ML20039G964
| ML20039G964 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood  |
| Issue date: | 12/30/1981 |
| From: | Tramm T COMMONWEALTH EDISON CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8201190354 | |
| Download: ML20039G964 (7) | |
Text
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C:mm:nw:dth Edis n y\\ew is one First National Plaza. Chicago. Ilknois s'
Address Reply to. Post Of5ce Box 767 Cnicago. !!hnois 60690 b
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iG December 30, 1981 Mr. Harold R.
Denton, Director Of fice o f Nuclear Reactor Regulation U.S. Nuclea r Regulatory Commission Washington, DC 20555
Subject:
Byron Station Units 1 and 2 Braidwood Station Units 1 and 2 Additional FSAR Information NRC Docket Nos. 50-454/455 and 50-456/457 Dea r Mr. Denton:
This is to provide information relative to anan items in the NRC sta f f's review o f the Byron /Braidwood FSAR.
Attachment A to this letter contains information requested by the Ef fluent Treatment Systems Branch.
Attachment B lists the responses to Procedures and Test Review Branch questions regarding the Initial Test Program.
These responses will be incorporated into the FSAR the next amendment.
One (1) signeo original and fif ty-nine (59) copies o f t his letter and the attachments are provided fo r you r review and approval.
Please address questions to this o f fice.
Very truly yours, d,I44-T. R.
Tramm Nuclear Licensing Administrator Pressurized Water Reactors Attachment 3126N hl g,a # E g$ A s
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Attachment A Ef fluent Treatment Sys* cm Branch Response to Open Items No.
SER Section 5psponse 1.
6.5.1.2 Calculations have been provided to Jack Hayes to justify an iodine efficiency rate of 90% for the fuel handling building charcoal filter.
Calculations to justify a 90% filter efficiency rate for the nonaccessible areas will available by Janua ry 7, 1982.
2.
10.4.2.2 The MCES meets the guidelines of
" Standards for Steam Surface Condensers".
An FSAR change will be made to indicate such.
3.
11.3.2 Inplace testing of filter systems will be performed in accordance witq ANSI N510-1980..The Technical Specifiest. ions will be revised to indicate periodicity l
and testing requirements.
Based on our experience at the Zion i
l Station we feel confident that the purge exhaust system will be adequately tested.
4.
11.3.2 The waste gas system is a typical Westinghouse design.
Westinghouse is prepared to defend this l
design.
We will schedule a l
meeting with staf f at a future j
date.
Acceptance Criterion II.3 o f SRP 11.3 is met in the waste gas sytem in that pressure relieving devices are safety valves not rupture discs.
These t/pically relieve back to the system rather than to the atmosphere.
Hence no special precautions for leakage paths (i.e. water seals on rupture discs) are required.
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No.
SER Section
Response
j 5.
11.5.2 We are attempting to find out from the vendor whether the design of i
monitoring insturmentation is in accordance with ANSI N13.10-1974.
We expect a response by January 7, 1982.
6.
11.1.2 The schedule for providing the 11.4.2 information concerning the Volume 11.5.2 Reduction System and the polymer binding system will be provided during the week of January 4, 1982.
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I Attachment B Initial Test Program Cuestions Resoonses Enclosed 423.22 423.32 423.23 423.34 423.25 423.35 423.27 423.36 423.28 423.38 423.29 423.39 423.31 423.40 423.32 423.41 423.43 e
1
Q423.22 "On-Site Review Group" 1
Response
1.
FSAR Subsection 14.2.2 will be revised to correct the reference to Chapter 17.
i
-i 2.
FSAR Subsection 14.2.2 will be revised to include the following information:
1 The Assistant Superintendent, Administrative and i
Support Services is appointed as the senior j
participant of the On-Site Review Group.
Other Assistant Superintendents are appointed as alternates on a case basis.
The senior participant will choose participants for a particular review j
Trom designated individuals qualified in the disciplines listed in Technical Specification l
6.1.G.l.f.
l Q423.23
" Initial Test Program"
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Response
FSAR Subsection 14.1 will be revised to incorporate j
the following:
1.
The entire test program will be described to include 1
both preoperational and startup tests.
2.
The response to item 423.6 will be included in the text.
t 3.
Unsuccessful results will~be recorded to permit post j
test review and resolution.
i 4.
Later.
l Q423.25 "Preoperational/Startup Testing" a
j
Response
1.
All preoperational tests will be completed,
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evaluated and approved prior to core load.
FSAR subsections 14.2.5 and 14.2.11 will be revised to l
include these commitments.
2.
All startup test data obtained at sach power test plateau will be evaluated and approved before i
increasing power level.
FSAR subsections 14.2.5 and l
14.2.11 will be revised to include these commitments.
4 Q423.27 "Oilution o f Staf f" l
Response
FSAR Subsection 14.2.11 will be revised to state that 1
any initial test schedule overlap at the Byron and i
Braidwood Station will not result in significant t
divisions of responsibility or dilution; in the staf f
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provided to implement the test programs.
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Q423.28
" Test Procedure Availability"
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Response
FSAR Subsection 14.2.11 will be revised to state that i
preoperational test procedure drafts will be_available-j for review by I&E inspectors at least 60 days prior to f
their intended use and not less than 60 days to i
scheduled fuel loading date for startup test procedure d ra f t s.
Q423.29
" Unit 1 - Unit 2 Test Program" l
Response
Essentially an identical test program will be conducted i
for each unit.
Initial tests conducted on common j
systems or startup tests conducted to prove acceptance of a prototype core will be completed to the extent d
necessary to support Byron Unit 1 operation.
Operational components in common systems will not be retested in the Unit 2 test program, i'
Q423.31
" Test Abstracts" l
Response
Prerequisites that identify the major components or i
system status necessary to conduct a gi.ven test are included in the test draft procedures mace available 60 j
days prior to intended use for preoperational test and j
60 days pri6r to core load for startup test.
1 Q423.34
" Valve Fall Position" l
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Response
The containment isolation valves for the compressed air j
systems, the power operated main steam relief valves and i
auxiliary feedwater control valves will be tested to insure they fail to their designed safe position on loss of air.
Q423.35
" Snubber Operability"
Response
Following system operation during Integrated Hot Functional testing, all snubbers will be inspected to be j
t Q423.36
" Emergency Ventilation" l
Response
Emergency ventilation systems will be demonstrated capable a f maintaining ESF equipment within its design temperature range by measuring air and cooling water -
l temperatures and flows and making engineering extrapolations to post-accident design heat loads.
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1 0423.38
" Auxiliary Power Distribution"
Response
The initial test program will verify the capacity o f the system auxiliary transformer (starting transformer) to supply power to its unit's vital buses while carrying its maximum load of plant auxiliaries and the other unit's vital buses.
Tests will be conducted to demonstrate transfer capabilities.
These tests will be performed as early as the necessary components become available for testing, but not during the period when electrical separation requirements are in ef fect for Uni' 1 operation and Unit 2 construction.
Q423.39
" Vital Buses Voltages
Response
The voltage levels at the vital buses are predicted throughout the anticipated range of voltage variation of the of f-site power source by an engineering analysis.
The analysis is validated by selected measurements taken during the test program.
Q423.40
" Basin Vo rtexing"
Response
Tests at Byron will demonstrata the adequacy of NPSH and t
the absence of vortexing over the range of basin levels anticipated in the essential service water cooling towers.
Such testing is not feasible at Braidwood but system design has provided a high degree of assurance of acceptalle NPSH and vortex minimization.
Q423.41 "Non-essential Startup Test"
Response
All listed startup tests are essential.
Q423.43
" Delta Temperature Linearity"
Response
Table 14.2-90 will be revised to incorporate an acceptance criteria for assuring that the linearity of the delta temperature measurements are within specifications.
3126N
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