ML20003E876

Revised Pages for Snubber Surveillance Tech Specs

ML20003E876
Person / Time
Site:	Cooper
Issue date:	04/09/1981
From:	NEBRASKA PUBLIC POWER DISTRICT
To:
Shared Package
ML20003E874	List: ML20003E873 ML20003E876
References
NUDOCS 8104170423
Download: ML20003E876 (14)

Text

.- .c' LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT 3.6.H Shock Suppressors (Snubbers) 4.6.H Shock Suppressors (Snubbers)

1. During all modes of operation The following surveillance requirements g except Cold Shutdown and Refuel, all safety related snubbers shall apply to all snubbers listed in Tables 3.6.1, 3.6.2, and 3.6.3.

be operable except as noted in 3.6.H.2 through 3.6.H.5 below. 1. All snubbers shall be visually in-spected in accordance with the

2. The snubbers listed in Tables following schedule:

) 3.6.1, 3.6.2, and 3.6.3 are re-quried to protect the primary Number of Snubbers Next Required I coolant system or other safety Found Inoperable Inspection-related systems or components. During Inspection Interval All others are therefore exempt or During Inspection from these specifications. Interval

3. With one or more snubbers in- 0 18 months i 25%

operable, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> re- 5% 12 months i 25%

place or restore the inoper- 10% 6 months i 25%

able snubber (s) to OPERABLE 25% 124 days i 25%

status and perform an engi- 37% 62 days i 25%

neering evaluation per 50% 31 days 1 25%

Specification 4.6.H.4 on the supported component or The required inspection interval declare the supported system shall not be lengthened more than inoperable and follow the one step at a time.

appropriate ACTION state-ment for that system. Snubbers may be categorized in groups, " accessible" or "inac-

4. If a snubber is determined to be cessible" based on their acces-inoperable while the reactor is in sibility for inspection during the shutdown or refuel mode, the reactor operation and by type.

snubber shall be made operable or These groups may be inspected replaced prior to reactor startup, independently according to the above schedule.

5. Snubbers may be added to or re-moved from safety related sys- 2. Visual Inspection Acceptance tems without prior License Criteria Amendment to Tables 3.6.1, 3.6.2, and 3.6.3, provided that a re- Visual inspections shall verify vision to these tables is in- (1) that there are no visible cluded with a subsequent Li- indications of damage or impaired cense Amendment request. OPERABILITY, (2) attachments to the foundation or supporting

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LIHITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT 4.6.H Shock Suppressors (Snubbers) (cont'd) structure are secure. Snubbers which appear inoperable as a result of vis-ual inspections may be determined OPERABLE for the purpose of establish-ing the next visual inspection inter-val, providing that (1) the cause of the rejection is clearly established and remedied for that particular snub-ber and for other snubbers that may be generically susceptible; or (2) the affected snubber is function-ally tested in the as found cendition and determined OPERABLE per Fpecif-ications 4.6.H.6 or 4.6.H.7 as ap-plicable. However, when the-fluid port of a hydraulic snubber is found to be uncovered, the snubber shall be determined inoperable and cannot be determined OPERABLE via functional testing for the purpose of establish-ing the next visual inspection inter-val. All snubbers connected to an inoperable common hydraulic fluid reservoir shall be counted as inop-erable snubbers.

3. At least once per 18 months during shutdown, a representative sample, 10% of the total of each type of snubber in use in the plant, shall be functionally tested either in place or in a bench test. For each snubber that does not meet the functional test acceptance criteria of Specification 4.6.4.6 or 4.6.4.7, an additional 10% of that type of snubber shall be functionally tested.

Hydraulic snubbers of rated capacity greater than 50,000 lbs. need not be functionally tested.

4. The representative sample selected for functional testing shall in-clude various configurations, op-erating environments and the range of size and capacity of snubbers.

Tables 3.6.1, 3.6.2, and 3.6.3 may l be used jointly or separately as the basis for the sampling plan.

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l LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT 4.6.H Shock Suppressors (Snubbers) (cont'd)

In addition to the regular sample, snubbers which failed the previous functional test shall be retested during the next test period. If a spare snubber has been installed in place of a failed snubber, then both the failed snubber (if it is repaired and installed in another position) and the spare snubber shall be retested.

Test results of these snubbers may not be included for the re-sampling.

Permanent or other exemptions from functional testing for individual snubbers, in high radition zones or that are difficult to remove may be granted by the Commission only if a justifiable basis for exemption is presented and/or snubber life de-structive testing was performed to qualifiy snubber operability for all design conditions at either the com-pletion of their fabrication or at a subsequent date.

If any snubber selected for func-tional testing either fails to lock-up or fails to move, i.e., frozen in place, the cause will be eval-uated and if caused by manufacturer or design deficiency all snubbers of

' the same design and subject to the same defect shall be tested or in-spected to determine if the defect is present. This testing require-ment shall be independent of the re-quire ments stated above for snubbers not meeting the functional test ac-ceptance criteria.

For the snubber (s) found inoperable, an engineering evaluation shall be performed to determine the need for further action or testing on affect-ed components.

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,- s LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT 4.6.H Shock Suppressors (Snubbers) (cont'd)

5. Hydraulic Snubbers Functional Test Acceptance Criteria The hydraulic snubber functional test shall verify that:

1. Activation (restraining action) is achieved within the specified range of velocity or acceleration in both tension and compression.

2. Snubber bleed, or release rate, where required, is within the specified range in compression or tension.

6. Mechanical Snubbera Functional Test Acceptance Criteria The mechanical snubber functional test shall verify that:

1. The force that initiates free movement of the snubber rod in either tension or compression is less than the specified maximum drag force.

2. Activation (restraining action) is achieved within the specified range of velocity or acceleration in both tension and compression.

3. Snubber release rate, where re-quired, is within the specified range in compression or tension.

7. Snubber Service Life Monitoring A record of the service life of each snubber, the date at which the des-Ignated service life commences and the installation and maintenance records on which the designated ser-vice life is based shall be main-tained as required by Specification 6.6.2.J.

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LIMITING CONDITION FOR OPERATION SURVEILLANCE REOUIREMENT 4.6.H Shock Suppressors (Snubbers) (cont'd)

Concurrent with the first inservice visual inspection and at least once per 18 months thereafter, the in-

. stallation and maintenance records i of each snubber listed in Tables l 3.6.1, 3.6.2, and 3.6.3 shall be reviewed to verify that the indi-cated service life has not been ex-ceeded or will not be exceeded prior to the next scheduled snubber service life review. If the indicated ser-vice life will be exceeded prior to the next scheduled snubber service

! life review, the snubber service 4 . life shall be reevaluated or the snubber shall be replaced or recon-ditioned so as to extend its service life beyond the date of the next scheduled service life review. This reevaluation, replacement or re-conditioning shall be indicated in the records.

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Table 3.6.1 SAFETY RELATED HYDRAUI.IC SHOCK SUPPRESSORS (SNUBBERS)

Snubber No. Location Elevation BS-S-1 Torus 870' BS-S-2 Torus Area' 889' BS-S-3 Torus Area 890' BS-S-113A Torus Area 890' BS-S-113B Torus Area 891' BS-S-116A Torus Area 889'

+- BS-S-116B Torus Area 889' BS-S-125A Torus Area 892' BS-S-125B Torus Area 891' CS-S-1 S.E. Quad 918'

) 929' CS-S-2 S.E. Quad 946' CS-S-3 S.E. Quad CS-S-6 S.E. Quad 918' CS-S-7 S.E. Quad 929' l 894' CS-VE-7 S.E. Quad CS-S-10 Rx Bldg, 931' 946' CS-S-11 Rx Bldg, 931' 946' CU-S-89 S.E. Torus Area 893' HP-S-4 S.W. Quad 872' HP-S-11 S.W. Quad 869' HP-S-15 S.W. Quad 874' HP-S-18A HPCI Rm 865' HP-S-22A HPCI Rm 865' 4

MS-S-1 S.W. Quad 864' MS-S-2 S.W. Quad 868' MS-S-3 S.W. Quad 880' MS-S-4 S.W. Quad 873' MS-S-7A S.W. Quad 874' MS-S-7B S.W. Quad 874' MS-S-8 Torus Area 885' MS-S-10 Torus Area 899'

S-S- 11 Torus Area 897' MS-S-11A Torus Area 897' l MS-S-12 Torus Area 888' MS-S-12A Torus Area 889' MS-S-13 "B" RHR Ex Rm 904' MS-S-13A "B" RHR Hx Rm 905' MS-S-13B "B" RHR Hx Rm 911' MS-S-14 "B" RHR Hx Rm 923' MS-S-15 "B" RER Hx Rm 934' MS-S-15A "B" RHR Hx Rm 934' l MS-S-16 Torus Area 885' MS-S- 16A Torus Area 881' MS-S-16B Torus Area 881'

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i Table 3.6.1 SAFETY RELATED HYDRAULIC SHOCK SUPPRESSORS (SNUBBERS) (Cont'd)

Snubber No. Location Elevation i

"A" RHR Hx Rm MS-S- 17 904' MS-S- 18 "A" RHR Hx Rm 905' MS-S- 19 "A" RHR Hx Rm 923' MS-S- 20 "A" RHR Hx Rm 934'

< MS-S- 20A "A" RHR Hx Rm 934' MS-S- 23 Torus Area 898' MS-S-24 Torus Area 898' MS-S- 25 N.E. Quad 877' MS-S-26 N.E. Quad 879' MS-S- 75 "A" RHR Hx Rm 932' l MS-S-76 "B" RHR Hx Rm 932' I, MS-S-111A "A" RHR Hx Rm 923' RCC-S- 3 Rx Bldg, 931' 945' RCC-S-4 Rx Bldg, 931' 943' i RCC-S- 20 Rx Bldg, 931' 953' l RCC-S-21 Rx Bldg, 931' 953' RCC-S-22 Rx Bldg, 931' 953' RF-S-1 N.E. Quad 898'

! RF-S- 1 A N.E. Quad 896' l RF-S- 2 N.E. Torus Area 896'

, RF-S- 3 HPCI Rm 870' R F-S-4 S.W. Torus Area 894' RF-S-5 S.W. Torus Area 897' RF-S- 6 S.W. Torus Area 891' RF-S-45C N.E. Quad 882' RF-S-45D N.E. Quad 882' RF-S-46A N.E. Quad 882' l RF-S- 51 A N.E. Torus 897' RF-S- 51B N E. Torus 897' t

RH-S-20 Rx Bldg, 903' 912' i Ril-S-21 Rx Bldg, 903' 911'

< RH-S-22 Torus Area 895' I l RH-S-23 Torus Area 892' FH-S-24 Torus Area 897' RH-S-25 N. RHR Ex Rm 927' RH-S-25A Rx Bldg, 903' 922' l RH-S-26 N. RHR Hx Rm 929' l RH-S-27A "A" RHR Hx Rm 933'

, RH-S-29 Rx Bldg, 903' 904' RH-S-30A Torus Area 898'

{ RH-S-30B Torus Area 898' l RH-S-32 Torus Area 894'

! RH-S-33D Torus 892' i

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Table 3.6.1 SAFETY RELATED HYDRAULIC SHOCK SUPPRESSORS (SNUBBERS) (Cont'd)

Snubber No. Location -Elevation Ril-S-34 Rx Bldg, 903' 919' l RII-S- 35 S. RHR Ex Rm 912' Ril-S- 36 S. RIIR Hx Rm 914' Ril-S- 37 S. RHR Hx Rm 916' Ril-S-38 S. RHR Hx Rm 930' Ril-S-39 S. RHR Hx Rm 927' RII-S-40 S. RHR Hx Rm 915' l RH-S-41 S.W. Quad 873' Ril-S-42 S.W. Quad 874' Ril-S-43 Torus Area 897' RII-S-44 S.W. Quad 884' l Ril-S-45 S.W. Quad 884' Ril-S-48 N.W. Quad 884' l RH-S-49 N.W. Quad 885' Ril-S-51 N. RHR Ex Rm 914' l Rll-S- 52 N. RHR Hx Rm 915' Ril-S- 54 N.W. Quad 873' l Ril-S-55 N.W. Quad 874' Ril-S-56 N. RHR Ex Rm 927' Ril-S- 57 N. RHR Hx Rm 927' Ril-S-59 Torus Area 896' Rll-S-65 S.W. Quad 887' Ril-S-66 Rx Bldg,903' 907' RII-S-76A Torus Area 898' RH-S-76B Torus Area 898' Ril-S- 77 Torus Area 890' Ril-S- 78A Torus Area 897' RH-S-78B Torus Area 897' Ril-S-80 N.W. Quad 889' Ril-S-96A Rx Bldg,903' 920' I Ril-S-98 N.W. Quad 891' Ril-S- 103A S.W. Quad 876' RII-S- 107A N.W. Quad 876' SW-II-23A Intake Str. 904' SW-H- 23D Intake Str. 904' SW-H-23E Intake Str. 904' SW-H-2311 Intake Str. 904'

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Table 3.6.2 ACCESSIBLE SAFETY RELATED MECHANICAL SHOCK SUPPRESSORS (SNUBBERS)

Snubber No. Location Elevation MS-S-9A Torus Area 894' MS-S-9B Torns Area 894' Ril-S-58 "A" RilR Hx Rm 921' RF-S-51C N.E. Torus Area 899' SW-il-23B Intake Str. 904' SW-II-23C . Intake Str. 904' SW-II-23F Intake Str. 904' SW-H-23G Intake Str. 904' I

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' Table 3.6.3 INACCESSIBLE SAFETY RELATED MECllANICAL S110CK SUPPRESSORS (SNUBBERS)

Snubber No. Location Elevation CS-S-4 Drywell 947' CS-S- 5 Drywell 951' CS-S-8 Drywell 947' CS-S-9 Drywell 951' CU-S- 3A Drywell 925' CU-S-3B Drywell 925' MS-S-21 Drywell 920' MS-S-22 Drywell 919' MS-S-63 Drywell 921' MS-S-149A Steam Tunnel, Rx Bldg 918' R F-S-8 Drywell 924' RF-S-9 Drywell 924' RF-S-10 Drywell 928' RF-S- 11 Drywell .924' RF-S- 12 Drywell 924'-

RF-S- 13 Drywell 928' RF-S-14 Drywell 925' RF-S- 15 Drywell 922' RF-S- 16 Drywell 923' RF-S-17 Drywell 927' RF-S- 18 Drywell 924' RF-S- 19 Drywell 924' Ril-S-3 Rx Under Shield Plug 972' Ril-S-4 Rx Cavity 972' Ril-S-5 Drywell 921' Ril-S-6 Drywell 920' Ril-S-7 Drywell 921' Ril-S-8A Drywell 918' Ril-S-8B Drywell 918' Ril-S-9 Drywell 915' Ril-S- 10 Drywell 911' Ril-S- 11 Drywell 916' Ril-S- 13 Drywell 922' Ril-S- 14 Drywell 921' Ril-S- 15 Dryvell 922' Ril-S- 16 Drywell 917' Ril-S- 17 Drywell 917' Ril-S- 18 Drywell 916' Ril-S- 19 Drywell 916' Ril-S- 67 Drywell 917' Ril-S- 68 Drywell 917' Ril-S-69A Drywell 915' Ril-S- 69B Drywell 915' Ril-S- 70 Drywell 916'

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\: o' Table 3.6.3 INACCESSIBLE SAFETY RELATED MECHANICAL SHOCK SUPPRESSORS (SNUBBERS) (Cont'd)

Snubber No. Location Elevation RH-S-71 Drywell 914' RH-S-72 Drywell 914' RH-S- 72A Drywell 914' RH-S-73 Drywell 916' SS-A2 Drywell 923' SS-A3 Drywell 922' SS-B2 Drywell 924' SS-B3 Drywell 922 SS-C2 Drywell 924' SS-C3 Drywell 922' SS-D2 Drywell 923' SS-D3 Drywell 923' SS-7Al Drywell 914' SS-7A2 Drywell 914' SS-7B1 Drywell 914' SS-7B2 Drywell 914' SS-8Al Drywell 917' SS-8A2 Drywell 917' SS-1A Drywell 891' SS-2A Drywell 898' SS-3Al Drywell 904' S S- 3A2 Drywell 904' 909' SS-4A Drywell SS-5A Drywell 898' SS-1B Drywell 891' i SS-2B Drywell 898' SS-3B1 Drywell 904' SS-3B2 Drywell 904' i SS-4B Drywell 909' SS-5B Drywell R98' VR-S-1 Drywell 902'

! VR-S- 2 Drywell 919' i VR-S- 3 Drywell 899'

- VR-S-4 Drywell 918' VR-S-5A Drywell 903'

', VR-S-5B Drywell 903' l VR-S- 6 Drywell 905' VR-S- 7A Drywell 898' VR-S- 7B Drywell 898' I VR-S- 8 Drywell 899'

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Table 3.6.3 INACCESSIBLE SAFETY RELATED MECHANICAL SHOCK SUPPRESSORS (SNUBBERS) (Cont'd)

Snubber No. Location Elevation VR-H- 61D Drywell VR-H-62C Drywell 899' V R-H- 63B Drywell 897' VR-H-63C Drywell 898' V R- 5 5-9-Y Drywell 919'

, VR- 55-9-Z Drywell 919' VR- S E-Z3-X Drywell 906' VR-55-23-Y Drywell 907' VR- 55-26-Z Drywell 906' VR 12-Y Drywell 913' VR 26-Y Drywell 916' VR 24-X Drywell 907' VR 24-Z Drywell 910' VR 12-Y Drywell 922' VR 12-Y Drywell 924' VR 7-X Drywell 920' VR 7-Z Drywell 920' VR 7-X Drywell 920' VR- 60-7-Z Drywell 920' VR 8-X Drywell 919' VR- 61-8-Y Drywell 919' i VR 8-Z Drywell 919' l VR 17-X Drywell 915' VR 17-Z Drywell 915' VR 8-X Drywell 922' VR- 62-8-Y Drywell 915' VR-62-8-Z Drywell 915' VR 17-X Drywell 915' Drywell 915' l VR 17-Z VR-S- 14 Drywell 896' VR-S- 32 Drywell 897' i VR-S-43 Drywell 894' VR-S- 51 Drywell 896' VR-S-87A Drywell 894' VR-S-87B Drywell 894'

' VR-S- 88 Drywell 894' VR-H- 62 B Drywell 899' VR-H- 64 D Drywell 899' 1

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e' BASES:

3.6.H and 4.6.H Snubbers i Snubbers are designed to prevent unrestrained' pipe motion under dynamic loads as might occur during an earthquake or severe trans-ient, while allowing normal thermal motion during startup and shutdown. The consequence of an inoperable snubber is an increase in the probability of structural damage to piping as a result of a seismic or other event initiating dynamic loads. It is therefore required that all snubbers required to protect the primary coolant system or any other safety system or component be operable during reactor operation.

Because the snubber protection is required only during relatively low probability events, a period of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> is allowed for repairs or replacement. In case a shutdown 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 will permit an orderly shutdown consistent with standard operating procedures. Since plant startup should not commence with knowingly defective safety related equipment, Specification 3.6.H.5 prohibits startup with inoperable snubbers.

All safety related snubbers are visually inspected for overall integrity and operability.

The inspection frequency is based upon maintaining a constant level of snubber protection. Thus the required inspection interval varies inversely with the observed snubber failures. The number of inoperable snubbers found during a required inspection determines the time interval for the next required inspection. Inspections performed before that interval has elapsed may be used as a new reference point to determine the next inspection. However, the results of such early inspections performed before the original required time interval has elapsed (nominal time less 25%) may not be used to lengthen the required inspection interval. Any' inspection wFose results require a shorter inspection interval will override the previous schedule.

When the cause of the rejection of a snubber is clearly established and remedied for that snubber and for any other snubbers that may be generically susceptible, and/or verified by functional testing, that snubber may be exempted from being counted as inoperable.

Generically susceptible snubbers are those which are of a specific -

make or model and have the same design features directly related to rejection of the snubber by visual inspection, or are similarly located or exposed to the same environmental conditions, such as temperature, radiation and vibration.

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e' BASES (cont'd)

When a snubber is found inoperable, an engineering evaluation is per-formed, in addition to the determination of the snubber mode of failure, in order to determine if any safety related component or system has been adversely affected by the inoperability of the snubber. The engineering evaluation shall determine whether or not the snubber mode of failure has imparted a significant effect or degradation on the supported com-ponent or system.

In cases where the cause of failure has been identified, additional snubbers,- having a high probability for the same type of failure or that are being used in the same application that caused the failure, shall be tested. This requirement increases the probability of locating inoper-

< able snubbers without testing 100% of the snubbers.

Hydraulic snubbers and mechanical snubbers may each be treated as a i different entity for the above surveillance programs.

To further increase the assurance of snubber reliability, functional tests should be performed once each refueling cycle. Ten percent of j each type of snubber represents an adequate sample for such tests.

1 Observed failures on these samples should require testing of additional units. Snabbers in high radiation areas or those especially dif ficult to remove need not be selected for functional tests provided operability was'previously verified.

The service life of a snubber is evaluated via manufacturer input and information through consideration of the snubber service conditions and associated installation and maintenance records (newly installed snubber, seal replaced, spring replaced, in high radiation area, in high temp-erature area, etc. . . ). The requirement to monitor the snubber ser-vice life is included to ensure that the snubbers periodically undergo a performance evaluation in view of their age and operating conditions.

These records will provide statistical bases for future consideration of snubber service life. The requirements for the maintenance of records and the snubber service life review are not intended to affect plant operation.

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6.6.2.G (cont'd) usage evaluation per the ASME Boiler and Pressure Vessel Code Section III was performed l for the conditions defined in the design specification. The locations to be monitored shall be:

1

a. The feedwater nozzles

b. The shell at or near the waterline

c. The flange studs

2. Monitoring, Recording, Evaluating, and Reporting l a. Operational transients that occur during plant operations will, at least annually, be reviewed and compared to the transient conditions defined in the component stress report for the locations listed in 1 above, and used as a basis for the existing fatigue analysis.

b. The number of transients which are comparable to or more severe than the transient evaluated in the stress report Code fatigue usage calculations will be recorded in an operating log book.

For those transients which are more severe, available data, such as the metal and fluid temperatures, pressures, flow rates, and other conditions will be recorded in the log book.

c. The number of transient events that exceed the design specification quantity and the number of transient events with a severity greater than that included in the existing Code fatigue usage calculations shall be added. When this sum exceeds the predicated number of design condition events by twenty-five2 , a fatigue usage evaluation of such events will be performed for the affected portion of the RCPB.

H. Records of individual plant staff members showing qualifications, training and retraining.

I.

Records for Environmental Qualification which are covered under the pro-visions of paragraph 6.8.

J. Records of the service lives of all hydraulic and mechanical snubbers, listed on Tables 3.6.1, 3.6.2, 3.6.3 including the date at which the ser-

' vice life commences and associated installation and maintenance records.

6.6.3 Records and logs relating to the following items shall be kept for two years.

A. The test results, in units of microcuries, for leak tests of scurces-l performed pursuant to Specification 3.8.A. -

1 B. Records of annual physical inventories verifying accountability of the sources on record.

1. See paragraph N-415.2, ASME Section III, 1965 Edition.

2. The Code rules permit exclusion of twenty-five (25) stress cycles from secondary stress and fatigue usage evaluation. (See paragraphs N-412(t)(3) and N-417.10(f) of the Summer 1968 Addenda to ASME Section III, 1968 Edition.)

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