ML20003F597

Proposed Changes to Tech Specs,Incorporating Revised Specs for Snubber Inservice Surveillance Requirements

ML20003F597
Person / Time
Site:	Hatch
Issue date:	04/14/1981
From:	GEORGIA POWER CO.
To:
Shared Package
ML20003F596	List: ML20003F595 ML20003F597
References
TAC-08298, TAC-08310, TAC-48362, TAC-48363, TAC-8298, TAC-8310, NUDOCS 8104230101
Download: ML20003F597 (51)

Text

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'8 O6 ATTAC K NT 2 PRC DOCKET 50-321 OPERATING LICENSE DPR-57 EDWIN I. HATCH MILEAR PLANT UNIT 1 PROPOSED CHANGES TO TEC WICAL SPECIFICATIONS The proposed change to Technical Specifications (Appendix A to Operating License DPR-57) would be incorporated as follows:

Remove Paae Insert Pace iv iv viii viii 3.6-10e through 3.6-10q 3.6-los through 3.6-10q 3.6-31 3.6-31 3.6-32 3.6-32 6-20 6-20 l

l

'810423D W

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 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 I. Jet 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 L. Snubbers 3. 6-10a 3.7 CONTAINMENT SYSTEMS 4.7 CONTAINMENT SYSTEMS 3.7-1 A. Pridary 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 3.8-1 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 A. Requirements for Reactor A. Auxiliary Electrical 3.9-1 Startup Systems Equipment iv i

LIST OF TABLES (Concluded)

Table Title 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 3.2-42 for Radiation Monitoring Systems Which Limit Radioactivity 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 Calibration Minimum Frequency for Instrumentation 3.2-48 Which Provides Surveillance Information 3.6-la 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 viii

3/4.6.L SNUBBERS LIMITING COBOITION FOR OPERATION 3.6.L All snubbers listed in Tables 3.6-la and 3.6-lb shall be OPERABLE.

APPLICABILITY: Conditions 1, 2, and 3.

ACTION:

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

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

1. Visual Insoections 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

• O 18 months + 25%

1 12 months T 25%

2 6 months T 25%

3, 4 124 days - 25%

1 5,6,7 62 days 1 25%

8 or more 31 days 1 25%

The snubbers may De categorized into two groups: Those accessible 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 cr impaired OPERASILITY, (2) attachments to tha foundation or supporting structure are secure, and (3) for mecnanical snub ~oers where snubber movement can be manually induced, the snubbers shall be inspected as follows: (a) At each ' refueling,

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

HATCH - UMIT 1 3.6 - 10a

3/4.6.L SNWBERS SURVEILLANCE REQUIREMENTS (Continued) safety-related systems associated with the snubbers listed in Table 3.6-lb shall be inspected to determine if tr. Ore 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. The inspection shall consist of verifying freedom of motion using one of the following: (1) Manually induced snubber movement; (ii) stroi<ing 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) before returning to power. 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.

However, if a hydraulic snubber is found to conte;n less than the required minimum volume of reserve fluid or if visible signs of leakage are present, the snubber shall be determined inoperable and cannot be determined OPERABLE via functional testing for the purpose of establishing the next visual inspection. All snubbers connected to an inoperable common hydraulic fluid reservoir shall be counted as inoperable snubbers.

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 requirements of this section for functionally testing mechanical snubbers may be waived pending acquisition of a conversion module for existing snubber test equipment or new test equipment by the next refueling outage.

~

HATCH - UNIT 1

i 3/4.6.L SNtBBERS M EILLANCE REQUIREMENTS (Continued)

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 identi?ied in Tables 3.6-la and 3.6-lb.

Snubbers 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 snall 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 Acceotance Criteria .

The hydraulic snubber functional test shall verify that:

a. Activation (restraining action) is achie ved 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. For snubbers specifically required to not displace under continuous load, the ability of the snubber to withstand load without displacement shall be verified.

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

HATCH - UNIT 1 3.6 - 10e

3/4.6.L SNLE8ERS SURVEILLANCE REQUIREMENTS (Continued)

5. Mechanical 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 fcree is nominally five (5) counds or one percent (1%) of rated snubber load, whichever is greater.

6. #nabber Service Life Monitoring A record of the service life of each snubber, the date at which the designated service life commences and the installation and maintmance 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 at the end of the 4th refueling cycle 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 tne next scheduled snubber service life ,

review, tne 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.

HATCH - UNIT 1 3.6 - 10d

5 N

=c e TABLE 3.6-la E

q SAFETY RELATED HYDRAULIC SNUB 0ERS*

~

HIGH RADIATION SNUB 8ER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR ZONE ESPECIALLY DIFFICULT NO. (Oty.) ON, LOCATION AND ELEVATION INACCESSIE,LE DURItC SHUTDOWN ** TO REMOVE Reactor Building (A or I) (Yes or No) (Yes or .5b) tbclear Boiler System SS-1 (1) Az. 720, El. 150' I tb tb SS-2 (1) Az. 720, El. 150' I No tb SS-3 (1) Az. 00, El. 140 I No No SS-4 (1) Az. 50, El. 128' I tb tb SS-5 (1) Az. 00, El. 140' I No tb SS-6 (1) Az. 1080, El. 150' I No No w

SS-7 (1) Az. 900, El. 150' I No tb m SS-8 (1) Az. 1600, El. 151 I tb No i SS-9 (1) Az. 950, El. 144' I No No

- SS-10 (1) Az. 900, El. 142' I No Yes

? SS-11 (1) Az. 1000, El. 138' I No Yes SS-12 (1) Az. 850, El. 144' I tb Yes SS-13 (1) Az. 820, El. 143' I No tb SS-14 (1) Az. 3159, El. 150' I tb No SS-15 (1) Az. 900, El. 145' I tb No SS-16 (1) Az. 900, El. 144' I No No SS-17 (1) Az. 1700, El. 145' I No Yes SS-18 (1) Az. 1600, El. 145' I tb Yes SS-19 (1) Az. 1600, El. 134' I tb No SS-20 (1) Az. 1600, El. 145' I tb 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 Licmse Amendmmt request.

• • Modifications to this column due to changes in bl h 0 radiation areas may be made without prior License Amendment provided that the revision to Table 3.6-la ls included with the next License Amendment request.

5 M

x TABLE 3.6-la SAFETY RELATED HYDRAULIC StJUBBERS*

• ~

HIGH RADIATION SNUBBER SYSTEM StJUBBER INSTALLE0 ACCESSIBLE OR ZONE ESPECIALLY DIFFICULT NO. (Qty.) Ofi, LOCATI0t1 Ato ELEVATION INACCESSIBLE DURING SHUTDOWN ** TO REMOVE Reactor Building (A or I) (Yes or f40) (Yes or tb) tbclear Boiler System (Continued)

SS-21 (1) Az. 1350, El. 158' I tb tb SS-22 (1) Az. 1600, El. 152' I tb ib SS-23 (1) Az. 2780, El. 150' I tb tb SS-24 (1) Az. 2700, El. 150' I tb tb SS-26 (1) Az. 2750, El. 145' I tb tb SS-27 (1) Az. 2700, El. 138' I ib tb w SS-28 (1) Az. 2700, El. 142' I tb Yes 6 55-29 (1) Az. 2700, El. 140' I ib tb

, SS-31 (1) Az. 2700, El. 139' I tb tb

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

• 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 i.o Table 3.6-la is included with the next License Amendment request.

5 E

TABLE 3.6-la 5

y SAFETY RELATED HYDRAULIC SNUBBERS

• HIGH RADIATION SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR ZONE ESPECIALLY DIFFICULT NO. (Qty.) ON, LOCATION AND ELEVATION INACCESSIllLE DURING SHUT 00WNa* TO REMOVE Reactor Building (A or I) (Yes or tb) (Yes or tb) tbclear Boiler System (Continued)

SS-42 (1) Az. 3470, El. 151' I No tb SS-43 (1) Az. 3400, El. 155' I No Tb SS-44 (1) Az. 3430, El. 155' I No tb SS-45 (1) Az. 670, El. 118' I No No SS-46 (1) Az. 670, El. 120' I No tb MVYH-23 (1) Az. 2700, El. 144' I No Yes F MVVH-24 (1) Az. 2700, El. 144' I No Yes MWH-25 (1) Az. 2700, El. 144' I No Yes

' Az. 2250, El. 124' MVVH-27 (1) I No No 5 MVVH-28 (1) Az. 2500, El. 128'- I No No

" Az. 2500, El. 128' MVVH-29 (1) I No ib MVVH-31 (1) Az. 1400, El. 149' I No ib MVVH-32 (1) Az. 1400, El. 148' I No tb MVVil-33 (1) Az. 1400, El. 145' I No ib MVVH-35 (1) Az. 900, El. 126' I No Ib MVVH-36 (1) Az. 900, El. 126' I No ib MVVH-37 (1) Az. 900, El, 126' I No tb FDH-11 (2) Az. 16c, El, 147' I No ib FDH-12 (2) Az. 00, El. 147' I No Ib F0H-13 (1) Az. 400, El. 148' I tb No

• Snubbers may be added to saf ety 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

=

i TABLE 3.6-la [

E g SAFETY RELATED HYDRAULIC SNUBBERS *

~

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

Nuclear Boiler Systen (Continue]d FDH-14 (1) Az. 750, El. 148' I No tb FDH-15 (1) Az. 530, El. 148' I No ib FDH-16 (1) Az. 790, El. 146' I No tb FDH-17 (1) Az. 2800, El. 148' I No tb FDH-18 (1) Az. 2810, El. 146' I No tb FDH-19 (1) Az. 980, El. 150' I tb No y FDH-21 (2) Az. 1500, El. 165' I No tb m & 2100, i FDH-22 (2) Az. 1200, El. 165' I tb tb

- & 2400, O FDH-23 (1) Az. 600, El. 164' I No ib FDH-24 (1) Az. 300, El. 167' I tb No FDH-25 (1) Az. 3300, El. 164' 1 No ib FDH-26 (1) Az. 3100, El. 1678 I No tb DFDH-28 (1) 4'S47-8' ERA, El. 132' I No tb DFDH-30 (1) 4'NR7-8' ERA, El. 132' I No ib DFDH-32 (1) Az. 140, El. 132' I No tb DFDH-36 (1) Az. 00, El. 132' I tb tb

• 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 Amendnent 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.

Q I i TABLE 3.6-la E SAFETY RELATED HYDRAULIC SNUBBERS

• U HICH 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)

Rm System S-1 (1) Az. 2700, El. 141' I tb ib S-2 (1) Az. 2700, El. 141' I No ib 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 ib SM-2 (1) Az. 1800, El. 140' I No Yes F SM-3 (1) Az. 2250, El. 146' I tb Yes SM-4 (1) Az. 2250, El. 146' ~

No Yes

[ SM-8 (1) Az. 900, El. 146' No ib a

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

• 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 Atendment 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-la I

@ SAFETY,RELATED HYDRAULIC SNUEBERS*

U

- 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)

Recirc System (Continued)

SS-A8 (1) Az. 100, El. 134' I No 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-82 (1) Az. 1350, El. 123' I No No SS-83 (1) Az. 1350, El. 123' I No No P SS-B4 (1) Az. 1450, El. 131' I No tb

• SS-B5 (1) Az. 1350, El. 131' No I No

' SS-86 (1) Az. 1350, El. 137' I No Yes E; SS-87 (1) Az. 1850, El. 140' I tb No SS-B8 (1) Az. 1800, El. 140' I No No SS-B12 (1) Az. 900, El. 145' I No No 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 No No CSH-79 (1) 2'NR 9- 7'WRi, El. 172' A No No

• Snubbers may be added to safety related systems without prior License Amendment to Table 3.~-la providW 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 TABLE 3.6-la E

U SAFETY RELATED HYDRAIA.IC SNUBBERS

• HIGH RADIATION SNU8BER 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 tb)

HPCI System HPCIH- 9 (1) 13'SRl- 6'ERC, El. 88' A tb tb FPCIH-13 (1) 7'SRl- 2'WRL, El. 94' A tb tb HPSEH- 2 (1) 12'NR2-10'WRL, El. 92' A No ib FPSEH- 8 (2) 6'NR2- 4'NRC, El. 112' A No tb HPSEH-12 (1) 5'NR3- 3'ERF, El. 123'-8" A No ib HPSEH-13 (2) 4 'tR3- 3 'ERF, El. 123'-6" A No tb F HPSEH-17 (1) 5'NR3-14'ERF, El. 123'-6" A No ib

' HPSEH-55 (1) 8'SRl-25'WRL, El. 98' A No tb HPSEH-57 (1) 1'SR1-18'WRL, El. 99'-6" A No tb E HPSEH-58 (1) 4'SRl-18'WRL, El. 99' A No tb HPSEH-60 (2) 4'NR2- 4'NRC, El. 120' A tb No HPSEH-61 (1) 3'tRS-ll'ERH, El. 123' A No tb HPSEH-62 (1) 3'NRS-ll'ERH, El. 123' A No tb HPSEH-63 (1) 8'NR7-13'ERH, El. 123' A No No HPSEH-66 (1) 13'SR9- 2'ERH, El. 122' A tb No HPSEH-67 (1) 8'SR11-6'ERH, El. 123' A tb tb HPSEH-72 (1) 11'SR 2-6'ERH, El. 124' A No tb

, IPSEH-73 (1) 11'SR 2-5'ERH, El. 124' A No tb HPSEH-74 (1) 7'SR3-ll'ERH, El. 122' A No Ib FPSEH-76 (1) l'tR3- 7'WRF, El. 123' A tb tb

• 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 M

x i TAB'.E 3.6-la SAFETY RELATED HYDRAULIC StJUBBERS*

~

HICH RADIATION StJUBBER SYSTEM StJUBBER INSTALLED ACCESSIBLE OR ZONE ESPECIALLY DIFFICULT NO. (Oty.) ON, LOCATION AND ELEVATION ItJACCESSIl3LE DURING SHUTDOWN ** 10 REMOVE Reactor Building (A or 1) (Yes or tJo) (Yes or ib)

IPCI System (Continued)

HPSEH-77 (1) 8'NR3-13'WRF, El. 123' A No ib iPSEH-80 (1) ll 'tR13-6 'ERH, El. 126' A No tb tPSEH-81 (1) 12 'tJR13-5 ' ERL , El. 126' A No ib iPSEH-82 (1) 3'SRll-5'WRH, El. 123' A tb No HPSEH-83 (1) 6'NRll-l'ERF, El. 123' A tb No IPSEH-84 (1) 8'NR11-13'WPF, El. 123' A No ib w HPSEH-85 (1) 7'NRll-ll'WRF, El. 122' A tb No b iPSEH-87 (1) l'SRll- 7'WRF, El. 125' A tb No i HPSEH-88 (1) 12'NR2-12' WRL, El 120' A tb tb

- HPSEH-89 (2) 11'SR2- 3' ERG, El. 123' A tb No S HPSEH-90 (1) 5'NR3-13' ERF, El. 125' A No tb iPSEH-91 (2) 5'SR3- 8' ERF, El. 123'-6" A . No No HPSEH-92 (1) 8'NR3- 3' ERH, El. 123' A tb tb HPSEH-93 (1) 8'tR3- 3' ERH, El. 123' A tb No RCIC System RCSEH-2 (1) 2'SRll-15' ERA, El. 101' A tb tb RCSEH-20 (1) l'NRll-14' ERA, El. 98' A No No RCSEH-21 (1) 7'SR 9- S' ERA, El. 120' A tb Yes RCSEH-23 (2) 14'SR 7- 9' ERA, El. 122' A No Yes

• 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 Licerise Amendment request.

M x

I TABLE 3.6-la E

SAFETY F. ELATED HYDRAULIC SNWBERS*

HIGH RADIATION SNUBBER SYSTEM SNWBER INSTALLED ACCESSIBLE OR ZONE ESPECIALLY DIFFICULT NO. (Qty.) ON, LOCATION Ato ELEVATION INACCESSIBLE DURIto SHUTDOWN ** TO REMOVE Reactor Building (A or I) (Yes or No) (Yes or ib)

Rm Sy-tem RHRH-184 (1) 3'SR3-17'ERH, El. 90' A No ib RHRH-185 (1) 3'SR3-17'ERH, El. 91' A No No RHRH-186 (2) O'SR3-12'ERH, El. 88' A No No RHRH-187 (2) 4'NR3- 8'ERH, El. 89' A No tb RHRH-188 (1) 5'SR5- S'WRL, El. 90' A No tb w RHRH-189 (1) 2'tRS- 8'WRL, El. 90' A No No

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

, RHRH-193 (1) 9 ' tR3-17 ' ERH , El. 123' A tb No

- RHRH-195 (1) 6'SR3-18'WRL, El. 125' A No tb g RHRH-196 (1) 6'SR3-18'WRL, El. 120' A No tb RHRH-199 (1) 10'SR3- 3'WRL, El. 123' A No ib RIRH-202 (1) 6'SR7- 7'ERH, El. 110' A tb No RHRH-207 (2) 10'SR7-15'ERH, El. 151' A No No RHRH-209 (2) 6'NR3-16'WRL, El. 105' A No No RHRH-210 (1) 9'NR3-16'WRL, El. 108' A No ib RmH-211 (2) 7'NR3-10'WRL, El. 100' A No No RHRH-212 (1) 6'NR3-12'WRL, El. 104' A No No RHRH-213 (1) 3'SR2-12'WRL, El. 124' A No No RHRH-234 (1) 3'SR2- 2'WRL, El. 119' A No ib RHRH-215 (2) 3'SR2-12'WRL, El. 118' A No tb

• 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 i TABLE 3.6-la SAFETY RELATED HYDRAULIC SNUBBERS *

~

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

RER System (Continued)

RHRH-216 (1) 11' tR3-16 ' WRL, El. 122' A No Ib RHRH-217 (1) 11'tE3-19'WRL, El. 121', A No tb RHRH-218 (1) 9'SR2-13'ERH, El. 116' A tb tb RHRH-220 (1) 4'SR7-12'WRL, El. 126' A tb tb RHRH-221 (1) 2'SR7-10'WRL, El. 122' A tb tb RHRH-222 (2) 2'SR7-10'WRL, El. 120' & 122' A tb tb w RHRH-223 (1) 1/2'NR11-4'ERH, El. 125' A No ib

'n c RHRH-224 (1) 3'SR11-7'ERH, El. 123' A No tb i RHRH-225 (1) 9'tR13-13'ERH, El. 117' A tb No RHRH-226 (1) 12'SR11-19'WRL, El. 121'~ A tb tb E RHRH-227 (1) 12'SR11-17'WRL, El. 122' A tb tb RHRH-228 (1) 3'NR13-12'WRL, El. 124' A No tb RHRH-229 (1) 3'NR13-12'WRL, El. 120' A tb No RHRH-230 (2) 3'NR13-12'WRL, El. 116' & 119' A No tb RHRH-231 (2) 9'SR11-17'WRL, El. 104' A No tb RHRH-232 (1) 9'SR11-17'WRL, El. 107' A No tb RHRH-233 (1) 7'SR11-10'WRL, El. 97' A No ib RHRH-234 (1) 6'SRll-12'WRL, El. 104' A tb tb RHRH-237 (2) 2'NR 9- 3'ERH, El. 155' A tb No RHRH-238 (2) 2'ta 9- 4'WRH, El. 159' A tb tb

• Snubbers may be added to safety related systems without prior License Amenduent 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 Amendmmt request.

5 N

( TABLE 3.6-la SAFETY RELATED HYDRAULIC SNLRBERS*

HIQi RADIATION SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR ZONE ESPECIALLY DIFFICULT NO. (Qty.) OtJ, LOCATION AND ELEVATION INACCESSIBLE DLEING SHUTDOWN ** TO REMOVE Reactor Building (A or I) (Yes or No) (Yes or tb)

RIE System (Continued)

RHRH-239 (1) 2'tR 9- 4'WRH, El. 160' A No tb Rt1RH-240 (2) 6'NR 5-25'WRL, El. 147' A tb tb RHRil-242 (1) 3'SR 4- 4'WRH, El. 150' A tb tb RHRH-244 (2) 10'SRll- 4'ERF, El. 121' A tb tb RHRH-245 (1) 10'SRll- 3'ERF, El. 121' A No No RERH-246 (1) 10'SRll- 3'ERF, El. 122' A tb No RHRH-249 (1) 11'SR11-10'ERF, El. 118' A No ib F RtRH-250 (2) 10'tR 3- 4'ERF, El. 121' A tb tb

[ RtRH-251 (1)

RHRH-252 (1) 10'NR 3- 3'ERF, El. 119' 10'ta 3- 3'ERF, El. 121' A

A No tb tb tb y RfRH-254 (1) 11'NR 3-10'ERF, El. 118' A No ib RtRH-279 (2) 3'SR 5- 3'WRL, El. 116' A No No RHRH-282 (1) 1/2'SR4- 7' ERG, El. 121' A tb tb RIRH-286 (2) 3'SR 2-17'WRL, El. 116' A tb tb RHRH-288 (2) 3'ta 9- 3'WRL, El. 116' A No ib RHRH-292 (1) 4'SR 2- 6'ERH, El. 124' A tb tb RHRH-299 (1) 4'SR13- 6'ERH, El. 122' A tb tb RtRH-305 (1) 5'ta 3- 4'ERH, El. 123' A No ib RHRH-306 (2) 3'ta 3- 7'ERH, El. 121' A No tb RHRH-307 (1) 10'SR 5-17'ERH, El. 132' A tb tb RHRH-309 (1) 9'SR11-18'ERH, El. 115' A No Ib

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

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

A x

8 TABLE 3.6 a E

y SAFETY RELATED HYDRAULIC StM3BERS*

HIQi RADIATION SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR 20rJE ESPECIALLY DIFFICULT NO. (Qty.) ON, LOCATION AND ELEVATION ItJACCESSIHLE_ DLRING SHUTDOWN #* TO REMOVE Reactor Building (A or I) (Yes or Nn) (Yes or ib)

RtB Systen (Continued)

RtRH-310 (1) 9'SR11-18'ERH, El. 124' A tb tb RilRH-312 (1) 6'tE11-18'WRL, El. 124' A No No RIHi-313 (1) 6'NRll-18'WRL, El. 125' A No ib RilRH-316 (1) 10'NRll- 4'WRL, El. 123' A tb No RilRH-319 (2) 9'tH 9-17'ERH, El. 136' A No ib RIHi-320 (1) 4'fE11-17'ERH, El. 90' A tb tb td RilRH-321 (1) 3'tEll-15'ERH, El. 91' A No ib

• 3'SR11-12'ERH, El. 89' RtEH-322 (2) A tb No RilRil-323 (2) 5'SR11- 9'ERH, El. 89' A tb tb 5 RtEH-324 (1) 5'ta 9- 5'WRL, El. 91' A No tb RHRH-325 (1) 2'SR 9- 9'WRL, El. 90' A tb tb Rt41H-332 (1) 2'SR 6- 2'WRH, El. 190' A tb ib RIRH-344 (1) 1/2'NR10-l'WRH, El. 122' A No No RHRH-348 (2) 3'NR13-17'WRL, El 117' A tb ib RHRH-399 (1) 6'NR 5- 6'ERH, El. 148' A No ib RiiRH-400 (1) 6'ta 5- l'ERH, El. 148' A tb tb

• 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 Licmse Amendmmt request.

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

5 M

x

' TABLE 3.6-lb I

E i y SAFETY RELATED MECHANICAL StAJBBERS*

HICH RADIATION SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR ZONE ESPECIALLY DIFFICULT NO. (Oty.) ON, LOCATION AND ELEVATION INACCESSIBLE DLRING SHUTDOWN ** TO REMOVE 4 Reactor Buildin0 (A or I) (Yes or No) (Yes or No) -

4 The list of Safety Related Mechanical Snubbers will be incorporated into these Technical Specifications pending completion of I&E Bulletin 79-14

. walkdown and plant modifications (IPC mechanical snubber replacement) during the 1981 maintencnce/ refueling outage.

f 4

1 2

• 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 4

4

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 in:pection 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 naintaining a constant level of snubber protection to systems. Therefore, the required inspection interval varies inversely with the observed snubber failures and is determined by the number of inoperable snubbers found during an inspection. Inspections performed before that interval has elapsed may be used as a new reference point to determine the next inspection. However, the results of such early inspections performed before the original required time interval has elapsed (nominal time less 25%) may not be used to lengthen the required inspection interval. Any inspection whose results require a shorter inspection interval will override the previous schedule.

When the cause of the rejection of a snubber is clearly established and remedied for that snubber and for any other snubbers that may be generically susceptible, and verified by inservice functional testing, that snubber may be exempted frcm being counted as inoperabic. Generically susceptible snubbers are those which are of a specific make or model and have the same design features directly related to rejection of the snubber by visual inspection, or are similarly located or exposed to the same environmental -

conditions such as temperature, radiation, and vibration.

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

To provide assurance of snubber functional reliability, a representative sample of the installed snubbers will be functionally tested during plant shutdowns at 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 3/4.6.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 area,etc...). The requirement to monitor the snubber service life is included to ensure that the snubbers periodically undergo a performance evaluation in view of their age and operating conditions. These records will provida statistical bases for future consideration of snubber service life. The requirenents for the maintenance of records and the snubber service life review are not intended to affect plant operation.

i I

l l

l l

I 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.

g. Records of training and qualification for current members for 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 SRB.

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

6.11 RADIATION PROTECTION PROGRAM 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 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 1

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

HATCH-UNIT 1 6-20

ATTAC)9ENT 3 960 DOCKET 50-366 OPERATING LICENSE PPF-5 ECMIN I. HATCH PLCLEAR PLANT LMIT 2 PROPOSED CHANGES TO TECWICAL SPECIFICATIONS The proposed change to Technical Specifics'41ons (Appardix A to Operating License ifV-5) would be incorporated as follows:

Remove 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 7-15a through 3/4 7-15d 3/4 7-16 3/4 7-16 3/4 7-16a through 3/4 7-161 3/4 7-17 3/4 7-17 3/4 7-18 3/4 7-18 3/4 7-18a 8 3/4 7-2 B 3/4 7-2 8 3/4 7-3 8 3/4 7-3 6-18 6-18 l

l

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.7 PLANT SYSTEMS 3/4.7.1 SERVICE WATER SYSTEMS Residual Hea t Removal Service Water System. . . . . . . . . . . . . . 3/4 7-1 Service Water Systems........e........................... 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 CONTAMINATION............................. 3/4 7-19 3/4.7.6 FIRE SUPPRESSION SYSTEMS

Fire Suppression Water System........................... 3/4 7-21 S pri n kl e r Sy s tems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 7-25 Low Pressure CO2 Systems................................ 3/4 7-27 Fire Hose Stations...................................... 3/4 7-28 3/4.7.7 PENETRATION FIRE BARRIERS............................... 3/4 7-30 3/4.7.8 SETTLEMENT OF CLASS I STRUCTURES.....................,.. 3/4 7-31 3/4.8 ELECTRICAL POWER SYSTEMS

3/4.8.1 A.C. SOURCES A.C. Sources-Operating.................................. 3/4 8-1 A.C. Sources-Shutdown................................... 3/4 8-9

~

i 3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS l A.C. Distribution - Operating........................... 3/4 8-10 A.C. Di s tribu tion - Shutdown. . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 8-12 D.C. Distribution - Operating. ......................... 3/4 8-13 D.C. Distribution - Shutdown............................ 3/4 8-16 A.C. Circuits Inside Primary Containment................ 3/4 8-17 I

Primary Containment Penetration Conductor Overcurrent Protective Devices.......................... 3/4 8-18 l

l HATCH-UNIT 2 VIII l

1 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 SYSTEM 54 .................................. 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 COMMUNICATIONS...................................... B 3/4 9-2 3/4.9.7 CRANE AND HOIST 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 R00 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 R0D SEQUENCE CONTROL SYSTEM......................... B 3/4 10-1 3/4.10.3 SHUTDOWN MARGIN DEMONSTRATIONS...................... B 3/4 10-1 3/4.10.4 RECIRCULATION L00PS................................. B 3/4 10-1 HATCH - UNIT 2 XIII

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 <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> replace or restore the inoperable snubber (s) to OPERABLE status and perform an engineering evaluation per Specification 4.7.4.c on the supported component 01 declare the supported system inoperable and follow the appropriate ACTION statement for that system.

SWVEILLANCE REQUIREMENTS 4.7.4 Each snubber shall be demonstrated OPERABLE by performance of the following inservice inspection program and the requirements of Specification 4.0.5.

a. Visual Inspections 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 per Inspection Period Insoection Period *#

0 18 months + 25%

1 12 months T 25%

2 6 months 7 25%

~

3, 4 124 days 25%

5,6,7 62 days 1 25%

8 or more 31 days 1 25% ,

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

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

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

1. The provisions of Specification 4.0.2 are not applicable.

HATCH-UNIT 2 3/4 7-11

. - , _ _ r m

l 1

PLANT SYSTEMS i SURVEILLANCE 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 snt,5ber movement can be manually induced, the snubbers shall be inspected as follows: (a) At each refueling, 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. The inspection shall consist of verifying freedom of motion using one of the following:

(1) 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) before returning to power. 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. However, if a hydraulic snubber is found to contain less than the required minimum volume of reserve fluid or if visible signs of leakage are present, the snubber shall be determined inoperable and cannot be determined OPERABLE via functional testing for the purpose of establishing the next visual inspection interval. All snubbers connected to an inoperable common hydraulic fluid reservior shall be counted as inoperable snubbers.

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

• The requirements of this section for functionally testing mechanical snubbers may be waived pending acquisition of a conversion module for existing snubber test equipment or new test equipment by the next refueling outage.

HATCH-UNIT 2 3/4 7-12

l PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) functionally tested either in place or in a bench test. For each snubber that does nnt 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.

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 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.

• 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 testing was performed to qualify snubber operability for all design conditions at either the completion of their fabrication or at a subsequent date.

HATCH-UNIT 2 3/4 7-13

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

d. Hydraulic Snubbers Functional Test Accectance 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 verifled.

e. Mechanical 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 load, whichever is greater.

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

Concurrent with the inservice visual inspection performed at the end of the end of the 1st refueling cycle 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 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 af 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.

HATCH-UNIT 2 3/4 7-14

TABLE 3.7.4-la E

M SAFETY RELATED HYDRAULIC SNUBBERS *

?

E HIGH RADIATION Q SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR 70NE ESPECIALLY DIFFICULT m NO.(_ qty.) ON. LOCATION AND ELEVATION INACCESSIBLE DURING SHUTDOWN ** TO REMOVE Reactor Building (A or I) (Yes or No) (Yes or No) 2 Ell-RHR SYSTEM R86 (1) 8' NR19 - l' ERJ, El. 212' A No No R88 (1) 10' NR17 - 3' WRJ, El .119' A No No R90 (1) R15 - 3 ' ERH , El . 119 ' A No No R93 (2) 8' SRl4 - 11' ERF, El. 118' A No No R94 (1) 8' SR14 - 10' ERF, El .118' A No No R98 (2) 10' SRl9 - l' ERJ, El. 121' A No No R100 (1) 10' SR21 - 3' WRJ, El 119' A No No R101 (1) 12' SR21 - S' WRJ, El 119' A No No w R102 (1) R23 - 3' ERH, El .119' A No No 1 R128 (1) 6 ' NR23 - 16' ERF, El .123 ' A No No u

' R129 (2) 18' SR21 - 16' ERF, El .123' A No No R146 (2) 5' SR21 - 8' WRL, El. 120' A No Yes R221 (1) 18' NR19 - 12' WRL, El. 90' A No No R222 (1) 18' SR19 - 12' WRL, El . 90' A No No 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' NR23 - 3' WRL, El .107 ' A No 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.

• • 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 *

[ HIGH RADIATION jz; SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR ZONE ESPECIALLY DIFFICULT

-4 NO. (Qty.) ON, LOCATION AND ELEVATION ~~ INACCESSIBLE DURING SHUTDOWN ** TO REMOVE N Reactor Building (A or I) (Yes or No) (Yes or No) 2E11-RHR SYSTEM (Continued)

R250 (1) 11 ' SR14 - 15' WRL, El .119' A No No R251 (2) 11 ' SR14 - 15' WRL, El .120' A No No R252 (1) 15' SRl4 - 15' WRL, El .112' A No No R253 (1) 15' SR14 - 15' WRL, El .120' A No No R254 (1) 17 ' SR14 - 17' WRL, El .112' A No No R256 (1) 17' SRl4 - 17' WRL, El .112' A No Yes R258 (1) 22' SR14 - 13' WRL, El . 99' A No No R:54 (1) 21' SRl4 - 9' WRL, El .104 ' A No Yes R267 (2) 15' 5R14 - 3' WRL, El .102' A No No R R268 (1) 11 ' NR24 - 15' WRL, El .119' A No No a

R269 (2) 11' NR24 - 15' WRL, El 120' A No No y R270 (1) 15' NR24 - 15' WRL, El .112' A No No

R271 (1) 15' NR24 - 15' WRL, El .120' A No No a 17 ' NR24 - 17 ' WRL, El .112' R272 (1) A No No R274 (1) 17' NR24 - 17' WRL, El .112' A No No R276 (1) 22' NR24 - 13' WRL, El. 99' A No No R282 (1) 21' NR24 - 9 ' WRL , El . 104 ' A No Yes R285 (2) 15' NR24 - 3' WRL, El .102' A No No R315 (2) 10' NRl9 - 6' ERJ, El 123' A No No R374 (2) 23' SR14 - 15' WRL, El .106' A No 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.

• • 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-l a SAFETY RELATED HYDRAULIC SNUBBERS

• 9 c-HIGH RADIATION 5 SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR ZONE

" ESPECIALLY DIFFICULT

" N0. (Qty.) ON, LOCATION AND ELEVATION INACCESSIBLE DURING SHUTDOWN ** TO REMOVE Reactor Building (A or I) (Yes or No) (Yes or No) 2E11-RHR SYSTEM (Continued)

R375 (2) 23' SR14 - 12' WRL, E1.108' A No No R376 (1) 23 ' SR14 - 12' WRL, El .109' A No No R377 (2) 23' NR24 - 15' WRL, El .106' A No Yes R378 (2) 23' NR24 - 12' WRL, El .108' A No No R379 (1) 23' NR24 - 12' WRL, E1.109' A No No 2 Ell-RHR SERVICE WATER SYSTEM R 15 (2) 7' SR14 - 11 ' ERH, El .115' A No No

{ R 23 (2) 7' NR24 - 11' ERH, El .115' A No No

[ 2E21-CORE SPRAY SYSTEM R 35 (1) 8' SR14 - 6' WRL, El. 95' A No No R 40 (1) 7' SR14 - 31' WRL, El. 95' A No No R 53 (2) 10' SR14 - 6' WRL, E1.106' A No No R 72 (2) 10' NR24 - 6' WRL, El. 102' A No No R 80 (1) 8' NR24 - 6' WRL, E1. 95' A No No R 87 (1) 7' NR24 - 6' WRL, El. 90' A No No R107 (2) 39' NR24 - 15' WRL, El .123' A No No

• 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 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 k SAFETY RELATED HYDRAULIC SNUBBERS

• 9

& HIGH RADIATION 5 SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR ZONE ESPECIALLY DIFFICULT H NO. (Qty.) ON, LOCATION AND ELEVATION INACCESSIBLE DURING SHUTDOWN ** TO REMOVE N Reactor Building (A or I) (Yes or No) (Yes or No) 2T46-SGTS SYSTEM R 65 (2) 6' NR24 - 9' WRB, El. 198' A No Yes R 66 (1) 2 ' NR24 - 9' WRB, El .186' A No No 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 R

• 2831-REACTOR RECIRCULATION SYSTEM T

g SSAl (1) Az 315 0, El .117' I No No o SSA2 (1) Az 328 0 El. 125' I No Yes SSA3 (1) Az 3020, El. 125' I No Yes SSA4 (1) Az 3280, El . 131 ' I No Yes 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 SSA12 (1) Az 2550, El. 129' I No No SSA13 (1) Az 2850, El. 129' I No No SSA14 (1) Az 2700, El . 121 ' I No No SSA15 (1) Az 3230 El. 144' I No Yes SSA16 (1) Az 2170, El. 144' I No 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.

• • 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 HYDC'"8IC SNUBBERS *

[ HIGH RADIATION 5 SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR ZONE ESPECIALLY DIFFICULT H NO. (Qty.) ON, LOCATION AND ELEVATION INACCESSIBLE DURING SHUTDOWN ** TO REMOVE N

Reactor Building (A or I) (Yes or No) (Yes or No) 2831-REACTOR RECIRCULATION SYSTEM (Continued)

SSA17 (1) Az 2700, El. 125' I No Yes SSA19 (1) Az 2700, El . 138 ' I No Yes SSA20 (1) Az 2700, El. 138' I No Yes SSA21 (1) Az 00, El . 140 ' I No Yes SSA22 (1) Az 00, El . 140' I No Yes SSBl (1) Az 1350, El . 117 ' I No No SSB2 (1) Az 148 , El .125' I No Yes SSB3 (1 ) Az 1220, El . 125' I No Yes SSB4 (1) Az 1480, El . 131 ' I No Yes R SSBS (1) Az 1220, El. 131' I No No a SSB6 (1 ) Az 1350, E1. 137 ' I No Yes y SSB7 (1 ) Az 198 , El .124' I No Yes

SSB8 (1) Az 1620, El. 123' I No Yes o- Az 0750, El. 129' SSB12 (1) I No No SSB13 (1) Az 1050, El . 129 ' I No No SSBl4 (1) Az 0900, El. 121' I No No SSB15 (1) Az 1430, El. 144' I No Yes SSB16 (1) Az 0370, 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 SSB21 (1) Az 180 0, El. 140' I No Yes SSB22 (1) Az 1800, El. 140' I No 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.

• • 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-lb 5

pj SAFETY RELATED MECHANICAL SNUBBERS

• f EE HIGH RADIATION

$ SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR ZONE ESPECIALLY DIFFICULT y NO. (Qty.) ON, LOCATION AND ELEVATION INACCESSIBLE DURING SHUTDOWN ** TO REMOVE Reactor Lbilding (A or I) (Yes or No) (Yes or No) 2821-Nuclear Boiler System MS-R34 (1) Az. 1100 El. 155' I No Yes MS-R35 (1) Az. 1450 El. 150' I No 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 No Yes MS-R39 (2) Az. 950 El. 150' I No Yes MS-R41 (1) Az. 1000 El. 150' I No Yes m MS-R42 (1) Az. 1400 El. 150' I No Yes

); MS-R43 (1) Az. 1300 El. 150' I No Yes y MS-R44 (2) Az. 1400 El. 150' I No Yes L MS-R45 (1) Az. 2500 El. 156' I No Yes m

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. 2880 El. 167' I No Yes MS-R50 (2) Az. 2700 El. 150' I No Yes MS-R52 (1) Az. 2650 El. 150' I No Yes MS-RS3 (2) Az. 2350 El. 150' I No Yes MS-RS4 (1) Az. 2350 El. 150' I No Yes MS-R55 (1) Az 2350 El. 150' 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 Amendment request.

TABLE 3.7.4-lb E

j SAFETY RELATED MECHANICAL SNUB 3ERS*

T 5 HIGH RADIATION

$ SNUB 8ER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR ZONE ESPECIALLY DIFFICULT s3 NO. (Qty.) ON, LOCATION AND ELEVATION INACCESSIBLE DURING SHUTDOWN ** TO REMOVE Reactor Building ( A or I) (Yes or No) (Yes or No) 2021-Nuclear Boiler System (Continued)

MSRV-R36 (1) Az. 2300 El. 137' I tb Yes MSRV-R37 (1) Az. 2300 El. 133' I No Yes MSRV-R38 (1) Az. 2300 El. 133' I No Yes MSRV-R40 (1) Az. 2300 El. 125' 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 u, MSRV-R50 (1) Az. 2700 El. 150' I No Yes

); MSRV-RS2 (2) Az. 1050 El. 150' I No Yes y MSRV-R53 (1) Az. 1050 El. 149' I No Yes L MSRV-R54 (1) Az. 800 El. 137' I No Yes g5 MSRV-RS6 (1) Az. 700 El. 131' I No Yes MSRV-R57 (1) Az. 700 El. 135' I No Yes MSRV-R58 (1) Az. 700 El. 125' I No Yes MSRV-R59 (2) Az. 1250 El. 154' I No Yes MSRV-R60 (2) Az. 1200 El. 152' I No Yes 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

• 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 Amendment request.

l TABLE 3.7.4-lb bh SAFETY RELATED MECHANICAL SNUBBERS

• 9 5: HICH RADIATION 5 SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR ZONE ESPECIALLY DIFFICULT

-i NO. (Qty.) ON, LOCATION AND ELEVATION INACCESSIBLE DURING SHUTDOWN ** TO REMOVE Reactor 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 No 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 MSRV-R75 (1) Az. 2550 El. 154' I No Yes Id MSRV-R76 (1) Az. 2500 El. 146' I No Yes MSRV-R77 (1) Az. 2500 El 137' I No Yes

? MSRV-R78 (1) Az. 2500 El. 136' I No Yes MSRV-R79 (1) Az. 2500 El. 133' I No Yes MSRV-R80 (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 No Yes MSRV-R88 (1) Az. 650 El. 127' I No Yes MSRV-R89 (1) Az. 650 El. 125' I No Yes MSRV-R90 (1) Az. 1150 El. 145' 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 Amendment request.

TABLE 3.7.4-lb SAFETY RELATED MECHANICAL SNUBBERS

• 5 HIGH RADIATION U SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR ZONE ESPECIALLY DIFFICULT m NO. (Qty.) ON, LOCATION AND ELEVATION INACCESSIBLE DURING SHUTDOWN ** TO REMOVE Reactor Building (A or I) (Yes or No) (Yes or No) 2821-Nuclear Boiler System (Continued)

MSRV-R91 (1) Az. 1100 El. 137' I Ne Yes MSRV-R92 (1) Az. 1100 El. 132' I tb 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

<" MSRV-R100 (1) Az. 3300 El. 146' I No Yes MSRV-R101 (1) Az. 3300 El. 140' I No Yes

? MSRV-R103 (1) Az. 3400 El. 129' I No Yes

" 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-R111 (1) Az. 220 El. 132' I No Yes MSRV-Rll3 (1) Az. 2700 El. 154' 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 Licmse Amendment provided that the revision to Table 3.7.4-lb is included with the next License Amendment request.

TABLE 3.7.4-lb I-g SAFETY RELATED MECHANICAL SNUBBERS *

?

c:

HICH RADIATION 5 SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR ZONE ESPECIALLY DIFFICULT NO. (Qty.) ON, LOCATION Ato ELEVATION INACCESSIBLE DURING SHUTDOWN ** TO REMOVE Reactor Building (A or I) (Yes or No) (Yes or No) 2B21-tOclear Boiler System (Continued)

MSRV-Ril4 (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 No Yes MSRV-R118 (1) Az. 2700 El. 125' I No Yes MSRV-R119 (1) Az. 2700 El. 120' I No Yes MSRV-R121 (2) Az. 2300 El. 141' I No Yes RFW-20 (2) Az 1000 El. 150' I No Yes RFW-31 (2) Az. 2600 El. 150' I tb Yes M

• S67-H10 (1) Az. 1670 El. 134' I No Yes S67-Hll (1) Az. 1140 El. 135' I No Yes

? S67-H12 (1) Az. 450 El. 136' I No Yes c"n

" S67-H13 (1) Az. 320 El. 136' I No Yes S67-H14 (1) Az. 220 El. 136' I No Yes S128-in (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-H4 (2) Az. 300 El. 179' I No Yes S143-H5 (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 l License Amendment provided that the revision to Table 3.7.4-lb is included with the next License Amendment request.

z TABLE 3.7.4-lb SAFETY RELATED MECHANICAL SNUBBERS

• HIGH RADIATION

-4 SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR ZONE ESPECIALLY DIFFICULT N NO. (Qty.) ON, LDCATION AfD ELEVATION INACCESSIBLE DURING SHUTDOWN ** TO REMOVE Reactor Building (A or I) (Yes or No) (Yes or No) 2821-Nuclear Boiler System (Continued)

S148-H1 (1) Az. 2120 El. 195' I No Yes S148-H2 (2) Az. 2100 El. 189' I No Yes S148-H3 (2) Az. 2l00 El. 184' I No Yes S148-H4 (2) Az. 2l00 El. 179' I No Yes S158-H5 (2) Az. 2120 El. 194' & 196' I No Yes 2831-Reactor Recirculation System R

• S14-H1 (1) Az. 170 El. 125' I No Yes y S17-H1 (1) Az. 1980 El. 126' I No Yes

S18-H1 (1) Az. 650 El. 126' I No Yes a S24-H1 (1) Az. 3090 El. 123' I No Yes S40-H1 (1) Az. 1100 El. 120' I No Yes S43-H1 (1) Az. 1550 El. 187' I No Yes 2 Ell-R m System R338 (1) Az. 00 El. 146' I No Yes R339 (1) Az. 3550 El. 155' 1 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 Amendment request.

TABLE 3.7.4-lb n SAFETY RELATED MECHANICAL SNUBBERS

• T g HIGH RADIATION y SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR ZONE ESPECIALLY DIFFICULT y NO. (Qty.) ON, LOCATION AND ELEVATION INACCESSIBLE DURING SHUTDOWN ** TO REMOVE Reactor Building ( A or I) (Yes or No) (Yes or No) 2 Ell-RHR System (Continued)

R340 (1) Az. 3420 El. 155' I No Yes R342 (1) Az. 3370 El 140' I No Yes R350 (1) Az. 800 El. 150' I No Yes 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 R354 (1) Az. 3280 El. 146' I No Yes m R355 (1) Az. 2850 El. 150' I No Yes 2 R356 (2) Az. 550 El. 150' I No Yes y R357 (2) Az. 370 El. 150' I No Yes L R358 (1) Az. 330 El 146' I No Yes Q R359 (1) Az. 380 El. 146' I No Yes R368 (1) Az. 200 El. 206' I No Yes 2E21-Core Spray System R59 (2) Az. 900 El. 178' I No Yes R98 (2) Az. 2670 El. 178' 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 Amendment request.

TABLE 3.7.4-lb h

n SAFETY RELATED MECHANICAL SNUBBERS

• Y HIGH RADIATION E SNUBBER SYSTEM SNWBER INSTALLED ACCESSIBLE OR ZONE ESPECIALLY DIFFICULT U NO. (Oty.) ON, LOCATION AND ELEVATION INACCESSIBLE DURING SHUTDOWN ** TO REMOVE N Reactor Building (A or I) (Yes or No) (Yes or No) 2E41-HPCI System R110 (1) Az. 180 El. 145' I No Yes Rlll (1) Az. 190 El. 145' I tb Yes R112 (1) Az. 120 El. 145' I No Yes R113 (2) Az. 110 El. 145' I No Yes R114 (1) Az. 460 El. 145' I No Yes R115 (2) Az. 560 El. 145' I tb Yes

{ 2E51-RCIC System E Rll4 (1) Az. 2130 El. 146' I No Yes cn

• RlM (1) Az. 1860 El. 142' I No Yes R2 ' (1) Az. 1860 El. 142' I No Yes 2G31-RWCU System R166 (1) Az. 130 El. 149' I No Yes R167 (2) Az. 170 El. 156' I No Yes R168 (1) Az. 170 El. 162' 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 Amendment request.

TABLE 3.7.4-lb x

SAFETY RELATED MECHANICAL SNLOBERS*

c: HICH RADIATION 5 SNUB 8ER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR ZONE ESPECIALLY DIFFICULT NO. (Qty.) ON, LOCATION Ato ELEVATION INACCESSIBLE DmING SHUTDOWN ** TO REMOVE Reactor Building (A or I) (Yes or No) (Yes or No) 2E11-Rm System R91 (2) 38'SR14-23'WRL, El. 119' A No No R92 (2) 14'SR14-22'WRF, El. 119' A No tb R103 (2) 35'SR14-26'WRL, El. 119' A No No R105 (2) 9'NR24-11'WRF, El. 118' A No No R106 (1) 9'NR24-11'WRF, El. 118' A No No R123 (1) l'SR22-13'WRH, El. 169' A tb No R125 (l' 6'SR22-12'WRF, El. 167' A No No R224 (1) 24'SR14-29'WRL, El. 90' A No No R

" R225 (1) 29'SR14-29'WRL, El. 90' A No No R226 (2) 23'SR14-27'WRL, El. 90' A No No 7 R228 (1) 18'SR14-23'WRL, El. 90' A No No R229 (1) 28'NR24-29'WRL, El. 90' A No No R230 (1) 25'SR14-30'WRL, El. 90' A No No R233 (2) 23'm24-28'WRL, El, 90' A No No R235 (1) 13'SR14-13'WRL, El. 121' A No No R240 (1) 24 'm24-28'WRL, El. 90' A No No R289 (1) 13'NR24-13'WRL, El. 121' A No No R290 (2) 25'SR14-28'WRL, El. 120' A No tb R292 (2) 36'SR14- l'WRL, El. 118' A No tb R295 (2) 25'NR24-28'WRL, El. 120' A No No R297 (2) 36'SR14-21'WRL, El. 118' A No tb

• 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 Amendment request.

TABLE 3.7.4-lh 5 SAFETY RELATED MECHANICAL SNWBERS*

FI Y HIGH RADIATION 5 SNWBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR ZONE ESPECIALLY DIFFICULT U NO. (Qty.) ON, LOCATION Ato ELEVATION INACCESSIBL_E_ DURING SHUTOOWN'" TO REMOVE m Reactor Building (A or I) (Yes or No) (Yes or No) 2 Ell-RHR System (Continued)

R326 (1) 18'SR19-17'ERH, El. 136' A No No R327 (1) 18'SR19-17'ERH, El. 136' A tb No R328 (1) 18'SR19-10'WRH, El. 139' A No No R329 (1) 18'SR19-10'WRH, El. 139' A tb No S4-H1 (1) 19'SR19-25'WRL, El. 123' A No No 2E32-MSIV Leakage Control Systen w Sll-H1 (1) 21'NR21- S'WRB, El. 118' A No No 2 S17-H1 (1) 20'NR21-21'WRB, El. 118' A No No u S18-H1 (1) 21'NR21- 4'WRB, El. 119' A No No S19-H1 (1) 21'tR21- S'WRO, El. 117' A No No k.

2E41-IPCI Systen R45 (2) 23'NR25-5'WRL, El. 117' A No No R50 (2) 10'tN25-4' ERG, El. 110' A tb No RSS (2) 10'NR25-24'WRL, El. 96' A No tb 2E51-RCIC Systen S6-H1 (1) 5'NR19-22' ERA, El. 129' A No No

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

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

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

The visual inspection frequency is based upon maintaining a constant level of snubber protection to systems. Therefore, the required inspection interval varies inversely with the observed snubber failures and is determined by the number of inoperable snubbers found during an inspection. Inspections performed before that interval has elasped 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 snubber is found inoperable, an engineering evaluation is performed,

. in addition to the determination of the snubber mode of failure, in order to l determine if any safety-related component or system has been adversely I affected by the inoperability of the snubber. The engineering evalution shall l 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.

l HATCH-UNIT 2 8 3/4 7-2

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 snubber, seal replaced, spring replaced, in high' radiation area, in high temperature area, etc...). The requirement to monitor the snubber service life is included to ensure that the snubbers periodically undergo a performance evaluation in view of their age and operating conditions. These records will provide statistical bases for future consideration of snubber service life. The requirements for the maintenance of records and the snubber service life review are not intended to affect plant operation.

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 no'. itkely to represent more than one maximum permissible body burden f ar total body irradiation if the source material is inhaled or ingested.

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, CO2 , and fire hose stations. The collective capability of the fire suppression systems is adequate to minimize potential damage 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.

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1 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.

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.

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 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 CFR 20, each high radiation area in which the intensity of radiation is greater 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

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

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