ML20039F079
| ML20039F079 | |
| Person / Time | |
|---|---|
| Site: | 05000561 |
| Issue date: | 08/31/1977 |
| From: | Taylor J BABCOCK & WILCOX CO. |
| To: | Boyd R Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML111090060 | List:
|
| References | |
| FOIA-80-515, FOIA-80-555 NUDOCS 8201110828 | |
| Download: ML20039F079 (6) | |
Text
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s Babcock &Wilcox go..,ceee,.i.oocroup P.O. Box 1260, Lynchburg. Va. 24503 Telephone: (804) 384-5111 August 31, 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 17
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 6 Wilcox Company Reference Safety Analysis Report, B - S AR-2 0 5,
Docket No. STN 50-561, July 9, 1977.
2)
J. H. Taylor to R. S. Boyd, "B-SAR-205 -
Outstanding Issues," July 15, 1977.
3)
J. H. Taylor to R. S. Boyd, "B-SAR-205 -
Outstanding Issues," July 21, 1977.
4)
J. H. Taylor to R. S. Boyd, "B-SAR-205 -
Outstanding Issues," August 4, 1977 5)
J. H. Taylor to R. S. Boyd, "B-SAR 205 -
Outstanding Issues," August 8, 1977.
Dear Mr. Boyd:
The Babcock 6 Wilcox Company herewith submits sixty copies of B-SAR-205 Amendment 17 for review.
This amendment is being submitted to formally include certain information in the B-SAR-205 in accordance with commitments in references (2) through (5), above.
Specifically, this amendment includes additional information concerning the following open items (Note: item numbers listed below are identical to those used in Table 1.6 of reference (1)):
Item (2) - Environmental Qualification Program In accordance with an informal request by the Staff and the B6W commitment made in reference (4) above, Section 3.11 of the B-SAR has been amended to provide information concerning the conservatism inherent in B-SAR figure 3.11-2.
'he Babcock & W4cox Company / Estachshed 1867 NADDEN80-515 PDR
BabeczksNWkox Mr. Roger S. Boyd Page 2 August 31, 1977 Item (3) - High Pressure Injection Line Break As committed by B4W in reference (5) above, table 6.3-4b has been included with this amendment to summarize flow alarm states associated with postulated high pressure injection line breaks.
Figure 6.3-7a has also been corrected to show check valves MU-MV131A, B, C and D which were inadvertently omitted during an earlier revision, and the HPI flow indicator range in Table 7.5-1 has been corrected to 0-500 gpm Section 6.3.2.17.2 has also been amended to describe mitigating o erator action required and the time period available for suc action.
Item (4) - Boron Dilution Event In accordance with a request made by the Staff at a meeting held on August 3, 1977, additional clarification has been added to Section 15.1.4 concerning the status of the makeup and purification system during refueling and maintenance operations.
Overpressure Protection Item (6)
In accordance with the B6W commitment in reference (5),
Section 5.2.2.4 and figure 5.2-3 have been added to describe the methods for providing assurance that overgressure limits as defined by Appendix G to 10CFR50 will not 3e exceeded.
B-SAR section 5.7.17 has also been amended to include additional interfaces relating to this subject.
In addition, Section 9.3.6.3 has been expanded to include a discussion of inadvertent starting of a reactor coolant pump during plant startup and also to clarify the case of accidently opening a core flood tank outlet valve during plant startup.
In keeping with the above, Section 15.1.24 and the responses to NRC requests 212.169 and 212.229 have been revised to be consistent.
Item (7) - Provisions for Shutdown In accordance with the commitments made in references (3) and (4) above, Section 10.5.9 of the B-SAR has been revised to include an interface requirement for auxiliary feedwater supply and the response to NRC request 212.223 has been revised to confirm that all systems and equipment required to achieve and maintain a safe hot shutdown are safety grade and can perform their function with loss of offsite power.
In addition, to reduce the probability that a loss of motive power could cause an increase in cooldown rate during operation of the decay heat removal system, by-pass valves DR-V14A and DH-V14B t
Babcock &Wilcox Mr. Roger S. Boyd Page 3 August 31, 1977 shown on figure 9.3-5 have been revised from pneumatic operators to electric motor operators with a " fail in position" feature.
DHRS Isolation Item (8)
To resolve this oaen issue, Sections 8.3.2 and 8.3.1.2 and figure 8.3-1 of t1e B-SAR are being revised in this amendment to require independent IE power supplies to each of the four decay heat removal system (DHRS) suction isolation valves (DH-VilA, V11B, V12A and B12B in figure 9.3-5).
The four recommended separate power supplies are nuclear service busses A and B and IE battery busses A and B via 480 VAC, 3 6 inverters.
In addition, by-pass check valves MV 35A and B and MV 36A and B have been added around DHRS suction isolation valves DH-V12A and DH-V12B in figure 9.3-5.
The addition of these check valves will prevent large pressure differences across these DHRS suction isolation valves and permit their operation using lower power electric motor operators.
Table 8.3-1 has been revised to reflect the change in valve motor power requirements.
Item (9) - Emergency Core Cooling System As committed in reference (2), a schedule for submittal of additional analysis results to the NRC Staff has been included in Section 6.3.1.1.
Item (10) - FMEA for the Engineered Safety Features Actuation System The commitment stated in reference (2) concerning the program plan to be followed in performing this failure modes and effects analysis for the ESFAS has been included in Section 7.3.2.9.
Item (11) - Compliance With IEEE 323-1974 for Makeup pump and Decay Heat Motors As discussed in reference (5), Section 3.9.2.4.3(6) has been revised to state that the subject motors will be qualified l
according to IEEE 323-1974 and that the qualification program l
will be described in generic documentation to be provided prior to application for final design approval for the B-SAR-205, l
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'9abcock&Wilcox Mr. Roger S. Boyd Page 4 August 31, 1977 Item (12) - Anticipated Transients As committed in reference (5), a footnote has been added to Table 15.1-4 to confirm that turbine by-pass is used as part of its normal role, that turbine by-pass is not a required function, and that adequate steam relief capacity is available without turbine by-pass action.
Item (13) - Turbine Trip Analysis As committed in reference (4), Section 15.1.7.2.4 has been revised to include a discussion of this analysis and figure 15.1.7-3 has been included to show the variation of power, temperature and steam pressure as a function of time during the transient.
The following additional changes have also been made in this amendment:
(1)
Table 1.6-1 and Section 17.0 have been updated to indicate the latest revision of Topical Report BAW-10096-A.
(2)
Interface sub-item 5 in Section 6.3.6, gart 2 requiring that the BWST be designed for a design basis tornado has been deleted.
Interface requirements for the BWST are limited to those listed in Section 9.3.6.6.18.
(3)
At the request of the Staff, Table 15.1-1 has been updated to cover all accidents discussed in Chapter 15.
(4)
Section 6A.S.3 in Appendix 6A has been expanded to discuss the e f fects of minimum and maximum ECCS assumptions on mass and energy release rates.
In addition, a new section 6A.S.4 has been added to discuss the use of mass and energy release rates by the applicant.
V ruly yours, f
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%&x& k jp,IL James H. Taylor e
Manager, Licensing)
JHT:dsf Enclosures
1 Babcock &Wilcox Mr. Roger S. Boyd Page 5 August 31, 1977 cc:
R. B. Borsum (B4W)(2)
U. S. Nuclear Regulatory Commission (1)
Office of Inspection and Enforcement - 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 i
401 M Street, S.W.
Washington, D.C.
20460 Mr. A. J. Oswald (1)
EGGG Idaho, Inc.
P. O. Box 1625 Idaho Falls, Idaho 83401 l
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~ 9abcock&Wilcox STATE OF VIRGINIA)
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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 4 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.
)9,/Yl6 Dated:
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JamesH.Tay1d Subscribgd and sworn to before me, this 49 day of August, 1977.
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NodryPublicinandfortheState of Virginia, City of Lynchburg My Commission expires _ /d,[/6/Jf
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