ML20040G293
| ML20040G293 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 02/02/1982 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20040G294 | List: |
| References | |
| NUDOCS 8202120125 | |
| Download: ML20040G293 (45) | |
Text
_.. _
%g UNITED STATES E
NUCLEAR REGULATORY COMMISSION o
3,
,I WASHINGTON, D. C. 20686
...../
PUBLIC SERVICE ELECTRIC AND GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-272 SALEM NUCLEAR GENERATING STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 40 License No. DPR-70 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Public Service Electric and Gas Company, Philadelphia Electric Company, Delmarva Power and t Company and Atlantic City Electric Company (the licensees)
Ligh.d August date 10, 1981, complies with the standards and requirements of the Atomic Elergy Act of 1954, as amended (the Act) and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
8202120125 820202 PDR ADOCK 05000272 p
e
+ 2.
A cordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-70 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 40, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
R,THE NUCL AR REGULATORY COMMISSION 3
f T/ t.t.t,L S veh A. Vargh, Ch
- Operating Reactors h #1 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: February 2,1982 l
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 40 TO FACILITY OPERATING LICENSE NO. DPR-70 DOCKET NO. 50-272 Revise Appendix A as follows:
Remove Pages Insert Pages 3/4 7-28 3/4 7-28 3/4 7-29 3/4 7-29 3/4 7-30 3/4 7-30 3/4 7-31 3/4 7-31 3/4 7-32 3/4 7-32 3/4 7-32a 3/4 7-32b 3/4 7-33 through 3/4 7-33o
__,-.6,.,
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,-.m-v m
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PLANT SYSTEMS 3/4.7.9 SNUBBERS LIMITING CONDITION FOR 6PERATION
)
l 3.7.9 All snucbers listed in Tables 3.7-4a and 3.7-4b shall be OPERABLE.
APoLICABILITY: MODES 1, 2, 3 and 4 (MODES 5 and 6 for snuboers locatee on systems required CPERABLE in thost MODES).
ACTION:
With one or more snubbers inoperable, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, replace or restore tr.e inoperab e snubber (s) to CPERABLE status and perform an engineering evaluation l
per Specification 4.7.9c on the supportec component or declare the succortec system inoperacle and follow appropriate ACTION statement for that system.
SURVEILLANCE RECUIREMENTS 4.7.9 Each snuceer sna11 be demonstrated OPERABLE by performance of the following augmented inservice inspection program and the requirements of Scecification 4.0.5.
a.
Visual Inseection An inservice visual inspection of all snubbers listed in Tables 3.7-4a and 3.7-4b shC' be performed in accordance with the followir.g schedule for each separate Table:
No. Inoperable Snubbers in Subsequent Inspection period a Table per Inspection Period for each Table *=
0 18 months t 254 1
12 months 2 25%
2 6 months 2 25%
3, 4 124 days t 25%
5, 6, 7 62 days 2 25%
8 or more 31 days 2 25%
Within each Table, the snubbers may be categorized into two groups:
These accessible and those inaccessible during reactor operation.
Each group within a Table may be inspected independently in accordance with the above schedule.
'The inspection interval shall not be lenghthened more than one step at a time, eThe provisions of Specification 4.0.2 are not applicable.
A l
SALEM - UNIT 1 3/4 7.z8 Amendment'No. 40
PLANT SYSTEMS SURVEILLANCE REQUIREWENTS (Continued) b.
Visual Inscection Acceotance Criteria Visual inspections shall verify (1) that there are no visible indications of da= age or impaired OPERABILITY, (2) attachments to the foundation or supporting structure are secure, and (3) in those locations where snubber sovement can be manually induced without disconnecting the snubber, that the snubber has freedom of movement and is not frozen up.
Snubbers which appear inoperable as a result of visual inspections may be determined OPERABLE for the purpose of establishing the next visual inspection interval, providing that (1) the cause of the rejection is clearly established and remediec for that particular snubber and for other snubbers that may be generically susceptible; and (2) the affected snucber is functionally tested in the as.found condition and determined OPERABLE per Specifi-cation 4.7.9d or 4.7.9e as applicable. However, when the fluid port of a hydraulic snubber is found to be uncovered, the snubber shall.be declared inoperable and cannot be determined OPERABLE via functional testing for the purpose of establishing the next visual inscection interval. All snubbers connected to an inoperable common hydraulic fluid reservoir shall be counted as inoperable snubbers.
c.
Functional Tests **
At least once 'per 18 months during shutdown, a representative sam;;N of 10% of the total of each type of snubber in use in the plant shall be functionally tested either in place or in a bench test.
For each type of snubber that does not oeet the functional test acceptance criteria of Specification 4.7.9d or 4.7.9e, an additional 10% of that type of snuttier shall be functienally tested.
The representative samole 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 snuceers in the representative sacole shall include snubbers from the following three categories:
1.
The first snubber away from each reactor vessel noz:le i
2.
Snubbers within five feet of heavy equipment.(valve, :umo, i
turbine, motor, etc.)
l 3.
Snubbers within ten feet of the discharge from a safety f
relief valve j
Snubbers identified in Tables 3.7-4a and 3.7-ab as "Especially Difficult to Remove" or in "High Radiation Zones During Shutcown" i
l shall also be included in the representative sample." Tables 3.7-aa l
' Permanent or c;ner exemptions from functional testing for individual snuboers l
in these categories may be granted by the Commission only if a justifiable l
basis for exemotion is presented and/or snubber life destructive testing was performed to qualify snucber operability for all design conditions at eitner I
the completion of their fabrication or at a subsequent date.
(
with a rated capacity of greater than 50,000 lbs. shall commence with the 4th refueling outage.
SAL M UNIT 1 3/4 7-29 AMENDMENT NO. 40 l
l
PLANT SYSTEMS O'RVEILLANCE REOUIREMENTS (Continuec) and 3.7-4b may be used jointly or separately as the basis for the sampling plan.
In addition to the regular sample, snubbers which failed the previous functional test shall be retesced 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 snuocers may not be included for the re-sampling.
If any snubber selected for functional testing either fails to lockup or fails to move, i.e., frozen in place, the cause will be evaluated and if caused by manufacturer or design deficiency all snubbers of the same design subject to the same defect shall be functionally tested. This testing requirement shall be independent of the requirements stated above for snubbers not meeting the functional test acceptance criteria.
For the snuceer(s) found inoperable, an engineering evaluation snall be performed on the components which are supported by the snubber (s).
The purpose of this engineering evaluation shall be to determine if the components succorted by the snubber (s) were adversely affected by the inoperacility of the snubber (s) in order to ensure that tne supported component remains capable of meeting the designed service, d.
Hydraulic Snubbers Functional Test Acceotance Criteria The hydraulic snubber functional test shall verify that:
1.
Activation (restraining action) is achieved within the sceciffec range of velocity or acceleration in both tension inc comcression.
2.
Snubber bleed, or release rate, where required, is within tne specified range in compression or tension. For snubbers scecifically required to not displace under continuous loac, the acility of the snubber to withstand load without displace-ment shall be verified.
e.
Meenanieri Snubbers Functional Test Acceotance Criteria The mecnanical snubber functional test shall verify that:
1 The force that initiates free movement of the snuceer roc in either tension or compression is less inan the scecifiec maximum drag force. The drag force shall not have increasec more tnan SC". since the last functional test.
2.
Activation (restraining action) is achieved within the specifiec range of velocity or acceleration in both tension anc comcression.
3/4 7-30 Amendment No. 40 l
SALDi - UNIT l 1
1 l
PLANT,5YSTEMS SURVEILLANCE RECUIREMENTS (Continued) e 3.
Snubber release rata, where required, is within the specified range in compression or tension. For snubbers specifically required not to displace under continuous load, the ability of the snubber to withstand load without displacement shall be verified.
f.
Snubber Service Life Monitorina l
A record of the service life of each snuccer, the date at unica the designated service life commences and the installation and mainten-ance records on whien the designated service life is based shall be maintained as required by Specification 6.10.2.1.
Concurrent with the first inservice visual inspection and at least once per 18 months thereafter, the installation and maintenance records for each snubber listed in Tables 3.7-4a and 3.7-4b shall be reviewed to verify that the indicated service life has not been exceeded or will not be exceeded prior to the next scheduled snubber service life review. If the indicated service life will be exceecec prior to the next scheduled snubber service life review, the snuceer service life shall be reevaluated or the snubber shall be replacec or reconcitic ned so as to extend its service life beyonc the date of the next sche 1uled service life review. This reevaluation, replacement or reconditioning shall be indicated in the records.
I SALEM - UNIT I 3/4 7-31 Amendment No. 40
l ll '
TABLE 3.7-4A
/*
SAFETY REL,A_TED IlY_DRAULIC SNUBBERS
- 9e5 SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR lilGil RADIATION ESPECIALLY DIFFICULT INACCESSIBLE ZONE **
TO REMOVE
-i NO.
ON, LOCATION AND ELEVATIUN"
~~(A or i F 7Ves orlo)
(YesorHo) 1 No. 11 Steam Generator, Reactor Yes Yes Containment. Elev. 128' 6" 2
No. 11 Steam Generator. Reactor i
Yes Yes Containment, Elev. 128' 6" 3
No. 11 Steam Generator, Reactor I
Yes-Yes Containment, Elev. 128' 6" 4
No. 11 Steam Generator, Reactor I
Yes Yes 3
Containment. Elev.128' 6"
[
5 No. 12 Steam Generator, Reactor I
Yes Yes Containment. Elev. 128' 6" r4 6
No. 12 Steam Generator, Reactor I
Yes Yes Containment, Elev. 128' 6" 7
No. 12 Steam Generator, Reactor I
Yes Yes Containment. Elev. 128' 6" E
8 No. 12 Steam Generator, Reactor I
Yes Yes
[
Containment, Elev. 128' 6" a
E f
O TABLE 3.7-AA(Continued) f!
SAFETY RELATED llVDRAULIC SNUBBERS
- E2 e
f5 SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR lilGH RADIAT10N ESPECIALLY DIFFICULT INACCESSIBLE ZONE **
TO REMOVE NO.
ON. LOCATION AND ELEVATION ~ ~ ~ ~ ~
~~~Tl or I)
(Yes or No)
(Yes or No) l 9
No. 13 Steam Generator. Reactor I
Yes Yes Containment, Elev. 128' 6" 10 No.13 Steam Generator. Reactor I
Yes Yes Containment, Elev. 128' 6" 11 No.13 Steam Generator, Reactor i
Ves Yes w
is Containment, Elev. 128' 6" 2
12 No.13 Steam Generator. Reactor I
Yes Yes D*
Containment Elev.128' 6" 13 No. 14 Steam Generator. Reactor I
Yes Yes Containment, Elev. 128' 6" 14 No. 14 Steam Generator. Reactor I
Yes Yes Containment, Elev. 128' 6" II 15 No. 14 Steam Generator. Reactor I
Yes Yes Containment, Elev. 128' 6" 16 No. 14 Steam Generator. Reactor I
Yes Yes
{
Containment. Elev.128' 6" O
8
=
8
1ABLE 3.1-4a(Continued) m
~
SAFETY RItAIID llYDRAULIC SNUBBER 5*
i h
SNUBBER SYSTIM SNUBBER INSTALLID ACCFSSIBLE OR IGli RADIAll0N ESPECIALLY DIFFit. ULT
]
- --.0 RE MOV E 1
. NO....
DN,.10 cal.l0..N.A.ND..I L.L..V.A.i.l.0N INACCL 55111L E.
10NL** --
17.
No. 11 Main Steam Isolation Valve A
No Yes Penetration Area, Elev. 115' 5" l
18.
No. Il Main Steam Isolation Valve A
No Yes Penetration Area, Elev. 115' 5" 19.
No. 12 Main Steam isolation Valve A
No yes l
l Penetration Area Elev. 115' 5" R
20.
No. 12 Main Steam isolation Valve A
No yes Penetration Area Elev. 115' 5" Y
M 21.
No.13 Main Steam Isolation Valve A
No yes Penetration Area, Elev. 115' 5" 22.
No.13 Main Steam Isolation Valve A
No yes Penetration Area. Elev. 115' 5" 23.
No. 14 Main Steam isolation Valve A
No "S
[
Penetration Area. Elev. 115' 5" o
{
24.
No. 14 Main Steam isolation Valve A
No Yes Penetration Area Elev. 115' 5" g
I ~3nubbers may be added to safety related systems without' prior License Amendment to Table 3.4 7-4a provided that a revision % Table 3.4 7-4a is included with the next License Amendment request.
ao
- Modifications to this column due to changes in high radiation areas may. be made without prior License Amendment provided that a revision to Table 3.7-4a is included with the next License Amendment request.
Y
TABLE 3.7-4b SAFETY RELATED MECHANICAL SNtlBBERS*
E M
a SNUBBER SYSTEM S* LUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLY DIFFICULT NO.
ON, LOCATION AND ELEVATION INACCESSIBLE DURING SHUTDOWN **
TO REMOVE (A or I)
(Yes or No)
(Yes or No) 1 1
Reactor Coolant System, Pressurizer I
Yes No South Centerline, Reactor Containment, Eley.158' 0" 2
Reactor Coolant System Pressurizer I
Yes No S.W. Quadrant, Reactor Containment Elev. 158' 0" 3
Reactor Coolant System Pressurizer I
Yes No S.W. Quadrant, Reactor Containment uy Elev.158' 0" 4
Reactor Coolant System, Pressurizer I
Yes No S.W. Quadrant, Reactor Containment Elev. 153' 0" 5
Reactor Coolant System, Pressurizer I
Ves No 5
S.E. Quadrant, Reactor Containment j
Elev. 158' 0" m*
4 6
Reactor Coolant System, Pressurizer I
Yes No S.E. Quadrant, Reactor Containment zP Elev.158' 0" 7
Reactor Coolant System. Pressurizer I
Yes No S.E. Quadrant, Reactor Containment Elev.158' 0" w
TABLE 3.7-4b E
SAFETY'RELATED MECHANICAL' SNUBBERS
- a:
E Z
SNUBBER SYSTEM SMtBBER INSTALLED ACCESSIBLE OR HIGi RADIATION ESPECIALLY DIFFICULT NO.
ON, LOCATION AND ELEVATION INACCESSIBLE DURING SHUTDOWN **
TO REMOVE (A or I)
(Ves or No)
(Yes or No) 8 Reactor Coolant System, Pressurizer I
Yes No N.W. Quadrant, Reactor Containment Eleir.142' 8" 9
Reactor Coolant System, Pressurizer I
Yes No N.E. Quadrant, Reactor Containment Elev.140' 3" 10 Reactor Coolant System, Pressurizer I
Yes No N.E. Quadrant, Reactor Containment y
L.
Ele'v. 137' 8" E'
11 Reactor Coolant System, Pressurizer I
Yes No N.E. Quadrant, Reactor Containment El e'v. 137 ' 8"-
12 Reactor Coolanti System, Pressurizer I
Yes No N.W. Quadrant, Reacto "ontainment k
Elev.137' 8" h
13 Reactor Coolant System, Pressurizer I
Yes No E
N.W. Quadrant, Reactor Containment
[
Eley.137 ' 8" O
14 Reactor Coolant System. Pressurizer I
Yes No N.W. Quadrant, Reactor Containment EleV. 137' 8" s
TABLE 3.7-4b SAFETY RELATED MECHANICAL SNUBBERS
- 2 E
A SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLY DIFFICULT NO.
ON, LOCATION AND ELEVATION INACCESSIBLE DURING SHUTOOWN**
TO REMOVE (A or I)
(Yes or No)
(Yes or No) 15 Reactor Coolant System Pressun izer I
Yes No N.E. Quadrant, Reactor Containment El ev. 144 ' 8" 16 Reactor Coolant System, Pressurizer I
Yes No N.E. Quadrant, Reactor Containment El ev. 141 ' 5" R*
17 Reactor Coolant System, Pressurizer I
Yes No
?
N.E. Quadrant, Reactor Containment t
O Elev. 141' 5" er 18 Reactor Coolant System, Pressurizer I
Yes No N.E. Quadrant, Reactor Containment Elev. 139' 8" 19 Reactor Coolant System, Pressurizer I
Yes No N.W. Quadrant, Reactor Containment g
Elev.139' 8" 20 Reactor Coolant System, Pressurizer I
Yes No S.E. Quadrant, Reactor Containment 4
Elet. 146' 4" 21 Reactor Coolant System, Pressurizer I
Yes No g
S.E. Quadrant, Reactor Containment Eley. 144' 8"
TABLE 3.7-4b 2-SAFETY RELATED MECHANICAL ' SNUB 8ERS*
p E
G SHb88ER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLY DIFFICULT NO.
ON, LOCATION AND ELEVATION INACCESSIBLE DURING SHUTDOWN **
TO REMOVE (A or I)
(Yes or No)
(Yes or No) 22 Reactor Coolant System. Pressurizer Y
Yes No N.E. Quadrant, Reactor Containment Elev. 142' 8" 23 Reactor Coolant System, Pressurizer I
Yes No N.E. Quadrant, Rea-tor Containment Elev.142' 8" 4
24 Reactor Coolant System, Pressurizer I
Yes No 7'
S.W. Quadrant, Reactor Containment jy Elev. 142' 6" 25 Reactor Coolant System. Pressurizer I
Yes No S.W. Quadrant, Reactor Containment Eley.141' 7 1/2" 26 Reactor Coolant System, Pressurizer I
Yes No S.E. Quadrar.t. Reactor Containment g.
Elev.151' 5 7/8" ni5 Ri 27 Reactor Coolant System Pressurizer
.I Yes No
'i S.E. Quadrant, Reactor Containment Eley.151.' 5 7/8" seP 28 Reactor Coolant System, Pressurizer I
Yes No S.E. Quadrant, Reactor Containment c'
i El es.149' 0" l
l l
TABLE 3.7-4b_
s:
SAFETY RELATED MECHANICAL ' SNUBBERS
- 4 x
E G
SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLY DIFFICULT NO.
ON, LOCATION AND ELEVATION INACCESSIBLE DURING SHUTDOWf8**
TO REMOVE (A or I)
(Yes or No)
(Yes or No) 29 Reactor Ceolant System, Pressurizer I
Yes No fl.W. Quadrant, Reactor Containment Elev.149' 0" 30 Reactor Coolant System, Pressurizer I
Yes No S.E. Quadrant, Reactor Contalmnent Elev. 147' 5" 31 Reactor Coolant System. Pressurizer I
Yes No
.d S.E. Quadrant, Reactor Containment t!
Elev. 146' 11" o.
32 Reactor Coolant System, Pressurizer I
Yes No S.E. Quadrant, Reactor Containment Elev.146' 11" 32 33 Reactor Coolant System, Pressurizer I
Yes No Eg S.W. Quadrant, Reactor Containment 5[
Elev.151' S 7/8" E
-4 34 Reactor Coolant System, Pressurizer I
Yes No E.
S.W. Quadrant, Reactor Containment El ey. 151' 8 7/8" 35 Reactor Coolant System, Pressurizer I
Yes No S.E. Quadrant Reactor Containment El ei. 147 ' 0"
TABLE 3.7-4b SAFETY RELATED MECHANICAL ~ SNUB 8ERS*
E Q
SNUBSER SYSTEM 590BBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLY DIFFICULT
_jiO.
ON, LOCATION AND ELEVATION INACCESSIBLE DURING SHUTDOWH**
TO REMOVE (A or I)
(Yes or No)
(Yes or No) 36 Reactor Coolant System, Pressurizer I
Yes No S.E. Quadrant, Reactor Containment Eley. 147' 0" 37 Reactor Coolant System Pressurizer I
Yes No S.E. Quadrant, Reactor Containment Elev. 147' 1 1/2" 38 Reactor Coolant System, Pressurizer I
Yes No S.W. Quadrant, Reactor Containment y
Elev.143' 8" g
39 Reactor Coolant System Pressurizer I
Yes Yes 9 Valve IPR-4, Reactor Containment Elev.154' 5 1/8" 40 Reactor Coolant System Pressurizer I
Yes Yes 0 Valve IPR-5, Reactor Containment
>M El ev. 154 ' 5 1/8" 2
h 41 Reactor Coolant, System, Pressurizer I
Yes Yes 5
9 Valve IPR-3, Reactor Containment Elev.154' 51/8" 2
42 Reactor Coolant System. Pressurizer I
Yes Yes
.c) 9 Valve IPR.6 Reactor Containment Elev.152' 1 7/8 *
/
TABLE 3.7-4b 5
SAFETY RELATED MECHANICAL SNUBBERS
- 9 E
G SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLY DIFFICULT NO.
ON, LOCATION AND ELEVATION INACCESSIBLE DURING SHUTDOWN **
TO REMOVE (A or I)
(Yes ci-No)
(Yes or Wo) 43 Reactor Coolant System, Pressurizer I
Yes Yes 9 Valve 1PR-7, Reactor Containment Ele'v.152' 1 7/8" 44 Reactor Coolant System, Pressurizer I
Yes No Support Frame, Reactor Containment Elev. 94' 11 1/2" 45 Reactor Coolant System, Pressurizer I
Yes No Support Frcmes Reactor Containment s,
L, Ele ~v. 94' 8 1/2" hl 46 Reactor Coolant System, Pressurizer I
Yes No Support Frame, Reactor Containment El ev _ 92' 8 5/8 "
47 Reactor Coolant System, Annulus Bet.
I No No 3;
A9-3 & A9-4, Reactor Containment gg El ey. 92' 5 5/16"
/
3 gg 48 Reactor Coolant System, Annulus Bet.
I No No
-4 A9-3 & A9-4, Reactor Containment 25 Elev. 92' 5 5/16" j;
49 Reactor Coolant System, Annulus Bet.
I No No A8-3 & A8-4 Reactor Containment Ele'. 92' 6 3/8" v
TABLE 3.7-4b 2-SAFETY RELATED MECHANICAL ' SNUBBERS *
- x E
A SHUBBER SYSTEM SMUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLY DIFFICULT l
NO.
DN, LOCATION AND ELEVATION INACCESSIBLE DURING SHUTDOWN **
TO REMOVE l
(A or I)
(Yes or No)
(Yes or ho) 50 Reactor Coolant System, Annulus Bet.
I No No A8-3 & A8-4, Reactor Containment Etev. 92' 6 3/8" 51 Stm. Gen. Drns. & Bldn., Bet. #13 I
Yes No Stm. Gen. & Crane Wall, Reactor Containment, Elev. 94' 8" j
52 CVC System, Off #14 RCP Platfm. 9 I
Yes No Valve 14CV-104, Reactor Containment s.
Ele'.103' 11 3/4" 2,
v
.h*
53 CVC System, Bet. #14 Stm. Gen. &
I Yes No Shield Wall, Reactor Containment EleV.100' 4 3/85 54 CC System, S.W. Corner of #13 RCP I
Yes No
(
I 3E Platfm., Reactor Containment 9
EleV.109' 0" E9 55 CC System, Bet. W. Side of #13 RCP I
Yes No Platfm. & Wall, Reactor Containment is EleV.102' 4" 56 RHR & SI System, #14 Stm. Gen. Near I
Yes No N.S. Centerline of Containment, Reactor Containment, Elev. 98' 0" 1
TABLE 3.7-4b h
SAFETY RELATED MECHANICAL SNUB 8ERS*
5
!ii A
SNUBBER SYSTEM SMUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLY DIFFICULT NO.
DN, LOCATION AND ELEVATION INACCESSIBLE DURING SHUTDOWN **
TO REMOVE (A or I)
(Yes or No)
(Yes or No) 57 RHR & SI System, 8et. #14 Stm. Gen.
I Yes No
& Crane Wall, Reactor Containment Eley. 98' 0" 58 RHR & SI System,10' 41/8" So. of A
No No 11.2, 7' 0" East of HH, N. Pen. Area.
Elev. 85' 2" Id 59 RHR & SI System,10' 41/8" So of A
No No 11.2, 7' 0" East of flH, N. Pen. Area, 7'
Elev. 85' 31/2" ti 60 RHR & SI Systen,10' 4 1/8"'So. of A
No No 11.2, 6' 9" East of HH, Pen. Area, Elev. 85' 31/2" 2
61 RHR & SI System,10' 41/8" So of A
No No
?!
11.2, 6' 9" East of HH, Pen. Area,
ll Elev. 87' 6" m'j 62 RHR & SI System, 8' 1" So. of 11.8, A
No No 22 7' 1" East of HH, Pen. Area, f'
El ev. 79' 6" 63 Cont. Spray System 2' 6" So. of 11.8, A
No No 6' 2" West of GG, Pen. Area, El et. 89' 0" i
4
/
TABLE 3.7-4b h5 SAFETY RELATED MECHANICAL SNUBBERS
- 9 E
Z SNUB 8ER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECI ALLY DIFFICULT NO.
ON, LOCATION AND ELEVATION INACCESSIBLE DURING SHUTDOWN **
TO REH0VE (A or I)
(Yes or No)
(Yes or No) 64 DELETED PER DCR flECl260 65 50 66 Stm. Gen. Fdwtr., 23' 4" So. of A
No No 11.8, 6' 6" West of DC, Pen. Area,
}[
Ele'.128' 10" v
67 Stm. Gen. Fdwtr., 23' 4" So. of A
No No 11.8, 6' 6" West of DC, Pen. Area.
Elev.128' 10" il 68 Stm. Gen. Fdwtr., 23' 4" So. of 11.8, A
No No 2' 0" East of DC, Pen. Area, lE Elev.130' 6" 2
E 69 Stm. Gen. Fdwtr., 23' 4" So. of 11.8, A
No No E2 2' 0" East of DC, Pen. Area,
[
Elev.130' 6" o
70 Stm. Gen. Fdwtr., Near East Wall.
A No No South Pen. Area, Elev.128' 10" l
l
t s
TABLE 3.7-4b Wp; SAFETY RELATED MECHANICAL SNUBBERS
- x E
A l
SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLY DIFFICULT NO.
DN, LOCATION AND ELEVATION INACCESSIBLE DURING SHUTDOWH**
TO REMOVE (A or I)
(Yes or No)
(Yes or No) l 71 Stm. Gen. Fdwtr., Near East Wall, A
No No l
South Pen. Area, Elev.128' 10" 72 Stm. Gen. Fdwtr., Outside East Wall, A
No No South Pen. Area, Elev.130' 6" 73 Stm. Gen. Fdwtr., 8' 4" So. of 11.8, A
No No 6' 6" West of DC, Pen. Area, u,
3:
Elev.108' 3" 74 Stm. Gen. Fdwtr., 8' 4" So. of 11.8, A
No No w
ff 6' 6" West of DC, Pen. Area, Elev.108' 9 1/8"-
75 Stm. Gen. Fdwtr., 8' 4" So. of 11.8, A
No No 6' 6" West of DC, Pen. Area, Elev.108' 9'1/8" N
92 76 Stm. Gen. Fdwtr., 8' 4" So. of 11.8, A
No No 6' 6" West of DC, Pen. Area.
E2 El et. 131 ' 2" 5
77 Stm. Gen. Fdwtr., 8' 4" So. of 11.8, A
No No 6' 6" West of DC, Pen. Area,
$2 El ev. 121 ' 2"
TABLE 3.7-4b 5;
SAFETY RELATED MECHANICAL SNUBBERS
- x E
i
CN, LOCATION AND ELEVATION INACCESSIBLE DURING SHUTDOWN **
TO REMOVE (A or I)
(Yes or No)
(Yes or No) 78 Stm. Gen. Fdwtr., S.E. Corner, A
No No South Pen. Area, Elev.108' 3" 79 Stm. Gen. Fdwtr., S.E. Corner.
A No No South Pen. Area, Elev. 108' 9 1/8" 80 Stm. Gen. Fdwtr., S.E. Corner, A
No No South Pen. Area Elev.131' 2" u,i 81 Stm. Gen. Fdwtr., S.E. Corner, A
No No u
L3 South Pen. Area, Elev. 131' 2" 82 M.S. SA Valve Strut, 23' 1 1/4" A
No No East of FF, South Pen. Area, Elev.104' 31/2" 2
83 M.S. SA Valve Strut,12' 0" A
No No di East of FF, South Pen. Area, 5
Eley.106' 0" di5 84 M.S. to Aux.FWP Exhaust, 8' 7" So. of A
No No 11.8, 16' 10" West of FF Pen. Area, se f'
Eley.~ 110' 5'1/2" i
l
TABLE 3.7-4b sy SAFETY RELATE 0 MECHANICAL SHUBBERS*
E 7
SHUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLY DIFFICULT NO.
ON, LOCATION AND ELEVATION INACCESSIBLE DURING SHUTDOWN **
TO REMOVE (A or I)
(Ves or No)
(Yes or No) 85 M.S. to FWP Exhaust, 8' 7" So. of A
No No 11.8, 16' 10" West of FF, Pen.
Area Elev. 110' 5 1/2" 86 M.S. to FWP Exhaust, 8' 1 1/8" North A
No No o' 12.3, 3' 8 3/8" East of LL, P'x. Bldg., Elev. 91' 2" 87 M.S. to FWP Exhaust, 8'1 1/8" North A
No No of 12.3, 3' 8 3/8" East of LL, u
Aux. Bldg., Elev. 91' 2" 88 M.S. to FWP Exhaust, 6' 4 3/8" North A
No No of 12.3, l' 101/8" East of LL, Aux. Bl dg., El ev. 90' 11" 3E 89 M.S. Yd FWP Exhaust, 6' 4 3/8" North A
No No E
of 12.3, l' 101/8" East of LL, E
Aux. Bldg., Elev. 90' 11" 90 M.S. to FHP Exhaust, 3' 3" North A
No No 5
of 11.8, 4' 7" East of LL, Aux. Bldg., El ev. 95' 0" o
91 M.S. to FWP Exhaust, 3' 3" North A
No No
- of 11.8, 4' 7" East of LL, s"
Aux. Bl dg., El ey. 95' 0" 4
9 TABLE 3.7-4b_
$g
' SAFETY RELATED MECHANICAL SNUBBERS
ON, LOCATION AND ELEVATION INACCESSIBLE DURING SHUTDOWN **
TO REMOVE (A or I)
(Yes or No)
(Yes or No) 92 CVC System, 3' 8" South of 12.3, A
No No l' 11" West of TT, Aux Bldg.,
Elev. 97' 2" 93 CVC System, 8' 4" North of 12.3, A
No No 3' 5" West of NN, Aux. Bldg.,
Elev.101' 11" 94 CC System, 6' 11' North of 12.3, A
No No 10' 9" East of GG, Aux. Bldg.,
y L,
Eleir. 96' 0" 95 CC System, 6' 11" North of 12.3, A
No No 10' 9" East of GG, Aux. Bldg.,
Eley. 96' 0" 96 CC System, 3' 5" North of 11.8, A
No No y
l' 3" East of JJ, Aux. Bldg.,
g Elev.107' 7" Eg 97 RHR h SI System,17' 10" South of A
No No a
14, 5' 6 1/4" East of RR, Aux. Bldg.,
l p
j Elev. 94' 7 1/2"
=
98
'RHR & 5I System,17' 10" South of A
No No i
14, 5' 6 1/4" East of RR, Aux. Bldg.,
EleV. 94' 7 1/2"
TABLE 3.7-4b T.g SAFETY RELATED MECHANICAL' SNUBBERS
- x E
ti i
SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLY DIFFICUL1 NO.
ON, LOCATION AND ELEVATION INACCESSIBLE DURING SHUTDOWN **
TO REMOVE (A or I)
(Yes or No)
(Yes or No) 99 RHR & SI System, 7' 9" South of A
No No 14, 4' 11" East of LL, Aux. Bldg.,
Elev. 94' 7 1/2" 100 RHR & SI System, 7' 9" South of A
No No 14, 3' 3" East of LL, Aux. Bldg.,
Elev. 94' 7 1/2" le 1 01 RHR & SI System,113/4" North of A
No No 13.2, 4 3/8" East of HH, Aux. Bldg.,
7' El ev. 86' 3" E!
=
102 RHR & SI System,11 3/4" North of A
No No 13.2, 4 3/8" East of HH, Aux. Bldg.,
El ey. 86' 3" 103 RHR & SI System, 8' 9" South of A
No No 13.2,.9' 10" East of SS, Aux. Bldg.,
2 Elev. 86' 1" sg 1 04 RHR & SI System, 8' 9" South of A
No No g
13.2, 9' 10" East of SS, Aux. Bldg.,
H Eley. 86' 1" 5
TABLE 3.7-4b h$
SAFETY RELATED MECHANICAL SNUBBERS
- 9 E
A SHUBBER SYSTEM SNUBBER INSTALLED ACCESS!BLE OR HIGH RADIATION ESPECIALLY DIFFICULT NO.
ON, LOCATION AND ELEVATION INACCESSIBLE DURING SHUTDOWN **
TO REMOVE (A or I)
(Yes or No)
(Yes or No)
S J
105 1
106 DELETED-REPLACED WITH RIGID STRUTS 107 108 ed 109 Spent Fuel Cooling System, S' 0" A
No No South of 12.3, 10' 2" East of LL, id Aux. Bldg., Elev. 94' 7" t!
o
- Snubbers may be added to safety related systems without prior License Amendment to Table 3.7-4b 3;
provided that a revision to Table 3.7-4b is included with the next License Amendment request.
Ey
- Modif.ications to this column due to changes in high radiation areas may be made without prior g;
. License Amendment provided that a revision to Table 3.7-4b is included with the next License
-4 Amendment request.
5
REO UNITED STATES NUCLEAR REGULATORY COMMISSION g
a wasmmaTom, o. c. 2 ossa Y
%,.... J PUBLIC SERVICE ELECTRIC AND GAS COMPANY P!!ILADELPHIA ELECTRIC COMPANY del'MARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-311 SALEM NUCLEAR GENERATING STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 5 License No. DPR-75 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for snendment by Public Service Electric and Gas Company, Philadelphia Electric Company, Delmarva Power and Light Company and Atlantic City Electric Company (the licensees) dated August 10, 1981, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I:
B.
The facility will operate in con'formity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized
~
by this amendment can be conducted without endangering the health t
and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and l
E.
The issuance of this amendment is in accordance with 10 CFR Part l
51 of the Commission's regulations and all applicable requirements have been satisfied.
. 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-75 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 5, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
F R THE NU EA REGULATORY COMMISSION h
)
ev Varg,
Operating Reactorsi ranch #1 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
February 2,1982 l
i i
4TTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 5 TO FACILITY OPERATING LICENSE NO. DPR-75 DOCKET NO. 50-311 Revise Appendix A as follows:
Remove Pages Insert Pages 3/4 7-23 3/4 7 '
3/4 7-25 3/4 7-25 3/4 7-29 3/4 7-29 3/4 7-30 3/4 7-30 3/4 7-30a through 3/4 7-301 0
- - - - ~.
PLANT SYSTEMS 3/4.7.9 SNU8BERS LIMITING CONDITION FOR'0PERATION 3.7.3 All snubbers listed in Tables 3.7-4a and 3.7-46 shall be OPERA 8LE.
APPLICA8ILITY: MODES 1, 2, 3 and 4.
(MODES 5 and 6 for snubbers located on systems required OPERABLE in those MODES).
ACTION:
With one or more snubbers inoperable, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, replace or restore the inoperable snubber (s) to OPERA 8LE status and perform an engineering evaluation per Specification 4.7.9c on the supported component or declare the supported system inoperacle and follow appropriate ACTION statement for that system.
SURVEILLANCE REQUIREMENTS 4.7.9 Each snubber shall be demonstrated OPERABLE by performance of the folicwing augmented inservice inspection program and the requirements of Specification 4.0.5.
a.
Visual Insoection The first inservice $1:aal inspection of snubbers shall be performed after four months but within 10 months of POWER OPERATION and shall include all snubbers listed in Tables 3.7-44 and 3.7-4b.
If less l
than two (2) snubbers 'in the same Table are found inorje:able duri.sg the first inser'vice visual inspection, the second inservice visual inspection for snubbers in that Table shall be performed 12 months i 254 from the date of the first inspection. Otherwise, subsequent visual inspections shall be performed for each separate Table in accordance with the following schedule:
(.
No. Inoperable Snubbers in Subsequent Inspection Period a Table per Inspection Period for each Table *8 0
18 mont.hs 1 25%
1 12 moatas i 25%
2 6 acaths i 254 3, 4 124 days t 254 5,6,7 62' days t 25%
8 or more 31 days 2 25%
Within each Table, the snubbers may be categorized into two <Joups:
These accessible and those inaccessible during reactor operation.
Each group within a Table may be inspected independently in accordance with the above schedule.
'The inspection interval shall not be lenghthened more than one step at a time.
- The provisions of Specification 4.0.2 are not applicable.
t SALEM - UNITZ 3/4 7-23 Amendment No. 5
-p
,-.,--.,e-----
V 1
PLANT SYSTEMS SURVEILLANCE RECu!REMENTS (Continued) and 3.7-4b say be used jointly or separately as the basis for the sampling plan.
In addition to the regular sample, snubbers which failed the previous functional test shall be ratested during the next test period.
If a spare snucber has been installed in place of a failed snuceer, then both the failed snuceer (if it is repaired and installed in another position) and the spare snubter shall be retested. Test results of these snubbers may not be included for the re-sampling.
If any snubber selected for functional testing either fails to lockup or fails to move, i.e., frozen in place, the cause will be evaluated and if caused by manufacturer or design deficiency all snubbers of the same design subject to the same defect shall be functionally tested. This testing requirement snall me indeoendent of the requirements stated acove for snuheers not setting tne functional test acceptance criteria.
For the snuteer(s) found inoperable, an engineering evaluation sna11 De performed on the components which are supported oy the snuccer(s).
The purpose of this engineering evaluation shall be to determine if tne conconents succorted by the snutber(s) were adversely affected by the inoperacility of the snumber(s) in order to ensure that the supported component remains capable of meeting the designed service.
d.
Hycraulic Snutters cunctional Test Accectance Criteria
~
The hydraulic snucber functional test shall verify that:
1.
Activation (restraining action) is achieved witnin the specifiec range of velocity or acceleration in both tension and comoression.
2.
Snubter bleed, or release rate, where required, is wi*nin tne specified range in compression or tension. For snuceers specifically required to not displace under continuous load, the ability of the snubber to withstand load witnout displace-sent shall be verified, e.
Meenanical Snutters cunctional Test Accectance Criteria The mechanical snutter functional test shall verify that:
f 1.
The force that initiates free movement of the snuccee red 'n d either tension or compression is le.s tnan the specifisc max mum drag force. The drag force sna11 rot have increased more taan SC% since the last functional test.
2.
Activation (aestraining action) is achieved witnin the specif'ec range of velocity or acceleration in motn tensio'n anc comoresst:r.
SALEM - UNIT 2 3/4 7-25 Amendment No. 5 p e g
-, - ~,.
y g-
-,, - - - - -, +
1 l
vs#
IAulE 3.7-4a (Continued)
'E SAFETY REIAllD llYDilAUIIC SNUB 8[R$*
E U
SHIN 181 R SY5ilH SNHBBER INSTALI[D ACCESSIBLE OH lilGil RADIAll0N ESPECIALLY DIFFICULT l
NO.
ON, ~IUCAll0N ANil Et[VAll0N INACCESSIBIE IMARING SilulDOWN**
10 REMOVE
~
(A or l}~
7 Yes or No)
(Yes or No) l 17.
No. 21 &in Steam Isolation Valve A
No Yes Penetration Area, Elev. 115' $"
18.
No. 21 Main Steam Isolation Valve A
No Yes Penetration Area, Elev. 115' 5" 19 No. 22 N in Steam Isolation Valve
.A No Yes Penetrattori Area, Elev. 115' 5" s
y 20.
No. 22 Main Steam isolation Valve A
No Yes i
5-Penetration Area, Elev. 115' 5" 7
gg 21.
No. 23 Main 5'eam Isolation Valve A
No Yes Penetration Area, Elev. 115' 5" 22s No. 23 N in Steam Isolation Valve A
No Yes
-Penetratiosi Area, Elev. 115' 5" R
23 No. 24 h in Steam isolation Valve A
No Yes
{
Penetration Area, Elev. 115' 5" e
'24.
No. 24 N in Steam Isolation Valve A
No Yes Penetration Area, Elev. 115' 5" N
Snubliers may be adileil to safety related systems without prior License Amendment to Iahle 3.1-4a provided l
that a revisioni to latile 3.1-4a is included with the next Lice.ase Amendment request.
^^ Hinliticatiness tu tiils colisin due to changes in liigh radiation areas may be made without prior License i
Amesulment provideal that a revision to I4hle 3.7-4a is included with the next License Amendment request.
1 TABLE 3.7-4b El SAFETY ~ RELATED MECHANICAL SNUBBER 5*
E 2
E 4
ri to SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLY DIFFICULT NO.
ON, LOCATION AND ELEVATION INACCESSIBLE DURING SHUTDOWN **
TO REMOVE (A or I)
(Yes or No)
(Yes or No) 1 Reactor Coolant System. Pressurizer I
Yes NO -
S.E. Quadrant, Reactor Containment El ev. 141 ' 3" 2
Reactor Coolant System, Pressurtzer I
Yes No S.E. Quadrant, Reactor Containment u,
Elev. 141' 3" 1;
3 Reactor Coolant System, Pressurizer I
Yes No
-4 L3 S.W. Quadrant, Reactor Contalmnent i
Elev. 141' 3" 4
Reactor Coolant System Pressurizer I
Yes No N.E. Quadrant, Reactor Containment Eley. 148' 6" i
5 Reactor Coolant System, Pressurizer I
Yes No 3;
N.W. Quadrant, Reactor Containment gg Elev.147' 0" EE 9
6 Reactor Coolant System, Pressurizer I
Yes No N.E. Quadrant, Reactor Containment
-1 Elev. 147' 0" 7
Reactor Coolant System, Pressurizer I
Yes No N.W. Quadrant, Reactor Containment EleV. 147' 0"
TABLE 3.7-4 b i
' SAFETY'RELATED MECHANICAL' SNUBBERS
- g E
M SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLY DIFFICULT NO.
ON, LOCATION AND ELEVATION INACCESSIBLE DURING SHUT 00Wt8**
TO REMOVE (A or I)
(Yes or No)
(Yes or No) 8 Reactor Coolant System, Pressurizer I
Yes No 1
S.W. Quadrant.at valve 2PR-1, Reactor l
Containment, Elev. 152' 1 7/8" 9
Reactor Coolant System, Pressurizer I
Yes No S.W. Quadrant, Reactor Containment Elev.145' 51/4 "
i 1
[
10 Reactor Coolant System, Pressurizer I
Yes No s
S.W. Quadrant, Reactor Containment e5 Elev. 143' 0" 11 Reactor Coolant System, Pressurizer I
Yes No S.W. Quadrant, Reactor Containment Elev.143' 0" 12 Reactor Coolant System, Pressurizer I
Yes ho S.W.-Quadrant, Reactor Containment 2y Elev. 148' 0" x
13 Reactor Coolant System, Pressurizer I
Yes No h
S.E. Quadrant at valve 2PR-47, Reactor y
Containment, Elev.156' 8" o
14 Reactor Coolant System, Pressurizer I
Yes No S.W. Quadrant, Reactor Containment Elev. 156' 8"
TABLE 3.7-4b E
S AFETY ' RELATED MECHANI CAL ' SNUBBERS
- Gc E
SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLY DIFFICULT NO.
ON, LOCATION AND ELEVATION INACCESSIBLE DURING SHUTDOWN **
TO REMOVE (A or I)
(Yes or No)
(Yes or No) 15 Reactor Coolant System, Pressurizer I
Yes No S.E. Quadrant, Reactor Containment Elev.145' 0" 16 Reactor Coolant System, Pressurizer I
Yes No S.E. Quadrant, Reactor Contaimnent Elev.145' 0" R
17 Reactor Coolant System, Pressurizer I
Yes No
,4 S.E. Quadrant, Reactor Containment g
Elev.145' 0" er i
18 Reactor Coolant System Pressurizer I
Yes No S.W. Quadrant, Reactor Contaimnent Elev.156' 8" l
19 Reactor Coolant System. Pressurizer I
Yes No 2
N.W. Quadrant, Reactor Containment M
Elev.141' 0" l
Ess 20 Reactor Coolant System, Pressurtizer I
Yes No Ei S.W. Quadrant, Reactor Containment Elev. 148' 0" 2
P 21 Reactor Coolant System, Pressurizer I
Yes No ui Support Frame, Reactor Containment Elev. 94' 10 5/8"
TABLE 3.7-4b a
h$
' SAFETY RELATED MECHANICAL' SNUBBERS
- G iE Z
m.
SHUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HIG: RADIATION ESPECIALLY DIFFICULT NO.
ON, LOCATION AND ELEVATION INACCESSIBLE DURING SHUTDOWN **
10 REMOVE (A or I)
(Yes or No)
(Yes or No) 22 Reactor Coolant System, Pressurizer I
Yes No Support Frame, Reactor Contaimnent Elev. 94' 10 5/8" 23 Reactor Coolant System, Pressurizer I
Yes No Support Frame, Reactor Containment Elev. 92' 8 5/8" R**
24 Reactor Coolant System, Annulus Bet.
I No; No-7' B9-3 & B9-4, Reactor Contaimnent 8
Elev. 92' 5 5/16" n
25 Reactor Coolant System. Annulus Bet.
I No No B9-3 & B9-4, Reactor Contaimeent Elev. 92' 5 5/16 "
$E 26 Reactor Coolant System. Annulus Bet.
I No No G!
B8-3 & 88-4, Reactor Containment 5!
Elev. 92' 6 3/8" 9
-1 27 Reactor Coolant System, Annulus det.
I No No Ei B8-3 & B8-4, Reactor Containment Elev. 92' 6 3/8" u,
28 CVC System East Side of #22 RCP I
Yes No PLTFM i Wall, Reactor Containment Elev 102' 31/4 "
i
TABLE 3.7-4 b g;
' SAFETY RELATED MECHANICAL SNUBBERS *
=
E "4
m SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLY DIFFICULT NO.
ON, LOCATION AND ELEVATION INACCESSIBLE DURING SHUTDOWN **
TO REH0VE (A or I)
(Yas or No)
(Yes or hu) 29 CC System, N.E. Corner of #24 I
Yes No RCP Platform, Reactor Containment Elev.101' 91/4" 30 CC System, Bet. West Side of #24 I
Yes No RCP Platform & Wall, Reactor Containment, Elev. 90' 6" M**
31 RHR & SI System Annulus 0 B8-3 I
No No
.d Reactor Containment, Elev. 85' 9" U
cm 32 RHR & SI System, Annulus 0 B6, I
No No Reactor Containment, Elev. 80' 9" 33 RHR & SI System, Bet. #23 Stm. Gen.
I Yes No Fr. &.#23 RCP Fr.. Reactor Containment 3;
Elev 94' 4" 9
E 34 RHR & SI System, Bet. S.W. Side of I
Yes No 9
- 24 RCP Fr. & Wall, Reactor Containment
-i Elev. 88' 7" 5
l 35 RHk & SI System, Bet. #24 Stm. Gen.
I Yes No Frame & Crane Wall, Reactor Containment Elev. 97' 11 1/8"
TABLE 3.7-4b f
' SAFETY ~ RELATED MECHANICAL ' SNUBBERS
- E E
Z SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLY DIFFICULT.
NO.
ON, LOCATION AND ELEVATION INACCESSIBLE DURING SHUTDOWN **
TO REMOVE (A or I)
(Yes or No)
(Yes or No) 36 RHR & SI System, S.E. Corner I
Yes No of #23 Stm. Gen. Fr., Reactor Containment, Elev. 93' 6" 37 RHR &*SI System, Bet. So. Side I
Yes No of Press. Frame & Wall, Reactor Containment, Elev. 93' 6" t'.
38 Stm Gen. Drns.& Bldn, 6" North of A
No No 7'
17.6, 19 1/2" West of JJ, S. Pen.
8 Area, Elev.108' 7" n
39 Stm. Gen. Drns. & Bldn.4' 1" North A
No No of 17.6, 6' 6" West of JJ S. Pen.
Area, Elev.108' 7" l
40 Stm. Gen. Drns. & Bldn., Annulus 9" I
No No a
West of B16-2, Reactor Containment 73 Elev. 90' 61/2 "
8 M
41 Stm. Gen. Drns. & Bldn., S.E. Corner I
Yes No
'i of #23 Stm, Gen. Fr., Reactor Containment, Elev. 99' 6" l
g m
42 Containment Spray, 2' 6" North of 16.2, A No No 1
l 6' 2" West of GG, S. Pen. Area, l
Elev 88' 3" I
l l
i TABLE 3.7-4b E2
' SAFETY 'RELATED MECHANICAL SNUBBER 5*
m=
1
.-4 ru SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLY DIFFICULT NO.
ON, LOCATION AND ELEVATION INACCESSIBLE DURING SHUTDOWN **
TO REH0VE (A or I)
(Yes or No)
(Yes or No) 43 St. Gen. Fdwtr., 23' 4" No. of A
No No 16.2 6' 6" West of DC, S. Pen.
Area, Elev.128' 10" 44 St. Gen. Fdwtr., 23' 4" No. of A
No No i
16.2 6' 6" West of DC, S. Pen.
Area, Elev.128' 10" 41 45 St. Gen. Fdwtr., 23' 4" No. of A
No No 16.2, 2' 0" East of DC S. Pen.
{
Area, Elev.130' 6" o
46 St. Gen. Fdwtr., 23' 4" No. of A
No No 16.2, 2' 0" East of DC, S. Pen.
Area, Elev.130' 6" 47 St. Gen. Fdwtr., Near East Wall, A
No No '
3; N. Pen. Area, Elev. 128' 10" 9g 48 St. Gen. Fdwtr., Near East Wall, A
No No
{
N. Pen. Area, Elev.128' 10" g
49 St. Gen. Fdwtr,. Outside East Wall, A
No No N. Pen. Area, Eley. 130' 6" o
u.
TABLE 3.7-4b h
SAFETY RELATED' MECHANICAL SNUBBERS
- i g
E G
~
SHUBBER SYSTEM SaluBBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLY DIFFICULT NO.
ON, LOCATION AND ELEVATION INACCESSIBLE DURING SHUTDOWr8**
TO REMOVE (A or I)
(Yes or No)
(Yes or No) 50 St. Gen. Fdwtr., 8' 4" No. of A
No No 16.2 6' 6" West of DC, S. Pen.
Area. Elev.108'. 3" 51 St. Gen. Fdwtr., 8' 4" No. of A
No No 16.2, 6' 6" West of DC. S. Pen.
Area, Elev. 108' 9 1/8" R
52 St. Gen. Fdwtr., 8' 4" No. of A
No No 16.2, 6' 6" West of DC S Pen 7'
Area Elev. 108' 9 1/8" 8
53 St. Gen. Fdwtr., 8' 4" No. of A
No No 16.2, 6' 6" West of DC, S. Pen.
l Area, Elev. 131' 2" 3
54 S t. Gen. Fdwt r., 8 ' 4" No. o f A
No No G
16.2, 6' 6" West of DC. S. Pen.
Area Elev. 131' 2" g
55 St. Gen. Fdwtr., N.E. Corner, A
No No 5
H. Pen. Area Elev.108' 3" 56 St. Gen. Fdwtr., N.E. Corner, A
No No N. Pen. Area, Elev. 108' 9 1/8" l
i l
l l
TABLE 3.7-4b GI SAFETY RELATED MECHANICAL ~ SNUBBERS
- x 4
EE Z
ro SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLY DIFFICULT NO.
ON, LOCATION AND ELEVATION INACCESSIBLE DURING SHUTDOWN **
TO REMOVE (A or I)
(Yes or No)
(Yes or No) 57 St. Gen. Fdwtr., N.E. Corner, A
No No H. Pen. Area, Elev.131' 2" 58 St. Gen. Fdwtr., N.E. Corner, A
No No N. Pen. Area, Elev.131' 2"
, 59 Main St. Drn.,13' 4" No. of
.A No No 16.2, 13' 6 3/4" West of DC, w
3:
S. Pen. Area, Elev.102' 1" 2
60 Main St. Drn., 27' 7" No. of A
No No EE 16.2, 8' 10" West of DC, S. Pen.
Area, Elev. 112' 0" 61 Main St. Drn., 27' 7" No. of A
No No 16.2, 9' 8 3/4" West of DC, S. Pen. Area, Elev. 112' 0" ll 62 Main St. Drn., 24' 1" No. of A
No No gg 16.2, 9' 4 3/4" West of DC, g
S. Pen. Area, Elev.103' 3" 2
[
63 RHR & SI System,17' 10" No. of A
No No o
14,5' 6 1/4" East of RR, Aux.
Bldg., Elev. 94' 7 1/2"
i e
TABLE 3.7-4b y,
2 hj SAFETY ~ RELATED MECHANICAL ~ SNUBBERS
ON, LOCATION AND ELEVATION INACCESSIBLE DURING SHUTDOWit**
TO REMOVE (A or I)
(Ves or ho)
(Yes or No) 64 RHR & SI System,17' 10" No.
A No No 1
of 14 5' 61/4" East of RR, Aux. Bldg., Elev. 94' 7 1/2" 65 RHR & SI System, 7' 9" No. of A
No No 14,4' 6" East of LL, Aux. Bldg.,
Eiev. 94' 7 1/2" R
66 RHR & SI System, 7' 9" No. of A
No No y
14, 2' 10" East of LL, Aux.
g2 Bldg., Elev. 94' 7 1/2" 67 RHR & SI System, 7' 7 7/8" So. of A
No No 17.6, 7' 0" East of HH, S. Pen.
Area, Elev. 87' 1" 68 RHR & SI System, 7' 7 7/8" So. of A
No No
,,g 17.6, 7' 0" East of HH, S. Pen.
sg Area, Elev. 86' 21/4" 2
69 RHR & SI System, 7' 7 7/8" So. of A
No No t
17.6, 6' 3" East of HH, S. Pen.
2 Area, Elev. 85' 41/4" c) 70 RHR & SI System, 7' 7 7/8" So. of A
No No 17.6. 6' 3" East of HH, S. Pen.
Area, Elev. 85' 0 3/4".
i
TABLE 3.7-4 b_
$.{
SAFETY RELATED MECHANICAL SNUBBERS
- E7 SHUBBER SYSTEM SNURBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLY DIFFICULT NO.
ON, LOCATION AND ELEVATION IN'CCESSIBLE DURING SHUTDOWt4**
TO REMOVE (A or I)
(Yes or No)
(Yes or No)
I 71 RHR & SI System, 8' 01/2" No. of A
No No l
16.2, 7' S 3/16" East of HH, S. Pen. Area. Elev. 79' 6" 72 RHR & SI System, 8' O 1/2", No.
A No No of 16.2 7' 5 3/16" Eas~t of HH, S. Pen. Area, Elev. 79' 6" R
73 RHR & SI System, 8' 9" No. of A
No No 14.8, 9' 10" East of SS, Aux.
?
Bldg., Elev. 86' 1" 74 RHR & SI System,-8' 9" No. of A
No No 14.8, 9' 10" East of SS, Aux.
Bldg., Elev. 86' 1" 75 R!;R & SI System,:5' 51/2" So. of A
No No 14.8,1" West of HH, Aux. Bldg.,
G Elev. 78' 0" E
G 76 M.S. To Aux. FilP. Exhaust, 4' 0" A
No No H
So. of 16.2,12' 0" West of KK, 5
Aux. Bldg., Elev. 97' 6" 77 M.S. To Aux. FNP. Exhaust, 71/16" A
No No North of.15.7, 6' 3" East of LL, Aux. Bldg., Eley, 92' 0" 1
TABLE 3.7-4b_
SAFETY ' RELATED MECHANICAL ' SNUBBERS
ON, LOCATION AND ELEVATION INACCESSIBLE DURING SHUTDOWt8**
TO REMOVE (A or I)
(Yes or No)
(Yes or No) 78 M. S. To Aux. FWP. Exhaust, 7 1/16" A
No No i
North of 15.7. 6' 3" East of LL, Aux. Bldg., Elev. 92' 0" l
79 M.S.
To Aux. FWP. Exhaust, 71/16" A
No No
'i North of 15.7. 3' 8" East of LL, Aux. Bldg., Elev. 89' 6" R
80 M.S. To Aux. FWP. Exhaust, 7 1/16" A
No No North of 15.7. 3' 8" East of LL, i
?
Aux. Bldg., Elev. 88' 6" E
81 M.S. To Aux. FWP. Exhaust, 7 1/16" A
No No North of 15.7, 3' 8" East of LL, Aux. Bldg., Elev. 88' 6" 82 M.S. To Aux. FWP. Exhaust, 11 11/16" A
No No So. of 15.7, 8' 7 5/8" East of LL,
>y Aux. Bldg., Elev. 92' 0" k
83 M.S. To Aux. FWP. Exhaust,11 1T716" A
No No "i
So. of 15.7, S' 3 5/8" East of Lt.
Aux. Bldg., Elev. 92' 0" 84 CVC System, 8' 4" So, of 15.7, 3' 5" A
No No u,
West of NN, Aux. Bldg., Elev.101' 11"
4 TABLE 3.7-4b s
r
[j SAFETY RELATED MECHANICAL SNUBBERS
ON, LOCATION AND ELEVATION INACCESSIBLE DURING SHUTDOWt4**
TO REMOVE (A or I)
(Yes or No)
(Yes or No) 85 CC System, 6' 11" So. of 15.7 A
No No 10' 9" East of GG, Aux. Bldg.,
Elev. 96' 0" 86 CC System, 6' 11" So. of 15.7 A
No No 10' 9" East of GG, Aux. Bldg.,
Elev. 96' 0" M**
87 u
h 88 DELETED-REPLACED WITH RIGID STRUTS 89 90 h(
91 Spent Fuel Cooling, 4' 6" No of A
No No g
15.7, S' 1/2" West of JJ Aux. Bldg.,
gj Elev. 92' 3" 5
g
- Snubbers may be added to safety related systems without prior License Amendment to Table 3,7-4b provided that a revision to Table 3.7-4b is included with the next License Amendment request, u,
- Modifications to this column due to changes in high radiation areas may be made without prior License Amendment provided that a revision to Table 3,7-4b is included with the next License Amendment request.