ML20090L732
| ML20090L732 | |
| Person / Time | |
|---|---|
| Site: | Monticello |
| Issue date: | 10/01/1976 |
| From: | NORTHERN STATES POWER CO. |
| To: | |
| Shared Package | |
| ML20090L727 | List: |
| References | |
| NUDOCS 9102120585 | |
| Download: ML20090L732 (5) | |
Text
,
3.0 LIMITING CONDITIONS FOR OPEPATION 4.0 SURVEILIANCE REQUIPDENTS 3.
Ibe diffuser to lower plenum differential pressure reading on an individual jet ptry is 107. or more, less than the mean of all jet pung differential pressures.
H.
Hydraulic Snubbers H.
Hydraulic Snubbers 1.
During all modes of operation, except Cold Shut-The following surveillsace requirements apply to all down and Refueling Shutdown, all hydraulic hydraulic snubbers listed in Table 3.6.1:
snubbers listed in Table 3.6.'
shall be operable except as noted in 3.6.H.2 through 3.6.H.4 1.
All hydraulic snubbers whose seal material has been below.
demonstrated by operating experience, lab testing, or analysis to be compatible with the operating 2.
From and after the time that a hydraulic simbber environment shall be visually inspected. *lhis is determined to be inoperable, continued reactor inspection shall include, but not necessarily be operation is permissible only during tne succeed-3g g
g 7
TT4 ing 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> unless the snubber is sooner made reservoir, fluid connections, and linkage connec-c-g PeraMe.
tions to the piping and anchor to verify snubber Perubility in accordance with the following 75 3.
If the requirements of 3.6.H.1 and 3.6.H.2 cannot schedule-
@O be met, an orderly shutdown shall be initiated om and the reactor shall be in a cold shutdown No. of Snubbers Found Next Required Inspectior M
condition within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
Inoperable During Inspec-Interval o9
" ' " ' ' '" '' '~' '
f*
"is determined to be inoperable while the reactor Interval fu -
is in the chutdown or refueling mode, the snubber O
18 months + 25%
3 g$
shall be made operable prior to reactor startup.
1 12 months {25%
2 6 months + 25%
3,4 12A days T 25%
5,6,7 62 days i 25%
>S 31 days 1 25%
121 306/4.6 ag
3.0 I.IMITING CONDITIONS FOR OPERATION 4.0 SURVEILIANCE REQl1IREMENTS 5.
Snubbers may be added to safety related The required inspection interval shall not be systems without prior License Amendment lengtbened more than one step at a time.
to Table 3.6.1 provided that safety evaluations, documantation and reporting Snubbers rny be categorized in two groups, are provided in accordance with 10CFR
" accessible" or " inaccessible" based on their 50.59 and that a revision to Table 3.6.1 accessibility for inspection during reactor is included with a subsequent License operstion. These two groups my be inspectc.d independently accordin6 to the above schedule.
Amendment request.
2.
All bydraulic snubbers whose seal mterials are other than ethylene propylene or other material that has been demonstrated to be compatible with the operating environment shall be visually in-l spected for operability every 31 days.
3-deleted 4.
Once each refueling cycle, a representative sample of 10 snubbers or approxistely 10% of the snubbers, whichever is less, shall be functionally tested for operability including verification of proper piston mvement, lock up, and bleed. For each unit and subsequent unit found inoperable, an additional 10%
or ten onubbers shall be so tested until no more failures are found or all units have been tested.
Snubbers designated in Table 3 6.1 as being especially difficult to remove or located in High Radiation Areas are exermt from this requirement.
5 Snubbers may be reclassified as being in or out uf High Radiation Areas in Table 3.6.1 based on the most recent radiation survey provided that a revision 3.6/4.6 to Table 3 6.1 is included with a subtequent License Amendment Fequest.
g REV
i i
t l
TABLE 3.6.1 e 1 of 2)
SAFETY RELATED HVDRAULI 5 BE RS
[
)
---~_______
7 I
Sa:UB8E R NO.
SYSTEM LJCATIDN E L EV AT ION AllMUTH HIGH R ADI A-D t'F ICUL T ACCESSISLE
-A
[
tAIRLDCR 0 REFS TION AREA 10 REMOVE INAECESSISLE-t 3
j l
PS1-H2 MAIN STE AM DRYWELL 9 53 071 g
[
i P51-H3 MAIN 5 TEAM CRYWELL 960 148 I
PS 2-H2 MAIN STEAM DRYW E LL 950 123 i
PS3-H2 MAIN ST E AM DRYWELL 9 50 240 t
P54-H3 MAIN STEAM DRYWELL 950 212 3
i Rv24-H3 S AF E T Y-R EL I EF DRYWELL 9 50 110 t
l' Rv24-H4 S AF ET Y-R ELIEF DR1 DELL 9 15 100 I
Rv24-H4A S AFE T Y-R Et t EF DRYWELL 9 35 100 t
Rv24-H5 5AFETY-RELIEF DAY WE LL 9 35 110 t
AV24A-H4A S AFE TY-R ELI EF DAYWELL 947 048 x
1 RV24A-NF SAFETY-RELIEF DRYWELL 9 53 115 i
RV24A-H8 S AFET Y-R EL IE F DRYWELL 9 39 032 1
Rv25-M1 S AFE TY-R ELI EF DRYWELL 953 180 g
i Rv25-H1A S AFET Y-R EL IE F DRYWELL 953 180 x
t 4
Rv25-H2 S AFE T Y-R EL I E F DRYWELL 948 190 K
t RW25-H2A SAFETY-REttEF DRYWELL 948 193 x
I l
4 l
Ev25-H3 SAFET Y-R ELI EF DRYWELL 9 34 180 x
4 Rv25A-H2 SAFETY-RELIEF ORYWELL 945 120 x
x
[
Rv 25 A-H2 A SAFETY-RELIEF DRYWELL 945 120 x
x 1
j RV25A-H7 S AFE T Y-R EL I E F DRYWELL 953 135 I
t
[
l CW 26-H 1 SAFETY-RELIEF DRYWELL 953 200 x
RW26-H1A S AF E T V-R EL I EF DRYWELL 953 200 t
Rv 26-H 2 SAFETY-RELIEF DRYWELL 9 47 200 x
KV26-H2A SAFETY-RELIEF
-DRYWELL 947 200 I
r RV264-H2 S AFE T Y-R EL I E F DRYWELL 940
'250 t
CV26A-H2A S AFET Y-R EL I EF ORYWELL 935 250 I
RY27-M1 S AFETY-RELI EF DRYWELL 9$0 320 t
[
RW2F-HIA S AFE T Y-R EL ICF DRYWELL 9 94 230 t
RV27-45
$AFETY-RELIEF DRYWELL 945 2F0 t
j_
RV27-H4 S AF E T Y-R EL I EF DRYWELL 945 270 t
[
]
RV274-H2 A S AFET Y-R ELIEF DRYWELL 953 290 t
Rv27A-H3 S AFE TY-R ELIEF DRYWELL 9 53 290 t
f CW27A-H9 SAFETY-RELIEF DRVWELL 9 38 293 I
l I
55-1 MAIN STEAM DRYWELL 953 279 x
I 55-1AR RECIR CUL AT IENs DRYWELL 922 315 K
x I
l l
j 55-104 RECIRCUL AT IDN DRYWELL 9 **
135 x
x 1
]
55-11 F EEDW AYER DAYWELL 952.
302 I
I i
55-12 FEEDW ATER ORYWELL 9 52 058 j
55-13 F EE DW ATE R DRYWELL 952 258 I
55-14 FEEDWATER DRYWELL 952 096 I
I
$5-17A RHR ORYWEtt 4M 0F2 x
t 55-178 RHR DRYWELL 9M 072 x
1 i
$5-18A RHR DRYWELL 9M 288 1
}
55-188 RHR DRYWELL 9M 288 I
(
55-19 R HR ORYWELL 9 64 341 1
I 55-2 MAIN STE AM DRYWELL 9 53 081 x
r
!'I i
55-2AR RECIRCULATIDM DRYWELL 927 30 2 x
x I
1 121B 3.6/4.6 REV j
m l
~
TA BL E 3.6.1 ( Bage 2 of 2 )
SAFE TY MELATED HYDR AULI C SNUB 8ERS
~~ ~~~~~~~
HIGHkADIA DIhAICULT ACCESSIRLE
.A SNUe8ER NO.
SYST LM LOCallON EL EV AT ION AZIMUTH (AIRLOCR 0 REF6 flog AREA T3 REMOYE IN aC CE S SI SL E -I 55-2BR R EC1 R CUL Af l 0N DR YW E L L 92T 122 x
1 55-20 R HR CRYWELL 9 64 019 x
t 55-3 Ma t'4 STEAM ORYWELL 9 50 212 1
55-3AR R ECIRCUL ATIDW DRYWELL 92T 728 z
I 55-38R R ECIRCUL ATI ON DR YW E L L 92T 148 x
g 35-4 MAIN STEAM DRYWELL 950 148 1
55-4 AR I A)
RECIRCUL Afl0N ORYWELL 9 34 302 I
55-4AR481 RECIR CUL ATION DRYWELL 9 14 323 I
55-48RIA8 RECIRCULATION ORYWELL 9 34 120 1
55-48Rt03 R ECIR Cut a it 0N DRYWELL 9 34 149 I
55-40 HPCI MAIN STEAM C HASE
~
t 55-5AR R ECIR CUL AT I ON ORYWELL 141 315 x
I 55-584 RECIR CUL AT I ON DR YW E L L 941 135 x
g 33-6AR R EC I R CUL Af l 0N DRYWELL 953 261 x
1 55-68R RECIRCUL ATION DRYWELL 9 53 099 x
I 55-7 MAIN STE AM DRYWELL 953 240 x
55-7AR RECIR CUL AT ION CRYWELL 9 53 323 1
55-78R R ECIR CUL AT ION DRYWELL 9 53 032 I
55-8 MAIN STEAN DAYWELL 953 120 x
55-8AR R ECIR CUL AT I ON DRYWELL 92T 270 x
I
$5-88R RECIR CUL AT I ON DRYWELL 927 090 x
I A
55-21 RHR TORUS FL L% - 5 WALL A
55-22 R HR TORUS FL Lv - 5 WALL A
55-4+
55-25 R HR TORUS CA ThR-5E WALL A
55-26 CORE SPRAY 8 RHR ROOM FL LVL A
55-27 CDRE SPR AY 8 RHR ROOM FL LVL A
$5-28A COME SPRAY A RHR ROOM FL LYL A
55-288 s0RE SPR AY A RHR ROOM FL LVL 55-29 R HR OVER N2 AN ALYZER 9 $4 x
55-30 R HR OVER N2 AN8LYZER 9 54 s
A A
55-31 R HR TORUS CAihK 55-32A RHR A RHR ROOM - 8. HK 916 m
A 55-328 AHR A RHR ROGM - SV HR 916 x
A A
55-33 R HR ABOVE TORUS l
A 55-34 R HR ABOVE TORUS A
55-35 HPCI HPCI RCOM - N WALL 9 12 v
A 55-36A HPC I HPCI RCOM - F L LWL A
55-368 HPCI HPCI ROOM - FL LVL 55-37 HPCI HPCI ROOM -W Watt 9 05 y
A A
55-38A RCIC RCIC RCOM - W WALL 9 06 A
55-388 RCIC RCIC RCOM - W WALL 9 06 m
A l
55-41 CORE SPR AY A8GWE TORUS CATWR 92T A
55-42 HPCI ABOVE TORLS RING HOR 9 06 121c 36/4.6 REV f
H.
Hydraulic Snubbers (c ontd.)
Examination of defective snubbers at reactor facilities and material tests performed at several laboratories has shcun that millable gum polyurethane deteriorates rapidly under the temperature and moisture conditions present in many snubber locations. Although molded polyurethane exhibits greater resistance to these conditions, it also may be unsuitable for application in the higher temperature environments. Data are not currently available to precisely define an upper temperature limit for the molded polyurethane. Lab tests and in-plant experience indicate that seal materials are available, primarily ethylene propylene compounds, which should give satisfactory performance under the most severe conditiocs expected in reactor installations.
To further increase the assurance of snubber reliability, functional tests should be performed once each refueling cycle. These testr will include stroking of the snubbers to verify proper piston movement, lock-up and bleed. Ten percent or ten snubbers, whichever is less, represents an adequate sample for such tests.
Observed failures on these samples should require testing of additional units. Snubbers in High Radiation Areas or these especially difficult to remove need not be selected for functional tests provided operability was previously verified. Snubbers are considered especially difficult to remove if they (1) have a rated capacity greater than 50,000 lb, (2) are located greater than 5 feet above the adjacent platform, or (3) located greater than 3 feet below the adjacent platform.
138A 3.6/4.6 BASES Het
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@UfJC L AS$1F le D 40 OcOPv ENCLOSURE LTR. RE. OUR 12-17-75 LTR......TRANS THE TOLL-LICENSE AMENDMENT REQUEST FOR CilANGE TO TECH.
Of SC RIP Tic'N SPEC., NOTARIZED 10-1-76, COVERING Tile SAFETY OWING.......
RELATED HYDRAULIC SNUBBER OPERABILITY AND SURVEILLANCE' REQUIREMENTS......
( 3 SIGNED CYS. RECEIVED)
( 10 PAGES)
%CKNOWLEDGED PIANT NAME:
MONTICELLO 00 NOT BDE SAB 10-5-76 FOR ACTION /INFORMATION ENVTRO SAFETY
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