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GeorgialbwerA P
                                          - ATTACHENT 2 NRC DOCKET 50-321
* OPERATING LICENSE DPR-57 EDWIN I. HATCH NUCLEAR PLANT UNIT 1 i
PROPOSED CHANGES TO 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 vill                                          viii 3.6-10a through 3.6-10g                3.6-10a through 3.6-10t ,
3.6-31                                3.6-31                  i 3.6-32                                3.6-32                  1 6-20                                  6-20                    f I
i li l
1 8205070292 820430                                                                  i PDR ADOCK 05000321 F              PDR i
 
Section                                    Section                            Page LIMITING CONDITIONS FOR OPERATION        SURVEILLANCE REQUIREMENTS 3.6 PRit1ARY SYSTEM BOUNDARY                4.6 PRIMARY SYSTEM BOUNDARY        3.6-1
~
A. Reactor Coolant Heatup              A. Reactor Coolant Heatup      3.6-1 and Cooldown                            and Cooldown B. Reactor Vessel Temperature          B. Reactor Vessel Temperature  3.6-1 and Pressure                            and Pressure C. Reactor Vessel Head Stud            C. Reactor Vessel Head Stud    3.6-2 Tensioning                              Tensioning D.      Idle Recirculation Loop              D. Idle Recirculation Loop      3.6-2 Startup                                  Startup E.      Recirculation Pump Start            E. Recirculation Pump Start    3.6-3 F.      Reactor Coolant Chemistry .a
                                                        .        F. Reactor Coolant Chemistry    3.6-4
:                  G.      Reactor Coolant Leakage            G. Reactor Coolant Leakage      3.6-7 H.      Safety and Relief Valves            H. Safety and Relief Valves    3.6-9 I.      Jet Pumps                            I. Jet Pumps                    3.6-9 J.      Recirculation Pump Speeds          J. Recirculation Pump Speeds    3.6-10 l'                  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 Gas Treatment System 3.7-10 C.      Secondary Containment              C. Secondary Containment        3.7-12 D.      Primary Containment                D. Primary Containment          3.7-13 Isolation Valves                        Isolation Valves 3.8 RADI0 ACTIVE MATERIALS                  4.8 RADI0 ACTIVE MATERIALS        3.8-1 A.      Miscellaneous Radioactive          A. Miscellaneous Radioactive    3.8-1 Materials Sources                        Materials Sources 3.9 AUXILIARY ELECTRICAL SYSTEMS            4.9 AUXILIARY ELECTRICAL SYSTEMS  3.9-1 A.      Requirements for Reactor            A. Auxiliary Electrical        3.9-1 Startup                                  Systems Equipment iv
 
i l
1.IST OF TABLES (Concluded)
Ta bl e                            Titl e                            Page 4.2-7  Check, Functional Test, and Calibration Minimum Frequency    3.2-40 For Neutron Monitoring Instrumentation Which Initiates Control Rod Blocks 4.2-8  Check, Functional Test, and Calibration Minimum Frequency    3.2-42 for Radiation Monitorir.g Systems Which Limit Radioactivity Release 4.2-9  Check and Calibration Minimum Frequency for Instrumentation 3.2-45 Which Initiates Recirculation Pump Trip 4.2-10  Check, Functional Test, and Calibration Minimum Frequency    3.2-46 for Instrumentation Which Monitors Leakage into the Prywell 4.2-11  Check and Calibration.; Minimum Frequency for Instrumentation 3.2-4R Which Provides Surveillance Information 3.6-la  Safety Related Hydraulic Snubbers                            3. 6-10e 3.6-lb  Safety Related Mechanical Snubbers                            3.6-10q 4.6-1  In-Service Inspection Program                                3.6-11 3.7-1  Primary Containment Isolation Valves                          3.7-16 3.7-2  Testable Penetrations with Double 0-Ring Seals                3.7-21 3.7-3  Testable Penetrations with Testable Bellows                  3.7-22 3.7-4  Primary Containment Testable Isolation Valves                3.7-23 3.13.1  Fire Detectors                                                3.13-2 3.13-2  Fire Hose Stations                                            '13-9 6.2.2-1 Minimum Shift Crew Composition                                6-3 6.9-1  Special Reporting Requirments                                6-19 viii
 
3/4.6.L SNWBERS LIMITING C0tOITION FOR OPERATION 3.6.L      All snubbers listed in Tables 3.6-la and 3.6-lb shall be OPERABLE.
APPLICABILITY: Conditions 1, 2, and 3.
ACTION:
With one or more snubbers inoperable, within 72 hours replace or restore the inoperable snubber (s) to OPERABLE status and perform an engineering evaluation per Specification 4.6.L.3 on the supported component or declare the supported system inoperable and follow the appropriate limiting condition of operation statement (s) for that system.
SURVEILLANCE REQUIREMENTS 4.6.L Each snubber shall be demonstrated OPERASLE by performance of the following inservice inspection program.
: 1. Visual Insoections All safety-related snubbers licted in Tables 3.6-la and 3.6-lb shall be    visually  examined  to  v erify  snubber    operability. Visual inspections shall be performed in accordance with the following schedule:
No, Inoperable Snubbers              Subsequent Visual per Insce-tion Period              Insoection Period
* O                        18 months t 25%
1                        12 months T 25%
2                          6 months T 25%
3, 4                    124 days    T 25%
5,6,7                    -12 days  i25%
8 or more                31 days    1 25%
The snobbers may be categorized into two groups:        Tho.* accessible and those inaccessible during reactor operation.        Each grc e . f be inspected independently in accordance with the above schedule.
: 2. Visual Insoection Acceptance Criteria Visual inspections shall verify (1) that there are no visible indications of damage or impaired OPERASILITY, (2) attachments to the foundation or supporting structure are s ecure, and (3) for mechanical snubbers where snubber movement can be manually induced, the snubbers snall be inspected as follows:      (a) At each refueling,
          *The inspection interval shall not be lengthened more than one step at a time.
IIATCd - UNIT 1                                3.6 - 10a
 
N 4
3/4.6.L SNWBERS SURVEILLANCE REQUIREMENTS (Continued) safety-related systems associated with the snubbers listed in Table 3.6-lb shall be inspected to determine if there has been a severe dynamic event. (b) In the event of a severe dynamic event, snubbers in that system which experienced the event shall be inspected during the refueling outage to assure the snubbers have freedom of movement and are not frozen up.      The inspection shall consist of verifying freedom of motion using one of the following: (1) Manually induced snubber movement; (ii) stroking the mechanical snubber through its full range of travel. If one or more mechanical snubbers are found to be frozen up during this inspection, those snubbers shall be replaced (or overhauled) before returning to power.      Re-inspection shall subsequently be performed according to the schedule of 4.6.L.1, but the scope of the examination shall be limited to the safety-related systems associated with the snubbers listed in Table 3.6-lb. Snubbers which appear inoperable as a result of visual inspections    may  be , determined  OPERABLE for  the  purpose  of establishing the next Visual inspection interval, providing that (1) the cause of the rejection is clearly established and remedied for that particular snubber and for other snubbers that may be generically    susceptible; and (2) the affected snubber is functionally tested in the "as found" condition and determined OPERABLE per Specification      4.6.L.4 or 4.6.L.5, as applicable.
However, if a hydraulic snubber is found to contain less than the required minimum volume of reserve fluid or if visible signs of leakage are present, the snubber shall be determined inoperable and cannot be determined OPERABLE via functional testing for the purpose of establishing the next visual inspection. All snubbers connected to an inoperable common hydraulic fluid reservoir shall be counted 33 Inoperable snubbers.
: 3. Functional Tests At least once per 18 months during shutdown *, a representative sample of 10% of the total of each type (hydraulic or mechanical) safety-related snubber in use in the plant shall be functionally tested either in place or in a bench test. For each snubber        that does    not meet the functional test acceptance criteria            of Specification 4.6.L.4 or 4.6.L.5, an additional sample of at least 1/2 the size of the initial lot of that 'ype of snubber shall be functionally tested.
Functional testing r, hall continue until no additional inoperable snubbers of a particular type are found within a sample or until all snubbers listed in Table 3.6-la or 3.6-lb, as applicable, have been functionally tested.
      'The requirements of this section for functionally testing mechanical snubbers may be waived pending acquisition of a conversion module for existing snubber test equipment or new test equipment by the next refueling outage.
                                                    ~
HATCH - UNIT 1
 
N 3/4.6.L SNWBERS SURVEILLANCE REQUIREMENTS (Continued)
The representative sample selected for functional testing shall include the various configurations, operating environments and the range of size and capacity of snubbers. The representative sample shall be selected randomly from the total population identified in Tables 3.6-la and 3.6-lb.
Snubbers identified in Tables 3.6-la and 3.6-lb as "Especially Difficult to Remove" or in "High Radiation Zones During Shutdown" shall also be included in the representative sample *. Tables 3.6-la and 3.6-lb may be used jointly or separately as the basis for the sampling plan.
In addition to the regular sample, snubbers placed in the same location as snubbers which failed the previous functional test shall be retested during the next test period.        Test results of these snubbers shall not be i cluded in the sampling plan.
If any snubber selected for functional testing either fails to lockup or fails to move, i.e., frozen in place, the cause will be evaluated and if caused by manufacturer or design deficiency all snubbers of the same design subject to the same defect shall be functionally tested. This testing requirement shall be independent of the requirements stated above for snubbers not meeting the functional test criteria.
For the cnubber(s) found inoperable, an engineering evaluation shall be p?rformed on      the components which are      supported  by  the snubbeds). The purpose of this engineering evaluation shall be to determine if the components supported by the snubber (s) were adversely affected by the inoperability of the snubber (s) in order to ensure that the supported component remains capable of meeting the designed service.
: 4. Hydraulic Snubbers Functional Test Acceotance Criteria The hydraulic snubber functional test shall verify that:
: a. Activation (restraining action) is achie ved within the specified range of velocity or acceleration in both tension and compression.
: b. Snubber bleed, or release rate, where required, is within the specified range in compression or tension.          For snubbers specifically required to not displace under continuous load, the ability of the snubber        to  withstand  load  without displacement shall be verified.
              ' Permanent or other exemptions from functional testing for individual snubbers in those categories may be granted by the Commission only if a justifiable basis for exemption is presented and/or snubber life destructive testing was performed to qualify snubber operability for all design conditions at either the completion of their fabrication or at a subsequent date.
IIA *;Cll - L' NIT 1                              3.6 - 10e                                  .
 
A                                                                                        __
3/4.6.L SNUBBERS SURVEILLANCE REQUIREMENTS (Continued)
: 5. Mechanical Snubbers Functional Test Acceptance Criteria The mechanical snubber functional test shall verify that:
: 1. The snubber operates freely over the stroke in both tension and compression.
: 2. The force that initiates free movement of the snubber rod in either tension or compression is less than the specified maximum drag force. Specified maximum drag force is nominally five (5) pounds or one percent (1%) of rated snubber load, whichever is greater.
: 6. Unit Datage Inaccessible Snubber Inspection In the event      that  all  inaccessible  snubbers  are  inspected, functionally tested, and repaired as necessary during a unit outage, and that it is thus demonstrated that all inaccessible snubbers are operable, the schedule in Specification 4.6.L.1 may be re-entered on a 6-month inspection interval for the inaccessible snubbers.
: 7. Snubber Service Life Monitoring A record of the service life of each snubber, the date at which the designated    service  life  commences  and  the  installation  and maintenance records on which the designated service life is based shall be maintained as required by Specification 6.10.2.1.
Concurrent with the inservice visual inspection performed at the end of the 5th refueling cycle and at least once per 18 months thereafter,    the installation and maintenance records for each snubber listed in Tables 3.6-la and 3.6-lb shall be reviewed to verify that the indicated service life has not been exceeded or will
                . lot 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 snuober 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 l                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.
i HATCH - UNIT 1                              3.6-10d
 
                                                                                                                                  /      ,.
5 2=                                                                                                                                -
s TABLE 3.6-la E
g                                              SAFETY RELATED HYDRAULIC' SNUB 8ERS*
      ~~
HIGH RAOIATION St.tE8ER        SYSTEM StL6BER INSTALLED                        ACCESSIBLE OR        ZONE    ESPECIALLY DIFFICULT NO. (Oty.)      ON, LOCATION Ato ELEVATION It4 ACCESSIBLE DURIPO SHUTDOWN **                      TO REMOVE Reactor Building                            (A or I)        (Yes or No)    (Yes or No) tbclear Boiler System                                                                                          -
SS-1 (1)          Az. 720, El. 150'                                    I                No            No SS-2 (1)          Az. 720, El. 150'                                  I                No            No SS-3 (1)          Az. 00, El, 140                                  I                No            No SS-4 (1)          Az. 50, El. 128'                                I                No            No SS-5 (1)          Az. 00, El. 140'                                I      .        No            No SS-6 (1)          Az. 1080, El. 150'                                  I                No            No u      SS-7 (1)          Az. 900, El. 150'                                  I                tb            No 6      SS-8. (1)          Az. 1600, El. 151                                  I                No            No i      SS-9 (1)          Az. 950, El. 144'                                  I                No            rio 55-10 (1)          Az. 900, El. 142'                                  I                No            Yes
      ?      SS-11 (1)          Az. 1000, El. 138'                                  I                No            Yes 55-12 (1)          Az. 850, El. 144'                                I                ib            Yes SS-13 (1)          Az. 820, El. 143'                                I-                No            No SS-14 (1)          Az. 3150, El. 150'                                  I                No            No SS-15 (1)          Az. 900, El. 145'                                  I                No            No SS '.6 (1)        Az. 900, El. 144'                                  I                No            No SS-37 (1)          Az. 1700, El. 145'                                  I                No            Yes SS-18 (1)          Az. 1600, El. 145'                                  I                No            Yes
;          SS-19 (1)          Az. 1600, El. 134'                                  I                No            No SS-20 (1)          Az. 1600, El. 145'                                  I                No            Yes
* Snubbers may be added to safety related systens without prior License Amendment to Table 3.6-la provided that a revision to Table 3.6-la is included with the next License 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.
 
r ,..
5 A
  =
a TABLE 3.6-la SAFETY RELATED HYDRALLIC SNUBBERS *
  ~
HIGH RA01ATION SN11BER          SYSTEM St.teeER InSTAtte0      Access 1 ele OR      z0nE      eSeEc1 Atty 01rrIcutT F40. (Oty.)    Otl, LOCATION Ato ELEVATION INACCESSIBLE OURItC SHUT 00WN**        TO REMOVE Reactor Building          (A or 1)        (Yes or NO)      (Yes or No) tbclear Boiler System (Continued) 55-21    (1)      Az. 1350, El. 158'                  I              tb              tb SS-22 (1)        Az. 1600, El. 152'                  I              tb              tb 55-23 (1)        Az. 2780, El. 150'                I                tb              tb 55-24 (1)        Az. 2700, El. 150'                I                No              ib SS-26 (1)        Az. 2750, El. 145'                I        v      tb              tb SS-27 (1)        Az. 2700, El. 138'                I                tb              tb v  SS-28 (1)        Az. 2700, El. 142'                I                ib              Yes SS-29 (1)        Az. 2700, El. 140'                I                tb              tb
  ,  SS-31 (1)        Az. 2700, El. 139'                I                tb              tb SS-32 (1)        Az. 2750, El. 125'                I                No              to R  SS-33A (1)        Az. 2850, El. 123'                I                ib              tb SS-338 '1)        Az. 2850, El. 123'                I                tb              No SS-34 (1)        Az. 2800, El. 120                  I                tb              tb SS-35 (1)        Az. 2920, El. 120'                I                tb              tb SS-36 (1)        Az. 3070, El. 148'                I                No              No SS-37 (1)        Az. 3150, El. 150'                I                tb              tb SS-38 (1)        Az. 90, El. 128'              I                tb              tb SS-39 (1)        Az. 90, El. 128'              I                tb              No SS-40 (1)        Az. 00, El. 123'              I                tb              tb SS-41  (1)      Az. 3450, El. 155'                I                tb              tb
* Snubbers may be added to safety related systems without prior License Amendment to Table 3.6-la provided that a revision to Table 3.6-la is included with the next License Amendment request.
      " Modifications to this column due to changes in high radiation areas may be made without prior License Amendment provided that the revision to Table 3.6-la is included with the next License Amendment request.
I
 
r    ,..
  ) g M
    .,'                                                                                                TABLE 3.6-la Q                                                            SAFETY RELATED HYDRAULIC' SNUBBERS
* HICH RADIATION SNUBBER                        SYSTEM SNUBBER INSTALLED                                  ACCESSIBLE OR            ZONE                ESPECIALLY DIFFICULT NO. (Oty.)                  CN, LOCATION Ato ELEVATION INACCESSIBLE DURItC SHUTDOWN **                                                          TO REMOVE            i Reactor Building                                      (A or I)          (Yes or tb)                        (Yes or it) t
                                                                                                                                                                                        )
tuclear Boiler System (Continued)
S5-42                      (1) Az. 3470, El. 151'                                            I                      tb                                tb SS-43                      (1) Az. 3400, El. 155'                                            I                      tb                                ib SS-44                      (1) Az. 3430, El. 155'                                            I                      tb                                tb SS-45                    (1)  Az. 670,  El. 118'                                          I                      tb                                ib SS-46                      (1) Az. 670,  El. 120'                                          I        ,1          tb                                tb MVVH-23 (1)                    Az. 2700,  El. 144'                                          I                      tb                                Yes P          MVVH-24 (1)                    Az. 2700,  El. 144'                                          I                      tb                                Yes MVVH-25 (1)                    Az. 2700, El. 144'                                            I                      tb                                Yes MVVH-27 (1)                    Az. 2250, El. 124'                                            I                    tb                                tb              -
5 MVVH-28 (1)                    Az. 2500, El. 128'                                            I                      tb                                No MVVH-29 (1)                    Az. 2500, El. 128'                                            I                      tb                                tb MVVH-31 (1)                    Az. 1400, El. 149'                                            I                    No                                tb MVVH-32 (1)                    Az. 1400, El. 148'                                            I                    tb                                tb MVVH-33 (1)                    Az. 1400, El. 145'                                            I                    tb                                tb MVVH-35 (1)                    Az. 900, El. 126'                                              I                      tb                                tb MVVH-36 (1)                    Az. 900, El. 126'                                            I                    tb                                tb MVVH-37 (1)                    Az. 900, El, 126'                                            I                    tb                                tb FDi-11 (2)                    Az. 160, El, 147'                                            I                    ib                                tb Ful-12 (2)                    Az. 00, El. 147'                                            I                    tb                                tb FDi-13 (1)                    Az. 400, El. 148'                                            I                    No                                No
* Snubbers may be added to safety related systens without prior License Amendment to Table 3.6-la provided that a revision to Table 3.6-la is included with the next License 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.
 
                                                                                                                            /*  ;=
b_.
  )                                                                                                                            ~
s TABLE 3.6-la                  '
E
  ;;                                      SAFETY RELATED HYDRAULIC SNUBBERS *
  ~
HIGH RADIATION St.UGBER          SYSTEM StJUBBER It1 STALLED      ACCESSIBLE OR      ZONE        ESPECIALLY DIFFICULT NO. (Oty.)      Oil, LOCATI0ti AtJD ELEVATI0tJ INACCESSIBLE DWING SHUTDOWN **        TO REMOVE Reactor Building            (A or I)      (Yes or No)      (Yes or No) tOclear Boiler System (Continued)
FDH-14 (1)        Az. 750,  El. 148'                I              No                No FDH-15 (1)        Az. 530,  El. 148'                I              No                No FDH-16 (1)        A2. 790,  El. 146'                I              No                No FDH-17 (1)        Az. 2800,    El. 148'                I              No                No FDH-18 (1)        A2. 2810,    El. 146'                I      ''      No                No FDH-19 (1)        Az. 980,  El. 150'                I              No                No u  FDH-21 (2)        Az. 1500,    El. 165'                I              No                No b                      & 2100, i  FDH-22 (2)        Az. 1200,    El. 165'                I              tb                No
                          & 2400, S  FDH-23 (1)        Az. 600,  El. 164'                I              No                No FDH-24 (1)      Az. 300,  El. 167'                I              No                No FDH-25 (1)      Az. 3300,    El. 164'                I              No                No FDH-26 (1)      Az. 3100, El. 167'                    I              No                No DFDH-28 (1)      4'S47-8' ERA, El. 132'                I              No                No DFDH-30 (1)      4'NR7-8' ERA, El. 132'                I              No                No DFDH-32 (1)      Az. 140,  El. 132'                I              No                No DFDH-36 (1)      Az.      00,  El. 132'                I              No                No
* 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.
 
l                                                                                                            !-  ,..
h
;  O-7                                                    TABLE 3.6-la E                                        SAFETY RELATED HYDRAULIC StJUBBERS*                                -
U HICH RADIATION StJU60ER        SYSTEM StAJBBER INSTALLED      ACCESSIBLE OR      Z0t1E    ESPECIALLY DIFFICULT t10. (0ty.)    OfJ, LOCATION AtO ELEVATION INACCESSIDLE DURItC SHUTDOWN **      TO REMOVE Reactor Buildinq            (A or I)      (Yes or (Jo)    (Yes or No)
Rifi Systen S-1    (1)      Az. 2700, El. 141'                    I              tb              ib S-2    (1)      Az. 2700, El. 141'                    I              tb              tb S-4    (1)      Az. 2100, El. 141'                    I              tb              tb S-5    (1)      Az. 2400, El. 141'                    I              tb              tb S-15 (1)          Az. 1850, El. 139'                    I    ..
tb              Yes SM-1 (1)          Az. 1800, El. 134'                    I              No              ib SM-2 (1)          Az. 1800, El. 140'                    I              No              Yes P    SM-3 (1)          Az. 2250, El. 146'                    I              No              Yes SM-4 (1)          Az. 2250, El. 146'                    I              No              Yes
[    St4-8 (1)        Az. 900, El. 146'                    I              tb              tb a
  ~
Recirc System SS-Al (1)        Az. 3150, El. 123'                    I              tb              tb SS-A2 (1)        Az. 3150, El. 123'                    I              No              ib SS-A3 (1)        Az. 3150, El. 123'                    I              No              tb SS-A4 (1)        Az. 3100, El. 131'                    I              tb              tb SS-A5 (1)        Az. 3200, El. 131'                    I              tb              No SS-A6 (1)        Az. 3150, El. 134'                    I              No              tb SS-A7 (1)        Az. 150, El. 134'                  I              No              Ib
* Snubbers may be added to safety related systems without prior License Amendment to Table 3.6-la provided that a revision to Table 3.6-la is included with the next License Amendment request.
        ** Modifications to this column due to changes in high radiation areas may be made without prior License Amendment provided that the revision to Table 3.6-la is included with the next License Amendment request.
L.            -                          -              -    ,-
 
.;                                                                                                          r      ,..
1 5
8 8
                                                      ' TABLE 3.6-la
                                                                                      ~
  @                                      SAFETY RELATED HYDRAULIC SNLEBERS*                                    .
U HICH RADIATIOf4 StJUBBER        SYSTEM SNUBBER INSTALLED        ACCESSIBLE OR      ZONE      ESPECIALLY DIFFICULT NO. (Oty.)      ON, LOCATION Ato ELEVATION INACCESSIBLE DLRItG SHUTDOWN **        TO REMOVE Reactor Building            (A or I)      (Yes or No)      (Yes or (b)
Recirc System (Continued)
SS-A8 (1)        Az. 100, El. 134'                  I              tb              tb SS-A12 (1)        Az. 2700, El. 145'                  I              tb              tb SS-A13 (1)        Az. 2700, El. 145'                  I              tb              No SS-A14 (1)        Az. 2700, El. 122'                  I              tb              tb SS-B1 (1)        Az. 1400, El. 120'                  I              tb              No 55-82 (1)        Az. 1350, El. 123+                  I tb              tb SS-03 (1)        Az. 1350, El 123'                    I              No              tb F  SS-84 (1)        Az. 1450, El. 131'                  I              tb              tb
* SS-85 (1)        Az. 1350, El. 131'                  I              tb              tb
    ' SS-86 (1)        Az. 1350, El. 137'                  I              tb              Yes g  SS-87 (1)        Az. 1850, El. 140'                  I              tb              tb SS-08 (1)        Az. 1800, El. 140'                  I              tb              tb SS-B12 (1)      Az. 900, El. 145'                  I              No              tb SS-B13 (1)      Az. 900, El. 145'                  I              No              Ib SS-B14 (1)      Az. 900, El. 116'                    I              tb              No Core Spray System C5H-75 (1)      10'NR 3- 7'WRL,    El. 125'          A              No              No CSH-71 (1)        7'NR13-10'WRL,  El. 121'          A              tb              tb CSH-79 (1)        2'NR 9- 7'WRH,  El. 172'          A              tb                            '
No
* Snubbers may be added to safety related systems without prior License Amendment to Table 3.6-la provided that a revision to Table 3.6-la is included with the next License Amendment request.
      ** Modifications to this column due to changes in high radiation areas may be made without prior License Amendment provided that the revision to Table 3.6-la is included with the next License Amendment request.
 
5 M
=
h                                                            TABLE 3.6-la 5
-4                                                                                                                  '
SAFETY RELATED HYDRAULIC SNUBBERS
* HIGH RADIATION St.LEBER        SYSTEM StJUB3ER It1 STALLED        ACCESSIBLE OR        ZONE      ESPECIALLY DIFFICULT T40. (Oty.)    Otl, LOCATION AtJD ELEVATION IrlACCESSIBLE DURIt0 SHUTDOWN **          TO REMOVE                .
Reactor Building            (A or I-)      (Yes or No)    (Yes or No)
HPCI System HPCIH- 9 (1)      13'SRl- 6'ERC,        El. 88'          A                tb              No iPCIH-13 (1)      7'SR1- 2'WRL,      El. 94'          A                No              No iPSEH- 2 (1)      12'ta2-10'WRL,        El. 92'          A                No              ib IPSEH- 8 (2)      6'tR2- 4'NRC,        El. 112'          A                No              tb HPSEH-12 (1)        5'tiR3- 3'ERF,      El. 123'-8"        A tJo            ib iPSEH-13 (2)      4't4R3- 3'ERF, El. 123'-6"              A                No              Ib F        liPSEH-17 (1)      5'tiR3-14'ERF,      El. 123'-6"        A                No
* ib
'      IPSEH-55 (1)      8'SRl-25'WRL,        El. 98'          A                tb              No HPSEH-57 (1)        l' SRI-18'WRL, El.        99'-6"      A                No              tb E        IPSEH-58 (1)      4'SRl-18'WRL,        El. 99'          A                tb              tb IPSEH-60 (2)      4 'f1R2- 4 'tJRC,    El. 120'          A                No              No liPSEH-61 (1)      3'tRS-11'ERH,        El. 123'          A                tb              tio tiPSEll-62 (1)    3'fRS-ll'ERH,        El. 123'          A                No              ib IPSElf-63 (1)      8 ' t JR7-13 ' ERH , El. 123'          A                No              flo IPSEH-66 (1)      13'SR9- 2'ERH,        El. 122'          A                tb              No IPSEH-67 (1)      8'SRll-6'ERH,        El. 123'          A                tb              tJo liPSEli-72 (1)  11'SR 2-6'ERH,        El. 124'          A                tb              tb iPSEli-73 (1)    ll'SR 2-5'ERH, El. 124'                  A                tb              tb HPSEH-74 (1)      7'SR3-11'ERH, El. 122'                  A                tb              tJo HPSEH-76 (1)      l'tR3- 7'WRF, El. 123'                  A                tb              fJo a
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.
 
                                                                                                                                        ?    ,..
t
    '    5 N
e                                                                TABLE 3.6-la d                                                      SAFETY RELATED HYDRAULIC'SNW BERS*
          ~
HIGH RADIATION StJUBBER        SYSTEM SNUBBER INSTALLED          ACCESSIBLE OR        ZONE        ESPECIALLY DIFFICULT 740. (Oty.)    Off, LOCATION AND ELEVATION INACCESSIBLE OURING SHUTDOWN **            TO REMOVE Reactor Building              ( A or I)      (Yes or ib)      (Yes or (b) tPCI System (Continued)
HPSEH-77 (1)        8'NR3-13'WRF,      El. 123'          A                tb                  No IPSEH-80 (1)      11' tal3-6'ERH,      El. 126'          A                tb                  tb iPSEH-81 (1)      12'tal3-5'ERL,        El. 126'          A                No                  ib IPSEH-82 (1)        3'SRll-5'WRH,      El. 123'          A                tb                  No HPSEH-83 (1)        6'NRll-l'ERF,      El. 123'          A      c        No                  No tFSEH-84 (1)        8'NRil-13'WRF, El. 123'              A                tb                  tJo u
HPSEH-85 (1)        7'fR11-11'WRF, El. 122'              A                tb                  No o,            IPSEH-87 (1)        l'SRll- 7'WRF, El. 125'              A                No                  No e          iPSEH-88 (1)      12'NR2-12' WRL, El. 120'                A                No                  Ib
            -            iPSEH-89 (2)      11'SR2- 3' ERG, El. 123'                A                tb                  No S              HPSEH-90 (1)        5'NR3-13' ERF, El. 125'              A                tb                  No iPSEH-91 (2)        5'SR3- 8' ERF, El. 123'-6"          A                No                  No HPSEH-92 (1)        8'tJR3- 3' ERH,    El. 123'          A                tb                  No IPSEH-93 (1)        8'fR3- 3' ERH, El. 123'              A                tb                  tb RCIC System RCSEH-2 (1)        2'SR11-15' ERA,      El. 101'        A                No                  Ib RCSEH-20 (1)        1.' NRll-14 ' ERA,  El. 98'          A                tb                  tb RCSEM-21 (1)        7'SR 9- 5' ERA,      El. 120'        A                tb                  Yes RCSEH-23 (2)      14'SR 7- 9' ERA,      El. 122'        A                tb                  Yes 1
* 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.
4
                          ** 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.
h
 
g                                                                                                          ? ,.
M
:=
TABLE 3.6-la a
SAFETY RELATED HYDRAULIC StGBERS*
]
HICH RADIATI0tl St E BER        SYSTEM StJUBBER It1 STALLED      ACCESSIBLE OR        ZOt1E      ESPECIALLY DIFFICULT F 20. (Oty.)    ON, LOCATION AtJD ELEVATION Il1 ACCESSIBLE DLRING SHUTDOWN **        TO REMOVE Heactor buildino          (A or I)        (Yes or tb)      (Yes or ib)
RtB System RHRH-184 (1)      3'SR3-17'ERH,      El. 90'        A                tb              tb RHRH-185 (1)      3'SR3-17'ERH,      El. 91'        A                tb              tb RiiRH-186 (2)      0'SR3-12'ERH,      El. 88'        A                tb                tb RHRH-187 (2)      4'NR3- 8'ERH,      El. 89'        A      ,.
tb                tb RHRH-183 (1)      5'SRS- S'WRL,      El. 90'        A
                                                                  '~
ib                No a  RHRH-189 (1)      2'tR5- 8'WRL,      El. 90'        A                tb                tb
,  RHRH-192 (1)      9 ' f1R3-18 ' ERH , El. 123'        A                No                No
, RHRH-193 (1)      9'tR3-17'ERH,      El. 123'        A                tb                tb
_  RHRH-195 (1)      6'SR3-18'WRL,      El. 125'        A                No                Ib p  RHRH-196 (1)      6'SR3-18'WRL,      El. 120'        A                tb                tb RHRH-199 (1)    10'SR3- 3'WRL,        El. 123'        A                tb                ib RHRH-202 (1)      6'SR7- 7'ERH,      El. 110'        A                tb                tb RHRH-207 (2)    10'SR7-15'ERH,        El. 151'        A                tb                tb RHRH-209 (2)      6't1R3-16'WRL,      El. 105'        A                tb              No RHRH-210 (1)      9't1R3-16'WRL,      El. 108'        A                No                tb RHRH-211 (2)      7 ' t1R3-10 ' WRL , El. 100'        A.              tb              tb RHRH-212 (1)      6't1R3-12'WRL,      El. 104'        A                tb                No RHRH-213 (1)      3'SR2-12'WRL,      El. 124'        A                tb              No RHRH-214 (1)      3'SR2- 2'WRL,      El. 119'        A                No                tb RHRH-215 (2)      3'SR2-12'WRL,      El. 118'        A                tb              tb
* Snubbers may be added to safety related systems without prior License Amendment to Table 3.6-la provided that a revision to Table 3.6-la is included with the next License Amendment request.
  *
* Modifications to this column due to changes in high radiation areas may be made without prior License Amendment provided that the revision to Table 3.6-la is included with the next License Amendment request.
 
r ,..
N
=
a TABLE 3.6-la SAFETY RELATED HYDRAULIC SNtBBERS*
HICH RADIATION STAB 8ER        SYSTEM StJUB8ER INSTALLED      ACCESSIBLE OR      ZONE      ESPECIALLY DIFFICULT tJ0. (Oty.)    ON, LOCATI0tJ AtJD ELEVATION INACCESSIBLE DURING SHUTDOWN **      TO REMOVE Reactor Building          (A or I)      (Yes or No)      (Yes or No)
RFR Systen (Continued)
RHRH-216 (1)      11'tR3-16'WRL,    El. 122'          A              No              tb RHRH-217 (1)      11'NR3-19'WRL,    El. 121'          A              tb              tb RHRH-218 (1)      9'SR2-13'ERH, El. 116'            A              No              ib RHRH-220 (1)      4'SR7-12'WRL, El. 126'            A              No              No RHRH-221 (1)      2'SR7-10'WRL,    El. 122'          A      ~6      No              tb RHRH-222 (2)      2'SR7-10'WRL,    El. 120' & 122'  A                No              No u  RHRH-223 (1)      1/2'tJRll-4'ERH, El. 125'          A                No              tb h  RHRH-224 (1)        3'SR11-7'ERH, El. 123'          A                No              No i RHRH-225 (1)      9'tR13-13'ERH, El. 117'          A                tb              No RHRH-226 (1)      12'SR11-19'WRL, El. 121'          A                tb              No
?  RHRH-227 (1)      12'SRll-17'WRL, El. 122'          A                tb              No RHRH-228 (1)      3'tJR13-12'WRL, El. 124'          A                tb              No RHRH-229 (1)      3'NR13-12'WRL, El. 120'          A                No              No RHRH-230 (2)      3'NR13-12'WRL, El. 116' & 119'    A                tb              No RHRH-231 (2)      9'SR11-17'WRL, El. 104'          A                No              tb RHRH-232 (1)      9'SRll-17'WRL, El. 107'          A                No              tb RHRH-233 (1)      7'SR11-10'WRL, El. 97'            A                No              No RHRH-234 (1)      6'SRll-12'WRL, El. 104'          A                tb              No RHRH-237 (2)      2'NR 9- 3'ERH, El. 155'          A                No              No RHRH-238 (2)      2'tJR 9- 4 'WRH, El. 159'        A                No              No
* Snubbers may be added to safety related systems without prior Lic. nse 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.
 
                                                                                                          .c ,..
5 N
=
,                                                    TABLE 3.6-la SAFETY RELATED HYDRAULIC StJUBBERS*
HIGH RADIATION STAJBBER          SYSTEM StAJOBER INSTALLED        ACCESSIBLE OR      ZONE      ESPECIALLY DIFFICULT NO. (Oty.)      OtJ, LOCATI0t1 AtJD ELEVATION ItJACCESSIBLE DURING SHUTDOWN **    TO REMOVE Reactor Building            ( A or I)      (Yes or No)    (Yes or No)
RHR Systen (Continued)
RHRH-239 (1)        2 ' tR 9- 4 ' WRH , El . 160 '      A              No              No RiiPH-240 (2)      6'tJR 5-25'WRL, El . 147'            4              tb              No RHRil-242 (1)      3'SR 4- 4'WRH, El. 150'              A              No              Ib RHRH-244 (2)      10'SRll- 4'ERF, El. 121'              A              tb              tb RHRH-245 (1)      10'SRll- 3'ERF, El. 121'              A      .,      No              No RtiRH-246 (1)      10'SRll- 3'ERF, El. 122'              A              tb              No RHRH-249 (1)      ll'SRll-10'ERF, El. 118'              A              No              ib F  RtiRH-250 (2)      10'tB 3- 4'ERF, El. 121'              A              No              tJo
' RHRH-251 (1)      10'tJR 3- 3'ERF, El. 119'            A              No              No RtiRH-252 (1)      10'ta 3- 3'ERF, El. 121'              A              No              No E  RifRH-254 (1)      ll'NR 3-10'ERF, El. 118'              A              fJo            No RiiRH-279 (2)      3'SR 5- 3'WRL, El. 116'              A              No              No RHRH-282 (1)      1/2'SR4- 7' ERG, El. 121'            A              No              No tii."!H-286 (2)    3'SR 2-17'WRL, El. 116'              A              No              No RHRH-288 (2)        3'ta 9- 3'WRL, El. 116'              A              No              No RiiRH-292 (1)      4'SR 2- 6'ERH, El. 124'              A              No              No RHRH-299 (1)        4'SR13- 6'ERH, El. 122'              A              No              No Rif1H-305 (1)      5'ta 3- 4'ERH, El. 123'              A              No              No RiiRH-306 (2)      3'NR 3- 7'ERH, El. 121'              A              No              No RHRH-307 (1)      10'SR 5-17'ERH, El. 132'              A              No              No RiiRH-309 (1)      9'SRll-18'ERH, El. 115'              A              No              ib
* Snubbers may be added to safet/ 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 colurm due to changes in high radiation areas may be made without prior Licmse Amendment provided that the revision to Table 3.6-la is included with the next License Amendment request.
 
                                                                                                                                          .c ;.
k 0
TABLE 3.6 _a E
y                                                                    SAFETY RELATED HYDRAULIC StJUBBERS*
HIGH RAOIATION S!AliEER        SYSTEM StJUBBER INSTALLED        ACCESSIBLE OR        ZONE        ESPECIALLY DIFFICULT to. (Oty.)      011, LOCATION Ato ELEVATION Ii1 ACCESSIBLE DlRING SHUTDOWN **        TO REMOVE Reactor Building            (A or I)        (Yes or No)      (Yes or NO)
RtB Systen (Continued)
RERH-310 (1)      9'SRll-18'ERH, El. 124'              A                tb                No RHRH-312 (1)      6'tRll-18'WRL,      El. 124'        A                tb                tb RHRH-313 (1)      6 'tEll-18 'WRL , El. 125'          A                tb                tb
,                                RHRH-316 (1)      10' tall- 4'WRL, El. 123'            A                tb                No RHRH-319 (2)      9'ta 9-17'ERH, El. 136'              A                No                ib RIGH-320 (1)      4 'f all-17 ' ERH, El. 90'          A                tb                No F                              RHRH-321 (1)      3'IRll-15'ERH, El. 91'              A                No                ib RHRH-322 (2)      3'SRll-12'ERH,      El. 89'        A                tb                tb RHRH-323 (2)      l'SRll- 9'ERH,      El. 89'      A                No                ib g                              RHRH-324 (1)      3'tR 9- 5'WRL,      El. 91'        A                No                No RHRH-325 (1)      2'SR 9- 9'WRL,      El. 90'      A                tb                tb RHRH-332 (1)      2'SR 6- 2'WRH,      El. 190'        A                tb                tb RHRH-344 (1)      1/2'tJR10-l'WRH,      El. 122'        A                No                No RHRH-348 (2)      3'tR13-17'WRL,      El. 127'        A                No                tb RHRH-399 (1)      6'NR 5- 6'ERH,      El. 148'        A                No                ib RHRH-400 (1)      6'tR 5- l'ERH,      El. 148'        A                tb                tb
* Snubbers may be added to safety related systems without prior License Amendment to Table 3.6-la provided that a revision to Table 3.6-la is included with the next License Amendment request.
                                  ' Modifications to this column due to changes in high radiation areas may be made without prinr LL:ense Amendment provided that the revision to Table 3.6-la is included with the next License Amendment request.
 
e r
TABLE 3.6-lb k
Q                                            SAFETY RELATED ECHANICAL SNUBBERS
* s HIGH RADIATION
  @    SNUB 8ER                  SYSTEM SNUB 8ER INSTALLED        ACCESSIBLE OR      ZONE      ESPECIALLY DIFFICULT y    NO. (Qty.)                ON, LOCATION Ato ELEVATION INACCESSIBLE DURING SHUTDOWN **        TO REMOVE
  ,                                    Reactor Building              (A or I)    (Yes or No)    (Yes or No)
Nuclear Boiler System B21-OFDH-16 (1)            6'SR7-27'WRF,El.131'-5"                I            No              Yes 821-OFDH-33 (1)            2 'tR7- 2 ' ERE , El .132 '-2"          I            No              Yes 821-OFDH-43 (1)            2'-10"SR7-3' ERA,El.134'-5"            I            No              Yes 821-DFDH-43 (1)            4'-2"SR7-3' ERA,El.134'-5"              I            No              Yes B21-FDH-20 (1)              Az.2620,El.149'-9"                      I            No              Yes B21-X28-lF19-H001 (1)      Az.1800,E1.192'-0"                      I            No              Yes 821-X28-lF19-H001A (1)      Az.1800,E1.193'-0"                      I            No              Yes F  B21-X29-1F17-H002 (1)      Az. 100,El.173'-0"                      I            No              Yes
* 821-X29-lF17-H003A (2)    Az. 00,El.168'-0"                    I            No              Yes 8
821-X29-1F17-H00LB (2)    Az. 00,El.182'-0"                    I            No              Yes g  021-X29-lF17-H003C (2)    Az. 00,El.177'-0"                    I            No              Yes
  .a  B21-X28-1F19-H004A (2)    Az.1800,El.177'-0"                                    No I                            Yes B21-X28-lF19-H0048 (2)    Az.1800,El.182'-0"                      I            No              Yes 821-X28-lF19-H004C (2)    Az.1800,El.188'-0"                      I            No              Yes B21-X29-lF24-H002 (1)      Az. 00,El.192'-0"                        I            No              Yes 821-X29-lF24-H003 (1)      Az. 00,El.192'-0"                        I            No              Yes 821-X29-lF18-H004 (1)      Az. 40,El.173'-0"                        I            No              Yes B21-FS-H005 (1)            Az. 00,El.197'-0"                        I            No              Yes 821-F22-H001 (1)          Az. 00,El.138'-0"                    I            No              Yes B21-F23-H001 (1)          Az. 00,El.137'-0"                    I            No              Yes
* Snubbers may be added to safety related systems without prior License Amendment to Table 3.6-lb provided that a revision to Table 3.6-lb is included with the next License Amendment request.
      ** Modifications to this column due to changes in high radiation areas may be made without prior License Amendment provided that the revision to Table 3.6-lb is included with the next License Amendment request.
 
h                                                            TABLE 3.6-lb 9                                                                                                                      .
              ,                                              SAFETY RELATED WCHANICAL SNUBBERS
* kH                                                                                HIGH RADIATION SPCJBBER                  SYSTEM SNUBBER INSTALLED    ACCESSIBLE OR      ZONE      ESPECIALLY DIFFIQJLT
              ~~
NO. (Qty.)                ON, LOCATION AND ELEVATION INACCESSIBLE DLRING SHUTDOWN **      TO REMOVE Reactor Building        (A or I)      (Yes or No)      (Yes or No)
Nuclear Boiler System Continued) 821-F24-H001 (1)            Az. 00,El.137'-0"              I              No              Yes B21-F25-f001 (1)            Az. 00,El.137'-0"              I              No              Yes 821-F38-H005 (1)            3'-6"tR7-8' ERA,El.133'-0"        I              No              Yes 821-F38-H005 (1)            8' ERA-6'-5"SR7,El.133'-0"        I              No              Yes 821-F16-H003 (1)            Az. 400,El.190'-0"                I              No              Yes B21-FS-H020 (1)            Az. 450,E1.201'-0"                I              No              Yes a          B21-F5-H021  (1)          Az. 450,E1.201'-0"                I              No              Yes cn
              ,                                    Recirc System k          B31-X31-lFS-H001    (2)    Az. 900,El.124'-O"                I              No              Yes B31-X33-lF5-H001    (1)    Az. 900,E1.132'-0"                I              No              Yes 831-X32-lF6-H001    (1)    Az.2900,El.123'-0"                I              No              Yes B31-X32-]F6-H002 (1)        Az.2950,El.121'-O"                I              No              Yes 831-X32-lF7-H001 (1)        Az.3400,El.ll6'-O"                I              No              Yes B31-X34-1F16-H001 (1)      Az.1350,El.124'-0"                I              No              Yes 831-X28-lF16-H811 (1)      Az.2170,El.172'-0"                I              No              Yes B31-X28-lF16-H812 (1)      Az.2170,El.172'-0"                I              No              Yes B31-F3-H800 (1)            Az.3150,El.115'-0"                I              No              Yes B31-F14-H800 (1)            Az.1800,El.115'-0"                I              No              Yes
* Snubbers may be added to safety related systems without prior License Amendment to Table 3.6-lb provided that a revision to Table 3.6-lb is included with the next License Amendment request.
                      ** Modifications to this column due to changes in high radiation areas may be made without prior License Amendment provided that the revision to Table 3.6-lb is included with the next License Amendment request.
 
r              ,
g                                                      TABLE 3.6-lb a
O                                          SAFETY RELATED W CHANICAL SNUBBERS
* 8 5                                                                          HIGH RADIATION
@    SNUBBER                  SYSTEM SNUBBER INSTALLED    ACCESSIBLE OR        ZONE    ESPECIALLY DIFFICULT NO. (Qty.)                ON, LOCATION AND ELEVATION INACCESSIBLE DLRING SHUTDOWN **      TO REMOVE Reactor Building          (A or I)        (Yes or No)    (Yes or No)
RFE System Ell-F20-H001 (1)            22'SR7-23'ERH,El.139'-0"          I                No              Yes E11-F208-H001 (1)          Az.2700,El.138'-0"                I                No              Yes Ell-RHR-405    (1)          Az.1550,El.211'-2"                I                No              Yes Core Spray System y  E21-F1-H001 (2)            Az. 800,El.175'-0"                I                No              Yes e  E21-F1-H002 (2)            Az.2700,E1.174'-0"                I                No              Yes l
g                              RCIC System u
E51-X408-lF4-H001 (1)      Az.3300,El.156'-0"                I                No              Yes RWCU System G31-SM-5 (1)                Az.1600,El.168'-ll"              I                No              Yes G31-SM-6 (1)                Az.1600,El.168'-ll"              I                No              Yes
* Snubbers may be added to safety related systems without prior License amendment to Table 3.6-lb provided that a revision to Table 3.6-lb is included with the next License Amendment request.
  ** Modifications to this column due to changes in high radiation areas may be made without prior License Amendment provided that the revision to Table 3.6-lb is included with the next License Amendment request.
 
r
{n                                                    TABLE 3.6-lb f
SAFETY RELATED KCHANICAL SNLEBERS*
E                                                                        HIGH RADIATION                          -
4    StAJB8ER                SYSTEM StAJBBER INSTALLED  ACCESSIBLE OR        ZONE      ESPECIALLY DIFFICULT
-  NO. (Qty.)              ON, LOCATION AND ELEVATION INACCESSIBLE DURING SHUTDOWN **      TO REMOVE Reactor Building          (A or I)        (Yes or No)    (Yes or No)
Equipment & Floor Drain System T45-F17-H001 (1)          Az. 900,El.ll7'-0"                I              No              Yes RER System E11-F8-FOO1  (1)          22'SR7-23'ERH,El.123'-0"          A              No              No Ell-F93-H001 (1)          17'tR7-24'WRL,El.124'-0"          A              No              No
{ Ell-F93-H002 (1)          17'NR7-24'WRL,El.122'-0"          A              No              No
[                            Primary Containment Purge & Inerting System T48-F30-H001 (1)          Az. 450,El.120'-0"                A              No              No T48-F30-F002 (1)          Az. 450,El.120'-0"                A              No              No
* Snthbers 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.
  *M4odifications to this column due to changes in high radiation areas may be made without prior License Mendment provided that the revision to Table 3.6-lb is included with the next License Amendment request.
 
O
(  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 cystems is maintained during and following a seismic or other event initiating dynamic loads. Snubbers excluded from this inspection program are those installed on nonsafety-related systems and then only if their failure or failure of the system on which they are installed, would have no adverse effect on any safety-related system.
The visual inspection frequency is based upon maintaining a constant level of snubber protection to systems. Therefore, the required inspection interval varies inversely with the observed snubber failures and is determined by the number of inoperable snubbers found during an inspection. Inspections performed before that interval has elapsed may be used as a new reference point to determine the next inspection. However, the results of such early inspections performed before the original required time interval has elapsed (nominal time less 25%) may not be used to lengthen the required inspection interval. Any inspection whose results require a shorter inspection interval will override the previous schedule.
Wher the cause of the rejection of a snubber is clearly established and remedied for that snubber and for any other snubbers that may be generically susceptible, and verified by inservice functional testing, that snubber may be exempted from being counted as inoperable. Generically susceptible snubbers are those which are of a specific make or model and have the same design features directly related to rejection of the snubber by visual inspection, or are similarly located or exposed to the same environmental conditions such as temperature, radiation, and vibration.
When a snubber is found inoperable, an engineering evaluation is performed, in addition to the determination of the snubber mode of failure, in order to 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
 
l 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 a rea , 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.
l l
1 l
HATCH-UNIT 1                            3.6-32
 
t                                                                                      )
q ADMINISTRATIVE CONTROL RECORD RETENTION (Continued)
: c. Records of radiation exposure for all individuals entering radiation control areas.
: d. Records of gaseous and liquid radioactive material released to the environs.
: e. Records of transient or operational cycles for those unit components identified in Table 5.7.1-1.
: f. Records of reactor tests and experiments.
: g. Records of training and qualification for current members for the unit staff.
: h. Records of in-service inspections performed pursuant to these Technical Specifications.
: 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 'he PRB and SRB.
: 1. Records of the service lives of all hydraulic and mechanical snubbers listed on Tables 3.6-la and 3.6-lb including the date at which the service life commences and associated installation and maintenance records.
6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.
6.12 HIGH RADIATION AREA 6.12.1      In lieu of the " control device" or " alarm signal" required by paragraph 20.203(c)(2) of 10 CFR20, each high radiation-area in which the intensity of radiation is greater than 100 mrem /hr but less than 1000 mrem /hr shall be barricaded and conspicuously posted as a high radiation l
area and entrance thereto shall be controlled by -aquiring issuance of a Radiation Work Permit *. Any individual or group of individuals permitted
* Health Physics perso'nnel, or personnel escorted by Health Physics person-nel in accordance with approved emergency procedures, shall be exempt from l      the RWP issuance requirement during the performance of their assigned radia-l      tion' protection duties, provided they comply with approved radiation pro-tection procedures for entry into high radiation areas.
HATCH-UNIT 1                          6-20
 
GeorgiaPower d ATTACFNENT 3 NRC DOCKET 50-366 OPERATING LICENSE NPF-5 EfMIN I. HATCH NUCLEAR PLANT UNIT 2 PRC&OSED CHANGES TO TECHNICAL SPECIFICATI0t6 The proposed change to Technical Specifications (Appendix A to Operating License NPF-5) would be incorporated as follows:
Remove Page                        Insert Page VIII                                VIII XIII                                XIII 3/4 7-11 through 3/4 7-15          3/4 7-11 through 3/4 7-15 3/4 7-16                            3/4 7-16 3/4 7-16a through 3/4 7-16d 3/4 7-17                            3/4 7-17 3/4 7-17a through 3/4 7-171 3/4 7-18                            3/4 7-18 3/4 7-18a B3/4 7-2                            83/4 7-2 B3/4 7-3                            B3/4 7-3 6-18                                6-18
 
                    -_-                  . _ _ _          .      _        ~_ .                            -            _ _ _ _        _ _
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.7 PLANT SYSTEMS a
3/4.7.1          SERVICE WATER SYSTEMS Residual Heat Removal Service Water System. . . . . . . . . . . . . . 3/4 7-1 4
Se rv i ce 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          SNUB B E RS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 7- 1 1 3/4.7.5            SEALED SOURCE CONTAMINATION.............................                                                  3/4 7-19 3/4.7.6            FIRE SUPPRESSION SYSTEMS Fire Suppression Water Sys tem. . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 7-21 S p ri nk l e r Sy s tems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/ 4 7- 2 5 Low Pressure C02 Systems................................                                                    3/4 7-27      ,
"                                        Fi re Hos e S ta tions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 7- 28 j                      3/4.7.7          PENETRATION FIRE        BARRIERS...............................                                            3/4 7-30 3/4.7.8            SETTLEMENT OF CLASS I            STRUCTURES........................ 3/4'7-31 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1            A.C. SOURCES A. C. Sources-0pera ti n9. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 8- 1 A.C. Sources-Shutdown...................................                                                3/4 8-9      !
3/4.8.2            ONSITE POWER DISTRIBUTION SYSTEMS t
A.C. Dis tribu tion - Opera ti ng. . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 8-10 A.C. Di s tribu tion - Shu tdown. . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 8-12 0.C. Di s tribu tion - 0pera ting. . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 8-13
: 0. C. Di s tribu tion - Shu tdown. . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 8-16 A.C. Circui ts Inside Primary Contai nment. . . . . . . . . . . . . . . . 3/4 8-17                                        '
Primary Containment Penetration Conductor Overcurrent Protective Devices . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 8-18 I
I HATCH-UNIT 2-                                                VIII
      , as- w m m&. u  w  m " + '                        *                                                  '
 
          .  -----          .              .-                            ~
fNDEX BASES SECTION                                                                                                                PAGE PLANT SYSTEMS (Continued) 3/4.7.3 REACTOR CORE ISOLATION C0OLING                        SYSTEM............... B 3/4 7-1 a
j                                3/4.7.4 S NUB B ERS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 7- 2 l          ,
3/4.7.5 SEALED SOURCE CONTAMINATION. . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 7-3 3/4.7.6 FIRE SUPPRESSION SYSTEMS. . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 7-3 3/4.7.7 PENETRATION FIRE BARRIERS........................... B 3/4 7-4 3/4.7.8 SETTLEMENT OF CLASS I                STRUCTURES.................... B 3/4 7-4                                            !
3/4.8 . ELECTRICAL POWER SYSTEMS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 8-1 3/4.9 REFUELING OPERATIONS 3/4.9.1 REACTOR MODE SWITCH. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 9-1  ,
3/4.9.2 INSTRUMENTATION..................................... B 3/4 9-1 3/4.9.3 CONTROL R00 P0SITION. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 9-1 3/4.9.4 DECAY TIME.......................................... B 3/4 9-1                                                            ,
j                                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 R0D REM 0 VAL. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B - 3/4 9-2 3/4.9.12 REACTOR COOLANT CIRCULATION. . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 9-3 P
3/4.10 SPECIAL TEST "XCEPTIONS 3/4.10.1 PRIMARY CONTAINMENT            INTEGRITY.......................                                  B 3/4 10-1 3/4.10. 2 R00 SEQUENCE CONTROL SYSTEM. . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 10-1
;                                3/4.10.3 SHUTD0WN MARGIN DEMONSTRATIONS. . . . . . . . . . . . . . . . . . . . . . B 3/4 10-1 3/4.10.4 RECIRCULATION L00PS. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4.10-1 i
HATCH --UNIT 2                                        XIII
 
PLANT SYSTEMS 3/4.7.4 SNUBBERS LIMITING C0tOITION FOR OPERATION 3.7.4    All snubbers listed in Tables 3.7. A-la and 3.7.4-lb shall be OPERABLE.
APPLICABILITY: Conditions 1, 2, and 3.
ACTION:
With one or more snubbers inoperable, within 72 hours replace or restore the inoperable snubber (s) to OPERABLE status and perforra 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.
                                                    .w SURVEILLANCE REQUIREMENTS 4.7.4    Each snubber shall be demonstrated OPERABLE by performance of the following inservice inspection program and the requirements of Specification 4.0.3.
: 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:
1 No. Inoperable Snubbers            Subsequent Visual per Insoection Period              Insoection Period *#
0                        18 months + 25%
1                        12 months T 25%
2                          6 months I 25%
3, 4                    124 days  i25%
5,6,7                    62 days  1 25%
;                                          8 or (nore                31 days 1 25%
4-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.
l                *The inspection intervai snall not ce 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
 
PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
: b. Visual Insoection Acceotance Criteria Visual inspections shall verify (1) that there are no visible indications of damage or impaired OPERABILITY, (2) attachments to the foundation or supporting structure are secure, and (3) for mechanical snubbers where snubber movement can be manually induced, the snubbers shall be inspected as follows:        (a) At each refueling, safety-related systems associated with the snubbers listed in Table 3.7.4-lb shall be inspected to determine if there has been a severe dynamic event. (b) In the event of a severe dynamic event, snubbers in that system which experienced the event shall de inspected during the refueling outage to assure the snubbers have freedom of movement and are not frozen up.      The inspection shall consist of verifying freedom of motion using one of the following:
(1) Manually induced .-snubber movement;        (ii) stroking the mechanical snubber through its full range of travel.      If one or more mechanical snubbers are found to be frozen up during this inspection, those snubbers shall be replaced (or overhauled) before returning to power. Re-inspection shall
,                              subsequently be performed according to the schedule of 4.7.4.a, but the scope of the examination shall be limited to the safety-related systems associated with the snubbers listed in Table 3.7.4-lb. Snubbers which appear inoperable as a result of visual inspections may be determined OPERABLE for the purpose of establishing the next visual inspection interval, providing that (1)    the cau's e of the rejection is clearly established and remedied for that particular snubber and for other snubbers that may be generically susceptible; and (2) the affected snubber is functionally tested in the "as found" condition and determined OPERABLE per Specification 4.7.4.d or 4.7.4.e, as applicable.      However, if a hydraulic snubber is found to contain less than the required minimum volume of reserve fluid or if visible signs of leakage are present, the snubber shall be determined inoperable and cannot be determined OPERABLE via functional testing for the purpose of establishing the next visual inspection interval.          All snubbers connected to an inoperable common hydraulic fluid reservior shall be counted as inoperable snubbers.
: c. Functional Tests At least once per 18 months during shutdown *, a representative sample of 10% of the total of each type (hydraulic or mechanical) Safety-related snubber in use in the plant shall be
                  *The requirements of this section for functionally testing mechanical          l snubbers may be waived pending acquisition of a conversion module for existing snubber test equipment or new test equipment by the next refueling outage.
HATCH-UNIT 2                            3/4 7-12                            .
l
 
PLAf1T SYSTEMS SURVEILLAfJCE REQUIREMENTS (Continued) functionally tested either in place or in a bench test.      For each snubber that does not meet the functional test acceptance criteria of Specification 4.7.4.d or 4.7.4. e, an additional sample of at least 1/2 the size of the initial lot of that type of snubber shall be functionally tested.
Functional    testing shall continue until no additional inoperable snubbers of a particular type are found within a sample or until all snubbers listed in Table 3.7.4-la or 3.7.4-lb, as applicable, have been functionally tested -
The representative sample selected for functional testing shall    include    the    various    configurations, operating environments and the range of size and capacity of snubbers.
The representative sample shall be selected randomly from the total population identified in Tables 3.7.4-la and 3.7.4-lb.
Snubbers identified in Tables 3.7.4-la and 3.7.4-lb as "Especially Difficult to Remove" or in "High Radiation Zones During Shutdown" shall also be included in the representative sample *, Tables 3.7.4-la and 3.7.4-lb may be used jointly or separately as the basis for the sampling plan.
In addition to the regular sample, snubbers placed in the same location as snubbers which failed the previous functional test shall be retested during the next test period. Test results of these snubbers shall not be included in the sampling plan.
If any snubber selected for functional testing either fails to lockup or fails to move, i.e., frozen in place, the cause will be evaluated arid if caused by manufacturer or design deficiency all snubbers of the same design subject to the same defect shall be functionally tested. This testing requirement shall be independent of the requirements stated above for snubbers not meeting the functional test criteria.
For the snubber (s) found inoperable, an engineering evaluation shall be performed on the components which are supported by the snubber (s). The purpose of this engineering evaluation shall be to determine if the components supported by the snubber (s) were adversely affected by the inoperability of the snubber (s) in order to ensure that the supported component remains capable of meeting the designed service.
* Permanent or other exemptions from functional testing for individual snubbers in those categories may be granted by the Commission only if a justifiable basis for exemption is presented and/or snubber life destructive testing was performed to qualify snubber operability for all design conditions at either the completion of their fabrication or at a subsequent date.
HATCH-UNIT 2                                3/4 7-13
 
PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
: d. Hydraulic Snubbers Functional Test Acceptance Criteria The hydraulic snubber functional test shall verify that:
: 1. Activation (restraining action) is achieved within the specified range of velocity or acceleration in both tension and compression.
: 2. Snubber bleed, or release rate, where required, is within the specified range in compression or tension.          For snubbers specifically required to not displace under continuous load, the ability of the snubber to withstand load without displacement shall be verified.
: e. Mechanical Snubbers Functional Test Acceptance Criteria The mechanical snubber functional test shall verify that:
: 1. The snubber operates freely over the stroke in both tension and compression.
: 2. The force that initiates free movement of the snubber rod in either tension or compression is less than the specified maximum drag force. Specified maximum drag force is nominally five (5) pounds or one percent (1%) of rated snubber load, whichever is greater.
: f. 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 4.7.4.a may be re-entered on a 6-month inspection interval for the inaccessible snubbers.
(      g. Snubber Service Life Monitoring i
j            A record of the service life of each snubber, the date at l            which    the  designated  service  life  commences  and  the l            installation and maintenance records on which the designated
!            service life is based shall be maintained as required by l            Specification 6.10.2.1.
!  HATCH - UNIT 2                            3/4 7-14 l
l
 
PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)                                  _
Concurrent with the inservice visual inspection performed at the end of the 2nd refueling cycle and at least once per 18 months thereafter, the installation and maintenance records for each snuboer 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.
HATCH - UNIT 2                            3/4 7-15
 
TABLE 3.7.4-la 5                                                                                                                        -
F1                              SAFETY RELATED HYDRAULIC SNUBRERS*
i:                                                                  O E                                                                          HIGH RADIATION Cl  SNUBBER      SYSTEM SNUBBER INSTALLED              ACCESSISLE OR          70NE          ESPECIALLY DIFFICULT m    NO. (Oty.)  ON. LOCATION AND ELEVATION            INACCESSIBLE      DURING SHUTDOWN **    TO REMOVE Reactor Building                  (A or I)          (Yes or No)        (Yes or No) 2 Ell-RHR SYSTEM R86 (1)        8 ' NR19 - l ' ERJ, El . 212'            A                  No                    No R88 (1)        10' HR17 -      3' WRJ, El .119'          A                  No                    No R90 (1)              R15 -    3' ERH, El .119'          A        .,        No                    No R93 (2)        8' SRl4 - 11' ERF, El. 118'              A No                    No R94 (1)        8' SRl4 - 10' ERF, El .118'              A    ''
No                    No R98 (2)        10' SR19 - l ' ERJ, El . 121 '            A                  No                    No R100 (1)      10' SR21 -      3' WRJ, El .119'          A                  No                    No R101 (1)      12' SR21 -      S' WRJ, El .119'          A                  No                    No ig  R102 (1)              R23 -    3' ERH, El .119'          A                  No                    No R128 (1)        6' NR23 - 16' ERF, El .123'              A                  No                    No y    R129 (2)      18' SR21 - 16' ERF, El .123'              A                  No                    No g    R146 (2)        5' SR21 - 8' WRL, El. 120'                A                  No                    Yes R221 (1)      18' NR19 - 12' WRL, El. 90'                A                  No                    No R222 (1)      18' SR19 - 12' WRL, El . 90'              A                  No                    No R223 (1)      18' SR14 - 23' WRL, El. 90'                A                  No                    No R227 (1)      18' NR24 - 23' WRL, El . 90'              A                  No                    No R231 (2)        3' SRl9 - 9' WRL, El .102'                A                  No                    No R238 (2)      12' SRIS - 3' WRL, El .107'                A                  No                    Yes R241 (2)        3' NR23 - 9' WRL, El .102'                A                  No                    No R245 (2)      12' NR23 - 3' WRL, El .107'                A                  No                    Yes
* Snubbers may be added to safety related systems without prior License Amendment to Table 3.7.4-la provided that a revision to Table 3.7.4-la is included with the next License Amendment request.
    ** Modifications to this column due to changes in high radiation areas may be made without prior License Amendment provided that the revision to Table 3.7.4-la is included with the next License Amendment request.                                                                                      -
t
 
TABLE 3.7.4-la SAFETY RELATED HYDRAULIC SNUBBERS *
[
HIGH RADIATION
    .,  SNUBBER            SYSTEM SNUBBER INSTALLED            ACCESSIBLE OR                          70NE          ESPECIALLY DIFFICULT H      fl0. (Qty.) Oil, LOCATION AND ELEVATION              INACCESSIBLE                      DURING SHUTDOWN **
TO REMOVE N                              Reactor Building                (A or I)                        7 Yes or No) ~        (Yes or No) 2 Ell-RHR SYSTEM (Continued)
R250 (1)            11 ' SR14 - 15' WRL, El .119'            A                                  No                    No R251 (2)            11 ' SR14 - 15' WRL, El .120'            A                                  No                    No R252 (1)            15' SRl4 - 15' WRL, El .112'            A                                  No                    No              '
R253 (1)            15' SRl4 - 15' WRL, El .120'            A                                  No                    No R254 (1).          17' SRl4 - 17' WRL, El .112'            A                                  No                    No R256 (1)            17' SR14 - 17' WRL, El .112'            A                                  No                    Yes R258 (1)            22' SR14 - 13' WRL, El .      99'        A                          v      No                    No R264 (1)            21 ' SR14 -  9' WRL, El .104'          A                                  No                    Yes R267 (2)            15' SR14 -    3' WRL, El .102'          A                                  No                    No w    R268 (1)            11 ' NR24 - 15' WRL, El .119'            A                                  No                    No S    R269 (2)            11 ' NR24 - 15' WRL, El .120'            A                                  No                    No u    R270 (1)            15' flR24 - 15' WRL, El .112'            A                                  No                    No 1    R271 (1)            15' flR24 - 15' WRL, El .120'            A                                  No                    No
  $    R272 (1)          17' NR24 - 17 ' WRL, El .112'            A                                  No                    No R274 (1)            17' NR24 - 17' WRL, El .112'            A                                  No                    flo l      R276 (1)          22' NR24 - 13' WRL, El. 99'              A                                  No                    No l      R282 (1)          21' NR24 -    9' WRL , El . 104 '        A                                  No                    Yes R285 (2)          15' NR24 - 3 ' WRL, El .102'              A                                  No                    No R315 (2)          10' flR19 - 6' ERJ, El. 123'              A                                  No                    flo l      R374 (2)          23' SR14 - 15' WRL, El .106'              A                                  No                    Yes
* Snubbers may be added to safety related systems without prior License Amendment to Table 3.7.4-la provided that a revision to Table 3.7.4-la is included with the next License Amendment request.
      ** Modifications to this column due to changes in high radiation areas may be made without prior License Amendment provided that the revision to Table 3.7.4-la is included with the next License Amendment request.
 
    ._. . . _ _ - _    ..  .      . _.                  -        - . ~
TABLE 3.7.4-la                    .
x h                                    SAFETY RELATED HYDRAULIC SNUBBERS *                                                '
                    ?                                                                                    -
s                                                                            HIGH PADIATION
* SfiUBBER      SYSTEM SNUBBER INSTALLED                ACCESSIBLE OR          ZONE NO. (Qty.)                                                                                ESPECIALLY DIFFICULT
                    "                    ,0N, LOCATION AND ELEVATION            INACCESSIBLE    DURING SHUTDOWN **        TO REMOVE Reactor Buildirig                (A or I)        (Yes or Nc)            (Yes or No) 2 Ell-RHR SYSTEM (Continued)
R375 (2)        23' SR14 - 12' WRL, El .108'                A                  No                      No R376 (1)        23' SR14 - 12' WRL, El. 109'                A                  No                      No R377 (2)        23' NR24 - 15' WRL, El .106'                A                No                      Yes R378 (2)    -
23' flR24 - 12' WRL, El .108'              A                No                      No R379 (1)        23' NR24 - 12' WRL, El. 109'                A                flo                      No 2E11-RHR SERVICE WATER SYSTEM u    R 15 (2)          7' SR14 - 11' ERH, El .115'              A                No S    R 23 (2)          7 ' tiR24 - 11 ' ERH, El .115'          A                No No No 2E21-CORE SPRAY SYSTEM R 35 (1)          8' SR14 -    6' WRL, El. 95'            A                No                      No R 40 (1)          7' SR14 - 31' WRL, El. 95'              A                No                      No R 53 (2)        10' SR14 - 6' WRL, El .106'                A                No                      No R 72 (2)        10' NR24 - 6' WRL, El. 102'                A                No                      No R 80 (1)          8' NR24 - 6' WRL, El. 95'                A                flo                      No
;                        R 87 (1)          7' NR24 - 6' WRL, El. 90'                A                flo                      No R107 (2)        39' NR24 - 15' WRL, El .123'                A                No                      No
* Snubbers may be added to safety related systems without prior License Amendment to Table 3.7.4-la provided that a revision to Table 3.7.4-la is included with the next License Amendment request.
                          ** Modifications to this column due to changes in high radiation areas may be made without prior License Amendment provided that the revision to Table 3.7.4-la is included with the next License Amendment request.
f
 
                                                                                                                            ~
TABLE 3.7.4-la
* k                                          SAFETY RELATED HYDRAULIC SNUBBERS *  ,
9
: a. .                                                                                HIGH RADIATION
=          SNUBBER          SYSTEM SilVBBER INSTALLED            ACCESSIBLE OR        70NE          ESPECIALLY DIFFICULT
* fiO. (Qty.) ON, LOCATION AND ELEVATION              IllACCESSIBLE  DURING SHUTDOWN **    TO REMOVE N
Reactor Building                  (A or I)      (Yes or No)        (Yes or flo) 2T46-SGTS SYSTEM R 65 (2)          6' flR24 - 9' WRB, El .198'                A              No                    Yes R 66 (1)          2' NR24 - 9' WRB, El .186'                  A              No                    No R 67 (1)          2 ' flR24 - 9' WRB , El . 180'              A              flo                  Yes R 68 (2)          6' NR24 - 9' ERA, El .198'                  A              No                    Yes R 69 (1)          2' NR24 - 9' ERB, El. 186'                  A              No                    No R 70 (2)          2' NR24 - 9' ERA, El .179'                  A              No                    Yes 5                            2831-REACTOR RECIRCULATION SYSTEM
$          SSAl (1)        Az 315 , El. 117'                            I              No                    No R          SSA2 (1)        Az 328 0, El. 125'                          I              No                    Yes SSA3 (1)        Az 3020, El. 125'                            I              No                    Yes SSA4 (1)        Az 3280, E1. 131 '                          I              !!o                  Yes SSA5 (1)        Az 3010, E1. 131 '                          I              flo                  No SSA6 (1)        Az 3150 El . 137 '                          I              No                    Yes SSA7 (1)        Az 0180, El . 124 '                          I              No                    Yes SSA8 (1)        Az 342 0, El .123'                          I              flo                  Yes SSA12 (1)        Az 2550, El. 129'                            I              No                    No SSA13 (1)        Az 2850, El. 129'                            I              flo                  No SSA14 (1)        Az 2700, El . 121 '                          I              No                    No SSA15 (1)        Az 3230, El. 144'                            I              i'o                  Yes SSA16 (1)        Az 2170, El. 144'                            I              No                    Yes
* Snubbers may be added to safety related systems without prior License Amendment to Table 3.7.4-la              .
provided that a revision to Table 3.7.4-la is included with the next' License Amendment request.
            ** Modifications to this column due to changes in high radiation areas may be made without prior License Amendment provided that the revision to Table 3.7.4-la is included with the next License Amendment request.
 
6 TABLE 3.7.4-la
  $                                  SAFETY RELATED HYDRAULIC SNUBBERS
* c                                                                            HIGH RADIATION
  =  SHUBBER          SYSTEM ShUBBER INSTALLED              . ACCESSIBLE OR          7.ONE        ESPECIALLY DIFFICULT
  -4    NO. (Qty.) Ott, LOCATI0il AND ELEVATION              INACCESSIBLE    DURiflG SHUTDOWN **
N                                                                                                    TO REMOVE Reactor Building                  (A or I)        (Yes or No)          (Yes or No) 2831-REACTOR RECIRCULATION SYSTEM (Continued)
SSA17 (1)        Az 2700, El. 125'                            I                No Az 2700, El . 138 '                                                                  Yes SSA19 (1)                                                    I                No                    Yes SSA20 (1)        Az 2700, El. 138'                            I                No 00, El . 14 0 '                                                                Yes SSA21 (1)        Az                                          I                No                    Yes SSA22 (1)        Az    00, El . 140'                          I                No Az - 1350, . El . 117 '                                                              Yes 55B1  (1)                                                    I                No                    ho SSB2 (1)          Az 1480, El. 125'                            I No                    Yes SSB3 (1)        Az 1220, El. 125'                            I                No                    Yes SSB4    (1)      Az 1480 El . 131 '                          I                fio Az 1220, El. 131'                                                                    Yes t'
* SSBS (1)                                                      I                No                    No SSB6 (1)        Az 1350, El . 137'                          I                No                    Yes
.7'  SSB7 (1)        Az 1980 El. 124'                            I                fio                  Yes E
"  SSB8 (1)        Az 1620, El . 123 '                          I                Mo Az 0750, El. 129'                                                                    Yes SSB12 (1)                                                    I                No                    No SSB13.(1)        Az 1050, El. 129'                            I                No                    llo SSB14 (1)        Az 0900, El. 121'                            I                No                    No 55815 (1)        Az 1430, El. 144'                            I                No Az 0370, El. 144'                                                                    Yes SSB16 (1)                                                    I                No                    Yes SSB17 (1)        Az 900, El. 126'                            I                No Az 900, E1. 138 '                                                                    Yes SSB19 (1)                                                    I                No Az 900, El. 138'                                                                    Yes SSB20 (1)                                                    I                No                    Yes SSB21 (1)        Az 1800, El. 140'                          I                  No                    Yes SSB22 (1)        Az 1800, El. 140'                          I                No                    Yes
* Snubbers may be added to safety related systems without prior License Amendment to Table 3.7.4-la provided that a revision to Table 3.7.4-la is included with the -next License Amendment request.
    ** Modifications to this column due to changes in high radiation areas may be made without prior License Amendment provided that the revision to Table 3.7.4-la is included with the next License Amendment request.
 
TABLE 3.7.4-lb 5                                                                                            '
g                                                                          .
SAFETY RELATED MECHANICAL SNUBBERS *                                        '
    ?                                                                                          '
E                                                                        HICH RADIATION 5          StJUBSER          SYSTEM StJUBBER INSTALLED ACCESSIBLE OR            ZONE        ESPECIALLY DIFFICULT y          14 0 . (Oty.)-  Otl, LOCATIOt1 Ato ELEVATION INACCESSIBLE DtJ11tC SHUTDOWN **          TO REMOVE Reactor Building          (A or I)        (Yes or tJo)      (Yes or tJo) 2821-fluclear Boiler System MS-R34 (1)        Az. 1100 El. 155'                    I                  tb                Yes MS-R35 (1)        Az. 1450 El. 150'                    I                  tJo              Yes MS-R36 (1)        Az. 1450 El. 150' '                  I                  ib                Yes MS-R37 (2)        Az. 1450 El. 150'                    I                  tb                Yes                    ,
MS-R38 (2)        Az. 720 El. 167'                  I        y        No                Yes MS-R39 (2)        Az. 950 El. 150'                  I                  No                Yes MS-R41 (1)        Az. 1000 El. 150'                    I                  tb                Yes u          MS-R42 (1)        Az. 1400 El. 150'                  I                  No                Yes 3          MS-R43 (1)        Az. 1300 El. 150'                  I                  tb                Yes y          MS-R44 (2)        Az. 1400 El. 150'                  I                  No                Yes MS-R45 (1)        Az. 2500 El. 156'                  I                  tb                Yes MS-R46 (1)        Az. 2500 El. 156'                  I                  No                Yes MS-R47 (1)      Az. 2200 El 150'                    I                  No                Yes MS-R48 (1)        Az. 2200 El. 150'                  I                  ib                Yes MS-R49 (2)      Az. 2880 El. 167'                    I                  No                Yes MS-R50 (2)        Az. 2700 El. 150'                  I                  tb                Yes MS-RS2 (1)      Az. 2650 El. 150'                    I                  ib                Yes MS-R53 (2)      Az. 2350 El. 150'                    I                  No                Yes MS-RS4 (1)      Az. 2350 El. 150'                    I                  No                Yes MS-RSS (1)      Az. 2350 El. 150'                    I                  No                Yes
* 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 3.7.4-101s included with the next License Amendment request.
 
TABLE 3.7.4-lb E                                                                                        -
g                                                                      ..
SAFETY RELATED tECHANICAL SNUBBERS
* Y E                                                                    HIGH RADIATION-3    SNUBBER          SYSTEM SNUBBER It1 STALLED ACCESSIBLE OR                ZOtE    ESPECIALLY DIFFICULT
  ,y        f40. (Oty.)    Ott, LOCATI0tl AfD ELEVATI0t1 INACCESSIBLE OURING SHUTDOWN **            TO REMOVE Reactor Buildiry;          (A or I)          (Yes or tJo)    (Yes or No) 2B21-tbelear Boiler System (Continued)
MSRV-R36 (1)      Az. 2300 El. 137'                      I                    tb            Yes MSRV-R37 (1)      Az. 2300 El. 133'                      I                    tb            Yes MSRV-R38 (1)      Az. 2300 El. 133'                      I                    tb            Yes-MSRV-R40 (1)      Az. 2300 El. 125'                      I                    tb            Yes MSRV-R41 (1)      Az. 2250 El. 122'                      I      .;
                                                                            .            tb            Yes MSRV-R45 (2)      Az. 1650 El. 119'                      I                    No            Yes MSRV-R46 (2)      Az. 2500 El. 155'                      I                    ib            Yes u    MSRV-R50 (1)      Az. 2700 El. 150'                      I                    No            Yes D    MSRV-R52 (2)      Az. 1950 El. 150'                      I                    No            Yes u    MSRV-R53 (1)      Az. 1050 El. 149'                      I                    tb            Yes b    MSRV-R54 (1)      Az. 800 El. 137'                      I                    ib            Yes E    MSRV-RS6 (1)      Az. 700 El. 131'                      I                    tb            Yes MSRV-R57-(1)      Az. 700 El. 135'                    I                    tb            Yes MSRV-R58 (1)      Az. 700 El. 125'                    I                    No            Yes MSRV-R59 (2)      Az. 1250 El. 154'                      I                    No            Yes MSRV-R60 (2)      Az. 1200 El 152'                      I                    No            Yes MSRV-R62 (1)      Az. 900 El. 131'                      I                    No            Yes MSRV-R63 (1)      Az. 900 El. 132'                      I                    No            Yes MSRV-R64 (1)      Az. 900 El. 125'                      I                    No            Yes MSRV-R65 (1)      Az. 1000 El. 120'                      I                    tb            Yes
* Snubbers may be added to safety related systems without prior License Amendment to Table 3.7.4-Ib provided that- a rev'sion to Table 3.7.4-lb is included with the next License Amendment request.
          ** Modifications to this column due to changes in high radiation areas may be made without prior License Amendment provided that the revision to Table 3.7.4-lb is included with the next License Amendment request.
:{      ,                                                        _
                                                                                    ._              .                _ _ . _ _ _ ~
 
                                                            ' TABLE 3.7.4-lb.
x                                                                                          -
M                                            SAFETY RELATED MECHANICAL StJLEBERS*
  -Q                                                                                        -
    !=-                                                                      HICH RADIATION 35    StJUBBER              SYSTEM StAJB8ER INSTALLED ACCESSIBLE OR            ZONE
  "                                                                                          ESPECIALLY DIFFICULT
_t10. (Oty.)      ON, LOCATION Ato ELEVATION INACCESSIBLE DlRING SHUTDOWN **              TO REMOVE Heactor Building          (A or I)        (Yes or NO)      (Yes or No) 2B21-Nuclear Boiler System (Continued)
MSRV-R67 (2)      Az.'2350 El. 146'                      I                  No              Yes MSRV-R68-(1)      Az. 2350 El. 146'                      I                  No              Yes MSRV-R69 (1)      Az. 2350 El. 141'                      I                  No              Yes MSRV-R70 (1)      Az. 2350 El. 137'                      I        .,      No              Yes MSRV-R71 (1)      Az. 2450 El. 133'                      I                  ib              Yes MSRV-R72 (1)      Az. 2450 El. 133'                      I                  ib              Yes MSRV-R73 (1)      Az. 2450 El. 130'                      I                  No              Yes u      MSRV-R75 (1)      Az. 2550 El. 154'                      I                  tJo            Yes 2      MSRV-R76 (1)      Az. 2500 El. 146'                      I                  tJo            Yes y      MSRV-R77 (1)      Az. 2500 El. 137'                      I                  No              Yes
  ,L      MSRV-R78 (1)      Az. 2500 El. 136'.                    I                  No              Yes j      MSRV-R79 (1)      Az. 2500 El. 133'                      I                  flo            Yes MSRV-R80 (1)      Az. 2500 El. 132'                      I                  No              Yes MSRV-R82 (1)    . Az. 950 'El. 148'                      I                  tJo            Yes
        .MSRV-R83 (2)      Az. -950 El. 145'                      I                  No              Yes MSRV-R84 (1)      Az. 900 El. 137'                      I                  No              Yes Az. 650 El. 132' MSRV-R87 (1)                                              I                  flo            Yes MSRV-R88 (1)      Az. 650 El. 127'                      I                  ilo            Yes MSRV-R89 (1)      Az. 650 El. 125'                      I                  No              Yes MSRV-R90 (1)      Az. 1150 El. 145'                      I                  No              Yes            -
* Snubbers raay 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.
          **t-bdifications 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.
b m., ,.      -    , - , -          -
 
TABLE 3.7.4-lb                        _
27                                                                                                                  -
: g.                                      SAFETY RELATED MECHANICAL StAE8ERS*          _
E                                                                      HICH RAOIATION Z    Sta)BBER          SYSTEM StAE8ER INSTALLED ACCESSIBLE OR            ZONE          ESPECIALLY DIFFICULT ro    PJO. (Oty.)
ON, LOCATION AtO ELEVATION INACCESSIBLE DURING SHUTDOWN **              TO REMOVE Reactor Building                (A or I)  (Yes or No)          (Yes or flo) 2821-tbclear Boiler System (Continued)
MSRV-R91 (1)      Az. 1100 El. 137'                        I            ib                  Yes MSRV-R92 (1)      Az. 1100 El. 132'                        I            ib                  Yes MSRV-R93 (1)      Az. 1100 El. 125' I            tb                  Yes MSRV-R94 (1)      Az. 950 El. 120'                          I    -
tb                  Yes MSRV-R96 (2)      Az. 2850 El. 152'                        I            tb                  Yes MSRV-R97 (1)      Az. 2850 El. 152'                        I            tb                  Yes MSRV-R98 (1)      Az. 2900 El. 150'                        I            ib                  Yes 11SRV-R99 (2)    Az. 3200 El. 150'                        I            tb                  Yes t'
* MSRV-R100 (1)    Az. 3300 El. 146'                        I            No                  Yes MSRV-R101 (1)    Az. 3300 El. 140'                          I            tb                  Yes I'    MSRV-R103 (1)    Az. 3400 El. 129'                          I            tb                  Yes O
          "    MSRV-R104 (2)    Az. 3400 El. 126'                        I            tb                  Yes MSRV-R105 (1)    Az. 750 El. 152'                      I            tb                  Yes itSRV-R106 (1)  Az. 750 El. 152'                          I            tb                  Yes-MSRV-R107 (1)    Az. 600 El. 150'                          I            No                  Yes 4
                !1SRV-R108 (2)  Az. 300 El. 150'                          I            tb                  Yes NSRV-R109 (1)    Az. 300 El. 150'                          I            tb                  Yes MSRV-R110 (1)    Az. 250 El. 137'                          I            ib                  Yes MSRV-Rill (1)    Az. 220 .El. 132'                        I            tb                  Yes MSRV-R113 (1)    Az. 2700 El. 154'                        I            ib                  Yes
* Snubbers may be added to safety related systems without prior License Amendment to Table 3.7.4-lb provided that a revision to Table 3.7.4-lb is included with the next License Amendment request.
                " Modifications to this column due to changes in high radiation areas may be made without prior
                  . License Amendment provided that the revision to Table 3.7.4-lb is included with the next License Amendment request.
 
              .                                                                      TABLE 3.7.4-lb SAFETY RELATED MECHANICAL SNUBBERS
* x                                                                                                  ~
h O                                                                                    HIGH RADIATION
,                        StJUBBER          SYSTEM SNUBBER It1 STALLED ACCESSIBLE OR                        ZONE ESPECIALLY DIFFICULT
                "        rJ0. (Oty.)      Ort, LOCATION Ato ELEVATI0t1 INACCESSIBLE DURItJG SHUTDOWN **                                TO REMOVE Reactor Building                      (A or I)      (Yes or No)                  (Yes or f40) 4 2821-tuclear Boiler System (Continued)
MSRV-R114 (1)      Az. 2700 El. 146'                                I                  No                        Yes
;                        MSRV-Rll5 (1)      Az. 2700- El. 137'                                I                  No                        Yes
                        .MSRV-R116 (1)      Az. 2700 El. 133'                                I                  tb                        Yes MSRV-R118 (1)      Az. 2700 El. 125'                                I                  No                        Yes t1SRV-R119 (1)    -Az. 2700 El. 120'                                I        c.        No                        Yes MSRV-R121 (2)      Az. 2300 El. 141'                                I                  No                        Yes RFW-20 (2)        Az. 1000 El. 150'                                I                  tb                        Yes w      RFW-31 (2)        Az. 2600 El. 150'                                I                  ib                        Yes Y        S67-H10 (1)        Az. 1670 El 134'                                  I                  flo                        Yes u      S67-Hil (1)        Az. 1140 El. 135'                                I                  tJo                        Yes 1        S67-H12 (1)        Az.      450 El. 136'                            I                  No                        Yes
,                5      S67-H13 (1)        Az.      320 El. 136'                            I                  No                        Yes                            >
567-H14 (1)        Az.      220 El. 136'                            I                  tb                        Yes                            '
5128-14 (1)        Az. 2400 El. 192'                                I                  tb                        Yes
                        $143-H1 (1)        Az. 400 El. 195'                                I                  tb                        Yes S143-H2 (2)        Az. 300 El. 189'                                I                  No                        Yes S143-H3 (2)        Az. 300 El. 184'                                I                  tJo                        Yes                            4 1
S143-in (2)      Az. 300 -El. 179'                                I                  No                        Yes S143-H5 (1)      Az. 300 El. 196'                                  I                  No                        Yes S146-It5 (1)      Az. 150 El. 191'                                  I                  ib                        Yes
:                                                                                                                                                                          i 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 due to changes in high radiation areas may be made without prior
                          . License Amendment provided that the revision to Table 3.7.4-lb is included with the next License Amendment request.                                                                                                                        '
 
s
                =                                                            TABLE 3.7.4-lb                                  ,
2-                                                                                .                                                  .
y                                                SAFETY RELATED MECHAN 1 CAL StJUBBERS*              .
HICH RADIATION
              -4      StJUGGER            - SYSTEM STABBER ItiSTALLED ACCESSIBLE OR                          ZONE        ESPECIALLY OIFFICULT N        tJO. (Oty.)        ON, LOCATION APO ELEVATI0tl INACCESSIBLE DLRING SHUTDOWN **                          'TO REMOVE Reactor Building            (A or I)                (Yes or No)            (Yes or No) 2821-tJuclear Boiler System (Continued)
S148-H1 (1)          AZ. 2120 El. 195'                        I                            tb                Yes S148-H2 (2)          Az. 2100 El. 189'                        I                            tb                Yes S148-t0 (2)          Az. 2100 El. 184'                        I                            tb                Yes S148-FM (2)          Az. 2100 El. 179'                        I                            tb                Yes
                                            .Az. 2120 El. 194' & 196' S158-H5 (2)                                                  I
                                                                                                  ~4 tb                Yes
    .g                                      2831-Reactor Recirculation System y            514-H1 (1)          Az. 170 El. 125'                      I        .                  No                Yes
          ;            S17-H1 (1)          Az. 1980 El. 126'                        I                            tb                Yes
* S18-H1 (1)          Az. 650 El. 126'                        I                            ib                Yes S24-H1 (1)          Az. 3090 El. 123'                        I                            ib                Yes S40-H1 (1)          Az. 1100 El. 120'                        I                            tb                Yes S43-H1 (1)          Az. 1550 El. 187'                        I                            tb                Yes 2 Ell-RIR System
                      -R338 (1)            Az. 00 El. 146'                      I                            No                Yes R339 (1)            Az. 3550 El. 155'                        I                            tb                Yes
* Snubbers may be added to safety related systems without prior License Amendment to Table 3.7.4-lb provided that a revision to Table 3.7.4-lb is included with the next License Amendment request.
                        ** Modifications to this column due to changes in high radiation areas may be made without prior License Amendment provided that the revision to Table 3.7.4-lb is included with the next License .
Amendment request.
 
          -.        .              . . -          .=  .-
TABLE 3.7.4-lb i                                                                                          -
g-                                      SAFETY RELATED MECHANICAL StJUBBERS*
F                .                                                                      .
E                                                                    HIGH RAOIATION 5  StJUESER            SYSTEM SNLE8ER INSTALLED ACCESSIBLE OR              ZONE          ESPECIALLY DIFFICULT y    tJ0. (Oty.)      ON, LOCATION AND ELEVATI0t1 INACCESSIBLE DLRItJG SHUTDOWN **                      TO REMOVE Reactor Buildinr1            (A or I)        (Yes or No)                  (Yes or ib) 2 Ell-RHR System (Continued)
R340 (1)          Az. 3420 El. 155'                    I                tb                          Yes R342 (1)          Az. 3370 El. 140'                    I                tb                          Yes R350 (1)          Az. 800 El. 150'                      I                ib                          Yes R351 (2)          Az. 3050 El. 150'                    I                tb                          Yes R352 (2)          Az. 3250 El. 150'                    I          .      ib                          Yes
    .R353 (1)          Az. 3280 El. 146'                    I                ib                          Yes R354 (1)          Az. 3280 El. 146'                    I                tb                          Ves w    R355 (1)          Az. 2850 El. 150'                    I                ib                          Yes
)    R356 (2)          Az. 550 El. 150'                      I                tb                          Yes y    R357 (2)          Az. 370 El. 150'                    I                  ib                          Yes
,8  R358 (1)          Az. 330 El. 146'                    I                  ib                          Yes
%  -R359 (1)          Az. 380 El. 146'                    I-                tb                          Yes R368 (1)          Az. 200 El. 206'                    I                  No                          Yes 2E21-Core Spray System R59 (2)            Az. 900 El. 178'                  I                  tb                          Yes R98 (2)            Az. 2670 El. 178'                    I                  tb                          Yes
* Snubbers may be added to safety related systems without prior License Amendment to Table 3.7.4-lb provided that a revision to Table 3.7.4-lb is included with the next License Amendment request.
    ** Modifications to this column due to changes in high radiation areas may be made without prior License Amendment provided that the revision to Table 3.7.4-lb is included with the next License Amendment request.
 
TABLE 3.7.4-lb 5                                                SAFETY RELATED MECHANICAt SNm BERS*                                            -
Y E                                                                                    HIGH RADIATION SficeneR            SYSTen StimeER IrSTAttEo ACCESSIete OR H
z0f2E        EseeCIAttY oIrrICutT fl0. (Oty.)      Otl, LOCATI0tl Ato ELEVATI0rl It4 ACCESSIBLE DWItJG SHUTDOWtl**                  TO REMO\E N
Reactor Building                    (A or I)          (Yes or TJo)      (Yes or f40) 2E41-HPCI System                                                                                      i R110 (1)          Az. 180 El. 145'                          I                    tb              Yes Rlll (1)          Az. 190 El. 145'      -
I                    tb              Yes R112 (1)          Az. 120 El. 145'                          I                    tb              Yes R113 (2)          Az. 110 El. 145'                          I                    tb              Yes Rll4 (1)          Az. 460 El. 145'                          I          ..        tb              Yes R115 (2)          Az. 560 El . 145'                          I
* tb              Yes
    .R
* 2E51-RCIC System Y
Z R114 (1)          Az. 2130 El. 146'                          I                    tb              Yes All6 (1)          Az. 1860 El. 142'                          I                    tb              Yes Rll7 (1)          Az. 1860 El. 142'                          I                    tb              Yes 2G31-RWCU System R166 (1)          Az. 130 El. 149'                          I                    tb              Yes R167 (2)          Az. 170 El. 156'                          I                    tb              Yes R168 (1)          Az. 170 El. 162'                          I                    ib              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.
                "ttdifications to this column due to changes in high radiation areas may be made without prior License Amendment provided that the revision to Table 3.7.4-lb is included with the next License Anendment request.
 
TABLE 3.7.4-lb SAFETY RELATED MECHANICAL SNUBBERS
* 9 h
O                                                                    HICH RADIATION
* StafsBER              SYSTEM St4tBBER IrtSTALLED ACCESSIBLE OR            20tJE tJ0. (Oty.)
ESPECIALLY DIFFICULT
  "                      OtJ, LOCATIGtJ AfD ELEVATION INACCESSIBLE DLRItJG SHUTDOWN **          TO REMOVE (A or I)
Reactor Building                              (Yes or ib)    (Yes or No) 2E11-RHR System R91 (2)            38'SR14-23'WRL, El. 119'              A                    No              No R92 (2)            14'SR14-22'WRF, El. 119'              A                    No              ib R103 (2)            35'SR14-26'WRL, El. 119'              A                    No              No R105 (2)              9'NR24-11'WRF, El. 118'            A                    No              No R106 (1)              9'NR24-ll'WRF, El. 118'            A        ..          No              No R123 (1)              l'SR22-13'WCH, El. 169'            A                    No            No R125 (1)              6'SR22-12'WRF, El. 167'            A                    No              No ti R224 (1)            24'SR14-29'WRL, El. 90'              A                    tb            No
  *- R225 (1)            29'SR14-29'WRL, El. 90'              A                    No              No y  R226 (2)            23'SR14-27'WRL, El. 90'              A                    No            No
  ;  R228 (1)            18'SR14-23'WRL, El. 90'              A                    No            No m-R229 (1)          28'NR24-29'WRL, El. 90'                A                    No            ib R230 (1)          25'SR14-30'WRL, El. 90'                A                    No            No R233 (2)          23'IR24-28'WRL, El. 90'                A                    No            No R235 (1)          13'SR14-13'WRL, El. 121'              A                    tb            No R240 (1)          24'NR24-28'WRL, El. 90'                A                    No            No R289 (1)          13'NR24-13'WRL, El. 121'              A                    tb              No R290 (2)          25'SR14-28'WRL, El. 120'              A                    No              No R292 (2)          36'SR14- l'WRL, El. 118'              A                    No              tJo 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 Amendment request.
    **t4odifications to this column due to changes ir, 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.
n                          ,e ..              ,                                  ~-
 
        ~ .            _  ..      _ _ . . _ _ - _ _ . _ .          __ . _ . - _ . _                        _            .      _ _ ._
TABLE 3.7.4-lb                      ,
D
{                                                    SAFETY RELATED MECHAtJICAL StJUBBERS*
7 HICH RADIATION E      S:1UBBER          SYSTEM StJLBBER INSTALLED ACCESSIBLE OR                                20tJE          ESPECIALLY DIFFICULT G        f f0. (Oty.)    ON, LOCATI0tl Ato ELEVATIO.! INACCESSIBLE DtRING SHUTDOWN **                                      TO REM 0W ro                                Reactor Building                              (,4 or I)      (Yes or NO)              (Yes or te) 2E11-RHR System (Continued)
R326 (1)        18'SR19-17'ERH, El.136'                                    A                tb                    tb R327 (1)        18'SR19-17'ERH, El. 136'                                  A                tb                    No R328 (1)          18'SR19-10'WRH, El.-139'                                  A                No                    ib R329 (1)          18'SR19-10'WRH, El. 139'                                  A                tb                    No S4-H1 (1)        19'SR19-25'WRL, El. 123'                                  A      , .;      No                    ib 2E32-MSIV Leakage Control System u      Sll-H1 (1)        21'tR21- S'WRB, El. 118'                                  A                No                    ib 7      S17-H1 (1)        20'tR21-21'WRB, El. 118'                                  A                No                    No y      S18-H1 (1)        21'NR21- 4'WRB, El. 119'                                  A                tb                    No
,    .L      S19-H1 (1)        21'tR21- 5'WRB, El.117'                                    A                tb                    No N
2E41-H3CI System R45 (2)          23'tJR25-5'WRL, El. 117'                                  A                tb                    tb                -
R50 (2)          10'tR25-4' ERG, El. 110'                                  A                tb                    ib RSS (2)          10'tJR25-24'WRL, El. 96'        .                          A                tb                    tb 2E51-RCIC System                                                                                                  *
            .S6-H1 (1)        5'NR19-22' ERA, El. 129'                                  A                No-                    No
* Snubbers may be added to safety related systems without prior License Amendment to Table 3.7.4-lb provided that.a 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.
 
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HATCH-UNIT 2 3/4 7-18
 
l (This page blank intentionally)
HATCH-UflIT 2            3/4 7-18a
 
PLANT SYSTEMS BASES 3/4.7.4 SNUBBERS All snubbers are required OPERABLE to ensure that the structural integrity of the reactor coolant system and all other safety-related systems is main-tained during and following a seismic or other event initiating dynamic loads. Snubbers excluded from this inspection program are those installed on non-safety related systems and then only if their failure or failure of the system on which they are installed, would have no adverse effect on any safety-related system.
The visual inspection frequency is based upon maintaining a constant level of snubber protection to systems. Therefore, the required inspection interval varies inversely with the observed snubber failures and is determined by the number of inoperable snubbers found during an inspection. Inspections performed before that interval has elasped may be used as a new reference point to determine the next inspection. However, the results of such early inspections performed before the or'iginal required time interval has elapsed (nominal time less 25%) may not be used to l'engthen the required inspection interval. Any inspection whose results require a shorter inspection interval will override the previous schedule.
When the cause of the rejection af a snubber is clearly established and remedied for that snubber and for any other snubbers that may be generically susceptible, and verified by inservice functional testing, that snubber may be exempted from being counted as inoperable. Generically susceptible snubbers are those which are of a specific make or model and have the same design features directly related to rejection of the snubber by visual inspection or are similarly located or exposed to the same environmental conditions, such as temperature, radiation, and vibration.
When a snubber is found inoperable, an engineering evaluation is performed, in addition to the determination of the snubber mode of failure, in order to 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 system.
To provide assurance of snubber functional reliability, a representative sample of the installed snubbers will be functionally tested during plant shutdown at 18-month intervals. Observed failures of sample snubbers shall require functional testing of additional units.
Hydraulic snubbers and mechanical snubbers may each be treated as a different entity for the above surveillance programs.
HATCH-UNIT 2                            B 3/4 7-2
 
PLANT SYSTEMS BASES i
3/4.7.4 SNUBBERS (Continued)
The service life of a snubber is evaluated via manufacturer input and information through consideration.of the snubber service conditions and asso-ciated installation and maintenance records (newly installed snubber, seal replaced, spring replaced, in high radiation area, in high temperature area, etc...). The requirement to monitor the snubber service life is included to ensure that the snubbers periodically undergo a performance evaluation in view of their age and operating conditions. These records will provide statistical bases for' future consideration of snubber service life. The requirements for the maintenance of records and the snubber service life review are not intended to affect plant operation.
3/4.7.5 SEALED SOURCE CONTAMINATION The limitations on sealed source removable contamination ensure that the total body or individual organ irradiation does not exceed allowable limits in the event of ingestion or inhalation of the source material.
The limitations on removable contamination for sources requiring leak testing, including alpha emitters, is based on 10 CFR 70.39(c) limits for plutonium. Quantities of interest to this specification which are exempt from the leakage testing are consistent with the criteria of 10 CFR Part 30.11-20 and 70.19. Leakage from sources excluded # rom 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 SUPPRESSION SYSTEMS The OPERABILITY of the fire suppression systems ensures that adequate fire suppression capability is available to confine and extinguish fires occurring in any portion of the facility where safety-related equipment is located. The fire suppression system consists of the water system, spray and/or sprinklers, CO    2 , and fire hose stations. The collective capability of the fire suppression systems is adequate to mi timize potential damage to safety-related equipment and is a major element in the facility fire protection program.
In the event that portions of the fire suppression systems are inoper-able, alternate backup fire fighting equipment is required to be made available in the affected areas until the inoperable equipment is restored to service.
In the event the fire suppression water system becomes inoperable, immediate corrective measures must be taken since this system provides the major fire suppression capability of the plant. The requirement for a twenty-four hour report to the Commission provides for prompt evaluation of the acceptability of the corrective measures to provide adequate fire suppression capability for the continued protection of the nuclear plant.
HATCH-UNIT 2                      B 3/4 7-3
 
                                                                          ~
ADMINISTRATIVE CONTROL RECORD RETENTION (Continued)
: c. Records of radiation exposure for all individuals entering radiation control areas,
: d. Records of gaseous and liquid radioactive material released to the environs,
: e. Records of transient or operational cycles for those unit components identified in Table 5.7.1-1.
: f. Records of reactor tests and experiments.
: g. Records of training and qualification for current members of the unit staff,
: h. Records of in-service inspections performed pursuant to these Technical Specifications.                .-
: 1. Records of Quality Assurar.ce activities required by the QA Manual.
J. Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.
: k. Records of meetings of the PRB and the SRB.
: 1. Records of the service lives of all hydraulic and mechanical snubbers listed on Tables 3'.7.4-la and 3.7.4-lb, including the date at which the service life commences and associated installation and mainte-nance records.
6.11  RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.
6.12 HIGH RADIATION AREA 6.12.1    In lieu of the " control device" or " alarm signal" required by paragraph 2.0.203(c)(2) of 10 CFR 20, each high radiation area in which the intensity of radiation is greater g                than 100 mrem /hr but less than 1000 mrem /hr shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring
,                issuance of a Radiation Work Permit *. Any individual or groups of individuals permitted
              , *Health Physics personnel, or personnel escorted by Health Physics personnel in accordance with approved emergency procedures, shall be exempt from the RWP issuance requirement during the performance of their assigned radiation pro-
,.              tection duties, provided they comply with approved radiation protection pro-n cedures for' entry 1nto high radiation areas.
                                      ./-
            " BATCH-UNIT 2        ' , .'f f              i  . 6-18
                                                            \}}

Latest revision as of 15:50, 10 March 2020

Proposed Tech Specs 3/4.6.1 & 3/4.7.4 Re Snubber Inservice Surveillance Requirements
ML20052D901
Person / Time
Site: Hatch  Southern Nuclear icon.png
Issue date: 04/30/1982
From:
GEORGIA POWER CO.
To:
Shared Package
ML20052D899 List:
References
TAC-08298, TAC-08310, TAC-48362, TAC-48363, TAC-8298, TAC-8310, NUDOCS 8205070292
Download: ML20052D901 (54)
v • d • e


Text

. . _ _ ._ _ . _ _ . _ _ _ _

GeorgialbwerA P

- ATTACHENT 2 NRC DOCKET 50-321

  • OPERATING LICENSE DPR-57 EDWIN I. HATCH NUCLEAR PLANT UNIT 1 i

PROPOSED CHANGES TO 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 vill viii 3.6-10a through 3.6-10g 3.6-10a through 3.6-10t ,

3.6-31 3.6-31 i 3.6-32 3.6-32 1 6-20 6-20 f I

i li l

1 8205070292 820430 i PDR ADOCK 05000321 F PDR i

Section Section Page LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.6 PRit1ARY SYSTEM BOUNDARY 4.6 PRIMARY SYSTEM BOUNDARY 3.6-1

~

A. Reactor Coolant Heatup A. Reactor Coolant Heatup 3.6-1 and Cooldown and Cooldown B. Reactor Vessel Temperature B. Reactor Vessel Temperature 3.6-1 and Pressure and Pressure C. Reactor Vessel Head Stud C. Reactor Vessel Head Stud 3.6-2 Tensioning Tensioning D. Idle Recirculation Loop D. Idle Recirculation Loop 3.6-2 Startup Startup E. Recirculation Pump Start E. Recirculation Pump Start 3.6-3 F. Reactor Coolant Chemistry .a

. F. Reactor Coolant Chemistry 3.6-4

G. Reactor Coolant Leakage G. Reactor Coolant Leakage 3.6-7 H. Safety and Relief Valves H. Safety and Relief Valves 3.6-9 I. Jet Pumps I. Jet Pumps 3.6-9 J. Recirculation Pump Speeds J. Recirculation Pump Speeds 3.6-10 l' 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 Gas Treatment System 3.7-10 C. Secondary Containment C. Secondary Containment 3.7-12 D. Primary Containment D. Primary Containment 3.7-13 Isolation Valves Isolation Valves 3.8 RADI0 ACTIVE MATERIALS 4.8 RADI0 ACTIVE MATERIALS 3.8-1 A. Miscellaneous Radioactive A. Miscellaneous Radioactive 3.8-1 Materials Sources Materials Sources 3.9 AUXILIARY ELECTRICAL SYSTEMS 4.9 AUXILIARY ELECTRICAL SYSTEMS 3.9-1 A. Requirements for Reactor A. Auxiliary Electrical 3.9-1 Startup Systems Equipment iv

i l

1.IST OF TABLES (Concluded)

Ta bl e Titl e Page 4.2-7 Check, Functional Test, and Calibration Minimum Frequency 3.2-40 For Neutron Monitoring Instrumentation Which Initiates Control Rod Blocks 4.2-8 Check, Functional Test, and Calibration Minimum Frequency 3.2-42 for Radiation Monitorir.g Systems Which Limit Radioactivity Release 4.2-9 Check and Calibration Minimum Frequency for Instrumentation 3.2-45 Which Initiates Recirculation Pump Trip 4.2-10 Check, Functional Test, and Calibration Minimum Frequency 3.2-46 for Instrumentation Which Monitors Leakage into the Prywell 4.2-11 Check and Calibration.; Minimum Frequency for Instrumentation 3.2-4R Which Provides Surveillance Information 3.6-la Safety Related Hydraulic Snubbers 3. 6-10e 3.6-lb Safety Related Mechanical Snubbers 3.6-10q 4.6-1 In-Service Inspection Program 3.6-11 3.7-1 Primary Containment Isolation Valves 3.7-16 3.7-2 Testable Penetrations with Double 0-Ring Seals 3.7-21 3.7-3 Testable Penetrations with Testable Bellows 3.7-22 3.7-4 Primary Containment Testable Isolation Valves 3.7-23 3.13.1 Fire Detectors 3.13-2 3.13-2 Fire Hose Stations '13-9 6.2.2-1 Minimum Shift Crew Composition 6-3 6.9-1 Special Reporting Requirments 6-19 viii

3/4.6.L SNWBERS LIMITING C0tOITION FOR OPERATION 3.6.L All snubbers listed in Tables 3.6-la and 3.6-lb shall be OPERABLE.

APPLICABILITY: Conditions 1, 2, and 3.

ACTION:

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

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

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

No, Inoperable Snubbers Subsequent Visual per Insce-tion Period Insoection Period

  • O 18 months t 25%

1 12 months T 25%

2 6 months T 25%

3, 4 124 days T 25%

5,6,7 -12 days i25%

8 or more 31 days 1 25%

The snobbers may be categorized into two groups: Tho.* accessible and those inaccessible during reactor operation. Each grc e . f be inspected independently in accordance with the above schedule.

2. Visual Insoection Acceptance Criteria Visual inspections shall verify (1) that there are no visible indications of damage or impaired OPERASILITY, (2) attachments to the foundation or supporting structure are s ecure, and (3) for mechanical snubbers where snubber movement can be manually induced, the snubbers snall be inspected as follows: (a) At each refueling,
  • The inspection interval shall not be lengthened more than one step at a time.

IIATCd - UNIT 1 3.6 - 10a

N 4

3/4.6.L SNWBERS SURVEILLANCE REQUIREMENTS (Continued) safety-related systems associated with the snubbers listed in Table 3.6-lb shall be inspected to determine if there has been a severe dynamic event. (b) In the event of a severe dynamic event, snubbers in that system which experienced the event shall be inspected during the refueling outage to assure the snubbers have freedom of movement and are not frozen up. The inspection shall consist of verifying freedom of motion using one of the following: (1) Manually induced snubber movement; (ii) stroking the mechanical snubber through its full range of travel. If one or more mechanical snubbers are found to be frozen up during this inspection, those snubbers shall be replaced (or overhauled) before returning to power. Re-inspection shall subsequently be performed according to the schedule of 4.6.L.1, but the scope of the examination shall be limited to the safety-related systems associated with the snubbers listed in Table 3.6-lb. Snubbers which appear inoperable as a result of visual inspections may be , determined OPERABLE for the purpose of establishing the next Visual inspection interval, providing that (1) the cause of the rejection is clearly established and remedied for that particular snubber and for other snubbers that may be generically susceptible; and (2) the affected snubber is functionally tested in the "as found" condition and determined OPERABLE per Specification 4.6.L.4 or 4.6.L.5, as applicable.

However, if a hydraulic snubber is found to contain less than the required minimum volume of reserve fluid or if visible signs of leakage are present, the snubber shall be determined inoperable and cannot be determined OPERABLE via functional testing for the purpose of establishing the next visual inspection. All snubbers connected to an inoperable common hydraulic fluid reservoir shall be counted 33 Inoperable snubbers.

3. Functional Tests At least once per 18 months during shutdown *, a representative sample of 10% of the total of each type (hydraulic or mechanical) safety-related snubber in use in the plant shall be functionally tested either in place or in a bench test. For each snubber that does not meet the functional test acceptance criteria of Specification 4.6.L.4 or 4.6.L.5, an additional sample of at least 1/2 the size of the initial lot of that 'ype of snubber shall be functionally tested.

Functional testing r, hall continue until no additional inoperable snubbers of a particular type are found within a sample or until all snubbers listed in Table 3.6-la or 3.6-lb, as applicable, have been functionally tested.

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

~

HATCH - UNIT 1

N 3/4.6.L SNWBERS SURVEILLANCE REQUIREMENTS (Continued)

The representative sample selected for functional testing shall include the various configurations, operating environments and the range of size and capacity of snubbers. The representative sample shall be selected randomly from the total population identified in Tables 3.6-la and 3.6-lb.

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

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

If any snubber selected for functional testing either fails to lockup or fails to move, i.e., frozen in place, the cause will be evaluated and if caused by manufacturer or design deficiency all snubbers of the same design subject to the same defect shall be functionally tested. This testing requirement shall be independent of the requirements stated above for snubbers not meeting the functional test criteria.

For the cnubber(s) found inoperable, an engineering evaluation shall be p?rformed on the components which are supported by the snubbeds). The purpose of this engineering evaluation shall be to determine if the components supported by the snubber (s) were adversely affected by the inoperability of the snubber (s) in order to ensure that the supported component remains capable of meeting the designed service.

4. Hydraulic Snubbers Functional Test Acceotance Criteria The hydraulic snubber functional test shall verify that:
a. Activation (restraining action) is achie ved within the specified range of velocity or acceleration in both tension and compression.
b. Snubber bleed, or release rate, where required, is within the specified range in compression or tension. For snubbers specifically required to not displace under continuous load, the ability of the snubber to withstand load without displacement shall be verified.

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

IIA *;Cll - L' NIT 1 3.6 - 10e .

A __

3/4.6.L SNUBBERS SURVEILLANCE REQUIREMENTS (Continued)

5. Mechanical Snubbers Functional Test Acceptance Criteria The mechanical snubber functional test shall verify that:
1. The snubber operates freely over the stroke in both tension and compression.
2. The force that initiates free movement of the snubber rod in either tension or compression is less than the specified maximum drag force. Specified maximum drag force is nominally five (5) pounds or one percent (1%) of rated snubber load, whichever is greater.
6. Unit Datage Inaccessible Snubber Inspection In the event that all inaccessible snubbers are inspected, functionally tested, and repaired as necessary during a unit outage, and that it is thus demonstrated that all inaccessible snubbers are operable, the schedule in Specification 4.6.L.1 may be re-entered on a 6-month inspection interval for the inaccessible snubbers.
7. Snubber Service Life Monitoring A record of the service life of each snubber, the date at which the designated service life commences and the installation and maintenance records on which the designated service life is based shall be maintained as required by Specification 6.10.2.1.

Concurrent with the inservice visual inspection performed at the end of the 5th refueling cycle and at least once per 18 months thereafter, the installation and maintenance records for each snubber listed in Tables 3.6-la and 3.6-lb shall be reviewed to verify that the indicated service life has not been exceeded or will

. lot 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 snuober 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 l 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.

i HATCH - UNIT 1 3.6-10d

/ ,.

5 2= -

s TABLE 3.6-la E

g SAFETY RELATED HYDRAULIC' SNUB 8ERS*

~~

HIGH RAOIATION St.tE8ER SYSTEM StL6BER INSTALLED ACCESSIBLE OR ZONE ESPECIALLY DIFFICULT NO. (Oty.) ON, LOCATION Ato ELEVATION It4 ACCESSIBLE DURIPO SHUTDOWN ** TO REMOVE Reactor Building (A or I) (Yes or No) (Yes or No) tbclear Boiler System -

SS-1 (1) Az. 720, El. 150' I No No SS-2 (1) Az. 720, El. 150' I No No SS-3 (1) Az. 00, El, 140 I No No SS-4 (1) Az. 50, El. 128' I No No SS-5 (1) Az. 00, El. 140' I . No No SS-6 (1) Az. 1080, El. 150' I No No u SS-7 (1) Az. 900, El. 150' I tb No 6 SS-8. (1) Az. 1600, El. 151 I No No i SS-9 (1) Az. 950, El. 144' I No rio 55-10 (1) Az. 900, El. 142' I No Yes

? SS-11 (1) Az. 1000, El. 138' I No Yes 55-12 (1) Az. 850, El. 144' I ib Yes SS-13 (1) Az. 820, El. 143' I- No No SS-14 (1) Az. 3150, El. 150' I No No SS-15 (1) Az. 900, El. 145' I No No SS '.6 (1) Az. 900, El. 144' I No No SS-37 (1) Az. 1700, El. 145' I No Yes SS-18 (1) Az. 1600, El. 145' I No Yes

SS-19 (1) Az. 1600, El. 134' I No No SS-20 (1) Az. 1600, El. 145' I No Yes
  • Snubbers may be added to safety related systens without prior License Amendment to Table 3.6-la provided that a revision to Table 3.6-la is included with the next License 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.

r ,..

5 A

=

a TABLE 3.6-la SAFETY RELATED HYDRALLIC SNUBBERS *

~

HIGH RA01ATION SN11BER SYSTEM St.teeER InSTAtte0 Access 1 ele OR z0nE eSeEc1 Atty 01rrIcutT F40. (Oty.) Otl, LOCATION Ato ELEVATION INACCESSIBLE OURItC SHUT 00WN** TO REMOVE Reactor Building (A or 1) (Yes or NO) (Yes or No) tbclear Boiler System (Continued) 55-21 (1) Az. 1350, El. 158' I tb tb SS-22 (1) Az. 1600, El. 152' I tb tb 55-23 (1) Az. 2780, El. 150' I tb tb 55-24 (1) Az. 2700, El. 150' I No ib SS-26 (1) Az. 2750, El. 145' I v tb tb SS-27 (1) Az. 2700, El. 138' I tb tb v SS-28 (1) Az. 2700, El. 142' I ib Yes SS-29 (1) Az. 2700, El. 140' I tb tb

, SS-31 (1) Az. 2700, El. 139' I tb tb SS-32 (1) Az. 2750, El. 125' I No to R SS-33A (1) Az. 2850, El. 123' I ib tb SS-338 '1) Az. 2850, El. 123' I tb No SS-34 (1) Az. 2800, El. 120 I tb tb SS-35 (1) Az. 2920, El. 120' I tb tb SS-36 (1) Az. 3070, El. 148' I No No SS-37 (1) Az. 3150, El. 150' I tb tb SS-38 (1) Az. 90, El. 128' I tb tb SS-39 (1) Az. 90, El. 128' I tb No SS-40 (1) Az. 00, El. 123' I tb tb SS-41 (1) Az. 3450, El. 155' I tb tb

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

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

I

r ,..

) g M

.,' TABLE 3.6-la Q SAFETY RELATED HYDRAULIC' SNUBBERS

  • HICH RADIATION SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR ZONE ESPECIALLY DIFFICULT NO. (Oty.) CN, LOCATION Ato ELEVATION INACCESSIBLE DURItC SHUTDOWN ** TO REMOVE i Reactor Building (A or I) (Yes or tb) (Yes or it) t

)

tuclear Boiler System (Continued)

S5-42 (1) Az. 3470, El. 151' I tb tb SS-43 (1) Az. 3400, El. 155' I tb ib SS-44 (1) Az. 3430, El. 155' I tb tb SS-45 (1) Az. 670, El. 118' I tb ib SS-46 (1) Az. 670, El. 120' I ,1 tb tb MVVH-23 (1) Az. 2700, El. 144' I tb Yes P MVVH-24 (1) Az. 2700, El. 144' I tb Yes MVVH-25 (1) Az. 2700, El. 144' I tb Yes MVVH-27 (1) Az. 2250, El. 124' I tb tb -

5 MVVH-28 (1) Az. 2500, El. 128' I tb No MVVH-29 (1) Az. 2500, El. 128' I tb tb MVVH-31 (1) Az. 1400, El. 149' I No tb MVVH-32 (1) Az. 1400, El. 148' I tb tb MVVH-33 (1) Az. 1400, El. 145' I tb tb MVVH-35 (1) Az. 900, El. 126' I tb tb MVVH-36 (1) Az. 900, El. 126' I tb tb MVVH-37 (1) Az. 900, El, 126' I tb tb FDi-11 (2) Az. 160, El, 147' I ib tb Ful-12 (2) Az. 00, El. 147' I tb tb FDi-13 (1) Az. 400, El. 148' I No No

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

/*  ;=

b_.

) ~

s TABLE 3.6-la '

E

SAFETY RELATED HYDRAULIC SNUBBERS *

~

HIGH RADIATION St.UGBER SYSTEM StJUBBER It1 STALLED ACCESSIBLE OR ZONE ESPECIALLY DIFFICULT NO. (Oty.) Oil, LOCATI0ti AtJD ELEVATI0tJ INACCESSIBLE DWING SHUTDOWN ** TO REMOVE Reactor Building (A or I) (Yes or No) (Yes or No) tOclear Boiler System (Continued)

FDH-14 (1) Az. 750, El. 148' I No No FDH-15 (1) Az. 530, El. 148' I No No FDH-16 (1) A2. 790, El. 146' I No No FDH-17 (1) Az. 2800, El. 148' I No No FDH-18 (1) A2. 2810, El. 146' I No No FDH-19 (1) Az. 980, El. 150' I No No u FDH-21 (2) Az. 1500, El. 165' I No No b & 2100, i FDH-22 (2) Az. 1200, El. 165' I tb No

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

  • 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.

l  !- ,..

h

O-7 TABLE 3.6-la E SAFETY RELATED HYDRAULIC StJUBBERS* -

U HICH RADIATION StJU60ER SYSTEM StAJBBER INSTALLED ACCESSIBLE OR Z0t1E ESPECIALLY DIFFICULT t10. (0ty.) OfJ, LOCATION AtO ELEVATION INACCESSIDLE DURItC SHUTDOWN ** TO REMOVE Reactor Buildinq (A or I) (Yes or (Jo) (Yes or No)

Rifi Systen S-1 (1) Az. 2700, El. 141' I tb ib S-2 (1) Az. 2700, El. 141' I tb tb S-4 (1) Az. 2100, El. 141' I tb tb S-5 (1) Az. 2400, El. 141' I tb tb S-15 (1) Az. 1850, El. 139' I ..

tb Yes SM-1 (1) Az. 1800, El. 134' I No ib SM-2 (1) Az. 1800, El. 140' I No Yes P SM-3 (1) Az. 2250, El. 146' I No Yes SM-4 (1) Az. 2250, El. 146' I No Yes

[ St4-8 (1) Az. 900, El. 146' I tb tb a

~

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

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

L. - - - ,-

.; r ,..

1 5

8 8

' TABLE 3.6-la

~

@ SAFETY RELATED HYDRAULIC SNLEBERS* .

U HICH RADIATIOf4 StJUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR ZONE ESPECIALLY DIFFICULT NO. (Oty.) ON, LOCATION Ato ELEVATION INACCESSIBLE DLRItG SHUTDOWN ** TO REMOVE Reactor Building (A or I) (Yes or No) (Yes or (b)

Recirc System (Continued)

SS-A8 (1) Az. 100, El. 134' I tb tb SS-A12 (1) Az. 2700, El. 145' I tb tb SS-A13 (1) Az. 2700, El. 145' I tb No SS-A14 (1) Az. 2700, El. 122' I tb tb SS-B1 (1) Az. 1400, El. 120' I tb No 55-82 (1) Az. 1350, El. 123+ I tb tb SS-03 (1) Az. 1350, El 123' I No tb F SS-84 (1) Az. 1450, El. 131' I tb tb

  • SS-85 (1) Az. 1350, El. 131' I tb tb

' SS-86 (1) Az. 1350, El. 137' I tb Yes g SS-87 (1) Az. 1850, El. 140' I tb tb SS-08 (1) Az. 1800, El. 140' I tb tb SS-B12 (1) Az. 900, El. 145' I No tb SS-B13 (1) Az. 900, El. 145' I No Ib SS-B14 (1) Az. 900, El. 116' I tb No Core Spray System C5H-75 (1) 10'NR 3- 7'WRL, El. 125' A No No CSH-71 (1) 7'NR13-10'WRL, El. 121' A tb tb CSH-79 (1) 2'NR 9- 7'WRH, El. 172' A tb '

No

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

5 M

=

h TABLE 3.6-la 5

-4 '

SAFETY RELATED HYDRAULIC SNUBBERS

  • HIGH RADIATION St.LEBER SYSTEM StJUB3ER It1 STALLED ACCESSIBLE OR ZONE ESPECIALLY DIFFICULT T40. (Oty.) Otl, LOCATION AtJD ELEVATION IrlACCESSIBLE DURIt0 SHUTDOWN ** TO REMOVE .

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

HPCI System HPCIH- 9 (1) 13'SRl- 6'ERC, El. 88' A tb No iPCIH-13 (1) 7'SR1- 2'WRL, El. 94' A No No iPSEH- 2 (1) 12'ta2-10'WRL, El. 92' A No ib IPSEH- 8 (2) 6'tR2- 4'NRC, El. 112' A No tb HPSEH-12 (1) 5'tiR3- 3'ERF, El. 123'-8" A tJo ib iPSEH-13 (2) 4't4R3- 3'ERF, El. 123'-6" A No Ib F liPSEH-17 (1) 5'tiR3-14'ERF, El. 123'-6" A No

  • ib

' IPSEH-55 (1) 8'SRl-25'WRL, El. 98' A tb No HPSEH-57 (1) l' SRI-18'WRL, El. 99'-6" A No tb E IPSEH-58 (1) 4'SRl-18'WRL, El. 99' A tb tb IPSEH-60 (2) 4 'f1R2- 4 'tJRC, El. 120' A No No liPSEH-61 (1) 3'tRS-11'ERH, El. 123' A tb tio tiPSEll-62 (1) 3'fRS-ll'ERH, El. 123' A No ib IPSElf-63 (1) 8 ' t JR7-13 ' ERH , El. 123' A No flo IPSEH-66 (1) 13'SR9- 2'ERH, El. 122' A tb No IPSEH-67 (1) 8'SRll-6'ERH, El. 123' A tb tJo liPSEli-72 (1) 11'SR 2-6'ERH, El. 124' A tb tb iPSEli-73 (1) ll'SR 2-5'ERH, El. 124' A tb tb HPSEH-74 (1) 7'SR3-11'ERH, El. 122' A tb tJo HPSEH-76 (1) l'tR3- 7'WRF, El. 123' A tb fJo a

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.

? ,..

t

' 5 N

e TABLE 3.6-la d SAFETY RELATED HYDRAULIC'SNW BERS*

~

HIGH RADIATION StJUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR ZONE ESPECIALLY DIFFICULT 740. (Oty.) Off, LOCATION AND ELEVATION INACCESSIBLE OURING SHUTDOWN ** TO REMOVE Reactor Building ( A or I) (Yes or ib) (Yes or (b) tPCI System (Continued)

HPSEH-77 (1) 8'NR3-13'WRF, El. 123' A tb No IPSEH-80 (1) 11' tal3-6'ERH, El. 126' A tb tb iPSEH-81 (1) 12'tal3-5'ERL, El. 126' A No ib IPSEH-82 (1) 3'SRll-5'WRH, El. 123' A tb No HPSEH-83 (1) 6'NRll-l'ERF, El. 123' A c No No tFSEH-84 (1) 8'NRil-13'WRF, El. 123' A tb tJo u

HPSEH-85 (1) 7'fR11-11'WRF, El. 122' A tb No o, IPSEH-87 (1) l'SRll- 7'WRF, El. 125' A No No e iPSEH-88 (1) 12'NR2-12' WRL, El. 120' A No Ib

- iPSEH-89 (2) 11'SR2- 3' ERG, El. 123' A tb No S HPSEH-90 (1) 5'NR3-13' ERF, El. 125' A tb No iPSEH-91 (2) 5'SR3- 8' ERF, El. 123'-6" A No No HPSEH-92 (1) 8'tJR3- 3' ERH, El. 123' A tb No IPSEH-93 (1) 8'fR3- 3' ERH, El. 123' A tb tb RCIC System RCSEH-2 (1) 2'SR11-15' ERA, El. 101' A No Ib RCSEH-20 (1) 1.' NRll-14 ' ERA, El. 98' A tb tb RCSEM-21 (1) 7'SR 9- 5' ERA, El. 120' A tb Yes RCSEH-23 (2) 14'SR 7- 9' ERA, El. 122' A tb Yes 1

  • 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.

4

    • 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.

h

g  ? ,.

M

=

TABLE 3.6-la a

SAFETY RELATED HYDRAULIC StGBERS*

]

HICH RADIATI0tl St E BER SYSTEM StJUBBER It1 STALLED ACCESSIBLE OR ZOt1E ESPECIALLY DIFFICULT F 20. (Oty.) ON, LOCATION AtJD ELEVATION Il1 ACCESSIBLE DLRING SHUTDOWN ** TO REMOVE Heactor buildino (A or I) (Yes or tb) (Yes or ib)

RtB System RHRH-184 (1) 3'SR3-17'ERH, El. 90' A tb tb RHRH-185 (1) 3'SR3-17'ERH, El. 91' A tb tb RiiRH-186 (2) 0'SR3-12'ERH, El. 88' A tb tb RHRH-187 (2) 4'NR3- 8'ERH, El. 89' A ,.

tb tb RHRH-183 (1) 5'SRS- S'WRL, El. 90' A

'~

ib No a RHRH-189 (1) 2'tR5- 8'WRL, El. 90' A tb tb

, RHRH-192 (1) 9 ' f1R3-18 ' ERH , El. 123' A No No

, RHRH-193 (1) 9'tR3-17'ERH, El. 123' A tb tb

_ RHRH-195 (1) 6'SR3-18'WRL, El. 125' A No Ib p RHRH-196 (1) 6'SR3-18'WRL, El. 120' A tb tb RHRH-199 (1) 10'SR3- 3'WRL, El. 123' A tb ib RHRH-202 (1) 6'SR7- 7'ERH, El. 110' A tb tb RHRH-207 (2) 10'SR7-15'ERH, El. 151' A tb tb RHRH-209 (2) 6't1R3-16'WRL, El. 105' A tb No RHRH-210 (1) 9't1R3-16'WRL, El. 108' A No tb RHRH-211 (2) 7 ' t1R3-10 ' WRL , El. 100' A. tb tb RHRH-212 (1) 6't1R3-12'WRL, El. 104' A tb No RHRH-213 (1) 3'SR2-12'WRL, El. 124' A tb No RHRH-214 (1) 3'SR2- 2'WRL, El. 119' A No tb RHRH-215 (2) 3'SR2-12'WRL, El. 118' A tb tb

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

r ,..

N

=

a TABLE 3.6-la SAFETY RELATED HYDRAULIC SNtBBERS*

HICH RADIATION STAB 8ER SYSTEM StJUB8ER INSTALLED ACCESSIBLE OR ZONE ESPECIALLY DIFFICULT tJ0. (Oty.) ON, LOCATI0tJ AtJD ELEVATION INACCESSIBLE DURING SHUTDOWN ** TO REMOVE Reactor Building (A or I) (Yes or No) (Yes or No)

RFR Systen (Continued)

RHRH-216 (1) 11'tR3-16'WRL, El. 122' A No tb RHRH-217 (1) 11'NR3-19'WRL, El. 121' A tb tb RHRH-218 (1) 9'SR2-13'ERH, El. 116' A No ib RHRH-220 (1) 4'SR7-12'WRL, El. 126' A No No RHRH-221 (1) 2'SR7-10'WRL, El. 122' A ~6 No tb RHRH-222 (2) 2'SR7-10'WRL, El. 120' & 122' A No No u RHRH-223 (1) 1/2'tJRll-4'ERH, El. 125' A No tb h RHRH-224 (1) 3'SR11-7'ERH, El. 123' A No No i RHRH-225 (1) 9'tR13-13'ERH, El. 117' A tb No RHRH-226 (1) 12'SR11-19'WRL, El. 121' A tb No

? RHRH-227 (1) 12'SRll-17'WRL, El. 122' A tb No RHRH-228 (1) 3'tJR13-12'WRL, El. 124' A tb No RHRH-229 (1) 3'NR13-12'WRL, El. 120' A No No RHRH-230 (2) 3'NR13-12'WRL, El. 116' & 119' A tb No RHRH-231 (2) 9'SR11-17'WRL, El. 104' A No tb RHRH-232 (1) 9'SRll-17'WRL, El. 107' A No tb RHRH-233 (1) 7'SR11-10'WRL, El. 97' A No No RHRH-234 (1) 6'SRll-12'WRL, El. 104' A tb No RHRH-237 (2) 2'NR 9- 3'ERH, El. 155' A No No RHRH-238 (2) 2'tJR 9- 4 'WRH, El. 159' A No No

  • Snubbers may be added to safety related systems without prior Lic. nse 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.

.c ,..

5 N

=

, TABLE 3.6-la SAFETY RELATED HYDRAULIC StJUBBERS*

HIGH RADIATION STAJBBER SYSTEM StAJOBER INSTALLED ACCESSIBLE OR ZONE ESPECIALLY DIFFICULT NO. (Oty.) OtJ, LOCATI0t1 AtJD ELEVATION ItJACCESSIBLE DURING SHUTDOWN ** TO REMOVE Reactor Building ( A or I) (Yes or No) (Yes or No)

RHR Systen (Continued)

RHRH-239 (1) 2 ' tR 9- 4 ' WRH , El . 160 ' A No No RiiPH-240 (2) 6'tJR 5-25'WRL, El . 147' 4 tb No RHRil-242 (1) 3'SR 4- 4'WRH, El. 150' A No Ib RHRH-244 (2) 10'SRll- 4'ERF, El. 121' A tb tb RHRH-245 (1) 10'SRll- 3'ERF, El. 121' A ., No No RtiRH-246 (1) 10'SRll- 3'ERF, El. 122' A tb No RHRH-249 (1) ll'SRll-10'ERF, El. 118' A No ib F RtiRH-250 (2) 10'tB 3- 4'ERF, El. 121' A No tJo

' RHRH-251 (1) 10'tJR 3- 3'ERF, El. 119' A No No RtiRH-252 (1) 10'ta 3- 3'ERF, El. 121' A No No E RifRH-254 (1) ll'NR 3-10'ERF, El. 118' A fJo No RiiRH-279 (2) 3'SR 5- 3'WRL, El. 116' A No No RHRH-282 (1) 1/2'SR4- 7' ERG, El. 121' A No No tii."!H-286 (2) 3'SR 2-17'WRL, El. 116' A No No RHRH-288 (2) 3'ta 9- 3'WRL, El. 116' A No No RiiRH-292 (1) 4'SR 2- 6'ERH, El. 124' A No No RHRH-299 (1) 4'SR13- 6'ERH, El. 122' A No No Rif1H-305 (1) 5'ta 3- 4'ERH, El. 123' A No No RiiRH-306 (2) 3'NR 3- 7'ERH, El. 121' A No No RHRH-307 (1) 10'SR 5-17'ERH, El. 132' A No No RiiRH-309 (1) 9'SRll-18'ERH, El. 115' A No ib

  • Snubbers may be added to safet/ 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 colurm due to changes in high radiation areas may be made without prior Licmse Amendment provided that the revision to Table 3.6-la is included with the next License Amendment request.

.c ;.

k 0

TABLE 3.6 _a E

y SAFETY RELATED HYDRAULIC StJUBBERS*

HIGH RAOIATION S!AliEER SYSTEM StJUBBER INSTALLED ACCESSIBLE OR ZONE ESPECIALLY DIFFICULT to. (Oty.) 011, LOCATION Ato ELEVATION Ii1 ACCESSIBLE DlRING SHUTDOWN ** TO REMOVE Reactor Building (A or I) (Yes or No) (Yes or NO)

RtB Systen (Continued)

RERH-310 (1) 9'SRll-18'ERH, El. 124' A tb No RHRH-312 (1) 6'tRll-18'WRL, El. 124' A tb tb RHRH-313 (1) 6 'tEll-18 'WRL , El. 125' A tb tb

, RHRH-316 (1) 10' tall- 4'WRL, El. 123' A tb No RHRH-319 (2) 9'ta 9-17'ERH, El. 136' A No ib RIGH-320 (1) 4 'f all-17 ' ERH, El. 90' A tb No F RHRH-321 (1) 3'IRll-15'ERH, El. 91' A No ib RHRH-322 (2) 3'SRll-12'ERH, El. 89' A tb tb RHRH-323 (2) l'SRll- 9'ERH, El. 89' A No ib g RHRH-324 (1) 3'tR 9- 5'WRL, El. 91' A No No RHRH-325 (1) 2'SR 9- 9'WRL, El. 90' A tb tb RHRH-332 (1) 2'SR 6- 2'WRH, El. 190' A tb tb RHRH-344 (1) 1/2'tJR10-l'WRH, El. 122' A No No RHRH-348 (2) 3'tR13-17'WRL, El. 127' A No tb RHRH-399 (1) 6'NR 5- 6'ERH, El. 148' A No ib RHRH-400 (1) 6'tR 5- l'ERH, El. 148' A tb tb

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

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

e r

TABLE 3.6-lb k

Q SAFETY RELATED ECHANICAL SNUBBERS

  • s HIGH RADIATION

@ SNUB 8ER SYSTEM SNUB 8ER INSTALLED ACCESSIBLE OR ZONE ESPECIALLY DIFFICULT y NO. (Qty.) ON, LOCATION Ato ELEVATION INACCESSIBLE DURING SHUTDOWN ** TO REMOVE

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

Nuclear Boiler System B21-OFDH-16 (1) 6'SR7-27'WRF,El.131'-5" I No Yes 821-OFDH-33 (1) 2 'tR7- 2 ' ERE , El .132 '-2" I No Yes 821-OFDH-43 (1) 2'-10"SR7-3' ERA,El.134'-5" I No Yes 821-DFDH-43 (1) 4'-2"SR7-3' ERA,El.134'-5" I No Yes B21-FDH-20 (1) Az.2620,El.149'-9" I No Yes B21-X28-lF19-H001 (1) Az.1800,E1.192'-0" I No Yes 821-X28-lF19-H001A (1) Az.1800,E1.193'-0" I No Yes F B21-X29-1F17-H002 (1) Az. 100,El.173'-0" I No Yes

  • 821-X29-lF17-H003A (2) Az. 00,El.168'-0" I No Yes 8

821-X29-1F17-H00LB (2) Az. 00,El.182'-0" I No Yes g 021-X29-lF17-H003C (2) Az. 00,El.177'-0" I No Yes

.a B21-X28-1F19-H004A (2) Az.1800,El.177'-0" No I Yes B21-X28-lF19-H0048 (2) Az.1800,El.182'-0" I No Yes 821-X28-lF19-H004C (2) Az.1800,El.188'-0" I No Yes B21-X29-lF24-H002 (1) Az. 00,El.192'-0" I No Yes 821-X29-lF24-H003 (1) Az. 00,El.192'-0" I No Yes 821-X29-lF18-H004 (1) Az. 40,El.173'-0" I No Yes B21-FS-H005 (1) Az. 00,El.197'-0" I No Yes 821-F22-H001 (1) Az. 00,El.138'-0" I No Yes B21-F23-H001 (1) Az. 00,El.137'-0" I No Yes

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

h TABLE 3.6-lb 9 .

, SAFETY RELATED WCHANICAL SNUBBERS

  • kH HIGH RADIATION SPCJBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR ZONE ESPECIALLY DIFFIQJLT

~~

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

Nuclear Boiler System Continued) 821-F24-H001 (1) Az. 00,El.137'-0" I No Yes B21-F25-f001 (1) Az. 00,El.137'-0" I No Yes 821-F38-H005 (1) 3'-6"tR7-8' ERA,El.133'-0" I No Yes 821-F38-H005 (1) 8' ERA-6'-5"SR7,El.133'-0" I No Yes 821-F16-H003 (1) Az. 400,El.190'-0" I No Yes B21-FS-H020 (1) Az. 450,E1.201'-0" I No Yes a B21-F5-H021 (1) Az. 450,E1.201'-0" I No Yes cn

, Recirc System k B31-X31-lFS-H001 (2) Az. 900,El.124'-O" I No Yes B31-X33-lF5-H001 (1) Az. 900,E1.132'-0" I No Yes 831-X32-lF6-H001 (1) Az.2900,El.123'-0" I No Yes B31-X32-]F6-H002 (1) Az.2950,El.121'-O" I No Yes 831-X32-lF7-H001 (1) Az.3400,El.ll6'-O" I No Yes B31-X34-1F16-H001 (1) Az.1350,El.124'-0" I No Yes 831-X28-lF16-H811 (1) Az.2170,El.172'-0" I No Yes B31-X28-lF16-H812 (1) Az.2170,El.172'-0" I No Yes B31-F3-H800 (1) Az.3150,El.115'-0" I No Yes B31-F14-H800 (1) Az.1800,El.115'-0" I No Yes

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

r ,

g TABLE 3.6-lb a

O SAFETY RELATED W CHANICAL SNUBBERS

  • 8 5 HIGH RADIATION

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

RFE System Ell-F20-H001 (1) 22'SR7-23'ERH,El.139'-0" I No Yes E11-F208-H001 (1) Az.2700,El.138'-0" I No Yes Ell-RHR-405 (1) Az.1550,El.211'-2" I No Yes Core Spray System y E21-F1-H001 (2) Az. 800,El.175'-0" I No Yes e E21-F1-H002 (2) Az.2700,E1.174'-0" I No Yes l

g RCIC System u

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

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

r

{n TABLE 3.6-lb f

SAFETY RELATED KCHANICAL SNLEBERS*

E HIGH RADIATION -

4 StAJB8ER SYSTEM StAJBBER INSTALLED ACCESSIBLE OR ZONE ESPECIALLY DIFFICULT

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

Equipment & Floor Drain System T45-F17-H001 (1) Az. 900,El.ll7'-0" I No Yes RER System E11-F8-FOO1 (1) 22'SR7-23'ERH,El.123'-0" A No No Ell-F93-H001 (1) 17'tR7-24'WRL,El.124'-0" A No No

{ Ell-F93-H002 (1) 17'NR7-24'WRL,El.122'-0" A No No

[ Primary Containment Purge & Inerting System T48-F30-H001 (1) Az. 450,El.120'-0" A No No T48-F30-F002 (1) Az. 450,El.120'-0" A No No

  • Snthbers 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.
  • M4odifications to this column due to changes in high radiation areas may be made without prior License Mendment provided that the revision to Table 3.6-lb is included with the next License Amendment request.

O

( 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 cystems is maintained during and following a seismic or other event initiating dynamic loads. Snubbers excluded from this inspection program are those installed on nonsafety-related systems and then only if their failure or failure of the system on which they are installed, would have no adverse effect on any safety-related system.

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

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

When a snubber is found inoperable, an engineering evaluation is performed, in addition to the determination of the snubber mode of failure, in order to 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

l 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 a rea , 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.

l l

1 l

HATCH-UNIT 1 3.6-32

t )

q ADMINISTRATIVE CONTROL RECORD RETENTION (Continued)

c. Records of radiation exposure for all individuals entering radiation control areas.
d. Records of gaseous and liquid radioactive material released to the environs.
e. Records of transient or operational cycles for those unit components identified in Table 5.7.1-1.
f. Records of reactor tests and experiments.
g. Records of training and qualification for current members for the unit staff.
h. Records of in-service inspections performed pursuant to these Technical Specifications.
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 'he PRB and SRB.
1. Records of the service lives of all hydraulic and mechanical snubbers listed on Tables 3.6-la and 3.6-lb including the date at which the service life commences and associated installation and maintenance records.

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

6.12 HIGH RADIATION AREA 6.12.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.203(c)(2) of 10 CFR20, each high radiation-area in which the intensity of radiation is greater than 100 mrem /hr but less than 1000 mrem /hr shall be barricaded and conspicuously posted as a high radiation l

area and entrance thereto shall be controlled by -aquiring issuance of a Radiation Work Permit *. Any individual or group of individuals permitted

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

HATCH-UNIT 1 6-20

GeorgiaPower d ATTACFNENT 3 NRC DOCKET 50-366 OPERATING LICENSE NPF-5 EfMIN I. HATCH NUCLEAR PLANT UNIT 2 PRC&OSED CHANGES TO TECHNICAL SPECIFICATI0t6 The proposed change to Technical Specifications (Appendix A to Operating License NPF-5) would be incorporated as follows:

Remove Page Insert Page VIII VIII XIII XIII 3/4 7-11 through 3/4 7-15 3/4 7-11 through 3/4 7-15 3/4 7-16 3/4 7-16 3/4 7-16a through 3/4 7-16d 3/4 7-17 3/4 7-17 3/4 7-17a through 3/4 7-171 3/4 7-18 3/4 7-18 3/4 7-18a B3/4 7-2 83/4 7-2 B3/4 7-3 B3/4 7-3 6-18 6-18

-_- . _ _ _ . _ ~_ . - _ _ _ _ _ _

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.7 PLANT SYSTEMS a

3/4.7.1 SERVICE WATER SYSTEMS Residual Heat Removal Service Water System. . . . . . . . . . . . . . 3/4 7-1 4

Se rv i ce 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 SNUB B E RS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 7- 1 1 3/4.7.5 SEALED SOURCE CONTAMINATION............................. 3/4 7-19 3/4.7.6 FIRE SUPPRESSION SYSTEMS Fire Suppression Water Sys tem. . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 7-21 S p ri nk l e r Sy s tems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/ 4 7- 2 5 Low Pressure C02 Systems................................ 3/4 7-27 ,

" Fi re Hos e S ta tions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 7- 28 j 3/4.7.7 PENETRATION FIRE BARRIERS............................... 3/4 7-30 3/4.7.8 SETTLEMENT OF CLASS I STRUCTURES........................ 3/4'7-31 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES A. C. Sources-0pera ti n9. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 8- 1 A.C. Sources-Shutdown................................... 3/4 8-9  !

3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS t

A.C. Dis tribu tion - Opera ti ng. . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 8-10 A.C. Di s tribu tion - Shu tdown. . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 8-12 0.C. Di s tribu tion - 0pera ting. . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 8-13

0. C. Di s tribu tion - Shu tdown. . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 8-16 A.C. Circui ts Inside Primary Contai nment. . . . . . . . . . . . . . . . 3/4 8-17 '

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

I HATCH-UNIT 2- VIII

, as- w m m&. u w m " + ' * '

. ----- . .- ~

fNDEX BASES SECTION PAGE PLANT SYSTEMS (Continued) 3/4.7.3 REACTOR CORE ISOLATION C0OLING SYSTEM............... B 3/4 7-1 a

j 3/4.7.4 S NUB B ERS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 7- 2 l ,

3/4.7.5 SEALED SOURCE CONTAMINATION. . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 7-3 3/4.7.6 FIRE SUPPRESSION SYSTEMS. . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 7-3 3/4.7.7 PENETRATION FIRE BARRIERS........................... B 3/4 7-4 3/4.7.8 SETTLEMENT OF CLASS I STRUCTURES.................... B 3/4 7-4  !

3/4.8 . ELECTRICAL POWER SYSTEMS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 8-1 3/4.9 REFUELING OPERATIONS 3/4.9.1 REACTOR MODE SWITCH. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 9-1 ,

3/4.9.2 INSTRUMENTATION..................................... B 3/4 9-1 3/4.9.3 CONTROL R00 P0SITION. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 9-1 3/4.9.4 DECAY TIME.......................................... B 3/4 9-1 ,

j 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 R0D REM 0 VAL. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B - 3/4 9-2 3/4.9.12 REACTOR COOLANT CIRCULATION. . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 9-3 P

3/4.10 SPECIAL TEST "XCEPTIONS 3/4.10.1 PRIMARY CONTAINMENT INTEGRITY....................... B 3/4 10-1 3/4.10. 2 R00 SEQUENCE CONTROL SYSTEM. . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 10-1

3/4.10.3 SHUTD0WN MARGIN DEMONSTRATIONS. . . . . . . . . . . . . . . . . . . . . . B 3/4 10-1 3/4.10.4 RECIRCULATION L00PS. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4.10-1 i

HATCH --UNIT 2 XIII

PLANT SYSTEMS 3/4.7.4 SNUBBERS LIMITING C0tOITION FOR OPERATION 3.7.4 All snubbers listed in Tables 3.7. A-la and 3.7.4-lb shall be OPERABLE.

APPLICABILITY: Conditions 1, 2, and 3.

ACTION:

With one or more snubbers inoperable, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> replace or restore the inoperable snubber (s) to OPERABLE status and perforra 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.

.w SURVEILLANCE REQUIREMENTS 4.7.4 Each snubber shall be demonstrated OPERABLE by performance of the following inservice inspection program and the requirements of Specification 4.0.3.

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:

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

0 18 months + 25%

1 12 months T 25%

2 6 months I 25%

3, 4 124 days i25%

5,6,7 62 days 1 25%

8 or (nore 31 days 1 25%

4-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.

l *The inspection intervai snall not ce lengthened more than one step at a time.

  1. The provisions of Specification 4.0.2 are not applicable.

HATCH-UNIT 2 3/4 7-11

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

b. Visual Insoection Acceotance Criteria Visual inspections shall verify (1) that there are no visible indications of damage or impaired OPERABILITY, (2) attachments to the foundation or supporting structure are secure, and (3) for mechanical snubbers where snubber movement can be manually induced, the snubbers shall be inspected as follows: (a) At each refueling, safety-related systems associated with the snubbers listed in Table 3.7.4-lb shall be inspected to determine if there has been a severe dynamic event. (b) In the event of a severe dynamic event, snubbers in that system which experienced the event shall de inspected during the refueling outage to assure the snubbers have freedom of movement and are not frozen up. The inspection shall consist of verifying freedom of motion using one of the following:

(1) Manually induced .-snubber movement; (ii) stroking the mechanical snubber through its full range of travel. If one or more mechanical snubbers are found to be frozen up during this inspection, those snubbers shall be replaced (or overhauled) before returning to power. Re-inspection shall

, subsequently be performed according to the schedule of 4.7.4.a, but the scope of the examination shall be limited to the safety-related systems associated with the snubbers listed in Table 3.7.4-lb. Snubbers which appear inoperable as a result of visual inspections may be determined OPERABLE for the purpose of establishing the next visual inspection interval, providing that (1) the cau's e of the rejection is clearly established and remedied for that particular snubber and for other snubbers that may be generically susceptible; and (2) the affected snubber is functionally tested in the "as found" condition and determined OPERABLE per Specification 4.7.4.d or 4.7.4.e, as applicable. However, if a hydraulic snubber is found to contain less than the required minimum volume of reserve fluid or if visible signs of leakage are present, the snubber shall be determined inoperable and cannot be determined OPERABLE via functional testing for the purpose of establishing the next visual inspection interval. All snubbers connected to an inoperable common hydraulic fluid reservior shall be counted as inoperable snubbers.

c. Functional Tests At least once per 18 months during shutdown *, a representative sample of 10% of the total of each type (hydraulic or mechanical) Safety-related snubber in use in the plant shall be
  • The requirements of this section for functionally testing mechanical l snubbers may be waived pending acquisition of a conversion module for existing snubber test equipment or new test equipment by the next refueling outage.

HATCH-UNIT 2 3/4 7-12 .

l

PLAf1T SYSTEMS SURVEILLAfJCE REQUIREMENTS (Continued) functionally tested either in place or in a bench test. For each snubber that does not meet the functional test acceptance criteria of Specification 4.7.4.d or 4.7.4. e, an additional sample of at least 1/2 the size of the initial lot of that type of snubber shall be functionally tested.

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

The representative sample selected for functional testing shall include the various configurations, operating environments and the range of size and capacity of snubbers.

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

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

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

If any snubber selected for functional testing either fails to lockup or fails to move, i.e., frozen in place, the cause will be evaluated arid if caused by manufacturer or design deficiency all snubbers of the same design subject to the same defect shall be functionally tested. This testing requirement shall be independent of the requirements stated above for snubbers not meeting the functional test criteria.

For the snubber (s) found inoperable, an engineering evaluation shall be performed on the components which are supported by the snubber (s). The purpose of this engineering evaluation shall be to determine if the components supported by the snubber (s) were adversely affected by the inoperability of the snubber (s) in order to ensure that the supported component remains capable of meeting the designed service.

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

HATCH-UNIT 2 3/4 7-13

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

d. Hydraulic Snubbers Functional Test Acceptance Criteria The hydraulic snubber functional test shall verify that:
1. Activation (restraining action) is achieved within the specified range of velocity or acceleration in both tension and compression.
2. Snubber bleed, or release rate, where required, is within the specified range in compression or tension. For snubbers specifically required to not displace under continuous load, the ability of the snubber to withstand load without displacement shall be verified.
e. Mechanical Snubbers Functional Test Acceptance Criteria The mechanical snubber functional test shall verify that:
1. The snubber operates freely over the stroke in both tension and compression.
2. The force that initiates free movement of the snubber rod in either tension or compression is less than the specified maximum drag force. Specified maximum drag force is nominally five (5) pounds or one percent (1%) of rated snubber load, whichever is greater.
f. 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 4.7.4.a may be re-entered on a 6-month inspection interval for the inaccessible snubbers.

( g. Snubber Service Life Monitoring i

j A record of the service life of each snubber, the date at l which the designated service life commences and the l installation and maintenance records on which the designated

! service life is based shall be maintained as required by l Specification 6.10.2.1.

! HATCH - UNIT 2 3/4 7-14 l

l

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) _

Concurrent with the inservice visual inspection performed at the end of the 2nd refueling cycle and at least once per 18 months thereafter, the installation and maintenance records for each snuboer 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.

HATCH - UNIT 2 3/4 7-15

TABLE 3.7.4-la 5 -

F1 SAFETY RELATED HYDRAULIC SNUBRERS*

i: O E HIGH RADIATION Cl SNUBBER SYSTEM SNUBBER INSTALLED ACCESSISLE OR 70NE ESPECIALLY DIFFICULT m NO. (Oty.) ON. LOCATION AND ELEVATION INACCESSIBLE DURING SHUTDOWN ** TO REMOVE Reactor Building (A or I) (Yes or No) (Yes or No) 2 Ell-RHR SYSTEM R86 (1) 8 ' NR19 - l ' ERJ, El . 212' A No No R88 (1) 10' HR17 - 3' WRJ, El .119' A No No R90 (1) R15 - 3' ERH, El .119' A ., No No R93 (2) 8' SRl4 - 11' ERF, El. 118' A No No R94 (1) 8' SRl4 - 10' ERF, El .118' A

No No R98 (2) 10' SR19 - l ' ERJ, El . 121 ' A No No R100 (1) 10' SR21 - 3' WRJ, El .119' A No No R101 (1) 12' SR21 - S' WRJ, El .119' A No No ig R102 (1) R23 - 3' ERH, El .119' A No No R128 (1) 6' NR23 - 16' ERF, El .123' A No No y R129 (2) 18' SR21 - 16' ERF, El .123' A No No g R146 (2) 5' SR21 - 8' WRL, El. 120' A No Yes R221 (1) 18' NR19 - 12' WRL, El. 90' A No No R222 (1) 18' SR19 - 12' WRL, El . 90' A No No R223 (1) 18' SR14 - 23' WRL, El. 90' A No No R227 (1) 18' NR24 - 23' WRL, El . 90' A No No R231 (2) 3' SRl9 - 9' WRL, El .102' A No No R238 (2) 12' SRIS - 3' WRL, El .107' A No Yes R241 (2) 3' NR23 - 9' WRL, El .102' A No No R245 (2) 12' NR23 - 3' WRL, El .107' A No Yes

  • Snubbers may be added to safety related systems without prior License Amendment to Table 3.7.4-la provided that a revision to Table 3.7.4-la is included with the next License Amendment request.
    • Modifications to this column due to changes in high radiation areas may be made without prior License Amendment provided that the revision to Table 3.7.4-la is included with the next License Amendment request. -

t

TABLE 3.7.4-la SAFETY RELATED HYDRAULIC SNUBBERS *

[

HIGH RADIATION

., SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR 70NE ESPECIALLY DIFFICULT H fl0. (Qty.) Oil, LOCATION AND ELEVATION INACCESSIBLE DURING SHUTDOWN **

TO REMOVE N Reactor Building (A or I) 7 Yes or No) ~ (Yes or No) 2 Ell-RHR SYSTEM (Continued)

R250 (1) 11 ' SR14 - 15' WRL, El .119' A No No R251 (2) 11 ' SR14 - 15' WRL, El .120' A No No R252 (1) 15' SRl4 - 15' WRL, El .112' A No No '

R253 (1) 15' SRl4 - 15' WRL, El .120' A No No R254 (1). 17' SRl4 - 17' WRL, El .112' A No No R256 (1) 17' SR14 - 17' WRL, El .112' A No Yes R258 (1) 22' SR14 - 13' WRL, El . 99' A v No No R264 (1) 21 ' SR14 - 9' WRL, El .104' A No Yes R267 (2) 15' SR14 - 3' WRL, El .102' A No No w R268 (1) 11 ' NR24 - 15' WRL, El .119' A No No S R269 (2) 11 ' NR24 - 15' WRL, El .120' A No No u R270 (1) 15' flR24 - 15' WRL, El .112' A No No 1 R271 (1) 15' flR24 - 15' WRL, El .120' A No No

$ R272 (1) 17' NR24 - 17 ' WRL, El .112' A No No R274 (1) 17' NR24 - 17' WRL, El .112' A No flo l R276 (1) 22' NR24 - 13' WRL, El. 99' A No No l R282 (1) 21' NR24 - 9' WRL , El . 104 ' A No Yes R285 (2) 15' NR24 - 3 ' WRL, El .102' A No No R315 (2) 10' flR19 - 6' ERJ, El. 123' A No flo l R374 (2) 23' SR14 - 15' WRL, El .106' A No Yes

  • Snubbers may be added to safety related systems without prior License Amendment to Table 3.7.4-la provided that a revision to Table 3.7.4-la is included with the next License Amendment request.
    • Modifications to this column due to changes in high radiation areas may be made without prior License Amendment provided that the revision to Table 3.7.4-la is included with the next License Amendment request.

._. . . _ _ - _ .. . . _. - - . ~

TABLE 3.7.4-la .

x h SAFETY RELATED HYDRAULIC SNUBBERS * '

? -

s HIGH PADIATION

  • SfiUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR ZONE NO. (Qty.) ESPECIALLY DIFFICULT

" ,0N, LOCATION AND ELEVATION INACCESSIBLE DURING SHUTDOWN ** TO REMOVE Reactor Buildirig (A or I) (Yes or Nc) (Yes or No) 2 Ell-RHR SYSTEM (Continued)

R375 (2) 23' SR14 - 12' WRL, El .108' A No No R376 (1) 23' SR14 - 12' WRL, El. 109' A No No R377 (2) 23' NR24 - 15' WRL, El .106' A No Yes R378 (2) -

23' flR24 - 12' WRL, El .108' A No No R379 (1) 23' NR24 - 12' WRL, El. 109' A flo No 2E11-RHR SERVICE WATER SYSTEM u R 15 (2) 7' SR14 - 11' ERH, El .115' A No S R 23 (2) 7 ' tiR24 - 11 ' ERH, El .115' A No No No 2E21-CORE SPRAY SYSTEM R 35 (1) 8' SR14 - 6' WRL, El. 95' A No No R 40 (1) 7' SR14 - 31' WRL, El. 95' A No No R 53 (2) 10' SR14 - 6' WRL, El .106' A No No R 72 (2) 10' NR24 - 6' WRL, El. 102' A No No R 80 (1) 8' NR24 - 6' WRL, El. 95' A flo No

R 87 (1) 7' NR24 - 6' WRL, El. 90' A flo No R107 (2) 39' NR24 - 15' WRL, El .123' A No No
  • Snubbers may be added to safety related systems without prior License Amendment to Table 3.7.4-la provided that a revision to Table 3.7.4-la is included with the next License Amendment request.
    • Modifications to this column due to changes in high radiation areas may be made without prior License Amendment provided that the revision to Table 3.7.4-la is included with the next License Amendment request.

f

~

TABLE 3.7.4-la

  • k SAFETY RELATED HYDRAULIC SNUBBERS * ,

9

a. . HIGH RADIATION

= SNUBBER SYSTEM SilVBBER INSTALLED ACCESSIBLE OR 70NE ESPECIALLY DIFFICULT

  • fiO. (Qty.) ON, LOCATION AND ELEVATION IllACCESSIBLE DURING SHUTDOWN ** TO REMOVE N

Reactor Building (A or I) (Yes or No) (Yes or flo) 2T46-SGTS SYSTEM R 65 (2) 6' flR24 - 9' WRB, El .198' A No Yes R 66 (1) 2' NR24 - 9' WRB, El .186' A No No R 67 (1) 2 ' flR24 - 9' WRB , El . 180' A flo Yes R 68 (2) 6' NR24 - 9' ERA, El .198' A No Yes R 69 (1) 2' NR24 - 9' ERB, El. 186' A No No R 70 (2) 2' NR24 - 9' ERA, El .179' A No Yes 5 2831-REACTOR RECIRCULATION SYSTEM

$ SSAl (1) Az 315 , El. 117' I No No R SSA2 (1) Az 328 0, El. 125' I No Yes SSA3 (1) Az 3020, El. 125' I No Yes SSA4 (1) Az 3280, E1. 131 ' I  !!o Yes SSA5 (1) Az 3010, E1. 131 ' I flo No SSA6 (1) Az 3150 El . 137 ' I No Yes SSA7 (1) Az 0180, El . 124 ' I No Yes SSA8 (1) Az 342 0, El .123' I flo Yes SSA12 (1) Az 2550, El. 129' I No No SSA13 (1) Az 2850, El. 129' I flo No SSA14 (1) Az 2700, El . 121 ' I No No SSA15 (1) Az 3230, El. 144' I i'o Yes SSA16 (1) Az 2170, El. 144' I No Yes

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

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

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

6 TABLE 3.7.4-la

$ SAFETY RELATED HYDRAULIC SNUBBERS

  • c HIGH RADIATION

= SHUBBER SYSTEM ShUBBER INSTALLED . ACCESSIBLE OR 7.ONE ESPECIALLY DIFFICULT

-4 NO. (Qty.) Ott, LOCATI0il AND ELEVATION INACCESSIBLE DURiflG SHUTDOWN **

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

SSA17 (1) Az 2700, El. 125' I No Az 2700, El . 138 ' Yes SSA19 (1) I No Yes SSA20 (1) Az 2700, El. 138' I No 00, El . 14 0 ' Yes SSA21 (1) Az I No Yes SSA22 (1) Az 00, El . 140' I No Az - 1350, . El . 117 ' Yes 55B1 (1) I No ho SSB2 (1) Az 1480, El. 125' I No Yes SSB3 (1) Az 1220, El. 125' I No Yes SSB4 (1) Az 1480 El . 131 ' I fio Az 1220, El. 131' Yes t'

  • SSBS (1) I No No SSB6 (1) Az 1350, El . 137' I No Yes

.7' SSB7 (1) Az 1980 El. 124' I fio Yes E

" SSB8 (1) Az 1620, El . 123 ' I Mo Az 0750, El. 129' Yes SSB12 (1) I No No SSB13.(1) Az 1050, El. 129' I No llo SSB14 (1) Az 0900, El. 121' I No No 55815 (1) Az 1430, El. 144' I No Az 0370, El. 144' Yes SSB16 (1) I No Yes SSB17 (1) Az 900, El. 126' I No Az 900, E1. 138 ' Yes SSB19 (1) I No Az 900, El. 138' Yes SSB20 (1) I No Yes SSB21 (1) Az 1800, El. 140' I No Yes SSB22 (1) Az 1800, El. 140' I No Yes

  • Snubbers may be added to safety related systems without prior License Amendment to Table 3.7.4-la provided that a revision to Table 3.7.4-la is included with the -next License Amendment request.
    • Modifications to this column due to changes in high radiation areas may be made without prior License Amendment provided that the revision to Table 3.7.4-la is included with the next License Amendment request.

TABLE 3.7.4-lb 5 '

g .

SAFETY RELATED MECHANICAL SNUBBERS * '

? '

E HICH RADIATION 5 StJUBSER SYSTEM StJUBBER INSTALLED ACCESSIBLE OR ZONE ESPECIALLY DIFFICULT y 14 0 . (Oty.)- Otl, LOCATIOt1 Ato ELEVATION INACCESSIBLE DtJ11tC SHUTDOWN ** TO REMOVE Reactor Building (A or I) (Yes or tJo) (Yes or tJo) 2821-fluclear Boiler System MS-R34 (1) Az. 1100 El. 155' I tb Yes MS-R35 (1) Az. 1450 El. 150' I tJo Yes MS-R36 (1) Az. 1450 El. 150' ' I ib Yes MS-R37 (2) Az. 1450 El. 150' I tb Yes ,

MS-R38 (2) Az. 720 El. 167' I y No Yes MS-R39 (2) Az. 950 El. 150' I No Yes MS-R41 (1) Az. 1000 El. 150' I tb Yes u MS-R42 (1) Az. 1400 El. 150' I No Yes 3 MS-R43 (1) Az. 1300 El. 150' I tb Yes y MS-R44 (2) Az. 1400 El. 150' I No Yes MS-R45 (1) Az. 2500 El. 156' I tb Yes MS-R46 (1) Az. 2500 El. 156' I No Yes MS-R47 (1) Az. 2200 El 150' I No Yes MS-R48 (1) Az. 2200 El. 150' I ib Yes MS-R49 (2) Az. 2880 El. 167' I No Yes MS-R50 (2) Az. 2700 El. 150' I tb Yes MS-RS2 (1) Az. 2650 El. 150' I ib Yes MS-R53 (2) Az. 2350 El. 150' I No Yes MS-RS4 (1) Az. 2350 El. 150' I No Yes MS-RSS (1) Az. 2350 El. 150' I No Yes

  • 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 3.7.4-101s included with the next License Amendment request.

TABLE 3.7.4-lb E -

g ..

SAFETY RELATED tECHANICAL SNUBBERS

  • Y E HIGH RADIATION-3 SNUBBER SYSTEM SNUBBER It1 STALLED ACCESSIBLE OR ZOtE ESPECIALLY DIFFICULT

,y f40. (Oty.) Ott, LOCATI0tl AfD ELEVATI0t1 INACCESSIBLE OURING SHUTDOWN ** TO REMOVE Reactor Buildiry; (A or I) (Yes or tJo) (Yes or No) 2B21-tbelear Boiler System (Continued)

MSRV-R36 (1) Az. 2300 El. 137' I tb Yes MSRV-R37 (1) Az. 2300 El. 133' I tb Yes MSRV-R38 (1) Az. 2300 El. 133' I tb Yes-MSRV-R40 (1) Az. 2300 El. 125' I tb Yes MSRV-R41 (1) Az. 2250 El. 122' I .;

. tb Yes MSRV-R45 (2) Az. 1650 El. 119' I No Yes MSRV-R46 (2) Az. 2500 El. 155' I ib Yes u MSRV-R50 (1) Az. 2700 El. 150' I No Yes D MSRV-R52 (2) Az. 1950 El. 150' I No Yes u MSRV-R53 (1) Az. 1050 El. 149' I tb Yes b MSRV-R54 (1) Az. 800 El. 137' I ib Yes E MSRV-RS6 (1) Az. 700 El. 131' I tb Yes MSRV-R57-(1) Az. 700 El. 135' I tb Yes MSRV-R58 (1) Az. 700 El. 125' I No Yes MSRV-R59 (2) Az. 1250 El. 154' I No Yes MSRV-R60 (2) Az. 1200 El 152' I No Yes MSRV-R62 (1) Az. 900 El. 131' I No Yes MSRV-R63 (1) Az. 900 El. 132' I No Yes MSRV-R64 (1) Az. 900 El. 125' I No Yes MSRV-R65 (1) Az. 1000 El. 120' I tb Yes

  • Snubbers may be added to safety related systems without prior License Amendment to Table 3.7.4-Ib provided that- a rev'sion to Table 3.7.4-lb is included with the next License Amendment request.
    • Modifications to this column due to changes in high radiation areas may be made without prior License Amendment provided that the revision to Table 3.7.4-lb is included with the next License Amendment request.
{ , _

._ . _ _ . _ _ _ ~

' TABLE 3.7.4-lb.

x -

M SAFETY RELATED MECHANICAL StJLEBERS*

-Q -

!=- HICH RADIATION 35 StJUBBER SYSTEM StAJB8ER INSTALLED ACCESSIBLE OR ZONE

" ESPECIALLY DIFFICULT

_t10. (Oty.) ON, LOCATION Ato ELEVATION INACCESSIBLE DlRING SHUTDOWN ** TO REMOVE Heactor Building (A or I) (Yes or NO) (Yes or No) 2B21-Nuclear Boiler System (Continued)

MSRV-R67 (2) Az.'2350 El. 146' I No Yes MSRV-R68-(1) Az. 2350 El. 146' I No Yes MSRV-R69 (1) Az. 2350 El. 141' I No Yes MSRV-R70 (1) Az. 2350 El. 137' I ., No Yes MSRV-R71 (1) Az. 2450 El. 133' I ib Yes MSRV-R72 (1) Az. 2450 El. 133' I ib Yes MSRV-R73 (1) Az. 2450 El. 130' I No Yes u MSRV-R75 (1) Az. 2550 El. 154' I tJo Yes 2 MSRV-R76 (1) Az. 2500 El. 146' I tJo Yes y MSRV-R77 (1) Az. 2500 El. 137' I No Yes

,L MSRV-R78 (1) Az. 2500 El. 136'. I No Yes j MSRV-R79 (1) Az. 2500 El. 133' I flo Yes MSRV-R80 (1) Az. 2500 El. 132' I No Yes MSRV-R82 (1) . Az. 950 'El. 148' I tJo Yes

.MSRV-R83 (2) Az. -950 El. 145' I No Yes MSRV-R84 (1) Az. 900 El. 137' I No Yes Az. 650 El. 132' MSRV-R87 (1) I flo Yes MSRV-R88 (1) Az. 650 El. 127' I ilo Yes MSRV-R89 (1) Az. 650 El. 125' I No Yes MSRV-R90 (1) Az. 1150 El. 145' I No Yes -

  • Snubbers raay 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.

    • t-bdifications 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.

b m., ,. - , - , - -

TABLE 3.7.4-lb _

27 -

g. SAFETY RELATED MECHANICAL StAE8ERS* _

E HICH RAOIATION Z Sta)BBER SYSTEM StAE8ER INSTALLED ACCESSIBLE OR ZONE ESPECIALLY DIFFICULT ro PJO. (Oty.)

ON, LOCATION AtO ELEVATION INACCESSIBLE DURING SHUTDOWN ** TO REMOVE Reactor Building (A or I) (Yes or No) (Yes or flo) 2821-tbclear Boiler System (Continued)

MSRV-R91 (1) Az. 1100 El. 137' I ib Yes MSRV-R92 (1) Az. 1100 El. 132' I ib Yes MSRV-R93 (1) Az. 1100 El. 125' I tb Yes MSRV-R94 (1) Az. 950 El. 120' I -

tb Yes MSRV-R96 (2) Az. 2850 El. 152' I tb Yes MSRV-R97 (1) Az. 2850 El. 152' I tb Yes MSRV-R98 (1) Az. 2900 El. 150' I ib Yes 11SRV-R99 (2) Az. 3200 El. 150' I tb Yes t'

  • MSRV-R100 (1) Az. 3300 El. 146' I No Yes MSRV-R101 (1) Az. 3300 El. 140' I tb Yes I' MSRV-R103 (1) Az. 3400 El. 129' I tb Yes O

" MSRV-R104 (2) Az. 3400 El. 126' I tb Yes MSRV-R105 (1) Az. 750 El. 152' I tb Yes itSRV-R106 (1) Az. 750 El. 152' I tb Yes-MSRV-R107 (1) Az. 600 El. 150' I No Yes 4

!1SRV-R108 (2) Az. 300 El. 150' I tb Yes NSRV-R109 (1) Az. 300 El. 150' I tb Yes MSRV-R110 (1) Az. 250 El. 137' I ib Yes MSRV-Rill (1) Az. 220 .El. 132' I tb Yes MSRV-R113 (1) Az. 2700 El. 154' I ib Yes

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

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

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

. TABLE 3.7.4-lb SAFETY RELATED MECHANICAL SNUBBERS

  • x ~

h O HIGH RADIATION

, StJUBBER SYSTEM SNUBBER It1 STALLED ACCESSIBLE OR ZONE ESPECIALLY DIFFICULT

" rJ0. (Oty.) Ort, LOCATION Ato ELEVATI0t1 INACCESSIBLE DURItJG SHUTDOWN ** TO REMOVE Reactor Building (A or I) (Yes or No) (Yes or f40) 4 2821-tuclear Boiler System (Continued)

MSRV-R114 (1) Az. 2700 El. 146' I No Yes

MSRV-Rll5 (1) Az. 2700- El. 137' I No Yes

.MSRV-R116 (1) Az. 2700 El. 133' I tb Yes MSRV-R118 (1) Az. 2700 El. 125' I No Yes t1SRV-R119 (1) -Az. 2700 El. 120' I c. No Yes MSRV-R121 (2) Az. 2300 El. 141' I No Yes RFW-20 (2) Az. 1000 El. 150' I tb Yes w RFW-31 (2) Az. 2600 El. 150' I ib Yes Y S67-H10 (1) Az. 1670 El 134' I flo Yes u S67-Hil (1) Az. 1140 El. 135' I tJo Yes 1 S67-H12 (1) Az. 450 El. 136' I No Yes

, 5 S67-H13 (1) Az. 320 El. 136' I No Yes >

567-H14 (1) Az. 220 El. 136' I tb Yes '

5128-14 (1) Az. 2400 El. 192' I tb Yes

$143-H1 (1) Az. 400 El. 195' I tb Yes S143-H2 (2) Az. 300 El. 189' I No Yes S143-H3 (2) Az. 300 El. 184' I tJo Yes 4 1

S143-in (2) Az. 300 -El. 179' I No Yes S143-H5 (1) Az. 300 El. 196' I No Yes S146-It5 (1) Az. 150 El. 191' I ib Yes

i 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.

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

s

= TABLE 3.7.4-lb ,

2- . .

y SAFETY RELATED MECHAN 1 CAL StJUBBERS* .

HICH RADIATION

-4 StJUGGER - SYSTEM STABBER ItiSTALLED ACCESSIBLE OR ZONE ESPECIALLY OIFFICULT N tJO. (Oty.) ON, LOCATION APO ELEVATI0tl INACCESSIBLE DLRING SHUTDOWN ** 'TO REMOVE Reactor Building (A or I) (Yes or No) (Yes or No) 2821-tJuclear Boiler System (Continued)

S148-H1 (1) AZ. 2120 El. 195' I tb Yes S148-H2 (2) Az. 2100 El. 189' I tb Yes S148-t0 (2) Az. 2100 El. 184' I tb Yes S148-FM (2) Az. 2100 El. 179' I tb Yes

.Az. 2120 El. 194' & 196' S158-H5 (2) I

~4 tb Yes

.g 2831-Reactor Recirculation System y 514-H1 (1) Az. 170 El. 125' I . No Yes

S17-H1 (1) Az. 1980 El. 126' I tb Yes
  • S18-H1 (1) Az. 650 El. 126' I ib Yes S24-H1 (1) Az. 3090 El. 123' I ib Yes S40-H1 (1) Az. 1100 El. 120' I tb Yes S43-H1 (1) Az. 1550 El. 187' I tb Yes 2 Ell-RIR System

-R338 (1) Az. 00 El. 146' I No Yes R339 (1) Az. 3550 El. 155' I tb Yes

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

Amendment request.

-. . . . - .= .-

TABLE 3.7.4-lb i -

g- SAFETY RELATED MECHANICAL StJUBBERS*

F . .

E HIGH RAOIATION 5 StJUESER SYSTEM SNLE8ER INSTALLED ACCESSIBLE OR ZONE ESPECIALLY DIFFICULT y tJ0. (Oty.) ON, LOCATION AND ELEVATI0t1 INACCESSIBLE DLRItJG SHUTDOWN ** TO REMOVE Reactor Buildinr1 (A or I) (Yes or No) (Yes or ib) 2 Ell-RHR System (Continued)

R340 (1) Az. 3420 El. 155' I tb Yes R342 (1) Az. 3370 El. 140' I tb Yes R350 (1) Az. 800 El. 150' I ib Yes R351 (2) Az. 3050 El. 150' I tb Yes R352 (2) Az. 3250 El. 150' I . ib Yes

.R353 (1) Az. 3280 El. 146' I ib Yes R354 (1) Az. 3280 El. 146' I tb Ves w R355 (1) Az. 2850 El. 150' I ib Yes

) R356 (2) Az. 550 El. 150' I tb Yes y R357 (2) Az. 370 El. 150' I ib Yes

,8 R358 (1) Az. 330 El. 146' I ib Yes

% -R359 (1) Az. 380 El. 146' I- tb Yes R368 (1) Az. 200 El. 206' I No Yes 2E21-Core Spray System R59 (2) Az. 900 El. 178' I tb Yes R98 (2) Az. 2670 El. 178' I tb Yes

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

TABLE 3.7.4-lb 5 SAFETY RELATED MECHANICAt SNm BERS* -

Y E HIGH RADIATION SficeneR SYSTen StimeER IrSTAttEo ACCESSIete OR H

z0f2E EseeCIAttY oIrrICutT fl0. (Oty.) Otl, LOCATI0tl Ato ELEVATI0rl It4 ACCESSIBLE DWItJG SHUTDOWtl** TO REMO\E N

Reactor Building (A or I) (Yes or TJo) (Yes or f40) 2E41-HPCI System i R110 (1) Az. 180 El. 145' I tb Yes Rlll (1) Az. 190 El. 145' -

I tb Yes R112 (1) Az. 120 El. 145' I tb Yes R113 (2) Az. 110 El. 145' I tb Yes Rll4 (1) Az. 460 El. 145' I .. tb Yes R115 (2) Az. 560 El . 145' I

  • tb Yes

.R

Z R114 (1) Az. 2130 El. 146' I tb Yes All6 (1) Az. 1860 El. 142' I tb Yes Rll7 (1) Az. 1860 El. 142' I tb Yes 2G31-RWCU System R166 (1) Az. 130 El. 149' I tb Yes R167 (2) Az. 170 El. 156' I tb Yes R168 (1) Az. 170 El. 162' I ib 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.

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

TABLE 3.7.4-lb SAFETY RELATED MECHANICAL SNUBBERS

  • 9 h

O HICH RADIATION

  • StafsBER SYSTEM St4tBBER IrtSTALLED ACCESSIBLE OR 20tJE tJ0. (Oty.)

ESPECIALLY DIFFICULT

" OtJ, LOCATIGtJ AfD ELEVATION INACCESSIBLE DLRItJG SHUTDOWN ** TO REMOVE (A or I)

Reactor Building (Yes or ib) (Yes or No) 2E11-RHR System R91 (2) 38'SR14-23'WRL, El. 119' A No No R92 (2) 14'SR14-22'WRF, El. 119' A No ib R103 (2) 35'SR14-26'WRL, El. 119' A No No R105 (2) 9'NR24-11'WRF, El. 118' A No No R106 (1) 9'NR24-ll'WRF, El. 118' A .. No No R123 (1) l'SR22-13'WCH, El. 169' A No No R125 (1) 6'SR22-12'WRF, El. 167' A No No ti R224 (1) 24'SR14-29'WRL, El. 90' A tb No

  • - R225 (1) 29'SR14-29'WRL, El. 90' A No No y R226 (2) 23'SR14-27'WRL, El. 90' A No No
R228 (1) 18'SR14-23'WRL, El. 90' A No No m-R229 (1) 28'NR24-29'WRL, El. 90' A No ib R230 (1) 25'SR14-30'WRL, El. 90' A No No R233 (2) 23'IR24-28'WRL, El. 90' A No No R235 (1) 13'SR14-13'WRL, El. 121' A tb No R240 (1) 24'NR24-28'WRL, El. 90' A No No R289 (1) 13'NR24-13'WRL, El. 121' A tb No R290 (2) 25'SR14-28'WRL, El. 120' A No No R292 (2) 36'SR14- l'WRL, El. 118' A No tJo 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 Amendment request.
    • t4odifications to this column due to changes ir, 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.

n ,e .. , ~-

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

TABLE 3.7.4-lb ,

D

{ SAFETY RELATED MECHAtJICAL StJUBBERS*

7 HICH RADIATION E S:1UBBER SYSTEM StJLBBER INSTALLED ACCESSIBLE OR 20tJE ESPECIALLY DIFFICULT G f f0. (Oty.) ON, LOCATI0tl Ato ELEVATIO.! INACCESSIBLE DtRING SHUTDOWN ** TO REM 0W ro Reactor Building (,4 or I) (Yes or NO) (Yes or te) 2E11-RHR System (Continued)

R326 (1) 18'SR19-17'ERH, El.136' A tb tb R327 (1) 18'SR19-17'ERH, El. 136' A tb No R328 (1) 18'SR19-10'WRH, El.-139' A No ib R329 (1) 18'SR19-10'WRH, El. 139' A tb No S4-H1 (1) 19'SR19-25'WRL, El. 123' A , .; No ib 2E32-MSIV Leakage Control System u Sll-H1 (1) 21'tR21- S'WRB, El. 118' A No ib 7 S17-H1 (1) 20'tR21-21'WRB, El. 118' A No No y S18-H1 (1) 21'NR21- 4'WRB, El. 119' A tb No

, .L S19-H1 (1) 21'tR21- 5'WRB, El.117' A tb No N

2E41-H3CI System R45 (2) 23'tJR25-5'WRL, El. 117' A tb tb -

R50 (2) 10'tR25-4' ERG, El. 110' A tb ib RSS (2) 10'tJR25-24'WRL, El. 96' . A tb tb 2E51-RCIC System *

.S6-H1 (1) 5'NR19-22' ERA, El. 129' A No- No

  • Snubbers may be added to safety related systems without prior License Amendment to Table 3.7.4-lb provided that.a 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 e

W D

C O

bC W

+a C

w 4

C m

C C1 CL v,

S v

HATCH-UNIT 2 3/4 7-18

l (This page blank intentionally)

HATCH-UflIT 2 3/4 7-18a

PLANT SYSTEMS BASES 3/4.7.4 SNUBBERS All snubbers are required OPERABLE to ensure that the structural integrity of the reactor coolant system and all other safety-related systems is main-tained during and following a seismic or other event initiating dynamic loads. Snubbers excluded from this inspection program are those installed on non-safety related systems and then only if their failure or failure of the system on which they are installed, would have no adverse effect on any safety-related system.

The visual inspection frequency is based upon maintaining a constant level of snubber protection to systems. Therefore, the required inspection interval varies inversely with the observed snubber failures and is determined by the number of inoperable snubbers found during an inspection. Inspections performed before that interval has elasped may be used as a new reference point to determine the next inspection. However, the results of such early inspections performed before the or'iginal required time interval has elapsed (nominal time less 25%) may not be used to l'engthen the required inspection interval. Any inspection whose results require a shorter inspection interval will override the previous schedule.

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

When a snubber is found inoperable, an engineering evaluation is performed, in addition to the determination of the snubber mode of failure, in order to 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 system.

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

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

HATCH-UNIT 2 B 3/4 7-2

PLANT SYSTEMS BASES i

3/4.7.4 SNUBBERS (Continued)

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

3/4.7.5 SEALED SOURCE CONTAMINATION The limitations on sealed source removable contamination ensure that the total body or individual organ irradiation does not exceed allowable limits in the event of ingestion or inhalation of the source material.

The limitations on removable contamination for sources requiring leak testing, including alpha emitters, is based on 10 CFR 70.39(c) limits for plutonium. Quantities of interest to this specification which are exempt from the leakage testing are consistent with the criteria of 10 CFR Part 30.11-20 and 70.19. Leakage from sources excluded # rom 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 SUPPRESSION SYSTEMS The OPERABILITY of the fire suppression systems ensures that adequate fire suppression capability is available to confine and extinguish fires occurring in any portion of the facility where safety-related equipment is located. The fire suppression system consists of the water system, spray and/or sprinklers, CO 2 , and fire hose stations. The collective capability of the fire suppression systems is adequate to mi timize potential damage to safety-related equipment and is a major element in the facility fire protection program.

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

In the event the fire suppression water system becomes inoperable, immediate corrective measures must be taken since this system provides the major fire suppression capability of the plant. The requirement for a twenty-four hour report to the Commission provides for prompt evaluation of the acceptability of the corrective measures to provide adequate fire suppression capability for the continued protection of the nuclear plant.

HATCH-UNIT 2 B 3/4 7-3

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ADMINISTRATIVE CONTROL RECORD RETENTION (Continued)

c. Records of radiation exposure for all individuals entering radiation control areas,
d. Records of gaseous and liquid radioactive material released to the environs,
e. Records of transient or operational cycles for those unit components identified in Table 5.7.1-1.
f. Records of reactor tests and experiments.
g. Records of training and qualification for current members of the unit staff,
h. Records of in-service inspections performed pursuant to these Technical Specifications. .-
1. Records of Quality Assurar.ce activities required by the QA Manual.

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

k. Records of meetings of the PRB and the SRB.
1. Records of the service lives of all hydraulic and mechanical snubbers listed on Tables 3'.7.4-la and 3.7.4-lb, including the date at which the service life commences and associated installation and mainte-nance records.

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

6.12 HIGH RADIATION AREA 6.12.1 In lieu of the " control device" or " alarm signal" required by paragraph 2.0.203(c)(2) of 10 CFR 20, each high radiation area in which the intensity of radiation is greater g than 100 mrem /hr but less than 1000 mrem /hr shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring

, issuance of a Radiation Work Permit *. Any individual or groups of individuals permitted

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

,. tection duties, provided they comply with approved radiation protection pro-n cedures for' entry 1nto high radiation areas.

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" BATCH-UNIT 2 ' , .'f f i . 6-18

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