from each side of the break and to include break areas.

The values shown for the postulated break in the core flood line have also been corrected to account for the presence of the 9-inch no::le at the reactor vessel.

Additional modifications to Table 6.2-32 in this amendment are:

1) the stagnation pressure and stagnation enthalpy bases used in computing discharge flows have been specified, 2) data has been added for a pressurizer surge line break in the 14-inch schedule 160 piping, 3) the discharge from the pressurizer side for the spray line break is based upon saturated vapor fluid prop-perties instead of saturated liquid, and 4) the stagnation pressure within the pressurizer has been corrected to 2219.4 psi from 2232.2 psi 8201110846 810403 e9 nd ape 1867 D

-515 PDR

Babcock &Wdcox Mr. Roger S. Soyd Page 2 June 28, 1977 (2) Section 3.11 has been revised to clarify the B6W position with regard to environmental temperature qualification of safety-related instrumentation and control equipment.

As requested by the Staff, this revision includes reference to specific environmental temperature profiles as a basis for qualification.

Section 3.11.6 has also been revised to include appropriate interfaces.

(3) In compliance with a request by the Staff, Section 15.1.4, which discusses postulated moderator dilution accidents, has been revised to include in the discussion the line which bypasses the makeup tank and to clarify the basis for final termination of the deboration.

Specifically, operator action for termination of both cases (full-power and refueling) has been addressed and also included in the operating sequence diagram (Figure 15C.4).

Informa-tion h:n; been added to show that ample time is available for the operator to perform this function.

l In addition, with regard to the revisions made to Section 15.1.4, the responses to NRC requests 212.178 and 212.181 have been modified for consistency.

Table 6.3-7 has also been modified to clarify footnote (b) and to add an additional footnote (c), which identifies valves which are locked closed during refueling.

(4) As committed in Reference (1), the revised B6W positions concerning fracture toughness testing requirements and classification of certain CA 6 BR system components, as described in the attachment to Reference (1) are being formally included in the B-SAR-205 with this amendment.

(5) As committed in Reference (2), the revised B6W position with regard to methods to be used for determining delta ferrite levels in austenitic stainless steel welds, as described in the attachment to Reference (2), is being formally included in the B-SAR-205 with this amendment.

1 (6) In accordance with a suggestion by the Staff, Tables 9.3-2, 9.3-5 and 9.3-8 have been clarified to note that where more than one component of a given type is specified, the data provided is for a single unit.

(7) Tabic 3.9-7, which describes design ?ressure limits for Category 1 ASME Section III valves, nas been revised to l

show correct subscripts, i

' Babuck&MScox Mr. Roger S. Boyd Page 3 June 28, 1977 An additional B-SAR-205 binder is also being distributed-with this amendment.

Instructions for filing B-SAR material in this additional binder are included with the instructions for filing this amendment.

Ve truly yours, g

  1. L es H.

ylor anager, Licensing JHT:dsf Enclosures cc:

R. B. Borsum (B6W)(2)

U.

S. Nuclear Regulatory Commission (1)

Office of Inspection and Enforecsent - Region IV 611 Ryan Plaza Drive - Stuie 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

I I

Babcock &Wilcox J

STATE OF VIRGINIA)

)

SS. Lynchburg CITY OF LYNCHBURG)

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

That he is the Manager of the Licensing Section of the Nuclear Power Generation Division, THE BABCOCK 6 WILCOX COMPANY, the applicant herein; that he is authorized to submit the 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.

Dated:

M l9)

U

  1. se W $ Un

[

James'li. Taygo'r Subscribed and sworn to before me, t his s-,.,f' day o f June, 1977.

1m < h r f j Ji n -(

l Notary Public in and for the State of Virginia, City of Lynchburg My Commission expires

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