ML20080R465
| ML20080R465 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 03/06/1995 |
| From: | Hansen A NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20080R468 | List: |
| References | |
| NUDOCS 9503090315 | |
| Download: ML20080R465 (15) | |
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_ O UNITED STATES '
q NUCLEAR REGULATORY. COMMISSION
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t WASHINGTON, D.C. 30666 4001
' WISCONSIN ELECTRIC POWER COMPANY b.;-
DOCKET NO. 50-266 POINT BEACH NUCLEAR PLANT. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE-Amendment No. 161 License No. DPR-24 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Wisconsin Electric Power Company (the licensee) dated December 22, 1994, as' supplemented February 1, 1995, and February 21, 1995, complies with the standards and requirements of'the Atomic Energy Act of 1954, as amended (the Act),
and the Commission's rules and regulations set forth in 10 CFR '
Chapter I; B.
The facility will operate in-conformity with the application, the provisions of the Act, and the rules and regulations of the-Commission; C.
There is reasonable assurance (i) that the activities-authorized by this amendment can be' conducted without endangering the health and safety of the public, and (ii) that such activities ' ill be w
conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
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9503090315 950306 PDR ADOCK 05000266 P
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' Accordingly,ithe. license is amended by. changes to the Technical Specifications asfindicated-in the attachment to this license amendment, and~ paragraph 3.B of Facility Operating License.No.
DPR-24 is hereby amended-to read as follows:
B.
Technica1>Soecifications The Technical, Specifications contained in Appendices A and B,-
as revised through Amendment No.161. are hereby incorporated in the license. The licensee sha11' operate the facility in accordance with. the Technical Specifications.
^
3.
This license amendment is effective immediately upon issuance. The Technical Specifications are to be implemented within 45 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION fff-- -f./
Allen G. Hansen, Project Manager Project Directorate III-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes.to the Technical Specifications-Date of issuance: March 6, 1995 i
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UNITED STATES g
gg NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20065-0001
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' WISCONSIN ELECTRIC POWER COMPANY DOCKET NO. 50-301L
' POINT BEACH NUCLEAR PLANT. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment'No. 165
-License No. DPR-27 1.-
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Wisconsin Electric Power Company
~
(the licensee) dated December 22, 1994, as supplemented February 1, 1995, and February 21, 1995, _ complies with:the standards'and-requirements of the Atomic Energy Act of 1954, as amended (the' Act),
and the Commission's rules and regulations l set forth in 10 CFR.
Chapter.I; i
B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by -
this amendment'can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
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Accordingly, the license ~is amended by changes to the Technical Specifications as-indicated in the attachment to this license amendment, and paragraph 3.B'of. Facility 0perating License No.
L DPR-27 is hereby amended to read as follows:
V L
B.
Technical Specifications t
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' The Technical Specifications contained in Appendices A and B, l-as revised through Amendment No.165, are hereby incorporated in the license. The licensee shalT operate the facility in
-accordance with the Technical Specifications.
3.
.This license amendment is effective immediately upon issuance. The Technical Specifications are to be implemented within 45 days from the date of issuance, i-FOR THE NUCLEAR REGULATORY COMMISSION
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Allen G. Hansen, Project Manager-Project Directorate-III-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: March ' 6, 1995 I
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' ATTACHMENT :TO LICENSE AMENDMENT-NOS.161 AND1An
.TO FACILITY GPERATING LICENSE f;0S. DPR-24 AND DPR-27:
DOCKET NOS. 50-266 AND 50-301' J evise' Appendix A Technical Specifications by removing the pages identified R
- below and inserting the enclosed pages. The revised pages are identified by amendment number and contain vertical lines indicating the ~ area of change..
REMOVE INSERT
'TS 15.3.3-6' TS 15.3.3-6
.TS 15.3.3-8 TS 15.3.3-8 TS 15.3.4-2a TS 15.3.4-2a TS Table.15.3.5-3, page 2 of 2 TS. Table 15.3.5-3, page 2 of 2 L TS 15.3.7-1 through TS 15.3.7-1 through TS'15.3.7-3 (3 pages)
TS.15.3.7-3 -(3 pages)
TS 15.3.7-8.
.TS 15.3.7-8 TS Table 15 3.14-1 TS Table 15.3.14-1 TS Table 15.4.1-1, page 2 of 6 TS Table 15.4.1-1, page 2. of 6
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Four; service water! pumps?are operable, two;from each train.* ' d E b. . All'. necessary valves,: interlocks:and ' piping required for. the. ~ w y functioning of the Service Water System during accident 1 4 f, conditions'are also operable. l .2. During power operatio'n,' thel requirements ofil5.3.3.D-l'may be modified 1 w B Tf to allow. one.of the fo110 wing 1 components to;be. inoperable atl any one: N time.,If~the system is not restored to meet:the conditions ofL 15.3.3.D-1 within the. time; period specified, both' reactors will be-f placed in the hot sh'utdown condition within:six hours;and in' cold d ' shutdown within 36 hours. One ofIthe four required service water, pumps ~may be out. of f h a. service 'provided a pump is restored to operable ~ status.within - 24 hours. i s b. One of the two loop' headers may be out of service' for a period sf I ~24 hours. - A valve or other passive component may be out' of. service-provided c. repairs can be completed within 48 hours. R Basis ~ j: 1 The normal procedure for starting the reactor is', first, to heat thelreactor l coolant to near operating temperature, by running the reactor coolant / pumps The reactor is then made' critical by withdrawing control rodsland/or diluting ~ l boron in the coolant.m With this mode of start-up,/the energy stored in the
- l reactor coolant during the approach to criticality is substantially equal to l
that during power operation and.therefore to be conservative mosteng'ineered safety. system components and auxiliary cooling. systems,"shall be fully operable. j .? During low temperature physics tests there is a negligible amount of stored i energyjin the reactor coolant, therefore an-accident comparable in severity to- ~ 3 the' Design Basis Accident-is not'possible,'and.'he engineered safety systems are j ^ t not-required.-
- l During the Unit 1 1995 refueling outage, one train A service water pump l
operating with power supplied by.the' Alternate Shutdown System, B08/B09 480E .i . volt buses, may be considered operable from a normal-(offsite) power - + ~' supply, under the provisions of Technical Specification 15.3.0.C.- lj t s Unit' 1 - Amendment No. -),7),))),))p,161 15.3.3-6 Unit 2L ' Amendment No. ,h,J)f,J)),165 y - 1 I -. ~.. -. - - .-.-~ J
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- g' l@ l DAssumingthereactorhaslbeenoperatingat' full;ratedpower;foriatilea'stl100: days,y
,', Lthe magnitude lof theTdecay heat decreases as followst aft'er. initiating. hot" / -Q -. ,.s T y w '"< (
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l 1 Time After Shutdown; Decav' Heat % of Rated Power-F ~ .c 1[t I min. 3.6? i 1.551 ' 30 min. m o~ w 3-hour- =1.25e Ih I $ J8 hours 0.7L ~ 48: hours. 10.4i g
- Based on"ANS;5 1-1979 ;" Decay' Heat Power inL Light-Water Reactors"1
~ 8,,,, LThus, the requirement for core cooling in case ofca, postulated loss-of-coolant- 'accidentwhileiinthehotishutdown' condition'issignificantlyreducedbelow(th'e 05-' requirementi for. a postulated loss-of-coolant accident during power.' operation.: ~ s Putting the reactor in the. 'i shutdown condition significantly reduces the-poten - ,,m ~ tial consequences of a loss-a -coolant accident, and alsoiallowsimore free' access--
- tosomeoftheengineered:safetysystemcomponents.incordertoeffectlrepairs.
-When the failures involve the residual heat removal. system,'in order to insure g redundant means of decay heat. removal, the reactor system may remain ~in a condition with reactor coolant, temperatures greater than 350'F so'that the' reactor. coolant-loops and associated steam generators'may be' utilized for re'dundant' decay. ~ heat'. removal. However,1when the remaining RHR loop must be ~ relied upon for' j redundant decay heat removal. capability, reactor. coolant ' temperatures shall. be ~ maintained between 350 F and 140 F. With respect to the core cooling function, there-is some functional redundancy for ~ certain ranges of break sizes.(2) The operability of the Refueling Water Storage Tank _(RWST) as part of the ECCS - ensures that a sufficient supply of. borated water ~ is available.for. injection ~ by Lthe ECCS in the event of either a L'CA or a steamline break. The limits _on RWST-O j n Unit 1 - Amendment No. J$,J2),J)),161 15.3.3-8
- Unit 2 - Amendment No. 7J,J2),Jp),165
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a. ,o 2.- Single Unit' Operation.- One of the three. operable auxiliary feedwater pumps. associated with a unit may be out-of-service for the below . specified times. The' turbine driven auxiliary feedwater_ pump may-be -out-of-service for. up ~ to 72 hours. If the turbine driven auxiliary feedwater pump cannot be restored to service within that 72 hour time period, the reactor'shall be in hot shutdown within the next 12 hours. Either one of the two ' motor driven auxiliary feedwater pumps A: may be out-of-service for up'to 7 days.- If the motor driven l auxiliary feedwater pump cannot be restored to service within.that.7 day period the operating unit shall be in hot shutdown within the next 12 hours. D. The main steam stop; valves (MS-2017 and MS-2018) and the non-return check valves (MS-2017A and MS-2018A) shall be 'o'perable.. If one main. steam stop. valve or non-return check valve is inoperable but open, power operation may continue provided the inoperable valve is restored to operable status-within 4 hours,- otherwise the reactor shall be placed'in a hot shutdown t' condition within the following 6 hours. With one or more main steam stop valves or non-return check valves-inoperable, subsequent operation in the hot shutdown condition may proceed provided the inoperable valve or val'/es are maintained closed.. An inoperable main steam stop valve or non-return check valve may however, be opened in the hot shutdown condition to cool down the affected unit and to perform testing to confirm operability. . E. The crossover steam dump system shall be operable. If.the crossover steam dump system is determined to be inoperable, reduce power to less than 480 MWe (gross) within 3 hours. j F. During power operation, at least one of the turbine overspeed protection systems that trip the turbine stop valves or shut'the turbine governor -valves shall be operable. If all three systems are determined to be inoperable, isolate the turbine from the steam supply within the'next six .j hours. l 1 ' Unit 1 - Amendment No. /ISS,AA3,AA/,AE3,161 15.3.4-2a Unit 2 - Amendment No. AA/,AA/,AEA,AA/,165
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.) ..N; ' -TABLE 15.3.5-3-(continued)- ENGINEERED SAFETY. FEATURES 1 2 3 4 NO. OF MINIMUM ' PERMISSIBLE ~ NO. OF CHANNELS OPERABLE BYPASS ' OPERATOR ACTION IF CONDITIONS = NO. FUNCTIONAL UNIT CHANNELS 'T0 TRIP-CHANNELS CONDITIONS 0F COLUP913 CANNOT BE MET b. Start Turbine-Driven Pump 1. Undervoltage on 4KV Buses (A01 &'A02) 2/each 1/each 1/each Be in. hot' shutdown in 8 hours,E_ bus bus bus. 11. Low low Steam Gen. Water level 3/SG 2/each '2/SG" Be'ia hot' shutdown in.8 hours * ~ s SG 4. SAFETY-RELATED ELECTRICAL LOADS a. 4.16KV Buses (A05, A06) 1. Degraded Voltage 3/ bus 2/ bus 2/ bus" 11. [,oj,sofVoltage 2/ bus 1/ bus 1/ bus 3/ bus 2/ bus 2/ bus b. 480V Buses (803, B04) 1. Loss of Voltage 3/ bus 2/ bus 2/ bus,, Be in hot shutdown in 8 hours,. i If minimum conditions are not met within 24 hours after. reaching hot shutdown,. the-unit:shall be in cold shutdownl within 48 hours of the event causing the unit shutdown. If a channel is. determined to be' inoperable, resulting in one less;than the total ~ number of channels-being L operable, power operation m' .ontinue if the following conditions are met: v, 1. The minimum number of operable channels is still satisfied. 2. The'affected channels placed'in trip within 1-hour. Declare the associated standby emergency power supply inoperable for the affected bus. The applicable Limiting. Condition.for Operation (LCO) shall be entered. Separate LCOs maylbe entered for the Degraded Voltage and Loss:of. Voltage functions. Both switches.must be activated simultaneously.-. ~ Use the 3/ bus specification for each A05'and A06 bus that has been modified to the 2 out cf 3. logic for;the loss: of. voltage protection function. Unit 1 - Amendment No. AB,N,pp,AA/,AA/,161 Page 2 of 2 Unit 2 - Amendment No.. 59,52,66,Iff,16I,165:
, p; - 1 ,3 ,f y -2d ll,. l y.( 115.3;7l: AUXILIARY. ELECTRICAL SYSTEMS 1 jf j A'nolicability- -f j, V Applie's; to thel availability of off-site andi on-site electrical power for plant: ) ~ .g j ',~ Lpower operation and for the operation of plant auxiliaries.. t I ~ IObiective To define those conditions of. electrical power availabi1Ny necessary '(1) to. j ~ 7 provide for safe reactor operation, and'(2) to provide for the continuing; l availability'of engineered safeguards. j
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' Specificat' ion ] ' A.l' Under normal conditions neither one nor both reactors shall-be made l critical unless the following conditions.are met: l 'a. . At least two 345 KV transmission lines are in service. I b.- -The 345/13.8 KV and the 13.8/4.16 KV station auxiliary transformers-j associated with the reactor (s) to be taken critical. are in service; j or one 345/13.8 KV station auxiliary transformer and the associated l 13.8/4.16~KV station auxiliary transformer (s) are in service with the j ,.r gas turbine operating. -l c. 4160 Volt. unit supply buses A03 and A04 for the unit to be'taken. ~ critical are energized from their ' normal supply. .{ d. Both units' B03/B04 bus tie-breakers are open'with' control power b. a removed. l e. A fuel supply of 11,000 gallons'is available in each tank which is being relied upon to supply any operable emergency diesel j 1 generator (s). j f. Four of the five safety-related station batteries and all four of the main DC distribution systems are operable. q g. Four battery chargers are operable with one charger carrying the DC' l loads on each main DC distribution busi D01, D02, D03 and 004.- 1 h. 120 VAC Vital Instrument Buses Y01', YO2, Y03, YO4, Y101,.Y102, Y103, l and Y104 for the unit (s) to be taken critical are. energized from a- ~ safety-related inverter. l i. For both units to be made critical, the normal power supply and a 1 . standby emergency power supply to all the 4160/480 Volt safeguards ,l buses shall. be operable and the buses are energized from their normal j supply. i q l i l [ . Unit 1 - Amendment No. AA,87,J)f,J)),J)/,161 15.3.7-1 f i Unit 2 - Amendment No. AA,Af,JAA,Jf),J)),165
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p-3g 4 p c p y h, ! j.' For UnitL I. to be made: critical', the normal powerfsupply and a standby l emergency power supply to the'4160/480 Volt safeguards buses . Unit 1 A05/B03, Unit;1-A06/B04, and Unit' 2-A06/B04 shall be operable ~ and the. buses are energized from their normal supply. k. For Unit 2 to be made critical,' the normal power supply and a _ standby . emergency power supply to'the.4160/480 Volt safeguards. buses - Unit:2 A05/B03, Unit.2 A06/B04, and Unit l' A05/B03'shal_1.beLoperable Land the buses are energized from their normal supply. B.1 During power operation of one or both reactors, the requirements of. -15.3.7. A.1 may be modified to allow the.following arrangements' of systems .and components: a. If the 345 KV lines are reduced to only one, any operating reactor (s).- must be promptly reduced to, and limited to, 50% power. If all 345 KV lines are lost, 'any operating reactor (s) will2 be reduced to supplying its auxiliary load, until one or more 345 KV transmission lines are again available. b. If.both 345/13.8 KV auxiliary transformers are out of service and-only the gas turbine.is operating, only one reactor will remain operating and it will be limited to 50% power. The second reactor will be placed in the hot shutdown condition. c. If the 13.8/4.16 KV auxiliary transformers are reduced. to only one, -the reactor associated with the out of service transformer must be placed in the hot shutdown condition. d. With a unit in-cold or refueling shutdown or defueled, B03 and B04,- for that shutdown unit, may.be' tied together through their common tie l breaker for up to 8 hours provided the required' redundant decay heat removal in the shutdown unit and the, required redundant ~ shared engineered safety features for the other unit are operable. If the tie breaker cannot be opened or the conditions of 15.3.7.B.1.e met within 8 hours, the operating unit.shall be placed in the hot shut-down condition within 6 hours and in cold-shutdown within the following 30 hours. e. With a unit defueled, 803 and B04, for that shutdown unit, may be J tied together through their common tie-breaker in excess of 8 hours l provided: 1) An evaluation is performed to show that the loads that remain or can be energized'by the buses will not cause a potential overload of the l Unit 1 - Amendment No. A4#/N44,/1)),Jf),J)J,161 15.3.7-2 Unit 2 - Amendment No. $$,J)$,JJP,J)/,J)$,165 ~,
I? j; associated diesel generator. Th'e applicable Limiting. i Conditions for Operation of the equipment removed from service shall be entered for the operating unit.. 2)- A single train of spent _ fuel cooling is adequate = to' cool the - spent fuel. pool. 3) The required redundant shared engineered safety. features for the other unit are operable, f. The normal power supply or standby emergency power supply to Unit 1 A05/B03 or Unit 2 A06/B04 may be out-of service for a period not exceeding 7 days provided the required redundant-engineered safety, ~ features are operable and the~ required redundant standby emergency power supplies are started within 24 hours before or after entry.into this LC0 and every 72 hours thereafter. If the normal; power supply'is out of service, an operable emergency diesel generator is' supplying the'affected 4160/480 Volt buses. After 7 days, both units will be placed in hot shutdown within the following 6 hours and cold shutdown within 36 hours. g. The normal power supply or standby emergency power supply to Unit 1 A06/B04 or Unit 2 A05/B03 or both may be out of service for a period not exceeding 7 days provided the required redundant engineered safety features are operable and the required redundant standby - emergency power supplies are started within 24 hours before or after entry into this LCO and every 72 hours thereafter. If the normal power supply is out of service, an operable emergency diesel-generator is supplying the affected 4160/480 Volt buses. After 7 days, the affected unit or units will be placed in hot shutdown within the following 6. hours and cold shutdown within 36 hours. h. The normal power supply or standby emergency power-' supply to Unit 1 A05/B03 and Unit 2 A05/B03, or Unit 1 A06/B04 and Unit 2 A06/B04 may. t be out of service for a period not' exceeding 7' days provided.the ( required redundant engineered safety features are operable and the required redundant standby emergency power supplies are started within 24 hours before or after entry-into this LCO and every 72 hours thereafter. If the normal power supply is out.of service, an operable emergency diesel Unit 1 - Amendment No. A,E/,JAA,AAE, AA1,Aht, AEA,161 15.3.7-3 Unit 2 - Amendment No. pp,97,J75,1 6,152,156,157,165 i
m g V . tank provides sufficient fuel;to operate one EDG at design 1oad for more than.48 e' hours'.-), 2) the' EDG day' tank for that EDG'is operable and.for G-01 and G-02 the ! R ' associated motor-operated fill valve is. operable, 3) for. G-01 and' G-02, at least .one of.the two base-mounted sump tank fuel. oil transfer pumps is operable, and 4) c the fuel oil transfer system associated with the EDG is operable. However, the fuel oil transfer system is allowed to be out-of-service'for:four hours for G01 and G-02 due to'a combined four-hour. supply of fuel oil in the diesel base and-day tanks which do not require a fuel oil transfer pump' for flow to 'the-associated EDG. The fuel oil transfer system is allowed to be out-of-service for two hours for G-03 and G-04 due to a two-hour supply of fuel oil in the ' day tank.
- The transfer system may be out-of-service for longer periods if an appropriate alternate source of fuel is made available to the diesel generators.
.The EDG ventilation system is considered operable when diesel room temperature. can be maintained $120*F with the diesel engine operating at full load. 2 Temperature will be maintained 5120 *F if:l) all gravity-operated louvers are operable, and 2) both diesel room exhaust fans are operable E for G-01 and G-02; one diesel room exhaust fan is operable and outside air temperature -is $80*F; E - for G-03 and G-04, only the large capacity fan (W-183C for G-03, W-184B for G-04) is operable and outside air temperature is <84*F or if the small-capacity. fan (W-183B for G-03, W-184C for G-04) is operable and outside air temperature ~is $36*F. i . Normal DC control power must energize all DC circuits for the associated EDG to be operable. The original AEC Safety Evaluation for PBNP states, "0nsite fuel storage capacity is sufficient for a minimum of seven days' operation of the required safety feature loads which is acceptable." Therefore, to satisfy this requirement, at least 34,500 gallons of fuel oil will be maintained available for the emergency diesel generators at Point Beach at all times when EDG operability is required. If only one 345 KV transmission line is in service to the plant switchyard, a temporary loss of this line would result in a reactor trip (s) if the reactor (s) power level were greater than 50%. Therefore, in order to maintain ) l Unit 1 - Amendment No. JAf,AAA,161 15.3.7-8 Unit 2 - Amendment No. Mt,/lA8,165 i
r. + (y - y3 g p + w s TABLE 15.3.14-1' SAFE SHUTDOWN AREA FIRE PROTECTION-AUTOMAtlC SUPPRES$104 MANUAL SUPPRESSION WATER GAS LSPRINKLER SUPPRESSION FIRE MOSE FIRE AREA ELEVAft04 SYSTEM SYSTEM STATION DETECTION 1. Auxiliary Buttding South 8' (X) Partist-X 15 2. Aux 1Liary Buitding Center X 13 A. Safety injection Puups 8' X 8. Component CootIng Water Pusp X 3. AuxitIary Butiding North 8' (X) Partist X 9 4. Auxitiary tuiIding West 8' & Betou X 16 5. Auxitiary Butiding South 26' X '3' 6. Auxiliary Building Center 26' X 17-7. Auxiliary Building North 26' X '7 8. Auxiliary Building Center 46' X 6 9. Auxiliary Feeduster Pump Roosa 8' X X 11 10. Vital Switchgear & Battery Rooni 8' X X 8-
- 11. G01 Diesel Generator Roost 8'
X X 4
- 12. G02 Dieset Generator Room
-8' X X 4'
- 13. Cable Spreading Room 26' X
X 17 -
- 14. Circulating Water Pumphouse
. 8' X X 15 A. Service Water Puups
- 15. G03 Dieset Generator Room 28' X
X* - 3
- 16. G04 Dieset Generator Room 28' X
M* 3
- 17. G03 Vital Switchgear Room 28' X*
2
- 18. C04 vitet Switchgear Room 28' X*
2
- 19. G03 Fuel Olt Day Tank Room 28' X
X* 1
- 20. G04 Fuet Oil Day Tank Room 28' X
X* 1 i
- 21. G01/G02 Fuet Oil Transfer Puup Room 28' X
X* 1 ~ l
- Diesel Generator Building fire hose stations are located in Mechanical Equipment Roont.
l Unit 1 - Amendment No. ))pJJif,161 Unit 2-'AmendmentNo.)/J,))),165 \\
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PLANT CONDITIONS'- CHANNEL DESCRIPTION CHECK-CALIBRATE TEST WHEN REQUIREDJ - +ca 4 9. Steam Generator Flow Mismatch S(22) R.- Q(1) ALL. s 10. Steam Generator Pressure S(16) R-Q(1)- ALLJ ^ X 11. 4KV Bus Undervoltage-(A01 & A02) 4 -AFW pump actuation R M(1)- ALL- ~R -Reactor Protection actuation R .M(1,2)) ALL4 12. 4KV Bus Underfrequency (A01 & A02) -to Reactor Coolant Pump trip R ALL- ~13. Safeguards Bus Voltage -Loss of 4KV S' R M-ALL -Degraded 4KV .5 R'
- M
.ALL -Loss of 480V S R M 'ALL-14. 120 Vac Instrument Buses W(6) ALL. 15. Reactor Trip Signal:From Turbine- -Turbine Autostop M(1) -- ALL. + -Turbine Stop: Valve-M(1). ~ALL 16. Reactor Trip Signal-From SI, M(1) -ALL. 17. Feedwater Isolation-on SI- -MFP Trip on Safety Injectica.
- R..
ALL1 -MFRV Shutting on Safety Injection R: ! ALL - 18. Accumulator Level and Pressure S Rh ALLi 19. Analog Rod Position .S(8,22) R. .M(1) ~ LALL' L -with step counters .S(22) --ALL= -Monitoring by On-Line. Computer: l(18): PWR,HOTfS/D; i Unit 1-AmendmentNo.'7h,M,9),p,yM,yp,yp,161. .Pagel2 of 6?: Unit 2 -. Amendment No'. Jy,M,99, yyy, yyy,yff, NY,165 4 y .}}