ML20039E586
| ML20039E586 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 12/28/1981 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20039E587 | List: |
| References | |
| NUDOCS 8201110052 | |
| Download: ML20039E586 (15) | |
Text
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UNITED STATES
.f
,9 g-NUCLEAR REGULATORY COMMISSION j
wasHtNG fON, D. C. 20555 C
O NORTHERN STATES DOWER COMPANY DOCKET NO. 50-263 MONTICELLO NUCLEAR GENERATING PLANT 4
AMENDMENT TO FACILITY JPERATING LICENSE NoendmentNo.9 License No. DPR-22 1.
Tne Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Northern States Poemr Company (the licensee) dated October 9,1981 complies with the standards and requtrements of the Atomic Energy 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 (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public and (ii) that such activitfes will be conducted in compliance with the Comission'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 Comission's regulations and all applicable. requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment, and paragraph 2.C.2 of Facility Operating License No. OPR-22 is hereby amended to read as follows:
2.
Technical Specifications 1
The Technical Specifications contained in Appendices A and B as revised through Amendment No. 9 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
-. ~. -.. _.. -.
2 3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY C0f9tISSION A
Chief Operating Reactors Branch #2 Division of Licensing-
Attachment:
Changes to the Technical Specifiestions Date of Issuance:
December 28, 1981 O
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ATTACHMENT TO LICENSE AMENDMENT NO. 9 FACILITY OPERATING LICENSE NO. DPR-22
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DOCKET NO. 50-263 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
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Remove Insert 11 if 129 129 130 130 130a 130b 131 131 132 132 132a 132a 154 154 155 155 247 247 274a 0
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Page 3.4 and 4.4' Scandby Liquid Control System-93 A.
Normal Operation 93 3.
Operatica with Inoperable Components 94 C.
Volume-Concentration Requ irements 95 3.4 and 4.4 Bases 99 3.5 and 4.5 Core and containaant Cooling system 101 A.
Core Spray System
- 101 3.
LPCI Subsystem 103 C.
RER Service Water System 106 D.
HPCI System 108 E.
Automatic Pressure Relief Systen 109 F.
RCIC System 111 C.
Minimum Core and Contai= ment Cooling System Availability 112 H.
Delet ed I.
Escirculation System 114 3.5 Bases 115 4.5 Bases 120 3.6 and 4.6 Pri=ary System 3oundary 121 A.
Reactor Coolant Heatup and Cooldown 121 3.
Reactor vessel Temperature and Pressure 122 C.
Coolant chemistry 123 D.
Coolant Leakage 126 E.
Safety / Relief Valves 127 F.
Deleted C.
Jet Pumps 12S H.
Scubberr 129 l
3.6 and 4.6 3ases 144 3.7 and 4.7 Contain=ent Sy s t e=s 156 l
A.
Pri=ary Contai==ent 156 3.
Standby Gas 2: eat =ent System 166 C.
Secondary Contain=ent 169 D.
Pri=ary Containment Isolation valves 170 3.7 Bases 175 4.7 3ases 183 i
Amendment No. 9_
l d
4
3.0 1.lHITING CONDITIONS FOR OPEllATION 4.0 SURVEll.l.AHCE REQUIREHENTS 3.
The di f fuser to lower' planum di f fe' rent ial pressure reading on an individual jet pump is i
10% or more, less than the mean of all jet pump di f ferential pressures.
11. Snubbers 11. Snubbers permitted below, all anubbers The following surveillance requirements apply j
l.
Except as listed in Table 3.6.1 shall he operable to all snubbers listed in Table 3.6.1.
above Cold Shutdown. Snuhinere may be inoperable in Cold Sliotdown and Refueling 1.
Visual inspect ion of snubbers -eliall be
]
Shutdown whenever the support ed systeis conducted in accordance with the following
)
is not required to be Operable, schedule:
4 2.
With one or more snuhbers made or found to Ho, of Snubbers Found Heat Required be inoperable for any reason when Operability Inoperable per Inspection Period j
is required, within 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />s:
Inspection Period 0
18 monthe j,25%
a.
Heplace or restore the inoperable snubbers i
12 monthe j,25%
to Operable status and perforia en engineer-2 6 months f. 25%
{
ing evaluation or inspect ion of the 3,4 124 days j;25%
i supported component s, or 5,6,7 62 days j;25%
8 or more 31 days j;25%
}
b.
Determine through engineering evaluation tlist the as-found condit ion of the snuhber The required inspection interval steell not be had no adverse effect on the supported
' lengthened more than one step at a time.
components and tlist they unuld retain their structural integrity in Snubbers may be categorized in two groups, the event of the design basis seismic
" accessible" or " inaccessible" based on their i
event, or accessibility for inspection during reactor i
operation. These two groups may be inspected i
c.
Declare the supported system inoperable independently according to the above schedule.
and take the action required by the Teclinical Specifications for Inoper-
?
ability of that system.
i I
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i 3.6/4.6 Amendment No. 9 129 9
l 8
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3.0 I.IMITING CONDITIONS FOR 01'ERATInti 4.0 SURVEII. LANCE REQbIREMENTS ~
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3.
Snubber nodificat ions may be made to safety 2.
Visual inspections shall verify (1) that there related systems without prior I.icense are no vlaible indications of damage or impared operability and (2) attachments to la Ame ndme nt to Table 3.6.1 provided tlist a
}.
revision to the Table is included with tlie the supporting structure are secure, j
next License Amendment Request.
Snubbers whicle appear inoperable as a result
!i of visual inspection may be determined Operable l'
4.
All safety-related snubbers installed or for the purpose of establishing the next visual planned for use at Monticello are hydraulic inspect ion interval by:
4 anubbers. No mechanical snubbers are
[
used on safety-related systems at a.
Clearly establishing
'e cause of the I[
Monticello.
If installed in the future, rejection for that par 'cular saubber appropriate Technical Specifications changes and for othere that ma, ae generically will be proposed within 60 days of susceptible; and installation.
4 b.
Functionally testing the af facted anubber in the as-found condition and finding it Operable per Speci ficat ion 4.6.11.4.
i' le Ilouever, wisen the fluid plunger gauge of a hydraulic anubber is below low range..the snubber aliall be considered inoperable for the purposes of j,
),
establishing the next visual inspection interval.-
e i
!i 1ii 3.6/4.6 Amendment No. /d 9 130 li
ij' il
- i 3.0 1.lHITING CONDITIONS FOR Ol'ERATinti 4.0 SilRVEll.l.ANCE HEQUlHEHENTS i
a 3.
Funct ional test ing of snubbers. shall. be I
conducted at least once per 18 months + 25%
during cold shutdown. Ten percent of the l-total number of each brand of snubber shall be functionally tested either in place or in j,
a bench test.
For each snubber that does a
not meet the functional test acceptance j
criteria in Specification 4.6.H.4 below, 4
i-an additional ten percent of that brand shall be functlonally tested until no more failures are found or all enubbers of that brand have been j
- tested, i
4 The representative sample selected for functional testing shall include the various I
configurations, operating environments, and
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the range of size and capacity of the snubbers.
t.
In addition to the regular sample and specified
,I, re-samples, snubbers which failed the previous functional test shall be ratested during the j
next test period if they were reinstalled as a safety-related snubber..If a spara snubber j
has been installed in place of a failed safety related snubber, it shall be tested j
during the next period, i
If any annbber selected for functional testing either fails to lockup or fails to move (i.e. frozen in place) the cause shall be 1
- ,i evaluated and if caused by manufacturer or j;
design deficiency, all snubbers of the same design subject to the same defert shall be functionally tested.
t s
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li 3.6/4.6. Amendment No. 9 130s
+
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3.0 1.lHITING CONDITIONS FOR OPERATION 4.0 SURVEll. LANCE HEQUIREHENTS l
4.
Hydraulic anubber functional testa shall verify j
that:
j a.
Act ivation (restraining actlan) is achieved
,j' within the _specified range of velocity or acceleration in both tension and compression.
i'j.
- b.
Snubber bleed, or release rate, where required, la is within the specified range in compression or
{,
tension.'
i i
S.
For any snubbers found inoperable, an engineering l
evaluation or inspection shall be performed on the com-j ponents which are supported by the snubbers. The pur-j pose of this engineering evaluat ion or inspection shall be to determine if the components supported by the snubbers were adversely affected by the inoperability
- .j.
of the snubbers in order to ensure that the supported
~
il component remains capable of meeting the designed service, y
l' 6.
The installation and maintenance records for each anubber listed in Table 3.6.1 shall be reviewed at least I
once every 18 months to verify that the indicated service,
j life will not be exceeded prior to the next scheduled j
snubber service life review. If the indicated service life will be exceeded, the sunbber service life shall be re-r evaluated or the snubber shall be replaced or reconditionsui to extend its service life beyond the date of thi next
'l scheduled service life review.- This reevaluation, l
replacement, or reconditioning shall be' indicated in the I
records.
l' J
- This requirement is effective on July 1, 1983. Until that j
time, only snubber bleed, or release, shall be demonstrated..,
i 3.6/4/6 Amendment No. 9.
- N j
130b
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i 1.6/4.6 Amendment No. $( 9 132a 9
e
Bases Continued 3.6 and 4.6:
A nozzle-riser system failure could also generate the coincident f ailure of a jet pump body; however, the.
converse is not true.
The lack of any substantial stress in the jet pump body makes failure impossible without an initial nozzle-riser systen failure.
II.
Snubbers i
All anubbers are required to be operable above Cold Shutdown to ensure that the structural integrhiy of the reactor coolant system and all otbar safety related systeine is maintained diaring and following a seismic or
)
other event initiating dynninic loads.
0.. SSere excluded from this inspection program are those installed l
on non-safety related systema and then only it their failure or failure of the system on which they are installed would have no adverse ef f ect on any safe 67-related system.
1 The visual inspection frequency is based upon maintaining a constant level of snubber protection to systems.
1 The re fore, the required inspect ion interval varies inversely witi. the observed snubber failures and is I
l determined by the number of inoperable snubbers found during so inspection.
Inspect ions performed be fore that.
l Interval has elapsed may be insed as a new reference point to dete mine the.' ext inspection. Ilowever, the results of such early inspections performed before the original required time it.terval has elspeed (nominal time less 25%) may not be used to lengthen the required inspection interval. Any lospection whose results require a shorter inspect ion interval will override the previous schedule.
f Wh'en the cause of the rejection of a snubber is clearly established and remedied for that snubber and for.
any other snubbers tlist may be generically susceptible, and verified by inservice functional testing, that enubber may be exempted from being counted as inoperable. Generically susceptible anubbers are those which j
are of a specific make or model and have the maine deslan feature directly related' to rejection of the snubber.
When a snubber is found inoperable, an engleieering evaluation or inspect ion is performed, ir. a'ddition to the determinat ion of the snubber mode of failure, in order to determine if any safety-related component or i
system has been adversely af fected by the inoperability of the snubber. The evaluation or inspection wil!
deteristne whether or not the snubber mode of failure has imparted a significant effect or degradation on the supported component or system.
1 i
t 3.6/4.6 BASES Amendment No. 9 154
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in 11.
. Snubbers (continuedl i
To provide assurance of snubber functional ieliability, a representative sample of 10% of the installed anubbers ullt be funct ionally tested during plant shutdowns at intervata of no esore than 18 annths 125%.
Observed failures of these enmple snubbers will require functional testing of additional units.
1 j
The service life of a snubtier is evaluated via manufacturer input and through consideration of the i
e snubber service conditions and associated installation and maintenance records (newly installed snubber, j -
seal replaced, spring replaced, in high radiat ion ares, in high temperature area, etc.
.).
I1ie requirement i
to monitor the snubber service life is included to ensure that the snubbers periodically undergo a performance i.
evaluation in view of their. age and opqrating conditions. These records will provide statistical bases for 4;
future consideration of snubber service life.
4 f
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i-a uf 3.6/4.'6 BASES AmendmentNo./,9 155 y
S.
Principal maintenance activities, including inspection, repaits and substitution or replacement of. principal items of equipment pertaining to nuclear safety.
4-
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6.
Records of changes to plant procedures and records of special tests and experiments.
il 7.
Records of wind speed and direct ion.
4
^
8.
Records of individual plant staf f members showing qualifications, training and
' retraining.
9.
Reportable occurrences.
j.
?
8.
Records Retained for Plant Li fe i
Records and logs relative to the following items shall be retained for the life of the j
plant:
1 t
1.
Liquid and gaseous radioact ive releases to the envir'one 2.
Radiation exposures for all plant, visitor and contractor personnel ij 3.
Of f-site environment al annitoring surveys J
l' 4.
Fuel accountability including new and spent fuel inventories and transfern, and fuel assembly histories
)k 5.
Radioact ive shipment s l'
6.
Plant radiation and contamination surveys 7.
Changes made to the plant as it is described in the Final Safety Analysis Report, reflected in updated, corrected and as-huilt drawings i
o j
8.
Cycling beyond normal liinits for those components that have been designed to operate
{:,
safely for a limited number of cycles beyond such limits ll 9.
Reactor coolant systein in-service inspections
!6 10.
Minutes of meetings of ti e Ssfaty Audit Committee l
{i 6.6 Amendment No. 9-247 e
6 I
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Records Retained for I'l ant 1.l fe (cont inueti) 1 j
11.
Hecords for Environmental Qualification which are covered under the' provisions o's paragraph 6.8.
1 12.
Records of the service lives of all safety-related snubbers, including the date at which i
the service life commences and associated installation and maintenance records.
4 4
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