ML20090L732

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Proposed Tech Specs Re Limiting Condition for Operation & Surveillance Requirements for Hydraulic Snubbers
ML20090L732
Person / Time
Site: Monticello Xcel Energy icon.png
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

' ' " " to be inoperable while the reactor

" ' " ' ' '" ' '~' ' " ' """' '" " " "

3 f*$

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"is determined is in the chutdown or refueling mode, the snubber Interval O 18 months + 25%

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 Snubbers may be added to safety related The required inspection interval shall not be

5. lengtbened more than one step at a time.

systems without prior License Amendment 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 Amendment request. independently accordin6 to the above schedule.

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

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TABLE 3.6.1 e BE1 RSof 2)

! SAFETY RELATED HVDRAULI 5 , [

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)

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 [

j - --____________

g PS1-H2 MAIN STE AM DRYWELL 9 53 071 i

[

l 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 i

P54-H3 MAIN STEAM DRYWELL 950 212 3 DRYWELL 9 50 110 t l Rv24-H3 S AF E T Y-R EL I EF I

Rv24-H4 S AF ET Y-R ELIEF DR1 DELL 9 15 100 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 DAYWELL 947 048 x 1 AV24A-H4A S AFE TY-R ELI EF RV24A-NF SAFETY-RELIEF DRYWELL 9 53 115 i 9 39 032 1  !"

RV24A-H8 S AFET Y-R EL IE F DRYWELL i Rv25-M1 S AFE TY-R ELI EF DRYWELL 953 180 g DRYWELL 953 180 x t 4

Rv25-H1A S AFET Y-R EL IE F 190 K 4

Rv25-H2 S AFE T Y-R EL I E F DRYWELL 948 t ,

DRYWELL 948 193 x I l RW25-H2A SAFETY-REttEF x l Ev25-H3 SAFET Y-R ELI EF DRYWELL 9 34 180 ORYWELL 945 120 x x [

4 Rv25A-H2 SAFETY-RELIEF x x j Rv 25 A-H2 A SAFETY-RELIEF DRYWELL 945 120 1

! t

RV25A-H7 S AFE T Y-R EL I E F DRYWELL 953 135 I SAFETY-RELIEF DRYWELL 953 200 x [

l CW 26-H 1 '

RW26-H1A S AF E T V-R EL I EF DRYWELL 953 200 t x

! SAFETY-RELIEF DRYWELL 9 47 200 Rv 26-H 2 I r SAFETY-RELIEF -DRYWELL 947 200 KV26-H2A '250 t RV264-H2 S AFE T Y-R EL I E F DRYWELL 940

' ORYWELL 935 250 I CV26A-H2A S AFET Y-R EL I EF 320 t RY27-M1 S AFETY-RELI EF DRYWELL 9$0 [

DRYWELL 9 94 230 t RW2F-HIA S AFE T Y-R EL ICF t

$AFETY-RELIEF DRYWELL 945 2F0 RV27-45 945 270 t

[

j_ RV27-H4 S AF E T Y-R EL I EF DRYWELL 953 290 t ,

RV274-H2 A S AFET Y-R ELIEF DRYWELL

]

9 53 290 t f

! Rv27A-H3 S AFE TY-R ELIEF DRYWELL l SAFETY-RELIEF DRVWELL 9 38 293 I CW27A-H9 279 x I  !

55-1 MAIN STEAM DRYWELL 953 I'

922 315 K x I l 55-1AR RECIR CUL AT IENs DRYWELL l 9 ** 135 x x 1 j 55-104 RECIRCUL AT IDN DRYWELL I DAYWELL 952. 302 I

] 55-11 F EEDW AYER 9 52 058  :  ;

i 55-12 FEEDW ATER ORYWELL 952 258 I  ;

j 55-13 F EE DW ATE R DRYWELL 952 096 I ,

55-14 FEEDWATER DRYWELL 4M 0F2 x t I

$5-17A RHR ORYWEtt i DRYWELL 9M 072 x 1 '

55-178 RHR 9M 288 1

! $5-18A RHR DRYWELL DRYWELL 9M 288 I

} 55-188 RHR 9 64 341 1 55-19 R HR ORYWELL r  !

DRYWELL 9 53 081 x 'I I 55-2 MAIN STE AM x x I 55-2AR RECIRCULATIDM DRYWELL 927 30 2 i  !

1 121B 3.6/4.6

REV j

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_ _ _ _ _ __ _- ~ _ _ __ _ _ _ - -_ _ ____ _ _ _ - . _ _ .. . _ . _ . _ _ _ _ _ _ _ _ . _ _ _ _ ____ _- . -

TA BL E 3.6.1 ( Bage 2 of 2 )

SAFE TY MELATED HYDR AULI C SNUB 8ERS

~~ ~~~~~~~

SNUe8ER NO. SYST LM LOCallON EL EV AT ION AZIMUTH HIGHkADIA DIhAICULT ACCESSIRLE .A (AIRLOCR 0 REF6 flog AREA T3 REMOYE IN aC CE S SI SL E -I 92T 122 x 1 55-2BR R EC1 R CUL Af l 0N DR YW E L L x t 55-20 R HR CRYWELL 9 64 019 55-3 Ma t'4 STEAM ORYWELL 9 50 212 1 DRYWELL 92T 728 z I 55-3AR R ECIRCUL ATIDW x g 55-38R R ECIRCUL ATI ON DR YW E L L 92T 148 MAIN STEAM DRYWELL 950 148 1 35-4 I 55-4 AR I A) RECIRCUL Afl0N ORYWELL 9 34 302 9 14 323 I 55-4AR481 RECIR CUL ATION DRYWELL RECIRCULATION ORYWELL 9 34 120 1 55-48RIA8 149 I 55-48Rt03 R ECIR Cut a it 0N DRYWELL 9 34

~

t 55-40 HPCI MAIN STEAM C HASE 141 315 x I 55-5AR R ECIR CUL AT I ON ORYWELL DR YW E L L 941 135 x g 55-584 RECIR CUL AT I ON DRYWELL 953 261 x 1 33-6AR R EC I R CUL Af l 0N 099 x 55-68R RECIRCUL ATION DRYWELL 9 53 I DRYWELL 953 240 x 55-7 MAIN STE AM 323 1 55-7AR RECIR CUL AT ION CRYWELL 9 53 9 53 032 I 55-78R R ECIR CUL AT ION DRYWELL DAYWELL 953 120 x  :

55-8 MAIN STEAN x I 55-8AR R ECIR CUL AT I ON DRYWELL 92T 270 DRYWELL 927 090 x I

$5-88R RECIR CUL AT I ON A 55-21 RHR TORUS FL L% - 5 WALL A 55-22 R HR TORUS FL Lv - 5 WALL A

'3 R HR 8 RHR ROON FL LV A

55-4+ R HR A RHR ROOM FL LV A

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 &

R HR OVER N2 AN ALYZER 9 $4 x 55-29 s A R HR OVER N2 AN8LYZER 9 54 55-30 A 55-31 R HR TORUS CAihK A 55-32A RHR A RHR ROOM - 8. HK 916 m A RHR ROGM - SV HR 916 x A 55-328 AHR A >

55-33 R HR ABOVE TORUS A 55-34 R HR ABOVE TORUS A 9 12 v 55-35 HPCI HPCI RCOM - N WALL A 55-36A HPC I HPCI RCOM - F L LWL A 55-368 HPCI HPCI ROOM - FL LVL y A HPCI HPCI ROOM -W Watt 9 05 55-37 9 06 . A 55-38A RCIC RCIC RCOM - W WALL m A RCIC RCIC RCOM - W WALL 9 06 55-388 92T A l 55-41 CORE SPR AY A8GWE TORUS CATWR A HPCI ABOVE TORLS RING HOR 9 06 55-42 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.

3.6/4.6 BASES 138A Het

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L.O.MAYER oaf t atCeive o 10-4-76 .

INPUT F Onu NUMet R OF Cortts etCEfvt D ONOTO8tilf D PAOP GLETTtR

@ ORIGIN AL @UfJC L AS$1F le D 40 OcOPv ENCLOSURE Of SC RIP Tic'N LICENSE AMENDMENT REQUEST FOR CilANGE TO TECH.

LTR. RE. OUR 12-17-75 LTR......TRANS THE TOLL- SPEC., NOTARIZED 10-1-76, COVERING Tile SAFETY OWING.......

RELATED HYDRAULIC SNUBBER OPERABILITY AND SURVEILLANCE' REQUIREMENTS......

' ( 3 SIGNED CYS. RECEIVED)

( 10 PAGES)

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