View source for W3F1-2015-0006, Application for Technical Specification Change Regarding Risk-Informed Waterford Steam Electric Station, Unit 3 - Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program. Part

{{Adams
| number = ML15170A124
| issue date = 06/17/2015
| title = Application for Technical Specification Change Regarding Risk-Informed Waterford Steam Electric Station, Unit 3 - Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program. Part 3 of 5
| author name = 
| author affiliation = Entergy Operations, Inc
| addressee name = 
| addressee affiliation = NRC/NRR
| docket = 05000382
| license number = NPF-038
| contact person = 
| case reference number = W3F1-2015-0006
| document type = License-Application for Facility Operating License (Amend/Renewal) DKT 50, Technical Specification, Bases Change
| page count = 72
| project = 
| stage = Request
}}

=Text=
{{#Wiki_filter:3/4.4   REACTOR COOLANT SYSTEM 3/4.4.1   REACTOR COOLANT LOOPS AND COOLANT CIRCULATION STARTUP AND POWER OPERATION LIMITING CONDITION FOR OPERATION 3.4.1.1   Both reactor coolant loops and both reactor coolant pumps in each loop shall be in operation.
APPLICABILITY:   MODES 1 and 2.
ACTION:
With less than the above required reactor coolant pumps in operation, be in at least HOT STANDBY within 1 hour.
K>
SURVEILLANCE REQUIREMENTS 4.4.1.1 The above required         or coolant loops shall be verified to be in operation and circulating ri        coolant at leaft once pe. 12 ho,,;s.
11              [Add INSERT la    I L_#
WATERFORD - UNIT 3                   3/4 4-1                    AMENDMENT NO.

P=Afft1AP r.        r) AMT QVcQTCIM HOT STANDBY LIMITING CONDITION FOR OPERATION 3.4.1.2 The reactor coolant loops listed below shall be OPERABLE and at least one of these reactor coolant Loops shall be in operation.*
: a. Reactor Coolant Loop I and its associated steam generator and at least one associated reactor coolant pump.
: b. Reactor Coolant Loop 2 and its associated steam generator and at least one associated reactor coolant pump.
APPLICABILI            : MODE 3".
ACTION:
: a. With less than the above required reactor coolant loops OPERABLE, restore the required loops to OPERABLE status within 72 hours or be in HOT SHUTDOWN 1 ( &#xfd; i I b. With no reactor coolant loop In operation, suspend operations that would
     !t- cause Introduction Into the RCS, coolant with boron concentration less than required to meet SHUTDOWN MARGIN of Technical Specification
     *,I 3.1.1.1 or 3.1.1.2 and Immediately initiate corrective action to return the required reactor coolant loop to operation.
,QSURVEILLANCE           REQUIREMENTS 4.4.1.2.1 At least the above required reactor coolant pumps, If not In operation, shall be determined to be OPERABLE onee-per:? day by verifying correct breaker alignments and indicated power availability.                           Add INSERT la 4.4.1.2.2 At least one reactor coolant loop shall be vedrfi               e in operation and circulating reactor coolant 1--'                       12 ho,..
4.4.1.2.3 The required steam                  a or(s) shall be determined OPERABLE by verifying the seconda                 water level to be > 50% of wide range indication t, Ia-t-On e....... 12 22' i-.S..
 *All reactor coolant pumps may be deenergized for up to 1 hour provided (1) no operations are permitted that would cause introduction into the RCS, coolant with boron concentration less than required to meet the SHUTDOWN MARGIN of Technical Specification 3.1.1.1 or 3.1.1.2, and (2) core outlet temperature is aintained at least 1O&deg;F below saturation temperature.
**See Special e"                        .1 .5.
                         ~ADA   rnar~r. SLSS           a   a                   A.. .. .. .. ..  . a-VV/    -MrI "IIUMLU - UiINI 1 .                          J14 4q-z                                     N*.-oj

REACTOR COOLANT SYSTEM HOT SHUTDOWN SURVEILLANCE REQUIREMENTS 4.4.1.3.1 to Sdetermined   T e      one reac be OPERABLE otc-' V or7I=*       *ol;-   ........
corcn  p breaker s
alignments and indicated power availabili              *Add              INSERT la S4.4.1.3.2 The requjrds             sc)ao~      shall be determi ed OPERABLE by verifying the sec     aysd       ae     ee   t~obe >_50% of wide range indication 4.4.1.3.3 At least one reactor coolant or shutdown cooling Iopsalb verified to be in operation and circulating reactor coolant 4L lud* uIe          pui ATERFORD  -  UNIT 3                    3/4 4-4                     AMENDMENT NO.

REACTOR COOLANT SYSTEM
-  COLD SHUTDOWN - LOOPS FILLED SURVEILLANCE REQUIREMENTS
: 4. .14        erqieratrcoatpm                     ) fntIperation, shall be determined to be       .
OPERABLE onepe                 by verifying correct breaker alignments and Indicated t        ~power availability.        '*     *       -Add INSERT l a
* 4.4.1.4.2  The required steam generator(s) shall be dete       ined OPERBL       by verifying the   .
secondary side water level to be ;50%of wide ange indication at-.east-oncep-ar 1.2-hours 4.4.1.4.3  At least one reactor coolant loop or shutdown oling train shall be verified to be in operation and circulating reactor coolant at lens, once pai 12 ,,,uI.
WATE          - N                             314 4-5a                             AMENDMENT NO. 1096- +

REACTOR COOLANT SYSTEM COLD SHUTDOWN - LOOPS NOT FILLED LIMITING CONDITION EOR OPERATION 3.4.1.5 Two shutdown cooling loops shall be OPERABLE# and at least one shutdown cooling loop shall be in operation.*
AP*LtCABI.*ITY:      MODE 5 with reactor coolant loops not filled.
ACTION:
: a. With less than the above required loops OPERABLE, Immediately initiate corrective action to return the required loops to OPERABLE status as soon as o s
: b. With       shutdown cooling loop in operation, suspend operations that would cau introduction into the RCS, coolant with boron concentration less than
                   .l re I ed to meet SHUTDOWN MARGIN of Technical Specification 3.1.1.1 or 3.'. .2 and immediately Initiate corrective action to return the required s tdown cooling loop to operation.
K~) 4.4.1.5 .t least one shutdown cooling loop shall be determined to be in operation and circulati reactor I" coolant Mt les. -;.. per An. ,'w-3.
                                                          "'F-&#xfd;Add&#xfd;INS&#xfd;ERT l&#xfd;a
    # One hutdown cooling loop may be Inoperable for up to 2 hours for surveillance testi provided the other shutdown cooling loop is OPERABLE and In operation.
The   hutdown cooling pump (LPSI pump) may be deenergized for up to 1 hour pro   ded (1) no operations are permitted that would cause Introduction Into the RCS, coo    nt with boron concentration less than required to meet the SHUTDOWN MARGIN of Tea   nical Specification 3.1.1.1 or 3.1.1.2, and (2) core outlet temperature is maintained atI    st 10OF below saturation temperature.
ERFORD - UNIT 3                          314 4-6                          AMENDMENT NO.      M5 MAR 07 2WO3 I

REACTOR COOLANT SYSTEM K) 3/4.4.3      PRESSURIZER LIMITING CONDITION FOR OPERATION 3.4.3.1      The pressurizer shall be OPERABLE with:
: a.      A steady-state water volume greater than or equal to 26% indicated level (350 cubic feet) but less than or equal to 62.5% indicated level (900 cubic feet), and, lb.'   *At least two groups of pressurizer heaters powered from Class IE buses each having a nominal capacity of 150 kW.
APPLICABILITY:       MODES 1, 2, and 3.
ACTION:
: a.      With only one group of the    above required pressurizer heaters OPERABLE, restore at least    two groups to OPERABLE status within 72 hours or be in at least    HOT STANDBY within the next 6 hours and in HOT SHUTDOWN within the   following 6 hours..
: b.      With the pressurizer otherwise inoperable, be in at least HOT STANDBY with the reactor trip .breakers open within 6 hours and in
   >HOT                    SHUTDOWN within the following 6 hours.
4.4.3.1.1      The pressurizer water volume shall be determined to be within its limit at least emcc peF 12 houps.
4.4.3.1.2 The capacity of ea          of the above required groups of pressurizer heaters shall be verified to be at least 150 kW ...         .em .... e .......
i.nter':a                             *-Add INSERT la
* 4.4.3.1.3 The emergency power supply          or the pressurizer heaters shall be demonstrated OPERABLE "        ah r-e           .
interv.
                                                          ..l by:
: a.      Verifying the above pressurizer heaters are automatically shed from the emergency power sources upon the injection of an SIAS test signal.
: b.      Verifying that the above heaters can be manually placed and energized on the emergency power source from the control room.
WATERFORD - UNIT 3                        3/4 4-9                 Amendment No.,   - C-I

REA:TOR COOLANT SYSTEM AUXILIARY SPRAY LIMITING CONDITION FOR OPERATIC03 3.4.3.2   Both auxiliary spray valves shall be OPERABLE.
APPLICABILITY:   MODES 1, 2 and 3.
ACTION:
: a. With only one of the above required auxiliary spray valves OPERABLE, restore both valves to OPERABLE status within 30 days or be in HOT STANDBY within the next 6 hours and in HOT SHUTDOWN within the following 6 hours.
: b. With none of the above required auxiliary spray valves OPERABLE, restore at least one valve to OPERABLE status within the next 6 hours or be in at least HOT STANDBY within the next 6 hours and in HOT SHUTDOWN within the following 6 hours.
SURVEILLANCE REQUIREMENTS 4.4.3.2.1   The auxiliary spray valve shall be verified to have power available  I to each valve -' '    ......
                      -Add A. . ....              INSERT la 4.4.1.2.2   The atuxiliary spra) valves shall be cycled  .- l--.        p-WATERFORD - UNIT 3                   3/4 4-9a                    Amendment No. 2 I

REACTOR COOLANT SYSTEM LIMITING CONDITION FOR OPERATION (Continued)
Perform SR 4.4.5.2.1 once per 24 hours and restore the containment sump monitor to OPERABLE status within 30 days; or Be inMO E 3 in6 hoursand M D 5 in thefollowing 30 hours.
: c. All required RCS leakage detection instrumentation inoperable.
Initiate ACTION within 1 hour to be in MODE 3 within the next 6 hours and MODE 5 in the following 30 hours.                            Add INSERT la SURVEILLANCE REQUIREMENTS                         ,,
: a. Containment atmosphere partio~te monitor syste      - performance of CHANNEL CHECK at ,eaet 3fl- per 12 hur.,     CHANNEL CA BRATION at least....       pat 1..
menth and CHANNEL FUNCTIONAL TEST at least *n*.e pai 92 days.
: b. Containment sump level and flow monitors - performance of a CHANNEL CHECK (containment sump level monitor only) ;atl      np
                                                      .a-      12,
: 2. tim, and a CHANNEL CALIBRATION atle_,t .... pa, ,edths.
VAddINSERT la M

REACTOR COOLANT SYSTEM OPERATIONAL LEAKAGE
>-a.
3.4.5.2      Reactor Coolant System operational leakage shall be limited to:
No PRESSURE BOUNDARY LEAKAGE,
                                                                                                        --F
*"b.              I gpm UNIDENTIFIED LEAKAGE,
: c. 75 gallons per day primary to secondary leakage through any one steam generator (SG),
: d. 10 gpm IDENTIFIED LEAKAGE from the Reactor Coolant System, and
: e. I gpm leakage at a Reactor Coolant System pressure of 2250 i 20 psia from any Reactor Coolant System pressure isolation valve specified in Table 3.4-1.
APPLICABILIT:           MODES 1,2,3, and 4.
S    ACTION:
: a. With any PRESSURE BOUNDARY LEAKAGE, or primary.to secondary leakage not within limit, be in at least HOT STANDBY within 6 hours and in COLD SHUTDOWN within the following 30 hours.
: b. With any Reactor Coolant System operational leakage greater than any one of the limits, excluding PRESSURE BOUNDARY LEAKAGE, primary to secondary leakage, and leakage from Reactor Coolant System pressure isolation valves, reduce the leakage rate to within limits within 4 hours or be In at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours.
: c. With any Reactor Coolant System pressure isolation valve leakage greater thgn the above limit, isolate the high pressure portion of the affected system from the low pressure portion within 4 hours by use of at least one dosed manual or deactivated automatic valve, or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours.
SURVEILLANCE REQUIREMENTS NOTE:            Not required to be performed until 12 hours after establishment of steady state operation.
4.4.5.2.1 Reactor Coolant System leakages, except for primary to secondary leakage, shall be demonstrated to be within each of the above limits by performance of a Reactor Coolant System water inventory balanceat ',east once                             Add    INSERT la IAdINSERT     la 4.4.5.2.2 Primary to secondary leakage shall be e              b<75 gallons per day through any one SG at           onaes p, 72 ,ho, WATERFORD - U1IT 3                              3/4 4-18             AMENDMENT NO. , -99 I

REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) 4.4.5.2.3 Each Reactor Coolant System pressure isolation valve specified in Table 3.4-1, Section A and Section B, shall be demonstrated OPERABLE by verifying leakage to be within its limit:               **---*Add INSERT l b
: a. Atl s  ...  . ... O    .f-int- .,
: b. Prior to entering MODE 2 whenever the plant has been in COLD SHUTDOWN for 7 days or more and if leakage testing has not been performed in the previous 9 months,
: c. Prior to returning the valve to service following maintenance, repair, or replacement work on the valve,
: d. Following valve actuation for valves in Section B due to automatic or manual action or flow through the valve:
: 1.       Within 24 hours by verifying valve closure, and
: 2.       Within 31 days by verifying leakage rate.
The provisions of Specification 4.0.4 are not applicable for entry into MODE 3 or 4.
4.4.5.2.4 Each Reactor Coolant System pressure isolation valve power-operated                     valve specified in Table 3.4-1, Section C, shall be demonstrated OPERABLE by verifying leakage to be within its limit:
: a. At             s p,,,1 , Mthand ox..
: b. Prior to returning the valve to service following maintenance, repair, or replacement work on the valve.
The provisions of Specification 4.0.4 are not applicable for entry into MODE 3 or4.
WATERFORD - UNIT 3                            3/4 4-19                  AMENDMENT NO. 96 -49 2"4

m                                                  PRIMARY COOLANT SPECIFIC ACTIVITY SAMPLE nAND                                                                   ANALYSIS PROGRAM OF MEASUREMENT                                  SAMPLE AND ANALYSIS                           MODES IN WHICH SAMPLE 1,       Gross Activity Determination                  At least en      per,72
                                                                                  ,,     hours S2.         Isotopic   Analysis for DOSE                   1 pe...    ** ay                              1 EQUIVALENT 1-131 Concentration                                                      Replace marked
                             ;*"                                                       .   /        Ithrough lines with"*
: 3.      Radiochemical for P. Determination             1-*peir6e'            ''SFCP.
: 4.       Isotopic Analysis for Iodine                  a)       Once per 4 hours,                    1#, 2#, 3#, 4#, 5#.
Including 1-131, 1-133, and 1-135                       whenever the specific activity exceeds 1.0 pCi/gram, DOSE EQUIVALENT 1-131 or 1001E pCi/gram, and b)       One sample between                   1, 2, 3 2 and 6 hours following 15 % of the RATED THERMAL POWER within a 1-hour 9period.
m z
ci
* Sample     to be taken after a minimum of 2 EFPD and 20 days of POWER OPERATION have elapsed since reactor m
z         was last subcritical for 48 hours or longer.
I-
_*_-     # Until the specific activity of the primary coolant system is restored within its limits.

REACTOR COOLANT SYSTEM K>
4.4.8.1 1 The Reactor Coolant Syste            erature and p    ure shall be determined to be withint e limits , l                           during system    atup, cooldown, and inservice leak an h drostatic testing operations.
4.4.8.1.2 The reactor vessel material Irradiation surveillance specimens shall be removed and examined, to determine changes In material properties, at the intervals required by 10 CFR Part 50 Appendix H in accordance with the Reactor Vessel material surveillance program -
withdrawal schedule in FSAR Table 5.3-10. The results of these examinations shall be used to update Figures 3.4-2 and 3.4-3.
K)
WATERFORD - UNIT 3                         3/4 4-29                    AMENDME        NO. 406, m K)                                                                                       JAN 08 2*0

K>  REACTOR COILANT UYSIEM SURVEILLANCE REQUIREMENTS
          ..1     ra~       DSstmutlo             elf         I:
: a. verify in the control room at :at
                                                 ,=,.      per 12 ,,u      that each valve In the suction path between the RCS and the SDC relief valve Is open                         Add INSERT 1a
: b. verify each SDC relief valve Is OPERABLE In accordance with t              In ervice Testing Program.
4.4.8.3.2 With the RCS vented per ACTIONS a, b, or c, the RCS vent( , and all alves In the vent path shall be verified to be open ,tl         ,,wee-              *..
K)
    *Except when the vent pathway is provided with a valve which Is locked, sealed, dkotherwise secured in the open position, then verify these valves open at least once per 31 day.
K~2 WATERFORD - UNIT 3                             314 4-35                  AMENDMENT NO. 6,24 40. M"9, L  ~      k      I.        I. ~. ~      ~ I   I    I    I  ' I  I  I   . I   ~  I  I I I

REACTOR COOLANT SYSTEM
"*)  3/4.4.10    REACTOR COOLANT SYSTEM VENTS LIMITING CONDITION FOR OPERATION 3.4.10 At least one Reactor Coolant System vent path consisting of at least two valves in series powered from emergency busses shall be OPERABLE and closed at each of the following locations:
: a. Reactor vessel head, and
: b. Pressurizer steam space.
APPLICABILITY:      MODES 1, 2, 3, and 4.
ACTION:
: a. With one of the above Reactor Coolant System vent paths inoperable, STARTUP and/or POWER OPERATION may continue provided the inoperable vent path is maintained closed with power removed from the valve actuator of all the vent valves and block valves in the inoperable vent path; restore the inoperable vent path to OPERABLE status within 30 days, or, be in HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours.
: b. With two or more Reactor Coolant System vent paths inoperable; maintain the inoperable vent paths closed with power removed from the valve actuators of all the vent valves and block valves in the inoperable vent paths, and restore at least one of the vent paths to OPERABLE status within 72 hours or be in HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours.
SURVEILLANCE REQUIREMENTS S4.4.10    Each Reactor 9o011ant System vent path shall be demonstrated OPERABLE at last        ..        . by:
S    a. Verifying all manual isolation valves in each vent path are locked in the open position.
: b. Cycling each vent valve through at least one complete cycle of full travel from the control room during COLD SHUTDOWN or REFUELING.
: c. Verifying flow through the Reactor Coolant System vent paths during venting during COLD SHUTDOWN or REFUELING.
TERFORD - UNIT 3                     3/4 4-37                AMENDMENT NO.
I

3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS)
Yj/    ACTION: (Continued)
M ODE     an 3       with 4               pressurizer                                750 psia (continued).
: d. With two of the required safety injection tanks inoperable, restore one of the tanks to OPERABLE status within 1 hour, or be in HOT STANDBY within the next 6 hours and reduce pressurizer pressure to less than 1750 psia within the following 6 hours.
    ,. MODES 3 and 4 with pressurizer pressure less than 1750 psia
: e. With one of the required safety injection tanks inoperable due to boron concentration not within limits, restore the boron concentration to within limits within 72 hours, or be in at least"COLD SHUTDOWN within the following 24 hours.
: f. With one of the required safety injection tanks inoperable due to inability to verify level or pressure, restore the tank to OPERABLE status within 72 hours, or be in at o         ileast SHUTDOWN within the following 24 hours.
COLD
: g. With one of the required safety Injection tanks inoperable for reasons other than ACTION a or b, restore the inoperable tank to OPERABLE status within 1 hour, or be in at least COLD SHUTDOWN within the following 24 hours.
Sh.           With two of the required safety Injection tanks inoperable, restore one of the tanks to OPERABLE status within 1 hour, or be in at least COLD SHUTDOWN within the following 24 hours.
SURVEILLANCE REQUIREMENTS 4.5.1 Each safety injection tank shall be demonstrated OPERABLE:
: a.       .s...,A      ..p, r 112 hat
                                               ..                                         Ad:d INSERT lb
: 1.       Verifying the contained borated water volume     . nitrogen cover-pressure in the tanks, and
: 2.        Verifying that each safety inj  i n tank isolation valve is open.
: b. Ad least a,,,ce pe. 3"1 da*s by verifying the boron concentration of the safety injection tank solution.
: c. Within 6 hours after each solution volume increase of greater than or equal to 1% of tank volume-by verifying the boron concentration of the safety Injection tank solution. This surveillance is not required when the volume Increase makeup source is the RWSP.
WATERFORD - UNIT 3                              314 5-2                          AMENDMENT NO.
F BO- 20

3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 1I'115  '-1  144       "
: d. M least                days, _hen the RCS pressure is above 1750 psia, by verifying that the isolation valve op        breakers are padlocked in the open position.
: e. Ay                                ve rifying        ach safety injection tank isolation valve opens automatically un er           of the fo         conditions:
: 1. When an actual or simulated RCS pressure               exce      535 psia, and
: 2. Upon receipt of a safety injection test signal.
Add INSERT lb K) WATERFORD - UNIT 3                         3/4 5-2a                             AMENDME NO.+2 'S F~EB      29

EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS
: 8. Mleast ones e,* 1-" ,ho,- by verifying that the following valves
             ,"       are In the Indicated poiftipns with the valves key-locked shut:
             *.Valve          Number                I*eucto                      Valve Position
: a. 2SI-V1556           a. H   Leg Injection        a. SHUT (SI-506A) b."    2S1-V1557           b. Hot Le   njection        b. SHUT (SI-502A)
: c. 2SI-VI558           c. Hot Leg Inje    n        C. SHUT (SI-502B)
: d.      2SI-V1559           d. Hot Leg Injection        d. SHUT (SI-506B)
                                                                          ~~d._.d--   INSERT lb
: b. A4lstee           er 4dy        y
: 1. Verifying that each valve (manual, power-o rated, or automatic) In the flow path that is not locked, sealed, or oth " rwise secured in position, is in its correct position.
: 2. Verifying the ECCS piping is full of
: c. By a visual Inspection which verifies that o loose debris (rags, trash, clothing, etc.) Is present in the containment whI could be transported to the safety Injection system sump and cause resrction of the pump suctions during LOCA conditions. This visual Inspection s II be performed:
: 1. ' For all accessible areas of        e containment prior to establishing CONTAINMENT INTEGR                and
: 2. Of the areas affected       hin containment at the completion of containment entry when CONTAI          ENT INTEGRITY Is established.
: d. AA. .... an= per ISh...           by:
: 1. Verifying the action of the open permissive Interlock (OPI) and Isolation valve position alarms of the shutdown cooling system when the reactor coolant system pressure (actual or simulated) Is between 392 psla and 422
-.. =psia.
RFORD - UNIT 3                           314 5-4                 AMENDMENT NO..&F*IO
                                                                                                   "'7                                                                                                              I

EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
: 2.       A visual inspection of the safety injection system sump and verifying that the subsystem suction inlets are not restricted by debris and that the sump components (trash racks, screens, etc.) show no evidence of structural distress or corrosion.
: 3.       Verifying that a minimum total of 380 cubic feet of granular trisodium phosphate dodecahydrate (TSP) is contained within the TSP storage baskets.
: 4.       Verifying that when a representative sample of 13.07 +/- 0.03 grams of TSP from a TSP storage basket is submerged, without agitation, In 4+/- 0.1 31 m the H of the mixed solution is raised to greater than or equal to wW hi h u
  >. e. AA1 11cast e,-ice per 11,2, ,montlso by:                 Add INSERT lb                     l 1       Verifying that each automatic valve in the flow path actuates to its correct position on SIAS and RAS test signals.
: 2.       Verifying that each of the following pumps start automatically upon receipt of a safety Injection actuation test signal:
: a.        High pressure safety injection pump.
: b.        Low pressure safety irijection pump.
: 3.       Verifying that on a recirculation actuation test signal, the low pressure safety injection pumps stop, the safety injection system sump isolation valves open.
: f. By verifying that each of the following pumps required to be OPERABLE performs as Indicated on recirculation flow when tested pursuant to the Inservice Testing Program:
: 1.       High pressure safety injection pump differential pressure greater than or equal to 1429 psid.
: 2.       Low pressure safety injection pump differential pressure greater than or equal to 168 psid.
WATERFORD - UNIT 3                              3/4 5-5    AMENDMENT NO. 64, W?7,        .2, 1,  -9 99,

EMERGENCY CORE COOLING SYSTEMS 3/4.5.4 REFUELING WATER STORAGE POOL
*.3.5.4 The refueling water storage pool shall be OPERABLE9 with:.
: a.       A minimum contained borated water volume of 83% Indicated level,                       *   "
: b.       Between 2050 and 2900 ppm of boron, and
: c.       A solution temperature of greater than or equal to 55&deg;F and less than or equal to        J 100&deg;F.
APPLICABILI.TY MODES 1, 2, 3, and 4.
ACTION:
With the refueling water storage pool inoperable, restore the pool to OPERABLE status within 1 hour or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours.
SURVEILLANCE REQUIREMENTS 4.5.4 The RWSP shall be demonstrated OPERABLE:
: a.      At        ... pe
                             .. " -'- by:
: 1. Verifying the contained borated w .r volume In the pool, and
: 2. Verifying the boron co      ration of the water.
: b.      M         ,as. per 24 h.,m by verifying the RWSP temperature when the RAB air temperature is less than 55&deg;F or greater than 1000F.
WATERFORD - UNIT 3                            3/4 5-9            AMENDMENT NO. i9,42           4 f%

f
.' ,   314.6   CONTAINMENT SYSTEMS
  <3/4.6.1       PRIMARY CONTAINNT CONTAINMENT INTEGRITY LIMITING CONDITION FOR OPERATION 3;6.1.1    PrimaryCONTAINMENT INTEGRITY shall be mainitained.-
APPh,,ABILII: *MODES 1, 2, 3, and 4.
ACTION:
Without primary CONTAINMENT INTEGRITY, restore CONTAINMENT INTEGRITY within 1 hour or be inmat least HOT STANDBYwithin the next 6 hours* andln COLD SHUTDOWN within'the following ,30 hours. "          .
RELL N E       UR Add INSERT lb 4.6.1.1    Primary CONTAINMENT INTEGRITY        be demonstrate :
(t.....1-4.....    .r 3     -by verifying that.all penetratlons   not capable of being closed by OPERABLE containment automatic isolation valves and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured in their positions, except for valves that are open under administrative control as permitted by Specification 3.6.3.
: b. By verifying that each containment air lock is in compliance with the requirements of Specification 3.6.1.3.
: c. After each closing of each penetration subject to Type B testing, except containment air locks, if opened following a Type A or B test, by leak rate testing the seal in accordance with the Containment Leakage Rate Testing Program.
      *Except valves, blind flanges, and deactivated automatic valves which are located inside the containment and are locked, sealed or otherwise secured in the closed position. These penetrations shall be verified closed during each COLD SHUTDOWN except that such verification need not be performed more often than once per .92 days.
WATERFORD - UNIT 3 W>                                    3/4 6-1                   AMENDMENT NO. 4i,42-4 APR 10 1397 I

CONTAINMENT SYSTEMS SURVEILLANCE REqUIREMENTS
: a. By verifying seal leakage in accordance with the Containment
 ~Rate                                                                    Leakige_.*
Testing Program,
: b. By conducting overall air lock leakage tests in accordance with the_J__
Containment Leakage Rate Testing Program.I
: c. At least-Pa- per 6 mn*,,-'., by verifying that only one door in each air lock can be opened at a time.
                                                *"*--I~ddINSER     lb WATERFORD - UNIT 3                     3/4 6-10

CONTAINMENT SYSTEMS Ku   INTERNAL PRESSURE LIMITING CON!DITION FOR OPERAIONb
   *.gauge and greater than 14.275 psia.
                                                                                                       --,I" APLCBLT: MODES 1, 2, 3, and 4.
SACTION:
With the containment internal pressure outside of the limits above, restore the internal pressure to within the limits within 1 hour or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours.
SURVEILLANCE REQUIREMENTS 4.6.1.4 The primary containment internal pressure shall be determined to be within the limits tt WATERFORD - UNIT 3                             3/46-11                      Amendment No. -2, 74 OCT 1 0 2001

CONTAINMENT SYSTEMS AIR TEMPERATURE LIMITING CONDITION FOR OPERATION 3.6.1.j Primary containment average air temperature shall be > 95&deg;F* and < 120 OF.
APPLVABILITY: MODES 1, 2, 3, and 4.
ACTl N1:
: a.       f the minimum containment average air temperature is less than 95 0 F* but greater than or equal to 90 0 F*, then within 8 hours either restore containment air temperature to greater han or equal to 95 0 F or reduce the peak linear heat generation rate limit in accordance with the COLR. Otherwise, be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours.
: b.      If the minimum containment average air temperature is less than 90&deg;F, then restore containment air temperature to greater than or equal to 95&deg;F within 8 hours or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the                   /
following 30 hours.
: c.      If maximum containment average air temperature is greater than 120 0 F, then restore containment air temperature to less than or equal to 120&deg;F within 8 hours or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours.
SUR EILLANCE REQUIREMENTS 4.6.1.t The primary containment average air temperature shall be the arith ietical average of the temperatures at any three of the following locations and all be determined -1t ---..'-             24
                                               .er .
                         ,AddINSERT                                                         la Loc      n
: a. ontainment Fan Cooler No. 1A Air Intake
: b.  'ontainment Fan Cooler No. 1 B Air Intake
: c. ontainment Fan Cooler No. 1C Air Intake
: d. ontainment Fan Cooler No. 1D Air Intake Th minimum containment average air temperature limit is only applicable at greater than 70%
ED THERMAL POWER.
W     ERFORD - UNIT 3                            3/4 6-13                   AMENDMENT NO. +99-,

CONTAINMENT SYSTEMS CONTAINMENT VENTILATION SYSTEM LIMITING CONDITION FOR OPERATION 3.6.1.7 Each containment purge supply and exhaust isolation valve (CAP 103, CAP 104, CAP 203, and CAP 204) shall be OPERABLE and may be open at no greater than the 520 open position allowed by the mechanical stop for less than 90 hours per 365 days.
APPLICABILITY: MODES 1, 2, 3, and 4.
ACTION:
: a.      With a containment purge supply and/or exhaust isolation valve(s) open for greater than or equal to 90 hours per 365 days at any open position, close the open valve(s) or isolate the penetration(s) within 4 hours, otherwise be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours.
: b.      With a containment purge supply and/or exhaust isolation valve(s) having a measured leakage rate exceeding the limits of Surveillance Requirement 4.6.1.7.2, restore the inoperable valve(s) to OPERABLE status within 24 hours, otherwise be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours.
4.6.1.7.1 The cumulative time that the purge supply or exhaust isolation valves are open during the past 365 days shall be determined               ene     r de-,6             INSERT a Adddest At
  .6.1.7.2 Each containment purge supply and exhaust isolation valve with resilient
.inaterial seals shall be demonstrated OPERABLE in accordance with the Contain ent
,_eakage Rate Testing Program.
  .6.1.7.3 Each containment purge supply and exhaust isolation valve shall be emonstrated OPERABLE duing esh COLD SuHUTDCW'N emeeed,.. 24 ,.'m by verifying that the mechanical stops limit the valve opening to a position < 520 open.
ATERFORD - UNIT 3                           3/4 6-15                    Amendment No. -24 24*

CONTAINMENT SYSTEMS 314.6.2 DEPRESSURIZATION AND COOLING SYSTEMS CONTAINMENT SPRAY SYSTEM LIMITING CONDITION FOR OPERATION 3.6.2.1 Two Independent containment spray systems shall be OPERABLE with each spray system capable of taking suction from the RWSP on a containment spray actuation signal and automatically transferring suction to the safety Injection system sump on a recirculation actuation signal. Each spray system flow path from the safety Injection system sump shall be via an OPERABLE shutdown cooling heat exchanger.
APPLICABILIWY: MODES 1, 2. 3, and 4*.
ACTION:
: a.       With one containment spray system Inoperable, restore the Inoperable spray system to OPERABLE status within 7 days or be in at least HOT STANDBY within the next 6 hours; restore the Inoperable spray system to OPERABLE status within the next 48 hours or be In COLD SHUTDOWN within the following 30 hours.
: b.       With two containment spray systems inoperable, restore at least one spray system to OPERABLE status within 1 hour or be Inat least HOT STANDBY within the next 6 hours and be In COLD SHUTDOWN within the following 30 hours.
SURVEILLANCE REQUIREMENTS
    .6.       c     nt in e ts.I ra s s m             e e o      t   e
: a.       AM iet ane e 1,2 ho           by verifying that the water level In the containment spray header riser is > 1         et MSL e,,.o ...                    .
p h r rAdd                 INSERT lb
: b.      Ait       acrecly ist      pa dayst by verifying that each valve (manual, power-operated, or automatic) Inthe flow path that Is not locked, sealed, or otherwise secured in position. Is correctly positioned to take suction from the RWSP.
C.       By verifying, that on recirculation flow. each pump develops atotal head of greater than or equal to 219 psid when tested pursuant to the Inservice Testing Program.
   *With Reactor Coolant System pressure > 400 psla.
K) WATERFORD - UNIT 3                               314 6-16                    AMENDMENT NO. 89,463, 16.9-,

CONTAINMENT SYSTEMS 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS (Continued) d.,H'ntenep,                !a   enh,,. by:Add                      INSERT 1b.J
      *"1.             Verifying that each automatic valve In/ e flow path actuates to Its correct
      * *"              position on a CSAS test signal.
: 2. Verifying that upon a recircula
* n actuation test signal, the safety Injection system sum isolation valves open and that a -
recirculation mode flow p n via an OPERABLE shutdown cooling heat exchanger is esta shed.
: 3. Verifying that eac hpray pump starts automatically on a CSAS test signal.
: e.        At as                  years by performing an air or smoke flow test through each spray header and verifying each spray nozzle is unobstructed.
UNIT 3                        3/4 6-17               AMENDMENT NO. 69,163,2v9

CONTAINMENT SYSTEMS
 -I yCONTAINMENT                 COOLING SYSTEM LIMITING CONDITION FOR OPERATION 3.6.2.2 Two Independent trains of containment cooling shall be OPERABLE with one fan cooler to each train.
APPLICABILITY: MODES 1, 2, 3, and 4.
ACTION:
With one train of containment cooling inoperable, restore the inoperable train to OPERABLE status within 72 hours or be in at least HOT STANDBY within the next 6 hours; restore the inoperable containment cooling train to OPERABLE status within the next 48 hours or be in COLD SHUTDOWN within the next 30 hours.
4.6.2.2 Each train of containment cooling shall be demonstrated OPERABLE:
: a. At :*east eea pe 31 d&ys by:                               Add INSERT lb S1. Starting each operational fan not alrea running from the control room and K..                      verifying that each operational fan erates for at least 15 minutes.
: 2.      Verifying a cooling water flo I   ate of greater than or equal to 625 gpm to each cooler.
: b. At
                      .... t.... p. 10...m... by:
: 1.      Verifying that each fan starts automatically on an SIAS test signal.
: 2.      Verifying a cooling water flow rate of greater than or equal to 1200 gpm to each cooler.
: 3.      Verifying that each cooling water control valve actuates to its full open position on a SIAS test signal.
K)     WATERFORD         - UNIT 3                     3/4 6-18                AMENDMENT NO.9,*+ i&
JUL 0 6 2030

I C~rONIAINMENT YSTEMS 4.6.3.2 Each containment posHiSt-io-n.
Isolation valve shall be demonstrated OPERABLE              Ue               a&deg;
                          >"~~--                                  ----            "-y:----I
: a.      Verifying that on a containment Isolation test signal, each Isolation valve actuates to Its  .
     *-        ~Isolation position,."
: b.      Verifying that on a containment Radiation-High test signal, each containment purge valve actuates to its Isolation position.
4.6.3.3 The Isolation time of each power-operated or automatic containment Isolation valve shall be determined to be within Its limit when tested pursuant to the Inservice Testing Program.
Q WATERFORD - UNIT 3 3/4 6-20                                AMENDMENT

\ CONTAINMENT SYSTEMS 3/4.6.6   SECONDARY CONTAINMENT SHIELD BUILDING VENTILATION SYSTEM LIMITING CONDITION FOR OPERATION 3.6.6.1 Two independent shield building ventilation systems shall be OPERABLE.
APPLICABILITY:    MODES 1, 2, 3, and 4.
ACTION:
With one shield building ventilation system inoperable, restore the inoperable system to OPERABLE status within 7 days or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours.
SURVEILLANCE REQUIREMENTS 4.6.6.1 Each shield building ventilation system shall be demonstrated OPERABLE:                                              NSERT lb
: a. At l       . pr  a!      ...     -.   .     .
TS    . by initiating, from the control room, flow      rough the HEPA filters.and charcoal adsorbers and verifying th -the system operates for at least 10 hours continuous witr      e heaters on.
: b. At least
                   *on          1B          or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire, or chemical release in any ventilation zone communicating with the system by:
WATERFORD   - UNIT 3                    3/4 637                    AMENDMENT NO.

CONTAINMENT SYSTEMS K>
SURVEILLANCE REQUIREMENTS (Continued)
: 1.      Verifying that the ventilation system satisfies the In-place testing acceptance criteria and uses the test procedures of Regulatory Positions C.5.a, C.5.c, and C.5.d of Regulatory Guide 1.52, Revision 2, March 1978, and the system flow rate is 10,000 cfm : 10%.
: 2.      Verifying within 31 days after removal that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, shows the methyl Iodide penetration less than 0.5% when tested in accordance with ASTM D3803-1989 at a temperature of 30oC and a relative humidity of 70%.
: 3.      Verifying a system flow rate of 10,000 cfm + 10% during system operation when tested In accordance with ANSI N510-1975.
: c. After every 720 hours of charcoal adsorber operation by verifying within 31 days after removal that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, shows the methyl Iodide penetration less than 0.5% when tested In accordance with ASTM D3803-1989 at a temperature of 300C and a relative Add INSERT lb
: d. AA' lat                   tow '
8*, --      by:
: 1.      Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks is less than 7.8 Inches water gauge while operating the system at a flow rate of 10,000 cfm
* 10%.
: 2.      Verifying that the system starts on a safety injection actuation test signal.
: 3.      Verifying that the filter cooling bypass valves can be manually cycled.
: 4.      Verifying that each system produces a negative pressure of greater than or equal to 0.25 Inch water gauge in the annulus within I minute after a start signal.
: 5.      Verifying that the heaters dissipate 60 + 6.0, -6.0 kW when tested in accordance with ANSI N510-1975.
ATERFORD    - UNIT 3                        3/4 6-38                    AMENDMENT NO. *?6       i9 I

CONTAINMENT SYSTEMS SHIELD BUILDING INTEGRITY LIMITING CONDITION FOR OPERATION 3.6.6.2 SHIELD BUILDING INTEGRITY shall be maintained with an annulus negative pressure greater than 5 inches water gauge.
APPLICABILITY:           MODES 1, 2, 3, and 4.
ACTION:
Without SHIELD BUILDING INTEGRITY, restore SHIELD BUILDING INTEGRITY within 24 hours or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours.
SURVEILLANCE REQUIREMENTS j
         ~' I   *~ I     I I    I   1   1  ~      I    I   I ~   I   I   I   I   I   I   '~   ~    I   I   I   I   I   I 4.6.6.2     SHIELD BUILDING INTEGRITY shall be demonstrated:
: a.      At least ... : per12 h2 r-*:             by verifying the annulus pressure to be within its limits.                             A
: b.             ...
At 4east        .1
                               .. pe-        d.ay by verifying that each door in each access opening is closed except when the access opening is being used for normal transit entry and exit, then at least one door shall be closed.
WATERFORD - UNIT 3                                    3/4 6-40                                AMENDMENT NO.
I        ~    ~   I  I  I   I   I    ~    I    I   I   I   I   I   I    I  I I   I   I   I   I   ~

\     PLANT SYSTEMS SURVEILLANCE REQUIREMENTS
     ~~~~~secured In position, Is InIts correct   .. ,.s po_            .    ..
: b. At least once per 92 days nla                                 bymu3at testing thesEFW pumps pursuant to the Inservice Testing Program.           surveillance requirement Is not required to be performed for the turbine-driven EFW p          until 24 hours after exceeding 750 psig In the steam generators.
Add INSERT lb C. Mt least, ee pe. 18 manthi3 by:
: 1. Verifying that each automatic valve In the flow path actuates to Its correct position upon receipt of an actual or simulated actuation signal.
NOTE:         This surveillance requirement Is not required to be performed for the turbine-driven EFW pump until 24 hours after exceeding 750 psig In the steam generators..
K..>2.               Verifying that each EFW pump starts automatically upon receipt of an actual or simulated actuation signal.
: d. Prior to entering MODE 2,whenever the plant has been In MODE 4, 5. 6 or defueled, for 30 days or longer, or whenever feedwater line cleaning through the emergency feedwater line has been performed, by verifying flow from the condensate storage pool through both parallel flow legs to each steam generator.
NATERFORD - UNIT 3                           314 7-5                   AMENDMENT NO.,           478, NAP-

PLANT SYSTEMS K.)  CONDENSATE STORAGE POOL LIMITING CONDITION FOR OPERATION 3.7.1.3 The condensate storage pool (CSP) shall be OPERABLE with:
: a. A minimum contained volume of at least 92% indicated level.*
: b. A water temperature of greater than or equal to 55 0 F and less than or equal to 1006F.
APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION:
In MODES 1. 2. and 3:
With the condensate storage pool inoperable, within 4 hours restore the CSP to OPERABLE status or be In at least HOT STANDBY within the next 6 hours and in HOT SHUTDOWN within the following 6 hours.
In MODE 4:
With the condensate storage pool Inoperable, within 4 hours restore the CSP to OPERABLE status or be in at least COLD SHUTDOWN within the next 24 hours.
SURVEILLANCE REQUIREMENTS
           .3.1   he con ensate storage pooi shall be demonstrated OPERABLE:
: a. At lat    ,,e, pJo e',   'l,   by verifying the contained water volume Is within its limits.                       Add INSERT l b
: b. At l-st a,,ice, pet 24 hours by verifying CSP temperature when the RAB air temperature is less than 55&deg;F or greater than 100&deg;F.
in   MODE 4, the CSP shall be OPERABLE with a minimum contained volume of at ast 11% indicated level.
WATERFORD - UNIT 3                              3/4 7-6                     AMENDMENT NO. 46-,-.1 !99 I

TABLE 4.7-1 SECONDARY COOLANT SYSTEM SPECIFIC ACTIVITY
_SAMPL                 AND ANALYSIS PROGRAM
               '   ''-''   '*            y    y*          V*           ~
PE OF MEASUREMENT                                    SAMPLE AND ANALYSIS AND ANALYSIS                                                FREQUENCY Gross Activity Determination I
Isotopic Analysis for DOSE                   a)   I per 31 dy-s, whenever EQUIVALENT 1-131 Concentration                    the gross activity determina-tion indicates iodine con-centrations greater than 10%
of the allowable limit.
b)   4-pe-p .6me^i, whenever the oss activity determination indicates iodine concentra-tions below 10% of the aIlowable limit.
I    I I I  I I  I    I
* I I   I I  I  I I I I   I
_j 1~~~~~
K)
WATERFORD - UNIT 3                          3/4 7-8                            MNT NO.
AM EN

PLANT SYSTEMS MAIN STEAM LINE ISOLATION VALVES (MSIVs)
LIMITING CONDITION FOR OPERATION 3.7.1.5 Two MSIVs shall be OPERABLE.
APPLICABILITY:      MODE 1, and MODES 2, 3, and 4, except when all MSIVs are closed and deactivated.
ACTION:
MODE 1 With one MSIV inoperable, restore the valve to OPERABLE status within 8 hours or be In STARTUP within the next 6 hours.
MODES 2, 3 and 4 With one MSIV inoperable, close the valve within 8 hours and verify the valve is closed once per 7 days. Otherwise, be in HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours.
The provisions of Specification 3.0.4 are not applicable.
Q> SURVEILLANCE REQUIREMENTS Note: Required to be performed for entry into MODES 1 and 2 only.
: a. By verifying full closure within 8.0 seconds when tested pursuant to the Inservice Testing Program.
: b. By verifying each MSIV actuates to the isolation position on an actual or simulated actuation signal at lea c".ee per ,0 m1,th8,s.
WAE        R 3Add                                                  INSERT la                   +
WAEFR           -UI                            1   -             MEDETN.-6*,9,19

PLANT SYSTEMS SMAIN        FEEDWATER ISOLATION VALVES LIMITING CONDITION FOR OPERATION.
3.7.1.6 Each Main Feedwater Isolation Valve (MFIV) shall be OPERABLE.
APPLICABILITY: MODES 1, 2, 3, and 4.
ACTION:
Note: Separate Condition entry is allowed for each valve.
With one or more MFIV inoperable, close and deactivate, or Isolate the inoperable valve within 72 hours and verify Inoperable valve dosed and deactivated or isolated once every 7 days; otherwise, be In at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours.
The provisions of Specification 3.0.4 do not apply.
SURVEILLANCE REQUIREMENTS
   *.4.7.1.6 Each main feedwater isolation valve shall be demonstrated OPERABLE:
 *.a.                 By verifying Isolation within 6.0 seconds when tested pursuant to the Inservice Testing Program.
: b.      By verifying actuation to the isolation position on an actual or simulated actuation signal e .,t . .. Pe.         ....n--
                                                            -4Add         INSERT la           4 W *TERFORD- UNIT 3                             3/4 7-9a               AMENDMENT NO.-3-, -I~89-099,.t

314.7 PLANT SYSTEMS 314.7.1.7 ATMOSPHERIC DUMP VALVES LIMITING CQNDITION FOR OPERATION 3.7.1.7 Each Atmospheric Dump Valve (ADV) shall be OPERABLE*.
APPLICABILITY:       MODES 1, 2, 3, and 4 ACTION:
: a. With the automatic actuation channel for one ADV inoperable, restore the inoperable ADV to OPERABLE status within 72 hours or reduce power to less than or equal to 70% RATED THERMAL POWER within the next 6 hours.
: b. With the automatic actuation channels for both ADVs inoperable, restore one ADV to OPERABLE status within 1 hour or reduce power to less than or equal to 70% RATED THERMAL POWER within the next 6 hours.
: c. With one ADV inoperable, for reasons other than above, restore the ADV to OPERABLE status within 72 hours or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours.
The provisions of Specification      .4 are not ap icble pe OPERABLE.
K> SURVEILLANCE REQUIREMENTS 4.7.1.7 The ADVs shall be demonstrated OPERABLE:
: a. By performing a CHANNEL CHECK at least mea per 12 ,ati when the automatic actuation channels are required to be OPERABLE.
: b. By veriflying each ADV automatic actuation channel is in automatic wit setpoint of less than or equal to 1040 psia at lcf.ts. ee per .the 9... ,dewhe automatic actuation channels are required to be OPERABLE.                          Add INSERT la
: c. By verifying one complete cycle of each ADV when teste                ant to t Inservice Testing Program.
: d. By performing a CHANNEL CALIB TION of each ADV automa                     actuation channel at least
                          ..      ...p18      rnhs.
: e. By verifying actuation of each ADV to the open position on an actual or simulated automatic actuation signal et least en.. pr       nths.
* ADV  automatic actuation channels (one per ADV, in automatic with a setpoint of less than or equal to 1040 psia) are not required to be OPERABLE when less than or equal to 70% RATED THERMAL POWER for greater than 6 hours.
WATERFORD - UNIT 3                             3/4 7-9b                           AMENDMENT NO. I=-

PLANT SYSTEMS 3/4.7.3 COMPONENT COOLING WATER AND AUXILIARY COMPONENT COOLING WATER SYSTEMS LIMITING CONDITION FOR OPERATION 3.7.3 At least two independent component cooling water and associated auxiliary component cooling water trains shall be OPERABLE.
APPLICABILITY: MODES 1,2, 3, and 4.
ACTION:
With only one component cooling water and associated auxiliary component cooling water train OPERABLE, restore at least two trains to OPERABLE status within 72 hours or be In at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours.
SURVEILLANCE REQUIREMENTS co     onent cooling water and associated auxiliary component cooling watertai s all bed          nr
: a.      A4 le 3tpr           .3+dy ~ n~nhat each valve (manual, power-operated, or automati            clng safety-related equipment*
that is not locked, sealed, or otherwise        red in position, is in its correct position.Ad                                             NET6-
: b.      mt least ese pe, iC   e mthft by       lying that dch automatic valve ser .vicing safety-related equipment actua       to Its correct position on SIAS and CSAS test signals.
C.      At !east oi eepe 1380mos th by verifying that each component cooling water and associated auxiliary component cooling water pump starts automatically on an SIAS test signal.
WATERFORD - UNIT 3                             314 7-11                            AMENDMENT NO. EGO-

PLANT SYSTEMS LIMITING CONDITION FOR OPERATION (Continued)
ACTION: (Continued)
: c.       With a Tornado Watch in effect, all 9 DCT fans under the missile protected portion of the DCT shall be OPERABLE. If the number of fans OPERABLE is less than required, restore the inoperable fan(s) to OPERABLE status within 1 hour, or be in at least HOT STANDBY within 6 hours and in HOT SHUTDOWN within the following 6 hours.
temperature at least once every 2 hours and verify that the minimum fan requirements of Table 3.7-3 are .satisfied (required only if the associated UHS is OPERABLE),
SURVEIL     NCE REQUIREMENTS 4.7.4. E ch train of UHS shall be determined OPERABLE:
I   a.  ,lAst  cnec per 24 he         by veying the average water temperature and water level to be i                  limits. Add INSERT lb
: b.      At-*,*st on'Ctpr ,.01 day-, by            nat each wet tower and dry tower fan that is not already running, starts and operates for at least 15 minutes.
WATE     ORD - UNIT 3                         3/4 7-13               AMENDMENT NO. 9        ,-123,2H

PLANT SYSTEMS ACTION (Continued):
: e. With one or more control room emer                         n            r      .     "  .,
0        nI       eo           8          OE       or 6,or during load movements with or over irradiated fuel assemblies, immediately suspend ,j.
                        -cn load movements with or over irradiated fuel assemblies and operations                            MODES 1, 2, involving CORE ALTERATIONS.                        air  filtration  trains inoperable in                               "
emergency                                               LCO 3.0.3.
          *. f. With two control room                                      b, immediately enter other    than   ACTION
               ~   3, or 4 for reasons                                                                              MODES 5 ..*t CORE ALTERATIONS.
air  filtration  trains inoperable in With two controlinvolving room emergency                                          fuel assemblies, i*-      ~g.                                                    with    or over irradiated                      assemblies or during load 6operations movements                         or over irradiated fuel and and                 suspend      load movements with
         *"        immediately hours with 10 continuous r,,least           byS initiating, mm%
TA,  . foZE  FED T       ESToE^  charcoal     adsorbers) 3,    ... .*,-; operates
                                                   *system              t  E     EPA filters     and a.from..........             the flow      through
              ~             the control  thatroom,                                                                                      .
      *"           and verifying
                   *"                                                                                INSERT b l             by:
_..,-Add                                        system
      ."the heaters on.                                                                  with the         on the        2 or  ') (after   any   structural maintenance fire or communicating
                                ;,*,         p;   13   ,' t~
m,-*            zone                              painting, following testing
: b.       *&#xa2;A*t cn*t                        ventilationhousings, or (2)
  ',. ~                              or          any adsorber charcoal in                                        the   in-place
               ~ HEPA release filter                                       satisfies                                            2,
     !             chemical                                        train                                      1.52, Revision the   filtration                                  Guide that
* Verifying                                            Regulatory 1.
f"                                          and   C.5.d of procedures of Regulatory C.5.a, C.5.c,  and uses the test                                                          .
        "                      , oPositions criteria
                    ~ acceptance                                                                 cfm     10%.
intermittently
                                                                                                       +/-
under flowmay          4225 ratebeis opened March 1978, and           the system boundary
       !*.*-                                       (CRE) gNote control     room envelope 1:    The control.
administrative T4AMEOS EWT   RFORDQUI

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
: 2. Verifying within 31 days after removal that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, shows the methyl iodide penetration less than 0.5% when tested in accordance with ASTM D3803-1989 at a temperature of 30&deg;C and a relative humidity of 70%.
: 3. Verifying a system flow rate of 4225 cfm +/-10% during train operation when tested in accordance with ANSI N510-1975.
: c. After every 720 hours of charcoal adsorber operation by verifying within 31 days after removal that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, shows the methyl iodide penetration less than 3     and a reaie        humty of .0 ~
Add INSETl
: d. At11.14        p    18men'ha by:
: 1. Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks Is less than 7.8 inches water gauge while operating the train at a flow rate of 4225 cfm +/-10%.
: 2. Verifying that on a safety injection actuation test signal or a high radiation test signal, the train automatically switches into a recirculation mode of operation with flow through the HEPA filters and charcoal adsorber banks and the normal outside airflow paths isolate.
: 3. Verifying that heaters dissipate 10 +1.0, -1.0 kW when tested in accordance with ANSI N510-1975.
: 4. Verifying that on a toxic gas detection signal, the system automatically switches to the isolation mode of operation.                                   +1
: e. After each complete or partial replacement of a HEPA filter bank by verifying that the HEPA filter banks remove greater than or equal to 99.95% of the DOP when they are tested in-place in accordance with ANSI N510-1975 while operating the train at a flow rate of 4225 cfm +/-10%.
: f. After each complete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorbers remove greater than or equal to 99.95% of a halogenated hydrocarbon refrigerant test gas when they are tested in-place in accordance with ANSI N510-1975 while operating the train at a flow rate of 4225 cfm +/-10%.
: g. Perform required control room envelope unfiltered air inleakage testing in accordance with the Control Room Envelope Habitability Program.                      4-W  'ERFORD - UNIT 3                        3/4 7-17            AMENDMENT NO. 14q5,14-,94

PLANT SYSTEMS CONTROL ROOM AIR TEMPERATURE - OPERATING LIMITING CONDITION FOR OPERATION 3.7.6.3   Two independent control room air conditioning units shall be OPERABLE.
APPLICABILITY*: MODES 1, 2, 3, and 4.
ACTION:
: a. With one control room air conditioning unit inoperable, restore the inoperable unit to OPERABLE status within 7 days or be in HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours.
: b. With two control room air conditioning units inoperable, return one unit to an OPERABLE status within 1 hour or be in HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours.
SURVEILLANCE REQUIREMENTS OPERABLE:
: a. A.t leat ene. pe.r 42 hrw, by rifying that the operating control room air conditioning unit is mn-           verage control room air temperature less than or equal to 800 F,                   Add INSERT lb
: b. A.At *ea*t qu.,t4ery, if  e ormed within the last quarter, by verifying that each control room air conditioning unit starts and operates for at least 15 minutes.
*During load movements with or over irradiated fuel assemblies, TS 3.7.6.4 is also applicable.
WATERFORD - UNIT 3                         3/447-18a    Amendment No. 115, 141,188, 218,2-36 I

PLANT SYSTEMS 3L4.7.7 CONTROLLED VENTILATION AREA SYSTEM K> *LIMITING CONDITION FOR OPERATIQN 3.7.7 Two independent controlled ventilation area systems shall be OPERABLE.
APPLICABILITY: MODES 1, 2, 3, and 4.
ACTION:
With one controlled ventilation area system inoperable, restore the Inoperable system to OPERABLE status within 7 days or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours.
SURVEILLANCE REQUIREMENTS
          *""  ~         ..  -.. I....                  .     .                     by..
: a. A la ct      rwe pz3ds e.... a .TAG.ER..T. T BAB! byinitiating, from the control room, flow throth the HEPA filters and charcoal adsorbers and verifying that the system opera         or at least 10 hours continuous with the heaters on.                                      Add INSERhTlbte
: b. At less
                       ,        . nee=
                                   .. p, ..... s (1)after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire, or chemical release in any ventilation zone communicating with the system by,:
: 1.      Verifying that the controlled ventilation area system satisfies the in-place testing acceptance criteria and uses the test procedures of Regulatory Positions C.5.a, C.5.c, and C.5.d of Regulatory Guide 1.52, Revision 2, March 1978, and the system flow rate is 3000 din t: 10%.
: 2.      Verifying within 31 days after removal that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, shows the methyl iodide penetration less than 0.5% when tested in accordance with ASTM D3803-1989 at a temperature of 30"C and a relative humidity of 70%.
: 3.      Verifying a system flow rate of 3000 cfm
* 10% during system operation when tested in accordance with ANSI N510-1975.
TERFORD - UNIT 3                           3/4 7-19                            AMENDMENT NO.       0 DEC 2 72009 I

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
: c. After every 720 hours of charcoal adsorber operation by verifying within 31 days after removal that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, shows the methyl iodide and c            asb            b s i       c r 7 n ineter'gauge 1989 at a temperature of 30sC and a relative humidity of 7000c%.
ask -           -1m---_.Add                              INSERT lb
         >. d.     ,At lee, . ene r     pe. .8 .. e,t,*,   by:---   "
         *.I1               Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks is less than 7.8 inches water gauge
            ~while                  operating the system at a flow rate of 3000 cfm +/- 10%.
: 2.       Verifying that the system starts on a Safety Injection Actuation Test Signal and achieves and maintains a negative pressure of .
0.25 inch water gauge within 45 seconds.
: 3.       Verifying that the filter cooling bypass valves can be manually cycled.
: 4.       Verifying that the heaters dissipate 20 + 2.0, -2.0 kW when tested in accordance with ANSI N510-1975.
: e. After each complete or partial replacement of a HEPA filter bank by verifying that the HEPA filter banks remove greater than or equal to 99.95% of the DOP when they are tested in-place in accordance with ANSI N510-1975 while operating the system at a flow rate of 3000 cfm +
10%.
: f. After each complete or partial replacement of a charcoal absorber bank by verifying that the charcoal adsorbers remove greater than or equal to 99.95% of a halogenated hydrocarbon refrigerant test gas when they are tested in-place in accordance with ANSI N510-1975 while operating the system at a flow rate of 3000 cfm +/- 10%.
WATER    RD - UNIT 3                           3/4 7-20                AMENDMENT NO. 170, i94,-219 Next Page is 3/4 7-27 k   I  I    '. I   ~  I   I     I  I  I  I  I I I  I. I  I I  I I I. I I I I

PLANT SYSTEMS 3/4.7.12 ESSENTIAL SERVICES CHILLED WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.12 Two independent essential services chilled water loops shall be OPERABLE.
APPLICABILITY: MODES 1, 2, 3, and 4 ACTION:
With only one essential services chilled water loop OPERABLE, restore two loops to OPERABLE status within 72 hours or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours.
SURVEILLANCE REQUIREMENTS
: 4. 12.1 achofheabvrqire                         sntIeicshie                  I      p sh be demonstrated OPERABLE:
: a. ,-,,as .......     ,-   8 d,,"y,by, verifyng that each valve (manual,
          *-power-operated, or autoniU                       ervicing safety-related equipment
          *-that               is not locked, sealed, or oth-efts       erd in position, is in its correct position.                                         Add INSERT 1b
: b. Ait :ast e,-x, ps 31 days by ,*ti-ing that t              ater outlet temperature is < 42&deg;F at a flow rate of > 0 gpm.
: c. Deleted
: d. At lent -nce per 1_ von~th_, by verifying that each essential services chilled water pump and compressor starts automatically on a safety
                                                                                                           -I-Injection actuation test signal.
4.7.    .2 The backup essential services chilled water pump and chiller shall be d   monstrated OPERABLE in accordance with Specification 4.7.12.1 whenever it is  rnctioning as part of one of the required essential services chilled wate     oops.
WAT       FORD - UNIT 3                              3/4 7-43                              AMENDMENT NO. M I    I                       I  ~  I  I   I  I  ~      I   I  I  I  I  I I I I I I I

ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS transmission network and the onsite       las  I E distributibn yse          s
: a. Determined OPERABLE at lcs't enc per 7 dy tverifying correct breaker alignments, indicated power availablity, an)Add                         INSERT Ia
: b. Demonstrated OPERABLE at least ene p.             18  *t*... by transferring manually and automatically unit power supply from the normal circuit to the alternate circuit.
4.8.1.1.2 Each diesel generator shall be demonstrated OPERABLE*:                          Add INSERT lb
: a. A4 leCat enee per 31, days,'-., e STAGGERED TEST B,,.              by:
: 1.      Verifying the fuel level in the diesel oil feed tank,
: 2.      Deleted,
: 3.      Verifying the fuel transfer pump can be started and transfers fuel from the storage system to the diesel oil feed tank,
: 4.      Verifying the diesel starts**. The generator voltage and frequency shall be at least 3920 volts and 58.8 Hz in r 10 seconds after the start signal. The steady state voltage and frequency shall be maintained at 4160 + 420, -240 volts and 60 +/- 1.2 Hz. The diesel generator shall be started for this test by using one of the following signals:
a)      Manual.
b)      Simulated loss-of-offsite power by itself.
c)      Simulated loss-of-offsite power in conjunction with an ESF actuation test signal.
d)      An ESF actuation test signal by itself.
 *AII planned starts for the purpose of surveillance in this section may be preceded by a prelube period as recommended by the manufacturer.
modified diesel generator start involving idling and gradual acceleration to
  .,nchronous speed may be used for this surveillance requirement as recommended by manufacturer. When modified start procedures are not used, the time, speed, oltage, and frequency tolerances of this surveillance requirement must be met.
TERFORD - UNIT 3                            3/4 8-3                  AMENDMENT NO. 39,4I26-24e

ELECTRICAL POWER SYSTEM SURVEILLANCE REQUIREMENTS (Continued)
: 5.       Verifying the generator is synchronized, loaded to an indicated 4000-4400 Kw* in accordance with the manufacturer's recommendation and operates for at least an additional 60 minutes#, and
: 6.       Verifying the diesel generator is aligned to provide standby ower to the rI
: b. At leas',   ,.... p.
                                 . -31 d.*ys and after each operation of the diesel where the period of operation was greatehhan or equal to 1 hour by checking for and removing accumulated water from t diesel oil feed tanks.
: c. Deleted
            "    .                                  *.-Add INSERT 1b          I
 *This band is meant as guidance to avoid routine overloading of the engine. Loads in excess of this band for special testing under direct monitoring of the manufacturer or momentary variation due to changing bus loads shall not invalidate the test.
"#Thissurveillance requirement shall be preceded by and immediately follow without shutdown a successful performance of 4.8.1.1.2a.4 or 4.8.1.1.2d.
WATERFORD - UNIT 3                               3/4 8-4     AMENDMENT NO. 4,23,92,126.10e,216 I

ELECTRICAL POWER SYSTEMS Add INSERT lb                       -,
: d. At lces'. enee pc, 184 day* a diesel g aerator fast start test shall be performed in accordance with TS 4.8.1.1.2a.4. P rformance of the 184 do fast start test satisfies the 31 day testing req uments specified in TS 4.8.1.1.2a.4.
: e.    ,, . .    .     .     ...     .
ss  by:
: 1.      Verifying the generator capability to reject a load of greater than or equal to 498 kW while maintaining voltage at 4160 +420, -240 volts and frequency at 60 +4.5, -1.2 Hz.
: 2.      Verifying the generator capability to reject a load of an indicated 4000-4400 kW without tripping. The generator voltage shall not exceed 5023 volts during and following the load rejection.
: 3.       During shutdown, simulating a loss-of-offsite power by itself, and:
a)        Verifying deenergization of the emergency busses and load shedding from the emergency busses.
b)       Verifying the diesel starts on the auto-start signal, energizes the emergency busses and the permanently connected loads within 10 seconds after the auto-start signal, energizes the auto-connected shutdown loads through the load sequencer and operates for greater than or equal to 5 minutes while its generator is loaded with the shutdown loads. After energization, the steady-state voltage and frequency of the emergency busses shall be maintained at 4160 +420, -240 volts and 60 +1.2, -0.3 Hz during this test.
: 4.      Verifying that on an SIAS actuation test signal (without loss-of-offsite power) the diesel generator starts on the auto-start signal and operates on standby for greater than or equal to 5 minutes. The steady-state generator voltage and frequency shall be 4160 +420, -240 volts and 60 +/- 1.2 Hz within 10 seconds after the auto-start signal; the generator voltage and frequency shall be maintained within these limits during this test.
WATERFORD - UNIT 3                   3/4 8-5         AMENDMENT NO. 4,23,,74,.8,9,,126,1,0,246

ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
: 8.      During shutdown, verifying the diesel generator's capability to:
a)       Synchronize with the offsite power source while the generator is loaded with its emergency loads upon a simulated restoration of offsite power, b)       Transfer its loads to the offsite power source, and c)       Be restored to its standby status.
: 9.      During shutdown, verifying that with the diesel generator operating in a test mode (connected to its bus), a simulated safety injection signal overrides the test mode by (1) returning the diesel generator to standby operation and (2) automatically energizes the emergency loads with offsite power.
: 10. Verifying that each fuel transfer pump transfers fuel to its associated diesel oil feed tank by taking suction from the opposite train fuel oil storage tank via the installed cross connect.
: 11. During shutdown, verifying that the automatic load sequence timer is OPERABLE with the time of each load block within +/-10% of the sequenced load block time.
: 12. Verifying that the following diesel generator lockout features prevent diesel generator starting only when required:
a)       turning gear engaged b)       emergency stop d)       governor-fuel oil linkage tripped
: f. Deleted                                      :Add INSERT l
: g. At least ene pe 19ye           or after any modifications which could affect diesel generator interdependence by starting the diesel generators simultaneously, during shutdown, and verifying that the diesel generators accelerate to at least 600 rpm (60 +/- 1.2 Hz) in less than or equal to 10 seconds.
: h. Deleted W ERFORD - UNIT 3                         3/4 8-6a AMENDMENT NO. 23,92,126,4100,21,246

ELECTRICAL POWER SYSTEMS DIESEL FUEL OIL LIMITING CONDITION FOR OPERATION 3.8.1.3 The stored diesel fuel oil shall be within limits for each required diesel generator (DG).
APPLICABILITY: When associated DG is required to be OPERABLE.
ACTION: (Note: Separate ACTION entry is allowed for each DG.)
: a. With the fuel oil storage tank volume less than 39,300 gallons and greater than 37,000 gallons, restore fuel oil storage tank volume to greater than or equal to 39,300 gallons within 5 days (provided replacement fuel oil is onsite within the first 48 hours).
: b. With one or more DGs with stored fuel oil total particulates not within limits, restore fuel oil total particulates to within limits within 7 days.
: c. With one or more DGs with new fuel oil properties not within limits, restore stored fuel oil properties to within limits within 30 days.
: d. Ifany of the above ACTIONS cannot be met, or if the diesel fuel oil is not within limits for reasons other than the above ACTIONS, immediately declare the associated DG(s) inoperable.
SURVEILLANCE REQUIREMENTS 4.8.1.3.1     A4eet    enee peF 31 dayS 0. a ST-AGGERED TEST BAS               verify each fuel oil storage tank volume.
4.8.1.3.2     Verify fuel oil properties of new or stored fuel oil are teste in accordance with, and maintained within the limits of, the Diesel Fuel Oil Testing      ogram.
jAdd INSERT l b WATERFORD         - UNIT 3                          3/4 8-8a                        AMENDMENT NO. 246'4%

ELECTRICAL POWER SYSTEMS 3/4.8.2   D.C. SOURCES OPERATING LIMITING CONDITION FOR OPERATION 3.8.2.1  As a minimum the following D.C. electrical sources shall be OPERABLE:
: a. 125-volt Battery Bank No.. 3A-S and one associated full capacity charger (3A1-S or 3A2-S).
: b. 125-volt Battery Bank No. 3B-S and one associated full capacity charger (3B1-S or 3B2-S).
: c. 125-volt battery Bank No. 3AB-S and one associated full capacity charger (3AB1-S or 3AB2-S).
APPLICABILITY:. MODES 1, 2, 3, and 4.
ACTION:
: a. With one of the required'battery banks inoperable, restore the inoperable battery bank to OPERABLE status within 2 hours or be in at least HOT STANDBY withinthe next 6 hours and in COLD SHUTDOWN within the following 30 hours.
: b. With one of the required full capacity chargers Inoperable, demonstrate the OPERABILITY of its associated battery bank by performing Surveillance Requirement 4.8.2.1a.1 within 1 hour, and at least once per 8 hours thereafter. If any Category A limit in Table 4.8-2 is not met, declare the battery. inoperable.
SURVEILLANCE REQUIREMENTS        .
: 4. .2.1 Each 125-volt battery bank and at-least one associated charger shall b demonstrated OPERABLE:                          Add INSERT lb--
a.*   At Ileat enee per 7 day-oby verifying that:
          .1. *The parameter's Ini Table 4.8-2 meet the Category A~limits, and
: 2. The total battery teminal'voltage Is greater than or-equal to 125 volts on float charge.
A RFORD - UNIT 3                     3/ 4 *.8-9         AmM1E1N4DU MIEC N4T1 INO.

S6VEILLANCE REUIREMENTS (Continued)
: b. At  le-.s. .... pe.. 92 days and within 7 days after a battery discharge with battery termital voltage below 110-volts, or battery overcharge with battery termina         tage above 150 volts, by verifying that:
: 1. The parameters in Table 4.          meet the Category B limits,
: 2. there is no visible corrosion at eit        terminals or connectors, or the connection resistance of these ite           1 AddINSERT
                                                                          "       lb 150 x 10-6 ohms, and
: 3. The average electrolyte            ture of a r a0om sample of at least ten of the        cde, cells is above/    F.
: c. At   l     t-o--r---IS.. months by verifying th   :
: 1. The cells, cell plates, and battery a s show no visual indication of physical damage or abnormal dete loration,
: 2. The cell-to-cell and terminal co e ions are clean, tight, and coated with anticorrosion.mater I
: 3. The resistance of each cell- -c 1 and terminal connection is less than or equal to 150x 0- ohms, and
: 4. The battery charger will upp        at least 150 amperes for 3A-S, 3A2-S; 3B1-S and 3B2-S nd 2 amperes for 3AB1-S and 3AB2-S at greater than or equal o 13 volts for at least 8 hours.
: d. At.least          .n.e18 .inths,d ing shutdown, by verifying that the pep battery capacity is adequate        supply and maintain in OPERABLE status all of the actual-or mulated emergency loads for the design duty cycle when the batte        s subjected to a battery service test.
: e. At least .n.e pep 60 months during shutdown, by verifying that the battery capacity is at least 80% of the manufacturer's rating when.
subjected to a performance discharge test. This performance discharge test may be performed in lieu of the battery service test required by Surveillance Requirement 4.8.2.1d.
: f. Annual performance discharge tests of battery capacity shall be' given to any battery thatshows signs of degradation or has reached 85% of the service life expected for the application. Degradation is indicated when the battery capacity drops more than 10% of rated capacity from its average on previous performance tests, or is below 90% of the manufacturer's rating.
WA  RFORD - UNIT 3                     3/4 8-10                  AMENDMENT NO. --
OCT 1 4 1992

ELECTRICAL POWER SYSTEMS LIMITING CONDITION FOR OPERATION (Continued)
ACTION:
: a. With one of the required divisions of A.C. ESF busses not fully energized, reenergize the division within 8 hours or be in at least HOT STANDBY within-the next*6 hours and in COLD SHUTDOWN within the following 30 hours.
: b. With one A.C. SUPS bus either not energized from its associated inverter, or with the inverter not connected to its associated D.C.
bus: (1) reenergize the A.C. SUPS bus within 2 hours or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours and (2) reenergize the A.C. SUPS bus from its associated inverter connected to its associated D.C. bus within 24 hours or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours.
: c. With one D.C. bus not connected to its associated battery bank, reconnect the D.C. bus from its associated OPERABLE battery bank within 2 hours or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours.
SURVEILLANCE REQUIREMENTS                                                       f 4.8.3.1 The specified busses shall be determined energized in the required manner at leat eee p*r 7 d-:- by verifying correct breaker alignment and indicated voltage on the bu es.
Add INSERT la rWATERFORD -  UNIT 3                  3/4 8-14            AMENDMENT NO.

ELECTRICAL POWER SYSTEMS ONSITE POWER DISTRIBUTION SHUTDOWN LIMITING CONDITION FOR OPERATION 3.8.3.2 As a minimum, the following electrical busses shall be energized in the specified manner:
: a.      One division of A.C. ESF busses consisting of one 4160 volt and one 480-volt A.C. ESF bus (3A3-S and 3A31 -S or 3B3-S and 3B31 -S).
: b. Two 120-volt A.C. SUPS busses energized from their associated inverters connected to their respective D.C. busses (3MA-S, 3MB-S, 3MC-S, or 3MD-S).
: c.      One 120-volt A.C, SUPS Bus (3A-S or 3B-S) energized from its associated inverter connected to its respective D.C. bus.
: d.      One 125-volt D.C. bus (3A-DC-S or 3B-DC-S) connected to its associated battery bank.
APPLICABILITY: MODES 5 and 6.
ACTION:
With anyie of the above required "electrical i
busses i      not energized in the required D
manner, p s N1vr        V ddltionfs ha could resuttin loss of required           D       M     No boron concentration, or load movements with or over irradiated fuel, initiate corrective        1 action to energize the required electrical busses in the specified manner as soon as possible.
SURVEILLANCE REQUIREMENTS 4.8.3.2 The specified busses shall be determined energized in the required manner-et lcast enc peF 7 days by verifying correct breaker alignment and indicated voltage on the busses.
WATERFORD         - UNIT 3                      3---1-MEDEN-                            O.--5 3

ELECTRICAL POWER SYSTEMS 3/4.8.4   ELECTRICAL EQUIPMENT PROTECTIVE DEVICES CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES LIMITING CONDITION FOR OPERATION
 *.8.4.1   Primary and backup containment penetration conductor overcurrent             ]
rotective devices associated with each containment electrical penetration circuit shall be OPERABLE. The scope of these protective devices excludes hose circuits for which credible fault currents would not exceed the elec-rical penetration design rating.
PPLICABILITY: MODES 1, 2, 3, and 4.
ACTION:
: a. With one or more of the above required containment penetration conductor overcurrent devices inoperable:                                                        1. Restore the protective device(s) to OPERABLE status or deenergize the circuit(s) by tripping, racking out, or removing the alternate device or racking out or removing the inoperable device within 72 hours, and
: 2. Declare the affected system or component Inoperable, and
: 3. Verify at least once per 7 days thereafter the alternate device is tripped, racked out, or removed, or the device is racked out or removed.
Otherwise, be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours.
: b. The provisions of Specification 3.0.4 are not applicable to overcurrent devices which have the inoperable device racked out or removed or, which have the alternate device tripped, racked out, or removed.
URVEILLANCE REQUIREMENTS 4.8.4.1 The above noted primary and backup containment penetration conductor overcurrent protective devices shall be demonstrated OPERABLE:
: a. At lest.......
eepe      mon-ths: <_         -,Ad   INSERT 1E]
: 1. By verifying that the medium voltage (4-15 kV) circuit breakers are OPERABLE by selecting, on a rotating basis, at least 10% of the circuit breakers of each voltage level, and performing the following:
(a)  A CHANNEL CALIBRATION of the associated protective relays, and (b)  An integrated system functional test which includes simulated automatic actuation of the system and verifying that each relay and associated circuit breakers and control circuits function as designed.                                          4 ATERFORD - UNIT 3                     3/4 8-16                AMENDMENT NO. 716-I   r

ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
(c)  For each circuit breaker found inoperable during these functional tests, an additional representative sample of at least 10% of all the circuit breakers of the inoperable type shall also be functionally tested until no more failures are found or all circuit breakers of that type have been functionally tested.
: 2. By selecting and functionally testing a representative sample of at least 10% of each type of lower voltage circuit breakers.
Circuit breakers selected for      t            .,11
* Lu ar aI       aif  . T ing Sf these circuit breakers, except for those rears with external trip devices,*
shall consist of injectinga current in excess of the breakers' nominal setpoint and measuring the response time. The measured response time will be compared to the manufacturer's data to ensure that it is less than or equal to a value specified by the manufacturer. Circuit breakers found inoperable during functional testing shall be restored to OPERABLE status prior to resuming operation. For each circuit breaker found inoperable during these functional tests, an additional representative sample of at least 10% of all the circuit breakers of the inoperable type shall also be functionally tested until no more failures are found or all circuit breakers of that type have been functionally tested.
: b. At least c... pep 6. mor.th. by subjecting each circuit breaker to an inspection and preve ive maintenance in accordance with procedures prepared in conjunctio with its manufacturer's recommendations.
sting of these circuit breakers (i.e., the 480 volts power from low ltage switchgear) shall be performed in accordance with the manufacturer's-4 ecommendations.
TERFORD  -    UNIT 3                  3/4 8-17                 AMENDMENT NO. 26-A1IG25 1992

ELECTRICAL POWER SYSTEMS MOTOR-OPERATED VALVES THERMAL OVERLOAD PROTECTION AND BYPASS DEVICES LIMITING CONDITION FOR OPERATION 3.8.4.2  The thermal overload protection and bypass devices, integral with the motor starter, of each valve used in safety systems shall be OPERABLE.
APPLICABILITY:  Whenever the motor operated valve is required to be OPERABLE.
ACTION:
With one or more of the thermal overload protection and/or bypass devices inoperable, declare the affected valve(s) inoperable and apply the appropriate ACTION Statement(s) for the affected valve(s).
SURVEILLANCE REQUIREMENTS 4.8.4.2 The above required thermal overload protection and bypass devices shall be demonstrated OPERABLE.
: a. At l:e:t en:e per 18 menth       .by the performance of a CHANNEL FUNCTIONAL TEST of the b       .. f   cuitry for thod devices which are either:                           Add INSERT lb
: 1. Continuously bypassed and temporari        placed in force only when the valve motors are undergoing ..riodlc or maintenance testing, or
: 2. Normally in force during        ant operation  Add iNERT accident conditions.                          Add I
: b. At.....t m.. pr18
                          ..    .e.... by the performadce of a CHANNEL CALIBRATION of a representative sample of at least 25% of:
: 1. All thermal overload devices which are not bypassed, suc       that each nonbypassed device is calibrated :t 1&#xfd;-t ^n-- f.
6 yeaps.
: 2. All thermal overload devices which are continuously byp sued and temporarily placed in force only when the valve mot rs are undergoing periodic or maintenance testing, and thermal overload devices normally in force and bypassed under a cident conditions such that each thermal overload is calibrat        and each valve is cycled through at least one complete cycc       of full travel with the motor-operator when the thermal o erload is OPERABLE and not bypassed, at least cnce pep 6 ye...
WATERFORD - UNIT 3                     3/4 8-52                    AMENDMENT NO. 75-fl! d-- 9

314.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION LIMITING CONDITION FOR OPERATION.
3.9.1 With the reactor vessel head closure bolts less than fully tensioned or with the head removed, the boron concentration of all filled portions of the Reactor Coolant System and the refueling canal shall be maintained uniform and sufficient to ensure that the more restrictive of the reactivity conditions specified in the COLR is met.
APPLICABILITY: MODE 6*.
ACTION:
With the requirements of the above specification not satisfied, immediately suspend all operations involving CORE ALTERATIONS or positive reactivity changes and initiate action to restore boron concentration to within COLR limits.
SURVEILLANCE REQUIREMENTS.
4.9.1.1 The more restrictive of the above two reactivity conditions shall be determined prior to:
: b.      Withdrawal of any CEA in excess of 3 feet from its fully inserted position within -.--
the reactor pressure vessel.
4.9.1.2 The boron concentration of the Reactor Coolant System and the refueling canal shall be determined by chemical analysis a, leat oe, pe 72 hu*.
              *"                                               ~Add INSERT la           I"
*The reactor shall be maintained in MODE 6 whenever fuel is in the reactor vessel with the reactor vessel head closure bolts less than fully tensioned or with the head removed.
WATERFORD         - UNIT 3                     3/4 9-1              AMENDMENT NO. 402,191

REFUELING OPERATIONS 314.9.2 INSTRUMENTATION LIMITING CONDITION FOR QPERATON                ..
3.9.2 As a minimum, two source range neutron flux monitors shall be OPERABLE
.and operating, each with continuous visual Indication in the control room and one with audible indication in the containment and control room.
APPLICABILITY: MODE 6.
: a. With one of the above required monitors Inoperable or not operating, immediately suspend all operations involving CORE ALTERATIONS or operations that would cause introduction into the RCS, coolant with boron concentration less than required to meet the boron concentration of Technical Specification 3.9.1.
: b. With both of the above required monitors inoperable or not operating, determine the boron concentration of the Reactor Coolant System at least once per 12 hours.
-SURVEILLANCE REQUIEMENTS.
4.9.2 Each source range neutron flux monitor shall be demonstrated OPERABLE by performance *" of:                                        *_       **,--Add       INSERT 1la.)
: a. A CHANNEL CHECK at :least m,.            d12 hoG,
: b. A CHANNEL FUNCTIONAL TEST within 8 hours prior to the I ial start of CORE ALTERATIONS, and
: c. A CHANNEL FUNCTIONAL TEST a,                 w       "7-.a, d-WATERFORD - UNIT 3                           314 9-2                         AMENDMENT NO. -10 MAR 07 2003

REFUELING OPERATIONS 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS LIMITING CONDITION FOR OPERATION 3.9.4 The containment building penetrations shall be in the following status:
: a. The equipment door is closed,
: b. A minimum of one door in each airlock is capable of being closed, and
: c. Each penetration providing direct access from the containment atmosphere to the outside atmosphere shall be either:
: 1. Closed by a manual or automatic isolation valve, blind flange, or equivalent, or
: 2.      Capable of being closed by an OPERABLE containment purge and exhaust isolation system.
Note: Penetration flow path(s) described in a, b, and c above, that provides direct access from the containment atmosphere to the outside atmosphere may be unisolated under administrative controls.
APPLICABILITY: During COR                              a      ,mn*~    dho 'e     radiated fuel within,,ki' h
ACTION:
With the requirements of the above specification not satisfied, immediately suspend all operations involving CORE ALTERATIONS or load movements with or over irradiated fuel in the containment building.
SURVEILLIANCE REQUIREMENTS 4.9.4.1 Verify each required containment penetration is in the required status prior to the start of and enee pet7*-day n       during CORE ALTERATIONS or load movements with or over irradiated fuel within .4 containment.     "'&#xfd;           Add INSE&#xfd;RT la 4.9.4.2 Verify each required containment p' ge and exhaust valve actuates to the isolation position on an actual or simulated actuation signal 72 he*,Fe prFir t pcfrming initial CORE A^""ERAT^O"'
or load movements with or over irradiated fuel within containment.
OTE - SR 4.9.4.2 is not required to be met for containment purge and exhaust valve(s) in enetrations closed to comply with LCO 3.9.4.c. 1.
TERFORD      - UNIT 3                      3/4 9-4           AMENDMENT NO. 69,231,2-M6

REFUELING OPERATIONS 314.9.8 SHUTDOWN COOLING AND COOLANT CIRCULATION HIGH WATER LEVEL LIMITING CONDITION FOR OPERATION 3.9.8.1 At least one shutdown cooling train shall be OPERABLE and in operation.*
APPLICABILITY: MODE 6 when the water level above the top of the fuel seated in the reactor pressure vessel Is greater than or equal to 23 feet.
ACTION.
With no shutdown cooling train OPERABLE and in op         tion, suspend all operations involving an increase in the reactor decay heat load or  perations that would cause introduction into the RCS, coolant with boron concentration less th    required to meet the boron concentration of Technical Specification 3.9.1 and im    diately initiate corrective action to return I the required shutdown cooling train to OPERABLE an      operating status. Close all containment penetrations providing direct access from the contain   ent atmosphere to the outside atmosphere within 4 hours.
SURVEILLANCE REQUIREMENTS 4.9.8.1 At least one shutdown cooling train shall be v ified to be In operation and circulating reactor coolant at a flow rate of greater than or equal 4000 gpm** at 1=3t 01-IM pe 12 hou.             .
 *The shutdown cooling loop may be removed from o ration for up to 1 hour per 8-hour period during the performance of CORE ALTERATIONS i he vicinity of the reactor pressure vessel hot legs, provided no operations are permitted that    uld cause Introduction into the RCS, coolant with boron concentration less than required o meet the minimum required boron concentration of Technical Specification 3.9.1.
 "The minimum flow may be reduced to 3000 gpm a r the reactor has been shut down for greater than or equal to 175 hours or by verifying a ast once per hour that the RCS temperature is less then 135F. The minimum flow ay be reduced to 2000 gpm after the reactor has been shut down for greater than or equ to 375 hours.
WATERFORD - UNIT 3                            314 9-8                 AMENDMENT NO. 85--O,      i4-,
PAR 0*7 2003

REFUELING OPERATIONS LOW WATER LEVEL LIMITING CONDITION FOR OPERATION 3.9.8.2 Two# Independent shutdown cooling trains shall be OPERABLE and at least one shutdown cooling train shall be In operation.*
A*PLICABILITY. MODE 6 when the water level above the top of the fuel seated In the reactor pressure vessel is less than 23 feet.
ACTION:
: a. With one of the r uired shutdown cooling trans Inopera e, Im e ia el In !a corrective action return the required train to OPERABLE status, or to establish greater than or e     I to 23 feet of water above the top of the fuel seated In the                  "<
reactor pressure essel.
: b. With no shutdow          oling train OPERABLE and In operation, suspend operations that would cause intr     uction into the RCS, coolant with boron concentration less than required to meet   ne boron concentration of Technical Specification 3.9.1 and Immediately InIti  e corrective action to return the required shutdown cooling train to 0    RABLE and operating status. Close all containment penetrations pro     ing direct access from the containment atmosphere       to the outside atmosph     e within 4 hours.
KJ SURVEILLANCE REQU EMENTS 4.9.8.2 At least one sh own cooling train shall be verified to be In operation and circulating reactor coolant at a flow te of greater than or equal to 4000 gpm** ,.".                    .,;-.
[Add INSERT la                .
    #Only one shutdown         ling train Is required to be OPERABLE and in operation provided there are no irradiated fuel ssemblies seated within the reactor pressure vessel.
    *The shutdown cooling op may be removed from operations for up to I hour per 8-hour period during the perf. ance of CORE ALTERATIONS In the vicinity of the reactor pressure vessel hot le, provided no operations are permitted that would cause introduction into the RCS, coolant th boron concentration less than required to meet the minimum required boron conce tration of Technical Specification 3.9.1.
   *"Theminimum flow m         be reduced to 3000 gpm after the reactor has been shut down for greater than or equal     175 hours or by verifying at least once per hour that the RCS, temperature is less t       135&deg;F. The minimum flow may be reduced to 2000 gpm after the reactor has been shu      own for greater than or equal to 375 hours.
WATERFORD - UNIT                                  3/4 9-9                   AMENDMENT NO. 85.48 ,-16          -
MAR 07 2003

REFUELING OPERATIONS
_> 3/4.9.10  WATER LEVEL - REACTOR VESSEL FUEL ASSEMBLIES LIMITING CONDITION FOR OPERATION 3.9.10.1 At least 23 feet of water shall be maintained over the top of the reactor pressure vessel flange..
APPLICABILITY: During movement of fuel assemblies within the reactor pressure vessel when either the fuel assemblies being moved or the fuel assemblies seated within the reactor pressure vessel are irradiated.
ACTION:
With the requirements of the above specification not satisfied, suspend all operations involving movement of fuel assemblies within the pressure vessel.
SURVEILLANCE RE VUI  EMTS 4.9.10.1 The water level shall be determined to be at least its minimum required depth within 2 hours prior to the start of and :ft. :at ece pc-24 he"ms thereafter during movement offuelassemblies.
Add INSERT l WATERFORD - UNIT 3                  3/4.9-11             AMENDMENT NO.

lltsn REFUELING OPERATIONS CEAs                                                                              JJ LIMITING CONDITION FOR OPERATION 3.9.10.2 At least 23 feet of water shall be maintained over the top of the fuel seated in the reactor pressure vessel.
APPLICABILITY: During movement of CEAs within the reactor pressure vessel, when the fuel assemblies seated within the reactor pressure vessel are irradiated.
ACTION:
With the requirements of the above specification not satisfied, suspend all operations involving movement of CEAs within the pressure vessel.
3.
4.9.10.2 The water level shall be determined to be at least its minimum required depth within 2 hours prior to the start of and at l*a*t .... Pe 24- hle*ti thereafter during movement of CEAs.               V      CAddINSERT la WATERFORD - UNIT 3                    3/4 9-12           AMENDMENT NO.

REFUELING OPERATIONS 3/4.9.11 WATER LEVEL - SPENT FUEL POOL LIMITING CONDITION FOR OPERATION 3.9.11 At least 23 feet of water shall be maintained over the top of irradiated fuel assemblies seated in the storage racks.
APPLICABILITY:   Whenever irradiated fuel assemblies are in the spent fuel pool.
ACTION:
With the requirement of the specification not satisfied, suspend all movement of fuel assemblies and crane operations with loads in the fuel storage areas and restore the water level to within its limit within 4 hours.
SURVEILLANCE REQUIREMENTS 4.9.11 The water level in the spent fuel pool shall be determined to be at least its minimum required depth at lceat enee per 7 day: when irradiated fuel assemblies are in the spent fuel pool.
                                                 \"-Add INSERT la K>
AMFNflMFNT NO
              - UNIT 3                  3/4 9-13

3/4.9.12 SPENT FUEL POOL (SFP) BORON CONCENTRATION LIMITING CONDITION FOR OPERATION 3.9.12 The spent fuel pool boron concentration shall be > 1900 ppm.
APPLICABILITY: When fuel assemblies are stored in the SFP.
ACTION:
: a.      With the spent fuel pool boron concentration not within limits immediately suspend movement of fuel in the SFP and immediately initiate actions to restore boron concentration to within limits.
: b.      The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.9.12 Verify the spent fuel pool concentration is within limits enee per7 ,dey,.
Add INSERT la         I WATERFORD - UNIT 3                           3/4 9-1 3a                       AMENDMENT NO. H -3

3/4.10 SPECIAL TEST EXCEPTIONS 3!4.10.1 SHUTDOWN MARGIN LIMITING CONDITION FOR OPERATION 3.10.1 The SHUTDOWN MARGIN requirement of Specification 3.1.1.1 or 3.1.1.2 may be suspended for measurement of CEA worth and SHUTDOWN MARGIN provided reactivity equivalent to at least the highest estimated CEA worth is available for trip insertion from OPERABLE CEA(s).
APPLIC6B&#xb6;LIIY: MODES 2 AND 3*.
ACTION:
: a.      With any CEA not fully inserted and with less than the above reactivity                   - "
equivalent available for trip insertion, immediately initiate boration to restore the SHUTDOWN MARGIN required by Specification 3.1.1.1.
: b.      With all CEAs fully inserted and the reactor subcritical by less than the above reactivity equivalent, Immediately initiate boration to restore the SHUTDOWN MARGIN required by Specification 3.1.1.2.
SURVEILLANCE REQUIREMENTS 4.10.1.1 The position of each CEA required either partially or fully withdrawn shall be determined -t        em,, per 2 hour . (                    IAdd INSERT la 4.10.1.2 Each CEA not fully inserted shall be demonstrated capable of full insertion when tripped from at least the 50% withdrawn position within 7 days prior to reducing the SHUTDOWN MARGIN to less than the limits of Specification 3.1.1.1.
       *Operation in MODE 3 shall be limited to 6 consecutive hours.
WATERFORD - UNIT 3                              3/4 10-1                AMENDMENT NO. -4144,          '1, K> .,,

SPECIAL TEST EXCEPTIONS 314.10.2 MODERATOR TEMPERATURE COEFFICIENT. GROUP HEIGHT. INSERTION. AND POWER DISTRIBUTION LIMITS LIMITING CONDITION FOR OPERATION 3.10.2 The moderator te        erature coefficient, group height, insertion, and power distribution limits of Specifications 3.1.  .3, 3.1.3.1,3.1.3.5, 3.1.3.6, 3.2.2, 3.2.3, 3.2.7, and the Minimum           Channels OPERABLE req         Jement of Functional Unit 15 of Table 3.3-1 may be suspended during the performance of      HYSICS TESTS provided:
: a. The THER        L POWER is restricted to the test power plateau which shall     t exceed 85% of RATED THERMAL POWER, and
: b. The limits o Specification 3.2.1 are maintained and determined as specified in pecification 4.10.2.2 below.
APPLICABILITY: MODES " nd 2.
ACTION:
With any of the limits of Sp cification 3.2.1 being exceeded while the requirements of Specifications 3.1.1.3, 3.1. ., 3.1.3.5, 3.1.3.6, 3.2.2, 3.2.3, 3.2.7, and the Minimum Channels               -"
OPERABLE requirement o .,unctional Unit 15 of Table 3.3-1 are suspended, either:
: a.      Reduce TH       MAL POWER sufficiently to satisfy the requirements of Specificatio     .2.1, or
                                        >-                   I~Add INSERT Ia         ]"
: b.      Be in HOT S NDBY within 6 hours.
SURVEILLANCE RZQUIR MENTS 4.10.2.1 The THERMAL P             ER shall be determined at .... :, .... per haw during PHYSICS TESTS in which the require ents of Specifications 3.1.1.3, 3.1.3.1, 3.1.3.5, 3.1.3.6, 3.2.2, 3.2.3,          -[
3.2.7, or the Minimum Cha els OPERABLE requirement of Functional Unit 15 of Table 3.3-1 are suspended and shall b verified to be within the test power plateau.
4.10.2.2 The linear heat ra      shall be determined to be within the limits of Specification 3.2.1 by monitoring it continuously         the Incore Detection Monitoring System pursuant to the requirements of Specificati     s 4.2.1.2 during PHYSICS TESTS above 5% of RATED THERMAL POWER in which the requi        ments of Specifications 3.1.1.3, 3.1.3.1, 3.1.3.5, 3.1.3.6, 3.2.2,           -h 3.2.3, 3.2.7, or the Minimu     Channels OPERABLE requirement of Functional Unit 15 of Table 3.3-1 are suspended.
WATERFORD        - UNIT 3                      3/4 10-2                  AMENDMENT NO. 4-3,136,        8&2-

SPECIAL TEST EXCEPTIONS 3/4.10.3      REACTOR COOLANT LOOPS                                   .
LIMITING CONDITION FOR OPERATION 3.10.3 The noted requirements of Tables 2.2-1 and 3.3-2 may be suspended during the performance of startup and PHYSICS TESTS, provided:
: a. The THERMAL POWER does not exceed S% of RATED THERPAL POWER, and either
: b. The reactor trip setpoints of the OPERABLE poer level channel c.. l~re core The          protection-calculator increased                      operatin tlic to greeaterithanthe'-logar   bypasspower-hi pemissve trip setpoints setpoint ppecified in Table 2.2-2 and less than 51% RATED THERMAL POWER.
APPLICAB LITY:      During startup and PHYSICS TESTS.
With the THERMAL POWER greater than t1 of RATED THERMAL POWER, Immediately trip the reactor.
I 4.10.3. The THERMAL POWER shall.e        determined to be less than or equal to 5%
of RATE    THERMAL   POWER at- least         per be-r during startup and PHYSICS TESTS.'*               "    ""          '*                " "   ."              .
4.10.3. Each wide range logarithwiic and pover level neutron fluxmonitoring channel hall be subjected to a CHANNEL FUNCTIONAL TEST within L2 hours prior to ini ating startup and PHYSICS.TESTS..
WATER    RD -   UNIT 3                    314 10-3                      AMENDMENT NO. 2 I

SPECIAL TEST EXCEPTIONS 3/4.10.5     NATURAL CIRCULATION TESTING LIMITING CONDITION FOR OPERATION 3.10.5 The limitation of Specification 3.4.1.2 may be suspended during the performance of natural circulation testing, provided the Reactor Coolant System saturation margin is maintained greater than or equal to 200 F.
APPLICABILITY:         MODE 3 during natural circulation testing.
ACTION:
With the Reactor Coolant System saturation margin less than 20*F,* immediately place at least one reactor coolant loop in operation, with at least one reactor coolant pump.
4.10.5.1 The saturation margin shall be determined to be within theabove limits by continuous monitoring with the saturation margin monitors required by Table 3.3-10 or, by calculating the saturation margin at leat e.ee per 39 m-,in-tes.   < - -- --- -- Add
           ...........                        S dd INSERT   la               .
4.10.5.2 The saturation margin monitor shall be demonstrated OPERABLE by performance of a CHANNEL CHECK within 24 hours prior to initiating natural circulation testing.
WATERFORD - UNIT 3                         3/4 10-5

I- RADIOACTIVE EFFLUENTS K> GAS STORAGE TANKS LIMITING CONDITION OR OPERATION shall be limited to less than or equal to 8.5 x 10 curies noble gases (considered as Xe-133 equivalent).
APPLICABILITY:    At all times.
ACTION:
: a. With the quantity of radioactive material in any gas storage tanks exceeding the above limit, immediately suspend all additions of radioactive material to the tank. Within 48 hours reduce the tank 1~
contents to within the limits and describe the events leading to this condition in the next Radioactive Effluent Release Report,                -
pursuant to Specification 6.9.1.8.
: b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
qHIfVFTI: airr DPflhITfFMflJTq 4.11.2.6 The quantity of radioactive material contained in each gas storage tank on-service shall be determined to be withir the above limit at least.'
per 7 dtys until the quantity exceeds 4.25 x 10 curies noble gases (50% of allowed limit) and then at least once per 24 hours when radioactive materi s are being added to the tank. Tanks isolated for decay will be sampled to verify above limit is met within 24 hours following removal from service.
Add INSERT la WATERFORD - UNIT 3                   3/4 11-17                           Amendment No. +-W
                                                  \...-
                                                    !%&#xfd;
                                                             .IJ LALAA&.
I&#xfd;P k C a C 1k YIt. I[
IF - 6 I (JI.
U-1   -70 (

ADMINISTRATIVE CONTROLS 6.5.17   Control Room Envelope Habitability Program (Continued)
: a. The definition of the CRE and the CRE boundary.
: b. Requirements for maintaining the CRE boundary in its design condition including configuration control and preventive maintenance.
: c. Requirements for (i) determining the unfiltered air inleakage past the CRE boundary into the CRE in accordance with the testing methods and at the Frequencies specified in Sections C.1 and C.2 of Regulatory Guide 1.197, "Demonstrating Control Room Envelope Integrity at Nuclear Power Reactors,"
Revision 0, May 2003, and (ii) assessing CRE habitability at the Frequencies specified in Sections C.1 and C.2 of Regulatory Guide 1.197, Revision 0.
: d. Measurement, at designated locations, of the CRE pressure relative to all external areas adjacent to the CRE boundary during the pressurization mode of operation by one train of the control room emergency air filtration, operating at the flow rate required by SR 4.7.6.1 .b1,a-t a, FREeIENY of 8 rnith-e         ,
STACCEEB TECT BASIS. The results shall be trended and used as par of the assessment of the CRE boundary.                                   Add INSERT la-
: e. The quantitative limits on unfiltered air inleakage into the CRE. These limits shall be stated in a manner to allow direct comparison to the unfiltered air inleakage measured by the testing described in paragraph c. The unfiltered air inleakage limit for radiological challenges is the inleakage flow rate assumed in the licensing basis analyses of DBA consequences. Unfiltered air inleakage limits for hazardous chemicals must ensure that exposure of CRE occupants to these hazards will be within the assumptions in the licensing basis.
: f. The provisions of SR 4.0.2 are applicable to the FREQUENCIES for assessing CRE habitability, determining CRE unfiltered inleakage, and measuring CRE pressure and assessing the CRE boundary as required by paragraphs c and d, respectively.
       <Add                          INSERT3           I WATERFORD - UNIT 3                            6-9}}