ML20084J043
| ML20084J043 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 05/02/1984 |
| From: | GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML20084J034 | List: |
| References | |
| TAC-08298, TAC-08310, TAC-48362, TAC-48363, TAC-8298, TAC-8310, NUDOCS 8405080308 | |
| Download: ML20084J043 (64) | |
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ENCLOSURE 2 NRC DOCKET 50-321 OPERATING LICENSE OPR-57 EDWIN 1. HATCH NUCLEAR PLANT 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:
Remove Page Insert Page iv iv viii viii 3.6-10a through 3.6-109 3.6-10a through 3.6-10u 3.6-31 3.6-31 3.6-32 3.6-32 6-20 6-20 8405000300 040502 ,
O Section Section Pa ge LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.6 PRIltARY SYSTEM B0UNDARY 4.6 PRIftARY SYSTEti 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 Mead 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 Coclant 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. Primary Containment A. Primary Containment 3.7-1 B. Standby Gas Treatment System B. Standby Cas 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. fliscellaneous Radioactive A. f!!scellaneous Radioactive 3.8-1 fiatorials 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
LIST OF TABLES ,
- (Concluded)
, Table Title Page 4.2-7 Check, Functional Test, and Calibration Minimum Frequency 3.2-40 For Neutron Monitoring Instrunentation 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 i Release l' 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 i for Instrunentation Which Monitors leakage into the Drywell l 4.2-11 Check and Calibration Minimum Frequency for Instrumentation 3.2-48 Which Provides Surveillance Infonnation a
l 3.6-la Safety Related !!ydraulic Snubbers 3.6-10e l
- 3.6-lb Safety Related Mechanical Snubbers 3. 6-10r l 4.6-1 In-Service Inspection Program 3.6-11
! 3.7-1 Primary Containment Isolation Valves 3.7-16 l 3.7-2 Testable Penetrations with Double 0-Ring Seals 3.7-21 f 1
- 3.7-3 Testable Penetrations with Testable Bellows 3.7-22 1
j 3.7-4 Primary Containment Testable Isolation Valves 3.7-23 !
! 3 13.1 Fire Detectors 3.13-2 i 3.13-2 Fire !!ose Stations 3.13-9 j 6.2.2-1 Minimum Shift Ctrw Composition 6-3 6.9-1 Special Reporting Regiirements 6-19 I l
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3/4.6.L SNUBBERS LIMITING CONDITION FOR OPERATION 3.6.L All snubbers listed in Tables 3.6-la and 3.6-Ib 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 RB)UIRBfENTS 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-Ib 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 i 25%
2 6 months 7 25%
3, 4 124 days T 25% '
5, 6, 7 62 days T 25%
8 or more 31 days [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.
- 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 he manually induced, the snubbers shall be inspected as follows: (a) At each refueling, Mhe inspection interval shall not be lengthened more than one step at a time.
!!ATCil - UNIT 1 3.6-10a
3/4.6.L SNUBBERS SURVEILLANCE REQUIREMENTS (Continued) safety-mlated systems associated with the snubbers listed in Table 3.6-1b shall be ins dynamic event. (b) pected to detemine In the event if there of a severe has event, dynamic been asnubbers severe 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 fro"ien up. The inspection shall consist of verifying 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) before returning to power. Re-inspection shall subsequently be perfomed 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 Tabic 3.6-1b. 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 mjection is clearly established and remedied for that particular snubber and for other snubbers that may be generically susceptible; and (2) the affected snuWoer is functionally tested in the "as found" condition and detemined OPERABLE per Specification 4.6.L.4 or 4.6.L.5, as applicable.
Ibwever, if a hydraulic snubber is found to contain less than the required minimum volume of reserve fluid or if visible signs of leakage are pmsent, the snubber shall be detemined inoperable and cannot be detemined OPERABLE via functional testing for the purpose of establishing the next visual inspection interval.
- 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 Sp/2 1
theecification size of the4.6.L.4 or 4.6.L.5, initial lot of an additional that type of sample snubberofshall at Icast be functionally tested.
Functional testing shall continue until no additional inoperable snubbers of a particular type are found within a sampic or until all snubbers listed in Tabic 3.o-la or 3.6-lb, as applicabic, have been functionally tested.
The representative sample selected for functional testing shall include the various configurations, operating environments and the range of si:e and capacity of snubbers. The representative sample shall be selected randomly from the total population identified in Tables 3.6-la and 3.6-lb. At least 25% of the snubbers in the IIATal - UNIT 1 3. 6-10b i
9 9
3/4. 6.L SNUBBERS SURVEILLANCE REQUIREMENTS (Continued) representative sample shall include snubbers from the following three categories:
- 1. The first snubber away from each reactor vessel nozzle,
- 2. Snubbers within 5 feet of heavy equipment (valve, pump, turbine, motor,etc.),and
- 3. Snubbers within 10 feet of the discharge from a safety-relief valve.
Snubbers identified in Tables 3.6-la and 3.6-1b as "Especially Difficult to Remove" or in "fligh Radiation Zones During Shutdown" shall also be included in the representative samples . 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, snubb rs 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 falls to lockup or fails to move, i.e., frozen in place, tbc 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 inoperabic, an engineering evaluation shall be perfomed on the components which are supported by the snubber (s) . The purpose of this engineering evaluation shall be to detemine 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 capabic of meeting the designed service.
- 4. _Ilydraulic Snubbers Functional Test Acceptance Criteria The hydraulle snubber functional test shall verify that:
Dennanent 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 perfonned to qualify snubber operability for all design conditions at either the completion of their fabrication or at a subsequent date.
IIATal - UNIT 1 3. 6-10c
3/4. 6.L SNUBBERS SURVEILIM CE REQUIREMENT $ (Continued)
- 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. For snubbers specifically required to not displace under continuous load, the ability of the snubber to withstand load without displacement shall be verified.
- 5. Mechanical Snubbers Functional Test Acceptance Criteria Die mechanical snubber functional test shall verify that:
- a. The snubber operates freely over the stroke in both tension and compression.
- b. The force that initiates free movement of the snubber rod in either tension or compression is less than the specified maximum drag force. Specified maximtsn drag force is nominally five (5) pounds or one percent (11) 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 inaccessibic snubbers.
- 7. 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 perfonned 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-Ib shall be reviewed to verify that the indicated service life has not been exceeded or will not be exceeded by more than 101 prior to the next scheduled snubber service life review. If the indicated service life will be exceeded by more than 101 3rior to the next scheduled snubber service life review, the snu3ber service life shall be reevaluated or the snubber shall be replaced or tuconditioned so as to extend its service life beyond the date of the next scheduled service life review. The results of the ruevaluation 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.
IIATCll - UNIT 1 3.6-10d
TABLE 3.6-la SAFEIY RELATED HYDRAULIC ShilBBERS*
I G li1GI RADIATION
$ Sh~UBBER SYSTDI SNUBBER INSTALLED ACCESSIBLE OR ZONE ESPECIALLY DIFFICJLT y NO. (Qty.) ON, IDCATION AND ELEVATION INACCESSIBLE DURING SIUrDOWN** TO RB10VE Reactor Building (A or I) (Yes or No) (Yes or No)
Nuclear Boiler System SS-1 (1) A:. 720, E1. 150' I No No SS-2 (1) A:. 720, El. 150' I No No SS-3 (1) A:. 00, E1. 140' I No No SS-4 (1) A:. 50, E1. 128 ' I No No SS-5 (1) A:. 00, El. 140' I No No SS-6 (1) A:. 1080, El. 150' I No No SS-7 (1) A:. 900, El. 150' I No No id SS-8 (1) A:. 1600, El. 156' -
I No No i SS-9 (1) A:. 950, E1. 144 ' I No No H
SS-10 (1) A:. 900, El. 142' I No Yes 8 SS-11 (1) A:. 1000, El. 138' I No Yes SS-12 (1) A:. 850, El. 144' I No Yes SS-13 (1) A:. 820, El. 143' I No No SS-14 (1) A:. 3150, E1. 150' I No No SS-15 (1) A:. 900, E1. 145' I No No SS-16 (1) A:. 900, E1. 144' I No No SS-17 (1) A:. 1700, El. 145'-4" I No Yes SS-18 (1) A:. 1600, El . 145 ' -4" I No Yes SS-19 (1) A:. 1600, E1. 134 ' I No No SS-20 (1) A:. 1600, E1. 144' I 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.
- 4todifications to this colisin due to changes in high radiation areasimay be made without prior License Amendment provided that the revision to Table 3.6-la is included with the next License Amendment request.
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t TABLE 3.6-la .
SAFETY RELATED HYDRAULIC SNUBBERS
- I
@ HIGI RADIATION y SNUBBIR SYSTIM SNUBBER INSTALLED ACCESSIBLE OR ZONE ESPECIALLY DIFFIQJLT
~ NO. (Qty.) ON, IDCATION AND ELEVATION INACCESSIBLE DURING SHtJTDOWN** TO RB10VE Reactor Building (A or I) (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, E1. 155' I No No SS-23 (1) Az. 2780, E1. 150' I No No SS-24 (1) Az. 2700, E1. 150' I No No SS-26 (1) Az. 2750, E1. 145' I No No SS-27-30 (1) Az. 2700, El. 138' I No No SS-28 (1) Az. 2700, E1. 142' I No Yes
. SS-29 (1) Az. 2700, El. 140' I No No i SS-31 (1) Az. 2700, E1. 139' I No No E SS-32 (1) Az. 2750, E1. 125 ' I No No SS-33A (1) Az. 2850, El. 123' I No No SS-33B (1) Az. 2850, E1. 123 ' I No No SS-34 (1) Az. 2800, E1. 120' I No No SS-35 (1) Az. 2920, E1. 120' I No No SS-36 (1) Az. 3070, E1. 148' I No No SS-37 (1) Az. 3150, El. 150' I No No SS-38 (1) Az. 90, E1. 128' I No No SS-39 (1) Az. 90, E1. 128' I No No SS-4 0 (1) Az. 00, E1. 123' I No No SS-41 (1) Az. 3450, El. 155' I No No
- Sntbbers may te 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.
- 4fodifications to this coltsin die 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 regmst.
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TABLE 3.6-la ,
SAFEIY RELATED IIYDRAULIC SNUBBERS
- i
@ IIIGI RADIATION y SNUBBIR SYSTEM SNUBBER INSTALLED ACCESSIBLE OR ZONE ESPECIALLY DIFFICULT
, NO. (Qty.) ON, IDCATION AND ELEVATION INACCESSIBLE DURING SIRTTDOWN** TO PS!0VE Reactor Building (A or I) (Yes or No) (Yes or No)
RilR System (Continued)
RllRII-209 (2) 6 'NR3-16 'hRL , E1. 105' A No No Rl!Ril-210 (2) 9 'NR3-16'WRL , El. 108' A No No RIIRIl-211 (2) 7 'NR3-10 'hRL , E1. 100' A No No RIRH-212 (1) 6 'NR 3-12 ' WRL , E1. 104' A No No RiiRII-213 (1) 3 'SR2-12 'hRL , E1. 124' A No No RIRil-214 (1) 3'SR2- 2'WRL, El. 119 ' A No No RIIRil-215 (2) 3 'SR2-12 'hRL , El. 118' A No No RIIRH-216 (1) 11 'NR3-16'WRL, El. 122' A No No F RilRH-217 (1) 11'NR3-19'hRL, El. 121' A No No i RilRil-218 (1) 9'SR2-13 ' ERil, E1. 116' A No No 5
RHRil-220 (1) 4 'SR7-12 'hRL , El. 126' A No No RIRil-221 (1) 2 'SR7-10 'WRL, E1. 122' A No No RHRH-222 (2) 2'SR7-10'WRL, E1. 120' 6 122 ' A No No
, RIRil-223 (1) 1/2 'NR11 -4 'ERil, El. 125 ' A No No RilRil-224 (1) 3'SR11-7'ERII, El. 123' A No No RIRil-225 (1) 9'NR13-13'ERil, E1.117' A No No RIRil-226 (1) 12'SR11-19'hRL, El. 121' A No No RHRil-227 (1) 12'SR11-17'WRL, E1. 122' A No No RiiRil-228 (1) 3'NR13-12'hRL, E1. 124 ' A No No RIRH-229 (1) 3 'NR13-12'WRL, El. 120' A No No a Snubbers may be added to safety related systems without prior License Amendment to Table 3.6-la provided that a revision to Tabic 3.6-la is included with the next License Amendment request.
- Hodifications 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.
TABLE 3.6-la
~
I SAFETY RELATED llYDRAULIC SNUBBERS *
- E IIIGli RADIATION 1
4 SNUBBER SYSTBf SNUBBER INSTALLED ACCESSIBLE OR ZONE ESPECIALLY DIFFICULT
~ NO. (Qty.) ON, IDCATION AND ELEVATION INACCESSIBLE DURING SIRITD0hW** TO RBf0VE 4
Reactor Building (A or I) (Yes or No) (Yes or No)
RllR System (Continued)
RIRil-230 (2) 3'NR13-12'hRL, El. 116' 4 119' A No No RIRil-231 (2) 9'SR11 -17'WRL, E1. 104 ' A No No RHRII-232 (2) 9'SR11-17'WRL, El. 107' A No No RHRil-233 (1) 7'SR11-10'WRL, E1. 97' A No No RHRil-234 (1) 6'SR11-12'WRL, E1. 104' A No No RIRil-237 (2) 2 'NR 9- 3 'ERII, E1. 155 ' A No No RHRil-238 (2) 2'NR 9- 4'hRH, E1 159' A No No RIRil-239 (1) 2 'NR 9- 4'WRH, El. 160' A No No F RHRH-240 (2) 6'NR 5-25 'WRil, E1. 147' A No No i RIRH-242 (1) 3'SR 4- 4'WRil, E1. 150' A No No y RHRil-244 (2) 10'SR11- 4'ERF, E1. 121' A No No RIRH-245 (1) 10'SR11- 3' ERF, E1. 121' A No No RHRil-246 (1) 10'SR11- 3'ERF, El. 122' A No No RIIRil-249 (1) 11'SR11-10'ERF, E1.118' A No No RIIRil-250 (2) 10'NR 3- 4'ERF, El. 121' A - No No RIRil-251 (1) 10 'NR 3- 3 'ERF, E1. 119' A No No RHRII-252 (1) 10'NR 3- 3'ERF, El. 121' A No No RilRII-254 (1) 11 'NR 3-10'ERF, El. 118' A No No RilRil-279 (2) 3'SR 5- 3'hRL, E1. 116' A No No RHRil-282 (1) 1/2'SR4- 7' ERG, El.121' A No No i
i
- 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 Amendnent provided that the revision to Table 3.6-la is included with the next License Amendment request.
r TABLE 3.6-la SAFELY RELATED IIYDRAULIC SNUBBERS
- i E 11101 RADIATION G SNUBBFR SYSrBi SNUBBER INSTALLED ACCESSIBLE OR ZONE ESPECIALLY DIFFICULT e NO. (Qty.) ON, IDCATION AND ELEVATION INACCESSIBLE DURING SIRTTDOWN** TO RBIOVE Reactor Building (A or I) (Yes or No) (Yes or No)
RIIR System (Continued)
RHRH-286 (2) 3'SR 2-17'hRL, El. 116' A No No RIIRil-288 (2) 3 'NR 9- 3'WRL, E1. 116' A No No RilRil-292 (1) 4'SR 2- 6'ERil, EI. 124 ' A No No RilRil-299 (1) 4'SR13- 6'ERH, E1. 122 ' A No No RHRll-305 (1) 5'NR 3- 4 'ERH, El. 123' A No No RiiRil-306 (2) 3 'NR 3- 7'ERii, E1. 121' A No No RilRH-307 (1) 10'SR 5-17'ERH, E1. 132' A No No RHRil-309 (1) 9'SR11-18'ERil, E1.115' A No No w
RIIRH-310 (1) 9'SR11-18'ERH, E1. 124' A No No m RIIRil-312 (1) 6 'NR11 -18 'WRL , El. 124' A No No
,L RIIRH-316 (1) 10'NR11- 4'hEL, E1. 123' A No No 8 RIIRil-319 (2) 9 'NR 9-17 ' ERII, El. 136' A No No RHRll-320 (1) 4 'NR11-17' ERH, El. 90' A No No R11RH-321 (1) 3 'NR11-15 ' ERH, E1. 91' A No No RilRil-322 (2) R11-12 ' ERil, El. 89' A No No RHRH-323 (2) 5 'SR11- 9'ERil, El. 89' A No No RIIRil-324 (1) 5'JR 9- 5'hRL, El. 91' A No No RHRH-325 (1) 2'SR 9- 9'URL, E1. 90' A No No RilRil-332 (1) 2'SR 6- 2'hRil, El. 190' A No No
! RIIRil-344 (1) 1/ 2 'NR10-l'WRH , E1. 122' A No No I
- 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 mquest.
TABLE 3.6-la
- SAFETY RELATED IIYDRAULIC SNUBBERS
- i
@ llIGli RADI ATION q SNUBBER SYSTRI SNUBBER INSTALLED ACCESSIBLE OR ZONE ESPECIALLY DIFFICULT g NO. (Qty.) ON, LOCATION AND ELEVATION INACCESSIBLE DURING SIRTfDOWN** TO RB10VE Reactor Building (A or I) (Yes or No) (Yes or No)
RIIR System (Contintied)
RIIRil-348 (2) 3 'NR13-17'hRL , El . 117 ' A No No RilRil-399 (1) 6 'NR 5- 6'ERil, El. 148' A No No
, RilRil-400 (1) 6'NR 6- l 'ERil, E1. 148' A No No Plant Service Water System Sh11-283 (1) 34 'SR 2- 6 ' hRL , ' El . 101 ' A No No 1
F Standby Gas Treatment System i
H SG-II-3 5 (2) 8'NR3-14'hRB, El. 174 '-1" A No No 3 SG-II-40 (2) 7'SR9- 4 'hRB, E1. 174 ' A No No Primary Containment Purge f Inerting System i
116 ( 2 ) 8'SR3-35'WRF, El. 122' A No No 1I13 (1) 28'SR3-7'hRil, E1. 190'-9" A No No II14 (1) 21 'NR7-10' WRE, E1. 12 2' A No No 1I20 (1) 41'SR7-7'-6" ERE, E1. 122' A No No 114 0 ( 1 ) 15 'NR7-9'WRE, El. 120' A No No ll50A (1) 26'SR3-7'hRll, El. 190'-9" A No No 115 1 ( 1 ) R7-9'hRB, E1. 119'-9" A No No 115 2 ( 1 ) 2'NR7-14'hRE, El. 119'-9" A No No 115 5 ( 1 ) 4"SR7-9'WRE, El. 120' 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.
e TABLE 3.6-lb ,
SAFETY RELATED MECIIANICAL SNUBBIES*
I g IIIGli RADIATION y SNUBBER SYSTB! SNUBBER INSTALLED ACCESSIBLE OR ZONE ESPECIALLY DIFFIWLT g NO. (Qty.) ON, IDCATION AND ELEVATION INACCESSIBLE DURING SifUTD0hN** TO RBf0VE
]; Reactor Building (A or I) (Yes or No) (Yes or No) i Nuclear Boiler System B21-DFDii-16 (1) 6'SR7-27'hRF,E1.131'-5" I No Yes B21-DFIll-33 (1) 2'NR7- 2'ERE,E1.132'-2" I No Yes B21-DFDIl-43 (1) 2 '-10"SR7-3 ' ERA ,E1.134 '-5" I No Yes B21-DFI11-43 (1) 4 ' -2"SR7-3 ' ERA ,E1.13 4 ' -5" I No Yes B21 -FDIl-20 (1) Az.2620,E1.149'-9" I No Yes B21 -X28-1F19-1001 (1) Az.1800, E1.192 ' I No Yes
, B21-X28-1F19-1001A (1) Az.1800, E1.193 ' I No Yes B21-X29-1F17-1002 (1) Az. 100, E1.173 ' I No Yes F B21-X29-1F17-1003A (2) Az. 00,E1.188' I No Yes T B21-X29-1F17-1003B (2) Az. 00,E1.182' I No Yes g B21-X29-IF17-II003C (2) Az. 00, E1.177 ' I No Yes M
B21-X28-1F19-1004A (2) Az.1800,E1.177' I No Yes B21-X28-1F19-1004B (2) Az.1800, E1.182 ' I No Yes B21-X28-1F19-11004C (2) Az.1800, E1.188 ' I No Yes B21 -X29-IF24-Il002 (1) Az. 00,E1.192' I No Yes B21 -X29-1F24-11003 (1) Az. 00, E1.192 ' I > No Yes B21-X29-1F18-1004 (1) Az. 40, E1.173 ' I No Yes B21-F5-II005 (1) Az. 00, E] .197 ' I No Yes B21-F22-Il001 (1) Az. 00,E1.138' I No Yes B21-F23-II001 (1) Az. 00,E1.137' I No Yes
- Snubbers may be added to safety related systems without prior License Amendment to Table 3.6-1b
! provided that a revision to Table 3.6-1b is included with the next License Amendment request.
- Modifications to this coltan due to changes in high radiation areas may be made without prior License Amendment provided that the revision to Table 3.6-]b is included with the next License Amendment mquest.
~
TABLE 3.6-1b 7 SAFETY RELATED MECHANICAL SNUBBERS
- O HIGi RADIATION U SNUBBER SYSTBt SNUBBER INSTALLED ACCESSIBLE OR ZONE ESPECIALLY DIFFIWLT H NO. (Qty.) ON, IOCATION AND ELEVATION INACCESSIBLE DURING SIIUTDOWN** TO REMOVE Reactor Building (A or I) (Yes or No) (Yes or No)
Nuclear Boiler System Continued)
B21-F24-H001 (1) Az. 00, E1.137 ' I No Yes B21-F25-II001 (1) Az. 00, E1.137 ' I No Yes B21-F38-H005 (1) 3'-6"NR7-8' ERA,E1.133' I No Yes B21-F38-H005 (1) 6'-5" SR7-8' ERA, E1.133 ' I No Yes B21-F16-H008 (1) Az. 400,E1.190' I No Yes B21-F5-!!0 20 (1) Az. 450,E1.203' I No Yes B21-F5-H021 (1) Az. 450,E1.203' I No Yes B21-3 (1) Az. 3550,E1. 139' I No Yes F B21-5 (1) Az. 3540,E1. 139' I No Yes i B21-11003 (1) 6'SR7-10 'IRB ,E1. 13 2 ' I No Yes g B21-H014 (1) 6"SR7-8 ' ERB, E1. 132 ' I No Yes a B21-FDil-20 (1) Az. 2610, E1. 149'-10" I No Yes Recirc System B31 -X31-1F5-H001 (2) Az. 900,E1.124' I No Yes B31-X33-1F5-II001 (1) Az. 900,E1.132' I No Yes B31-X32-1F6-H001 (1) Az.2900,E1.123' I No Yes B31-X32-1F6-H002 (1) Az.2950,E1.121' I No Yes B31 -X32-IF7-H001 (1) Az. 3400, E1.116' I No Yes
- Snubbers may be added to safety related systems without prior License Amendment to Table 3.6-Ib provided that a revision to Table 3.6-1b 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 Tabic 3.6-1b is included with the next License Amendment request.
+.
- TABLE 3.6-lb .
7 SAFETY RELATED MEQlANICAL SNUBBERS
- E IIIGli RADIATION U SNUBBIR SYSTDI SNUBBER INSTALLED ACCESSIBLE OR ZONE ESPECIAI.LY EIFFIOJLT H NO. (Qty.) ON, IDCATION AND ELEVATION INACCESSIBLE DURING SilUTD0h'N** TO R1310VE I Reactor Building (A or I) (Yes or No) (Yes or No) i Recirc System (Continued)
B31-X34-1F16-H001 (1) Az.1350, E1.124 ' I No Yes B31-X28-1F16-il811 (1) Az.2170,E1.172' I No Yes B31-X28-1F16-If812 (1) Az.2170,E1.172' I No Yes B31-F3-il800 (1) Az.3150,E1.115' I No Yes B31-F14-il800 (1) Az.1800, E1.115 ' I No Yes B31-SS-B1(1) Az.1400,E1.120' I No Yes RIIR System 1 T E11-F20-11001 (1) 22'SR7-23'ERH,E1.139' I No Yes
$; E11-F20B-Il001 (1) Az.2700,E1.138' I No Yes F I E11-RIIR-405 (1) Az .1550, E1. 211 ' -2" No Yes
! Core Spray System i
E21-F1-Il001 (2) Az. 800,E1.175' I No Yes E21-F1-II002 (2) Az.2700,E1.174' I No Yes RCIC System E51-X4OB-1F4-H001 (1) Az.3300,E1.156' I No Yes t
- Snubbers may be added to safety related systems without prior License Amendment to Table 3.6-Ib provided that a revision to Tabic 3.6-1b 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 3.6-1b is included with the next License Amendment mquest.
TABLE 3.6-Ib 7 SAFETY RELATED MECl!ANICAL SNUBBFRS*
E IIIGli RADIATION U SNUBBBt SYSTIM SNUBBER INSTALLED ACCESSIBLE OR ZONE ESPECIALLY DIFFIGLT H NO. (Qty.) ON, IDCATION AND ELEVATION INACCESSIBLE DURING SIRTTDOWN** TO RB10VE Reactor Building (A or I) (Yes or No) (Yes or No)
RWW System G31-SM-5 (1) Az .1600, E1.168 ' -11 " I No Yes G31-SM-6 (1) Az .1600, E1.168 ' -11" I No Yes Equipment 6 Floor Drain System T45-F17-1001 (1) Az. 900,E1.117' I No Yes F RIIR System i
g E11-F8-ID 01 (1) 22 'SR7-23 'ERii,E1.123 ' A No No C E11-F93-11001 (1) 17 'NR7-24 ' WRL,E1.124 ' A No No E11-F93-Il002 (1) 17'NR7-24'WRL,E1.122' A No No E11-RIIRil-43 (1) 9 'NR13-13 ' ERII, E1. 116 ' A No No E11-RIIRil-313 (1) 6'NRII-18'WRL, E1. 125 ' A No No Primary Containment Purge 6 Inerting System T48-F30-Il001 (1) Az. 450,E1.120' A No No T48-F30-Il002 (1) Az. 450,E1.120' A No No
- 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 3.6-1b is included with the next License Amendment mquest.
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 load L 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 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 ir.spection whose results require'a shorter inspection interval will override the previous schedule.
When the cause of the rejection of a snubber is clearly c;tablished 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 determine if any safety-related component or system has been adversely affected by the inoperability of the snubber. The engineering evaluation shall determine whether or not the snubber mode of failure has imparted a significant effect or degradation on the supported component or system.
To provide assurance of snubber functional reliability, a representative sample of the installed snubbers will be functionally tested during plant shutdowns at 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 provide statistical bases for future consideration of snubber service life. The requirenients for the maintenance of records and the snubber service life review are not intended to affect plant operation, 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 identi fied in Tabl e 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 RADI ATION 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
- 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 protec*, ion duties, provided they comply with approved radiation pro-tection pro:edures for entry into high radiation areas.
HATCH-UNIT 1 6-20
r ENCIOSURE 3 NRC DOCKET 50-366 OPERATING LICENSE NPF-5 EDWIN I. HAICH NUCLEAR PIANT UNIT 2 REQUEST TO AMEND TECHNICAL SPECIFICATIONS The 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 though 3/4 7-15 3/4 7-11 through 3/4 7-15 3/4 7-16 3/4 7-16 3/4 7-16a through 3/4 7-16e 3/4 7-17 3/4 7-17 3/4 7-17a through 3/4 7-17m 3/4 7-18 3/4 7-18 B 3/4 7-2 B 3/4 7-2 B 3/4 7-3 B 3/4 7-3 6-18 6-18
. 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 S e rv i c e Wa te r Sy s 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 CONTAMINATION............................. 3/4 7-19 3/4.7.6 FIRE SUPPRESSION SYSTEMS Fi re Suppres sion Wa ter Sys tem. . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 7-21 S p r i n k l e r Sy s t em s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 / 4 7- 2 5 Low Pressure C02 Systems................................ 3/4 7-27 F i re Ho s e S ta t i o ns . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 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 . Sou rc es -Op e ra t i ng. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/ 4 8- 1 A.C. Sources-Shutdown................................... 3/4 8-9 3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS A. C. Di s tribu tion - Opera ti ng. . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 8- 10 A. C. Di s tribu tion - Shu tdown. . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 8- 12 D.C. Di s tribu tion - 0pera ti ng. . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 8-13 D . C . D i s tr i bu ti o n - S h u tdown . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/ 4 8- 16 A.C. Circui ts Inside Primary Containment. . . . . . . . . . . . . . . . 3/4 8-17 Primary Containment Penetration Conductor Overcurren t Protec tive 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 E L E CT R I C AL PO'.lE R SY ST EMS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 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-!
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 ROD 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
O 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 rore 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 or declare the supported system inoperable and follow the appropriate ACTION statement for that system.
SURVEILLANCE 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 Inspection Period *#
0 18 months + 25%
1 12 months I 25%
2 6 months 7 25%
3, 4 124 days 125%
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, s1he 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
9 PIsWP SYSTEMS SURVEILLANCE REQUIREMENIS (Continued)
- b. Visual Inspection Acceptance Criteria Visual inspections 'shall verify (1) that there are no visible indications of dmage or impaired OPERABILITY, (2) attachments to the foundation or supporting structure are secure, and (3) for mechanical snubbers where snubber movment can be manually induced, the snubbers shall be inspected as follows: (a) At each refueling, safety-related systes associated with the snubbers listed in Table 3.7.4-lb shall be inspected to determine if there has been a severe dynmic event. (b) In the event of a severe dynamic event, snubbers in that systs which experienced the event shall be inspected during the refueling outage to assure the snubbers have freed s of movment and are not frozen up. The inspection shall consist of verifying freeds of motion using, one of the tollowing:
(i) Manually induced snubber movment; (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 subsquently be performed according to the schedule of 4.7.4.a, but the scope of the exmination shall be limited to the safety-related systes associated with the snubbers listed in Table 3.7.4-lb. Snubbers which appear inoperable as a result of visual inspections may be determined OPERIGLE for the purpose of establishing the next visual inspection interval, providing that (1) the cause of the rejection is clearly established and rmedied 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 anubber is .found to contain less than the rquired minimm 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.
- c. Functional Tests At least once per 18 months during shutdown, a representative smple 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 smple of at least 1/2 the size of the initial lot
! of that type of snubber shall be functionally tested.
I 11/d01 - UNIT 2 3/4 7-12
PI1WP SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
Functional testing shall continue until no additional inoperable snubbers of a particular type are found within a saple or until all snubbers listed in Table 3.7.4-la or 3.7.4-lb, as applicable, have been functionally tested.
The representative smple selected for functional testing shall include the various configurations, operating environments and the range of size and capacity of snubbers. The representative smple shall be selected randmly frm the total population identified in Tables 3.7.4-la and 3.7.4-lb. At least 25% of the snubbers in the representative smple shall include snubbers frm the following three categories:
- 1. The first snubber away frm each reactor vessel nozzle,
- 2. Snubbers within 5 feet of heavy quipnent (valve, pump, turbine, motor, etc.) , and
- 3. Snubbers within 10 feet of the discharge frm a safety relief valve.
Snubbers identified in Tables 3.7.4-la and 3.7.4-lb as "Especially Difficult to Rmoie" or in "High ' Radiation Zones During Shutdown" shall also be included in the representative smple*. 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 sme 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 smpling 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 causcd by manufacturer or design ceficiency all snubbers of the s'ame design subject to the same defect shall be functionally tested.
This testing rquirment shall be independent of the rquirments stated above for snubbers not meeting the functional test critiera.
Ebr the snubber (s) found inoperable, an engineering evaluation shall be performed on the cmponents which are supported by the snubber (s) . .The purpose of this engineering evaluation shall be to determine if the cmponents supported by the snubber (s) were adversely affected by the inoperability of the snubber (s) in order to ensure that the supporta3 cmponent rmains capable of meeting the designed service.
- Pernanent or other exmptions frm functional testing for individual snubbers in those categories may be granted by the Camission only if a justifiable basis for exmption is presented and/or snubber life destructive testing was perfomed to qualify snubber operability for all design conditions at either the empletion of their fabrication or at a subsquent date IW101 - UNIT 2 3/4 7-13
i i
PLAN 1' SYSTBiS SURVEILIJAG RBDUIREMENIS (Continued)
- d. Hydraulic Snubbers Ebnctional Test Acceptance Criteria
'Ihe 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 cmpression.
- 2. Snubber bleed, or release rate, where required, is within the specified range in cmpression or tension. For snubbers specifically required to not displace under continuous load, the ability of the snubber to withstand load without displac m ent shall be verified.
- e. Mechanical Snubbers Functional Test Accept'ance Criteria
~
'Ihe mechanical snubber functional test shall verify that:
- 1. 'Ihe snubber operates freely over the stroke in both tension and cmpression.
- 2. The force that initiates free movment of the snubber rod in either tension or cmpression is less than the specified maximum drag force. Specified maximum drag force is nminally five (5) pounds or one percent (1%) of rated snubber load, whichever is greater.
- f. Unit Outage Inaccessible Snubber Inspection In the event that all inaccessible snubbers are inspected, functionally tested, and repaired as necessary durire a unit outage, and that it is thus dmonstrated 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 cmmences 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.
liA'IG - UNIT 2 3/4 7-14 1
4 PIR7f SYSTEMS SURVEIIlRCE REQUIRDENTS (Continued)
Concurrent with the inservice visual inspection performed during the first refuelirg 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 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 M - UNIT 2 3/4 7-15
TABLE 3.7.4-la SAFETY REIAl'ED HYDRAULIC SNUBBERS *
- HIGH RADIATION
' SNUBBER SYSTD1 SNUBBER INSTALLED ACCESSIBLE OR ZONT ESPECIAILY DIFFICULT
@ NO. (Oty. ) ON, LOCATION AND ELEVATION INACCESSIBIE DURING SHUTDOWN ** 'IO RD10VE y Reactor Building (A or I) (Yes or No) (Yes or No)
N 2 Ell-RHR SYSTD1 R86 (1) 8' NR19 - l' ERJ, El. 121'-5" A No Ib R88 (1) 10' NRl7 - 3' WRJ, El. 119'-3" A No No R90 (1) R15 - 3' ERH, El. 119'-3" A No Ib R93 (2) 8' SRl4 - 11 ERF, El. 118'-5" A No No R94 (1) 8' SR14 - 10' ERF, El. 118'-5" A No Ib R98 (2) 10' SR19 - l' ERJ, El. 121'-5" A No Ib R100 (1) 10' SR21 - 3' hPJ, El. 119'-3" A No Ib R101 (1) 12' SR21 - 5' WRJ, El. 119'-3" A No No R R102 (1) R23 - 3' ERH, El. 119'-3" A No Eb
- R128 (1) 6' NR23 - 16' ERF, El. 123'-5" A No No y R129 (2) 18' SR21 - 16' ERF, El. 123'-5" A No Ib 5 R146 (2) 5' SR21 - 8' WRL, El. 120'-5" 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. 96' A lb lb R238 (2) 12' SR15 - 3' WRL, El. 107' A lb No R241 (2) 3' NR23 - 9' WRL, El. 96'-10" A No hb R245 (2) 12' NR23 - 3' WRL, El. 107' A No No
- Snubbers may be added to safety related systens without prior License Imendment to Table 3.7.4-la provided that a revision to Table 3.7-4-la is included with the next License Imendment request.
- Modifications to this coltan 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 leendment request.
TABLE 3.7.4-la -
,,. SAFETY RELATED HYDRAULIC St? BBERS*
HIGI RADIATION 7 SNUBBER SYSTD1 SNUBBER INSTATJFn ACCESSIBLE OR ZONE ESPIIIALLY DIFFICULT to. (Oty.) ON, IOCATION AND ELEVATION INACCESSIBLE DURING SHUIDOWN** 'IO RBIOVE h Reactor Building (A or I) (Yes or No) (Yes or No)
H N
2 Ell-RHR SYSTDi (Continued)
R250 (1) 11' SR14 - 15' WRL, El. 119'-2" A No No R251 (2) 11' SR14 - 15' hRL, El.119'-2" A No No R252 (1) 15' SR14 - 15' WRL, El. 118'-6" A No No R253 (1) 15' SRl4 - 15' WRL, El. 118'-6" A lb No R254 (1) 17' SRl4 - 17' WRL,'El. 112'-6" A. No No R256 (1) 17 ' SR14 - 17 ' hRL, El. 112 ' -6" A No Ib R258 (1) 22' SR14 - 13' hEL, El. 99'-6" A No No R264 (1) 21' SR14 - 9' hRL, El. 103'-11" A No Ib y R267 (2) 15' SRl4 - 3' KEL, El. 100'-11" A No Ib 3 R268 (1) 11' NR24 - 15' KRL, El. 119'-2" A No No y R269 (2) 11' NR24 - 15' hTtL, El. 119 '-2" A No Ib 4 R270 (1) 15' NR24 - 15' KRL, El. 118'-6" A No No p R271 (1) 15' Nh24 - 15' WRL, El. 118'-6" A No No R272 (1) 17 ' NR24 - 17 ' hEL, El . 112 ' -6" A No No R274 (1) 17' NR24 - 17' h3L, El. 112'-6" A No Ib R276 (1) 22' NR24 - 13' KEL, El. 99'-6" A No No R282 (1) 21' SR24 - 11' hPL, El. 103'-11" A No No R285 (2) 15' NR24 - 3' hRL, El. 100'-11" A No No R315 (2) 10' NR19 - 6' ERJ, El. 123' A No No R374 (2) 23 ' SR14 - 15 ' hPL, El . 105 '-3" A No No
- Snubbers may be added to safety related systens without prior License Anendment to 'Ibble 3.7.4-la provided that a revision to Table 3.7-4-la is included with the next License Amendment rquest.
- 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 rquest.
g' TABLE 3.7.4-la g SAFETY RELATED HYDRAULIC SNUBBERS *
' HIGI RADIATION SNUBBER SYSTEM SNUBBER INSTAurn ACCESSIBLE OR ZONE ESPIIIALLY DIFFICULT
@ NO. (Oty.) ON, LOCATION AND ELEVATION INACCESSIBLE DURING SHUIDOWN** 'IO REMOVE Q (Yes cr No) g Reactor Building (A or I) (Yes or No) 2E11 - RHR SYSTEM (Continued)
R375 (2) 23' SRl4 12' hTIL, El. 107'-2" A No Ib R376 (1) 23' SR14 - 12' WRL, El. 107'-2" A No No R377 (2) 23 ' NR24 - 15 ' KE, El. 105 ' -3" A No Ib R378 (2) 23' NR24 - 12' hE, El.107'-2'l A tb tb R379 (10 23 ' NR24 - 12' hE, El. 107 '-2 A No Ib R 2 Ell - RHR SERVICE WATER SYSTEN n
A No
? R 15 (2) 7' SR21 - 11' ERH, El. 115' A
tb tb g R 23 (2) 7' NR24 - 11' ERH, El. 115' tb o-2E21 CORE SPRAY SYSTEM R 35 (1) 8' SRl4 - 6' WRL, El. 95' A No Ib R 40 (1) 7' SR14 - 31' WRL, El. 90' A No tb R 53 (2) 10' SRl4 - 6 ' WRL, El. 102' A lb lb R 72 (2) 10' NR24 - 6 ' WRL, El. 103'-5 A lb No R 80 (1) 8' NR24 - 6' WRL, El. 95' A No No R 87 (1) 7' NR24 - 6' WRL, El. 90' A No No si
?
- Snubbers may be addea to safety related systens without prior License Anendnent to Table 3.7.4-la provided that a revision to Table 3.7-4-la is included with the next License Amendnent request.
- Modifications to this coltunn due to changes in high radiation areas may be made without prior License Anendment provided that the revision to Table 3.7.4-la is included with the next License Anencanent request.
TABLE 3.7.4-la SAFETY RELATID HYDRAULIC SNUBBERS
- O 7 HIGi RADIATION SNUBBER SYSTEM SNUBBER INSTATJFn ACCESSIBIE OR ZONE ESPECIALLY DIFFICULT ON, IOCATION AND ELEVATION INAOCESSIBLE DURING SIKTII]OWN** 'IO REMOVE h NO. (Oty.)
(Yes or Ib) (Yes or No)
H Reactor Building (A or I) l M 2G41 - FUEL IOOL COOLIIG & CLEANUP SYSTEM Rll4 (2) 20 ' SR19 - 17 ' ERF, El. 193 ' -3" A No Ib 2T46-SGIS SYSTH4 R 65 (2) 6' NR24 - 9' WRB, El. 197'-10" A No !b R 66 (10 2' NR24 - 9' WRB, El. 185'- 4" A No No R 67 (1) 2' NR24 - 9' WEB, El. 180'- 3" A No No y R 68 (2) 6' NR24 - 9' ERA, El. 197'-10 A No No
) R 69 (1) 2' NR24 - 9' ERA, El. 185'-4" A No lb y R 70 (2) 2' NR24 - 9' ERA, El. 178'-6' A tb No Y
R 2T48 - CONTAIIMENT PURGE & INERTING SYSTEM Rll (1) 42' NRl9 - 64' ERB, El. 175'-7" A No Ib R12 (1) 42' NRl9 - 64' ERB, El. 185'-10" A tb No R13 (1) 42' NR19 - 64' ERB, El. 185'-10" A No Ib R14 (2) 20' NR19 - 64' ERB, El. 193' A tb No R15 (1) 13' NR19 - 64' ERB, El. 193' A No No R49 (2) 26' SR19 - RB, El. 120'-4" A No Ib R50 (2) 24' SR19 - RB, El. 120'-4" A No Ib R51 (1) 48' SR19 - 9' ERB, El. 120'-4" A tb tb R55 (1) 66' SR19 - 8' ERB, El. 130'-3" A No Ib RS6 (1) 66' SR19 - 8' ERB, El. 130'-3" A No Ib
- Snubbers may be added to safety related systens without prior License teendnent 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 colunn due to changes in high radiation areas may be made without prior License Amendnent provided that the revision to Table 3.7.4-la is included with the next License Imendment reluest.
i TABLE 3.7.4-la SAFEIY RELATED HYDRAULIC SNUBBERS
- HICH RADIATION SNCBBER SYSTEM SNUBBER INSTAU Fn ACCESSIBLE OR ZONE ESPECIALLY DIFFICULT E NO. (Oty.) ON, IOCATION AND ELEVATION INILCESSIBIE DURING SETIDOm** 'IO RmOVE 4 Reactor Building (A or I) (Yes or No) (Yes or tb)
N 2B31 - REAC'IOR RECIRCULATION SYSTEM SSAl (1) Az 3150, El. 117' I No tb SSA2 (1) Az 3280, El. 125' I No Yes SSA3 (1) Az 3020, El. 125' I No Yes SSA4 (1) Az 3280, El. 131' I No Yes SSA5 (1) Az 3010, El. 131' I tb tb SSA6 (1) Az 3150, El. 137' I No Yes SSA7 (1) Az 0180, El. 124' I No Yes SSA8 (1) Az 3420, El. 123' I No Yes M SSA12 (1) Az 2550, El. 129' I No No SSA13 (1) Az 2850, El. 129' I No Ib
'd SSA14 (1) Az 2700, El. 121' I No No 5
" SSA15 (1) Az 3230, El. 144' I No Yes SSA16 (1) Az 2170, El. 144' I No Yes SSA17 (1) Az 170 0, El. 125' I tb Yes SSA19 (1) Az 2700, El. 138' I tb Yes SSA20 (1) Az 2700, El. 138' I No Yes SSA21 (1) Az 00, El. 140' I tb Yes SSA22 (1) Az 00, El. 140' I tb Yes SSBl (1) Az 1350, El. 117' I No No SSB2 (1) Az 1480, El. 125' I No Yes
- Snubbers may be added to safety related systens without prior License teendnent to Table 3.7.4-la -
provided that a revision to Table 3.7-4-la is included with the next License Amendment reauest.
- Modifications to this colunn due to changes in high radiation areas may be made without prior License Amendtent provided that the revision to Table 3.7.4-la is included with the next License Inencreent rquest.
~'*
TABE 3.7.4-la SAFEfY REIATED HYDRAULIC SNUBBERS
- 9 8 HIW RADIATION G SIM BER SYSID4 SNUBBS INSTAum ACCESIBE OR ZONE ESPECIAILY DIFFIG LT ID. (Oty.) ON, IOCATION AND ELEVATION INAOCESSIBLE DURING SFUIDOWN** 'IO REMOVE Q (Yes or tb) (Yes or Ib) y Reactor Building (A or I) 2B31 - REAC'IOR RBCIRCULATION SYSTEM (Continued)
SSB3 (1) Az 1220, El. 125' I tb Yes SSB4 (1) Az 1480, El.' 131' I tb Yes SSB5 (1) Az 1220, El. 131' I No Ib SSB6 (1) Az 1350, El. 137' 'I No Yes SSB7 (1) Az 1980, El. 124' I No Yes SSB8 (1) 72 162 0 , El. 123' I No Yes SSB12 (1) Az 0750, El. 129' I re Ib R SSB13 (1) Az 1050, El. 129' I No Ib
- SSB14 (1) Az 0900, El. 121' I No Ib y SSB15 (1) Az 1430, El. 144' I tb Yes 5 SSB16 (1) Az 0370, El. 144' I No Yes O
SSB17 (1) Az 090 0, El. 126' I No Yes SSB19 (1) Az 0900, El. 138' I lb Yes SSB20 (1) 72 0900, El. 140' I No Yes SSB21 (1) Az 1800, El. 140' I , No Yes SSB22 (1) Az 1800, El. 140' I tb Yes
- Snutbers may be added to safety related systems without prior License Ircen&ent to Table 3.7.4-la provided that a revision to Table 3.7-4-la is included with the next License Amendment re]uest.
- Fxxlifications to this coluen due to changes in high radiation areas may be made without prior Licmse Icen&ent provided that the revision to Table 3.7.4-la is included with the next Ilcense Icencicent re]uest.
l T7JiLE 3.7.4-lb U SAFEIY REIRIID MEIJW;ICAL St;UBBERS*
l
~
HIGII RADIATION St.'UBBER SYSI'D4 St;UBBER INSTATJFn ACCESSIBLE OR 2Ct2: ESPIrIALLY DIFFIQJLT l
- 3 I;O. (Oty.) 0;, IOCATION A'D ELEVATION INTCCESSIBLE DURING SIKTIDOkZ;** 'IO RE>OVE y Reactor Buildirn (A or I) (Yes or I;o) (Yes or I;o) w 2B21-7.'.rlear Boiler System PS-R34 (1) Az. 1100 El. 150'-4" I tb Yes PS-R35 (1) Az. 1450 El. 150'-1" I 'd Yes i PS-R36 (1) Az. 1450 El. 150'-1" I tb Yes l
FS-R37 (2) Az. 1450 El. 150'-1" I !b Yes FS-R38 (2) Az. 0720 El. 167' I tb Yes FS-R39 (2) Az. 0950 El. 150'-2" I ib Yes PS-R41 (1) Az. 10CP El. 150'-2" I Ib Yes MS-R42 (1) Az. 1400 El. 150'-1" I tb Yes M
MS-R43 (1) Az. 1300 El. 150'-1" I Ib Yes MS-R44 (2) Az. 1400 El. 150'-1" I No Yes 7 MS-R45 (1) Az. 2500 El. 155'-5 1/8" I No Yes G PS-R46 (1) Az. 2500 El. 155'-S 1/8" I No Yes MS-R47 (1) Az. 2200 El. 150'-1" I f;o Yes PS-R48 (1) Az. 2200 El. 150'-1" I tb Yes MS-R49 (2) Az. 2880 El. 167' I No Yes PS-R50 (2) Az. 2700 El. 150'-2" I tb Yes FS-RS2 (1) Az. 2650 El. 150'-2" I No Yes FS-R53 (2) Az. 2350 El. 150'-1" I lb Yes PS-R54 (1) Az. 2350 El. 150'-1" I No Yes MS-R55 (1) Az. 2350 El. 150'-1" I tb Yes
- Saubbers ray be ailed to safety related systems without prior License Amerdment to Table 3.7.4-lb provided that a revision to Table 3.7-4-lb is irclu3ed with the next License knenchent regaest.
- c'bdifications to this colu:n due to charr3es in high radiation areas may be made without prior License Amendment provided that the revision to Table 3.7.4-lb is inclu3ed with the next License Amend.wnt regaest.
[
TABLE 3.7.4-lb -
- p SAFEIY ICATrD KtD%NICAL St.1EBERS*
l G 9 HIGH RADIATIO 3 STJEER SYSIU4 STJ3BER II:STAIlID ACCESSIBLE OR ZOE ESPECIALLY DIFFIQJLT e IX). (Ctv.) 01, IDCATIO3 AND EIEVATIO3 I?;7CCESSIBLE IXJRI?C SHITIDOR2** "O RDC/E 5 Reactor Buildiry (A or I) (Yes or I;o) (Yes or I;o)
-4 PJ 2B21-!belear Boiler System (Continue 3)
FR/-R36 (1) Az. 2300 El. 137' I No Yes MSRV-R37 (1) Az. 2300 El. 131'-8" I ?b Yes PSI-R33 (1) Az. 2300 El. 133'-3" I !b Yes MSif/-R40 (1) Az. 2300 El. 121'-9" I Tb Yes PSI-R41 (1) Az. 2250 El. 121'-9" I tb Yes FM-R45 (2) Az. 1650 El. 119'-1" I !b Yes MSRV-R46 (2) Az. 2500 El. 149'-10" I ?b Yes Z
MSRV-R50 (1) Az. 2700 El. 116'-8" I tb Yes FRJ-RS2 (2) Az. 1050 El. 152' I tb Yes 7 MSRV-R53 (1) Az. 1050 El. 148'-9" I Ib Yes C
MSi?I-RS4 (1) Az. 0300 El. 137'-1" I tb Yes FRJ-R56 (1) Az. 0700 El. 130'-7" I !b Yes FEl-R57 (1) Az. 0700 El. 134'-6" I No Yes PSRV-R58 (1) Az. 0700 El. 125' I lb Yes PSRV-R59 (2) Az. 1250 El. 153*-7" I tb Yes PSRV-R60 (2) Az. 1200 El. 152' I ?b Yes MSRV-R62 (1) Az. 0900 El. 131'-2" I ib Yes MSRV-R63 (1) Az. 0900 El. 133'-3" I !b Yes MSRV-R64 (1) Az. 0900 El. 125'-5" I ?b Yes FRJ-R65 (1) Az. 1000 El. 120'-6" I !b Yes
- Snuncers r.3y be sided to safety related systecs witbut prior License Are:rt:ent to Table 3.7.4-lb provided that a revision to Table 3.7-4-lb is incitr3ed with the next License A erdwnt request.
- 41odifications to this coltz:n due to changes in high radiation areas may be made witMut prior License Icxnt ent provided that tre revision to Table 3.7.4-lb is ircluded with the next License Aerd ent regrst.
t .
TABLE 3.7.4-lb SAETIY RE[ATD MDIANICAL StKEBERS*
, HIGH RADIATION
, SNCBBER SYSITM SNrRRFR INSTATIrn AOCESSIBIE OR 20tE ESPECIALLY DIETICIILT U !D. (Otv.) (N, IOCATION APO EIEVATION INAOCESSIBLE DURIPC SIKTIDObtI** 'IO REMA'E Reactor Building (A or I) (Yes or No) (Yes or I;o) 2B21-?bclear Boiler System (Continued) .
MSRV-R67 (2) Az. 2350 El. 145'-11" I tb Yes MSRV-R68 (1) Az. 2350 El. 146' I No Yes MSRV-R69 (1) Az. 2350 El. 140'-6" I tb Yes MSRV-R70 (1) Az. 2350 El. 137' I No Yes MSRV-R71 (1) Az. 2450 El. 133'-3" I No Yes ERV-R72 (1) Az. 2450 El. 133'-3" I No Yes MSRV-R73 (1) Az. 2450 El. 130'-4" I No Yes v MSRV-R75 (1) Az. 2550 El. 153'-8" I No Yes i ) MSRV-R76 (1) Az. 2500 El. 145'-11" I No Yes l
y MSRV-R77 (1) Az. 2500 El. 137' I No Yes
! A MSRV-R78 (1) Az. 2500 El. 135' I No Yes l Bf PGRV-R79 (1) Az. 2500 El. 132'-10" I No Yes I
MSRV-R80 (1) Az. 2500 El. 132' I No Yes MSRV-RS2 (1) Az. 0950 El. 148' I No Yes MSRV-R83 (2) Az. 0950 El. 144'-11" I No Yes MSRV-R84 (1) Az. 0900 El. 137'-1" I No Yes MSRV-R88 (1) Az. 0659 El. 127'-5" I No Yes MSRV-RB3 (1) Az. 0659 El. 125' I No Yes MSRV-R90 (1) Az. 115P El. 146' I No Yes
- Sn*-Nrs 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 ircluded with the next License A1:erdnent request.
- Modifications to this coltaan due to changes in high radiation areas may be made without prior License Amentnent provided that the revision to Table 3.7.4-lb is included with tre next License A::vmdment recpest.
. - _ m . _ . . . . _ , - . - - _ _ - _ _ . - - - - . _ -- _ - - _ - . . . - . - - - - . - . - . . ~ _ _ . - . . _ _ _ _ . . - . - - - _ - - -
O
~*
TABLE 3.7.4-lb SAFE 1Y REIATED MEGANICAL SNUBBERS
- i HIGI RADIATION g SNUBBER SYSITM SNUBBER INSTAUEn ACCESSIBLE OR ZONE ESPECIALLY DIFFIWLT q NO. (Oty.) ON, IOCATION AND ELEVATION INAOCESSIBLE DURING SIRJI'DCkN** 'IO REMOVE Reactor Buildina (A or-I) (Yes or No) (Yes or No) 2B21-Nuclear Boiler System (Continued)
MSRV-R91 (1) Az. 110 El. 137'-3" I No Yes MSRV-R92 (1) Az. 1100 El. 132'-3" I No Yes MSRV-R93 (1) Az. 1100 El. 125'-5" I No Yes MSRV-R94 (1) Az. 0950 El. 119'-7" I No Yes MSRV-R96 (2) Az. 2850 El. 152' I No Yes MSRV-R97 (1) Az. 2850 El. 151'-6" I No Yes MSRV-R98 (1) Az. 2900 El. 150'-1" I No Yes u MSRV-R99 (2) Az. 3200 El. 150' I No Yes 3 MSRV-R100 (1) Az. 3300 El. 145' I No Yes y MSRV-R101 (1) Az. 3300 El. 140' I No Yes y MSRV-R103 (1) Az. 3400 El. 129' I No Yes o MSRV-R104 (2) Az. 3400 El. 125'-7" I No Yes MSRV-R105 (2) Az. 0750 El. 152' I No Yes MSRV-R106 (1) Az. 0750 El. 151'-6" I No Yes MSRV-R107 (1) Az. 0600 El. 150' I No Yes MSRV-R108 (2) Az. 0300 El. 150' I No Yes MSRV-R109, (1) Az. 0300 El. 150' I No Yes MSRV-R110 (1) Az. 0250 El. 137' I No Yes MSRV-R111 (1) Az. 0220 El. 132'-3" I No Yes MSRV-Rll3 (1) Az. 2700 El. 153'-8" 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 charges 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 MBCHANICAL SNUBBERS
- HIGI RADIATION
' SNUBBER SYSTEM SNUBBER INSTArLEn ACCESSIBLE OR ZONE ESPECIALLY DIFFIQJLT
@ NO. (Qty.) ON, LOCATION AND ELEVATION INATESSIBLE DURING SHUPDOWi** 'IO IMNE y Reactor Building (A or I) (Yes or No) (Yes or No)
N .
2B21-Nuclear Boiler System (Continued)
MSRV-Rll4 (1) Az. 2700 El. 145'-11" I No Yes MSRV-Rll5 (1) Az. 2700 El. 137' I No Yes MSRV-Rll6 (1) Az. 2700 El. 133'-3" I No Yes MSRV-Rll8 (1) Az. 2700 El. 125'-5" I No Yes MSRV-R119 (1) Az. 2700 El. 120'-6" I No Yes MSRV-R121 (2) Az. 2300 El. 140'-7" I No Yes RFW-20 (2) Az. 1000 El. 149'-7" I No Yes RFW-31 (2) Az. 2600 El. 149'-7" I No Yes R S67-H10 (1) Az. 1670 El. 134' I No Yes
- S67-Hil (1) Az. 1140 El. 135' I No Yes 78 S67-H12 (1) Az. 0450 El. 136' I No Yes t; S67-H13 (1) Az. 0320 El. 136' I No Yes O-S67-H14 (1) Az. 0220 El. 136' I No Yes S128-H4 (1) Az. 2400 El. 192' I No Yes S143-H1 (1) Az. 0400 El. 195' I No Yes S143-H2 (2) Az. 0300 El. 189' I ,, No Yes S143-H3 (2) Az. 0300 El. 184' I No Yes S143-H4 (2) Az. 0300 El. 179' I No Yes S143-HS (1) Az. 0300 El. 196' I No Yes S146-H6 (1) Az. 0150 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 inclix3ed with the next License Amendment request.
- Modifications to this column due to changes in high radiation areas may be made without prior License Amerriment provided that the revision to Table 3.7.4-lb is included with the next License Amendment request.
I TABLE 3.7.4-lb SAFETY RELATED MEGANICAL SNUBBERS *
) 7 HIGH RADIATION g SNUBBER SYSTEM SNUBBER INSTAnrFn ACCESSIBLE OR ZONE ESPECIALLY DIFFIQJLT g NO. (Oty.) ON, IOCATION AND ELEVATION INACCESSIBLE DURING SIRTIDOIE** 'IO REMOVE 3
, N Reactor Building (A or I) (Yes or No) (Yes or No) 1 2B21-Nuclear Boiler System (Continued)
S148-H1 (1) Az. 2120 El. 195' I No 'Yes ,
S148-H2 (2) Az. 2100 El. '.89' I No Yes j S148-H3 (2) Az. 2100 El. 184' I No Yes ,
3 S148-H4 (2) Az. 2100 El. 179' I No Yes j S158-H5 (2) Az. 2120 El 196' I No Yes 2B31-Reactor Recirculation System S14-H1 (1) Az. 0170 El. 125' I No Yes y S17-H1 (1) Az. 1980 El. 126' I No Yes
,L S18-H1 (1) Az. 0650 El. 126' I No Yes y S24-H1 (1) Az. 3090 El. 123' .
I No Yes i S40-H1 (1) AZ. 1100 El. 120' I No Yes S43-H1 (1) Az. 1550 El. 187' I No Yes i 2 Ell-RHR System R338 (1) Az. 00 El. 145'-8" I No Yes j R339 (1) Az. 3550 El. 154'-6" I No Yes 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.
- Modifications to this column dae to charxjes 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 *
[ HIGH RADIATION g SNUBBER SYSTEM SNUBBER INSTATJFn ACCESSIBLE OR ZONE ESPECIALLY DIFFIQJLT p NO. (Qty.) ON, IDCATION AND ELEVATION INATESSIBLE DURING SHUTDOkN** 'IO REMOVE Reactor Building (A or I) (Yes or No) (Yes or No) 2 Ell-RHR System (Continued)
R340 (1) Az. 3420 El. 154'-6" I No Yes R342 (1) Az. 3370 El. 139'-10" I No Yes R350 (1) Az. 0800 El. 150'-1" I No Yes R351 (2) Az. 3050 El. 150'-1" I No Yes R352 (2) Az. 3250 El. 150'-1" I No Yes R353 (1) Az. 3280 El. 145'-11" I No Yes R354 (1) Az. 3280 El. 145'-11" I No Yes v R355 (1) Az. 2850 El. 150'-1" I No Yes
) R356 (2) Az. 0550 El. 150'-1" I No Yes y R357 (2) Az. 0370 El. 150'-1" I No Yes
,L R358 (1) Az. 0330 El. 145'-11" I No Yes X R359 (1) Az. 0380 El. 145'-11" I No Yes R368 (1) Az. 0200 El. 206'-3" I No Yes 2E21-Core Spray System R59 (2) Az. 0900 El. 177' -6" I No Yes R98 (2) Az. 2670 El. 177'-6" 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 ircluded 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 irrluded with the next License Amendment request.
TABLE 3.7.4-lb
- SAFETY REUdED MECHANICAL SNUBBERS
- O HIGH RADIATION
' SNUBBER SYSTD4 SNUBBER INSTAUFn ACCESSIBLE OR ZONE ESPEEIALLY DIFFIGLT
, NO. (Qty.) ON, IDCATION AND ELEVATION INACCESSIBLE DURING SHUIDOWN** 'IO RD40VE Reactor Building (A or I) (Yes or No) (Yes or No)
N 2E41-HPCI System R110 (1) Az. 0180 El. 145' I No Yes d
Rlll (1) Az. 0190 El. 145' I No Yes Rll2 (1) Az. 0120 El. 145' I No Yes Rll3 (2) Az. 0110 El. 145' I No Yes Rll4 (1) Az. 0460 El. 145' I No Yes Rll5 (2) Az. 0560 El. 145' I No Yes 2E51-RCIC System M
i e Rll4 (1) Az. 2130 El. 145'-11" I No Yes
? Rll6 (1) Az. 1860 El 142'-6" I No Yes
, [ Rll7 (1) Az. 1860 El. 14 2'-6" I No Yes ca 2G31-RWW System Rl66 (1) Az. 0130 El. 149' I ., No Yes Rl67 (2) Az. 0170 El. 156' I No Yes R168 (1) Az. 0170 El. 162' I No Yes
- Snubbers may be added to safety related systems without prior Licensd 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.
a TABLE 3.7.4-lb SAFETY REIATED MBOIANICAL SNUBBERS
~ NO. (Oty.) ON, IOCATION AND ELEVATION INACCESSIBLE DURING SHIT 11XAN** 'IO REMOVE N Reactor Building (A or I) (Yes or No) (Yes or No)
N 2 Ell-RHR System H700 (1) 14' SRl4-18'ERF, El. 123'-3" A No No H702 (1) 14' SR14-ll'ERF, El. 119'-3" A No No H703 (1) 8' SRl4-5'ERF, El. 118'-10" A No No H705 (1) 8' SR14-13 'ERF, El. 118'-9" A No No H706 (1) 8' SR14-13'ERF, El. 118'-5" A No No H707 (1) 14' NR24-18'ERF, El. 119'-3" A No No H708 (1) 14' NR24-5'ERF, El. 119" A No No y H709 (1) 11' NR24-9'ERF, El. 118'-3 A No No j
) H710 (1) 14' NR24-13'ERF, El. 119'-3" A No No y H712 (1) 11' NR24-ll' ERF, El. 118'-2" A No No
,L H713 (1) 42' NR24-52' ERF, El. 121'-5" A No No 3! H714 (2) 32' SR14-20' WRL, El.90' A No No H715 (2) 32' SR14-20' WRL, El. 90' A No No R91 (2) 38'SR14-23'WRL, El.119' A No No j
R92 (2) 14'SR14-22'WRF, El. 119' A No No R103 (2) 35'SR14-26'WRL, El.119' A '
No No R105 (2) 9'NR24-ll'WRF, El. 118' A No No R106 (1) 9'NR24-ll'WRF, El.118' A No No
- R123 (1) l'SR22-13'WRH, El. 169' A No No I
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 Amendment request.
i M
- TABLE 3.7.4-lb k SAFETI RELATED MEDIANICAL SNUBBERS
- a -
i HIGI RADIATION g; SNUBBER SYSIDI SNUBBER INSTAT.rEn ACCESSIBLE OR ZONE ESPECIALLY DIFFIWLT y NO. (Qty.) ON, LOCATION AND ELEVATION INACCESSIBLE DURIFE SHUrDOWi** 'IO REbKNE Reactor Building (A or I) (Yes or No) (Yes or No) l 2 Ell-RHR System (Continued)
R125 (1) 6'SR22-12'WRF, El. 167' A No No R221 (1) 53'-5" SR14-12'-5" WRL, El. 90' A No No R222 (1) 53'-5" SR14-12'-5" NRL, El. 90' A No No R221 (1) 53'-5"SR14-12'-5"WRL, El. 90' A No No R222 (1) 53'-5"SR14-12'-5"WRL, El. 90" A No No R224 (1) 24'SR14-29'WRL, El. 90' A No No R225 (1) 29'SR14-29'WRL, El. 90' A No No ta R226 (2) 23'SR14-27'WRL, El. 90' A No No 3 R228 (1) 18'SR14-23'WRL, El. 90' A No No u R229 (1) 28'NR24-29'WRL, El. 90' A No No e' . R230 (1) 25'SR14-30'WRL, El. 90' A No No M R233 (2) 23 'NR24-28'WRL, El. 90' A No No R235 (1) 13'SR14-13'WRL, El. 121' A No No R240 (1) 24'NR24-28'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 No 3 R292 (2) 36'SR14- l'WRL, El. 118' A No No R295 (2) 25'NR24-28'WRL, El. 120' A No No R297 (2) 36'SR14-21'WRL, El. 118' A No No
- 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 Ameniment 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 *
, HIGI RADIATION g SNUBBER SYSTEM SNUBBER INSTAUEn ACGSSIBLE OR ZONE ESPECIALLY DIFFIQJLT p NO. (Oty.) W , IDCATION AND ELEVATION INACCESSIBLE DURING SHUIDOkN** 'IO REMOVE d
N Reactor Building (A or I) (Yes or No) (Yes or No) 2 Ell-RHR System (Continued) i R326 (1) 18'SR19-17'ERH, El. 135'-9" A No No R327 (1) 18'SR19-17'ERH, El. 135'-9" A No No i R382 (1) 9'NR23-12'ERF, El. 135' A No No S4-H1 (1) 19'SR19-25'WRL, El. 123' A No No 2E21-Core Spray System l w H702 (1) 5'NR24-37'WRL, El. 95' A No No 3 H703 (1) 10'NR24-20'WRL, El. 95' A No No y H706 (1) 5'SR14-31'WRL, El. 95' A No No l_. H707 (1) 10'SR14-20'WRL, El. 95' A No No
- C' H37 (2) 10'SR14-4' WRL, El. 97'-6" A No No R42 (2) 9'SR14-41'WRL, El.90 A No No i R82 (2) 10'NR24-4' WRL, El. 97' A No No
- R90 (2) 9'NR24-41'WRL, El. 90 A No No R107 (2) 32'SR19-19'-6"WRL, El. 123'-2" A '
No No R110 (1) 6'NR24-4'WRL, El. 102'-9" A No No 2E32-MSIV Leakage Control System I Sll-H1 (1) 21'NR21- 5'WRB, El. 118' A No No S17-H1 (1) 20'NR21-21'NRB, El. 118' A No No
- 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 ircluded with the next License Amendment request.
- TABLE 3.7.4-lb SAFETY RELATED MBCHANICAL SNUBBERS
- 7 HIGH RADIATION SNUBBER SYSTEM SNUBBER INSTALTEn ACCESSIBLE OR ZONE ESPECIALLY DIFFICULT h NO. (Qty.) CN, IOCATION AND ELEVATION INAOCESSIBLE DURIE SIRTIDMJ** 'IO R940VE Reactor Building (A or I) (Yes or No) (Yes or No) 2E32-MSIV Leakage Control System (Continued)
S18-H1 (1) 21'NR21- 4'WRB, El. 119' A No No S19-H1 (1) 21'NR21- 5'WRB, El. 117' A No No 2E41-HPCI System H702 (1) 5'NR24-24'ERF, El.90' A No No R19 (1) 14'SR24-25' ERG, El. 112'-5" A No No u R20 (2) 14'SR24-7' ERG, El. 112'-5" A No No 3 R21 (1) 8'NR24-26'ERF, El. 112'-6" A No No y R22 (2) 8'NR24-9'ERF, El. 121'-9" A No No k R23 (2) 15'NR24-3'ERF, El. 121'-3" A No No W R45 (2) 23'NR25-5'WRL, El. 116'-6" A No No R50 (2) 10'NR25-4'EFG, El.109'-6" A No No R55 (2) 10' NR25-24'WRL, El. 95'-9" A No No R73 (2) 57' SR19-58'WRH, El.120-8" A No No R74 (1) 92'SR19-59'WRH, El. 120' A
- No No R78 (2) 95'SR19-38'WRH, El. 115'-8" A No No R80 (2) 95'SR19-38'WRH, El. 101'-6" A No No R82 (2) 66'SR19-4 7'WRH, El. 122'-6" A No No R91 (2) 12'NR19-2'ERH, El. 122' A No No R93 (1) 46'NR19-4'WRH, El. 123' A No No
- Snubbers may be added to safety related systems without prior License Ameninent 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 3.7.4-16
] ;;:: SAFETY RELATED MEDIANICAL SNUBBERS
- _ HIGI RADIATION i SNUBBER SYSTEM SNUBBER INSTATJFn ACCESSIBIE OR ZONE ESPECIALLY DIFFIOJLT 1 g NO. (Qty.) 01, IDCATION AND ELEVATIOI INAOCESSIBLE DURING SHU'IDOW** 'IO REMOVE A Reactor Building (A or I) (Yes or No) (Yes or No) l N
2E51-RCIC System R40 (2) 26'SR14-57'WRF, El. 89'-5" A No No l
R41 (2) 25'SR14-56'WRF, El. 97'-9" A No No R43 (1) 22'SR14-53'WRF, El. 97'-3" A No No R44 (1) 22'SR14-53'WRF, El. 97'-3" A No No R58 (2) 92'SR17-49' ERA, El. 106'-3" A No No R70 (1) 25'NR17-14' ERA, El.91'-6" A No No R110 (1) l'NR17-7' ERA, El. 119'-10" A No No j R705 (1) 53' SR14-10' ERA, El. 89'-6" A No No 5 g S6-H1 (1) 5'NR19-22' ERA, El. 129' A No No
{ u 2G31-RWQJ System
} O l M R154 (1) 10'SR19-6'ERH, El. 171'-3" A No No 1 R155 (1) R19-6"ERH, El. 167'-6" A No No l R156 (1) 10'SR19-2'ERH, El. 166' A No No R157 (1) 10'SR19-2'ERH, El. 166' A No No R158 (1) 10' SR19-5'ERH, El. 166' A No No R159 (1) 10' SR19-5'ERH, El. 166' 7 No No j 2G41-Fuel Pool Coolirg & Cleanup System l R125 (1) 69'SR15-26'ERH, El. 196'-6" A No No i
l
- 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 Ameniment request.
1 j ** Modifications to this column due to changes in high radiation areas may be made without prior j License Amerdment provided that the revision to Table 3.7.4-lb is included with the next License i
Ameniment request.
t I
a
6 TABLE 3.7.4-lb k FAFETY REIATED MECHANICAL SNUBBERS
- a HIGH RADIATION g; SNUBBER SYSITM SNUBBER INSTAUEn ACCESSIBLE OR ZONE ESPfrIALLY DIFFICULT A NO. (Oty.) ON, IOCATION AND ELEVATION INAOCESSIBLE DURING SHITIIXMi** 'IO REMOVE d
to Reactor Building (A or I) (Yes or No) (Yes or No) 2G51-Torus Water Cleanup System H700 (1) 7'SR19-3' ERA, El. 89' A No No 2T48-Containment Purge & Inerting System H721 (2) 47' SR19-4'WRF, El. 120'-2" A No No H722 (1) 49' SR19-9'WRF, El. 120'-2" A No No R54 (1) 55' SR19-14' ERD, El.120'-4" h No No 2T49-Hydrogen Recombiner System
.'. R700 (1) 16'NR24-8'WRF, El. 121'-11 1/2" A No No s' R701 (1) 14'NR24-8'WRF, El. 121'-11 1/2" A No No R702 (1) 12'-6"NR24-8'WRF, El 121'-11-1/2 A No No
- 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 Amerdnent 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 regaest. -
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5 8
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IIATCit-UtilT 2 3/4 7-M
o f
l 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. Snubbers excluded from this inspection program are those installed on non-safety related systems and then only if their failure or failure of the system on which they arc 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 clasped 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 257.) may not be used to lengtnen the rcquired 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 susceptibic 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 evalution 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 shutdown at 18-month intervals. Observed failures of sample snubbers shall require functional testing of additional units.
Hydraulic snubbers and mechanicai snubbers may each be treated as a different entity for the above surveillance programs, i i
HATCH-UNIT 2 B 3/4 7-2
f PLANT SYSTEMS BASES 3/4.7.4 SNtJBBERS (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 S0tJRCE 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.
3/4.7.6 FIRE StJPpRESSION SYSfEMS 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 minimf re 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 a f fected 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, ilATCH-UNIT 2 0 3/4 7-3
I ADMIfilSTRATIVE C0f4 TROL
_ RECORD RETEf4T!0ft (Continued)
- c. Records of radiation exposure for all individuals entering radiation control areas.
- d. Records of gaseous and liquid radioactive material released to the envlrons,
- c. Records of transient or operational cycles for those unit components
!!antified in Tabic 5.7.1-1.
- f. Records of reactor tests and experiments.
- g. Records of training and qualification for current members of the unit staf f,
- b. Records of in-service inspections performed pursuant to these Technical Specifications.
- 1. 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 RADIAT!0fl PROTfCTIOP1 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.
6.1? H!Qi RADI AT!0fl AREA 6.12.1 In lico of the " control device" or " alarm signal" required by paragraph 20.203(c)(?)
of 10 CfR 20, each hiqh 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
~*Hhal tii'Piiy's ic a, personnel, or personnel escorted by Health Physics personnel in accordance with approved energency procedures, shall he exempt from the PWP issuance requirement during the performance of their assigned radiation pro-tection duties, provided they comply wilh approved radiation protection pro-cedures for entry into high radiation arca..
HATCH-Ufilf ; 6-18
DCIDSUIE 4 NIC DOCKETS 50-321, 50-366 OPERATItG LICENSES DPR-57, NPF-5 EIMIN I. IIA'IOl NUCLEAR PIANr UNI'Is 1, 2 140UEST 'IO AMEND TFrHNICAL SPirIFICATIOtE Pursuant to 10 CFR 50.92, Georgia Power Corguny has evaluated the attached proposed amendments for the two Itatch units and has determined that their adoption would not involve a significant hazard. The basis for this determination is as follows:
a PROIOSED OIAfGE As requested by NRC letter dated November 20, 1980, revise the
" Action" statement for the Snubbers Limiting Condition for Operation to require an engineerirg evaluation on the supported component or declare the supported system inoperable and follow the appropriate " Action" statement for that system if inoperable snubber (s) are not returned to operable status within the Technical Specification-allottal time.
11 ASIS This chanje for both llatch units constitutes an a611tional control not previously included in the 'Nchnical Specitteations. This chanjo does not affcct the protubility or consequences of an accident or malfunction analyzed in the FSAR. *This change does not create the possibility of an accident or malfunction of a different type than analyzed in the PSAR. The margin of safety as defined in the tusin of any Technical Specification is not affectml. The ef fect of this charge is therefore within the acceptan e criteria and the chanje is consistent with Item (ii) of the "Fy.ampics of Amenlments That Are Considered Not Likely to Involve Significant flazards Considerations" listed on page 14870 of the April 6,1983 issue of the Faleral Register,
- b. PROrosl:D CilAfK;E As requestal by NRC letter dated Novemtwr 20, 1980, revice the
" Action" statement for the Snubbers Limiting Conclition for Operation noch that if one or more inoperabic snubler(s) is not replacal or returned to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, declare the supportal system inoperable anr1 follow the appropriate limitinj coalition for operation statement (s) for that system.
BASIR Sin:o snubtor protection is only required durirvj low protubility events such as earthquakes or severe transients, charvjinj ot the Snublers Limitin] Conlition for Operation such that the a[propriate limitiivj conlition for operation statement (s) is
O ENCIDSURE 4 (Continued)
NRC DOCKE'IS 50-321, 50-366 OPERATING LICENSES DPR-57, NPF-5 EDWIN I. IIA'ICli NUCLEAR PIANT UNITS 1, 2 REQUIST 'IO IMEND TBCIINICAL SPECIFICATICNS followed for the systs on which the affected snubber (s) is located does not significantly affect the probability or consaluences of an accident or malfunction of a dif ferent type than analyzed in the FSAR. This change does not create the possibility 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 significantly affected. 'Ihe effect of this change is therefore within the acceptance criteria of Itm (vi) of the "Exanples of Amendments
'Ihat Are Not Likely to Involve Significant flazards Consideration" listed on page 14870 of the April 6, 1983 issue of the Federal Register.
- c. PROPOSED CIIAM;ES As raluestal by NRC letter datal Novmber 20, 1980, revise snutter surveillance reluirments to incorporate the folowing:
- 1. Revise snubber visual inspections and visual acceptance criteria to include the followings
- a. Md the table listing of the safety-related mechanical snubbers,
- b. Add visual inspections rajuirments for safety-related mechanical snubbers.
- c. Md assurance that snubber attachnents to foundation or supporting structure are secure.
- d. Md reluirment that safety-relatal mechanical snutters be inspectai to determine if there has been a severe dynamic event and perform specific actions if such an event has occurred.
- e. Provide statment for detennination of operability.
- 2. Revise functional test ruluironents to include the follo41ng
- a. Increase functional test sanple size such that 10% of each type safety-related snubbers are exaninal at least once per 18 months during shutdown,
- b. Change re-sanple size for each snutter failing functional test to at least one-half the size of the initial saople size for the particular snutters functionally testol.
f O I
ENCIDSURE 4 (Continued)
NRC DOCKE'IS 50-321, 50-366 OPEPATING LICENSES DPR-57, NPF-5 EDWIN I. HA'ICH NUCLEAR PLANT UNITS 1, 2 REOUEST 'IO IMEND TECHNICAL SPECIFICATIONS
- c. Md the requirment that 25% of the representative sanple for the functional test be selected frm the three areas specified in Standard Technical Specification Section 4.7.9.c.
- d. Md the rquirment such that snubbers placed in the sane location as snubbers which failed the previous functional test be tested during the next test period.
- e. Md the rquirment such that cause of failure will be evaluated for snubbers failing functional testing.
- f. Md the requirment such that an engineering evaluation will be perfortned on cmponents which are found to be supported by failed snubbers.
- 3. Md functional test acceptance criteria for safety-related mechanical snubbers.
- 4. Md 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 dmonstrated all inaccessible snubbers are operable, the visual examination scheduled 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. Md rq uirment for service life monitoring of each safety-related snubber and retention of records thereof.
BASIS These 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 consquences of an accident or malfunction analyzed in the FEAR. 'Ihese char'ges do not create the possibility of an accident or inalfunction of a different type than analyzed in the FEAR. 'Ihe margin of safety, as definea in the basis for any Technical Specification is not affected. 'Ihe effect of these changes is therefore within the acceptance criteria arel these changes are consistent with Its (ii) of the "Exmples of Anendment That Are Considered Not Likely to Involve Significant Hazards Considration" listed on page 14870 of the April 6, 1983 issue of the Federal Register.
I o ENCIDSURE 4 (Continued)
NRC DOCKETS 50-321, 50-366 OPERATING LICENSES DPR-57, NPF-5 EDNIN I. HA'IOi NUCLEAR PLANT UNITS 1, 2 REOUEST 'IO IMEND TECHNICAL SPECIFICATIONS
- d. PROPOSED CHANGES As necessitatea 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.
- 2. Change the bases sections to reflect the revised snubber inservice surveillance requirments.
- 3. Add record retention rquirments for service life monitoring as a result of the revised snubber inservice surveillance in the administrative controls section of Technical Specifications.
BASIS These changes to the Technical Specifications for both Hatch units are administrative in nature. 'Ihese changes do not affect the probability or consquences of an accident or malfunction analyzed in the FSAR. These changes do not create the possibility of an accident or malfunction of a different type than analyzed in the FSAR. 'Ihe 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 Itm (i) of the "Exmples 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.
I
Y, ENCIDSURE 5 NRC DOCKE'IS 50-321, 50-366 OPERATING LICENSES DPR-57, NPF-5 EDWIN I. HA'lui NUCLEAR PIANT UNITS 1, 2 RDJUEST 'IO IMEND TECHNICAL SPECIFICATIONS Pursuant to 10 CFR 170.22, Georgia Power Cmpany has evaluated the attached proposed mendment to Operating License DPR-57 and hTF-5, and has determined that:
- a. The propoced amendment does not raluire evaluation of a new Safety Analysis Report and rewrite of the facility license;
- o. The proposed amendment does not require evaluation of several cmplex issues, involve ACRS review, or rajuire an envirorrnental impact statanent;
- c. The proposed amendment involves one safety issue, namely, the revision of snubber inservice surveillance requirenents as requested by the D. G. Eisenhut (NRC) letter dated Novenber 20, 1980;
- d. The proposed change to Opet ating License DPR-57 is therefore a Class III anendment. 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 anendment.