ML20004E702
| ML20004E702 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 05/06/1981 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20004E703 | List: |
| References | |
| NUDOCS 8106150080 | |
| Download: ML20004E702 (8) | |
Text
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(o UNITED STATES NUCLEAR REGULATORY COMMISSION fg
- g WASHINGTON, D. C. 20$$5 p
%pC f COMMONWEALTH EDISON COMPANY DOCKET NO. 50-237 1
DRESDEN STATION, UNIT NO. 2 AMEN 0 MENT TO PROVISIONAL OPERATING LICENSE Amendment No. 60 License No. DPR-19 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated March 27, 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 operats in conformity with the appli-cation, the provisions of the Act, and the rules and regulations of the Commission; i
C.
There is reasonable assurance (i) that the activities l
authorized by this amendment can be conducted without t
endangering the health and safety of the public, and '
l' (ii) that such activities will be conducted in compliance with the Commission's regulations; f
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 j
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.
l t
THIS DOC'JMENT CONTAINS M W MS 81061500W
~
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 3.B of Provisional Operating License No.
DPR-19 is hereby amended to read as follows:
3.B Techn.ical Specifications The Technical Specifications contained in Appendix A as revised through Amei.dment No. 60, 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 issuance.
FOR THE NUCLEAR REGULATORY COMMISSION en s tc Operating Reactors Branch #5 Division of Licensing Date of Issuance:
May 6,1981 h.,
O 9
l I
O
ATTACHMENT TO LICENSE AMENDMENT NO. 60 PROVISIONAL OPERATING LICENSE N0. DPR-19 DOCKET NO. 50-237'
, = -
1 Replace page 91b, 91d, and 91e with the enclosed page 91b and add the following new pages: 91 d-1, 91 d-2, 91 e-1 and 91 e-2 e
l-O
'DPR-19 3.6 LIMITING CONDITION FOR OPERATION 4.6 SURVEILLANCE REQUIREMENT I.
Shock Suppressors.(Snubbers)
I.
Shock Suppressors '(Snubbers) i.
During all modes of operation except The following surveillance requirements 2
cold shutdown and refuel, all safety-apply to all hydraulic snubbers listed i
related snubbers listed in Tables
~..
in Table 3.6.la.
~
j 3.6.la and b shall be operable except i
as noted in Specification 3.6.I.2 1.
All hydraulic snubbers whose seal l
through 3.6.I.4.
raterial has been demonstrated by operating experience, lab testing -
4
}
2.
From and after the time that a snubber or analysis to be compatible with in detennined to be inoperable, continued the operating environment shall be reactor operation is pennissible only visually inspected.
This inspec-a i
during the succeeding 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> unless the tion shall include, but not neces-i snubber is sooner made operable or replaced.
sarily be limited to inspection of Torus ring header snubbers may be inoperable the hydraulic fluid reservior, fluid-i in groups of up to three (3) pairs until connections, and linkage connection September 1,1980, to facilitate the to the piping and anchor to verify installation of Mark I Torus Support snubber operability. in accordance j
Modi fications.
with the following schedule:
j.
No. of Snubbers Found 3.
If the requirements of 3.6.I.1 and Inoperable During In-Next Required 3.6.I.2 can not be met,. an orderly Spection Interval Inspection Interval 5
shutdown shall be initiated and the f
reactor shall be in cold shutdown or 0
18 months i 25%
refuel condition within a6 hours.
j 1
12 months i 25%
2 6 months i 25%
i 4.
If a snubber is determined to be 3, 4
,124 days i 25%
1 inoperable while the reactor is in the cold 5, 6, 6
q shutdown or refuel mode, the snubber shall 3
ys i
be made operable or replaced prior to I
reactor startup. This requirement does not The required inspection intervai shall apply to torus ring header' snubbers for the not be lengthened more than one step period identified in paragraph 3.6.I.2 above.
at a time.
t j
5.
Snubbers may be added to safety related
{
systems without prior license amendment to 1
Tables J.6.la and b prov'ided that a revision i
to Tables 3.6.la and b is included with the l
next license amendment request.
Amendment No. p[ 60 91b i
i
TABt2 3'.6.In i
SAFETY RELATED HYDRAULIC SNUBBERS
)
SNUBBERS SilHRDERS SHUBBRR IN HICil INACCESSIBLE ACCESSlHl.1 I
SHtJRRER LOCATION ELEVATION AZlHUTil RADIATION AREA DURING HolulAL DllRIHC HORit l
HO.
DURIHC SillfTDOWN 01' ERA TION Ol' Ell AT I Oi!,
2 Torus Ring Ileader 1501-24" 483' 83*
X i
3 Tori.s Ring IIcader 1501-24" 483' 74*
X 1
)
4 Torus Ring IIcader 1501-24" 483' 38' X
i 5
Torus Ring Ileader 1501-24" 483' 29*
X 1
i 7
Torus Ring Ilcader 1501-24" 483' 331' X
)
8 Torus Ring Ileader 1501-24" 483' 322*
X 4
286*
X 4
j 9
Torus Ring Ileader 1501-24" 483' 10 Torus Ring Ileader 1501-24" 483' '.
277*
E X
i i
12 Torus Ring Ileader 1501-24" 483' 218" h.
X j4 1
13 Torus Ring lleader 1501-24" 483' 209*
X i
Il 15 Torus Ring llender 1501-24" 483' 151' X
i X
16 Torus Rins llender 1501-24" 483' 142" l
b*
\\,-
1
- Ho.llIIcations to this table due to changes In high radiatiosi should be nubesitted to the NRC se part of the next itcense I
Amendment No. 60 onenilinent request.
I1 91d-1
i TAB 12 3.6.In SAFETY RELATED HYDRAULIC SNUBBER 8 h
l SHUBBERS Sil0BRERS SHUBBER IN M1 Cit INACCESS13LE ACCESSIBLE
, Sil0BBER LOCATION ELEVATION AZlHUTII RADIATION AREA DURIHC HORMAL DURING IM)RilAll i
HO.
~
DURIHC SilUTDOWN OPERATION Ol' ERAT 10ll i
Isolation Condenser Pipeway Room:
{
1 Isolation condenser Line 1303-12" 558' 180*
X X
4 2
Isolation Condenser Line 1303-12" 568' 180*
X X
i 3
Isolation condenser Line 1302-14" 580' 195" X
X l
4 i
L 1
]
I 1
i l
)
l i
license f 'Hodificat ions to thle table due to chances in high radiation ohnold be subesitted to the NRC as part of the next 91d-2 essendem ut request.
Amenenent No. 60
TABLE 3.6.lb I
1 SAFETY RELATED MECHANICAL 8NUBBERS SNUBBERS SHulinElis SNUBBER IN HICll INACCESSIBLE ACCESSIBLE l
StlilnllER LOCATION ELEVATION AZIHUTil RADIATION AREA DURING NORMAL DURIlH: HORilAI.-
NO.
DURING SilUTDOWN OPERATION UPI.RATIOli 1
Drywell itectrc. Motor 25-202 524' 328' X
X 2
Drywell Recire. Hotor 2B-202 524' 302*
x x
'a Drywell Recirc. Motor 2H-202 524' 315*
X X
l 4
Drywell Recire. Hotor 2A-202 524' i48*
X X
j 5
l)rywell Recire. Motor 2A-202 524' 122' x
x
]
6 Dryuell Recire. Hotor 2A-202 524' 135*
X X
7 Dryuell Recire. Pump 28-202 512' 326' N
X i
304*
x x
8 Dryuell Recire. Pump 211-202 512' 9
Dryuell Recirc. Puwp 211--202 517' 315' X
X 10 liryuell Recire. Pump 2A-202 512' 124' x
x 11 Dryuell Recire. Pump 2A-2(12 312' 146*
K X
12 Daywell Recire. Pump 2A-202 507' 135" X
X 11-16 lu m ved i
I7 Dtyw11 Itecirc Ileader 201n-22" -
533'6" 195 X
X 18-20 lo.1 roved 21 Drywell Recire lleader 201A-22" 533'6" 22 X
X 22-23 lum ived 24 D ywl1 Feedwater Line 3204D-12" 538' 108 X
X 25-29 Itcmved 30 Drywell Core Spray Line 1403-10" 575' 336*
X X
31 Drywell Core Spray Line 1404-10" 562' 231*
X X
i 32 Drywell Targst Rock Valve 203-3A 542'6" 16*
K X
31 11rywell Target Rock Valve 203-3A 542'4" 31*
X X
34 11rywell Target Rock Valve 203-3A 540'0" 19*
'K X
35 Drywell Target Rocit Valve 203-3A 540'3" 34*
X X
4 36 Drywell Recire. Line 201B-28" 518' 270*
K X
j 1
!! todifications to this table due to changes in high radiation sh'ould be submitted to the HRC as part of the next license nendment request.
Amendment No. 60 91e-1
l TABLE 3.6.lb 8AFETY RELATED MECHANICAL 8NUBBERS i
SHUBBERS SHUBBERS SHUBBER IN HICH INACCESSIBLE ACCESSIBl.E l
SHURBER LOCATION ELEVATION AZlHUTil RADIATION AREA DURING NOR}tAL DURIllG HohttAt j
NO.
DURINC B?.lUTDOWN OPERATION OPEllATION i'
37 Drywell Recire. Line 201A-28" 518' 90 X
X 38 Drywell Shutdown Cooling Line 1001A-16" 523' 0*
X X
39 Drywell Rx Water Cicanup Line 1201-8" 533' 316*
X X
40 Drywell Rx Water Cleanup Line 1201-8" 533' 301*
X X
4 1
i f
1 i
4 i
i i
i i
i 1
J i
i l
i i
i i
i i
- HoJIfications to this table due to changes in high radiation should be subesitted to the NRC as part of the next l cense i
ame dment request.
Amendment No. 60 9te-2