ML20101A236
| ML20101A236 | |
| Person / Time | |
|---|---|
| Site: | Three Mile Island  |
| Issue date: | 12/13/1984 |
| From: | Hukill H GENERAL PUBLIC UTILITIES CORP. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| 5211-84-2294, NUDOCS 8412180287 | |
| Download: ML20101A236 (45) | |
Text
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.yg GPU Nuclear Corporation
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- ',emea=48o Middletown, Pennsylvania 17057-0191 717 944 7621 TELEX 84 2386 Writer's Direct Dial Number:
December 13, 1984 5211-84-2294 Office of Nuclear Reactor Regulation Attn: Harold R. Denton, Director U. S. Nuclear Regulatory Commission Washingtor., D. C. 20555
Dear Sir:
Three Mile Island Nuclear Station Unit 1 (TMI-1)
Operating License No. DPR-50 Docket No. 50-289 Final Safety Analysis Report Update - 3, Chapter 11 Enclosed are one original and twelve copies of changed pages from Chapter 11 of the Final Safety Analysis Report Update - 3 for TMI-1, filed pursuant to 10 CFR 50.71(e).
Due to the late identification of certain errors, Chapter 11 Update was withheld from the FSAR Update - 3 submitted on July 26, 1984. The up-dated List of Effective Pages is also included.
Sincerely, H. D. Hukill Director, TMI-1 HDH/MI/ RAS /kds Enclosures cc: R. Conte J. Van Vliet ,
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-Sworn and Subscribed to Before me this aday I(
of % awa , 1984 0412180287 841213 PDR ADOCK 05000
"'dPtfNU6taliboF66FalldriWa subsidiary of the General Public Utilities Corporation
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PAGE REPLACEMENT PAGE GUIDE TMI-l FSAR Update - 3 7/84 Remove Page Insert Page Remove'Page Insert Page Chapter - 2 2.5-1 -2.5-1 9.8-18 9.8-18 2.5-2 2.5-2 9.9-1 9.9-1 2.5-5 2.5-5 9.9-2 9.9-2 2.5-6 2.5-6 9.9-2 through 9.9.2 through 2.5-14 2.5-14 9.9-14 9.9-14 2.5-15 2.5-15 9.9-17 9.9-17 2.5-22 9.9-18 9.9-18 Fig. 9.2-4 Fig. 9.2-4 Chapter - 4 Sh. 1 of 1 Sh. 1 of 2.
Sh. 2 of 2 4.2-20a - '
4.2-21 through 4.2-21 through Chapter - 10 4.2-26 4.2-26 '
Fig. 4.2-1 Fig. 4.2-1 10.4-5 10.4-5 Table 10.3-1 Table 10.3-1 Chapter - 5 Sh. 3 of 3 Sh. 3 of 3 5.3-9 5.3-9 Chapter - 11 5.3-10 5.3-10
\ ~ Table 5.3.2 Table 5.3-2 11.2-9 through 11.2-9 through Sh. 3 of 8 Sh. 3 of 8 11.2-14 11.2-14 Table 5.3-6 Table 5.3-6 ll.2-14a -
Fig. 5.3-1 Fig. 5.3-1 11.2-15 through 11.2-15 through
-Sh. 1 of 2 Sh.1 of 2 11.2-21 11.2-21 Sh. 2 of 2 Sh. 2 of 2 -
11.2-22 Fig. 5.3-5 Fig. 5.3-5 11.4-5 through 11.4-5 through 11.4-12 11.4-12
, Chapter - 7 -
11.4-13 Table 11.2-2 Table 11.2-2 7.1-29 thrrugh 7.1.29 through Sh.1 of 2 Sh. 1 of 2 7.1-31 7.1-31 Fig. 11.2-1 Fig. 11.2-1 7.2-7 7.2-7 Fig. 11.2 Fig. 11.2-6 7.2-8 7.2-8 Chapter - 12 Chapter - 8 12.1-3 12.1-3 8.2-13 through_ 8.2-13 through 12.1-4 12.1-4 8.2-16 8.2-16 12.1-43 12.1-43 8.2-19 8.2-19 12.1-44 12.1-44 8.2-20 8.2-20 12.1-53 12.1-53 Fig. 8.2-4 Fig. 8.2-4 12.1-54 12.1-54 12.2-1 through 12.2-1 through Chapter - 9 12.2-13 12.2-13 ,
9.2-5 through 9.2-5 through Appendix 14A 9.2-10 9.2-10 9.8.17 9.8-1J 14A-13 14A-13 14A-14 14A-14
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Paae a Update # Date Pace # Update # Date Table 2.3-2 1 7/82 Table 2.5-13 g Sh. 1 of 4 1 7/82 Sh.1 of 1 1 7/82 W Sh. 2 of 4 1 7/82 Table 2.5-14 Sh. 3 of 4 1 7/82 Sh. 1 of 1 1 7/82 Sh. 4 of 4 1 7/82 Table 2.5-15 Table 2.3-3 Sh. 1 of 1 1 7/82 Sh. 1 of 2 1 7/82 Table 2.5-16 Sh. 2 of 2 1 7/82 Sh. 1 of 1 1 7/82 Table 2.4-1 Table 2.5-17 Sh. 1 of 1 1 7/82 Sh. 1 of 7 1 7/82 Table 2.4-2 Sh. 2 of 7 1 7/87.
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Table 4.3-6
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l 7 .1-5 1 7/82 1 7.1-6 1. 7/82 7.2-25 1 7/82 7.1-7 1 7/82 7.2-26 1 7/82 7.1-8 1 7/82 7.3-1 1 7/82 7.1-9 1 7/82 7.3-2 1 7/82 7.1-10 1 7/82 7.3-3 1 7/82 7.1-11 1 7/82 7.3-4 1 7/82 7.1-12 1 7/82 7.3-5 1 7/82 7.1-13 1 7/82 7.3-6 1 7/82 7.1-14 1 7/82 7.3-7 1 7/82 7.1-15 1 7/82 7.3-8 1 7/82 l .g 7.1-16 1 .
7/82 7.3-9 1 7/82 7.1-17 1 7/82 7.3-10 1 7/82 v 7.1-18 1 7/82 7.3-11 1 7/82 l 7.1-19 1 7/82 7.3-12 1 7/82
, 7.1-20 1 7/82 7.3-12a 2 7/83 7.1-21 1 7/82 7.3-13 2 7/83
, 7.1-22 1 7/82 7.3-14 2 7/83 7.1-23 1 7/82 7.3-15 2 7/83 7.1-24 1 7/82 7.3-16 2 7/83 7.1-25 1 7/82 7.3-17 2 7/83 7.1-26 1 7/82 7.3-18 2 7/83 7.1-27 1 7/82 7.3-19 2 7/83
[ 7.1-28 1 7/82 7.3-20 2 7/83 l- 7.1-29 3 7/84 7.3-21 2 7/83 l
7.1-30 3 7/84 7.3-22 2 7/83 7.1-31 3 7/84 7.3-23 2 '7/83 i- 7.2-1 1 7/82 7.3-24 2 7/83 7.2-2 1 7/82 7.3-25 2 7/83 7.2-3 1 7/82 7,4-1 1 7/82 7.2-4 1 7/82 7.4-2 1 7/82 7.2-5 1 7/82 7.4-3 1 7/82 7.2-6 1 7/82 7.4-4 1 7/82 7.2-7 3 7/84 7.4-5 1 7/82 7.2-8 3 7/84 7.4-6 1 7/82 7.2-9 1 7/82 7.4-7 2 7/83 7.2-10 1 7/82 7.4-8 1 7/82 7.2-11 1 7/82 7.4-9 1 7/82 P-21
THI-1/FSAR LIST OF EFFECTIVE PAGES . -
Pace a Ucdate # Date Pace a Update # Date 7.4-10 1 7/82 g w
7.4-11 1 7/82 7.5-1 1 7/82 Table 7.1-1 Sh. 1 of 2 2 7/83 Sh. 2 of 2 2 7/83 Table 7.1-2 Sh. 1 of 2 2 7/83 Sh. 2 of 2 2 7/83 Table 7.1-3 Sh. 1 of 2 1 7/82 Sh. 2 of 2 1 7/82 Table 7.1-4 ,.
Sh.'1 of 2 1 7/82 Sh. 2 of 2 1 7/82 Table 7.2-1 Sh. 1 of 1 1 7/82 Table 7.3-1 2 7/83 Fig. 7.1-1 1 7/82 Fig. 7.1-2 1 7/82 Fig. 7.1-3 1 7/82
- Fig. 7.1-4 l Sh. 1 of 2 1 7/82 i Sh. 2 of 2 1 7/82 l Fig. 7.1-5 1 7/82 Fig. 7.1-6 1 7/82
- Fig. 7.1-7 1 7/82 Fig. 7.1-8 2 7/83 l Fig. 7.2-1 1 7/82 Fig. 7.2-2 1 7/82 l Fig. 7.2-3 1 7/82
! Fig. 7.2-4 1 7/82 l
Fig. 7.2-5 1 7/82
- Fig. 7.2-6 1 7/82 i
Fig. 7 2-7 1 7/82 Fig. 7.2-8 1 7/82 Fig. 7.2-9 1 7/82 Fig. 7.3-1 1 7/82 Fig. 7.3-2 1 7/82 Fig. 7.3-3 1 7/82 Fig. 7.3-4 Sh. 1 of 2 1 7/82 Sh. 2 of 2 1 7/82 Fig. 7.3-5 Sh. 1 of 2 1 ,7/82 Sh. 2 of 2 1 7/82 Fig. 7.3-6 1 7/82 Fig. 7.3-7 1 7/02 Fig. 7.4-1 1 7/82 P-22 h
THI-1/FSAR LIST OF EFFEL M PAGES i
Pace # Update # Date Pace # Uedate # Date 8-1 1 7/82 Table 8.2-7 l 11 2 7/83 Sh. 1 of 2 1 7/82 8-111 1 7/82 . Sh. 2 of 2 1 7/82 8-iv 2 7/83 Table 8.2-8 8.1-1 2 7/83 Sh. 1 of 6 1 7/82 8.2-1 2 7/83 Sh. 2 of 6 1 7/82 ,
8.2-2 2 7/83 Sh. 3 of 6 1 7/82 8.2-3 2 7/83 Sh. 4 of 6 1 7/82
- 8.2-4 2 7/83 Sh. 5 of 6 1 7/82 8.2-5 2 7/83 Sh. 6 of 6 2 7/83 8.2-6 2 7/83 Table 8.2-9 8.2-7 2 7/83 Sh. 1 of 6 1 7/82 8.2-8 2 7/83 Sh. 2 of 6 2 7/83 8.2-9 2 7/83 Sh. 3 of 6 2 7/83 8.2-10 2 7/83 Sh. 4 of 6 2 7/83 8.2-11 2 7/83 Sh. 5 of 6 2 7/83
, 8.2-12 2 7/83 Sh. 6 of 6 2 7/83
! 8.2-13 3 7/84- Fig. 8.2-1 1 - 7/82 8.2-14 3 7/84 Fig. 8.2-2 2 7/83 j 8.2-15 3 7/84 Sh. 1 of 2 2 7/83 8.2-16 3 7/84 Sh. 2 of 2 2 7/83 8.2-17 2 7/83 Fig. 8.2-3 2 7/83 8.2-18 2 7/83 Fig. 8.2-4 3 7/84 8.2-19 3 7/84 . Fig. 8.2-5 1 7/82 8.2-20 . 3 7/84 Fig. 8.2-6 2 7/83 8.3-1 1 7/82 -Fig. 8.2-7 2 7/83 L 8.4 2 7/83 7/82 8.4-2 1
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8.4-3 1 7/82 8.5-1 2 7/83 Table 8.2-1 Sh. 1 of 3 2 7/83 Sh. 2 of 3 1 7/82 Sh. 3 of 3 2 7/83 Table 8.2-2 Sh. 1 of 2 1 7/82' i
Sh. 2 of 2 1 7/82 Table 8.2-3 Sh. 1 of 2 1 7/82 Sh. 2 of 2 1 7/82 Table 8.2-4 Sh. 1 of 3 2 7/83 Sh. 2 of 3 2 7/83 Sh. 3 of 3 1 7/82 Table 8.2-5 Sh. 1 of 2 1 7/82 Sh. 2 of 2 1 7/82 Table 8.2-6 Sh. 1 of 2 1 7/82 Q Sh. 2 cf 2 1 7/82 P-23
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TMI-1/FSAR .. .
LIST OF EFFECTIVE PAGES Pace a @date # Date Pace # Update # Date 9-1 1 7/82 9.6-5 1 7/82 9-11 1 7/82 9.6-6 1 7/82 9-111 1 7/82 9.6-7 1 7/82 9-iv 1 7/82 9.6-8 '1 7/82 9-v 1 7/82 9.6-9 1 7/82 9-vi 2 7/83 9.6-10 1 7/82 9-vii 2 7/83 9.6-11 1 7/82 9-viii 2 7/83 9.6-12 1 7/82 9-ix 2 7/83 9.6-13 1 7/82 9-x 2 7/83 9.7-1 2 7/83 9-xi 1 7/82 9.7-2 1 7/82 9-xii 1 7/82 9.7-3 1 7/82 9.0-1 1 7/82 9.7-4 1 7/82 9.0-2 1 7/82 9.7-5 1 7/32 9.1-1 1 7/82 9.7-6 1 7/82 9.1-2 1 7/82 9.7-7 1 7/82 9.1-3 1 7/82 9.7-8 1 7/82 9.1-4 1 7/82 9.7-9 1 7/82 9.1-5 1 7/82 9.7-10 1 7/82 9.1-6 1 7/82 9.7-11 1 7/82 9.1-7 1 7/82 9.7-12 1 7/82 9.1-8 1 7/82 9.7-13 1 7/82 9.2-1 1 7/82 9.8-1 1 7/82 9.2-2 1 7/82 9.8-2 1 7/82 &
9.2-3 1 7/82 9.8-3 1 7/82 W 9.2-4 1 7/82 9.8-4 1 7/82 9.2-5 3 7/84 9.8-5 1 7/82 9.2-6 3 7/84 9.8-6 1 7/82 9.2-7 3 7/84 9.8-6a 2 7/83 9.2-8 3 7/84 9.8-7 2 7/83 9.2-9 3 7/84 9.8-8 2 7/83 9.2-10 3 7/84
- 9.8-9 2 7/83 9.2-11 1 7/82 9.8-10 2 7/83 9.3-1 2 7/83 9.8-11 2 7/83 9.3-2 1 7/82 9.8-12 2 7/83 9.3-3 1 7/82 9.8-13 2 7/83 9.4-1 1 7/82 9.8-14 2 7/83 9.4-2 1 7/82 9.8-15 2 7/83 9.4-3 1 7/82 9.8-16 2 7/83 9.4-4 1 7/82 9.8-17 3 7/84 9.4-5 1 7/82 9.8-18 2 7/83 9.5-1 1 7/82 9.9-1 3 7/84 9.5-2 2 7/83 9.9-2 1 7/82 9.5-3 2 7/83 9.9-3 1 7/92 9.5-4 1 7/82 9.9-4 1 7/82 9,.5-5 1 7/82 9.9-5 1 7/82 9.6-1 2 7/83 9.9-6 1 7/82 9.6-2 2 7/83 9.9-7 1 7/82 9.6-3 2 7/83 9.9-8 1 7/82 g 9.6-4 1 7/82 9.9-9 3 7/84 W P-24 1
TMI-1/FSAR LIST OF EFFECTIVE PAGES Pace # Update # Date Pace # Update # Date 9.9-10 3 7/84 Sh. 2 of 2 1 7/82 9.9-11 3 7/84 Table 9.6-1 9.9-12 3 7/84 Sh. 1 of 4 1 7/82 9.9-13 3 7/34 Sh. 2 of 4 1 7/82 9.9-14 3 7/84 Sh. 3 of 4 1 7/82 '
9.9-15 2 7/83 Sh. 4 of 4 1 7/82 9.9-16 2 7/83 Table 9.7-1 .
9.9-17 2 7/83 Sh. 2 of 1 1 7/82 9.9-18 3 7/84 Table 9.8-1 9.9-19 2 7/83' Sh 1 of 1 2 7/83 9.9-20 2 7/83 Table 9.10-1 9.9-21 2 7/83 Sh. 1 of 2 2 7/83 9.9-22 2 7/83 Sh. 2 of 2 2 7/83 9.9-23 2 ' 7/83 Fig. 9.1-1 9.9-24 2 7/83 Sh. 1 of 3 1 7/82 9.9-25 2 7/83 Sh. 2 of 3 1 7/82 9.10-1 2 7/83 Sh. 3 of 3 1 7/82 9.10-2 2 7/83 Fig. 9.1-2 9.10-3 2 7/83 Sh.'1 of 2 2 7/83 9.10-4 2 7/83 Sh. 2 of 2 2 7/83 9.10-5 2 7/83 Fig. 9.2-1 1 7/82 9.10-6 2 7/83 Fig. 9.2-2 2 7/83 9.11-1 2 7/83 Fig. 9.2-3 1 7/82 Table 9.1-1 Fig. 9.2-4 3 7/84 Sh. 1 of 1 1 7/82 Sh. 1 of 2 3 7/84 Table 9.1-2 Sh. 2 of 2 3 7/84 Sh.1 of 4 1 7/82 Fig. 9.3-1 1 7/82 Sh. 2 of 4 1 7/~ Fig. 9.4-1 2 7/83 Sh. 3 cf 4 1
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Fig. 9.5-1 1 7/82 Sh. 4 of 4 1 Fig. 9.6-1 2 7/83 Tabla 9.2-1 Fig. 9.6-2 1 7/82 Sh. 1 of 3 1 Fig. 9.6-3 1 7/82 Sh. 2 of 1 1 Fig. 9.6-4 1 7/82 Sh. 3 of 3 1, Fig. 9.6-5 1 ,
7/82 Table 97.2-2 Fig. 9.6-6 1 7/82 Sh. 1 of 1 1 7. 9.6-7 1 7/82 Table 9.2-3 J. 9.6-8 1 7/32 Sh. 1 of 1 2 '
J. 9.6-9 1 7/82 Table 9.3-1 .g. 9.7-1 :. 7/82 Sh. 1 of 1 1 7/. ig. 9.7-2 1 7/82 Table 9.3-2 Fig. 9.8-1 1 7/82 Sh. 1 of i 1 7/82 Fig. 9.8-2 1 7/82 Table 9.4-1 Fig. 9.8-3 1 7/82 Sh. 1 of 3 1 7/82 Fig. 9.8-4 1 7/82 Sh. 2 of 3 1 7/82 , Fig. 9.8-5 1 7/82 Sh. 3 of 3 1 7/82 , Fig. 9.9-1
. 2 7/C3 Table 9.5-1 Fig. 9.9-2 1 7/82 Sh. 1 of 1 1 7/82 Fig. 9.9-3 1 7/82 Table 9.5-2 Sh. 1 of 2 1 7/82
THI-1/FSAR LIST OF EFFECTIVE PAGES .- -
Pace # Ucdate # Date Pace # Ucdate # Date 10-1 1 7/82 Sh. 1 of 1 1 7/82 g 10-11 2 7/83 Table 10.4-1 W 10-111 1 7/82 Sh. 1 of 5 1 7/82 10-iv 1 7/82 Sh. 2 of 5 1 7/82 10-v i 7/82 Sh. 3 of 5 1 7/82 10.1-1 1 7/82 Sh. 4 of 5 1 7/82 10.2-1 1 7/82 Sh. 5 of 5 1 7/82 10.2-2 2 7/83 Table 10.4-2 10.2-3 2 7/83 Sh. 1 of 1 1 7/82 10.2-4 1 7/82 Table 10.4-3 10.3-1 2 7/83 Sh. 1 of 2 1 7/82 10.3-2 2 7/83 Sh. 2 of 2 1 7/82 10.3-3 2 7/83 Table 10.5-1 10.3-4 1 7/82 Sh. 1 of 3 1 7/82 10.3-5 2 7/83 Sh. 2 of 3 1 7/82 10.3-6 ,
2 7/83 Sh. 3 of 3 1 7/82 10.3-7 2 7/83 Table 10.6-1 10.4-1 2 7/83 Sh.1 of 2 1 7/82 10.4-2 2 7/83 Sh. 2 of 2 1 7/02 10.4-3 -1 7/82 Fig. 10.2-1 1 7/82 10.4-4 1 7/82 Fig. 10.3-1 1 7/82 10.4-5 3 7/84 Fig. 10.3-2 1 7/82 10.4-6 1 7/82 Fig. 10.4-1 1 7/82 10.5-1 1 7/82 Fig. 10.4-2 1 7/82 10.5-1 1 7/82 Fig. 10.4-3 1 7/82 10.6-1 2 7/83 Fig. 10.5-1 2 7/83 g 10.6-2 2 7/83 W 10.6-3 1 7/82 10.6-4 1 7/82 10.6-5 1 7/82 10.7-1 2 7/83
. 10.7-2 2 7/83 10.7-3 2 7/83 10.7-4 2 7/83 10.8-1 2 7/83 10.8-2 2 7/83 10.9-1 1 7/82 Table 10.2-1 Sh. 1 of 1 1 7/82 Table 10.2-2 Sh. 1 of 1 1 7/82 Table 10.3-1 Sh. 1 of 3 1 7/82 Sh. 2 of 3 1 7/82 Sh. 3 of 3 3 7/84 Table 10.3-2 Sh. 1 of 3 1 7/82 Sh. 2 of 3 1 7/82 Sh. 3 of 3 1 7/82 Table 10.3-3 i -
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THI-1/FSAR LIST OF DTECTIVE PAGES Pace a Update # Date Pace a Update a Date O
\_-) 11-1 1 7/82 11.5-4 2 7/83 11-11 1 7/82 11.5-5 2 7/83 11-111 1 7/82 11.5-6 2 7/83 11-iv 1 7/82 11.5-7 1 7/82 l
11-v 1 7/82 11.5-8 2 7/83
! 11-vi 1 7/82 11.5-9 2 7/83 l 11-vii 1 7/82 11.5-10 1 7/82 11-viii 1 7/82 11.5-11 1 7/82 11.1-1 1 7/82 11.5-12 2 7/83 11.1-2 1 7/82 11.5-13 2 7/83 11.2-1 1 7/82 11.5-14 2 7/83 11.2-2 1 7/82 11.6-1 1 7/82 11.2-3 1 7/82 11.6-2 1 7/82
'.11.2-4 2 7/83 11.6-3 2 7/83 11.2-5 2 7/83 11.6-4 2 7/83 11.2-6 2 7/83 11.6-5 1 7/82 11.2-7 1 7/82 11.7-1 1 7/82 11.2-8 1 7/82 11.7-2 1 7/82 11.2-9 3 7/84 Table 11.1-1 11.2-10 3 T/84 Sh. 1 of 1 1 7/82 11.2-11 3 7/84 Table 11.1-2 11.2-12 3 7/84 Sh. 1 of 1 1 7/82 11.2-13 3 7/84 Table 11.1-3 11.2-14 3 7/84 Sh. 1 of 3 1 7/82 fs 11.2-15 1 7/82 Sh. 2 of 3 1 7/82
(
) 11.2-16 1 7/82 Sh. 3 of 3 1 7/62 11.2-17 1 7/82 Table 11.2-1 11.2-18 1 7/82 Sh. 1 of 11 1 7/M 11.2-19 1 7/82 Sh. 2 of 11 1 7/82 11.2-20 1 7/82 Sh. 3 of 11 1 7/82 11.2-21 1 7/82 Sh. 4 of 11 1 7/82 11.2-22 3 7/84 Sh. 5 of 11 1 7/82 11.3-1 2 7/83 Sh. 6 of 11 1 7/82 11.3-2 1 7/82 Sh. 7 of 11 1 7/82 11.3-3 1 7/82 Sh. 8 of 11 1 7/82 11.3-4 1 7/82 Sh. 9 of 11 1 7/82 11.4-1 1 7/82 Sh. 10 of 11 1 7/82 11.4-2 1 7/82 Sh. 11 of 11 1 7/82 11.4-3 1 7/82 Table 11.2-2 11.4-4 2 7/83 Sh. 1 of 2 3 7/84 11.4-5 3 7/84 Sh. 2 of 2 1 7/82 11.4-6 3 7/84 Table 11.2-3 11.4-7 3 7/84 Sh. 1 of 1 1 7/82 11.4-8 3 7/84 Table 11.2-4 11.4-9 3 7/84 Sh. 1 of 2 1 7/82 11.4-10 3 7/84 Sh. 2 of 2 1 7/82 11.4-11 3 7/84 Table 11.2-5 11.4-12* 3 7/84 Sb 1 of 2 1 7/82 11.5-1 1 7/82 Sh. 2 of 2 1 7/82 11.5-2 1 7/82 Table 11.2-6 11.5-3 1 7/82 Sh. 1 of 1 1 7/82 P-27
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TMI-1/FSAR LIST OF EFFECTIVE PAGES Pace # Update # Da_tg Pace # Update
- Date 12-1 2 .7/83 12.1-45 2 7/83 12-11 2 7/83 12.1-46 2 7/83 12-111 2 7/83 12.1-47 2 7/83
- 12-iv 2 7/83 12.1-48 2 7/83 12-v 2 7/83 12.1-49 2 7/83 12-vi 2 7/83 12.1-50 2 7/83 12-vii 2 7/83 12.1-51 2 7/83 l
12.1-1 1 7/82 12.1-52 2 7/83 12.1-2 2 7/83 12.1-53 3 7/84 12.1-3 1 7/82 12.1-54 3 7/84
. 12.1-4 3 7/84 12.1-55 2 7/83 12.1-5 1 7/82 12.1-56 ~
2 7/83 12.1-6 ~ 1 7/82 12.2-1 3 7/84
-12.1-7 2 7/83 12.2-2 3 7/84 12.1-8 2 7/83 12.2-3 3 7/84 12.2-4 7/83 12.1-9 2 7/83 2 12.1-10 2 7/83 12.2-5 3 7/84~
12.1-11 2 7/83 12.2-6 3 7/84 1 12.1-12 2 7/83 12.2-7 3 7/84 l 12.1-13 2 7/83 . 12.2-8 3 7/84 12.1-14 2 7/83 12.2-9 3 7/84 12.1-15 2 7/83 12.2-10 3 7/84 l 12.1-16 2 7/83 12.2-11 3 7/84 l -12.1-17 2 7/83 12.2-12 3 7/84 12.1-18 2 7/83 12.2-13 3 7/84 12.1-19 2 7/83 12.3-1 2 7/83 12.1-20 2 7/83 12.3-2 2 7/83 12.1-21 2 7/83 12.3-3 2 7/83 l 12.1-22 2 7/83 12.3-4 2 7/83
- 12.1-23 2 7/83 12.3-5 2 7/83 l 12.1-24 2 7/83 12.4-1 2 7/83 l 12.1-25 2 7/83 12.4-2 2 7/83 12.1-26 2 7/83 12.5-1 2 7/83 12.1-27 2' 7/83 12.5-2 2 7/83 12.1-28 2 7/83 12.5-3 2 7/83 12.1-29 2 7/83 12.6-1 1 7/82 12.1-30 2 7/83 12.7-1 1 7/82 12.1 2 7/83 12.8-1 1 7/02 12.1-32 2 7/83 12.9-1 2 7/63 12.1-33 2 7/83 Fig. 12.1-1 12.1-34 2 7/83 Fig. 12.1-2 12.1-35 2 7/83 Fig. 12.2-1 12.1-36 2 7/83 12.1-37 2 7/83 ,
l 12.1-38 2 7/83 12.1-39 2 '7/83 ,
12.1-40 2 7/83 12.1-41 2 7/83 12.1-42 2 7/83
- 12.1-43 3 7/84 l 12.1-44 3 7/84 P-29
THI-1/FSAR LIST OF t.arCIIVE PAGES Update
- Date Pace a Update a Date Pace s %w*
1 7/82 13A-13 1 7/82 13-1 7/82 1 7/82 13A-14 1 13-11 1 7/82 13-111 1 7/82 13A-15 7/82 13A-16 1 7/82 13-iv i 1 7/82 13.1-1 1 7/82 13A-17
- 1. 7/82 13A-18 1 7/82 13.1-2 1 7/82 13.1-3 1 7/82 13A-19 1 7/82 13A-20 1 7/82 13.1-4 1 7/82 13.1-5 1 7/82 13A-21 13.1-6 1 7/82 13A-22 1 7/82 13.1-7 1 7/82 13A-23 1 7/02 13.1-8 1 7/82 13A-24 '1 7/82 13.1-9 1 7/82 13A-25 1 7/82 13.2-1 1 7/82 13A-26 1 7/82 13.2-2 1 7/82 13A-27 1 7/82 13.2-3 1 7/82 13A-28 1 7/82 1 7/82 13A-29 1 7/82 13.2-4 1 7/82 13.2-5 1 7/82 13A-30 1 7/82 13A-31 1 7/82 13.2-6 7/82 7/82 13A-32 1 13.2-7 1 1 7/82 13.2-8 1 7/82 13A-33 13A-34 1 7/82 Table 13.1-1 Sh. 1 of 1 1 7/82 13A-35 13A-36 1
1 7/82 7/82 h
Table 13.1-2 7/82 Sh. 1 of 6 1 7/82 13A-37 1 Sh. 2 of 6 1 7/82 13A-38 1 7/82 Sh. 3 of 6 1 7/82 13A-39 1 7/82 Sh. 4 of 6 1 7/82 13A-40 1 7/82 Sh. S cf 6 1 7/82 13A-41 1 7/82 Sh. 6 of 6 1 7/82 13A-42 1 7/82 Table 13.1-3 13A-43 1 7/82 Sh. 1 of 2 1 7/82 13A-44 1 7/82 Sh. 2 of 2 1 7/82 13A-45 1 7/82 13A-46 1 7/82 Taele 13.1-4 1 7/82 Sh. 1 of 2 1 7/82 13A-47 Sh. 2 of 2 1 7/82 13A-48 1 7/82 Fig. 13.2-1 13A-49 1 7/82 13A-i 1 7/82 13A-50 1 7/82 1 7/82 13A-51 1 7/E2 13A-ii 1 7/82 13A-52 1 7/82 13A-1 13A-2 1 7/82 13A-53 1 7/82 13A-3 1 7/82 13A-54 1 7/82 1 7/82 13A-55 1 7/82 13A-4 13A-5 1 7/82 13A-56 1 7/82 13A-6 1 7/82 13A-57 1 7/82 13A-7 1 7/82 13A-58 1 7/82 13A-8 1 7/82 13A-59 1 7/82 13A-9 1 7/82 13A-60 1 7/82 13A-10 1 7/82 13A-11 1 7/82 13A-12 1 7/82
LIST OF EFFECTIVE PAGES.
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~* Pace n Ur# te o Da_tig Pace O . Updatn O Date Fig. 14.1-14 1 7/82 Fig. 14.2-42 1 7/82 Fig. 14.1-15 1 7/82 Fig. 14.2-43 1 7/82 Fig. 14.1-16 1 7/s2 Fig. 14.2-44 1 7/82
~Q Fig."14.1-17 1 7/82 Fig. 14.2-45 1 7/82 Fig. 14.1-18 1 7/82 Fig. 14.2-46 1 7/82 Fig. 14.1-19 1 7/82 Fig. 14.2-47 1 7/82 Fig. 14.1-20 1 7/82 Fig. 14.2-48 1 7/82 Fig. 14.1-21 1 7/82 Fig. 14.2-49 1 7/82 Fig. 14.1-22 1 7/82 Fig. 14.2-50 1 7/82 Fig. 14.2-1 1 7/82 Fig.'14.2-51 1 7/82 Fig. 14.2-2 1 7/82 Fig. 14.2-52 1 7/82 Fig. 14'.2-3 1 7/82 Fig. 14.2-53 1 7/82 Fig. 14.2-4 '1 7/82 Fig. 14.2-54 1 7/82 Fig. 14.2-5 1 7/82 Fig. 14.2-55 1 7/82 Fig. 14.2-6 1 7/82 14A-i 1 _. 7/82
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Fig. 14.2-7 1 7/82 14A-li 1 ' 7/82 Fig. 14.2-8 1 7/82 14A-lii 1 7/82 Fig. 14.2-9 1 7/82 14A-iv 1 7/82 Fig. 14.2-10 1 7/82 14A-v 1 7/82 Fig. 14.2-11 1. 7/82 14A-1 1 7/82 Fig. 14.2-12 1 7/82 14A-2 1- 7/82
. Fig.'14.2-13 1 7/82 14A-3 1 7/82 Fig. 14.2-14 1 7/82 14A-4 1 7/82 Fig. 14.2-15 1 7/82 14A-5 1 7/82 Fig. 14.2-16 1 7/82 14A-6 1 7/82 Fig. 14.2-17 1 7/82 14A-7 1 7/82 Fig. 14.2-18 1 7/82 14A-8 1 7/82 Fig. 14.2-19 1 7/82 14A-9 1 7/82 Fig. 14.2-20 1 7/82 14A-10 1 7/82 Fig. 14.2-21 1 7/82 14A-11 1 7/82 Fig. 14.2-22 1 7/82 14A-12 1 7/82 Fig. 14.2-23 1 7/82 14A-13 1 7/82 Fig. 14.2-24 1 7/82 14A-14 3 7/94 Fig. 14.2-25 1 7/82 14A-15 1 7/82 Fig. 14.2-26 1 7/82 14A-16 1 7/82 Fig. 14.2-27 1 7/82 ^14A-17 1 7/82 L Fig. 14.2-28 1 7/82 14A-18 1 7/82 4 Fig. 14.2-29 .
1 7/82 14A-19 1 7/82 Fig. 14.2-30 1 7/82 14A-20 1 7/82 Fig. 14.2-31 1 7/82 14A-21 1 7/82 Fig. 14.2-32 1 7/82 14A-22 1 7/82 Fig. 14.2-33 1 7/82 14A-23 1 7/S2 Fig. 14.2-34 1 7/82 14A-24 1 7/82 Fig. 14.2-35 1 7/82 14A-25 1 7/82 Fig. 14.2-36 1 7/82 14A-26 1 7/82 Fig. 14.2-37 1 7/82 14A-27 1 7/82
' Fig. 14.2-38 1 7/82 14A-28 1 7/82 '
Fig. 14.2-39 1 7/82 14A-29. 1 7/82 Fig. 14.2-40 1 7/82 14A-30 1 7/82 Fig. 14.2-41 1 7/82 14A-31 1 7/82 P-33
- . . ~ . ~ - - - - , _ , . . - . . . , . . . , _ -
, , , , , , . . _ . . _ - ,- -~._,.y-,,,-,-,.,,m_.,-.....,m.-.,.
LIST OF r e r r CHVE PAGES ,
Pace s Update # Date Pace # Uedate # Date 14A-32 1 7/82 14B-19 1 7/82 14A-33 1 7/82 14B-20 1 7/82 14A-34 1 -
7/82 Table 14B-1 Table 14A-1 Sh. 1 of 1 1 7/82 Sh. 1 of i 1 7/82 Table 14B-2 Table 14A-2 Sh. 1 of 2 1 7/82 Sh. 1 of 2 1 7/82 Sh. 2 of 2 1 7/82 '
Sh. 2 of 2 1 7/82 Table 14B-3 Table 14A-3 Sh. 1 of 1 1 7/82 Sh. 1 of 2 1 7/82 14C-1 1 7/82 Sh. 2 of 2 1 7/82' 14C-ii 1 7/82 Table 14A-4 14C-1 1 7/82 Sh. 1 of 2 1 7/82 14C-2 1 7/82 Sh. 2 of 2 1 7/82 14C-3 1 7/82 Table 14A-5 14C-4 1 7/82 Sh. 1 of 2 1 7/82 14C-5 1 7/82 Sh. 2 of 2 1 7/82 14C-6 1 7/82 Table 14A-6 14C-7 1 7/82 Sh. 1 of 1 1 7/82 14C-8 1 7/82 Table 14A-7 14C-9 1 7/82 Sh. 1 of 1 1 7/82 14C-10 1 7/82 Table 14A-8 14C-11 1 7/82 Sh. 1 of 3 1 7/82 Table 14C-1 Sh. 2 of 3 1 7/82 Sh. 1 of 1 1 7/82 Sh. 3 of 3 1 7/82 Table 14C-2 Table 14A-9 Sh. 1 of 1 1 7/82 14B-i Sh. 1 of 1 1 1
7/82 7/82 14D-i 14D-ii 1
1 7/82 7/82 g
- 14B-iii 1 7/82 14D-iv i 7/82 14B-iv 1 7/82 14D-v 1 7/82 14B-1 1 7/82 14D-1 1 7/82 14B-2 1 7/82 14D-2 1 7/82 14B-3 1 7/82 14D-3 1 7/82 14B-4 1 7/82 14D-4 1 7/82 14B-5 1 7/82 14D-5 1 7/82 14B-6 1 7/82 14D-6 1 7/82 14B-7 1 7/82 14D-7 1 7/82 14B-8 1 7/82 14D-8 1 7/82 14B-9 1 7/82 14D-9 1 7/82 14B-10 1 7/82 14D-10 1 7/82 14B-11 1 7/82 -
14D-11 1 7/82 14B-12 1 7/82 14D-12 1 7/82 14B-13 1 7/82 14D-13 1 7/82 14B-14 1 7/82 14D-14 1 7/82 14B-15 1 7/82 14D-15 1 7/82 14B-16 1 7/82 140-16 1 7/82 14B-17 1 7/82 14D-17 1 7/82 14B-18 1 7/82 14D-18 1 7/82 P-34
THI-1/FSAR h
The Haste gas system provides for the safe collection and storage of gases evolved from reactor coolant in all tanks or items of equipment where this might occur.
The folloHing items are indicated in Table 11.2-1 as being vented to the atmosphere of the cubicles in which they are located: spent resin storage tank, ' used filter precoat tank, concentrated Haste storage tanks, neutralizer tank, neutralizer feed tank, neutralized Haste storage tank, laundry Haste tank, and the preCoat filters. Although some of these items may contain highly radioactive material, essentially none of it is in ~the form' of radioactive gases. .In all cases, the radioactive material contained in these items of equipment is either in the form of crystalline, dissolved ionic, or resin-fixed ionic, solids.
~
~ Also, the Hater in these items is either clean Hater (not primary coolant) that has been provided from the plant ' supply for regenerating resin, flushing resin er filter precoat from their process beds, and so forth, or previously degassed primary coolant (concentrated Haste storage tanks, only) that contains only dissolved ionic solids._ Therefore, the
~ probability of radioactive gases evolving from the normal contents of these items of equipment is extremely low. However, in the unlikely event that l significant amounts of radioactive gas did escape from any of these tanks,
. . it Hould pass into the exhaust ventilation system for the Auxiliary and Fuel Handling Buildings, through the roughing, HEPA, and charcoal filters,
! and be sensed by the unit vent radiation monitor.
Volumetrically, hydrogen is the principal gas evolved in those tanks Hhich
, normally might receive reactor coolant and are vented to the low-pressure vent. header system or to waste gas Compressors. The radioactive fission products, activated dissolved gases, and so forth, contribute an extremely small fraction of the total volume of gas liberated. The Haste gas system has been designed to provide a blanket of inert nitrogen gas in Hhich to collect the gases evolved from the reactor coolant. The mixture of gases
~
- collected (nitrogen, hydrogen, and' radioactive gaseous isotopes) is compressed and stored for decay of the radioactive components prior to recycle (as blanket gas) or disposal to the atmosphere.
' The loH-pressure portions of the vent header system are protected from
- overpressure by relief valves off the piping of the vent header proper, and
- by' Hater filled loop seals or relief valves on the liquid Haste storage tanks whose gas spaces form a portion of the system. Protection of tanks' and piping against excessive vacuum in the event of a combination of highly unlikely equipment malfunctions has been provided. The Haste gas decay I
. 11.2-9
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tanks are protected from overpressures by individual relief valves, as are the Haste gas Compressors.
11.2.2.2 System Description Figures 11.2-6 and 11.2-7 are process floH diagrams of the Haste Gas Disposal System and the Haste gas compressor packages, respectively.
Component data for the Haste gas system are given in Table 11.2-5.
The waste gas vent header system is essentially split into tHo sections, one section Hithin the Reactor Building and one section Hithin the tuxiliary Building. Condensing Hater vapor or liquids entering the section of the vent header system Hithin containment drain to the reactor coolant drain tank while those entering the vent header system Hithin the Auxiliary Building drain to the miscellaneous Haste storage tank. The vent header from the reactor coolant drain tank discharges to the miscellaneous Haste storage tank. The gas spaces of the miscellaneous Haste storage tank and
=
the three reactor coolant bleed tanks are joined as an intermediate gas storage area and discharge the gases they collect to the suction of the Haste g83 Compressors via an intermediate Haste gas delay tank. Make up tank gas sample return and Haste gas release are routed directly doHnstream of Haste gas delay tank and upstream of Haste gas Compressors to avoid hydrogen pockets in the low pressure radHaste liquid and gas tanks. Prior to makeup tank venting, the decay tank Hill be filled Nith dilluting nitrogen to insure Ha content to comply with Technical Specification limitations.
The compressed gas portion of the Haste gas system starts at the Haste gas compressors and includes the three Haste gas decay tanks which provide for h a design minimum of 30 days of storage for gases during normal operation prior to release to the atmosphere. Release is possible prior to the design minimum of 30 days if calculations according to Reference [23] indicate concentration within Appendix I limits. When currently filled decay tank is pressurized to 80 psig an automatic sequencing system preferentially selects a neH Haste gas decay tank for filling based on the pressure Hithin the tank being less than 80 psig and that Haste gas is not being discharged from it. Administrative approval is required to manually initiate either recycle or release to the atmosphere of Haste gases stored in any Haste gas decay tank.
11.2.2.3 Summary. Methods Of Operation Except for initiating the makeup tank sample and Haste gas venting and the recycle or disposal of compressed Haste gases stored in the Haste gas decay tanks, the operation of the Haste gas system is entirely automatic. One Haste gas compressor comes on automatically, removing gases from the vent 11.2-10 UPDATE-3 7/84 9
2 mm.m -mmmm
TMI-1/FSAR header -system as required to maintain the pressure therein at a maximum of O. about 16.4 psia. The second Haste gas compressor is on_ standby and automatically starts as required to back up the running compressor.
- Before receiving Haste gas, the decay tanks Hill be filled with dilluting nitrogen to insure Ha content to comply with Technical Specification limitations.
Compressed Haste gases are sampled shortly after completion of filling of a Maste gas decay tank. The analysis of this sample is the basis for determining whether the gas in the tank should be reused (as makeup blanket gas to the vent header system) or disposed to the environment. If stored gas is to be recycled, recycle may be initiated at any convenient time following analysis of the initial sample.
Any release of radioactive gases from the Haste gas system Hill be made as folloHs:
i
- a. After analysis of samples taken from batches prior to their release,
- ' and establishing flow and radiation level alarm point per Reference (23].
- b. Only through paths that require positive manual operation in order to effe.ct the release.
- c. Through a path in Hhich the gas is monitored tHice, once as it Itaves O the decay tanks, and assign, after it mixes with other gases in the Auxiliary Building ventilation system. Either monitor Hill terminate L the gas discharge automatically in the event its set point is exceeded.
11.2.2.4 System Desion Evaluation Waste Gas Disposal System equipment and piping (external to the Reactor Building) are designed for pressures considerably in excess of those i capable of being applied. The maximum gas pressure capability in the loH-pressure vent header system is positively limited to approximately 8.0 psig by relief valves and the overflow loop seals on the tanks vented to it. A highly unlikely combination of equipment malfunctions and operation in-attention is required to blow the Hater in these loop seals. The absolute minimum volume provided by the gas spaces of tanks associated Hith the low-pressure vent header system is approximately 4000 ft'. Therefore, the 3 maximum gas flow rate anticipated in the system (80 scfm) Hould have to occur for a minimum of about 27 minutes, with no removal of gases by either waste gas compressor, before the loop seals Hould blow. All gas floHs in
! the Haste gaC system of this order of magnitude are initiated by operator i
action, by either pumping Hater into the system from a source not connected 11.2-11 UPDATE-3 I
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TMI-1/FSAR .
to the vent header system, or by venting the pressurized gas space of a tank to the system. Therefore, the operator has adequate time to terminate &
the gas displacement or discharge in the event that both Haste gas compressors fail.
W The design pressure of the high pressure Haste gas system piping and equipment is 150 psig while the design discharge capability of the Haste gas compressors provided is only 80 psig. Further, each Haste gas decay tank is protected by its oHn relief valve, Hhich is set to relieve the tank at 85 psig. The relief valve on the discharge of the compressors is also
, set to relieve at 85 psig. Consequently, it is not considered credible
- that a rupture or major failure resulting from overpressure could occur in the piping or other components of the high-pressure portion of the Haste gas system.
Accidental discharges resulting from the relieving of a Haste g33 decay tank or compressor relief valve are not considered credible as the operator Hill have approximately 8 minutes (between receiving the alarm that the automatic sequencer has not been able to transfer waste gas discharge to a fresh tank, and the popping of the relief valve on the overfilled tank) in Hhich to take the action required to get an empty, or partially empty, tank on the line, and/or to terminate the gas displacement or discharge into the vent header system.
The potential for adverse concentrations of hydrogen and oxygen in the Haste Gas (HG) System is very loH. A nitrogen overpressure is maintained on the HG headers; therefore, the only source of oxygen in the system during operation is from the Reactor Coolant System (RCS). The RCS is maintained with about 20 cc/kg hydrogen in solution in order to eliminate oxygen. The source of hydrogen in the MG System is the RCS due to letdown evolutions through the makeup tank. When letting doHn coolant, the volume l of the HG System (bleed tanks and vent header) must at least equal the volume of coolant gas letdoHn in order to accommodate the amount of gas l 1etdown. Therefore, in order to exceed 4 percent hydrogen throughout the vent header, assuming 100 percent degassing, RC hydrogen concentration must exceed 40 cc/kg. This analysis does not include consideration of local pockets of gas exceeding 4% hydrogen due to piping configuration.
Normally, the available HG volume for letdoHn gas greatly exceeds the l volume of coolant letdoHn gas. The RCS hydrogen concentration also rarely exceeds 25 cc/kg and is essentially limited by the hydrogen overpressure maintained in the makeup tank (30 psi hydrogen pressure) to less than 30 cc/kg. The vent header concentration is further diluted by the volume of the HG tanks (1125 ft').
The automatic on-line gas analyzer (Hays) at TMI-1 has the capability to sample hydrogen / oxygen at 10 different points in the Haste gas system:
11.2-12 UPDATE-3 7/84 O
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- a. Miscellaneous waste evaporator tank
- b. Miscellaneous waste storage tank
- c. Reactor coolant bleed tanks (3)
- d. Haste gas decay tanks (3)
- e. Reactor coolant evaporator f.. Reactor coolant drain tank This analyzer system is further described in Section 9.2.2.
There are also installed Beckman Ha/02 anlyzers built into a panel with
- manual eleven.(11) point sampling manifold, selectable from the front of the panel. It is a self-contained unit with pressure regulators for the.
high pressure points, sample moisture removal equipment, sampling pump and a recorder to continuously monitor Ha and 0 2, concentrations.
The nen panel is hooked up with the same ten (10) existing sampling points par Hays analyzer, .and one (1) additional point tapped-off from low pressure header.
Since all the piping and equipment are housed in hypothetical aircraft incident proof Class I structures, within cubicles enclosed by concrete 0 shield walls, it is not considered credible that any physical damage could occur to the waste gas system that would release radioactive gases to the environment from any of the components of the waste gas sy3 tem in an uncontrolled manner.
Although such an event is not considered credible, an analysis of the-rupture of a waste gas decay tank is presented in Chapter 14 to demonstrate Enat the results of such an accident are well below the limits of the 10CFR100 guidelines.
All -normal releases of radioactive waste gases from the Hasta Gas Disposal System will be made in a controlled manner, with double monitoring of the release, to assure that annual average activity levels at or beyond the site boundary will be within the limits of 10CFR20.
An analysis was made of waste gas release from the Wasta Gas Disposal System. The analysis assumes a design maximum 90 day holdup period for compressed radioactive gases prior to their release to the environment, that all gas compressed during the year is released (no gas recycled) and averages the release over the year. Assumptions of this analysis are 11.2-13 UPDATE-3 7/84
_ - l
TMI-1/FSAR .
(
presented in Table 11.2-6 and the results of the analysis are summarized in Table 11.2-7.
This analysis indicates that Kr85 is essentially the sole contributor (99.9 percent) to the activity in the Haste gas system's discharge to the unit vent, and that the annual average concentration resulting at the site boundary is 0.00263 MPC for the mixture estimated to be discharged.
A detailed analysis which demonstrates compliance Hith 10CFR50 Appendix I gaseous releases in accordance Hith Reg. Guides 1.109, 1.110, 1.111, and 1.112 is presented in References [19] and (20].
11.2.3 RADIOACTIVE SOLID HASTE DISPOSAL SYSTEM Interim Mobil Solidification System (Hittman System) for packaging radioactive solid and liquid Hastes is located outside of the Auxiliary Building. Filled packages Hill normally be loaded aboard a truck adjacent to the Solidification Building Packaging of Hastes for offsite shipment is in DOT approved containers supplied and transported by a subcontractor licensed for such activity.
Shipping packages are shielded with overpacks if required.
Five general types of Haste are produced, processed, and shipped from THI-1 as solid radioactive Haste. These Hastes are:
- a. Concentrated liquid Haste (evaporator bottoms) O
- b. Used precoat (spent poHdered resin)
- c. Spent resin (bead type)
- d. Dry compactible trash
- e. Dry noncompactible trash Dry trash is shipped offsite directly (i.e., Hithout solidification) following compaction (to reduce the vo1 Lee) where possible. THI-1 has a trash compactor for use With 55 gal drums ded':ated for the exclusive use of the unit. Trash is segregated during colic sn to insure that THI-1 and TMI-2 Hastes remain separate. Appropria.e packaging of dry trash is performed in accordance With applicable shipping and disposal regulations.
11.2-14 UPDATE-3 7/84 9
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b Concentrated liquid waste, and contaainated used precoat and spent resin Hill be solidified prior to being shipped offsite for disposal Where required by TMI-1 Technical ~ Specifications and applicable regulations.
When sclidification is not required for contaminated precoat and spent resin, they Hill be properly deHatered prior to being shipped offsite for disposal. Permanently installed plant equipment does not currently exist to solidify radHaste.
A tHo part program has been initiated to solidify these Hastes. For the-short term, until the permanent system is available, TMI-1 Hill use a contractor supplied mobile solidification system.
11.2.3.1 System Function The function of the Solid Haste Disposal System is to package radioactive solid and concentrated liquid Hastes in such manner as to ensure minimum exposure of unit personnel during the packaging process, produce Haste packages that provide protection for the public during their transportation from the unit to the ultimate disposal site, and meet ultimate disposal requirments for Maste packages.
11.2.3.2 System Description The Solid Haste Disposal System consists of the concentrated Haste storage tanks (WDL-T6-A and B), pumps and associated piping system, the spent resin O (WDL-T-4) and used precoat (WDL-T-5) tanks, and the slurry pump and associated piping system, which are part of the LWDS and are located on the 281-ft elevation of the Auxiliary Building, and the mobile Haste packaging and solidification equipment and controls which are described below. Two piping systems, one from the slurry pump serving the spent resin and used precoat storage tanks and the other from the concentrated Haste pumps, provide for recirculating radioactive slurries or concentrated radioactive evaporator bottoms from the storage tanks through the Haste packaging area and back to the particular source tank.
The mobile solidification system uses cement to solidify all three types of Haste in a preshielded container. The shielding is designed to be sufficient to protect operating personnel for the Horst case of solidifying spent resin. A disposal liner with an internal mixer is used as the solidification container. The ratios of cement, additives (if required),
and Maste that Hill produce a dry product are determined through test solidification in a laboratory in accordance with the Process Control Plan (PCP).
11.2-15 UPDATE-3 7/84
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The quantity of waste to be solidified is pumped into the liner. (Bead resin may be dewatered to reduce the waste volume.) The mixer is starte.d and cement is added. Mixing is continued until the mixer motor current increases indicating the mixture is beginning to set. Following visual and tactile verification of solidification, the liner and cask are closed and shipped.
The solidification process rates are as follows:
Evaporator Bottoms 45 ft'/ day Used Precoat 25 ft'/ day Spent Resin 25 ft'/ day The radwaste production rates are as follows:
Evaporator Bottoms 20 ft /3week Used Precoat <1 ft'/ week Spent Resin <5 ft'/ week The available storage capacity for unsolidified radwaste is as follows:
Evaporator Bottoms 1456 ft' Used Precoat 300 ft' Spent Resin 500 ft' 11.2.3.3 System Storace Capacity Prior to the accident at THI-2, the solid radwaste system installed at 9 THI-1 was shared by both THI-1 and THI-2. The TMI-2 design utilized the THI-1 solid radwaste system to provide for the solidification of the THI-2 waste by transferring all TMI-2 wastes to TMI-1 and by solidifying them at-THI-1. As a result of the isolation / separation requirement of the Order, the THI-1 solid radwaste system will be Completely separated from THI-2.
THI-1 has a trash compactor for use with 55 gallon drums dedicated for the exclusive use of THI-1. Trash is segregated during collection to insure that TMI-1 and TMI-2 wastes remain separate.
The Solid Waste Disposal System also provides capability for spent resin and used precoat to be shipped either solidified with cement or dewatered in licensed shipping casks. If the waste is dewatered, the water is returned to the floor drain system and subsequently to the auxiliary building sump.
11.2-16 UPDATE-3
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' Storage capacity is provided within the liquid Haste system estimated to be O- sufficient to provide the periods indicated below between packaging of the various wastes:
Maximum period between required Tvoe of Haste packaainas of waste Concentrated liquids about 72 Hetks (average)
Sper.t resins about 2 years .
Used precoat filter material about 6 years Based on prior analyses of samples obtained from the Hastes to be packaged and the P'P, the operator determints the approximate maximum quantities of the wastes that may be put in a container.
11.2.3.4 System Storace Capacity Low activity waste (solidified evaporator bottoms, dry trash and other LSA Ndste) Hill be stored in existing space in the THI-1 Auxiliary Building.
Other storage space is available outside the Auxiliary Building, and has the capacity of:
- a. 200,.55-gal drums unshielded (compacted trash)
- b. Spent resin storage - with EPICOR waste This amount of storage would provide storage for up to one month.
Solidified evaporator bottoms and packaged used precoat and spent resin could be stored in the EPICOR II waste staging facility. Fifty five gallon drums and boxes of uncompacted waste will be stored in the Interim Solid Haste Staging Facility. That Facility has the capacity for a minimum of six months of solid Haste storage of material other than evaporator bottoms, used precoat, and spent resin.
11.2.4 OPERATING POLICY ON RADI0 ACTIVE DISCHARGES TO THE ENVIRONMENT The policy for the control of radioactive discharges to the environment from unit is (1) to discharge the minimum quantity of radioactive materials (either liquids or gases) to the environment which is consistent Hith the capability of the equipment provided in the unit, and (2) to meet all the conditions of the operating license and all applicable federal, state, and local regulations. It is expected that during periods of norm 61 operation when all equipment is operable and functioning, the quantities and concentrations of liquid and gaseous activity discharged to the environment Hill be maintained below the limits specified in 10CFR20 as indicated i
11.2-17 UPDATE-3 7/84 1
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herein by the design basis analysis. HoHever, during periods of operation 4 a
WhEn some equipment has failed or is unavoidably out of service and, if a-taking the unit out of service would jeopardize the public power supply in 2 areas served (either directly or indirectly) by Met-Ed, GPUN Hould continue N to operate the unit until it is feasible to take remedial action. Such 4 operation Hill 81 Hays be in aCCordance Hith applicable regulations and 5 Hithin technical specification limitations. 5-y, In implementing the above stated policy with respect to disposal of liquid I Hastes, GPUN has no plans to utilize any specific holdup times in order to 3 take advantage of radioactive decay since the degree of reduction in the [.
activity disch'arged from the unit achieved by radioactive decay is !'
insignificant When Compared Hith that which can be achieved by the )
equipment, which is installed in the Unit for decontaminating the liquid j.
Hastes. This equipment consists of cation and mixed-bed demineralizers, =!
precoat filters, and Haste evaporators, and is so interconnected that M liquid Hastes in any stage of processing may be reprocessed as required to j reduce activity levels and quantities in the effluent from the unit, g Although no credit is taken for radioactive decay of liquid Hastes in the y design basis analyses presented herein, it is anticipated that there Hill be a minimum period of about tHo days betHeen the time a batch of primary 1
coolant is letdown and the time that demineralized distillate (produced 4 from that batch) is discharged into the effluent from the mechanical draft 4 cooling toHers.
{
=l a the design analysis presented herein for the quantities and activity i evels of liquid Hastes to be discharged to the environment (see Table .
11.2-3, Item e.2), credit was taken for only one pass of Reactor Coolant through the cation demineralizer prior to evaporation and subsequent demineralization of the evaporator distillate which is to be discharged to @
the environment. Since the unit is designed to recover and reconcentrate y boric acid from the reactor coolant letdoHn for the purpose of using the e concentrated boric acid produced as makeup to the reactor coolant system, j it is necessary to achieve an average decontamination factor of about 3 200 for the reactor coolant (letdoHn over a core lifetime) prior to 5 evaporation to ensure that the activity level in the reclaimed boric acid 3 does not contribute to buildup of activity in the Reactor Coolant system or 1 offer any significant radiation hazard to operating personnel. The actual i decontamination factor required varies from a minimum of about 60 for letdoHn produced during dilution of the refueling Hater boric acid %
concentration, to 700 for letdoHn produced at the point in core lifetime 1 when resin deboration replaces bleed and feed as the means of adjusting d chemical shim concentration. Therefore, the actual decontamination factor
. to be achieved in the cation demineralizers during normal operation is, :
conservatively, about four times greater than that utilized in the design -~
basis analysis presented herein. J R
11.2-18 d UPDATE-3 4 7/84 5 2
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! Nith respect to the discharge of tritium to the environment, there is no I %
equipment available to remove tritium -from the liquid wastes prior to dilution in the cooling tower effluent.
In implementing the above stated policy With respect to disposal of gaseous Hastes from the radHaste system, GPUN utilizes a combination of hold-up for radioactive decay and filtration through roughing, HEPA and charcoal filters prior to release. For the radioactive Haste gases stored in the waste gas system, a design maximum storage capacity is provided to permit storage of radioactive gases for periods of up to a maximum of 90 days
~during normal operation prior to release to the environment. HoNever, it is anticipated that a minimum holdup time, prior to release, of about two
!- weeks might be ' anticipated during periods when equipment has failed, j malfunctioned, or is unavoidably out of service. For waste gas releases i
during normal operation, the design minimum holdup period prior to release of gas from the Haste gas syst3m is set at 30 days Hith releases prior to 30 days allowed after calculations, according to Reference (23] indicating release Hould be Within 10CFR50 Appendix I limits.
When purging of the Reactor Building atmosphere is required to obtain access, these releases Hill be made through roughing and HEPA filters for removal of particulates and charcoal filters for the removal of iodine.
With regard to the capability of the equipment provided in the unit to 4
maintain the radioative Maste releases to the environment to values as low
- as achievable. The design basis analysis presented herein (in which i activity levels associated with 1 percent failed fuel are postulated) i indicates that the annual average mixed, identified fission product (cther 4
than tritium) concentration activity is at 1/12,500 of its 10CFR20 MFC level and is 0.015 times the 10CFR20 MPC level for tritium in the mechanical draft cooling tower effluent released to the river and that the
- waste ' gases released to the atmosphere through plant vent achieve 1/380 of their 10CFR20' MPC level at the site boundary on an average basis.
, Therefore, the equipment provided is capable of achieving environmental activity levels substantially below applicable 10CFR20 MP3 values for all radioactive wastes even under conservativa assumptions of activity release from the fuel and equipment decontamination capability. Further, redundant ,
, equipment is provided for all phases of liquid Haste processing so that
! loss of cleanup capability due to equipment failure is unlikely.
References (19] and (20] demonstrate compliance with 10CFR50 Appendix I i
requirements for liquid and gaseous releases. Potential pathways for releases and subsequent doses to population are also analyzed in References
- [19] and (20].
l I
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! UPDATE-3 4
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Section 11.2.5 presents analysis of the activity concentration in the Susquehanna River doHnstream of che plant for the design basis (activity levels in reactor coolant associated with 1 percent failed fuel) case.
11.2.5 DILUTION FACTORS IN SUSQUEHANNA RIVER Three Mile Island is located between two channels near the east bank of the Susquehanna River in a section of the river which is oriented in a north-south direction (refer to Figure 2.2 1). The river floH in this area is from north to south. The unit is icuated near the north end of the island and the effluent from the mechanical draft cooling towers (which has been mixed with the radioactive liquid Hat te) discharges into the Hest Channel off the island about 1500 ft doHnstream of the unit. A section of the York Haven Dam blocks the east channel off the island (refer to the upper right hand quadrant of Figure 2.1-3) approximately one mile downstream of the unit. The remainder of the York Haven Dam extends in a south southeasterly direction from the southern dip of Three Mile Island to the West bank of the Susquehanna River, where the York Haven Hydro Plant is located. At this point, the Hest bank of the river lies east of the unit.
The head race of the York Haven plant extends about 3000 ft upstream of the plant and, as long as the river floH is about 20,000 cfs or less, all the river flow discharges through the York Haven Hydro Plant tail race into the loHer section of the Conewago Falls. When the river flow is above 20,000 cfs, the excess floH discharges across the portion of the dam downstream of the head race and floHs doHn through the ConeHago Falls, joining the tail
_ race at the foot of the dam Hith the full flow then continuing through the q lower sections of the falls. Therefore, regardless of river flow, there Hill be Complete mixing of the full river water floH Hith the effluent from the mechanical draft toHers below the York Haven Hydro Plant.
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During periods of low to average river Water flow, the Hater is nearly stagnant in the portion of the river between the point of cooling tower effluent discharge to the river and the York Haven Hydro Plant such that there is, in effect, slug flow. Therefore, for this section of the river the only dilution which Hill be considered is that Hhich occurs at the cooling toHer effluent outfall, Hhere one volume of Cooling toHer effluent is assumed to mix Hith one volume of previously unmixed river Water.
Thereafter, an approximately 250 ft Hide band (maximum) of mixed river pater and cooling tower effluent is assumed to floH doHn the west bank of the island and the upstream face of the dam and into the head race. As this band approaches the juncture of the island with the dam, it Hill start to narrow, or neck doHn, because of the reduced cross-sectional ficH area available in the river at this point. The width of the band Hill continue to decrease until it enters the head race (which has a relatively uniform flow area throughout its length), where it Hill occupy the eastern one-11.2-20 UPDATE-3 7/84 e
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l THI-1/FSAR l third to one-half of the head race. If the river flow is above 20,000 cfs, T part or most of this band of water will flow over the dam into Conowego Falls before reaching the head race depending on the excess of river flow above 20,000 cfs. As a result, the dilution factor for the cooling tower effluent shall be considered as two for the entire section of, the river described immediately above.
The criteria for radioactive releases from the unit that establish the maximum activity level in the downstream Susquehanna are: (1) that the cooling tower effluent cannot exceed MPC level while being discharged to the river, and (2) that dilution credit will be taken for as much as 38,000 gpm of cooling tower effluent. The criterion that establishes the maximum activity level in the downstream Susquehanna is that radioactive liquids will not be discharged to the river when the cooling tower effluent flow rate is below 5000 gpm.
The river flow rates, which will be considered in this analysis to establish maximum and minimum activity levels in the two applicable sections of the downstream Susquehanna, are: (1) 1700 cfs (765,000 gpm) which is the minimum daily river flow rate recorded, and (2) 34,000 cfs (15,300,000 gpm) which is the annual average river flow rate.
Since batch releases of radioactive liquid wastes from the unit will be made at flow rates between 5 and 30 gpm, the capacity of an evaporator condensate storage tank (7500 gal) sets the maximum and minimum duration of batch radioactive liquid releases.
The maximum frequency of discharge of batches of radioactive liquid waste to the river is determined by the maximum quantity of radwaste liquids estimated to be produced in2 the plant per year. This is indicated in i Table 11.1-3 to be 135,000 ft or approximately 1,000,000 gal per year.
This is equivalent to 135 seventy-five-hundred-gallon batches per year or one batch disposed approxinately every two-and-a-half days. However, the average activity level in this 1,000,000 gal per year would be approximately one-sixth of that indicated in Table 11.2-4 since the design i basis quantity of activit is contained in the 135,000 ft' of liquid l
instead of in the 23,500 ft'yof design basis letdown. This also represents the minimum design basis activity level in the batches of radioactive j liquid waste disposed to the river and is more nearly representative of the activity level normally present in the evaporator condensate storage tanks I since these collect condensate from the evaporation of both reactor coolant l and miscellaneous liquid wastes.
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Table 11.2-8 presents an isotopic breakdoHn of the activity levels and fractions of MPC to be anticipated in the evaporator condensate storage tanks Hhen the annual design basis quantity of activity is mixed With 23,500 ft3 and Hith 135,00 ft of Hater. The mixed isotope and tritium h'
activity levels and fractions of MPC are utilized in Table 11.2-8 to calculate the activity levels cnd fractions of MPC for these tHo constituents in the cooling tower effluent, the river betHeen the point at Hhich cooling tower effluent discharges into it, and at the tail race of the York Haven Hydro Plant (" upstream river" in Table 11.2-9) and the river downstream of the York Haven Hydro Plant tail race ("doHnstream river" in Table 11.2-9) as functior.s of cooling toHer effluent to liquid Haste dilution ratios, section of the river, and river flow rates.
The cooling toHer effluent (CTE) dilution of the liquid Haste (LH) Can vary from a maximum of 7600 (38,000 gpm CTE to 5 gpm LH) to a minimum of 167 .
(5000 gpm CTE to 30 gpm LW). HoHever, Table 11.2-9 analyzes only those dilution ratios which Hould result in the cooling toHer effluent entering the river at MPC level, or below, per the administrative limits for liquid Haste disposal indicated above.
From Table 11.2-9, it is apparent that tritium may be the limiting isotope
- ince its fraction of MPC is appreciably greater than that of the mixed isotopes in all cases. For all cases of cooling toHer effluent to liquid Haste dilution ratios studied, the mixed isotopes in the cooling tower effluent flowing into the river Here considerably below their MPC level.
Thus, on the desis n basis case studied, mixed isotopes are insignificant relative to tritium. This occurs because there are no practical methods of removing tritium from the reactor coolant letdoHn into the liquid radHaste system.
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- g. Reactor Building Purge Exhaust: Channel RM-A9
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The activity of the air discharged in the unit vent When purging the Reactor Building is meaJured by a PIG type affluent monitoring system.
Should its preset level be exceeded, the monitor Will initiate closure of the purge valve. The monitoring range is the same as RM-A1.
The radiation monitors RM-A8 and RM-A9 take a continuous sample of air from the Auxiliary and Fuel Handling Buildings' concrete ventilation exhaust duct located against but outside the Auxiliary Building.
This sample W'thdrawal location meets the requirements of ANSI 13.1 (1969).
A building housing the monitors is located on top of the exhaust duct abutting the Auxiliary Building. Concrete Halls and roof provide radiation shielding from external sources.
The ambient temperature is thermostatically controlled in the building housing the monitors, between 65'F and 90"F and the background radiation is less than 100 mR/hr at time zero of the accident. The ambient temperature of the building is bounded by a temperature range of 70 to 110 8F. To prevent co.densation during sampling, an alarm will sound in the control Room if the building temperature drops below a predetermined set point of
. 65'F. To prevent overheating of the radiation monitor ele.ctronics, an alarm Hill sound if the building temperature reaches 90'F.
Extended ranges for postaccident monitoring are described in Subsection 11.4.5.
- h. Radiochemical Laboratory Monitor: Channel RM-A12 and Spent Fuel Area Monitor: Channel RM-A13 These tHo Channels are movable cart mounted PIG type monitors which will be used for in-plant air monitoring of particular plant areas during sampling and/or refueling. Their ranges are the same as those of channel RM-A1.
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Sample panels are provided on air monitor stations RM-A2, AS, A7, A8, and A9 to divert sample air to the panel for surveillance testing.
11.4.4 LIGUID MONITORING SUBSYSTEM DESCRIPTION The liquid monitoring subsystem performs the following basic functions:
l effluent monitoring, leak detection, and monitoring of the Reactor Coolant i System activity.
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G THI-1/PSAR The liquid monitoring subsystem consists of tHelva liquid monitors, tan of l Which are operating. Four of these monitors (RM-L2, RM-L3, RM-L4, and RM-L9) are used for leak detection of closed cooling loops which act as barriers against release of activity to the river. These four monitors have identical scale, sensitivity and range data. The 7scales are 10-10' cpm. The sensitivities in response to Cs-137 are 7.16x10 cpm /uci/ml. The ranges are 1.4x10~7 to 1.4x10-a UCi/ml.
RM-L5 is part of leak detection monitoring and consists of a GM tube monitor designed to detect changes in the radioactivity concentrations of the spent fuel pool Heter, Which may indicate the presence of a leaking fuel element. The scale is 10-10' cpm. The sensitivity in response to Cs-137 is 2.2x10+ cpm /uci/ml. The range is 4.5x10" to 45 uCi/ml.
The primary coolant letdoHn, after passing through a delay line, is monitored by RM-L1, Which is equipped Hith one gamma radiation scintillation loH range detector and one GM Tube gamma high range detector. Both detectors have scales of 10-10' cpm. The loH range detector 8
sensitivity in response to Cs-137 is 1.27x10 cpm /uci/ml. The loH detector range is 7.9x10-2 to 787 uCi/ml. The high range detector sensitivity is 22.2 cpm /uci/ml. The high detector range is 4.5x10~1 to 4x10' uCi/ml. Since the ranges of the tHo detectors overlap, they provide redundant measurement of the gross gamma activity resulting from defective fuel from a fractional percent to greater than 1%.
The liquid effluent moniter RM-L6 monitors 5 the radioactive Haste water discharge. The RM-L6 monitor has a 10-10 scale and a Cs-137 response sensitivity of 7.16x10 7 cpm /uci/ml. The range is 1.4x10~7 to 1.4x10-a UCi/ml.
RM-L6 is located prior to the postcooling tower discharge dilution point.
Should its preset level be reached, it Hill initiate Closing of its related liquid Haste discharge valve. RM-L8 is not in service but could be used if required.
Channel RM-L7 monitors the plant effluent discharge to the river and is a backup for RM-L6 and RM-L12, its scale is 10-10' cpm and its response
. sensitivity is 7.16x10 7 cpm /uci/ml for Cs-137. Its range is 1.4x10-7 to 1.4x10-a uCi/ml. i RM-L10 is a submersible scintillation detector located in the turbine building sump. This monitor is used to monitor Hater routed into the turbine building sump prior to its being pumped to the INTS. i The range of this monitor is 10-10' counts per second. The sensitivity of this monitor when operating on the I-131 HindcH is 1.8E9 cpm /uci/ml. The i
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THI-1/FSAR sensitivity of this monitor When operating on the Cs-137 HindoH is 1.0E9
.cpa/uci/ml.
.RM-L11 is a submersible scintillation detector located in the Powdex sump.
l This monitor is used to determine When radiological cleanup of the powdex backHash Heter is required. The range of this monitor is10-105 counts per second. The sensitivity of this monitor Hhen operating on the I-131 Window is 1.8E9 cpavuCi/al. The sensitivity of this monitor When operating on the Cs-137 WindoH is 1.0E9 cpavuCi/ml. RM-L11 is not currentiv installed but could be restored to service if required.
RM-L12 is a gamma scintillation detector on the discharge of the Industrial
. Haste Treatment System (INTS) and Industrial Haste Filter System (IHFS) before affluent is diluted by the flow from the cooling towers. This monitor is especially designed and calibrated to insure that concentrations of isotopes in all liquid effluents, except water monitored by RM-L6, do not exceed the limits in 10CFR20, Appendix B, Table II Column 2. Its scale is 10-10' cpm. Its sensitivity to I-131 when centered at i 25% of the I-131 8
energy peak is 1.5x10 cpm /uCi/ml and its corresponding I-131 range is t 6.7x10*' to 6.7x10-3 uCi/nl. Its sensitivity to Cs-137 when centered at
!
- 25% of the Cs-137 energy peak is 6.5x10 7 cpm /uci/ml and its corresponding Cs-137 range is 6x10-8 UCi/ml to 6x10~3 uCi/ml. When its high radiation set point is exceeded, it will terminate both the IWTS and IWFS discharge to the river.
. O composite proportional to flow samplers are installed on the turbine building sump discharge, the pcudex sump discharge and the discharge to the Susquehanna River near RM-L7. Piping and centrol valves are provided to alloH flushing of radiation monitor RM-L6 following a discharge of the WECST.
Monitor samplers have removable liners to facilitate decontamination. The exception is RM-L10 Nhich is submerged directly in the turbine sump Hater.
11.4.5 POSTACCIDENT RADIATION MONITORING l The postaccident radiation instrumentation, in conformance With Hureg 0578 and 0737, consists of the following:
Instrumentation in Items a. through c. is described in Chapter 7.
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- a. High-Range Effluent Monitors-The Auxiliary Building, the Fuel Handling Building, and the Reactor Building ventilation exhausts, the discharges from the condenser vacuum pumps, and OTSG safety valves and atmospheric dump are considered as potential significant effluent paths. Therefore, extended range monitors are provided to assure monitoring and readout capability for postulated accidents.
The purpose of the high range monitors is to provide extended ranges to radiation monitors RM-AS, RM-AB, and RM-A9, and to provide additional monitoring capability and include radiation monitors RM-G24, RM-G25, RM-G26, and RM-G27. Included are three additional sampling stations, one for the Auxiliary and Fuel Handling Building ventilation exhaust, one for the Reactor Building ventilation exhaust, and one- for the condenser vacuum pump exhaust. The monitors and their locations are listed on Table 11.4-1.
A GM detector for extended range gas monitorir.g of the Auxiliary and Fuel Handling Building ventilation exhaust is provided in the cabinet of radiation monitor RM-A8. The detector has a scale of 10-10' cpm, a sensitivity in response to Xe-133 of 1.08E3 cpm /uci/cc and a corresponding range from 9x10- to 925 uCi/cc. The detector is mounted in the RM-A8G Channel Lead Pig to meritor the sample lines inside RM-A8's cabinet. A readout module tagged RM-A8G High is located in the Control doom Hith a local panel meter provided on the cabinet.
A GM da?uctor for extended range gas monitoring of the Reacter Building Purge ventilation exhaust is provided in the cabinet of radiation monitor RM-A9. The detector has a scale of 10-10' cpm, a sensitivity of 2.64E3 cpm /uci/cc and a corresponding range of 3.8x10'3 to 378 uCi/cc. The detector is mounted in the RM-A9G Channel Lead Pig to monitor the sample lines inside E'i-A9 's cabinet. A readout module tagged RM-A9G High is located in the Control Room Hith a local panel meter provided on the cabinet.
An ionization chamber is provided for extended range gas monitoring of the Reactor Building exhaust and has a scale of 0.1 to 107 MR/hr, a sensitivity to Kr-8pof9.7HR/hr/uci/ccandacorrespondingrangeof 1x10~2 uCi/cc to 1X10 pCi/cc. The upper range covers the expected concentration for the postulated Horst case acc.ident concentrations. A readout module tagged RM-G24 is located in the Control Room.
A GM detector for extended range gas monitoring of the condenser vacuum pump discharge is provided in the shield of radiation menitor RM-A5.
The detector has a scale of 10 to 10' cpm, a sensitivity of 4.74E3 11.4-8 UPDATE-3 7/84
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( cp /uci/cc in response to Xe 182 and a corresponding rangs'of 2x10-' -to 210 uCi/cc. Although it measures the noble gas from the same sample chamber as AM-A5 LO, it has a thin lead partition between the RM-A5 LO l gas chamber to attenuate it to tl.a proper high range. A readout module
' tagged RM-A5 High is located in the Control Roon Nith a local panel meter provided on a NDIA 4 enclosure in the vicinity of RM-A5's sample 1 l chamber. Also, an ionization chamber is provided for further extended; l range monitoring the condenser vacuum pump discharge. The detector has )
7 a scale of 0.1 to 10 mR/hr and a sensitivity of 'J5.2 mR/hr/uci/cc .in ,
response to Xe 13' with a corresponding range of 3x10 uCi/cc to i 2.84x10 5 uCi/cc. Its sensitivity in resnonse to Kr-85 is 1.48
! mR/hr/uCi/cc with a corresponding range of 6.8x10-a to 6.8x10' UCi/cc. ,
- It is presently set to alarm in response to Xe 183 .A readout. module l tagged RM-G25 is located in the Control Room.
Two scintillation detectors are provided for gas monitoring of steam line effluent A and B OTSG safety valves and atmospheric dump associated with the main steam lites. The range of the monitors is 1x10-a to 1x10*' UCi/cc for Xe133 The r.3nitors provide detection of significant releases and provide information for release assessment.
Readout modules are provided in the Control Room, one tagged RM-G26 and the cther tagged RM-G27, with a panel indicator provided in the area of the detectors in a HDfA 4 enclosure.
Although the instrumentation of item a. does not actuate safety equipment, nor is it required by safety analyses, it is appropriate to l O provide surveillance requirements to assure reliable postaccident performance of the instrumentation.
j The equipment of item a. is designed for postaccident environment i usage; however, the equipment is not redundant, nor protected from casualty events. The equipment of item a. is seismically supported but is not seismically qualified.
- b. High-Range Containment Radiation Monitor
- 1) Design Description l
Two high-range radiation monitoring channels RM-G22 and RM-G23 are l provided to monitor containment radiation levels during and following a postulated accident. Radiation levels are continuously indicated, recorded, and alarr.2d should the radiation level exceed a predetermined set point.
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- 2) Detailed System Description Two icnization chamber radiation monitors arc mounted inside the Reactor Building on the secondary shald Hall above elevation 346 ft 0 in.
7 The detectors have a range of 1 R/hr to 10 R/hr. These detectors are constructed of hermetically sealed, stainless steel outer surfaces and are ion chamber detectors containing no active electronics. The detector Halls are strong enough to withstand LOCA pressures, but thin enough to provide full response to Xe 133 (80-kev energy level) and to be able to measure down to 60 kev i gamma photons. The detectors are hermetically sealed, parallel plate, three terminal, guarded ionization chambers, operated in the saturation mode. All external surfaces are 316 stainless steel. The mounting brackets of the same esterial are integral to the housing. Electrical connections are brought out through two Helded connectors. Mineral oxide insulated cable is used between the detector and the electrical penetrations.
The electrical installation is designated Nuclear Safety-Related to include the detectors and their associated electrical cabling up to, but not including, the Main Control Room vertical panel PRF. The readout consists of two readout modules. These readouts present a seven-decade logarithmic range across a 4 inch l meter. Each readout contains its own independent power supply and dual independent radiation alarms. The alarm set point is l adjustable over the full scale range and is verified by periodic l checks. The alarm circuits actuate local panel indicating lights l and relays for external annunciators.
The system automatically initiates a self-check to assure the integrity of the electrode configuration and electrical operation of the detector / cable / readout system. A successful check (no equipment fault) turns on a front panel indicator light Hhich remains on until a fault is detected, thereby providing fail-safe indication of proper operation of the system. An equipment fault initiates an alarm.
For manual tests, a test button on the readout panel injects a signal level which approximates one-third *of full scale signal.
This tests all alarm lights and relays and allows test-check of all phases of the system.
Depressing the radiation alarm indicator light causes the meter to indicate the alarm set point.
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THI-1/FSAR The outputs of the high rans,e radiation monitors are continuously recorded in the vertical PRF panel.
The containment. high radiation menitoring system is designed for continuous operation in all plant operating modes and abnormal !
accident conditions.
l The containment high radiation monitor _ system is a completely l independent system and interfaces With no other system, except for. {
.its source of power, the PRF vertical panel, and the plant ;
annunciator system.
Calibration and frequency of calibration are provided in accordance with plant procedures.
The high radiation emergency evacuation alarm system is described in Section 11.5.4.
11.4.6 RADIOLOGICAL SAMPLING
.A description of the sampling system is provided in Section 9.2.2.
Radiological sampling associated with the Radiation Monitoring System is described as follows:
Postaccident analysis of reactor coolant samples and the containment
.- atmosphere is recognized as a means to better define core damage and anticipate. the need for remedial actions. TMI-1 capabilities for postaccident sampling are provided to cbtain key sample results within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> of directing that a sample be taken.
The key parameters to be determined include containment atmosphere,.
containment hydrogen concentratica, and reactor coolant boron concentration and gross beta / gamma activity. The on-line hydrogen monitoring capability is described in Cnapter 6.
A Reactor Building atmosphere sampling station is provided at the Reactor Building atmosphere radiation monitor RM-A2 station. Radiation monitor.RM-A2 sample line includes a three-way ball valve to divert samples to the postaccident sampling system. The sampling system provides samples for radiological and hydrogen analysis of the Reactor Building atmosphere, from which an indication of the extent of core damage could be obtained. -The postaccident sampling system is capable of providing a sample of Reactor Building atmosphere following an accident coincident with a loss of offsite
-pOHer and Hith limited personnel exposure. The sampling system is located 1Jn\ a postaccident, accessible area, the Reactor Building atmosphere
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THI-1/FSAR radiation monitor RM-A2 is in the Intermediate Building. Sample station location Hill alloH for obtaining a sample Within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />, of directing that a sample be taken. Only the amount of Reactor Building gaseous atmosphere required for the analysis Hill be transported Shay from the sampling station. The existing shielding Hill provide the reduction of radiation levels such that any individual in this area Hill not be exposed to more than 5 rem to the Hhole body and 75 rem to the extremities.
Samples of the Reactor Building atmosphere are drawn by an eductor.
Once flow has been established from the local control panel, a sample is Withdrawn from the sample station through a septum using a syringe. After sampling it is transported to the chemistry lab for analysis. To minimize condensation in the sample line, heat tracing is applied. The unused portion of a sample Hill be disposed of, at the sampling station, by sending it back into the containment. The system design Hill limit containment air loss from a rupture of the sample lines by utilizing passive flow restrictions. Pressure protection is provided to prevent exceeding the rating of the sampling devices. Valves located in high radiation areas, postaccident, are provided Hith remote operators.
All lines are capable of being flushed with either instrument air or compressed air / gas from bottles. The RM-A2 sample line and containment isolation valves are capable of being operated with bottle air sources in the event the instrument air system is inoperable.
The high-range effluent radiciodine and particulate sampling analysis is provided by a sampling system that includes silver zeolite cartridges. The system design and operation both decrease the activity on the cartridges so they can be handled and decrease the xenon to iodine ratio. Counting of the cartridges is by use of NaI crystal connected to a single or dual channel analyzer Hith appropriate HindoH and discrimination settings for the 364-kev gamma of I-131, or by use of a GeLi/MCA system. The postaccident portion of the sampling system would be placed in service following an accident and is located in an area exhibiting low background.
Procedures are provided for the use of silver zeolite cartridges and normal particulate filters for sampling with an Ha7 detector and a single or dual channel analyzer for iodine and gross particulate release rate determination. Specific details to insure exposures are maintained as low as reasonably achievable are incorporated into the procedures.
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THI-1/FSAR Three processor-controlled iodine and particulate sampling stations are provided and'alloH a sample to be obtained independent of radiation monitors RM-A5, RM-A8, and RM-A9. The stations are processer-controlled solenoid valves Hith a valve in one or more of the three parallel filter cartridges provided in each station. The sampling times for each filter cartridge are adjustable and provided on each local control panel as part of the sampling station. The filter cartridges must be manually removed and analyzed elseHhere. Each station provides iodine and particulata samples of high and low radiation level. Two of the stations are located adjacent to the Auxiliary Building and located on top of the concrete exhaust duct of the Auxiliary and Fuel Handling Building ventilationi exhaust duct. Of these tHo stations, one samples the Auxiliary Building ventilation exhaust and the other the Reactor Building ventilation exhaust.
The third station is associated Nith radiation monitor RM-A5 and provides samples of the condenser vacuum pump discharge.
The sampling stations are normally idle. Upon receipt of a high radiation signal from RM-A8G, the Auxiliary and Fuel Handling Building vent monitor MAP-5 sampling station is initiated. Upon receipt of a high rediation signal from RM-A9G, the reactor building exhaust monitor MAP-5 sampling station is initiated. Upon receipt of a high radiation signal from RM-A5G, the condenser vacuum pump discharge monitor MAP-5 sampling station is initiated. An annunciator alarm is provided in the Control Room Hhen the sampling station vacuum pump for either the RM-A8 or RM-A9 MAP-5 sampler fails to start after a predetermined interval. The RM-O A5 associated MAP-5 sampler does not require any sample vacuum pump since it draHs its sample from the discharge side of the main condenser vacuum pump header and returns it to the suction side of the pumps.
For the sampling stations, three sampling cartridges are installed in 4
parallel and, by using sequenced solenoid valves, the sample floH through each filter cartridge is established.
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,, TMI-1/FSAR TABLE 11.2-2 (Sheet 1 of 2) 0 EQUIPMENT IN PRIMARY COOLANT AND MISCELLANEDUS WASTE TRAINS Primary Coolant Train Miscellaneous Waste Train WDL-T-1A, 1B and 1C Reactor coolant Reactor and Auxiliary Building I bleed tanks sumps WDL-T-3 Reactor coolant drain tank WDL-T-2 Misc. Haste storage tank WDL-C-1 Reactor coolant drain tank WDL-P-7A and 7B Misc. Haste heat exchanger transfer pumpe HDL-P-8 Reactor coolant. drain tank Pump WDL-P-16 Reactor drain pump WDL-P-15 Laundry Haste pump
- WDL-P-6A, 6B and 6C Waste HDL-T-8 Neutralizer mixing tank transfer pumps WDL-K-1A and 1B Deborating HDL-T-9 Neutralizer feed tank demineralizers
. HDL-F-1A and 1B Precoat filters WDL-T-10 Neutralized Haste storage tank WDL-K-2A and 2B Cation WDL-P-9A and 9B Neutralizer demineralizers pumps WDL-Z-1A Reactor coolant Haste HDL-Z1B Miscellaneous Haste evaporator evaporator WDL-T-7A and 7B Reclaimed WDL-T-6A and 6B Concentrated f
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