ML13310B562

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Proposed Tech Spec Change 132,eliminating Snubber Listings from Shock Absorbers Surveillance & Operability Specs,Per Generic Ltr 84-13
ML13310B562
Person / Time
Site: San Onofre Southern California Edison icon.png
Issue date: 07/23/1984
From:
SOUTHERN CALIFORNIA EDISON CO.
To:
Shared Package
ML13310B558 List:
References
GL-84-13, TAC-55407, NUDOCS 8407250397
Download: ML13310B562 (21)


Text

3.13 SHOCK SUPPRESSORS (SNUBBERS)

OPERABILITY Applicability:

Applies to safety related shock suppressors (snubbers) delineated in Tables 3.13.1 and 3.13.2.

Objective:

To define operability requirements of snubbers required to protect safety related piping from unrestricted motion when subjected to dynamic loading as might occur during a seismic event or severe transient.

Specification:

A.

During MODES 1, 2, 3, and 4, all snubbers listed in Tables 3.13.1 and 3.13.2 shall be operable except as noted in 3.13.B through 3.13.D below.

B. Within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of finding one or more snubbers inoperable, replace or restore the inoperable snubber(s) to OPERABLE status and perform an engineering evaluation per Specification 4.14.C on the supported component.

Alternatively, declare the supported system inoperable and follow the appropriate Specification for that system.

C.

If the requirements of A and B above cannot be met, perform the actions required in Section 3.0.

D.

If a snubber is determined to be inoperable while the 68 reactor is in MODES 5 or 6, the snubber shall be made 10/8/

operable or replaced prior to reactor startup.

E.

Snubbers may be added to safety related systems without prior License knendment to Tables 3.13.1 and/or 3.13.2 provided that a revision to Tables 3.13.1 and/or 3.13.2 are included with a subsequent License Amendment request.

Basis:

All snubbers are required to be OPERABLE to ensure that the structural integrity of the reactor coolant system and all other safety related systems is maintained during and following a seismic or other event initiating dynamic loads.

Snubbers excluded from this inspection program are those installed on non-safety related systems and then only if their failure, or failure of the system on which they are installed, would have no adverse effect on any safety-related system.

The visual inspection frequency is based upon maintaining a constant level of snubber protection to systems.

Therefore, the required inspection interval varies inversely with the observed snubber failures and is determined by the number of inoperable snubbers found during an inspection.

Inspections performed before that interval has elapsed may be used as a new reference point to determine the next inspection.

How ever, 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 whose results require a shorter inspection interval will override the previous schedule.

8407250397 840723 PDR ADOCK 05000206 3-35 Revised:

10/8/82 P

PDR

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 verified by in-service 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.

When a snubber is found inoperable, an engineering evaluation is performed, 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 component or system.

To provide assurance of snubber functional reliability, a 68 representative sample of the installed snubbers will be 10/8/:

functionally tested during plant shutdowns at refueling outage intervals. Observed failures of these sample snubbers shall require functional testing of additional units.

Snubbers of rated capacity greater than 50,000 pounds are exempt from functional testing requirements because of the impracti cability of testing such large units.

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

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 temperature area, etc...).

The requirement to monitor the snubber service 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 require ments for the maintenance of records and the snubber service life review are not intended to affect plant operation.

3-36 Revised:

1018/82

TABLE 3.13.1 Page 1 of 4 SAFETY RELATED HYDRAULIC SNUBBERS SNUBBERS IN SNUBBERS HIGH RADIATION ESPECIALLY SNUBBERS AREA DURING DIFFICULT ACCESSIBLE SNUBBER NO.

LOCATION LINE NO.

SHUTDOWN' TO REMOVE CATEGORY" OR INACCESSIBLE (YES OR NO)

(A OR I) 1-S--SW--1 Main Steam 1

YES I

1--SW-1-2 Piping System YES I

1 -S-SW-1 -3 YES I

1-S-SW-1-4 YES I

2-S-SW-1-5 NO A

2-S-SW-1-8 NO 2

A 2-S-SW-1-9 NO 2

A 2-S-SW.1-10 NO A

2-S-SW-1-11 NO A

I-SW-2-1 Main Steam 2

YES I

1-SW-2-2 Piping System YES I

1-SW-2-3 YES I

1 -SW-2-4 YES I

2-SW-2-5 NO A

2-SW-2-8 NO 2

A 2-SW-2-9 NO 2

A 2 -SW-2-10 NO A

2-SW-2-11 NO A

1-SW-3-1 Main Steam 3

YES Piping System 1-SW-4-1 Main Steam 4

YES I

Piping System 1-SW-5-1 Main Steam 5

YE3 Piping System

Page 2 of 4 SNUBBERS IN SNUBBERS HIGH RADIATION ESPECIALLY SNUBBERS AREA DURING DIFFICULT ACCESSIBLE SNUBBER NO.

LOCATION LINE NO.

SHUTDOWN' TO REMOVE CATEGORY"*

OR INACCESSIBLE (YES OR NO)

(A OR I) 1-S-SW-6, 7-1 Main Steam 6

YES I

1-S-SW-6-1 Piping System YES I

1-S-SW-6-2 YES I

1-S-SW-6-3 YES I

1-S-SW-6-4 YES I

1-S-SW-6-5 YES I

1-S-S-6-6 1-S-SW-7-1 Main Steam 7

YES I

1-S-SW-7-2 Piping System YES I

1-S-SW-7-3 YES I

1-S-SW-7-4 YES I

1-S-SW-7-5 YES I

1-S-SW-7-6 YES I

2-9-SW-5 Main Steam 9

NO A

Piping System 6-15-SW Main Steam 15 NO A

6-15-SW-6 Piping System NO A

2-S-SW-17-1 Main Steam 17 NO A

2-S-SW-17-2 Piping System NO A

2-S-SW-17-4 NO A

2-S-17-Sw-6 NO A

2-S-17-SW-9 NO A

2-S-SW-18-1 Main Steam 18 NO A

2-S-SW-18-2 Piping System NO A

2-S-SW-18-4 NO A

2-S-18-SW-6 NO A

2-3-18-SW-8 NO A

Page 3 of 4 SNUBRERS IN SNUBBERS HIGH RADIATION ESPECIALLY SNUBBERS AREA DURING DIFFICULT ACCESSIBLE SNUBBER NO.

LOCATION LINE NO.

SHUTDOWN' TO REMOVE CATEGORY" OR INACCESSIBLE (YES OR NO)

(A OR I) 2-S-50-SW-1 Main Steam 50 NO A

2-S-50-SW-2 Piping System NO A

2-S-51-SW-1 Main Steam 51 NO A

2-S-51-SW-2 NO A

1-S-SW-391-1 Feedwater 391 YES I

1-S-SW-391-2 Piping System YES I

1 -S-SW-391-3 YES I

1 -S-SW-391-4 YES I

1-S-SW-392-1 Feedwater 392 YES I

1-S-SW-392-2 Piping System YES I

1-S-SW-392-3 YES I

1-S-SW-392-4 YES 1-S-SW-392-5 YES I

1-S-SW-393-1 Feedwater 392 YES I

1-S-SW-393-2 Piping System YES I

1-S-SW-393-3 YES I

1-S-SW-393-4 YES I

1-SW-734-2 Containment 734 YES I

Spray System T-8-PS-27 Refueling Water 734 & 747 NO A

Piping System In 1-8-735-SW-1 Refueling Water 735 YES 2

I Piping System 00 (1)c)

Page 4 of 4 SNIBBERS IN SNUBBERS HIGH RADIATION ESPECIALLY SNUBBERS AREA DURING DIFFICULT ACCESSIBLE SNUBBER NO.

LOCATION LINE NO.

SHUTDOWN*

TO REMOVE CATEGORY**

OR INACCESSIBLE (YES OR NO)

(A OR I) 1-SC-602R-6 Pressurizer 5035 YES I

Relief Piping System 5-SW-151R-10 Safety Injection 6002 NO 2

A 5-SW-151R-11 Piping System NO 2

A 6-151R-13 Safety Injection 6003 NO 2

A 6-151R-14 Piping System NO 2

A 5-S-1501R-40 Safety Injection 6004 NO A

5-S-1501R-41 NO A

5-3S-1501R-9 NO A

6-1501-R-42 Safety Injection 6005 NO A

6-1501-R-43 Piping System NO A

1-SS-1501R-4 Safety Injection 6006 YES I

1-SS-1501R-5 Piping System YES I

1-SS-1501R-3 YES I

1-83-1501R-6 Safety Injection 6007 YES I

1-SS-1501R-7 Piping System YES I

1-SS-1501R-1 Safety Injection 6008 YES I

1-SS-1501R-2 Piping System YES I

E-1A Steam Generators YES 2

I E-lB YES 2

I E-1C YES 2

I 0 Modifications to this column due to changes in high radiation areas may be made within prior License Amendment provided that a revision to Table 3.13.2 is included with the next License Amendment Request.

  • CATEGORY
1.

First snubber away from each reactor vessel nozzle.

2.

Snubber within 5 feet of heavy equipment.

3.

Snubber within 10 feet of the discharge from a safety relief valve.

Ul)

TABLE 3.13.2 Page 1 of 2 SAFETY RELATED MECHANICAL SNUBBERS SNUBBERS IN SNUBBERS HIGH RADIATION ESPECIALLY SNUBBERS AREA DURING DIFFICULT ACCESSIRLE SNUBBER NO.

LOCATION LINE NO.

SHUTDOWN' TO REMOVE CATEGORY**

OR INACCESSIBLE (YES OR NO)

(A OR I) 5-318-sW-10 Safety Injection 318 NO A

5-318-SW-11 Piping System NO A

1-6019-SS-2 Safety Injection 734 NO A

1-734-SS-003 Sphere Spray 734 YES I

SA-16-1 No.

I D/G 1540 NO A

SA-16-2 Intake 15112 NO A

SA-16-3 No.

1 D/G 1544 NO A

SA-16-4 Exhaust NO A

SA-16-5 NO A

SA-16-6 NO 3

A SA-17-1 No.

2 D/G 1547 NO A

SA-17-2 Intake 1549 NO A

SA-17-3 No.

2 D/G 1551 NO A

SA-17-4 Exhaust NO 3

A SA-17-5 NO A

SA-17-6 NO 3

A SA-1 Safety Injection 3122 NO A

Piping System 5-8S-151R-lI Safety Injection 6002 NO A

14-PS-2A Piping System NO A

6-sw-151R-15 6003 NO A

14 -PS -r1A_

NO A

Page 2 of 2 Table 3.13.2 (Cont'd)

SNUBBERS IN SNUBBERS HIGH RADIATION ESPECIALLY SNUBBERS AREA DURING DIFFICULT ACCESSIBLE SNUBBER NO.

LOCATION LINE NO.

SHUTDOWN*

TO REMOVE CATEGORY" OR INACCESSIBLE (YES OR NO)

(A OR I) 2-SC-1501R-03 Safety Injection 6005 A

6-SC-1501R-02 Piping System A

1 -SS-1501-11 6006 A

1-SS-1501-R-14 YES 1

I 1-SS-1501 -R-10 6008 YES I

1-SS-1501-R-1 3 YES 1

I 1-SS-1501-12 Safety Injection 6007 YES 1

I 1-SS-1501-R-15 Piping System YES I

1-6018-SS-006 Safety Injection 6018 YES I

Piping System YES I

1-6019-SS-006 Safety Injection 6019 YES I

Piping System Modifications to this column due to changes in high radiation areas may be made without prior License Amendment provided that a revision to Table 3.13.2 is included with the next License Amendment Request.

6 CATEGORY -

1. First snubber away from each reactor vessel nozzle.
2.

Snubber within 5 feet of heavy equipment.

3.

Snubber within 10 feet of the discharge from a safety relief valve.

J.

(1) 0 (I0

4.14 SHOCK SUPPRESSW (SNUBBERS) SURVEILLANCE 0

Applicability:

Applies to surveillance of safety related snubbers delineated in Tables 3.13.1 and 3.13.2.

Objective:

To ensure the operability of safety related snubbers.

Specification:

Each snubber listed in Tables 3.13.1 and 3.13.2 shall be demonstrated OPERABLE by performance of the following augmented in-service inspection program and the requirements of Specification 3.13.

A.

Visual Inspections Visual inspections shall be performed in accordance with the following schedule:

No. of Snubbers Found Inoperable During Inspection or During Inspection Subsequent Visual Interval Inspection Period*

0 18 months + 135 days 68 1

12 months +

90 days 10/8/

2 6 months +

45 days 3, 4 124 days

+

31 days 5, 6, 7 62 days

+

16 days 8 or more 31 days +

8 days The snubbers may be categorized into two groups: Those accessible and those inaccessible during normal reactor operation.

Each group may be inspected independently in accordance with the above schedule. Further, the subgroups -

mechanical and hydraulic -

may be inspected independently.

All hydraulic snubbers, with seal material not fabricated from ethylene propylene or other materials demonstrated compatible with the operating environment, shall be visually inspected for operability at intervals of roughly half the duration that the seal material has been demonstrated to remain operable or the Visual Inspection Period, if less.

For materials of uncertain compatibility with the environment, the seals shall be visually inspected every 31 + 8 days.

(As of mid-1981, there were no such seals.)

  • The inspection interval shall not be lengthened more than one step at a time.

4-29 Revised:

10/8/82

B.

Visual Inspection Acce ce Criteria Visual inspections shall verify (1) that there are no visible indications of damage or impaired OPERABILITY, (2) attachments to those foundation or supporting structure are secure, and (3) in those locations where snubber movement can be manually induced without disconnecting the snubber, that the snubber has freedom of movement and is not frozen up.

Snubbers which appear inoperable as a result of visual inspections may be determined OPERABLE for the purpose of establishing the next visual inspection interval, providing that (1) the cause of the rejection is clearly established and remedied for that particular snubber and for other snubbers that may be generically susceptible; and (2) the affected snubber is functionally tested in the as found condition and determined OPERABLE per Specifications 4.14.D or 4.14.E, as applicable.

C.

Functional Tests At least once per refueling cycle shutdown, a representative sample (10% of the total, the next larger integer number, of each type of 68 snubber in use in the plant) shall be 10/8/82 functionally tested either in place or in a bench test.

For each snubber that does not meet the functional test acceptance criteria of Specification 4.14.D or 4.14.E, an additional 10% of that type of snubber shall be functionally tested.

The representative sample selected for functional testing shall include the various configurations, operating environments and the range of size and capacity of snubbers, exempting snubbers of capacity greater than 50,000 pounds, i.e., E-1A, E-1B and E-1C. At least 25% of the snubbers in the representative sample shall include snubbers from the following three categories:

1. The first snubber away from each reactor vessel nozzle
2.

Snubbers within five feet of heavy equipment (valve, pump, turbine, motor, etc.)

3.

Snubbers within ten feet of the discharge from a safety relief valve 4-30 Revised:

10/8/82

Snubbers identified inble 3.13.1 and 3.13.2 as "Especially Difficult to Remove" or in "High Radiation Zones During Shutdown" shall also be included in the representative sample. Tables 3.13.1 and 3.13.2 may be used jointly or separately as the basis for the sampling plan.

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.

If any snubber selected for functional testing either fails to lockup or fails to move, i.e.,

frozen in place, the cause will be evaluated and if caused by manufacturer or design 68 deficiency, all snubbers of the same design 10/8/82 subject to the same defect shall be functionally tested. This testing requirement shall be independent of the requirements stated above for snubbers not meeting the functional.

test acceptance criteria.

For the snubber(s) found inoperable, an engineering evaluation shall be performed on the components which are supported by the snubber(s).

The purpose of this engineering evaluation shall be to determine if the components supported by the snubber(s) were adversely affected by the inoperability of the snubber(s) in order to ensure that the supported component remains capable of meeting the designed service.

D. 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. For snubbers specifically required to not displace under continuous load, the ability of the snubber to withstand load without displacement shall be verified.

4-31 Revised:

10/8/82

E.

Mechanical Snubbers Fultional Test Acceptance Criteria The mechanical snubber functional test shall verify, after visual examination for damage, that the snubbers have freedom of movement by performing a manual test over the range of stroke in both compression and tension.

(Per IE Bulletin 81-01)

F.

Snubber Service Life Monitoring A record of the service life of each snubber, the date at which the designated service life commences and the installation and maintenance records on which the designated service is based shall be maintained as required by Specification 6.10.2.k.

Concurrent with the first inservice visual 68 inspection and at least once per refueling 10/8/8 outage thereafter, the installation and maintenance records for each snubber listed in Tables 3.13.1 and 3.13.2 shall be reviewed to verify that the indicated service life has not been exceeded or will not be exceeded prior to the next scheduled snubber service life review. If the indicated service life will be exceeded prior to the next scheduled snubber service life review, the snubber service life shall be reevaluated or the snubber shall be replaced or reconditioned so as to extend its service life beyond the date of the next scheduled service life review. This reevaluation, replacement or reconditioning shall be indicated in the records.

Basis:

Refer to the basis given in 3.13.

4-31a Revised:

10/8/82

6.10.2 The following records shall be retained for the duration of the Facility Operating License:

a.

Record and drawing changes reflecting facility design modifications made to systems and equipment described in the Final Safety Analysis Report.

b.

Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.

c.

Records of radiation exposure for all individuals entering radiation control areas.

d.

Records of gaseous and liquid radioactive material released to the environs.

e. Records of transient or operational cycles for those facility components designed for a limited number of transients or cycles.
f.

Records of in-service inspections performed pursuant to these Technical Specifications.

g. Records of Quality Assurance activities as required by the QA Manual.
h.

Records of reviews performed for changes made to procedures or equipment or reviews or tests and experiments pursuant to 10CFR50.59.

i.

Records of meetings of the OSRC and NARC.

j.

Records for Environmental Qualification which are covered under the provisions of paragraph 6.12.

k.

Records of the service lives of all hydraulic and mechanical snubbers listed in Tables 3.13.1 and 3.13.2, including the date at which the service life commences and associated installation and maintenance records.

ENCLOSURE 2

3.13 SHOCK SUPPRESSORS (SNUBBERS) OPERABILITY Applicability Applies to safety-related shock suppressors (snubbers).

Objective To define operability requirements of snubbers required to protect safety-related piping from unrestricted motion when subjected to dynamic loading as might occur during a seismic event or severe transient.

Specification A. During MODES 1, 2, 3 and 4 (MODES 5 and 6 for snubbers located in systems required OPERABLE in those MODES) all snubbers shall be OPERABLE. The only snubbers excluded from this requirement are those installed on non-safety-related systems and then only if their failure or failure of the system on which they are installed, would have no adverse effect on any safety-related system.

B. With one or more snubbers inoperable, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> replace or restore the inoperable snubber(s) to OPERABLE status and perform an engineering evaluation per Specification 4.14.C on the supported component or declare the supported system inoperable and follow the appropriate ACTION statement for that system.

Basis Snubbers are provided to ensure that the structural integrity of the reactor coolant system and all other safety-related systems is maintained during and following a seismic or other event initiating dynamic loads.

The visual inspection frequency is based upon maintaining a constant level of snubber protection to systems.

Therefore, the required inspection interval varies inversely with the observed snubber failures and is determined by the number of inoperable snubbers found during an 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 whose 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 verified by in-service 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.

When a snubber is found inoperable, an engineering evaluation is performed, 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 component or system.

To provide assurance of snubber functional reliability, a representative sample of the installed snubbers will be functionally tested during plant shutdowns at refueling outage intervals.

Observed failures of these sample snubbers will require functional testing of additional units.

Snubbers of rated capacity greater than 120,000 pounds are exempt from functional testing requirements because of the impracticability of testing such large units.

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

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 temperature area, etc...).

The requirement to monitor the snubber service 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.

4.14 SHOCK SUPPRESSORS (SNUBBERS) SURVEILLANCE Applicability Applies to surveillance of safety-related snubbers.

Objective :

To ensure the operability of safety-related snubbers.

Specification Each snubber shall be demonstrated OPERABLE by performance of the following augmented in-service inspection program and the requirements of Specification 3.13.

A. Visual Inspections.

Visual inspections shall be performed in accordance with the following schedule:

No. Inoperable per Inspection Subsequent Visual Period Inspection Period*

0 18 months +

25%

1 12 months +

25%

2 6 months + 25%

3, 4 124 days

+

25%

5, 6, 7 62 days

+

25%

8 or more 31 days

+

25%

The snubbers may be categorized into two groups:

Those accessible and those inaccessible during normal reactor operation. Each group may be inspected independently in accordance with the above schedule. Further, the subgroups -

mechanical and hydraulic - may be inspected independently.

B. Visual Inspection Acceptance Criteria Visual inspections shall verify (1) that there are no visible indications of damage or impaired OPERABILTY, and (2) attachments to the foundation or supporting structure are secure. Snubbers which appear inoperable as a result of visual inspections may be determined OPERABLE for the purpose of establishing the next visual inspection interval, providing that (1) the cause of the rejection is clearly established and remedied for that particular snubber and for other snubbers that may be generically susceptible; and (2) the affected snubber is functionally tested in the as-found condition and determined OPERABLE per Specification 4.14.D or 4.14.E, as applicable.

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 establishing the next visual inspection interval.

All snubbers connected to an inoperable common hydraulic fluid reservoir shall be counted as inoperable snubbers.

  • The inspection interval shall not be lengthened more than one step at a time.

C. Functional Tests At least once per refueling cycle 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 4.14.0 or 4.14.E, an additional 10% of that type of snubber shall be functionally tested until no more failures are found or until all snubbers have been functionally tested.

The representative sample selected for functional testing shall include the various configurations, operating environments and the range of size and capacity of snubbers, exempting snubbers of capacity greater than 120,000 pounds, i.e., E-1A, E-1B and E-1C. At least 25%

of the snubbers in the representative sample shall include snubbers from the following three categories:

1. The first snubber away from each reactor vessel nozzle;
2. Snubbers within five feet of heavy equipment (valve, pump, turbine, motor, etc.);
3. Snubbers within ten feet of the discharge from a safety relief valve.

Snubbers that are especially difficult to remove or are located in high radiation zones during shutdown shall also be included in the representative sample.*

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.

If any snubber selected for functional testing either falls to lockup or falls to move, I.e., frozen in place, the cause will be evaluated and if caused by manufacturer or design deficiency all snubbers of the same design subject to the same defect shall be functionally tested.

This testing requirement shall be independent of the requirements stated above for snubbers not meeting the functional test acceptance criteria.

  • Permanent or other exemptions from functional testing for individual snubbers in these categories may be granted by the Commission only if a justifiable basis for exemption is presented and/or snubber life destructive testing was performed to qualify snubber operability for all design conditions at either the completion of their fabrication or at a subsequent date.

For the snubber(s) found inoperable, an engineering evaluation shall be performed on the components which are supported by the snubber(s).

The purpose of this engineering evaluation shall be to determine if the components supported by the snubber(s) were adversely affected by the inoperability of the snubber(s) in order to ensure that-the supported component remains capable of meeting the designed service.

D. 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.

For snubbers specifically required to not displace under continuous load, the ability of the snubber to withstand load without displacement shall be verified.

E. Mechanical Snubbers Functional Test Acceptance Criteria The mechanical snubber functional test shall verify that:

1.

The force required to initiate or maintain motion of the snubber is within the specified range in both directions of travel;

2. Activation (restraining action) is achieved within the specified range of velocity or acceleration in both tension and compression;
3. Snubber release rate, where required, is within the specified range in compression or tension.

For snubbers specifically required not to displace under continuous load, the ability of the snubber to withstand load without displacement shall be verified.

F. Snubber Service Life Monitoring A record of the service life of each snubber, the date at which the designated service life commences and the installation and maintenance records on which the designated service life is based shall be maintained as required by Specification 6.10.2.k. Concurrent with the first in-service visual inspection and at least once per refueling cycle shutdown thereafter, the installation and maintenance records for each snubber shall be reviewed to verify that the indicated service life has not been exceeded or will not be exceeded prior to the next scheduled snubber service life review. If the indicated service life will be exceeded prior to the next scheduled snubber service life review, the snubber service life

shall be reevaluated or the snubber shall be replaced or reconditioned so as to extend its service life beyond the date of the next scheduled service life review. This reevaluation, replacement or reconditioning shall be indicated in the records.

Basis:

Refer to the basis given in 3.13

6.10.2 The following records shall be retained for the duration of the Facility Operating License:

a. Record and drawing changes reflecting facility design modifications made to systems and equipment described in the Final Safety Analysis Report.
b. Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.
c. Records of radiation exposure for all individuals entering radiation control areas.
d. Records of gaseous and liquid radioactive material released to the environs.
e. Records of transient or operational cycles for those facility components designed for a limited number of transients or cycles.
f. Records of in-service inspections performed pursuant to these Technical Specifications.
g. Records of Quality Assurance activities as required by the QA Manual.
h. Records of reviews performed for changes made to procedures or equipment or reviews or tests and experiments pursuant to 10 CFR 50.59.
i. Records of meetings of the OSRC and NARC.
j. Records for Environmental Qualification which are covered under the provisions of paragraph 6.12.
k. Records of the service lives of all safety-related hydraulic and mechanical snubbers including the date at which the service life commences and associated installation and maintenance records.

2048F