ML20206L507
| ML20206L507 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 08/19/1986 |
| From: | OMAHA PUBLIC POWER DISTRICT |
| To: | |
| Shared Package | |
| ML20206L499 | List: |
| References | |
| GL-84-13, TAC-62173, NUDOCS 8608200211 | |
| Download: ML20206L507 (25) | |
Text
{{#Wiki_filter:.o. 4 .o. 2.0 LIMITING CONDITIONS FOR OPERATION 2.18 Shock Suppressors (Snubbers) Applicability
-This-specification-applies-to-safety-related-shock-suppressors-(snubbere-) r-Operating Modes 1, 2 and 3 (. operating Modes 4 and 5 for snubbers located on systems required operable in those Operating Modes).
-Objective-
-The-objective is-to-specify-modes-of-reactor-operation-for-given-condit4cns-
-of-safety-related-snubbers,--
Specifications coolant and o4 Lee sesty re\sie' re .deci red fe prefecd sys tem s N reactor <
/
(1) All snubbers listed-in-Table-2-6(al-and-(b-)- shall be operable except as noted in 2.18(2) through 2.18(h) below. These swMers sWi be
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D.icaN C.J e safety - re lated so se b b e rs. (2) With one or moregsnubbers inoperable, within 72 hours replace or Saf**y-relatsd' restore the inoperable snubber (s) to operable status and perform an engineering evaluation per Specification 3.1k(.3) on the supported component or declare the supported system inoperable and follow the appropriate actions specified in the Technical Specifications for that system.
, - safc+y - r=1 tcd (3) AY snubber may be removed for surveillance in accordance with d,
(. Section 3.14(3) of these Technical Specifications, provided the following conditions are met: 1 (a) A given snubber station shall not be without an operable snubber for more than two hours during surveillance of attendant snubber. A snubber may be replaced by an operable snubber during surveillance and repair. (b) No other snubber station,u ontaining-snubbers-1-isrted-4n-Table-2-6(a-)-and-{b-)y. is known to be inoperable. (c) Only one snubber station,<.-oontaining-snubbers-listed- '
-in-Table-2-6(a)-and-(b).# shall be removed for test-ing at a time to ensure that no two snubber stations are without an operable snubber during the same time interval.
g.fety - rel.t 4 (h) Y Snubbers may be added, changed, or deleted from-Table 2-6(a)-and-(b)-vithout-prior-licensing-amendments- provided an accepted-engineering analysis justifies each change. -Deletions-vil-1-be-
.allowe d-only-af t e r-an-inde pende nt-revi ev-o f-t he-en gine e r i ng-d us t i fic a t ion-i s-pe r fo rmed- and-t he-dele t i ons -are-app roved-by-SARC .
Any-revisions-to-Table-2-6(a)-and-(b)-vill-be included in-
-sub s eque nt -lic en s ing- ame ndme nt -reque s t s .
AmendmentNo.27,;(B,$) 2-73 8608000211 860919 PDR P ADOCK 05000285 PDR (1C I'llO lh 4
J 2.0 LIMITING CONDITIONS FOR OPERATION 2.18 Shock Sucoressors (Snubbers) Basis Snubbers are designed to prevent unrestrained pipe motion under dynamic loads as might occur during an earthquake or severe transient, while allowing normal thermal motion during startup or shutdown. The conse-
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j quence of an inoperable snubber is an increase in the probability of structural damage to piping as a result of a seismic, or other event, initiating dynamic loads. It is therefore required that all snubbers required to protect the primary coolant system or any other safety system or component be operable during reactor operation. Because the snubber protection is required only during low probability events, an inoperable period of 72 hours is allowed for repairs or l- rep.lacements and an inoperable period of two hours is allowed for surveillance. (~ ble 2-6(a) and (b) lists the snubbers that are on safety-relate I systeD The snubbers that are inside of the containment,btf1'iding are listed 'as ' Inaccessible During Normal Operation" and wouTd require a ' j significant expl.nditure in man-rems to inspect orva periodic basis. RevisionsmaybemalescoTable2-6(a)and(Jbtithout prior notice McIEC provided that an engineering analysis justifies the changes. Those snubbers listed as "Di Remove for Functional Testing" are so listed because they are'either:
- 1) rated at greater 50,000 lbs. force,
./(2) ( inaccessible'due to surrounding structures, or j
((3) located'such that an excessive amount of time and erfort wo [d be required to remove them for testing. a l
- Amendment No. 27,43,39,/d 2-74
, e TABLE 2-6(a)
( ACCESSIBILITY OF SAFETY-RELATED SYSTEM HYDRAULIC SNUBBERS Located Accessible In High Difficult to During Inaccessible Radiation Re' move for
- Snubber Normal During Normal Areas During / unctional f
Operation Operation Shutdown / Testing No. Elevation
" X ACS-18 996 ..
" X X ACS-112 1040' X 1040' 0" X ACS-113 X 1040' 0" X ACS-113A 1031' 4" X ACS-116 ACS-117 1031' 4" X 1031' 4" X ACS-118 ACS-121 1031' 4" X '
1031' 4" X ACS-123 X 1040' 0" X ACS-127A X 1040' 0" X ACS-128 1056' 4-11/16'\ X ACS-299 1056' 6" X ACS-299A l 1056' 4-11/16" X , ACS-302 ACS-304 1056' 4-11/16" X p_, e_T 6 C 1056' 4-11/16" X ACS-305 ( ACS-306 ACS-307 ACS-313 1056' 4-11/16" 1056' 4-11/16" 1054' 11" X X g l ACS-384 1000' 6" X ACS-385 987' 5-1/4" X ACS-386A 1020' 0" ACS-386B 1020' 0" % 1011' 0" X ACS-406 1011' 0" X ACS-407 AW-60 1007' 6" 7. AW-65 1002' 10" X WS-1 X Top 1038' 6" X WS-1 X Bottom 1038' 6') x X X WS-1 A 1033'76" X 1033' 5-1/2" X WS-18 X 1033' 5-1/2" X WS-1C WS-2 X X Top / 038' 6" WS-2 / 1038' 6" X X Bottom , Amendment No. 27, 77, 72 2-75 .
**s
TABLE 2-6 (a) ,j ' (Centinu d) l Located */ Accessible In High Difficult to During Inaccessible Radiation Removejfor C)CSnubber Normal During Normal Areas During' Functional N,. levation Operation Operation Shutdown Testing FWS-2A 10 8' 6" X X FWS-2B 1038' 5\" X X FWS-2C 1038' \" X X FWS-3B-North 1038' 5\" X , FWS-3B-S:uth 1033' 6" X FWS-7D-N2rth 1038' 6" X FWS-7D-S:uth 1038' 6" X FWS-28 1002' 6" X FWS-29A 1002' 6" X FWS-30 1002' 6" X
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FWS-32 1005' 1" X FWS-32A 1005' 1" X i ~ I e lR. IC Q ( FWS-33 1001' 6" X FWS-34 1001' 6" X FWS-35 1005' 5" X FWS-36 1005' 5" X FWS-37 1005' 5" X FWS-38 1010' 0" X FWS-39 1012' 1 " X FWS-64 1043' 0" FWS-64A 1041' 0" X <l' FWS-64B 1041' 0" X FWS-65 1049' 6" - X FWS-66 1049' 6" X FWS-67 1049' 6' X FWS-68 1049' X FWS-68A 1049 6" X EVS-69 1[9'6" X FWS-71 037' 6" X Amendment No. h.7, 59 2-76
#4
- - . - - - - , , , ., - - , - - , , , . , , , - , -. , - - - , - - ~ , - - . - - - - - . -
i.* . 1 TABLE 2-6(a) (Continued) Located Accessible In High Difficult to During Inaccessible Radiation Remove for
- Snubber Normal During Normal Areas During Functional No. \ Elevation Operation Operation Shutdown Testing FWS-74 053' 0" X FWS-75A (1053' 0" X -
FWS-78 1038' 4" X FWS-79 1049\ 6" X FWS-80 1049' (" X FWS-81 1049' 6 X FWS-83 1033' 4" X FWS-86A 999' 0" X FWS-87 999' 0" X FWS-88 999' 0" X FWS-88A 999' 0" X FWS-89 1002' 6" X FWS-90 1001' 6" X FWS-90A 1005' 6-5/8" X FWS-91 1019' 0" FWS-92 1019' 0" FWS-92A 1026' 0" X ( FWS-93 FWS-94 FWS-95 1032' 0" 1032' C" 1032' 0" X X X glgfgd FWS-96 1032' 0" X FWS-97 1032' 0" X[- X X FWS-98 1032' 0" X X FWS-100 1039' 0" X FWS-101 1039' 0" X HCV-327-S 1025' 0" X llCV-329-S 1025' 0" X HCV-331-S 1025' 0" X HCV-333-S 1025' 0" X MSS-1 1054' 7" X X MSS-2 1054' 8-1/ " X X MSS-3 1038' 0" X MSS-4 Top 1038' 6" X X L Amendment No. 21, 77, 72, 79 2-77 e
o
- l TABLE 2-6(a)
(Continued) Located Accessible In High Difficult to During Inaccessible Radiation Re' move for
- Snubber Normal During Normal Areas During unctional No. \ Elevation Operation Operation Shutdown . Testing MSS-4 Bottom 1 38' 6" X X MSS-5 1054' 7" X X MSS-6 1054'N 81"3" X X MSS-7 1038' X X MSS-8 Top 1038' 6" X X MSS-8 Bottom 1038' 6" X X MSS-8A 1038' 6" X X MSS-8B 1038' 6" X X MSS-8C 1038' 6" X X MSS-8D 1038' 6" X X MSS-9 1040' 7" X MSS-9A 1040' 7" MSS-9B-North 1033' 6" X '
MSS-9B- e_ ,e.hC.O South 1033' 6" X MSS-13 1040' 7" X MSS-13A-East 1040' 0" MSS-13A- X[ West 1040' 0" X MSS-13B-North 1038' 6" X MSS-13B-South 1038' 6" X RCP-Al 1016' 0" X RCP-A2 1016' 0" X RCP-A3 1016' 0" X RCP-A4 1016' 0" X RCP-B1 1016' 0" X RCP-B2 1016' Q X RCP-B3 X RCP-B4 1016/0"
.1016 0" X RCP-C1 101
6 0" X - Amendment No. 27, 11, 7/ 2-78 e
. /
TABLE 2-6 (Continued)
/ Located ALcessible in High Difficultjo During Inaccessible Radiation Remove for
- Snubber s, Nomal During Normal Areas During Functional N ". Ele.vation Operation Operation Shutdown Testing
\
RCP-C2 1016' 0" X RCP-C3 1016' q" X RCP-C4 1016' 0' X RCP-D1 1016' 0" X RCP-D2 1016' 0" X' RCP-D3 1016' 0" X RCP-D4 1016' 0" X RCS-1 1008' 7" X RCS-2 1006' h-1/2" X X RCS-3 1006' h-1/2" X RCS-3B 996' 6" X' RCS k 1010' 7" X RCS-5 1010' 7" X RCS-5A 1010' 7" X RCS-5B 1010' 7" RCS-7 1017' 0" XX X RCS-TA 1017' 0" X RCS-8 1032' 0" X RCS-8A 1031' 0" X' X RCS-9 1017' 0" X, X RCS-11 1041' 0" X X RCS-12 1041' 0" X X RCS-13 1032' 0" X X RCS-lb 1032' 0" X X - RCS-14B 1032'j o" X X RCS-lhC 1032' 0" X X
/ ,
RCS-15 1032' 0" X X-RCS-18 015' 0" X RCS-19 1015' 0" X 7 RCS-19A-Left 1015' 0" X
/
CS-39A-Right 1015' 0" X , RCS-20 1015' 0" _, X ._ (MdM-ant Nn. W I4 P 70
., s*,
TABLE 2-6(a) (Continued) Located Accessible in High Difficult to During Inaccessible 3adiation Remove for i
*Snubbeg Nonnal During Normal Areas During Fun' e tional N Elevation Operation Operation Shutdown Testing No.
RCS-21 \(032' 0" X RCS-22 1037' 6" X RCS .\ '
- Bo ttom 0 X RCS-25 1032 1033 \' q"" X ,
RCS-27 1052' 9" X RCS 1052' 9" X RC'-30 1045' 6" X . RCS-30A 1047' 0" < X
~
RCS-31 1052' 0" X RCS-32 1052' C" X kCS-33 1052' 0" X RCS-34 1047' 0" X RCS-42 1007' 9" X RCS-44 1007' 9" X RCS n t ( l ] Top 1009' 6" X Ll e_l e.T C Q - RCS Bottom 1009' 6" '\ X RCS-4 7- \ Top 1009' 6" 1 RCS-4 7- \ Bottom 1009' 6" X RCS-49 1009' 6" X RCS-51 1007' 9" X mendment No. 27, 79,9$ 2-80
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. . _ . . , , - _ . . . . , , , . . , . , _ . . r. _ , - _ . - _ . - _ _ . _ . - _ _ . . _ . , _ . . _ . . - _ _ _ _ _ -
TABLE 2-6(a) (Continued) Located Accessible In High Difficult to During Inaccessible Radiatior. Remove for
- Snubber Normal During Normal Areas During Functional No. Elevation Operation Operation Shutdown Tes ting RCS-52 1007' 9" X ,
RCS-64 ' Top 1032' ' X RWS-79 1046' 0 X X RWS-128A 998' 8- 2" X RWS-128B 998' 8-1/2's' X RWS-130 998' 8-1/2" X RWS-131 998' 8-1/2" X SG-Al 1049' 0" X X SG-A2 1049' 0" X X SG-A3 1049' 0" X X SG-A4 1049' 0" X X SG-31 1049' 0" X X SG-B2 1049' 0" X X SG-B3 1049' 0" X X SG-B4 1049' 0" X SIS-1 979' 6" X SIS-1A 979' 6" X - C , P- C SIS-3 979' 6" X SIS-4 979' 6" X SIS-4A 979' 6" X SIS-5 979' 6" X SIS-SA 979' 6" X SIS-6 979' 6" K SIS-6A 979' 6" X SIS-7 979' 6" X SIS-8 979' 4" X SIS-8B 9 79' 6 " X SIS-8C 979' 6" X SIS-9 979' 6" X SIS-9A 979' 6" X SIS-9B 979' 6" X SIS-10 983' 6" X SIS-11 983' 6" X SIS-16 X SIS-16 A 981'/" 981' 6" X SIS-17 979' 6" X L endment No. 27, 59, 12, 7'9 2-81
**. e
- , , . , - - . - - - . . - - - . . - . _ . - , - - ~, .- . . - -
TABLE 2-6(a) (Continued) Located Accessible In Righ Difficult to During Inaccessible Radiation Remove for
- Snub er No rmal During Normal Areas During functional No. \ Elevation Operation Ope ra tion Shutdown / Testing SIS-17A 9 79' 6 " X SIS-18 '979' 6" X SIS-19 9R9' 6" X SIS-20 97h' 6" X SIS-21 979'\6" X SIS-21A 981' 8" X SIS-21B 981' 6" X SIS-21C 981' 6" X SIS-22 981' 6" X SIS-23 981' 6" X 'l-SIS-24 983' 6" X SIS-24A 983' 6" X SIS-26 979' 6" X SIS-27 981' 6" X SIS-27A 981' 6" X SIS-27B 981' 6" SLS-28 9 80 ' 0" X SIS-28A 980' 0" X 1 SIS-29 980' 0" X '] 41[) di i C-
{ SIS-30 979' 6" X SIS-30A 979' 6" X SIS-31 981' 6" X SIS-31A 981' 6" X SIS-32 980' 0" X SIS-32A 980' 0" X SIS-32B 9 80' 0 " X SIS-33-Top 981' 6" X SIS Bo t tom 981' 6" X X j SIS-34 980' 0" X SIS-35-To p 980' 0" X SIS Bo t tom 980' 0') X SIS-36-To p 974' X L Amendment No. 21, 39, 19 2-82 4
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. ,._m_
~, f, TABLE 2-6(e).'[, t
, /'
(C:ntinu2d) < ,
, )
*i $cated I
Accessible Gn ):igh Difficult to ( Snu ber
*No. \
SIS Elevation During Normal Operation Inaccessible During Normal Operation (. Radiation' l Areas During' iShutdown Remove /for Functional Test'ing 974' 6" Botton X f .i SIS t Top 981 6" X \. , SIS u [I~ , 981' 6' Bottom X > SIS-38 981' 6" X \ X SIS-38B 981' 6" X ' ' X SIS-38C 981' 6" X
' ,t
,, < X SIS ' ' %
'j. *
) i Top 973' 0" / .. , . b, ' /,
\ r i <
SIS :s -c - Bottom 973'-0" X
..I-i SIS-39A 973' 0" X SIS ..
Top 981' 6" X , ( SIS 1 [ O #-- C Bottom 981' 6" X SIS-41A 979' 6" X - s .,, SIS-42 979' 6" X 4 SIS-42A 979' 6" X , SIS-43 979' 6" X -I SIS-43A 979' 6" X SIS-44 979' 6" SIS-44A 979' 6" X SIS-44B 979' 6" X , SIS-44C 979' 6" X SIS-45 974' 6" X , SIS-45A X s i SIS-46 979')6" 979
/
X .. < SIS-47 979' 6" X, .' s
' i SIS-48 979' 6" X h
SIS-49 979' 6" X '. s .- '.
/ 979' 6" X >
{ SIS
/ '
endmentNo.If.I$ 2-83 \ l' K e' . . _ . - . . ._ _-[ . . . .__,-__.y r ___ ._
TABLE 2-6(o) (C:ntinusd) Located
/
Accessible In High
/
Difficult to ( Snubber
*No. \
SIS-53 Elevation 997' 6" During Normal Operation X
. Inaccessible During Normal Operation Radiation Areas During Shutdown Remove' fo r Funct'ional Testing SIS-53A 997' 6" X SIS-54 196' 6" X
. \ SIS-55 996 6" X SIS-56 X 996'{
- SIS-56A 996' 6' X SIS-57 995' 11-3/8" X
\
SIS-58 995' 11-3/8 X SIS-59 996' 6" X SIS-60 996' 6" X , SIS-63 990' 6" SIS-64 990' 6" X SIS-65 990' 9" X SIS-66 1000' 0" X SIS-67 1000' 0" X SIS-68 1001' 9-3/8" X - 1003' 6" X X ( SIS-69 SIS-70 1000' 0" X , SIS-71A 1002' 8" X SIS-72 1002' 8" X SIS-73 1002' 8" X SIS-74 1002' 8" X SIS-74A 1002' 8" X/
/
SIS-75 1002' 8" X SIS-76 997' 6" X SIS-76A 997' 6" X SIS-77 991' 0" X SIS-77A 991' 0" X SIS-78 991' 0" X SIS-79 1001'/ 7 4" X SIS-79A 1001' 4" X L Amendment No. A7, )9 2-84
- -+w,w
- w . r w rm -
1 , TABLE 2-6 (Continued) Located . Accessible in High Dif icult to During Inaccessible Radiation Rer$ove for
- Snubber Normal During Normal Areas During unctional No. Elevation Operation Operation Shutdown Testing SIS-80 Ol' 4" X SIS-81 99h'6" X -
SIS-81A 991'\6" X SIS-81B 991' 6's' X SIS-82 991' 0' X SIS-82A 991' 0"~ X SIS-83 1001' 9-3/ " X SIS-84 1001' 9-3/8" X
' SIS-85 1002' 8" X
'SIf-85A 1006' 8" X SIS-86' 991' 6" X SI'3-87 SIS-88 990' 9" 989' 11"
\X X ,
SIS-89 1000' 0" - SIS-89A 1000' 0" X SIS-90 1000' 0" X SIS-91 1002' 8" X ( SIS-91A SIS-92 SIS-93 1002' 8" 990' 9" 990' 9" X X X P k R. d SIS-93A 990' 9" X SIS-94 1001' 9-3/8" X SIS-95 1001' 9-3/8" X SIS-96 1002' 8" f2 SIS-96A 1002' 8" /X SIS-97 1002' 8" X SIS-98 1000' 0" X SIS-99 998' 6" X SIS-100 997' 6" X Amendment No. 77,/I 2-85 L
"o
I , TABLE 2-6(a) (Continued) Located Accessible In liigh Difficult to During inaccessible Radiation "Smove far
*Snubbeg No rmal During Normal Areas During unctional No. N Elevation Operation Operation Shutdown Testing SIS-101 l' 0" X ,
SIS-101A 991' 0" X SIS-102 991 \ 0"" X SIS-103 1001' X SIS-104 1001' 4 X SIS-104A 1001' 4" X SIS-10LB 1001' 4" X SIS-112C 1111' 6" X SIS-112D 1111' 6" X /
' SIS-112E 1111' 6" X /
SIS-112F 1111' 6" X SIS-115 1009' 5-3/4" X SIS-116 1009' 5-3/4" X SIS-117 1009' 5-3/4" X/ SIS-117A 1009' 5-3/4" X SIS-118 1009' 5-3/4" X SIS-118A 1009' 5-3/4" ( X SIS-119 6[8 i4O I Top 1006' 4-1/2" X SIS-119 Bottom 1006' 4-1/2" X SIS-120 SIS-121 1006' 4-1/2" 1007' 10"
\(r SIS-122 1003' 0-1/8" X SIS-122A 1003' 0-1/3" X SIS-123 1003' 0-1/3" X SIS-124' 1010' 4" X SIS-127 1010' 4" X SIS-127A 1010' 10-1/2" X SIS-129 1005' 5" X SIS-130 1008' 2" X SIS-132 1008' 2" X SIS-134 1003' 0',' X SIS-135 1003' 0" X SIS-140 1008'j10" X SIS-150 1008' 10" X SIS-159A 1004' 3-1/6" X SIS-161 1014' 0" X Amendment No. 27,59,7$ 2-86 o
TABLE 2-6(a) (Continued) located Accessible In High Di ficult to During Inaccessible Radiation ldmove for
- Snubber Normal During Normal Areas During Functional No. \ Elevation Operation Operation Shutdown Testing SIS-162 1014' 6" X SIS-164 014' 0" X
' SIS-165 SIS-165 A Id(4'6" 1014 6" X
X Top SIS-165A 1014' X Bottom SIS-166 1014' 6" X SIS-16 7 1014' 6" X SIS-168 1014' 6" X SIS-168A 1014' 6" X Top SIS-168A 1014' 6" X Bottom SIS-169 1007' 7" X SIS-169A 1007' 7" SIS-170 1007' 8" X
!is-170A 1007' 5" X
]g{gy
(- SIS-172 SIS-173 1032' 0" 1036' 8" X X SIS-174 1049' 2" X - SIS-174A 1049' 6" . X SIS-174B 1051' 7-1/4" X X SIS-174C 1052' 6" X SIS-174 D 1063' 7-1/4" X X SIS-174E 1064' 6" X X SIS-175 1057' 9" X X SIS-175A 1056' 5-1/2" X l SIS-176B 1052' 6" X' X SIS-176C 1051' 7-1/4"' X X SIS-176D 1064' 6" X X SIS-176E 1063' 7-1 4" X X SIS-176G 1074' 0"' X X SIS-17611 1074' X X i ( .- endreent No. 27,48,59,7s 2-87
*e
\
e
e
- TABLE 2-6(a)
(Continued) Located Accessible In High Difficult to During Inaccessible Radiation demove for
- Snub (er Normal During Normal Areas During Functional No. N Elevation Operation Operation Shutdown / Testing SIS-183 1055' 9-1/2" X l SIS-184 79' 6" X '
SIS-185 (9' 6" X SIS-187 983' 6" X SIS-188 988'\s" 6 X SIS-202 1009' X SIS-204 995' 0" X SIS-205 979' 6" X SIS-206 983' 6" X SIS-208 1003' 1-1/8" X WDS-107 1004' 0" X WDS-122 Right 991' 6" X WDS-122 Left 991' 6" X C'. C'- C NOTE: Modifications to this table due eq changes in high radiation areas should be submitted to lhe NRC as part of the next licensing amendment request.' N g
- Loca tion ACS Auxiliary Coolan,t System AFW Auxiliary Feedwater System FWS Feedwater Sys, tem MSS Main Steam ystem RCP Reactor Co lant Pump RCS ReactoryolantSystem RWS Raw Watpr System SG Steamj Generator SIS Safety Injection System WDS Waste Disposal System
(,, Amendment No. 27, 17, 11 (9 2-88 9 O e
( Table 2-6(b) ACCESSIBILITY OF SAFETY-RELATED SYSTEM MECHANICAL SNUBBERS LOCATED ACCESSIBLE INACCESSIBLE IN HIGH DIFFICULT TO DURING .DURING RADIATION REMOVE FOR SNUBBER NCRMAL NORMAL AREAS DURING FUNCTIONAL NO. ELEVATION OPERATION OPERATION SHUTDOWN TESTING !
\
RCS-3A 996' X
\ -
RCS-16 1015' X RCS-29 1047' X RCS-29A 1045' X RCS-39 1048' ,. RCS-41 1048' X , 1051'6" RCS-61 X Q RCS LOWER 1032' X RCS-65 1051.'6" RCS-67 1032' X RCS-68 1031' X RCS-69 1032' X RCS-70 1032' X RCS-71 10 2' X SIS-114-A 1074' X SIS-114-B 1074' X SIS-114-E 1074' X SIS-114-F 1074' X
~
L Amendment No. h, 7///,96 2-88a
% e M -
e *
)
3.0 SURVEIIIANCE RECUIRBEUTS 3.lk Shock Suuuressors (Snubbers) Applicability s afc+y - relste41 Thisspecificationappliestoallhydraulio. snubbers,on-the '
-re ac t o P-c oolant-and-s a fe ty-relat ed- sy s t ems -li s t ed-in-T able-2 ,
fa-}--and-(.b}v
-Objective
-The-ob,j ec t ive-o f-thi s-spec i f ic at ion-i s-to-insur e-t he -ove ral ,
-int e grity-and-operability-of--safety-related-hydraulio-snubbers, Seacifications (1) All hydraulic snubbers whose seal material has been de-monstrated by operating experience, lab testing or analysis to be cc=patible with the operating environ =ent shall be ,
visually 1nspected. This inspection shall include, but not necessarily be limited to, inspection of the hydraulic fluid reservoir, fluid connections, and linkage connections to the piping and anchor to verify snubber operability. In those locaticns where snubber movement can be manually ' induced without disconnecting the snubber, verify that the , snubber has freedom of covement and is not frozen up. ( Visual inspections shall be performed in accordance with the following schedule: Number of Hydraulic Snubbers Found Next Required Inoperable During Inspection or Inspection During Inspection Interval Interval 0 18 months + 25% 1 12 months 7 255 2 6 months +[25% 3, h 124 days 2; 25% 5, 6, 7 62 days j; 25%
>8, 31 days f; 25%
The required inspection interval shall not be lengthened more than one step at a time. Snubbers may be categorized in two groups, " accessible" or
" inaccessible" based on their accessibility for inspection during reactor operation. These two groups may be in-spected independently according to the above schedule.
(2) All hydraulic snubbers whose seal materials are other than eythlene propylene or other material that has been de-monstrated to be compatible with the operating environment shall be visually inspected for operability every 31 days. L AnendmentNo.27,$p 3-77
, e . 3.0 SURVEILLUTCE RECUIREME'ITS gonf ed{cg h Mc r 3.14 shock sunnressors (snubbers) (continued) cen&&,4 Leleg; (3) Atleastonceper18monthsduringshutdovn[a-represent-
-ati-ve-sample-of SS-snubbers-shall--be-functionally-tested
-ei-t her-in-pl ac e-or-in-a-bench-tes t . Br-each-number-of s nubb e r s-above-3-wh ic h-doe s-not-me e t-t h e -fun c t i on al-t e s t
-acceptance-criteriar an-additional-sample-selected-according-to-t he-exp res s ion-22 (a-3 )-e Sall-be-fun c t io nal-ly-t e s t ed; whe re-a-i s-the-tot al-numbe r -o f-snubbe rs-found-inope rable Muring-the-functional-testing-of the-representative-sa=ple.
-For-each-inoperable-snubber-round-during-a-resample-test ran-
-add i t ion al-22-s n ubb e r s-v ill-be-t e s t e d-unt il-no-additi on al-
-inoperable-anubbers-aro found-within-a-sample-or-until-all-
-s nubbe r s-i n -Table-2-6-(_a )-an d-{bl-h ave-be e n-func t io nally tested, The-re p r e se n ta t ive-s ample-sele ct ed-fo r-func t ion al-t e s t i n g-s h all--i n e1+:d e-t h e-va ri o u s-con f-igura tion sspe ratin g-e n-
-vi ronme n t s-and-t he-range -o f-si ze-and-c apac i ty-o f-s nubbers .
At-leas t -25 *,-o f-the -s nubbe rs -in - the -repres e ntat ive -s ample-s h all-i n clud e - s n u b b e rs - from -any-o f-t h e - fo llowi ng-t hre e categoriest e c. (al Th e- firs t -s nubbe r-away-from-each-rea ctor-ve s s el,
- no::le.
_Lnsert A ' fb) Snubb e rs -wit hin f e e t -o f-he avy-equipment-(valve,, # pump rturbiney-motorretc ), (c-) ---Snubbers-within-10-feet-of-the discharge-frem-a. safe ty-relief-valve. Snubbers-identified-in-Table-2-6-(a)-and_(b)-as "Especially-Di-fficult-to-Remove"--or-in "High-Radiation Zones During Shutdown"-s hall-als o -be-included-in-the-rep res ent at ive-campic.*
-In-add i t io n- t o- t h e - re gul ar- s ample rsnubbers-which-failed-the-pre v i ous -fune t ion al-t es t-s h all-b e -re t e s ted-during-t he - next test period. If a spare-snubber-has-been-installed-in-place-o f-a-fa iled-s n ubbe rT-t he n -bot h-t h e -f ailed-s nubb e r-( i f-it-i s-re pa i red-end -i n s t alled -i n-anoth e r-pos i tio n )--and -the-spar e-e nubbe r-s hu ll-be -re t es t ed .-Te s t- re s ults -o f-thes e - s nubbe rs -
-may-no t-be -i nclude d-fo r- the- re s ampling .
- Pe rma ne nt,-o r-ot he r-exempt ions-f rom -func t ion al-t e s t in g -for -individual-anubbers in-these-categories-may--be-granted-by-the-Commission-only-if-a ,}ustif,iable basis-for-exemption-is-presented-and/or-snubber-life-destructive-testing-was-performed to-qualify-snubber-operability-for-all-de s ign -c ond i t ion s -at-e i t he r-t he - c omplet ion-o f-t he i r-f abric at io n or-at-a-subsequent date.
A endment :Io. 27, L9 3-78
n .S e. r ! / \ (a) A representative sample of hydraulic h8)' snubbers shall be functionally tested either in-place or in a bench test. (i) For each hydraulic snubber above 3 which does not meet the functional test acceptance criteria, an additional sample of 22 hydraulic snubbers shall be functionally tested. (ii) For each inoperable hydraulic snubber found during a resample test, an additional 22 hydraulic snubbers will be tested until no additional inoperable hydraulic snubbers are found within a sample or until all hydrau-lic snubbers have been functionally tested; and (b) 10% of the safety-related mechanical snubbers shall be functionally tested either in-place or in a bench test. (i) For each mechanical snubber which does not meet the functional test acceptance criteria, an additional sample of 10% of the mechanical snub-bers shall be functionally tested. - (ii) For each inoperable mechanical snubber found dur-ing a resample test, an additional 10% of the mechanical snubbers will be tested until no additional inoperable mechanical snubbers are found within a sample or until all mechanical snubbers have been functionally tested. (c) The representative sample selected for functional testing shall-include the various configurations, operating environments and the range of size and capacity of snubbers. At least 25% of the snubbers in the representative sample shall include snubbers from any of the following three categories: .
- 1. The first snubber away from each reactor vessel nozzle.
- 2. Snubbers within 5 feet of heavy equipment (valve, pump turbine, motor,etc).
- 3. Snubbers within 10 feet of the discharge from a safety relief valve.
Snubbers that are especially difficult to remove or in high radia-tion zones during shutdown shall also be included in the representa-tive sample. Permanent or other exemptions from functional testing for individual snubbers in these categories may be granted by the Commission only if a justifiable basis for exemption is presented and/or snubber life destructive testing was performed to qualify 1
a ,, , I
~
O $ d. F l \ C.o e'l f 0 tt ed .I snubber operability for all design conditicns at either the completion of their fabrication or at a subsequate date. (d) In addition to the regular sample, snubbers which failed the previous functional test shall be retested during the next test period. If a spare snubber has been installed in place of a failed snubber,'then both the failed snubber (if it is repaired and installed in another position) and the spare. snubber shall be retested. Test results of these snubbers may not be included for the resampling. 0 1 e l _ _ _ _ . _ _ _ _ _ - ~ - _ _ _ _ . ~ . _ _ _ _ . _ _ _ _ _ _ _ ._ . . . , . _ _ _ _ _ _ _ _ _ _ . . . _ _ . _ . _ -
c <* * . . 3.0 SURVEIIIANCE RECUIFBfETS 3.lk Shock Suppressors (Snubbers) (.Continuedl If any snubber selected for functional testing either fails to lockup or fails to move, i.e. , is frozen in place, the cause vill be evaluated. If the cause is a =anufacturer or design deficiency, appropriate action shall be taken for snubbers of the same design subject to the same defect to determine if any more defects exist. This testing requirement shall be indepen-dent of the requirements stated above for snubbers not meeting the functional test acceptance criteria. For any snubber (,s) found locked up during norm operation or found inoperable following a seismic event, an engineering evalua-tion shall be performed on the components which are supported by the snubber (s). The purpose of this engineering evaluation shall be to determine if the co=ponents supported by the snubber (s) were adversely affected by the inoperability of the snubber (s) in order to ensure that the supported component re=ains capable of meeting the designed service. If the engineering evaluation shows the components to be capable of meeting the designed service without the failed snubber, that snubber may be deleted fron service and-Eable-2-6(.a-}-and-6b) per Specification 2.18(h) . _ (h) Snubber Service Life Monitorinc y ( A record of the service life of each snubber, the date at which the designated service life ec==ences and the insvallation and maintenance records on which the designated servige life is based shall be maintained as required by Specification 510.2 m. ' At least once per 18 months the installation and maintenance record for each snubber listed-in-Table-2-6(aband-{-ir) shall be reviewed to verify that the indicated service life has not been exceeded or vill not be exceeded prior to the next scheduled snubber service life review. If the indicated service life vill be exceeded prior to the next scheduled snubber service life review, the snubber service life shall be re-evaluated or the snubber shall be replaced or reconditioned so as to extend its service life beyond the date of the next scheduled service life review. This re-evaluation, replacement or reconditioning shall be indicated in the records. Basis fdeh-rcg W g h4ll [:, e All^ snubbers 1-isted-in-Table-2-6(a)-and-(bl_are-required-operable to ensure that the structural integrity of the reactor coolant system and all other safety-related systems is maintained during and following a seismic or other event initiating dynamic loads. Snubbers excluded from this inspection program are those installed on non-safety-related systems and then only if their failure or failure of the system on which they are installed would have no adverse effect on any safety-related system. The visual inspection frequency is based upon =aintaining a constant level of snubber protection to systems. Therefore the required inspection interval varies inversely with the observed snubber failures and is determined by the number of inoperable snubbers found during an inspection. Inspections performed before that interval has elapsed =ay be used as a new reference A=endmentNo.27,5f 3-79 ,
.a .= o 3.0 SURVEIIIANCE REQUIRDIENTS 3.14 Shock Surtressors (Snubbersl (Continued) point to determine the next inspection. However, the results of such early inspections perfor=ed before the original required time interval has elapsed (nominal time less 2551 may not be used to lengthen the required inspection interval. Any inspection whose results require a shorter inspection interval vill override the previous schedule.
k' hen a snubber is found locked up or frozen in place or when a snubber has been inoperable during a seismic event, an engineering evaluation shall be performed, in addition to the determination of the snubber mode of failure. The purpose of the engineering evaluation is to determine if any safety-related component or system has been ariversely affected oy the inoperability of the snubber. The engineering evaluatien shall deter =ine whether or not the snubber mode of failure has imparted a significant effect or degradation on the supported co=ponent or system. To provide assurance of snubber functgnal reliability, a repre-sentative sample of the installed sy - ers will be functionally h intervals. Selection of og g., tested during sample a representative plant shutdowns
$according to at t 183 @ lie gxpression 35(1+c/2)*c
$nda provides a confidence level of approxir,.ately 95% that 90% to 100",
of the snubbers in the plant vill be ejerable within acceptance limits.3 Observed failures of these su.ple snubbers shall require " For each number of (gp,,dffunctionaltestingofadditionalunits.sc.s u Jed , _ i snubbers above c which does not meet the 48% c4. c 'ceptance criteria, an additional sanele selected according to the b bc 3. expression 35(1+c/2)(2/(c+1))2(.a-cl vill be functionally tested, where a is the total number of snubbers found inoperable during the functional testing of the representative sample. Functional testing vill continue according to the expression b(35(1+c/2)(2/(c+1))2) where b is the number of snubbers found inoperable in the previous resa=ple, until no additional inoperable snubbers are found within a sa=ple or until all snubbers in Table 2-6 have been functionally tested. h u. % bsc<f 8 Hydraulic snubbers and mechanical snubbers vill each be treated as a different entity for the above surveillance programs. The service life of a snubber is evaluated via manufacturer input and information through consideration of the snubber service conditions and associated installation cnd maintenance records (newly installed snubber, seal replaced, spring replaced, in nigh radiation area, in high temperature area, etc.). The requirement to monitor the snubber service life is included to ensure that the snubbers periodically undergo a performance evaluation in view of their age and operating conditions. These records vill provide statistical bases for future consideration of snubber service life. The requirements for the maintenance of records and the snubber service life review are not intended to affect plant operation.
*The-value-e-vi-1-1--be-arbitrarily-chosen-by-the-applicant and incorporated into-the-expression-for-the-representative-sample-and for-the-resample
-prior-to-the-is suance-o f-the -Technic al-Speci ficat ions .
A=end=ent No. 59 3-79a .
e ce c y i
- n 5er+ .D A "lO %" c.ri4ccis.1 ic uf.l;=cJ Ac mcda,3; cal sow 66ces bueawse a G &be cons,derably sena.llec awnser c G mcchu,cr]
SillANb<.eS. L _
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5.0 ADMINISTRATIVE CONTROLS 5.10.2 The following records shall be retained for ,the duration of the Facility C Operating License: ~
- a. Records of drawing changes reflecting facility design codifications made to systems and equipment described in the Final Safety Anal-ysis Report.
- b. Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.
- c. Records of facility radiation and contamination surveys.
- d. Records of radiation exposure for all individuals entering radia-tion control areas.
- e. Records of gaseous and liquid radioactive material released to the environs.
- f. Records of transient or operational cycles for those facility components designed for a limited number of transients or cycles.
- g. Records of training and qualification for current members of the plant staff.
- h. Records of in-service inspections performed pursuant to these Technical Specifications.
- i. Records of Quality Assurance activities required by the QA Manual.
- j. Records of reviews performed for changes made to procedures or
(' equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.
- k. Records of meetings of the Plant Review Committee and the Safety Audit and Review Committee.
- 1. Records of Environmental Qualification of Electric Equipment- /
pursuant to 10 CFR 50.49. '
- m. Records of the service lives of all hydraulic and mechanical
, snubbers Msted-on-Table-24(-a)-and-(b)-including the date at l . W'ich~th'e service life commences and associated installation and maintenance records.
- n. Records of analyses required by the Radiological Environmental Monitoring Program.
5.11 Radiation Protection' Program Procedures for personnel radiation protection shall be prepared consis-tent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radia-tion exposure. 5-19 Ofddt 66 tid JD/U/50, ' Amendment No. E9, , 93 Q!i.c4 mcc co vc.r ed und e_c N prowsions J S ec Re n 2. 1 8 a& TecJmicd SpM;cn%s _ l
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