ML20024G679
ML20024G679 | |
Person / Time | |
---|---|
Site: | Monticello |
Issue date: | 08/15/1975 |
From: | NORTHERN STATES POWER CO. |
To: | |
Shared Package | |
ML20024G276 | List: |
References | |
NUDOCS 9104230504 | |
Download: ML20024G679 (8) | |
Text
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4.0 SURVEILINiCE REQUIREMENTS 3.0 LIMITIN ' CONDITIONS FOR OPERATION
- 3. The diffuser to lower plenum differential pressure reading on an individual jet pump is 107, or more, less than the mean of all jet pump differential pressures.
!! . Ilydraulic Snubbers II . Ilydraulic Snubbers During all modes of operation, except Cold Shut- The follwing surveillance requirements apply to all 1.
d wn and Refueling Shutdown, all hydraulic hydraulic snubbers listed in Table 3.6.1:
snubbers listed in Table 3.6.1 shall be operable except as noted in 3.6.11.2 through 3.6.H.4 1. All hydraulic snubbers whose seal material has been demonstrated by operating experience, lab testing below.
or analysis to be compatible with the operatinn From and after the time that a hydraulic stubber environment shall be visually inspected to verify 2.
is determined to be inoperable, continued reactor their operability in accordance with the fo11cwing operation is pemissible only during the succeed- schedule:
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 Next Required operable.
Number of Snubbers Found Inoperable Inspection If the requirements of 3.6.H.1 and 3.6.11.2 cannot' During Inspection Interval f~
- 3. or During Inspection be me t , an orderly shutdown shall be initiated Interval and the reactor shall be in a cold shutdown condition within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. 0 18 months + 257.
12 months _+ 257.
- 4. If a hydraulic snubber listed in Table 3.6.1 1 6 months + 257, is determined to be inoperable while the reactor 2 -
3,4 124 days f 257.
is in the shutdown or refueling mode, the snubber 62 days 1 257, shall be made operable prior to reactor startup. 5,6,7 28 31 days f 257 The required inspection interval shall not be lengthened more than one step at a time.
121 3.6/e.6 REV 9104230504 750815 PDR ADOCK 05000263 P pm
3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILIRfCE REQUIRE 1ENTS
- 5. Snubbers may be added to,or removed from, safety related systems without prior Lic- Snubbers may be categorized in two groups, ense Amendment to Table 3.6.1 provided that " accessible" or " inaccessible" based on their safety evaluations, documentation and re- accessibility for inspection during reacter porting are provided in accordance with 10CFR operation. These t'o groups may be inspected r independently according to the above schedt le.
50.59 and that a revision to Tabic 3.6.1 is included with a subsequent License Amend- 2. All hydraulic snubbers whose seal materials have nent request.
not been demonstrated to be campatibic with the operating environment shall be visually inspected for operability every 31 days.
- 3. The initial inspection shall be performed within a i
6 months from the date of issuance of these l :
specifications. For the purpose of entering the }
schedule in Specification 4.6.H.1 itshall be assumed that the facility had been on a 12-nonth ,
inspection interval. -
f
- 4. Once each refueling cycle, a representative sample ,
of 10 snubbers or approximately 107, of the snubbers, whichever is less, shall be functional:
tested for operability including verification of ~ ,
proper piston movement, lock up and bleed. For each unit and subsequent unit fornd inoperable, an additional 107, or ten snubbers shall t so ,
tested until no more failures are found or all units have been tested.
' 5. Once each refueling cycle at usst two repre-sentative snubbers from a relative!v severe environment shall be completely disassembled and examined for damage and abnormal seal degredatien.
3.6/4.6 121A [
REV i
i TABLE 3.6.1 (Page 1 of 4 )
Safety Related liydraulic Snubbers Accessible or Inaccessible Snubber No. Location - System - Elevation (A or I) i SS-1 Drywell - Main Steam 953' Az 279 0 I i SS-2 Dqrvell - Main Steam 953' Az 810 I SS-3 Drywell - Main Steam 950' Az 2120 I
, Cr-4 Drywell - Main Steam 950' Az 1480 I SS-7 Drywell - Main Steam 953' Az 2400 1 SS-S Drywell - Main Steam 953' Az 1200 I SS-11 Drywell - Feedwater 952' Az 3020 I t SS-12 Drywell - Feedwater 952' Az 5 80 1 SS-13 Drywell - Feedwater 952' Az 2580 1 SS-14 Drywell - Feedwater -
952' Az 960 I SS-17A Drywell - RHR 964' Az 720 I SS-17B Drywell - RilR 964' Az 720 I SS-ISA Drywell - RilR 964' Az 2880 I SS-18B Drywell - Tant 9 64' Az 2880 I SS-19 Drywell - MtR 964' Az 3410 I SS-20 Drywell - RIIR 9 64 ' Az 19 I SS-1AR Erywell - Recirculation 922' Az 3150 I SS-1BR Dryweli - Recirculation -
922' Az 1350 I ,_
SS-2AR Drywell - Recirculation 927' Az 3020 I SS-2BR Drywell - Recircula tion 927- Az 1220 I SS-3AR Drywell - Recirculation 927' Az 3280 I i SS-3BR Drywell - Recirculation 927' Az 1480 I SS-4AR(a) Dr- well - Recirculation 934' Az 3020 1 SS-4AR(b) Drywell - Recirculation 934' Az 3230 I SS-4BR(a) Drywell - Recirculation 934' Az 1200 1 SS-4BR(b) Drywell - Recirculation 934' Az 1490 1 SS-SAR Drywell - Recircul:ition 941' Az 315 I SS-5BR Dryvell - Recircula tion -941' Az 1350 1 SS-6AR Drywell - Recirculation 953' Az 2610 I l SS-6BR Drywell - Recirculat ion 953' Az 9 90 1 3.6/4.6 121B
- REV
__ . - - _ _ - _ _ - _ _ _ - _ - _ _ - - _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _- _l
Mm TAlllE ? . 6.1 (Page 2 of 4 )
Bi fety R,: lated fly <lraulic Snubbers Accessible or Inaccessible Ircetion - System - Elevation (A or I)
Snubber No. .
953' Az 323" I SS-7AR D rywel ? - Recirculati<n Az 32" I j Drywell - Recirculatian 953' ;
S S- 71,R Az 2700 I Drywell - Recircula ~en 927' SS-SAR 927' Az 9 00 I SS-8SR Drywell - Recirculation Az 710 I Drywell - Main Steaii 953' PSI-H2 950' Az 1480 I PSI-H3 Drywell - Main Stec a Az 1200 I Drywell - Main Ste:m 950' I PS2-H2 950' Az 2400 I PS3-H2 Drywell - Main Ste to Az 2120 I Drywell - Main St.am 950' PS4-il2 950' Az 1100 I av24-1.3 Drywell - Safety telief Az 1000 I RV24-1;4 Drywell - Safety Relief 935' l 935' Az 1000 I l
Rv24-?i4A Drywell - Safety Relief Az 1100 I
' Drywell - Safety Relie f 935' RV24 ~15 947' Az 4 80 I RV24A-!!4A Drywell - Sa fet" Relie f Az 115o 1 Drywell - Safety Relief 953' RV24/ -il7 939' Az 32 I RV24b-l!8 Drywell - Safe;y Relief Az 1800 I Drywell - Safe ty Relief 953' RV25-H1 ,
953' Az 1800 I RV2' -illa Drywell - Saf 2ty Relief Az 1900 1 Drywell - Sa!.ety Relief 948' RV23-il2 948' Az 1900 1 R V'.5 -112A Drywell - Sa fety Relie f Az 1800 I Drywell - Sitfety Relief 934' RV25-II3 945' Az 1200 I R'!25A-ll2 Drywell - Fafety Relie f Az 1200 I Drywell 'iafety I'elief 945' r.V25A-Il2A 953' Az 1350 I RV25A-l!7 Drywell - Safety Relief Az 2000 I Drywell - Safety Relief 953' RV26-Ill 953' Az 2003 I RV26-IIIA Drywell Safety Relief Az 2000 Drywell - Safety Relief 947' I RV26-H2 947' Az 2000 I RV26-il2A Dry sell - Safety Relief Az 2500 Drywel t - Sa fety Re lie f 940' I RV26A-il2 935' Az 2503 I RV26A-H2A Dryve'.1 - Sa fr ' f Pelief 121 C
( 3.6/A.6 REV
TABLE 3.6.1 (Page 3 o f 4 )
Sa fety Related Hydraulic Snubbers Accessible or inaccessible Location - System - Elevation (A or I)
Snubber !!o. e 950' Az 320 I RV27-Ill Drywell - Sa fety Polie f Az 230 I Drywell - Safety Relief 950' RV27-HIA 945' Az 270 I RV27-ll5 Drywell - Sa fety Relie f Az 270 I Drywell - Safety Relief 945' RV27-II6 Az 290" I Drywell - Safety Relief 953' RV27A-H2A 953' Az 290 I RV27A-ll3 Drywell - Safety Relief 938' Az 290 I RV27A-H9 Drywell - Safety Felief South Wall A SS-21 Torus Floor Level - RHR South W a ll A SS .22 Torus Floor Level - RHR Floor Level A SS-23 "B" RIIR Room - EllR A "A" RHk Room - RHR Floor Level SS-24 Southeast wall just A SS-25 RllR Discharge - BirR below torus catwalk A
"B" RilR Room - Core Spray Floor Level SS-26 A "B" RIIR Room - Core Spray Floor Level SS-27 Floor level A SS-2&A "A" RHR Room - Core Spray A "A" RilR Room - Core Spray Floor level S.-28B 954' A SS-29 Overhead, by N2 Analyzer - RHR A Overhead, by N2 Analyzer - RilR 954' SS-39 A Torus catwalk - RHR Discharge SS-31 916' A SS-32A "A" RHR Room; Behind Heat Exchanger - RHR A "A" RilR Room; Behind Heat Exchanger - RIIR 916' SS-32B SS-33 Above Torus on side sloping towards A Drywell - RilR Discharge SS-34 Above Torus on side sloping towards ---
A Drywell - RHR Discharge On North Wall, 912' A S5-35 HPCI Room - HPCI Pump Discharge A HPCI Rcom - IIPCI Turbine Exhaust Floor level A SS-36A Floor Level SS-363 HPCI Room - IIPCI Turbine Exhaust 121 D 3.4/4.6 REV
- 7 s
TABLE 3.6.1 (Page 4 of 4 )
igfety Related liydraulic Snubbers Accessible or i Inaccessible Snu_bbe r N o . _Locatio1 - System - Elevation (A or I) f S: -37 IIPCI Room - IIPCI Turbine Exhaust West Wall, 905' A
, SS-38A RCIC Rcoc2 - RCIC Turbine Exhaust West Wall, 906' A
! S' 'F B RCIC Foom - RCIC Turbine Exhaust West Wall, 906' A
[ MJ 0 Main Etean Chase - !!PCI Steam suppl'/ -
I
- SS-41 Above Torus Catvalk - Core Spray Discharge 927' A Sd-4. Above Torus Ring Header - IIPCI Steam E: haust North West Wall, 906' A 1
1 1
3.6/4.6 121 E RE7
Bases Continued 3.6 and 4.6:
A no::1c-riser systen failure ceuld also generate the ceincident failure of a jet pump body; hewever, the converse is not t rue.
The lack of any substantial stecs- in the jet purp body nakes failure frponsible j uithout an initial no :1c-riser synt. n f ailure.
II . I!ydraulIc Snubbers Snubbers ar, ' signed to prevent unrestrained pipe motion under dynamic loads as might occur curing an eartS-The consequence quake or severe transient, while al f < ming normal thernal notion during startup and shutdewn.
of an inoperable snubber is an increase in the probabilit:. of structural damage to piping as a res2It of a seismic or other event initiating dynamic loads. It is therefore required that all hydraulic snubbers required to protect the primary coolant systen or any other safety syst en or component be operable during reactor operation.
Because the snubber protection is required only during relatively low probability events, a period of 72 hcurs is allowed for repsirs or replacements. In case a shutdewn 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 vill permit an orderly shutdcen consistent with standard operating procedures. Since pin t startup should not c. mace with knmingly defective safety related equipment, Specification 3.6.II.4 prohibi ts startup with ineperabic snubbers.
All safety related hydraulic snubbers are visually inspected for overall integrity and eperability. The in-spection will include verification of proper orientation, adequase hydraulic fluid level and proper attach-ant of snubber to piping and structures.
Th e inspection frequency is based upon maintaining a constant level of snubber protection. Thus the required failurer. The number of inoperable snubbers inspection interval varies inversely with the observed snubber found during a required inspection determines the
- tine interval for the next required inspection. Inspectiens in-perfonted before that interval has elapsed may be used as a new reference point to determine the next spection. Ilowever, the results of such early inspections performed before the original required time interval has elapsed (nominal time less 257.) nay not be used to lengthet the required inspection interval. Any inspection whose results require a shorter inspection interval will override the previous schedule.
Experience at operating facilities has shown that the required surveillance program should assure an acceptable level of snebber performance provided that the seal materials are compatibic with the operating environrent.
Snubbers containing seal material which has not been demenstrated by operating experience, lab tests or analysis to be ccupatible with the operating environment should be inspected more frequently (every menth) until material cempatibility is confirmed or an appropriete changcout is completed.
{
138 3.6/4.6 BASES arv
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4 11 . Ilydraulic Snubbers (cantd.)
Exactination of defectiv snubbers at reactor facilities and material tests performed at several laboratorles has shcun that millable gwi polyurethane deteriorates rapidly under the temperature and moisture co vJitio-s present in many snubber locations. Although nolded polyurethane exhibits greater resistance to these conditions, it also msy be unsuitable for application in the higher terperature environments. Data are net currently available to precisely define an upper te=perature limit for the polded polyurethane. Lab tests i
and in-plant experience indicate that seal materials are avail ble, a primarity ethylene propylene compounds, j vhich should give satisfactory perfervance under the most severe conditions expected in reactor install tions.
To further increase the assurance of snubber reliability, functional tests should be performed once each j
refueling cycle. These tests will include stroking of the snubbers to verify preper pistion novement, lock-i 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 redistion areas or those especially difficult to remove need not be selected for functional tests provided operability was previcusly verified. To complement the visual external inspections, disassembly and internal examinat ion 3
t for coqonent damage and ' abnormal seal degradation should be performed. ' Die examinatien of two units, car's refueling cycle, selected from relatively severe environments should adequately serve this purpose. Any observed wear, breakdown or deterieration will provide a basis for additional inspections.
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l 3.6/4.6 MSES 138A
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- NRC DISThillUTION FOR PART 50 DOCKET MATERI AL S (1 LMPOR ARY FORM)
CONTROL NO: E 9_9_ b flLE:
FROM: N tthern state: Ivr Co DATl OF DOC DATE REC'D LTR TWX RPT OTHER
!!inneapolis,!!n L 0 Mcycr P -lhp 8-18-75 XXX ORIG CC OTHER SENT liRC PDR XX TO:
Mr cia:tbus n 3 signed SENT LOCAL PDR XX _
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CLASS UNCL ASS PROPINFO INPUT NO CYS REC'D DOCKET NO:
XXXXX 3 50-263
~ DESCRIPTION: ENCLOSURES:
d Ltr notari c 8-15-75...trans the following: /odt to OL7 Change to Tech Specs: Consistini of revisions to operability cind surveille.nci of hydraulic snubbers on sdfety related systri
....(40 cyr enc 1 ree'd)
PLANT NAME: P.: n t i :e 1 t ;
FOR ACTION /lNFORMATION 6-16-75 chf BUTLER (L) SCHWENCE R (L) ZIEM ANN (L) REG AN (E) REID(L)
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INTERNAL DISTRIBUTION TECH REVIEW DENTON LIC ASST , aft IND yI{EGflLE3 SCHROEDER GRIMES R. 'DIGGS (L) BR AIT M AN 7 NRC PDR MACCARY GAMMILL j
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P. KREUTZER (E)
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