Text

Proposed Tech Spec Changes Reflecting Revised Specs for Snubber Inservice Surveillance Requirements
	ML20081J240
Person / Time
Site:	Hatch
Issue date:	10/27/1983
From:	; GEORGIA POWER CO.
To:	;
Shared Package
ML20081J235	List: ML20081J231; ML20081J240;
References
	TAC-08298, TAC-08310, TAC-48362, TAC-48363, TAC-8298, TAC-8310, NUDOCS 8311080380
	Download: ML20081J240 (58)
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ENCLOSURE 1 NRC DOCKET 50-321 OPERATING LICENSE DPR-57 EDWIN I. HATCH NUCLEAR PIANP UNIT 1 REQUEST TO AMEND TECHNICAL SPECIFICATIONS The proposed change to Technical Specifications (Appendix A to Operating License DPR-57) would be incorporated as follows:

Renove Page Insert Page iv iv viii viii 3.6-10a through 3.6-109 3.6-10a through 3.6-10t 3.6-31 3.6-31 3.6-32 3.6-32 6-20 6-20 8311080380 831027 PDR ADOCK 05000321 PDR p

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Section Section Page LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.6 PRIMARY SYSTEM BOUNDARY 4.6 PRIMARY SYSTEM BOUNDARY 3.6-1 A. Reactor Coolant Heatup A. Reactor Coolant Heatup. 3.6-1 and Cooldown and Cooldown B. Reactor Vessel Temperature -

B. Reactor Vessel Temperature 3.6-1 and Pressure and Pressure r C. Reactor Vessel Head Stud C. Reactor Vessel Head Stud 3.6-2 Tensioning Tensioning D. Idle Recirculation Loop D. Idle Recirculation Loop 3.6-2 Startup Startup E. Recirculation Pump Start E. Recirculation Pump Start 3.6-3 F. Reactor Coolant Chemistry ,. F. Reactor Coolant Chemistry 3.6-4 G. Reactor Coolant Leakage G. Reactor Coolant Leakage 3.6-7 H. Safety and Relief Valves H. Safety and Relief Valves 3.6-9

1. det Pumps I. Jet Pumps 3.6-9 J. Recirculation Pump Speeds J. Recirculation Pump Speeds 3.6-10 K. Structural Integrity of K. Structural Integrity of Primary System Boundary Primary System Boundary 3.6-10 L. Snubbers t. Snubbers 3.6-10a 3.7 CONTAINMENT SYSTEMS 4.7 CONTAINMENT SYSTEMS 3.7-1 A. Primary Containment A. Primary Containment 3.7-1 B. Standby Gas Treatment System B. Standby Gas Treatment System 3.7-10 C. Secondary Containment C. Secondary Containment 3.7-12 D. Primary Containment D. Primary Containment 3.7-13 Isolation Valves Isolation Valves 3.8 RADI0 ACTIVE MATERIALS 4.8 RADI0 ACTIVE MATERIALS 3.3-1 A. Miscellaneous Radioactive A. Miscellaneous Radioactive 3.8-1 Materials Sources Materials Sources 3.9 AUXILIARY ELECTRICAL SYSTEMS 4.9 AUXILIARY ELECTRICAL SYSTEMS 3.9-1 i

A. Requirements for Reactor A. Auxiliary Electrical 3.9-1 i Startup Systems Equipment iv

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LIST OF TABLES (Concluded)

Table Titl e Page 4.2-7 Check, Functional Test, and Calibration Minimum Frequency. 3.2-40 For Neutron Monitoring Instrumentation Which Initiates Control Rod Blocks .

4.2-8 . Check, Functional Test, and Calibration Minimum Frequency <3.1-42 for Radiation Monitoring Systems Which Limit Radioactivity P Release 4.2-9 Check and Calibration Minimum Frequency for Instrumentation 3.2-45 Which Initiates Recirculation Pump Trip 4.2-10 Check, Functional Test, and Calibration Minimum Frequency 3.2-46 for Instrumentation Which Monitors Leakage into the Drywell 4.2-11 Check and CalibrationjMinimum Frequency for Instrumentation 3.2-48 Which Provides Surveillance Information 3.6-l a Safety Related Hydraulic Snubbers 3. 6-10e ,

3.6-lb Safety Related Mechanical Snubbers 3.6-10q

4. 6-1 In-Service Inspection Program 3.6-11 3.7-1 Primary Containment Isolation Valves 3.7-16 3.7-2 Testable Penetrations with Double 0-Ring Seals 3.7-21 3.7-3 Testable Penetrations with Testable Bellows 3.7-22 3.7-4 Primary Containment Testable Isolation Valves 3.7-23 3.13.1 Fire Detectors 3.13-2 3.13-2 Fire Hose Stations 3.13-9 6.2.2-1 Minimum Shift Crew Composition 6-3 6.9-1 Special Reporting Requirments 6-19 h

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3/4.6.L SNUBBERS LIMITIIG COEITION IOR OPERATION 3.6.L All snubbers listed in Tables 3.6-la and 3.6-lb shall be OPERABLE.

APPLICABIL' Conditions 1, 2, and 3.

ACTION:

With one or more snubbers inoperable, within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months replace or restore the inoperable snubber (s) to OPERABLE status and perform an engineering evaluation per Specification 4.6.L.3 on the supported component or declare the supported system inoperable and follow the appropriate limiting condition of operation statement (s) for that syst a.

SURVEILIANCE REQUIREMENIS 4.6.L Each snubber shall be demonstrated OPERABLE by performance of the following inservice inspection program.

1. Visual Inspections All safety-related snubbers listed in Tables 3.6-la and 3.6-lb shall be visually examined to verify snubber operability. Visual inspections shall be performed in accordance with the following schedule:

No. Inoperable Snubbers Subsequent Visual per Inspection Period Inspection Period

0 18 months + 25%

1 12 months T 25%

2 6 months T 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 l and those inaccessible during reactor operation. Each group may be inspected independently in accordance with the above schedule.

2. Visual Inspection Acceptance Criteria Visual inspections shall verify (1) that there are no visible indications of damage or impaired OPERABILITY, (2) attachments to the foundation or supporting structure are secure, and (3) for mechanical snubbers where snubber movement can be manually induced, the snubbers shall be inspected as follows: (a) Safety-related

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

HA'ICH - UNIT 1 3.6-10a

e 3/4.6.L SNUBBERS SURVEILLAICE REQUIREMENTS (Continued) systems associated with the snubbers listed in Table 3.6-lb shall be inspected to determine if there has been a severe dynamic event.

(b) In the event of a severe dynamic event, snubbers in that system which experiaced the event shall be inspected during the refueling outage to assure the snubbers have freedom of movement and are not frozen up. The inspection shall consist of verifying freedan of motion using one of the following: (i) Manually induced snubber movement; (ii) stroking the mechanical snubber through its full rang of travel. If one or more mechanical snubbers are found to be frozen up during this inspection, those snubbers shall be replaced (or overhauled) . Re-inspection shall subsequently be performed according to the schedule of 4.6.L.1, but the scope of the examination shall be limited to the safety-related systems associated with the snubbers listed in Table 3.6-lb. 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 4.6.L.4 or 4.6.L.5, as applicable.

3. Functional Tests At least once per 18 months during shutdown, a representative sample of 10% of the total of each type (hydraulic or mechanical) safety-related 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.L.4 or 4.6.L.5, an additional sample of at least 1/2 the size of the initial lot of that type of snubber shall be functionally tested.

Functional testing shall continue until no additional inoperable snubbers of a particular type are found within a sample or until all snubbers listed in Table 3.6-la or 3.6-lb, as applicable, 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. The representative sample shall be selected randomly from the total population identified in Tables 3.6-la and 3.6-1b. ,

HATG - UNIT 1 3.6-10b

3/4.6.L SNUBBERS SURVEIILAFCE REQUIREMENTS (Continued)

Snutters identified in Tables 3.6-la and 3.6-lb as "Especially Difficult to Remove" or in "High Radiation Zones During Shutdown" shall also be included in the representative sample *. Tables 3.6-la and 3.6-lb may be used jointly or separately as the basis for the sampling plan.

In addition to the regular sample, snubbers placed in the same location as snubbers which failed the previous functional test shall be retested during the next test period. Test results of these snubbers shall not be included in the sampling plan.

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 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 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.

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

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

b. Snubber bleed, or release rate, where required, is within the specified range in compression or tension. Ebr snubbers specifically required to not displace under continuous load, the ability of the snubber to withstand load without displacement shall be verified.

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

HNIG - UNIT 1 3.6-10c I

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3/4.6.L SNUBBERS SURVEILLMCE REQUIREMENTS (Continued)

5. Mechanical Snubbers Functional % st Acceptance Criteria The mechanical snubber functional test shall verify that:

1. The snubber operates freely over the stroke in both tension and compression.

2. The force that initiates free movement of the snubber rod in either tension or conpression is less than the specified maximum drag force. Specified maximum drag force is nominally five (5) pounds or one percent (1%) of rated snubber load, whichever is greater.

6. Unit Outage Inaccessible Snubber Inspection In the event that all inaccessible snubbers are inspected, functionally tested, and repaired as necessary during a unit outage, and that it is thus demonstrated that all inaccessible snubbers are operable, the schedule in Specification 4.6.L.1 may be re-entered on a 6-month inspection interval for the inaccessible snubbers.

7. Snubber Service Life Monitoring A record of the service life of each snubber, the date at which the designated service life comences and the installation and maintenance records on which the designated service life is based shall be maintained as required by Specification 6.10.2.1.

Concurrent with the inservice visual inspection performed during the first refueling outage following issuance of this amendment and at least once per 18 months thereafter, the installation and maintenance records for each snubber listed in Tables 3.6-la and 3.6-lb shall be reviewed to verify that the indicated service life has not been exceeded or will not be exceeded by more than 10% prior to the next scheduled snubber service life review. If the indicated service life will be exceeded by more than 10% 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. The results of the reevaluation may be used to justify a change to the service life of the snubber. This reevaluation replacement or reconditioning shall be indicated in the records.

HA'IG - UNIT 1 3.6-10d

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i . TABLE 3.6-la -

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SAFETY RELATED HYDRAULIC' SNUBBERS

HIGH RADIATION SNUBSER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR ZONE .ESPECIALLY DIFFICULT NO. (Oty.) ON, LOCATION AND ELEVATION INACCESSIBLE DURING SHUTDOWN ** TO REMOVE Reactor building (A or I) (Yes or No) (Yes or No) tbclear Boiler System SS-1 (1) Az. 720, El. 150' I No No SS-2 (1) Az. 720, El. ISU' I No No SS-3 (1) Az. 00, El. 140 I No No SS-4 (1) Az. 50, El. 128' I No No SS-5 (1) Az. 00, El. 140' I c. tb No SS-6 (1) Az. 1080, El. 150' I No No w SS-7 (1) Az. 900, El. 150' I No tb b SS-8 (1) Az. 1600, El. 151 I No No i SS-9 (1) Az. 950, El. 144' I No No SS-10 (1) Az. 900, El. 142' I No 'Yes

? SS-ll (1) Az. 1000, El. 138' I No Yes SS-12 (1) Az. 850, El. 144' I No Yes SS-13 (1) Az. 820, El. 143' I No No SS-14 (1) Az. 3150, El. 150' I No No SS-15 (1) Az. 900, El. 145' I No No SS-16 (1) Az. 900, El. 144' I TJo No SS-17 (1) Az. 1700, El. 145' I No Yes SS-18 (1)

Az. 1600, El. 145' I No Yes SS-19 (1) Az. 1600, El. 134' I tb No SS-20 (1) Az. 1600, El. 145' I No Yes

Snubbers may be added to safety related systens without prior License Amendment to Table 3.6-la provided that a revision to Table 3.6-la is included with the next License ,Amendmmt request.

- Modifications to this column due to changes in high radiation areas may be made without prior License Amendment provided that the revision to Table 3.6-la is included with the next License Amendment request.

_ _s

5 N

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i TABLE 3.6-la -

SAFETY RELATED HYDRAULIC' SNUBBERS *

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HIGH RADIATION SNUBBER SYSTEM SNUG 8ER INSTALLED ACCESSIBLE OR ZONE .ESPECIALLY DIFFICULT NO. (Oty.)

ON, LOCATION AND ELEVATION INACCESSIBLE DURINC SHUTDOWN ** TO REMOVE Reactor Building (A or 1) (Yes or No) (Yes or No)

Nuclear Boiler System (Continued)

SS-21 (1) Az. 1350, El. 158' I No No SS-22 (1) Az. 1600, El. 152' I No No SS-23 (1) Az. 2780, El. 150' I No No SS-24 (1) Az. 2700, El. 150' I No No SS-26 (1) Az. 2750, El. 145' I ,- No No SS-27 (1) Az. 2700, El. 138' I No No w SS-28 (1) Az. 2700, El. 142' I No Yes SS-29 (1) Az. 2700, El. 140' I No No

, SS-31 (1) Az. 2700, El. 139' I No No

,_. SS-32 (1) Az. 2750, El. 125' I No No R SS-33A (1) Az. 2850, El. 123' I No No SS-338 (1) Az. 2850, El. 123' I No No SS-34 (1) Az. 2800, El. 120 I No No SS-35 (1) Az. 2920, El. 120' I No No SS-36 (1) Az. 3070, El. 148' I No No SS-37 (1) Az. 3150, El. 150' I No No SS-38 (1) Az. 90, El. 128' I No No SS-39 (1) Az. 90, El. 128' I No No SS-40 (1) Az. 00, El. 123' I No No 55-41 (1) Az. 3450, El. 155' I No No

Snubbers may be added to safety related systems without prior License Amendment to Table 3.6-la provided that a revision to Table 3.6-la is included with the next License, Amendment request.

- Modifications to this column due to changes in high radiation areas may be made without prior License Amendment provided that the revision to Table 3.6-la is included with the next License Amendment request.

5 A

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. TABLE 3.6-la .

E *

j SAFETY RELATED HYDRAULIC' SNUBBERS

HIGH RADIATION SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR ZONE ,ESPECIALLY DIFFICULT NO. (Oty.) ON, LOCATION AND ELEVATION INACCESSIBLE DURING SHUTDOWN **

TO REMOVE Reactor Buildinq (A or 1) (Yes or No) (Yes or No)

Nuclear Boiler System (Continued)

SS-42 (1) Az. 3470, El. 151' I No No SS-43 (l' Az. 3400, El. 155' I No No SS-44 (1) Az. 3430, El. 155' I No No SS-45 (1) Az. 670, El. 118' I No No SS-46 (1) Az. 670, El. 120' I .; No No MVVH-23 (1) Az. 2700, El. 144' I No Yes P' MVVH-24 (1) Az. 2700, El. 144' I No Yes

Az. 2700, El. 144' MVVH-25 (1) I tb Yes MVVH-27 (1) Az. 2250, El. 124' I No No Es MVVH-28 (1) Az. 2500, El. 128' I No No

" Az. 2500, El. l'28' MVVH-29 (1) I No No MVVH-31 (1) Az. 1400, El. 149' I No No MVVH-32 (1) Az. 1400, El. 148' I No No MVVH-33 (1) Az. 1400, El. 145' I No No MVVH-35 (1) Az. 900, El. 126' I No tb MVVH-36 (1) AZ. 900, El. 126' I No tb MVVH-37 (1) Az. 900, El, 126' I No No FDH-ll (2) Az. 160, El, 147' I No No FDH-12 (2) Az. 00, El. 147' I No No FDH-13 (1) Az. 400, El. 148' I No No

Snubbers may be added to safety related systems without prior License Amendment to Table 3.6-la provided that a revision to Table 3.6-la is included with the next Licens.e, Amendment request.

- Modifications to this column due to changes in high radiation areas may be made without prior License Amendment provided that the revision to Table 3.6-la is included with the next License Amendment request.

__-a

5

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i -

TABLE 3.6-la '

SAFETY RELATED HYDRAULIC SNUBBERS *

~

HIGH RADIATION SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR ZONE ;ESPECIALLY DIFFICULT NO. (Oty.) ON, LOCATION AND ELEVATION INACCESSIBLE DURING SHUTDOWN ** TO REMOVE Reactor Building (A or I) (Yes or No) (Yes or No)

Nuclear Boiler System (Continued)

FDH-14 (1) Az. 750, El. 148' I No No FDH-15 (1) Az. 530, El. 148' I No No FDH-16 (1) Az. 790, El. 146' I No No FDH-17 (1) Az. 2800, El. 148' I No No FDH-18 (1) Az. 2810, El. 146' I '- No No FDH-19 (1) Az. 980, El. 150' I No , No y FDH-21 (2) Az. 1500, El. 165' I No No o & 2100, i FDH-22 (2) Az. 1200, El. 165' I No No

- & 2400, O FDH-23 (1) Az. 600, El. 164' I No No FDH-24 (1) Az. 300, El. 167' I No No FDH-25 (1) Az. 3300, El. 164' I No No FDH-26 (1) Az. 3100, El. 167' I No No DFDH-28 (1) 4'S47-8' ERA, El. 132' I No No DFDH-30 (1) 4'NR7-8' ERA, El. 132' I No No DFDH-32 (1) Az. 140, El. 132' I No No DFDH-36 (1) Az. 00, El. 132' I No No

SnuDbers may be added to safety related systems without prior License Amendment to Table 3.6-la provided that a revision to Table 3.6-la is included with the next License Amendment request.

- Modifications to this column due to changes in high radiation areas may be made without prior License Amendment provided that the revision to Table 3.6-la is included with the next License Amcndment request. .

5 g ,-

f ,

TABLE 3.6-la

~

E SAFETY RELATED HYDRAULIC SNUBBERS

U

- HICH RADIATION SNU90ER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR ZONE ESPECIALLY DIFFICULT NO. (Oty.) ON, LOCATION AND ELEVATION INACCESSIBLE DURING SHUTDOWN ** - TO REMOVE Reactor Huilding (A or I) (Yes or No) (Yes or No)

Rift System S-1 (1) Az. 2700, El. 141' I No No S-2 (1) Az. 2700, El. 141' I No No S-4 (1) Az. 2100, El. 141' I No No S-5 (1) Az. 2400, El. 141' I No No S-15 (1) Az. 1850, El. 139' I ..

No Yes SM-1 (1) Az. 1800, El. 134' I No No SM-2 (1) Az. 1800, El. 140' I No -

Yes F SM-3 (1) Az. 2250, El. 146' I No Yes SM-4 (1) Az. 2250, El. 146' I No Yes SM-8 (1) Az. 900, El. 146' I No No a

~

Recirc System SS-Al (1) Az. 3150, El. 123' - I No No SS-A2 (1) Az. 3150, El. 123' I No No SS-A3 (1) Az. 3150, El. 123' I No No SS-A4 (1) Az. 3100, El. 131' I No No SS-A5 (1) Az. 3200, El. 131' I No No SS-A6 (1) Az. 3150, El. 134' I No No SS-A7 (1) Az. 150, El. 134' I No No

Snubbers may be added to safety related systems without prior License Amendment to Table 3.6-la provided that a revision to Table 3.6-la is included with the next License Amendment request.

- Modifications to this column due to changes in high radiation areas may be made without prior License Amendment provided that the revision to Table 3.6-la is included with the next License Amendment request.

1 5

M

= TABLE 3.6-la .

g SAFETY RELATED HYORAULIC SNUBBERS

U

- HIGH RADIATION SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR ZONE ESPECIALLY DIFFICULT NO. (Oty.) ON, LOCATION AND ELEVATION INACCESSIBLE DURING FHUTDOWN** . TO REMOVE Reactor Building (A or I) (Yes or No) (Yes or No)

Recirc System (Continued)

SS-A8 (1) Az. 100, El. 134' I N3 No SS-Al2 (1) Az. 2700, El. 145' -

I No No SS-A13 (1) Az. 2700, El. 145' I No No SS-A14 (1) Az. 2700, El. 122' I No No SS-B1 (1) Az. 1400, El. 120' I ..

No No SS-B2 (1) Az. 1350, El. 123' I No No SS-B3 (1) Az. 1350, El. 123' I No . No F SS-84 (1) Az. 1450, El. 131' I No No

SS-85 (1) Az. 1350, El. 131' I No No

' Az. 1350, El. 137' SS-B6 (1) I No Yes g SS-B7 (1) Az. 1850, El . 140 ' - I No No SS-88 (1) Az. 1800, El. 140' I No No SS-B12 (1) Az. 900, El. 145' I No tb ,

SS-Bl3 (1) Az. 900, El. 145' I No No SS-B14 (1) Az. 900, El. 116' I No No Core Spray System CSH-75 (1) 10'NR 3- 7'WRL, El. 125' A No No CSH-71.(1) 7'NR13-10'WRL, El. 121' A tb No CSH-79 (1) 2'NR 9- 7'WRH, El. 172' A No No 4-

Snubbers may be added to safety related systems without prior License Amendment to Table 3.6-la provided that a revision to Table 3.6-la is included with the next License Amendnsit request.

- Modifications to this column due to changes in high radiation areas may be made without prior License Amendment provided that the revisien to Table 3.6-la is included with the next License Amendment request. '

i

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TABLE 3.6-la -

4 SAFETY RELATED HYDRAULIC SNUBBERS

HIGH RADIATION SNUBEER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR ZONE ;ESPECIALLY DIFFICULT NO. (Oty.) ON, LOCATION AND ELEVATION INACCESSIBLE DURING SHUTDOWN #* TO REMOVE Heactor building (A or I) (Yes or No) (Yes or No)

HPCI System HPCIH- 9 (1) 13'SRl- 6'ERC, El. 88' A No No FFCIH-13 (1) 7'SR1- 2'WRL, El. 94' A No No HPSEH- 2 (1) 12'NR2-10'WRL, El. 92' A No No HPSEH- 8 (2) 6'NR2- 4'NRC, El. 112' A No No HPSEH-12 (1) 5'NR3- 3'ERF, El. 123'-8" A V No No HPSEH-13 (2) 4'NR3- 3'ERF, El. 123'-6" A No No P

" HPSEH-17 (1) 5'NR3-14'ERF, El. 123'-6" A No tb

' iPSEH-55 (1) 8'SRl-25'WRL, El. 98' A No No HPSEH-57 (1) l'SRl-18'WRL, El. 99'-6" A No No E UPSEH-58 (1) 4'SRl-18'WRL, .El. 99' A No No HPSEH-60 (2) 4'NR2- 4'NRC, El. 120' A No No HPSEH-61 (1) 3'NRS-ll'ERH, El. 123' A No No HPSEH-62 (1) 3'NRS-ll'ERH, El. 123' A No No IPSEH-63 (1) 8'NR7-13'ERH, El. 123' A No No HPSEH-66 (1) 13'SR9- 2'ERH, El. 122' A No No HPSEH-67 (1) 8'SRll-6'ERH, El. 123' A No No HPSEH-72 (1) ll'SR 2-6'ERH, El. 124' A No No HPSEH-73 (1) 11'SR 2-5'ERH, El. 124' A No No HPSEH-74 (1) 7'SR3-ll'ERH, El. 122' A No No HPSEH-76 (1) l'NR3- 7'WRF, El. 123' A No No

Snubbers may be added to safety related systems without prior License Amendment to Table 3.6-la provided that a revision to Table 3.6-la is included with the next License Jimendment request.

- Modifications to this column due to changes in high radiation areas may be made without prior License Amendment provided that the revision to Table 3.6-la is included with the next License Teendment request.

5 '

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=

i TABLE 3.6-la .

e: -

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~

SAFETY RELATED HYDRAULIC'SNUBGERS*

HIGH RADIATION SNUBSER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR ZONE .ESPECIALLY DIFFICULT NO. (Oty.) ON, LOCATION AND ELEVATION INACCESSIBLE DURING SHUTDOWN ** ' TO REMOVE Reactor Building (A or I) (Yes or No) (Yes or No)

HPCI System (Continued)

HPSEH-77 (1) 8'NR3-13'WRF, El. 123' A No No HPSEH-80 (1) ll'NR13-6'ERH, 'El. 126' A No No HPSEH-81 (1) 12'NR13-5'ERL, El. 126' A No No HPSEH-82 (1) 3'SRll-5'WRH, El. 123' A No No HPSEH-83 (1) 6'NRll-l'ERF, El. 123' A .

. No No HPSEH-84 (1) 8'NRll-13'WRF, El. 123' A No No u HPSEH-85 (1) 7'NR11-ll'WRF, El. 122' A No No

's a HPSEH-87 (1) l'SRll- 7'WRF, El. 125' A No No i HPSEH-88 (1) 12'NR2-12' WRL, El. 120' A No No

-. HPSEH-89 (2) ll'SR2- 3' ERG,' El. 123' A No No S HPSEH-90 (1) 5'NR3-13' ERF, El. 125' A No No HPSEH-91 (2) 5'SR3- 8' ERF, El. 123'-6" A No No HPSEH-92 (1) 8'NR3- 3' ERH, El. 123' A No No HPSEH-93 (1) 8'NR3- 3' ERH, El. 123' A No No RCIC System RCSEH-2 (1) 2'SRll-15' ERA, El. 101' A No No RCSEH-20 (1) l'NRll-14' ERA, El. 98' A tb No RCSEH-21 (1) 7'SR 9- S' ERA, El. 120' A No Yes RCSEH-23 (2) 14'SR 7- 9' ERA, El. 122' A No Yes t

Snuboers may be added to safety related systems without prior License Amendment to Table 3.6-la provided that a revision to Table 3.6-la is included with the next License 'Anendment request.

- Modifications to this column due to changes in high radiation areas may be made without prior License Amendment provided that the revision to Table 3.6-la is included with the next License Amendment request. ,

.-i 9

h ,

TABLE 3.6-la ,

s H

SAFETY RELATED HYORAULIC SNUBBERS

q HIGH RADIATION j SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR ZONE :ESPECIALLY DIFFICULT

~

NO. (Oty.) ON, LOCATION AND ELEVATION 1HACCESSIBLE DURING SHUTDOWN ** TO REMOVE

, Heactor Buildinr1 (A or I) (Yes or No) (Yes or No) ,

i i

{ RHR System RHRH-184 (1) 3'SR3-17'ERH, El. 90' A No No

, RHRH-185 (1) 3'SR3-17'ERH, El. 91' A No No I RHRH-186 (2) 0'SR3-12'ERH, El. 88' A No No I RHRH-187 (2) 4'NR3- 8'ERH, El. 89' A No No l RHRH-188 (1) 5'SRS- S'WRL, El. 90' A Y No No j u RHRH-189 (1) 2'tRS- 8'WRL, El. 90' A No . No

, RHRH-192 (1) 9'NR3-18'ERH, El. 123' A No No

, RHRH-193 (1) 9'NR3-17'ERH, El. 123' A No No l

- RHRH-195 (1) 6'SR3-18'WRL, El. 125' A No No p RHRH-196 (1) 6'SR3-18'WRL, El. 120' A No No j RHRH-199 (1) 10'SR3- 3'WRL, El. 123' A No No ;

j RHRH-202 (1) 6'SR7- 7'ERH, El. 110' A No No

) RHRH-207 (2) 10'SR7-15'ERH, El. 151' A No N'o j RHRH-209 (2) 6'NR3-16'WRL, El. 105' A No No j

RHRH-210 (1) 9'NR3-16'WRL, El. 108' A No No l l RHRH-211 (2) 7'NR3-10'WRL, El. 100' A No No j RHRH-212 (1) 6'NR3-12'WRL, El. 104' A No No 9 RHRH-213 (1) 3'SR2-12'WRL, El. 124' A No No l RHRH-214 (1) 3'SR2- 2'WRL, El. 119' A No No j: RHRH-215 (2) 3'SR2-12'WRL, El. 118' A No No ll l

Snubbers may be added to safety related systems without prior License Amendment to Table 3.6-la provided that a revision to Table 3.6-la is included with the next License-Amendment request. t l ** Modifications to this column due to changes in high radiation areas may be made without prior License Amendment provided that the revision to Table 3.6-la is included with the next License i Amendment request.

l

5

?

=

i TABLE 3.6-la '

c

y SAFETY RELATED HYDRAULIC SNUBBERS *

~

HIGH RADIATION SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR ZONE :ESPECIALLY DIFFICULT NO. (Oty.) ON, LOCATION AND ELEVATION INACCESSIBLE DURING SHUTDOWN ** TO REMOVE Reactor Building (A or I) (Yes or No) (Yes or No)

RHR System (Continued)

RHRH-216 (1) ll'NR3-16'WRL, El. 122' A No No RHRH-217 (1) ll'NR3-19'WRL, El. 121' A No No RHRH-218 (1) 9'SR2-13'ERH, El. 116' A No No RHRH-220 (1) 4'SR7-12'WRL, El. 126' A No No RHRH-221 (1) 2'SR7-10'WRL, El. 122' A V No No RHRH-222 (2) 2'SR7-10'WRL, El. 120' & 122' A No , No y RHRH-223 (1) 1/2'NRll-4'ERH, El. 125' A No No o RHRH-224 (1) 3'SR11-7'ERH, El. 123' A No No i RHRH-225 (1) 9'NR13-13'ERH, El. 117' A No No RHRH-226 (1) 12'SRll-19'WRL, El. 121' A No No E RHRH-227 (1) 12 SRll-17'WRL, El. 122' A No No RHRH-228 (1) 3'NR13-12'WRL, El. 124' A tb No RHRH-229 (1) 3'NR13-12'WRL, El. 120' A No No RHRH-230 (2) 3'NR13-12'WRL, El. 116' & 119' A No No RHRH-231 (2) 9'SRll-17'WRL, El. 104' A No No RHRH-232 (1) 9'SRll-17'WRL, El. 107' A No No RHRH-233 (1) 7'SRll-10'WRL, El. 97' A No No RHRH-234 (1) 6'SRll-12'WRL, El. 104' A No No RHRH-237 (2) 2'NR 9- 3'ERH, El. 155' A No No RHRH-238 (2) 2'NR 9- 4'WRH, El. 159' A No No

Snubbers may be added to safety related systems without prior License Amendment to Table 3.6-la provided that a revision to Table 3.6-la is included with the next License Amendment request.

- Modifications to this column due to changes in high radiation areas may be made without prior License Amendment provided that the revision to Table 3.6-la is included with the next License Amendment request.

5 F!

f TABLE 3.6-la -

SAFETY RELATED HYDRAULIC SNUBBERS

HIGH RADIATION SNUB 3ER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR ZONE .ESPECIALLY DIFFICULT NO. (Oty.) ON, LOCATION AND ELEVATION ItJACCESSIBLE DURING SHUTDOWN **

TO REMOVE Reactor Building ( A or 1) (Yes or No) (Yes or No)

RHR System (Continued)

RHRH-239 (1) 2'NR 9- 4'WRH, El. 160' A No No RHRH-240 (2) 6'NR 5-25'WRL, E'l. 147' A lb No RHRil-242 (1) 3'SR 4- 4'WRU, El. 150' A No Ib RHRH-244 (2) 10'SRll- 4'ERF, El. 121' A tb No RHRH-245 (1) 10'SR11- 3'ERF, El. 121' A , No No RHRH-246 (1) 10'SRll- 3'ERF, El. 122' A No No RHRH-249 (1) ll'SRll-10'ERF, El. 118' A No No F RHRH-250 (2) 10'NR 3- 4'ERF, El. 121' A tb tb

[ RHPH-251 (1)

RH'lH-252 (1) 10'UR 3- 3'ERF, El. 119' 10'NR 3- 3'ERF, El. 121' A

A No No No No E RHRH-254 (1) ll'NR 3-10'ERF,'El. 118' A No No RHRH-279 (2) 3'SR 5- 3'WRL, El. 116' A No No RHRH-282 (1) 1/2'SR4- 7' ERG, El. 121' A No No RHRH-286 (2) 3'SR 2-17'WRL, El. 116' A No No RHRH-288 (2) 3'NR 9- 3'WRL, El. 116' A No it RHRH-292 (1) 4'SR 2- 6'ERH, El. 124' A No No RHRH-299 (1) 4'SR13- 6'ERH, El. 122' A No ib RHRH-305 (1) 5'NR 3- 4'ERH, El. 123' A No No RHRH-306 (2) 3'NR 3- 7'ERH, El. 121' A tb No RHRH-307 (1) 10'SR 5-17'ERH, El. 132' A No No RHRH-309 (1) 9'SRll-18'ERH, El. 115' A No ib

Snuobers may be added to safety related systems without prior License Amendment to Table 3.6-la provided that a revision to Table 3.6-la is included with the next License' Amendment request.

- Modifications to this column due to changes in high radiation areas may be made without prior License Amendment provided that the revision to Table 3.6-la is included with the next License Amendment request. ,

5 '

N

=:

TABLE 3.6 _a E

y SAFETY RELATED HYDRAULIC SNUBBERS

HIGH RADIATION SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR ZONE :ESPECIALLY DIFFICULT NO. (Qty.) ON, LOCATION AND ELEVATION IllACCESSIBLE DlRING SHUTDOWN ** TO REMOVE Reactor Building (A or I) (Yes or No) (Yes or No)

RHR System (Continued)

RHRH-310 (1) 9'SRll-18'ERH, El. 124' A No No RHRH-312 (1) 6'NRll-18'WRL, El. 124' A No No RHRH-313 (1) 6'NRll-18'WRL, El. 125' A No No RHRH-316 (1) 10'NRll- 4'WRL, El. 123' A No No RHRH-319 (2) 9'ta 9-17'ERH, E1. 136' A No tb RiiRH-320 (1) 4'NR11-17'ERH, El. 90' A No . No F RHRH-321 (1) 3'NRll-15'ERH, El. 91' A No No

RHRH-322 (2) 3'SRll-12'ERH, 89' A No El. No

' RHRH-323 (2) 5'SRll- 9'ERH, 89' A No El. No 5 RHRH-324 (1) 5 ' NR 9- 5 'WRL , - El. 91' A No No t

RHRH-325 (1) 2'SR 9- 9'WRL, El. 90' A No ib RHRH-332 (1) 2'SR 6- 2'WRH, El. 190' A No No RiiRH-344 (1) 1/2'NR10-l'WRH, El. 122' A No No RHRH-348 (2) 3'NR13-17'WRL, El. 117' A No No RHRH-399 (1) 6'NR 5- 6'ERH, El. 148' A No No RHRH-400 (1) 6'NR 5- l'ERH, El. 148' A No No

.

Snubbers may be added to safety related systems without prior License Amendment to Table 3.6-la provided that a revision to Table 3.6-la is included with the next License Amendment request.

- Modifications to this column due to changes in high radiation areas may be made without prior License Amendment provided that the revision to Table 3.6-la is included with the next License Amendment request. 4 C

I TABLE 3.6-lb

? .

g . SAFETY RELATED MECHANICAL SNUBBERS

I HIGH RADIATION Q SNUBBER SYSTEM SNUBBER INSTALLE0 ACCESSIBLE OR ZONE ESPECIALLY DIFFICL T y NO. (Oty.) ON, LOCATION AND ELEVATION INACCESSIBLE DURING SHUTDOWN ** TO REMOVE

_ Heactor Building ( A or I) (Yes or No) -

(Yes or No)

Nuclear Boiler System B21-DFDH-16 (1) 6'SR7-27'WRF,El.131'-5" I No Yes B21-DFDH-33 (1) 2'NR7- 2'ERE,El.132'-2" I No Yes B21-DFDH-43 (1) 2'-10"SR7-3' ERA,El.134'-5" I No Yes 821-DFDH-43 (1) 4'-2"SR7-3' ERA,El.134'-5" I No Yes B21-FDH-20 (1) Az.2620,El.149'-9" I No Yes 821-X28-lF19-H001 (1) Az.1800,El.192'-0" I No Yes B21-X28-1F19-H001A (1) Az.1800,El.193'-0" I No Yes F B21-X29-lF17-H002 (1) Az. 100,El.173'-0" I No -

Yes B21-X29-1F17-H003A (2) Az. 00,El.188'-0" I No Yes i

B21-X29-1F17-H0038 (2) Az. 00,El.182'-0" I No Yes g B21-X29-lF17-H003C (2) Az. 00,El.177'-0" I No Yes e B21-X28-lF19-H004A (2) Az.1800,El.177-0" I No Yes B21-X28-lF19-H004B (2) Az.1800,El.182'-0" I No Yes B21-X28-lF19-H004C (2) Az.1800,El.188'-0" I No Yes 821-X29-1F24-H002 (1) Az. 00,El.192'-0" I No Y.es B21-X29-1F24-H003 (1) Az. 00,El.192'-0" I No Yes B21-X29-1F18-H004 (1) Az. 40,El.173'-0" I No Yes B21-FS-H005 (1) Az. 00,El.197'-0" I No Yes B21-F22-H001 (1) Az. 00,El.138'-0" I No Yes 821-F23-H001 (1) Az. 00,El.137'-0" I No Yes T nubbers S may be added to safety related systems without prior License Amendment to Table 3.6-lb provided that a revision to Table 3.6-lb is included with the next License Amendment request.

- Modifications to this column due to changes in high radiation areas may be made without prior License Amendment provided that the revision to Table 3.6-lb is included with the next License Amendment request.

t h TABLE 3.6-lb a ~

, SAFETY RELATED MECHANICAL SNUBBERS

k H

HIGH RADIATION SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR ZONE ESPECIALLY DIFFICULT

~

NO. (Qty.) ON, LOCATION AND ELEVATION INACCESSIBLE DURING SHUTDOWN ** TO REMOVE Reactor Building ( A or I) (Yes or No) (Yes or No)

Nuclear Boiler System Continued)

B21-F24-H001 (1) Az. 00,El.137'-0" I No Yes

B21-F25-H001 (1) Az. 00,El.137.'-0" I No Yes B21-F38-H005 (1) 3'-6"NR7-8' ERA,El.133'-0" I No Yes l B21-F38-H005 (1) 8' ERA-6'-5"SR7,El.133'-0" I No Yes B21-F16-H008 (1) Az. 400,El.190'-0" I No Yes B21-F5-H020 (1) Az. 450,El.201'-0" I No Yes a B21-F5-H021 (1) Az. 450,El.201'-0" I No , Yes Recirc System k B31-X31-lF5-H001 (2) Az. 900,El.124'-0" I No Yes

B31-X33-lFS-H001 (1) Az. 900,El.132'-0" I No Yes B31-X32-lF6-H001 (1) Az.2900,El.123'-0" I No Yes

] B31-X32-lF6-H002 (1) Az.2950,El.121'-0" I No Yes j B31-X32-lF7-H001 (1) Az.3400,El.ll6'-O" I No Yes i B31-X34-lF16-H001 (1) Az.1350,El.124'-O" I No Yes i B31-X28-lF16-H811 (1) Az.2170,El.172'-O" I No Yes

! B31-X28-lF16-H812 (1) Az.2170,El.172'-0" I No Yes 831-F3-H800 (1) Az.3150,El.ll5'-0" I No Yes

) 831-F14-H800 (1) Az.1800,El.ll5'-0" I No Yes l

Snubbers may be added to safety related systems without prior License Amendment to Table 3.6-lb provided that a revision to Table 3.6-lb is included with the next License Amendment request.

- Modifications to this column due to changes in high radiation areas may be made without prior q License Amendment provided that the revision to Table 3.6-lb is included with the next License Amendment request.

g TABLE 3.6-lb a -

~

O SAFETY RELATED MECHANICAL SNUBBERS

i 5 HIGH RADIATION

$ SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR ZONE ESPECIALLY DIFFICULT NO. (Qty.) ON, LOCATION AND ELEVATION INACCESSIBLE DURING SHUTDOWN ** . TO REMOVE Reactor Building (A or I) (Yes or No) (Yes or No)

RHR System Ell-F20-H001 (1) 22'SR7-23'ERH,El.139'-O" I No Yes Ell-F208-H001 (1) Az.2700,El.138'-G" I No Yes Ell-RHR-405 (1) Az.1550,El.211'-2" I No Yes Core Spray System y E21-F1-H001 (2) Az. 800,El.175'-0" I No . Yes e E21-F1-H002 (2) Az.2700,El.174'-0" I No Yes I

g RCIC System m .

E51-X408-lF4-H001 (1) Az.3300,El.156'-0" I No Yes RWCU System G31-SM-5 (1) Az.1600,El.168'-ll" I No Yes G31-SM-6 (1) Az.1600,El.168'-ll" I No Yes

Snubbers may be added to safety related systems without prior License Amendment to Table 3.6-lb provided that a revision to Table 3.6-lb is included with the next License Amendment request.

- Modifications to this column due to changes in high radiation areas may be made without prior License Amendment provided that the revision to Table 3.6-lb is included with the next License Amendment request.

l TABLE 3.6-lb ,

o f

~

SAFETY RELATED MECHANICAL SNUBBERS

E HIGH RADIATION O SNUBBER SYSTEM SNUBBER INSTALL.ED ACCESSIBLE OR ZONE ESPECIALLY DIFFICULT

- NO. (Qty.) ON, LOCATION AND ELEVATION INACCESSIBLE DURING SHUTDOWN ** . TO REMOVE f

Reactor Building (A or I) (Yes or No) (Yes or No) 1 Equipment & Floor Drain System j T45-F17-H001 (1) Az. 900,El.ll7'-0" I No Yes 1

i RHR System _

i Ell-F8-FOOL (1) 22'SR7-23'ERH,El.123'-0" A No No Ell-F93-H001 (1) 17'NR7-24'WRL,El.124'-0" A No No

) {'

Ell-F93-H002 (1) 17'NR7-24'WRL,El.122'-0" A No . No Primary Containment Purge & Inerting System T48-F30-H001 (1) Az. 450,El.120'-0" A No No T48-F30-H002 (1) Az. 450,El.120'-0" A No No i

Snubbers may be added to safety related systems without prior License Amendment to Table 3.6-lb provided that a revision to Table 3.6-lb is included with the next License Amendment request.

l ** Modifications to this column due to changes in high radiation areas may be made without prior 4 License Amendment provided that the revision to Table 3.6-lb is included with the next License j Amendment request.

j ,

4 I

f

BASES 3/4.6.L SNUBBERS All snubbers are required 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 nonsafety-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 cons' tant 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 inservice 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 snubbe.' 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 systen.

To provide assurance of snubber functional reliability, a representative sample of the installed snubbers will be functionally tested during plant shutdowns at 18 month intervals. Observed failures of sample snubbers shall require functional testing of additional units.

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

HATCH-UNIT 1 3.6-31

BASES 3/4.0.L SNUBBERS (Continued)

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 The requirement to monitor the snubber service life is area,etc...).

4 included to ensure that the snubbers periodically undergo a performance evaluation in view of their age and operating conditions. These records twill 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.

e I

9 F

HATCH-UNIT 1 3.6-32

ADMINISTRATIVE CONTROL RECORD RETENTION (Continued)

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 unit components identified in Table 5.7.1-1. -

f. Records of reactor tests and experiments.

i g. Records of training and qualification for current members for the

! unit staff.

h. Records of in-service inspections performed pursuant to these Technical Spc:4 .'i ca tio ns .

i. Records of Quality Assurance activities required by the QA Manual.

J. Records of reviews performed for changes made to procedures or ..

equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.

k. Records of meetings of the PRB and SRB.

l 1. Records of the service lives of all hydraulic and mechanical snubbers l

listed on Tables 3.6-la and 3.6-lb including the date at which the service life commences and associated installation and maintenance

! records. g l 6.11 RADIATION PROTECTION PROGRAM l

Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.

6.12 HIGH RADIATION AREA 6.12.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.203(c)(2) of 10 CFR20, each high radiation area in which the intensity of radiation is greater than 100 mrem /hr but less than 1000 i mrem /hr shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit *. Any individual or group of individuals permitted

Health Physics personnel, or personnel escorted by Health Physics person-nel in accordance with approved emergency procedures, shall be exempt from the RWP issuance requirement during the performance of their assigned radia-tion. protection duties, provided they comply with approved radiation pro-tection procedures for entry into high radiation areas.

HATCH-UNIT 1 6-20 l

- - _ _ _ _ __ __ . , - __-._ _ _,_ . _ _ _ . . ~ _ _ .._._

ENCIDSURE 2 NRC DOCKET 50-366 OPERATING LICENSE NPF-5 EDWIN I. HA'ICH NUCIEAR PIANT UNIT 2 REQUEST 'IO AMEND TECHNICAL' SPECIFICATIONS

'1he proposed change to Technical Specifications (Appendix A to Operating License NPF-5) would be incorporated as follows:

Renove Page Insert Page VIII VIII XIII XIII 3/4 7-11 through 3/4 7-15 3/4 7-11 through 3/4 7-15 3/4 7 3/4 7-16 3/4 7-16a through 3/4 7-16b 3/4.7-17 3/4 7-17 3/4 7-17a through 3/4 7-17i 3/4 7-18 3/4 7-18 3/4 7-18a B3/4 7-2 B3/4 7-2 B3/4 7-3 B3/4 7-3 6-18 6-18 1

3 1

INDEX i

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS i

SECTION PAGE l 3/4.7 PLANT SYSTEMS

, 3/4.7.1 SERVICE WATER SYSTEMS -

l 1

Residual Heat Removal Service Water System. . . . . . . . . . . . . . 3/4 7-1 ,

Serv ice Wa ter Sys tems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/ 4 7-3 3/4.7.2 MAIN CONTROL ROOM ENVIRONMENTAL CONTROL SYSTEM.......... 3/4 7-6 3/4.7.3 REACTOR CORE ISOLATION COOLING SYSTEM................... 3/4 7-9 3/4.7.4 SNUBBERS................................................ 3/4 7-11 3/4.7.5 SEALED SOURCE C0NTAMINATICN............................. 3/4 7-19

. 3/4.7.6 FIRE SUPPRESSION SYSTEMS i

! Fi re Suppres s ion Wa ter Sys tem. . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 7-21 S p ri n kl e r Sys tems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 7- 25 Low Pressure C02 Systems................................ 3/4 7-27 Fire Hose Stations...................................... 3/4 7-28 3/4.7.7 PENETRATION FIRE BARRIERS............................... 3/4 7-30 i- 3/4.7.8 SETTLEMENT OF CLASS I STRUCTURES........................ 3/4 7-31 l 3/4.8 ELECTP,ICAL POWER SYSTEMS

I 3/4.8.1 A.C. SOURCES i

f A . C . Sou rces-Opera ti ng . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4_8-1 ,

A. C. Sou rces -Shu tdown. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 8-9 i

3/4.8.2 C.' SITE POWER DISTRIBUTION SYSTEMS .

. A. C. Di s tribu tion - 0pera ti ng. . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 8-10 i

A.C. Distribution - Shutdown............................ 3/4 8-12 4

D.C. Dis tribution - Operating. . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 8-13 D.C. Distribution - Shutdown. . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 8-16

. A.C. Circui ts Ins ide Primary Containment. . . . . . . . . . . . . . . . 3/4 8-17 Primary Containment Penetration Conductor

, Overcurrent Protective Devices.......................... 3/4 8-18

)

HATCH-UNIT 2 VIII

INDEX BASES SECTION PAGE PLANT SYSTEMS (Continued) 3/4.7.3 REACTOR CORE ISOLATION COOLING SYSTEM............... B 3/4 7-1 3/4.7.4 SNUBBERS............................................ B 3/4 7-2 l 3/4.7.5 SEALED SOURCE CONTAMINATION......................... B 3/4 7-3

~

. 3/4.7.6 FIRE SUPPRESSION SYSTEMS............................ B 3/4 7-3 3/4.7.7 PENETRATION FIRE BARRIERS........................... B 3/4 7-4 3/4.7.8 SETTLEMENT OF CLASS I STRUCTURES. . . . . . . . . . . . . . . . . . . . B 3/4 7-4 3/4.8 ELECTRICAL POWER SYSTEMS................................... B 3/4 8-1 3/4.9 REFUELING OPERATIONS 3/4.9.1 REACTOR MODE SWITCH................................. B 3/4 9-1 3/4.9.2 INSTRUMENTATION..................................... B 3/4 9-1 .

3/4.9.3 CONTROL R0D P0SITION................................ B 3/4 9-1 3/4.9.4 DECAY TIME.......................................... B 3/4 9-1

3/4.9.5 SECONDARY CONTAINMENT.................. ............ B 3/4 9-1 3/4.9.6 COMMUNICATI0NS...................................... B 3/4 9-2 l 3/4.9.7 CRANE AND H0IST OPERABILITY......................... B 3/4 9-2

! 3/4.9.8 CRANE TRAVEL-SPENT FUEL STORAGE P00L................ B 3/4 9-2 3/4.9.9 and 3/4.9.10 WATER LEVEL - REACTOR VESSEL AND WATER LEVEL - SPENT FUEL STORAGE P00L........... B 3/4 9-2 3/4.9.11 CONTROL R0D REM 0 VAL................................. B 3/4 9-2 3/4.9.12 REACTOR COOLANT CIRCULATION. . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 9-3 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 PRIMARY CONTAINMENT INTEGRITY....................... B 3/4 10-1

, 3/4.10.2 R00 SEQUENCE CONTROL SYSTEM......................... B 3/4 10-1 l 3/4.10.3 SHUTDOWN MARGIN DEMONSTRATIONS...................... B 3/4 10-1 j 3/4.10.4 RECIRCULATION L00PS................................. B 3/4 10-1 HATCH - UNIT 2 XIII L

PLANT SYSTEMS 3/4.7.4 SNUBBERS -

LIMITING CONDITION FOR OPERATION 3.7.4 All snubbers listed in Tables 3.7.4-la and 3.7.4-lb shall be OPERABLE.

APPLICABILITY: Conditions 1, 2, and 3. :

ACTION:

With one or more snubbers inoperable, within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months replace or restore the inoperable snubber (s) to OPERABLE status and perform an engineering evaluation per Specification 4.7.4.c on the supported component or declare the supported system inoperable and follow the appropriate ACTION statement for that system.

.y SURVEILLANCE REQUIREMENTS

~

4.7.4 Each snubt'er shall be demonstrated OPERABLE by performance of the following inservice inspection program and the requirements of Specification 4.0.5.

a. Visual Insoections All safety-related snubbers listed in Tables 3.7.4-la and 3.7.4-lb shall be visually examined to verify snubber operability. Visual inspections shall be performed in accordance with the following schedule:

No. Inoperable Snubbers Subsequent Visual I per Insoection Period Insoection Period *#

0 18 months + 25%

1 12 months 7 25%

2 6 months T 25%

3, 4 124 days i25% ,

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 reactor nperation.

Each group may be inspected independently in accordance with the above schedule.

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

The-provisions of Specification 4.0.2 are not applicable.

HATCH-UNIT 2 3/4 7-11 l

PLANT SYSTEMS SURVEILIRCE REQUIREMENTS (Continued)

b. Visual Inspection Acceptance Criteria Visual inspections shall verify (1) that there are no visible indications of damage or impaired OPERABILITY, (2) attachments to the foundation or supporting structure are secure, and (3) for mechanical snubbers where snubber movement can be manually induced, the snubbers shall be inspected as follows: (a)

Safety-related systems associated with the snubbers listed in Table 3.7.4-lb shall be inspected to determine if there has been a severe dynamic event. (b) In the event of a severe dynamic event, snubbers in that system which experienced the event shall be inspected during the refueling outage to assure the snubbers have freedom of movement and are not frozen up.

'Ihe inspection shall consist of v?rifying freedom of motion using one of the following: (i) Manually induced snubber movement; (ii) stroking the mechanical snubber through its full range of travel. If one or more mechanical snubbers are found to be frozen up during this inspection, those snubbers shall be replaced (or overhauled). Re-inspection shall subsequently be performed according to the schedule of 4.7.4.a, but the scope of the examination shall be limited to the safety-related systems associated with the snubbers listed in Table 3.7.4-lb. 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 4.7.4.d or 4.7.4.e, as applicable.

c. Functional Tests At least once per 18 months during shutdown, a representative sample of 10% of the total of each type (hydraulic or mechanical) safety-related 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 4.7.4.d or 4.7.4.e, an additional sample of at least 1/2 the size of the initial lot of that type of snubber shall be functionally tested.

HA'IGI - UNIT 2 3.4 7-12

PLANT SYSTEMS SURVEILIRCE REQUIRENENTS (Continued)

Functional testing shall continue until no additional inoperable snubbers of a particular type are found within a sample or until all snubbers listed in Table 3.7.4-la or 3.7.4-lb, as applicable, 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.

The representative sample shall be selected randomly from the total population identified in Tables 3.7.4-la and 3.7.4-lb.

Snubbers identified in Tables 3.7.4-la and 3.7.4-lb as "Especially Difficult to Remove" or in "High Radiation Zones During Shutdown" shall also be included in the representative sample *. Tables 3.7.4-la and 3.7.4-lb may be used jointly or separately as the basis for the sampling plan.

In addition to the regular sample, snubbers placed in the same location as snubbers which failed the previous functional test shall be retested during the next test period. Test results of these snubbers shall not be included in the sampling plan.

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 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 critiera.

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.

Permanent or other exemptions from functional testing for individual snubbers in those categories may be granted by the Cmmission 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 fabricatio,n or at a subsequent date.

HAICH - UNIT 2 3/4 7-13 w

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

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

1. The snubber operates freely over the stroke in both tension and compression. -

2. The force that initiates free movement of the snubber rod in either tension or compression is less than the specified maximum drag force. Specified maximum drag force is nominally five (5) pounds or one percent (1%) of rated snubber losd, whichever is greater.

f. Unit Outage In" accessible Snubber. Inspection In the event that all inaccessible snubbers are inspected, functionally tested, and repaired as necessary during a unit outage, and that it is thus demonstrated that all inaccessible snubbers are operable, the schedule in Specification 4.7.4.a may be re-entered on a 6-month inspection interval for, the inaccessible snubbers.

g. Snubber Service Life Monitoring A record of the service life of each snubber, the date at which the designated service life commences and the installatim and maintenance records on which the designated service life is based . shall be maintained as required by Specification 6.10.2.1.

HATCH - UNIT 2 3/4 7-14

PLANP SYSTEMS SURVEILIRCE REQUIREMENTS (Continued)

Concurrent with the inservice visual inspection performed durirx3 the first refueling outage following issuance of this amendment and at least once per 18 months thereafter, the installation and maintenance records for each snubber listed in Tables 3.7.4-la and 3.7.4-lb shall be reviewed to verify that the indicated service life has not been exceeded or will not be exceeded by more than 10% prior to the next scheduled snubber service life review. If the indicated service life wil' be exceeded by more than 10% 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. The results of the reevaluation may be used to justify a change to the service life of the snubber. This reevaluation, replacement or

reconditioning shall be indicated in the reccrds.

HA101 - UNIT 2 3/4 7-15

TABLE 3.7.4-la %

5 ~

N SAFETY RELATED HYDRAULIC SNUBBERS * .

?

E HIGH RADIATION Z SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR 70NE . ESPECIALLY DIFFICULT m l'0. (Qty. ) ON. LOCATION AND ELEVATI0fl INACCESSIBLE DURING SHUTDOWN ** TO REMOVE Reactor Building (A or I) (Yes or flo) (Yes or No) 2 Ell-RHR SYSTEM R86 (1) 8' NRl9 - l' ERJ, El. 212' A flo No R88 (1) 10' ilR17 - 3' WRJ, El .119' A No No R90 (1) R15 - 3' ERH, El .119' A No No R93 (2) 8 ' SR14 - 11 ' ERF, El .118 ' A No flo R94 (1) 8' SR14 - 10' ERF, El .118' A '-

No No R98 (2) 10' SR19 - l' ERJ, El. 121' A flo No R100 (1) 10' SR21 - 3' WRJ, El .119' A No . No R101 (1) 12' SR21 - S' WRJ, El .119' A No No R R102 (1) R23 - 3 ' ERH , El . 119 ' A No No o R128 (1) 6' NR23 - 16' ERF, El .123' A No No y R129 (2) 18' SR21 - 16' ERF, El .123' A flo No g R146 (2) 5' SR21 - 8' WRL, El. 120' A No Yes R221 (1) 18' NR19 - 12' WRL, El. 90' A No No 18' SR19 - 12' WRL, El .

R222 (1) 90' A No flo R223 (1) 18' SR14 - 23' WRL, El. 90' A No No R227 (1) 18' NR24 - 23' WRL, El . 90' A No No R231 (2) 3 ' SR19 - 9' WRL, El .102' A No No R238 (2) 12' SR15 - 3' WRL, El .107 ' A No Yes R241 (2) 3' NR23 - 9' WRL, El .102 ' A No No R245 (2) 12 ' ilR23 - 3' WRL, El .107' A !!o Yes

Snubbers may be added to safety related systems without prior License Amendment to Table 3.7.4-la provided that a revision to Table 3.7.4-la is included with the next License Amendment request.

- Modification's to this column due to changes in high radiation areas may be made without prior License Amendment provided that the revision to Table 3.7.4-la is included with the next License Amendment request.

i

! TABLE 3.7.4-la j h SAFETY RELATED HYDRAULIC SNUBBERS

i 9 l l_ HIGH RADIATION ,

= SilVBBER SYSTEM SNUBBER IflSTALLED ACCESSIBLE OR 70f!E ESPECIALLY DIFFICULT ;

H f!0. (Qty.) Oil, LOCATION Afl0 ELEVATION If! ACCESSIBLE DURING SHUTDOWil** TO REMOVE N Reactor Building (A or I) (Yes or fio) (Yes or flo) l i

2 Ell-RHR SYSTEM (Continued) i R250 (1) 11 ' SR14 - 15' WRL, El .119' A No No l

R251 (2) 11 ' SR14 - 15' WRL, El .120' A f!o flo

R252 (1) 15' SR14 - 15' WRL, El .112' A No flo R253 (1) 15' SRl4 - 15' WRL, El .120' A No !!o i R254 (1) 17 ' SR14 - 17' WRL, El .112' A f!o No

! R256 (1) 17 ' SR14 - 17 ' WRL, El .112 ' A No Yes

{ R258 (1) 22' SR14 - 13' WRL, El . 99' A V No No l R264 (1) 21 ' SR14 - 9' WRL, El .104 ' A No

Yes

! R267 (2) 15' SR14 - 3' WRL, El .102' A f!o No w R268 (1) 11 ' NR24 - 15' WRL, El .119' A No No i S R269 (2) 11 ' flR24 - 15' WRL, El .120' A flo No I u R270 (1) 15' NR24 - 15' WRL, .El .112' A flo No 4

1 R271 (1) 15' NR24 - 15' WRL, El .120' A flo No

E R272 (1) 17 ' NR24 - 17 ' WRL, El .112' A No No

! R274 (1) 17 ' flR24 - 17 ' WRL, El . 112' A No No l R276 (1) 22' NR24 - 13' WRL, El. 99' A No No j R282 (1) 21' NR24 - 9' WRL, El .104 ' A No Yes i R2.85 (2) 15' NR24 - 3' WRL, El .102' A No No 1 R315 (2) 10' NR19 - 6' ERJ, El. 123' A No No .

j R374 (2) 23' SR14 - 15' WRL, El .106' A No Yes l .

i i -

I

Snubbers may be added to safety related systems without prior License Amendment to Table 3.7.4-la '

provided that a revision to Table 3.7.4-la is included with the next License Amendment request.

- Modification's to this column due to changes in high radiation areas may be made without prior

) License Amendment provided that the revision to Table 3.7.4-la is included with the next License L Amendment request.

i ,

i i

, .-_ , m _

TABLE 3.7.4-la SAFETY RELATED HYDRAULIC SilUBBERS*

x -

53 HIGH PADIATION O SilVBBER SYSTEM SilVBBER INSTALLED ACCESSIBLE OR 70flE ESPECIALLY DIFFICULT

[ 110. (Qty.) Off, LOCATI0fl AND ELEVATI0fl IflACCESSIBLE

~

CURING SHUTD0Wil** TO REMOVE Reactor Building (A or I) (Yes or flo) (Yes or flo) 2 Ell-RHR SYSTEM (Continued)

R375 (2) 23 ' SRl 4 - 12 ' WRL , El . 108 ' A flo No R376 (1) 23' SR14 - 12' WRL, El .109' A No flo R377 (2) 23' NR24 - 15' WRL, ET.106' A fio Yes R378 (2) 23 ' flR24 - 12' WRL, El .108' A flo flo R379 (1) 23' NR24 - 12' WRL, El .109' A f!o rio 2 Ell-RHR SERVICE WATER SYSTEM t; R 15 (2) 7 ' SR14 - 11' ERH, El .115' A No flo o R 23 (2) 7 ' NR24 - 11 ' ERH, El .115' A No No Y

g 2E21-CORE SPRAY SYSTEM c-R 35 (1) 8' SR14 - 6' WRL, El. 95' A f!o No R 40 (1) 7' SR14 - 31' WRL, El. 95' A flo flo R 53 (2) 10' SRl4 - 6' WRL, El .106' A fio fio R 72 (2) 10' flR24 - 6' WRL, El. 102' A flo flo R 80 (1) 8' flP,24 - 6' WRL, E1. 95' A fio flo R 87 (1) 7' flR24 - 6' WRL, El. 90' A No flo R107 (2) 39' flR24 - 15' WRL, El. 123' A No fio

Snubbers may be added to safety related systems without prior License Amendment to Table 3.7.4-la provided that a revision to Table 3.7.4-la is included with the next License Amendment request.

- Modifications to this column due to changes in high radiation areas may be m'ade without prior License Amendment provided that the revision to Table 3.7.4-la is included with the next License Amendment request.

1 TABLE 3.7.4-la h SAFETY RELATED HYDRAULIC SNUBBERS *,

, 9 HIGH RADIATION

a: .

5 SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR ZONE ESPECIALLY DIFFICULT 1 -4 NO. (Qty.) ON, LOCATION AND ELEVATION INACCESSIBLE DURING SHUTDOWN ** TO REMOVE

]

N Reactor Building (A or I) (Yes or No) (Yes or No) 4 2T46-SGTS SYSTEM i l j R 65 (2) 6' NR24 - 9' WRB, El. 198' A No Yes j R 66 (1) 2 ' NR24 - 9' WRB, El .186' A No No ,

i R 67 (1) 2' NR24 - 9' WRB, El.,180' A No Yes R 68 (2) 6' NR24 - 9' ERA, El. 198' A No Yes R 69 (1) 2' NR24 - 9' ERB, El. 186' A No No R 70 (2) 2' NR24 - 9' ERA, El. 179' A No Yes u

1 3: 2B31-REACTOR RECIRCULATION SYSTEM

%J l L SSA1 (1) Az 315 0, El .117' I No No 8' SSA2 (1) Az 3280, El. 125' I No Yes

! SSA3 (1) Az 3020, El. 125' .

I No Yes 3

SSA4 (1) Az 3280, El . 131 ' I !!o Yes i

SSAS (1) Az 3010, El . 131 ' I No No ;

SSA6 (1) Az 3150, El . 137 ' I No -

Yes

, SSA7 (1) Az 0180, El . 124 ' I No Yes

SSA8 (1) Az 342 , El .123' I No Yes l SSAl2 (1) Az 2550, El. 129' I No No l l SSA13 (1) Az 2850, El. 129' I No No l SSA14 (1) Az 2700, El . 121 ' I No No i SSA15 (1) Az 3230, El. 144' I t!o Yes i SSA16'(1) Az 2170, El. 144' I No Yes i

i j

Snubbers may be added to safety related systems without prior License Amendment to Table 3.7.4-la provided that a revision to Table 3.7.4-la is included with the next License Amendment request.

i

- Modifications to this column due to changes in high radiation areas may be made without prior

! License Amendment provided that the revision to Table 3.7.4-la is included with the next License Amendment request.

TABLE 3.7.4-la .

~

[ SAFETY RELATED HYDRAULIC SNUBBERS

x *

;. HIGH RADIATION

= SilVBBER SYSTEM StiUBBER INSTALLED ACCESSIBLE OR ZONE ESPECIALLY DIFFICULT i H NO. (Qty.) ON, LOCATI0fl AND ELEVATION IflACCESSIBLE DURING SHUTOOWN** TO REMOVE I

N Reactor Building -(A or I) (Yes or flo) (Yes or flo)

I 2831-REACTOR RECIRCULATION SYSTEM (Continued) 1 SSA17 (1) Az 2700, El .125' I fio Yes j SSA19 (1) Az 270 0 , El .138' I flo Yes SSA20 (1) Az 2700, El. 138' -

I f!o Yes '

i SSA21 (1) Az 00, El 140'. I flo Yes j SSA22 (1) Az 00, El . 140' I No Yes

! SSBl (1) Az 1350, El . 117 ' I .. No fio Az 1480, El. 125' (1)

SSB2 I No Yes l SSB3 (1) Az 1220, El. 125' I No -

Yes SSB4 (1) Az 1480, El . 131 ' I feo Yes

& SSB5 (1) Az 1220, El . 131 ' I No No I SSB6 (1 ) Az 1350, El . 137 ' I fio Yes i 7' SSB7 (1 ) Az 1980 , El .124 ' I f!o Yes 5

" SSB8 (1 ) Az 1620, El. 123' I f!o Yes

} SSB12 (1) Az 0750, El. 129' I No No i

SSB13 (1) Az 1050, El. 129' I No No l SSB14 (1) Az 0900, El . 121 ' I No flo l SSB15 (1) Az 1430, El. 144' I flo Yes l SSB16 (1) Az 037 0, El. 144' I No Yes SSB17 (1) Az 900, El. 126' I No Yes SSB19 (1) Az 900, El. 138' I No Yes

! SSB20,(1) Az 900, El . 138 ' I No Yes i

SSB21 (1) Az 180 , El .140' I No Yes SSB22 (1) Az 1800, El. 140' I No , Yes l

a

Snubbers may be added to safety related systems without prior License Amendment to Table 3.7.4-la i

i provided that a revision to Table 3.7.4-la is included with the next License Amendment request.

- Modifications to this column.,due to changes in high radiation areas may be made without prior i License Amendment provided that the revision to Table 3.7.4-la is included with the next License h Amendment request.

4

)

TABLE 3.7.4-lb .

g SAFETY RELATED MECHANICAL SNUBBERS

f j- HICH RADIATION p SNUBSER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR ZONE ESPECIALLY DIFFICULT y NO. (Qty.) ON, LOCATION AND ELEVATION INACCESSIBLE OURING SHUTDOWN ** '

TO REMOVE Heactor Building (A or I) (Yes or No) (Yes or No) 2B21-Nuclear Boiler System MS-R34 (1) Az. 1100 El. 155' I No Yes MS-R35 (1) Az. 1450 El. 150' ' I flo Yes MS-R36 (1) Az. 1450 El. 150' I No Yes MS-R37 (2) Az. 1450 El. 150' I No Yes MS-R38 (2) Az. 720 El. 167' I s No Yes MS-R39 (2) Az. 950 El. 150' I No Yes MS-R41 (1) Az. 1000 El. 150' I No Yes v ItS-R42 (1) Az. 1400 El. 150' I No Yes 3 MS-R43 (1) Az 1300 El. 150' I No Yes y MS-R44 (2) Az. 1400 El. 150' I No Yes

.L MS-RAS (1) Az. 2500 El. 156 I No Yes MS-R46 (1) Az. 2500 El. 156' I No Yes MS-R47 (1) Az. 2200 El. 150' I No Yes-MS-R48 (1) Az. 2200 El. 150' I No Yes.

MS-R49 (2) Az. 2830 El. 167' I No Yes MS-RSO (2) Az. 2700 El. 150' I No Yes MS-RS2 (1) Az. 2650 El. 150' I No Yes MS-R33 (2) Az. 2350 El. 150' I No Yes MS-RS4 (1) Az. 2350 El. 150' I No Yes MS-RSS (1) Az. 2350 El. 150' I No Yes

Snubaers may be added to safety related systems without prior License Amendment to Table 3.7.4-lb provided that a revision to Table 3.7.4-lb is included with the next License Amendment request.

- Modifications to this column due to changes in high radiation areas may be made without prior License Amendment provided that the revision to Table 3.7.4-lb is included with the next License Amendment request. ,

s i

TABLE 3.7.4-lb i i

5

g SAFETY RELATED MECHANICAL SNUBBERS

j Y l @ HIGH RADIATION Q SNUSSER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR ZONE ESPECIPLLY DIFFICULT m NO. (Oty.) ON, LOCATION AND ELEVATION INACCESSIBLE DURING SHUTDOWN ** TO REMOVE j Reactor Buildino (A or I) (Yes or tJo) (Yes or tJo) 2821-Nuclear Boiler System (Continued)

! MSRV-R36 (1) Az. 2300 El. 137' I No Yes Az. 2300 El. 133' '

} MSRV-R37 (1) I No Yes l MSRV-R38 (1) Az. 2300 El. 133' I No Yes Az. 2300 El. 125' MSRV-R40 (1) I No Yes

MSRV-R41 (1) Az. 2250 El 122' I ; No Yes MSRV-R45 (2) Az. 1650 El. 119' I No Yes

! MSRV-R46 (2) Az. 2500 El. 155' I No Yes I u MSRV-RSO (1) Az. 2700 El. 150' I No Yes l D MSRV-R52 (2) Az. 1050 El. 150' I No Yes a w MSRV-RS3 (1) Az. 1050 El. 149' I No Yes

! h MSRV-R54 (1) Az. 800 El. 137' I No Yes l

m MSRV-RS6 (1) Az. 700 El. 131' I No Yes i MSRV-R57 (1) Az. 700 El. 135' I No Yes l MSRV-R58 (1) Az. 700 El. 125' I No Yes.

{ MSRV-R59 (2) Az. 1250 El. 154' I No Yes 1 MSRV-R60 (2) Az. 1200 El. 152' I No Yes j MSRV-R62 (1) Az. 900 El. 131' I No Yes MSRV-R63 (1) Az. 900 El. 132' I No Yes

MSRV-R64 (1) Az. 900 El. 125' I No Yes

MSRV-R65 (1) Az. 1000 El. 120' I No Yes 4

Snubbers may be added to safety related systems without prior License Amendment to Table 3.7.4-lb provided that a revision to Table 3.7.4-lb is included with the next License , Amendment request.

l " Modifications to this column due to changes in high radiation areas may be made without prior l License Amendment provided that the revision to Table 3.7.4-lb is included with the next License Amendment request.

! a

TABLE 3.7.4-lb .

x -

3 SAFETY RELATED MECHANICAL SNUBBERS _*_

9 E: HIGH RADIATION if SNUaaER SYSTEM SNUBSER INSTALLED ACCESSIBLE OR ZONE ESPECIALLY DIFFICULT

. J0. (Oty.) ON, LOCATION AND ELEVATION INACCESSIBLE DURING SHUTDOWN ** '

TO REMOVE Heactor Building (A or I) (Yes or No) (Yes or No) 2B21-Nuclear Boiler System (Continued)

MSRV-R67 (2) Az. 2350 El. 146' '

I No Yes MSRV-R68 (1) Az. 2350 El. 146' I io Yes MSRV-R69 (1) Az. 2350 El. 141' I No Yes MSRV-R70 (1) Az. 2350 El. 137' I .. No Yes MSRV-R71 (1) Az. 2450 El. 133' I No Yes MSRV-R72 (1) Az. 2450 El. 133' I No Yes MSRV-R73 (1) Az. 2450 El. 130' I No Yes w MSRV-R75 (1) Az. 2550 El. 154' I No Yes 2: MSRV-R76 (1) Az. 2500 El. 146' I No Yes y MSRV-R77 (1) Az. 2500 El. 137' I t!o Yes 1 MSRV-R78 (1) Az. 2500 El. 136i I No Yes

?! MSRV-R79 (1) Az. 2500 El. 133' I No Yes MERV-RSO (1) Az. 2500 El. 132' I No Yes-MSRV-R82 (1) Az. 950 El. 148' I No Yes.

MSRV-R83 (2) Az. 950 El. 145' I No Yes MSRV-R84 (1) Az. 900 El. 137' I No Yes MSRV-R87 (1) Az. 650 El. 132' I t!o Yes MSRV-R88 (1) Az. 650 El. 127' I tJo Yes MSRV-R89 (1) Az. 650 El. 125' I No Yes MSRV-R90 (1) Az. 1150 El. 145' I No Yes

Snutoers may be added to saf ety related systems without prior License Amendment to Table 3.7.4-lb provided th. t a revision to Table 3.7.4-lb is included with the next License , Amendment -request.

- t'cdifications to this column due to changes in high radiation areas may be made without prior License Amendment provided that the revision to Table 3.7.4-lb is included with the next License Amendment request.

x TABLE 3.7.4-lb .

SAFETY RELATED MECHANICAL SNUBBERS

E5 HICH RA01ATION Z SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR ZONE ESPECIALLY DIFFICULT N NO. (Oty.) ON, LOCATION AND ELEVATION INACCESSIBLE DURING SHUTDOWN ** TO REMOVE Heactor Building (A or I) (Yes or No) (Yes or No) 2821-Nuclear Boiler System (Continued)

MSRV-R91 (1) Az. 1100 El. 137'. I tb Yes MSRV-R92 (1) Az. 1100 El. 132' I No Yes MSRV-R93 (1) Az. 1100 El. 125' I No Yes MSRV-R94 (1) Az. 950 El. 120' I -

No Yes MSRV-R96 (2) Az. 2850 El. 152' I No Yes MSRV-R97 (1) Az. 2850 El. 152' I No . Yes MSRV-R98 (1) Az. 2900 El. 150' I No Yes MSRV-R99 (2) Az. 3200 El. 150' I No Yes ti MSRV-R100 (1) Az. 3300 El. 146' I No Yes MSRV-R101 (1) Az. 3300 El. 140.' I No Yes 7 MSRV-R103 (1) Az. 3400 El. 129' I No Yes O

MSRV-R104 (2) Az. 3400 El. 126' I No Yes MSRV-R105 (1) Az. 750 El. 152' I No Yes MSRV-R106 (1) Az. 750 El. 152' I No Yes' MSRV-R107 (1) Az. 600 El. 150' I No Yes MSRV-R108 (2) Az. 300 El. 150' I No Yes MSRV-R109 (1) Az. 300 El. 150' I No Yes MSRV-R110 (1) Az. 250 El. 137' I No Yes MSRV-Rlll (1) Az. 220 El. 132' I No Yes MSRV-R113 (1) Az. 2700 El. 154' I No Yes 1

Snubbers may be added to safety related systems without prior License Amendment to Table 3.7.4-lb provided that a revision to Table 3.7.4-lb is included with the next License Amendment request.

- Modifications to this column due to changes in high radiation areas may be made without prior License Amendment provided that the revision to Table 3.7.4-lb is included with the next License Anendment request. .

TABLE 3.7.4-lb .

5 g SAFETY RELATED MECHANICAL SNUBBERS *

?

E HICH RADIATION SiJUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR ZONE ESPECIALLY DIFFICULT

[ 1J0. (Oty.) ON, LOCATION ANO ELEVATION INACCESSIBLE OURIljG SHUTOOWN**

TO REMOVE Heactor Building (A or I) (Yes or No) (Yes or No) 2821-Nuclear Boiler System (Continued)

MSRV-Rll4 (1) Az. 2700 El. 146' I No Yes MSRV-R115 (1) Az. 2700 El. 137' ' I No Yes MSRV-Rll6 (1) Az. 2700 El. 133' I tJo Yes MSRV-Rll8 (1) Az. 2700 El. 125' I No Yes tiSRV-R119 (1) Az. 2700 El. 120' I , No Yes MSRV-R121 (2) Az. 2300 El. 141' I No "es RFW-20 (2) Az. 1000 El 150' I No Yes u RFW-31 (2) Az. 2600 El. 150' I tJo Yes D 567-H10 (1) AZ. 1670 El. 134' I No Yes u $67-H11 (1) Az. 1140 El. 135' I No Yes b S67-H12 (1) Az. 450 El. 136 I No Yes E S67-H13 (1) Az. 320 El. 136' I No Yes S67-H14 (1) Az. 220 El. 136' I No Yes-S128-m (1) Az. 2400 El. 192' I No Yes-S143-H1 (1) Az. 400 El. 195' I No Yes S143-H2 (2) Az. 300 El. 189' I No Yes S143-H3 (2) Az. 300 El. 184' I No Yes S143-m (2) Az. 300 El. 179' I No Yes

$143-HS (1) Az. 300 El. 196' I No Yes S146-H6 (1) Az. 150 El 191' I No Yes

Snubbers may be added to safety related systems without prior License Amendment to Table 3.7.4-lb provided that a revision to Table 3.7.4-lb is included with the next License Amendment request.

- Modifications to this column due to changes in high radiation areas may be made without prior License Amendment provided that the revision to Table 3.7.4-lb is included with the next License AT,endment request. ,

4

= TABLE 3.7.4-lb ,

C -

g SAFETY RELATED MECHANICAL SNUBBERS * .

! HIGH RADIATION

-d SNUBGER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR ZONE ESRECIALLY DIFFICULT N NO. (Oty.) ON, LOCATION AND ELEVATION INACCESSIBLE DURING SHUTDOWN ** 0 REMOVE Reactor Building (A or I) (Yes ur No) (Yes or No) 2821-Nuclear Boiler System (Continued)

S148-H1 (1) Az. 2120 El. 195' - I No Yes S148-FG (2) Az. 2100 El. 189' I No Yes S148-10 (2) Az. 2100 El. 184' I No Yes S148-H4 (2) Az. 2100 El. 179' I No Yes

$158-f6 (2) Az. 2120 El. 194' & 196' I No Yes a

g) 2831-Reactor Recirculation System y S14-H1 (1) Az. 170 El. 125' I No Yes

S17-H1 (1) Az. 1980 El. 126' I No Yes o S18-H1 (1) Az. 650 El. 126' I No Yes

$24-H1 (1) Az. 3090 El. 123' I No Yes

$40-H1 (1) Az. 1100 El. 120' I No Yes

$43-H1 (1) Az. 1550 El. 187' I No Yes' 2 Ell-RHR Systan R338 (1) Az. 00 El. 146' I No Yes R339 (1) Az. 3550 El. 155' I No Yes

Snubbers may be added to safety related systems without prior License Amendment to Table 3.7.4-lb provided tha,t a revision to Table 3.7.4-lb is included with the next License Amendmalt request.

- Modifications to this column due to changes in high radiation areas may be made without prior License Amendment provided that the revision to Table 3.7.4-lb is included with the next License Amendment request.

-. -. - . - = - - . . - - - - . - - -~. . - - - - . -.

t i

t TABLE 3.7.4-lb -

T lj h SAFETY RELATED MECHANICAL SNUBBERS

5 *

! Si HIGH RADIATION l q SNUBBER SYSTEM SNUBBER INSTN LED ACCESSIBLE OR ZONE ESPECIALLY DIFFICULT i m NO. (Qty.) OM, LOCATION AND ELEVATION INACCESSIBLE DURIfJG SHUTDOWN **

TO REMOVE i Reactor Building (A or 1) (Yes or No) (Yes or No) j 2E11-RHR System (Continued) i l R340 (1) Az. 3420 El. 155' '

I No Yes

R342 (1) Az. 3370 El. 140' I No Yes l R350 (1) Az. 800 El. 150' I No Yes i

R351 (2) Az. 3050 El. 150' I No Yes R352 (2) Az. 3250 El. 150' I . No Yes R353 (1) Az. 3280 El. 146' I No Yes a R354 (1) Az. 3280 El. 146' I No Yes w R355 (1) Az. 2850 El. 150' I No Yes

} R356 (2) Az. 550 El. 150' I No Yes 1 y R357 (2) Az. 370 El. 150' I No Yes l ,L R358 (1) Az. 330 El. 146' I No Yes i N R359 (1) Az. 380 El. 146' I No Yes l R368 (1) Az. 200 El. 206' I No Yes' i .

2E21-Core Spray System i

j R59 (2) Az. 900 El. 178' I No Yes R98 (2) Az. 2670 El. 176' I No Yes S

j ,

Snubbers may be added to safety related systems without prior License Amendment to Table 3.7.4-lb jl provided that a revision to Table 3.7.4-lb is included with the next License , Amendment request.

" Modifications to this column due to changes in high radiation areas may be made without prior License Amendment provided that the revision to Table 3.7.4-lb is included with the next License

Amendment request.

i f

i i

5 TABLE 3.7.4-lb SAFETY RELATED MECHANICAL SNUBBERS

i

[

u HICH RADIATION j Si4UBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR ZONE ESPECIALLY DIFFICULT i --< f!O. (Oty.) Of1, LOCATION AND ELEVATION INACCESSIBLE DURING SHUTDOWN ** -

TO REMOVE N

i Reactor Building (A or I) (Yes or flo) (Yes or No) 2E41-HPCI System i

i R110 (1) Az. 180 El. 145' I No Yes j Rlll (1) Az. 190 El. 145' - I No Yes R112 (1) Az. 120 El. 145' I No Yes i R113 (2) Az. 110 El. 145' I No Yes Rll4 (1) Az. 460 El. 145' I No Yes u

R115 (2) Az. 560 El. 145' I No Yes S 2E51-RCIC System 1

y I C Rll4 (1) Az. 2130 El. 146' I No Yes l

3' R116 (1) Az. 1860 El. 142' I No Yes Rll7 (1) Az. 1860 El. 142' I No Yes a

9 2G31-RWCU System R166 (1) Az. 130 El. 149' I No Yes l R167 (2) Az. 170 El. 156' I No Yes R168 (1) Az. 170 El. 162' I No Yes l

i 1

i

Snubbers may be added to safety related systems without prior License Amendment to Table 3.7.4-lb provided that a revision to Table 3.7.4-lb is included with the next License' Amendment request.

4 j ** Modifications to this column due to changes in high radiation areas may be made without prior i License Amendment provided that the revision to Table 3.7.4-lb is included with the next License

] Anendment request. ,

]

1 I .___ ._ . . _ _ _ __

l TABLE 3.7.4-lb .

r ..

i

{ SAFETY RELATED MECHAN'ICAL SNUBBERS

i Y c HIGH RADIATION 1

i 5 SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR ZONE ESPECIALLY DIFFICULT 4

NO. (Oty.) ON, LOCATION AND ELEVATION INACCESSIBLE OURIrlG SHUTDOWN ** TO REMOVE

) Reactor Builoing (A or I) (Yes or No) (Yes or flo)

I 1

2 Ell-RHR System f R91 (2) 38'SR14-23'WRL, El. 119' A No No a R92 (2) 14'SR14-22'WRF, El.'119' A No flo

) R103 (2) 35'SR14-26'WRL, El. 119' A No tb i j '

R105 (2) 9'tR24-ll'WRF, El. 118' A flo No !

R106 (1) 9'NR24-ll'WRF, El. 118' A .,- No ib R123 (1) l'SR22-13'WRH, El. 169' A No No ,

{ R125 (1) 6'SR22-12'WRF, El. 167' A No No i R R224 (1) 24'SR14-29'WRL, El. 90' A No No

R225 (1) 29'SR14-29'WRL, El. 90' A No No l y R226 (2) 23'SR14-27'WRL, El. 90' A No No

] ; R228 (1) 18'SR14-23'WRL, El. 90' A No No '

i c' R229 (1) 28'NR24-29'WRL, El. 90' A tb No l

{ R230 (1) 25'SR14-30'WRL, El. 90' A No No -

R233 (2) 23'ta24-28'WRL, El. 90' A No No R235 (1) 13'SR14-13'WRL, El. 121' A No No

R240 (1) 24'tR24-28'WRL, El. 90' A No No j R289 (1) 13'NR24-13'WRL, El. 121' A tio No R290 (2) 25'SR14-28'WRL, El. 120' A No No R292 (2) 36'SR14- l'WRL, El. 118' A No No R295 (2) 25'tR24-28'WRL, El. 120' A tb No )

, R297 (2) 36'SR14-21'WRL, El. 118' A No ib

Snubbers may be added to safety related systems without prior License Amendment to T'able 3.7.4-lb ,

, provided that a revision to Table 3.7.4-lb is included with the next License Amendment request. i 1

- Modifications to this column due to changes in high radiation areas may be made without prior License Amendment provided that the revision to Table 3.7.4-lb is included with the next License i Amendment request. ,

4 w

_ ._ __ - . _ _ . . _ . _ . _-_ _ - - ___ _ _ _ . . . _ _ _ - ___.__ _ .. _~ . _ _ _

i 1

TABLE 3.7.4-lb ,

{a j SAFETY RELATED MECHANICAL SNUBBERS

i ,

^

7 HIGH RADIATION E SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR ZONE ESPECIALLY DIFFICULT I

Z NO. (Oty.) ON, LOCATION AND ELEVATION INACCESSIBLE DURING SHUTDOWN ** . TO REMOVE

ro Reactor Building (A or I) (Yes or No) (Yes or No)

I 2 Ell-RHR System (Continued) i R326 (1) 18'SR19-17'ERH, El. 136' A No No R327 (1) 18'SR19-17'ERH, El. 136' A No No '

R328 (1) 18'SR19-10'WRH, El. 139' A fjo ib 4

R329 (1) 18'SR19-10'WRH, El. 139' A tb No J S4-H1 (1) 19'SR19-25'WRL, El. 123' A ,

No ib 2E32-MSIV Leakage Control System .

! u Sll-H1 (1) 21'NR21- 5'WRB, El. 118' A No No j

~

2 Sl7-H1 (1) 20'NR21-21'WRB, El. 118' A No No i

y S18-H1 (1) 21'NR21- 4'WRB, El. 119' A No No

,' S19-H1 (1) 21'NR21- 5'WRB, El. 117' A No No 1 u 1 r ,

2E41-HPCI System R45 (2) 23'NR25-5'WRL, El. 117' A No No R50 (2) 10'NR25-4' ERG, El. 110' A tb No i j RSS (2) 10'NR25-24'WRL, El. 96' A No No f

1 2E51-RCIC System y

S6-H1 (1) 5'NR19-22' ERA, El. 129' A No No 11 a l be added to safety related systems without prior License Amendment to Table 3.7.4-lb j *provided Snubbers thamay't a revision to Table 3.7.4-lb is included with the next License Amendment request.

Modifications to this column due to changes in high radiation areas may be made without prior j License Amendment provided that the revision to Table 3.7.4-lb is included with the next License i Amendment request. '

1 l

1 1

- 1 e

j l

m P

O C

O

.e.

M C

C

+2 C

=w eM C

to e

W O

C C1 to CL th ac-aC H

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llATCH-UNIT 2 3/4 7-18

(This page blank intentionally) 6 1

1 HATCH-UttIT 2 3/4 7-18a

PLANT SYSTEMS BASES 3/4.7.4 SNUBBERS

. -All snubbers are required OPERABLE to ensure that the structural integrity of the reactor coolant system and all other safety-related systems is main-tained during and following a seismic or other event initiating dynamic loads. Snubber.s excluded from this inspection program are those installed on non-sa.fety 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 elasped may be used as a new reference point to determine the next inspection. However, the results of such early inspections performed before the or'iginal 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 inservice functional testing, that snubber may be exempted from being counted as inoperable. Generically susceptible snubbers 4

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 detcrmine if any safety-related component or system has been adversely affected by the inoperability of the snubber. The engineering evalution 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 shutdown at 18-month intervals. Observed failures of sample snubbers shall require functional testing of additional units.

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

HATCH-UNIT 2 B 3/4 7-2 4

PLANT SYSTEMS BASES 3/4.7.4 SNUBBERS (Continued)

The service life of a snubber is evaluated via manufacturer input and information through consideration' of the snubber service conditions and asso-ciated installation and maintenance records (newly installed snubberf 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 evaluttion in view of their age end operating conditions. These records will provide statistical bases for-futire consideration of snubber service life. The r'equirements for the maintenance of records and the snubber service life review are not intended to affect plant operation.

3/4.7.5 SEALED SOURCE CONTAMINATION The limitations on sealed source removable contamination ensure that the total body or individual organ irradiation does not exceed allowable

limits in the event of ingestion or inhalation of the source material. _

The limitations on removable contamination for sources requiring leak testing, including alpha emitters, is based on 10 CFR 70.39(c) limits for plutonium. Quantities of interest to this specification which are exempt from the leakage testing are consistent with the criteria of 10 CFR Part 30.11-20 and 70.19. Leakage from sources excluded from the require-ments of this specification is not likely to represent more than one maximum permissible body burden for total body irradiation if the source material is inhaled or , ingested.

t 3/4.7.6 FIRE SUPPRESSION SYSTEMS The OPERABILITY of the fire suppression systems ensures that adequate fire suppression capability is 'available to confine and extinguish fires occurring in any portion of the facility where safety-related equipment is located. The fire suppression system consists of the water system, spray and/or sprinklers, CO 2

, and fire hose stations. The collective capability of the fire suppression systems is adequate to minimize potential damage I to safety-related equipment and is a major element in the facility fire protection program. .

In the event that portions of the fire suppression systems are inoper-able, alternate backup fire fighting equipment is required to be made available in the affected areas until the inoperable equipment is restored to service.

In the event the fire suppression water system becomes inoperable, immediate corrective measures must be taken since this system provides the

! major fire suppression capability of the plant. The requirement for a twenty-four hour report to the Commission provides for prompt evaluation

' of the acceptability of the corrective measures to provide adequate fire suppression capability for the continued protection of the nuclear plant.

HATCH-UNIT 2 B 3/4 7-3

4 ADMINISTRATIVE CONTROL RECORD RETENTION (Continued)

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

~

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

. r

e. Records of transient or operational cycles for those unit compone'nts identified in Table 5.7.1-1.

f. Records of reactor tests and experiments.

g. Records of training and qualification for current members of the unit staff.

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

! i. Records of Quality Assurance activities required by the QA Manual .

j. Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.

k. Records of meetings of the PRB and the SRB.

I

1. Records of the service lives of all hydraulic and mechanical snubbers

, listed on Tables 3.7.4-la and 3.7.4-lb, including the date at which the service life commences and associated installation and mainte-nance records.

6.11 RADIATION PROTECTION PROGRAM 4 Procedures for personnel radiation protection shall be prepared consistent

- with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all-operations involving personnel radiation exposure.

L 6.12 HIGH RADIATION AREA l

i 6.12.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.203(c)(2) l of 10 CFR 20, each high radiation area in which the intensity of radiation is greater t

l than 100 mrem /hr but less than 1000 mrem /hr shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit *. Any individual or groups of' individuals permitted l

Health Physics personnel, or personnel escorted by Health Physics personnel in accordance with approved emergency procedures, shall be exempt from the RWP issuance requirement during the performance of their assigned radiation pro-tection duties, provided they comply with approved radiation protection pro-

edures for entry into high radiation areas.

HATCH-UNIT 2 6-18 -

ENCIDSURE 3 NRC DOCKEIS 50-321, 50-366 OPERATING LICENSES DPR-57, NPF-5 EDNIN I. HA'ICH NUCLEAR PIAVI' UNITS 1, 2 REQUEST 'IO AMEND TECHNICAL SPECIFICATIONS Pursuant to 10 CFR 50.92, Georgia Power Cmpany has evaluated the attached proposed mendments for the two Hatch units and has determined that their adoption would not involve a significant hazard. The basis for this determination is as follows:

a. PROPOSED CHANGE As requested by NRC letter dated Novmber 20, 1980, revise the

" Action" statment for the Snubbers Limiting Condition for Operation to require an engineering evaluation on the supported cmponent or declare the supported systs inoperable and follow the appropriate " Action" statment for that systs if inoperable snubber (s) are not returned to operable status within the Technical Specification-allotted time.

BASIS This change for both Hatch units constitutes an additional control not previously included in the Technical Specifications. This change does not affect the probability or consquences of an accident or malfunction of a different type than analyzed in the FSAR. The margin of safety as defined in the basis of any Technical Specification is not affected. The effect of this change is therefore within the acceptance criteria and the change is consistent with Its (ii) of the " Examples of Amendments That Are Considered Not Likely to Involve Significant Hazards Considerations" listed on page 14870 of the April 6,1983 issue of the Federal Register,

b. PROPOSED CHANGES As requested by NRC letter dated Novsber 20, 1980, revise snubber surveillance requirments to incorporate the following:

1. Revise snubber visual inspections and visual acceptance criteria to include the following:

a. Add the table listing of the safety-related mechanical snubbers,

b. Add visual inspection requirments for safety-r elated mechanical snubbers.

c. Add assurance that snubber attachttents to foundation or supporting structure are secure.

J

ENCIDSURE 3 (Continued)

NRC D00TTS 50-321, 50-366 OPERATING LICENSES DPR-57, NPF-5 EDNIN I. HA'ICH NUCLEAR PLANP UNITS 1, 2 REQUEST 'IO AMEND TECHNICAL SPECIFICATIONS

d. Md requirement that safety-related mechanical snubbers be inspected to determine if there has been a severe dynmic event and perform specific actions if such an event has occurred. 1

e. Provide statm ents for determination of operability.

2. Revise functional test requirements to include the following:

a. Increase functional test sample size such that 10% of each type safety-related snubbers are examined at least once per 18 months during shutdown,

b. Change re-smple size for each snubber failing functional test to at least one-half the size of the initial sample size for the particular type snubbers functionally tested.

c. Md the requirment such that snubbers placed in the sme location as snubbers which failed the previous functional test be tested during the next test period.

d. Md the requirment such that cause of failure will be evaluated for snubbers failing functional testing.

e. Add the requirment such that an engineering evaluation will be performed on cmponents which are found to be supported by failed snubber (s).

3. Add functional test acceptance criteria for safety-related mechanical snubbers.

4.. Add statment such that in the event that all inaccessible snubbers are inspected, functionally tested, and repaired, as necessary, during a unit outage, and that it is thus demonstrated all inaccessible snubbers are operable, the visual examination schedule may be reentered on a 6-month inspection interval. This addition will apply to Hatch Unit 2 only as this type statment is presently in the existing Hatch Unit 1 Technical Specifications and will be included in the proposed changes included herein.

5. Add requirement for service life monitoring of each safety-related snubber and retention of records thereof.

f ENCIOSURE 3 (Continued)

NRC DOCKEIE 50-321, 50-366 OPERATING LICENSES DPR-57, NPF-5 EIMIN I. HA'ICH NUCLEAR PLANT UNITS 1, 2 REQUEST 'IO AMEND TECHNICAL SPECIFICATIONS BASIS

%ese changes for both Hatch units constitute additional controls and/or limitations, as appropriate, not presently included in the Technical Specifications. These changes do not affect the probability or consequences of an accident or malfunction analyzed in the PSAR. These changes do not create the possibility of an accident or malfunction of a different type than analyzed in the FSAR. We margin of safety, as defined in the basis for any Technical Specification is not affected. We effect of these changes is therefore within the acceptance criteria and these changes are consistent with Its (ii) of the "Exsples of Amendnents %at Are Considered Not Likely to Involve Significant Hazards Considerations" listed on page 14870 of the April 6,1983 issue of the Federal Register,

c. PROPOSED CHANGES As necessitated by the NRC letter dated Novsber 20, 1980, revise the following to reflect changes in snubber surveillance rquirments:

1. Change " Table of Contents" and " List of Tables" pages, where appropriate, to correct and/or add pages, tables, etc.

resulting frm these snubber surveillance changes.

l l 2. Change the bases sections to reflect the revised snubber inservice surveillance rq uir m ents.

i

3. Add record retention rquirments for service life monitoring as a result of the revised snubber inservice surveillance in the adninistrative controls section of Technical Specifications.

BASIS These changes to the Technical Specifications for both Hatch units are administrative in nature. These changes do not affect the probability or consequences of an accident or malfunction analyzed l in the FSAR. %ese changes do not create the possibility of an i accident or malfunction of a different type than analyzed in the FSAR. We margin of safety as defined in the basis for any Technical Specification is not affected. The effect of these changes are therefore within the acceptance criteria and these

! changes are consistent with Its (i) of the " Examples of Amendments hat Are Considered Not Likely to Involve Significant Hazards Considerations" listed on page 14870 of the April 6,1983 issue of the Federal Register.

i l

l 1

ENCIDSURE '4 NRC DOCKETS 50-321, 50-366 OPERATING LICENSFC DPR-57, NPF-5 EDh'IN I. HA'ICH NUCIBR ?LANP UNITS 1, 2 REQUEST 'IO AMEND TECHl1ICil SPECIFICATIONS

-Pursuant to 10 CFR 170.12 (c), Georgia lower Company has evaluated the attached proposed mendment to Operating License DPR-57 and NPF-5, and has determined that:

a. We proposed mendnent does not require evaluation of a new safety analysis report or a rewrite of the facility license;

b. We proposed mendment does not require evaluation of several canplex issues, involve ACRS review, or rquire an environmental impact statenent;

c. We proposed mendment involves one safety issue, nmely, the revision of snubber inservice surveillance rq uirements as requested by the D. G. Eisenhut (NRC) letter dated November 20, 1980;

d. %e proposed change to Operating License DPR-57 is therefore a Class III amendment. A similar proposed change to Operating License NPF-5 is also being subnitted at this time;

e. The proposed change to Operating License NPF-5 is therefore a Class I amendnent.

l l

l

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. _ - _, , . . . . ~

v t e Letter Sequence Other
TAC:08298, (Withdrawn, Closed) TAC:08310, (Withdrawn, Closed) TAC:48362, (Withdrawn, Closed) TAC:48363, (Withdrawn, Closed) TAC:8298, (Withdrawn, Closed) TAC:8310, (Withdrawn, Closed)
Initiation Request, Request, Request Acceptance... Administration Questions Answers Results Withdrawal Other: ML20081J240, ML20084J043, ML20099F380
MONTHYEAR1983-05-31 [Table View]

ML20081J240

Text

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