ML20037B256
| ML20037B256 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 08/09/1976 |
| From: | Ziemann D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20037B254 | List: |
| References | |
| NUDOCS 8009100730 | |
| Download: ML20037B256 (9) | |
Text
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7 COMH0mlEALTil EDIS0!4 COMPAtlY
/0 DOCKET NO. 50 4
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ORESDEtl t.tICLEAR POWEP. STATION UNIT NO. 1 g
81 H DMEt:T TO FACILITY OPERATING LICEMSE Anendment No. /d License fio. DPR-2 1.
The !!uclear Pegolatory Cconission (the Cennission) hss found thr :
A.
The application for asendaent by the Conmnwealth Edison Company (the licensee) dated March 16, 1976, conplies with the standards and requirements of the Atonic Energy Act of 1954, as amended (the Act), and the Connission's rules and reculations set forth in 10 CFR Cnapter I; a
6.
The facility will operate in conformity with the application, the provisions of the Act and the rules and reculations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this acerdment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Connission's regulations; D.
The issuance of this amendment will not be ininical to the coamon defense and security or to the health and safety of the public; and E.
The issuance of this awndment is in accordance with 10 CFR Part 51 of the Cocaission's regulations and all applicable require *ents have been satisficd.
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2.
Accordingly, the license is acended by chan.ces to the Technical Specifications as indicated in the attachment to this license a:.;e nanent.
3.
This ifcense amendment is effective as of the date of its issuance.
FOR THE HUCLEAR REGULATORY C0"'ilSS10H Orf4 iaal signed by Dm -;I h mann
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Dennis L. Ziemann, Chief Operating Reactors Branch #2 Division of Operating P.eactors
Attachment:
Changes to the Technical Specifications Date of Issuance: AUG S 1976 s
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4 ATTACHMENT TO LICENSE AMENDMENT t:0./6 FACILITY OPERATING LICENSE NO. DPR-2 00CV,ET ?!O. 50-10 l
l Peplace the existing third page of the Table of Contents of the Technical Specifications with the attached revised third page and add new pages l
70c, 70d, 70e, 76a and 76b.
The change on page three is shown by _a carpinal line.
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L]MITING CONDITION FOR OPERP. TION SURVEILLANCE REQUIREMENT 3.6 G.
Shock Suppressors (Snubbers)
G.
Shock Suppressors (Snabbers) 1.
During all modes of operation The following surveillance require-exce pt-cold shutdown and refuel, monts apply to all hydraulic snubbers listed in Table 3.6.1.
all. sa,fety-related snubbera listed in Table 3.6.1 shall be operable l
cxcept as noted in Specification 1.
All hydraulic snubbers whose scal material has been demonstrated by 3.6.G.2 through 3.6.G.4.
operating experience, lab tc.s ti n.:
r analysis to be co.patible nta l
2.
Froni and af ter the time that a cp daalI a p a en rc
{
snubber is determined t'o be inoperable, visually inspected.
ahis inspection'
'% 1 continued reactor operation is permissible shalJ include, but not necessar::;.
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only during the succeeding 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> unless be limited to, inspection of tne the snubber is sooner made operable or g
hydraulic fluid reservcir, fluin replaced.
connections, and tir.kaye connecticn to the piping and anchor to verify snubber operability in accorde.nce with the fo11cwing schedule:
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Amendment No.16
16 LI:iTTING CONDITION F0:1 OPERATION 4.6 SURVEILIRICE REQUIREMENT 3.
If the requiremer.ts of 3.6.G.1 and Number of Snubbers Next Required 1.6.c.2 cannot be met, an orderly Found Inoperable Inspection shutdown shall be initiated and the During Inspection Interval reactor sha'.1 he in a cold shutdown or During Inspection condition within 36 ho,urs.
Interval 4.
If a snubber is determined to be inoperable 0
18 months + 25%
while the reactor is in the shutdown or 1
12 months + 25%
refuel mode, the snubber shall be made 2
6 months 7 25%
operable or replaced prior to reactor 3,4 124 days
{25%
startup.
5,6,7 62 days 3 25*4
>8 31 days
+ 25%
5.
Snubbers may be added to safety related The required inspection interval shall systems without prior licenec amendment not be lengthened more than one step to Table 3.6.1 provided that a revision at a time.
to Table 3.6.1 is included with the next license amendment request.
Snubbers may be categorized in two
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groups, " accessible" or " inaccessible" based on their accessibility for inspection during reactor operation.
These two groups may be inspected independently according to the above schedule.
2 All hydraulic snubbers whose seal materials are other than ethylene propylene or other material that has been demonstrated to'he compatibic with the operating environment shall be visually inspected for operability every 31 days.
70d Amendment fic.16
q.
t 4.6 SURVEILLANCE REQUIRDIENT 3.6 LIMITING CONDITION FOR OPERATION' 3.
The Initial inspection shall he performed within 6 months from the.
date of issuance of these specifi-cations. For the purpose of entering the schedule in Specifi-cation 4.6.G.1, it shall be assumed that the facility had been on a 12-month inspection it,terva) (t.ased on the refueling inspection performed in December 1975 which indicated that there were no failed snubbers).
4.
Once cach refuc.ing cycle, a repre-sentative sample of 10 hydr rulic snubbers or approximately 10% of.,
the hydraulic snubbers, whichever is less, shall be functionally tested for operability including verification of proper piston movement, lock up and biced.
For each unit and subsequent unit found inoperabic, an additional 10% or ten hydraulic snuabers shall be so tested unti! no more failures are found or all units l
- 1. ave been tested.
Snubbers of rated capacity greater than 50,000 lb need not be functionally tested.
70e Amendment No.16
I Tabic 3.6.1 SAFE 1Y RELATED S110CK SLTPRESSORS (SNUBBERS)
Snubber No Location Elevation Azi-Snubber in Ifigh Snubbers Snubbers Snubbers much Radiation Arca Accessibic Inaccessibic Especially During Shutdown During Ncrual During Normal Difficult to Operation Operation Remove Reactor Canal:
X C9 R.-12 Core Spray Line CS-115-10" 583'0" 0*
X X
CSR-13 Core Spray Linc. CS-115-10" 583'6" 90*
X Refueling Floor:
CSR-14 Core Spray Line CS-115-10" 585'5" 327*
X X
CSP.-15 Core Spray Line CS-115-10" 587'7" 332' X
X CSU-15A core Spray Line CS-114-10" 585'5" 336*
X X
r.SI:.-16 Core Spray Lihe CS-114-10" 585'5" 342*
X X
CSR-17 Core Spray Line CS-114-10" 587'5" 342*
X X
t Note: The above snubbers are listed in the order in which they appear on the pipe going away from the reactor.
O null fications to this Tahic due to changes in high radiation areas should he submitted to the NRC as part of the next license mnendmen t.
70f Amendment No.16'
l.im_i t ing Condi t i.ms for Operat on Ikises (Cont'd),
required that all snubbers required to protect the primary coolant system or any other safety system or component be operabic during reactor operation.
Because the snubber protection is required only during low probability events, a period of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> is allowed for repairs or replacements.
In case a shutdown is required, the allowance of 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> to reach a cold shutdown condition will permit an orderly shutdown consistent with standard operating l
procedures.
Since plant startup should not commence with knowingly defective safety related equipment, Specification 3.6.G.4 prohibits startup with inoperable snubbers.
I All safety related hydraulic snubbers are visually inspected for overall integrity and operability.
The inspection will include verification of proper crientation, adequate hydraulic fluid Icvel and proper attachment of snubber to piping and structures.
The inspection frequency is based upon maintaining a ccnstant level of snubber protection.
Thus the required inspection interval varies inversely with the observed snubber failures.
The number of inoperabic snubbers found during a required inspection determines the time interval for the next rcqui' red inspection.
Inspections performed G.
Shock Suppressors (Snubbers) before that interval has clapsed may be used as a new reference point to determine the next inspection.
Snubbers arc designed to prevent unrestrained
!!owever, the results of such carly inspections pipe motica under dynamic' loads as might performed before the original required time
'ccur during an carthquake or severe transient, interval has elapsed (nominal time less 25*.) may owhile n11 wing normal thernal motion during not be used to lengthen the required inspection sta:rup and shutdown.
The consequence of interval.
Any inspection whose results require a an inoper:.ble snubber is an increase in the shorter inspection interval will override the probability of structural damage to piping previous schedule.
as a result of a scismic or other event 76a initiatinn dynamic loads.
It is therefore Amendment No.'16
1.irn i t ing Cond i t ions for Operat ion Itu;es (Cont'd) nxperience at operating fact 11 tics has shown To furt.her increa n the annurance of nerabb-r reliability, a
p-rrorm-:1 ence each recue]Inc that the required surveillance program chould
.scuce nn acceptable level of snubber per-cycle. These testa vill include atrokin't of the nnubb-rc to verify proper piston movement, locbup and bleed. Ten far mn ace prcvided that the soal materials are percent or ten snubbers, whichever is less, represents an compatible with the operating environment.
ndequate sample for such tests. Observed fn13nres on these samples should require testing of addit,ional units.
Unubb-rn containing s-al muterial which hna not been Those snubbern denignated in Tab 3e 3 6.1 nn beirqs in high radiation arean or especially difficult to remove need demcnst.ruted by operating experience, lab tests or not be selected for functional tests provided operabil-nnalysis to be compatible with the operating environ-ity was previously verified. Snubbers'of rated capacity ment should be inspected more frequently (every month)
Greater'than 50,000 lb. are exempt from the functional until material compatability is confirmed or an appro-priate changeout is completed.
testing requirements because of the impracticality of testing such large unita.
Examination of defective snubbers at reactor facilitics and material tests performed at several laboratories (Reference 1) has shown that millable gum polyurethane deteriorates rapidly under the temperature and moisture Ieanditiors present in many snubber locations.
Islthough molded polyurethane exhibits greater resistance to these conditions, it also may be unsuitable for applicat ion in the higher tempernt.ure environments.
Data are not cur-U rently tvailable to precisely defino an upper N
t.cmperature limit for the molded polyurethane.
I:nb tests and in-plant experience indicate D
that seal materials are available, primarily
- thylene propylene compounds, which should h
give satisfactory performance under the most
- cvere conditions expected in reactor instal-N lations.
M b
(1) Report H.
R. Erickson, Bergen Paterson to K.
R. Goller, NRC, October 7, 1974 Subjcct:
Hydraulic Shock Sway Arrestors 76b Amendment No. 16
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