ML20024G679

Proposed Tech Specs Re Operability & Surveillance of Hydraulic Snubbers on Safety Related Sys

ML20024G679
Person / Time
Site:	Monticello
Issue date:	08/15/1975
From:	NORTHERN STATES POWER CO.
To:
Shared Package
ML20024G276	List: ML20024G275 ML20024G280 ML20024G679
References
NUDOCS 9104230504
Download: ML20024G679 (8)

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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 1.

During all modes of operation, except Cold Shut-The follwing surveillance requirements apply to all 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 2.

From and after the time that a hydraulic stubber environment shall be visually inspected to verify 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 Number of Snubbers Next Required operable.

Found Inoperable Inspection 3.

If the requirements of 3.6.H.1 and 3.6.11.2 cannot' During Inspection Interval f~

be me t, an orderly shutdown shall be initiated or During Inspection and the reactor shall be in a cold shutdown Interval condition within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

18 months + 257.

0 1

12 months _+ 257.

If a hydraulic snubber listed in Table 3.6.1 6 months + 257, 4.

2 is determined to be inoperable while the reactor is in the shutdown or refueling mode, the snubber 3,4 124 days f 257.

shall be made operable prior to reactor startup.

5,6,7 62 days 1 257, 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

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3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILIRfCE REQUIRE 1ENTS 5.

Snubbers may be added to,or removed from, Snubbers may be categorized in two groups, safety related systems without prior Lic-

" accessible" or " inaccessible" based on their ense Amendment to Table 3.6.1 provided that accessibility for inspection during reacter safety evaluations, documentation and re-operation. These t'o groups may be inspected porting are provided in accordance with 10CFR r

50.59 and that a revision to Tabic 3.6.1 independently according to the above schedt le.

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

6 months from the date of issuance of these l

i specifications. For the purpose of entering the

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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

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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 I

i 0

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

0 SS-6AR Drywell - Recirculation 953' Az 261 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 (A or I)

Ircetion - System - Elevation Snubber No.

953' Az 323" I

SS-7AR D rywel ? - Recirculati<n 953' Az 32" I

j S S-71,R Drywell - Recirculatian 927' Az 2700 I

SS-SAR Drywell - Recircula ~en 927' Az 9 00 I

SS-8SR Drywell - Recirculation 953' Az 710 I

PSI-H2 Drywell - Main Steaii 950' Az 1480 I

PSI-H3 Drywell - Main Stec a 950' Az 1200 I

I PS2-H2 Drywell - Main Ste:m 950' Az 2400 I

PS3-H2 Drywell - Main Ste to 950' Az 2120 I

PS4-il2 Drywell - Main St.am 950' Az 1100 I

av24-1.3 Drywell - Safety telief 935' Az 1000 I

l RV24-1;4 Drywell - Safety Relief 935' Az 1000 I

l Rv24-?i4A Drywell - Safety Relief RV24 ~15 Drywell - Safety Relie f 935' Az 1100 I

947' Az 4 80 I

RV24A-!!4A Drywell - Sa fet" Relie f 953' Az 115o 1

RV24/ -il7 Drywell - Safety Relief 939' Az 32 I

RV24b-l!8 Drywell - Safe;y Relief 953' Az 1800 I

RV25-H1 Drywell - Safe ty Relief 953' Az 1800 I

RV2' -illa Drywell - Saf 2ty Relief 948' Az 1900 1

RV23-il2 Drywell - Sa!.ety Relief 948' Az 1900 1

R V'.5 -112A Drywell - Sa fety Relie f 934' Az 1800 I

RV25-II3 Drywell - Sitfety Relief 945' Az 1200 I

R'!25A-ll2 Drywell - Fafety Relie f 945' Az 1200 I

r.V25A-Il2A Drywell

'iafety I'elief 953' Az 1350 I

RV25A-l!7 Drywell - Safety Relief 953' Az 2000 I

RV26-Ill Drywell - Safety Relief 953' Az 2003 I

RV26-IIIA Drywell Safety Relief 947' Az 2000 I

RV26-H2 Drywell - Safety Relief 947' Az 2000 I

RV26-il2A Dry sell - Safety Relief 940' Az 2500 I

RV26A-il2 Drywel t - Sa fety Re lie f RV26A-H2A Dryve'.1 - Sa fr ' f Pelief 935' Az 2503 I

121 C

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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 950' Az 230 I

RV27-HIA Drywell - Safety Relief 945' Az 270 I

RV27-ll5 Drywell - Sa fety Relie f 945' Az 270 I

RV27-II6 Drywell - Safety Relief 953' Az 290" I

RV27A-H2A Drywell - Safety Relief 953' Az 290 I

RV27A-ll3 Drywell - Safety Relief 938' Az 290 I

RV27A-H9 Drywell - Safety Felief A

South Wall SS-21 Torus Floor Level - RHR A

South W ll a

SS.22 Torus Floor Level - RHR A

Floor Level SS-23 "B" RIIR Room - EllR A

Floor Level SS-24 "A" RHk Room - RHR A

Southeast wall just SS-25 RllR Discharge - BirR below torus catwalk A

Floor Level SS-26 "B" RilR Room - Core Spray A

Floor Level SS-27 "B" RIIR Room - Core Spray A

Floor level SS-2&A "A" RHR Room - Core Spray A

Floor level S.-28B "A" RilR Room - Core Spray A

954' SS-29 Overhead, by N2 Analyzer - RHR A

954' SS-39 Overhead, by N2 Analyzer - RilR SS-31 Torus catwalk - RHR Discharge A

A SS-32A "A" RHR Room; Behind Heat Exchanger - RHR 916' A

SS-32B "A" RilR Room; Behind Heat Exchanger - RIIR 916' Above Torus on side sloping towards SS-33 Drywell - RilR Discharge A

Above Torus on side sloping towards A

SS-34 Drywell - RHR Discharge On North Wall, 912' A

S5-35 HPCI Room - HPCI Pump Discharge A

Floor level SS-36A HPCI Rcom - IIPCI Turbine Exhaust A

Floor Level HPCI Room - IIPCI Turbine Exhaust SS-363 121 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

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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.

level of snubber protection. Thus the required Th e inspection frequency is based upon maintaining a constant 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-interval has elapsed may be used as a new reference point to determine the next perfonted before that Ilowever, the results of such early inspections performed before the original required time interval spection.

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.

lab tests or Snubbers containing seal material which has not been demenstrated by operating experience, 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.

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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, primarity ethylene propylene compounds, a

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 for coqonent damage and ' abnormal seal degradation should be performed. ' Die examinatien of two units, car's 3

t 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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CLASS UNCL ASS PROPINFO INPUT NO CYS REC'D DOCKET NO:

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~ 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)

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