ML19316A778
| ML19316A778 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  (DPR-44-A-69, DPR-56-A-068, DPR-56-A-68) |
| Issue date: | 05/16/1980 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19316A779 | List: |
| References | |
| NUDOCS 8005270508 | |
| Download: ML19316A778 (28) | |
Text
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.e UNITED STATES
[ %.. - [%h NUCLEAR REGULATCRY COMMISSION C
WASHING 1"sN. D C. 20555 s.g g...
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PHILADELPHIA ELECTRIC COMPANY PUBLIC SERVICE ELECTRIC AND GAS COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-277 PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 2 AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendment No. 69 License No. DPR-44 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Philadelphia Electric Company, et al. (the licensee) dated April 15, 1980, complies with the stand-ards 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 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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c Ob 8005270
- 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-44 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 69, are hereby incorporated in the license.
PECO shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
.gJ v. Q ]
Robert W. Reid, Chief Operating Reactors Branch #4 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
May 16, 1980 L
ATTACHMENT TO LICENSE AMENDMENT NO. 69 FACILITY OPERATING LICENSE N0. OPR-44 DOCKET N0. 50-277 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
Remove Pages Insert Pages 63 63 64 64 173 173 174 174 219 219 220 220 225 225 226 226 240f 240f 243 243 249 249 Page 63 is unchanged and is included for your convenience only.
4 PBAPS i
'0IES FOR TABLE 3.2.A 1.
V.hanever Primary Containment integrity is required by l
Section 3.7, there shall be two operable or tripped trip systems for each function.
2.
If the first column cannot be met for one of the trip systems, that trip system shall be tripped or the appropriate action i
listed below shall be taken.
A.
Initiate an orderly shutdown and have the reactor in Cold shutdown Condition in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
B.
Initiate an orderly load' reduction and have Main Steam Lines isolated within eight hours.
C.
Isolate Reactor Water Cleanup System.
D.
Isolate Shiftdown Cooling.
3.
Instrument set point corresponds to 177.7" above top of active fuel.
4.
Instrument set point corresponds to 129.7" above top of active fuel.
5.
Two required for each steam line.
6.
These signals also start SBGTS and initiate secondary contain-ment isolation.
7.
Only required in Run Mode (interlocked with Mode Switch).
2 E
8.
At a radiation level of 1.5 times the nomal rated power background g
an alarm will be tripped in the control room to alert the control j
room operators to an increase in the main stesa line tunnel radiation level.
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4 4
I APRIL 1974
TA!!!.E 3.?.n INSTPflMEt4T ATION TilAT If81TI ATES Olt CONTPof.S Tile ColtE AND cot 4TAINNENT COOI,1WI SYSTEMS p$
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9
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k Mi ni miin No.
Number of Instru-5 of Operatilo I ns t rirnen t Trip Flinction Trip T,evel Setting ment Channels Pro.
Remarks vided by Design 2
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Channelr; Por IE.!U_EZ!it #~' O cn l
e
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P o.ict o r t.ow-t.ow 2 - 4 11 in. In dica te d is itPCI c RCIC Initiates llPCI C RCIC W.i t er f.evel level Inst. Channels 2
Reactar Low-Low-Low-1-160 in. Indicated 4 Core Spray &
1.
In conjunction with Water Level level (4)
EllR Instrument Low Reactor Pressure Channels initiates Core Spray
.and LPCI 14 ADS Instrument Channels
- 2. In conjunction with T
con firmatory low level fligh Drywell Pressure, 120 second time delay and LPCI' or Core Spray pump interlock initiates Auto P8 owdown (ADS) 3.
Initiates startinq of Diesel Generatters e
PBAPS L1MITIN'; CONDITIOt1S FOh OPERATION SURVEILLANCE REQUIREMENTS 3.7.A.6.c (Cont ' d) 4.7.A.6.c.
(Cont ' d) the affected reactor must
- The CAD system H2 and O2 he taken out of power analyzers shall be tested o peration.
for operability using standard bottled H2 and 02 once per month and shall be calibrated once per 6 months. The atmosphere analyzing system shall be functionally tested once per operating cycle in conjunction with specification 4.7.A.6.a.
Should one of the two H2 or O2 analyzers serving the drywell or suppression pool be found inoperable the remaining analyzer of the same type serving the same compartment shall be tested for operability once per week until the defe~ctive analyzer is made operable.
- d. A 30 psig limit is the maximum containment re pressurization allowable using the CAD system. Venting via the SBG1 system to this stack must be initiated at 30 psig following the initial peak pressure of 49.1 psig.
Amendment No. ZA, 69
-173-
PBkPS LIMIT 3Mti CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 307.A.7 If the specifications of 3.7.A.1 through 3.7.A.5 cannot be met, an orderly shutdown shall be initiated and the reactor shall be in a cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />..
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-17u-Amendment No. #, 69
PBAPS f.IMITING CONDITIONS FOP OPERATION SURVEILLANCE F EOUIREMENTS
- 1. 9. D Qu=j rat ion with Inoverable 4.9.D E f ui pmen t Whenever the reactor is in Run Mode or Startup Mode with the reactor not in a Cold Condition, the availability of electric power shall be as specified in 3. 9. A, except as follows:
1.
Prom and after the date incoming oower is not available from one startup or emergency transformer, continued reactor operation is permissible for seven days.
During this period, the four diesel generators and associated emergency buses must be demonstrated to be operable.
2.
From and after the date that incoming power is not available from both start-up or emergency transformers, continued operation is permissible, provided the four diesel generators and associated emergency buses are operable, all core and containment cooling systems are operable and reactor power level is reduced to 25%
of the design.
-219-Miendment No. 69 t
PDAPS 1,1.1 T! :<; CC:1Di'"IO!!S FOP OPER ATION SURVEILLANCE I<EOUIREMENTS 4.9 B
- 3. '). b (Cunt'd)
- 3. From ami af ter the date that one of the diesel generators or associated emergency bus is made or found to be inoperable for any reasons,
-continued reactor operation is permissible in accordance with Specification 3.5.F if Specification 3. 9. A.1 is satisfied.
4.
From and after the date that one of the diesel generators or associated emergency buses and either the emergency or startup transformer power source are made or found to be inoperable for any reason, continued reactor operati-on is permissible in accordance with Specification 3. 5. F, provided the other off-site source, startup transformer and emergency transformer are available and capable of automatically supplying power to the 4KV emergency buses.
L. from and ofter the date that one of the 125 volt battery systems is made or found to be inoperable for any reason, continued reactor operation is permissible during the succeedine three days within electrical safety considerations, provided repair work is initiated in
- he most expeditious manner
- a return the failed
.::.n t.c n ei. t to an operable state, and Soecification 3.5.F is satisfied.
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0-Amendment No.69
PBAPS 1lM1 TING CONDITIONS FOR OPERATION SURVEILIANCE PEOUIREMEN*S 4.10 COFE ALTERATIONS J.10 Col (E ALTMPATIONS Applicability Apolicability Applies to the fuel handling Applies to the periodic and core reactivity limit-testing of those interlocks and instrumentation used ations.
during refueling and core alterations.
Obiective Obiective To ensure that core reactivity To verify the operability is within the capability of of instrumentation and the control rods and to pre-interlocks used in refueling vent criticality during and core alterations.
refueling.
Soecification Speci fica tion A.
Pefueling Interlocks A.
Refueling Interlocks
- 1. The reactor mode switch 1.
Prior to any core altera-shall be locked in the tions within or over the
" Refuel" position during reactor core, the reactor etre alterations and the switch " Refuel" position refueling interlocks interlocks shall be shall be operable except functionally tested.
as specified in 3.10.A.5 and They shall be tested 3.10. A. 6 below.
at weekly intervals thereafter until no longer required. They shall also be tested following any repair work associated with the interlocks.
t 2.
Tuel shall not be loaded
- 2. Prior to performing control l
into the reactor core un-rod or control rod drive less all control rods are maintenance on control full / inserted.
cells without removing fuel assemblies, it shall be demonstrated that the core can be made subcritical by a margin of 0.25 percent a k at any time during the maintenance with the strongest operable control rod
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Amendment No. 69
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PBAPS I.I M L TI !:G COtJDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS J.10.A Pefueling Interlocks 4.10.A.2 (Cont ' d) fully withdrawn and all other operable rods
- 3. The fuel grapple hoist load fully inserted. Alternatively :
nwitch shall be set at $1000 if the remaining control reds :
lbs.
are fully inserted and have their directional control 4
If the frame-mounted valves electrically dis-
'a uxiliar y ' hoist, the monorail-armed, it is sufficient mounted auxiliary hoist, to demonstrate that or the service platform the core is subcritical hoist is to be used with a margin of at for handling fuel with least 0.25% A k at any the head off the reactor time during the main-vessel, the load limit tenance. A control switch on the boist to rod on which maintenance be used shall be set at is being performed
_ 400 lbs.
shall be considered inoperable.
- 5. A maximum of two n'onadjacent control rods may be withdrawn from the core for the purpose of perforncing control rod and/or control rod drive 7
maintenance, provided the
~ '
following conditions are satisfied:
1 a
- a. The reactor mode switch j
shall be locked in the q
" refuel" position.
The j
refueling interlock which 1
prevents more than one
]
control rcd from being
.I withdrawn may be bypassed for one of the control rods on which maintenance is being performed.
All other refueling interlocks shall be operable.
c.
A sufficient number of control rods shall be operable so that the core i
can be made suberitical with the strongest operasle control rod fully withdrawn and all other operable controls rods fully inserted, or all
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Amendment No. 69
-226-i
PBAPS LIMIT 1HG col 1DITIONS FOR OPERATION SURVEILLANCE REOUIREMENTS 3.14.A (Cont'd) c.
Turbine ndilding
- c. Hose station valve
- d. Circulating Water Pump Structure operability and blockage check - once every 3 years.
- 6. When a hose station serving
- d. Hose hydrostatic test at an area which contains a pressure at least equipment which is required 50 psig greater than to be operable becomes the maximum pressure ingperable/ establish a available at that hose continuous fire watch station but not less equipped with portable than 150 psig, or replace fire suppression equip-with an appropriately ment within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> tested hose-every 3 years and provide equivalent protection to the area
- 6. None served by the inoperable station from the operable hose station within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
7.
Except as specified in
- 7. The SGTS fire suppression 3.14.A.8 below, the spray system testing fire suppression shall be performed as spray system serving a follows:
Standby Gas Treatment System charcoal filter
- a. Simulated automatic train shall be operable actuation test once when a train -s required every 18 months to be operabl;.
8.
If the requirements of 3.14.A.7
- b. Inspection of no::les cannot be met, and spray header-once every 18 months a.
establish a fire water patrol to inspect the
- c. Header and nor:le air area with inoperable flow test - once every fire suppression 3 years equipment at least once per shift.
b.
restore the system to an operable status within 14 days, or in lieu of any other report required by specification 6.9.2 submit a Special Report to the Commission pursuant to Specification 6.9.3 within 31 days outlining the cause of t he malf unction and the plans for restoring the system to an spera ble status. The SGTS may 1.o considered operable for the
~
purposes or specification 3.7.3.
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Amendment No. 39, 53, 69
PEAPS
- 6. 0 ADMINISTRATIVE CONTROLS 6.1 Responcibility 6.1.1 The sta' tion Superintendent shall be responsible f or overall facility operation.
In the absence of the Station Superintendent, the Assistant Superintendent or the Engineer-Technical (or any other person that the Station superintendent may designate in writing) shall, in that 8
order, assume the Superintendent s responsibility for overall facility operat. ion.
6.2 Or ganization Offsite 6.2.i The offsite organization for facility management and technical support shall be as shown on Figure 6.2-1.
Facility Staff 6.2.2 The f acility organization shall be as shown on Figure 6.2-2 and:
a.
Each on duty shift shall be composed of at least the minimum shif t crew composition shown in Figure 6. 2-2, except that the Thift crew composition may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of on duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements.
b.
At least one licensed operator shall be in the control room and assigned to each reactor that contains f uel.
c.
At least two licensed operators, excluding the operator on the second unit, shall be present in the control room during reactor start-up, scheduled reactor shutdown and during recovery from reactor trips.
d.
An individual qualified in radiation protection procedures shall be on site when fuel is in the reactor.
e.
All CORE ALTERATIONS shall be directly supervised by either a licensed Senior Reactor operator or Senior Peactor Operator Limited to Fuel Handling who has no other concurrent responsibility during this operation.
l f.
A Fire Brigade of at least 5 members shall be maintained i
onsite at all times.
The Fire Brigade shall not include l
the minimum shift crew necessary for safe shutdown cf l
the unit (s) (3 members) or any personnel required fcr other essential functicns during a fire' emergency.
-243-Amendment No. 39, 69
+
PBAPS 6.5.2 Operation and safety Review commitee Function shall function to 6.5.2.1 The Operation and Safety Review Committee provide independent review and audit of designated activities in the area of:
' nuclear power plant operations a.
b.
nuclear engineering chemistry and radiochemistry c.
d.
metallurgy e.
instrumentation and control f.
radiological safety mechanical and electrical engineering g.
h.
quality assurance practices The members of the OSR Committee will be competent in the area of quality assurance practice and cognizant of the Quality Assurance requirements of 10 CFR 50, Appendix B.
Additionally, they will be cognizant of the corporate Quality Assurance Program and will have the corporate Quality Assurance Organization available to them.
Oroanization 6.5.2.2 The chairman, Members and alternate Members or the OSE l
Com.nittee shall be appointed in writing by the Vice President, Electric Production, and shall have an academic degree in an engineering or physical science field; and in addition, shall have a minimum of five years technical experience, of which a minimum of three years shall be in ene or more areas given in 6.5.2.1.
-2ug-
~ Amendment No. 70, 37, #7, 63, 69
[ga rse
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UNITED STATES NUCLEAR REGULATORY COMMISSION y
../ 3 g o p "o-C WASHINGTON, D. C. 20555
- 1 g
2., n j PHILADELPHIA ELECTRIC COMPANY PUBLIC SERVICE ELECTRIC AND GAS COMPANY
~
DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-287 PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendmenc No. 68 License No. DPR-56 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Philadelphia Electric Company, et al. (the licensee) dated April 15, 1980, complies with the stand-ards 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 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 Comission's regulations and all applicable requirements have been satisfied.
i
. 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-56 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 68, are hereby incorporated in the license. PEC0 shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION k
Wf Robert W. Reid, Chief Operating Reactors Branch #4 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: May 16,1980 e
+
+
ATTACHMENT TO LICENSE AMENDMENT NO. 68 FACILITY OPERATING LICENSE NO. DPR-56 DOCKET NO. 50-278 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are' icentified by amendment number and contain vertical lines indicating the area of change.
Remove Pages Insert Pages 4
63 63 64 64 173 173 174 174 219 219 220 220 i
225 225 226 226 I
240f 240f 243 243 249 249 Page 63 is unchanged and is included for your convenience only.
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PBAPS SOTES FOR TABLE 3.2.A 3.
Vihanever Primary Containment integrity is required by 1.,ection 3. 7, there shall be two operable or tripped trip systems for each function.
2.
If the first column cannot be met for one of the trip systems, that trip system shall be tripped or the appropriate action listed below shall be taken.
A.
Initiate an orderly shutdown and have the reactor in Cold Shutdown Condition in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
B.
Initiate.an orderly load reduction and have Main Steam Lines isolated within eight hours.
C.
Isolate Reactor Water Cleanup System.
D.
Isolate Shtitdown Cooling.
3.
Instrument set point corresponds to 177.7" above top of active fuel.
4.
Instrument set point corresponds to 129.7" above top of active fuel.
5.
Two required for eact. steam line.
6.
These signals also start SBGTS and initiate secondary contain-ment isolation.
U 7.
Only required in Run Mode (interlocked with Mode Switch).
E 8.
At a radiation level of 1.5 tines the normal rated power background 5
an alarm will be tripped in the control room to alert the control 6
room operators to an increase in the main steam line tunnel radiation level.
M t-
. APRIL 1974
TABLE 3.2.0 I t3 r ~ IIMF.HT ATION TilAT lt3ITI ATES OR CONTROt.S Tile Colt E AND CONTAINMENT CODI,1NG SY ITEMS 1
~~~
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Minimon r;o.
o Nitmber of Instru-nt Opera b le
'~ Instrument Trip Function Trip T,evel Setting ment Channels Pro, R ema rk s vided by Design Channels Pe r TE u_s_y;itom (1 i
?
React o r t.ow-t.ow 2-411 in. Indicated 4 IIPCT C RCIC Initiates HPCI C PCIC l Water f.evel level Inst. Channels 2
Reactar Law-Low-Low-1-160 in. Indicat ed 4 Core Spray G 1.
In conjunction with Water IEvel Level (4)
RilR Instrumen t Low Reactor Pressure Channels initiates Core Spray
, and LPCI 4 ADS Instrument Channels 2.
In conjunction with O
con firmatory low I
1evel liigh Drywell Pressure, 120 second time delay and LPCI or Core Spray pump interlock initiates Auto Blowdown (ADS) 3.
Initiates startinq of Diesel Generators
PBAPS L1 MI TI N8; cot 4DITIOt1S FOR OPERATION SURVEILLANCE REQUIREX7NTS 3.7.A.6.c (Cunt'd) 4.7.A.6.c.
(Cont ' d) the affected reactor must
- The CAD system Hi and 02 he taken out of power analyzers shall be tested o peration.
for operability using standard bottled H2 and 02 once per month and shall be calibrated once per 6 months. The atmosphere
~
analyzing system shall be functionally tested once per operating cycle in conjunction with specification 4.7.A.6.a.
Should one of the two H2 or 02 analyzers serving the drywell or suppression pool be found inoperable the remaining analyzer of the same type serving the same compartment shall be tested for operability once per week until the defective
)
analyzer is made operable.
1
- d. A 30 psig limit is the maximum containment re pres surization allowable using the CAD system. Venting via the SBGT system to this stack must be initiated at 30 psig following the initial peak pressure of 49.1 psig.
-173-Amendment No. 73, 68
I PDhPS j
.j L ir41 T I:!t; CUf!DI TIONS FOK OPER ATION SURVEILLANCE REQUIRE **ENTS
- I 3.7.A.7 If the specifications of
,l 3.7.A.1 through 3. 7. A. 5
]
cannot be me, an orderly shutdown shall t>e initiated and the reactor shall be in a cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />..
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-17u-Amendment No. 23, 68
PBAPS l.I MI TI 3f COtmITIONS FOR OPEP ATION SURVEILLANCE FEOUIREMENTS 1.9.D Oi=' ration with Inoperable 4.9.D E!u i tnwn t Whenever t.ie reactor is in Run Mode or Startup Mode with the reactor not in a cold condition, the availability of electric power shall be as specified in 3. 9. A, except as follows:
~
1.
From and after the date incoming power is not available from one startup or emergency transformer, continued reactor operation is permissible for seven Jays.
During this period, the f our diesel generators and associated emergency buses must be demonstrated to be operable.
- 2. From and after the date that incoming power is not available from both start-up or emergency transformers, continued operation is permissible, provided the four diesel generators and associated emergency buses are operable, all core and containment cooling systems are operable and reactor power level is reduced to 25%
of the design.
l
-219-M:endment No. 68 5
PDAPS MNITi th; CONDITIO?!S FOP OPERATION SURVEILLANCE REOUIREMENTS 4.9.B
- 3. '). B (cout'd) 3.
From anel after the date that one of the diesel generators or associated emergency bus is made or found to be inoperable for any reasons, continued reactor operation is permissibic in accordance with Specification 3.5.F if Specification 3.9.A.1 is satisfied.
4.
From and after the date that one of the diesel generators or associated emergency buses and either the emergency or startup transformer power source are made or found to be inoperable for any reason, continued reactor operation is permissible in accordance with Specification 3.5. F, provided the other off-site source, startup transf ormer and emergency transformer are available and capable of automatically supplying power to the 4KV emerge.ncy buses.
5.
From and after the date that one of the 125 volt battery systems is made or found to be inoperable for any reason, continued reactor operation is permissible during the succeeding three days within electrical safety considerations.
-rovidcd repair work is >litiated in the most expeditious manner o return t.ne failed
.:c.n t.c n er. t to an operable state, and Specification 2.5.7 is satisfied.
~
Amendment No. 68
PBAP3 1.lMITING CONDITIONS FOR OPERATION SURVEILLANCE PEQUIREMENTS J.10 col (E ALTMPATIONS 4.10 COF.E ALTERATIONS Applicability Applicability Applies to the fuel handling Applies to the periodic and core reactivity limit-testing of those interlocks ations.
and instrumentation used during refueling and core alterations.
Obiective Obie ctive To ensure that core reactivity To verify the operability is within the capability,of of instrumentation and the control rods and to pre-interlocks used in refueling vent criticality during and core alterations.
refueling.
S peci fication Soecification A.
Pefueling Interlocks A. Refueling Interlocks 1.
The reactor mode switch 1.
Prior to any core altera-shall be locked in the tions within or over the
" Refuel" position during reactor core', the reactor cure alterations and the switch "Refuela position refueling interlocks interlocks shall be shall be operable except f unctionally tested.
as specified in 3.10.A.5 and They shall be tested 3.10.A.6 below.
at weekly intervals thereafter until no longer required. They shall also be tested following any repair work associated with the interlocks.
2.
Fuel shall not be loaded
- 2. Prior to pe1 forming control into the reactor core un-rod or control rod drive less all control rods are maintenance on control fully inserted.
cells without removing fuel assemblies, it shall be demonstrated that the core can be made subcri-ical by a margin of 0.25 percent o k at any time during the maintenance with the strongest operable control rod
'25-Amendment No. 68
PBAPS l.1MLTIHG CONDITIONS FOR OPERATION SURVEILLANCE REOUIREMENTS J.10.A Fefueling Interlocks 4.10.A.2 (Cont'd) fully withdrawn and all i
other operable rods
- 3. The fuel grapple hoirt load fully inserted. Alternatively s nwitch shall be set at f,1000 if the remaining control rods l lbs.
are fully inserted and have 9
their directional control 4
If the frame-mounted valves electrically dis-9
' auxiliary' hoist, the monorail-armed, it is sufficient mounted auxiliary hoist, to demonstrate that
)
or the service platform the core.'; subcritical y
hoist is to be used with a margin of at 1
for handling fuel with least 0.25% A k at any j
the head off the reactor time during the main-c' vessel, the load limit tenance. A control rod on which maintenance switch on the hoist to be used shall be set at is being performed
$ 400 lbs.
shall be considered inoperable.
e
- 5. A maximum of two no'nadjacent control rods may be withdrawn g
from the core for the purpose i
of performing control rod 3
and/or control rod drive maintenance, provided the i
following conditions are' satisfied:
- a. The reactor mode switch shall be locked in the
" refuel" position.
The refueling interlock which prevents more than one control rod from being withdrawn may be bypassed for one of the control rods on which maintenance is being performed.
All other
~
refueling interlocks shall be operable.
b.
A sufficient number of control rods shall be operable so that the core can be made subcritical with the strongest operable control rod fully withdrawn and all other operable l
l controls rods fully inserted, or all Amendment No. 68
-226-
PBAPS l
LIMIT 1HG COllDITIONS FOR OPERATION SURVEILLANCE REOUIREMENTS 3.14.A (Cont ' d)
- c. Turbine ndilding
- c. Hose station valve
- d. Circulating Water Pump Structure operability and blockage check - once every 3 years.
- 6. When a hose station serving
- d. Hose hydrostatic test at an area which contains a pressure at least equipment which is required 50 psig greater than to be operable becomes the maximum pressure available at that hose ingperable/ establish a continuous fire watch station but not less equipped with portable than 150 psig, or replace fire suppression equip-with an appropriately ment within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> tested hose-every 3 years and provide equivalent protection to the area
- 6. None served by the inoperable i
station from the operable hose station within 6 nours.
7.
Except as specified in 7.
The SGTS fire suppression 3.14.A.8 below, the spray system testing fire suppression shall be performed as spray system serving a follows:
Standby Gas Treatment System charcoal filter
- a. Simulated automatic train shall be operable actuation test once when a train is required every 18 months to be operable.
8.
If the requirements of 3.14.A.7
- b. Inspection of noz les cannot be met, and spray header-
- a. establish a fire water patrol to inspect the
- c. Header and nozzle air area with inoperable flow test - once every fire suppression 3 years equipment at least once per shift.
b.
restore the system to an operable utatus within 14 days, or in lieu of any other report required by specification 6.9.2 submit a Special Report to the Commission pursuant to specification 6.9.3 within 31 days outlining the cause of t he malf unction and the plans for restoring the system to an spor a ble status. The SGTS may be considered operable for t.".e
~
purposes or Specification 3. 7.3.
--2-af,-
Amendmer.t No. M, 67, 68 1
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PEAPS 6.0 ADMINISTRATIVE CONTROLS 6.1 Be sponcibility 1
6.1.1 The Station Superintendent shall be responsible f or overall facility operation.
In the absence of the Station Superintendent, the Assistant Superintendent or the Engineer-Technical (or any other person that the Station superintendent may designate in writing) shall, in that order, assume the Superintendent s responsibility for overall
.l 8
facility operation.
6.2 Organization Offsite 6.2.i The offsite organization for facility r.anagement and technical support shall be as shown on Figure 6.2-1.
Facility Staff 6.2.2 The f acility organization shall be as shown on Figure 6.2-2 and:
Each on duty shift shall be composed of at least the a.
minimum shift crew composition shown in Figure 6. 2-2, except that the'thift crew composition may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of on duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements.
b.
At least one licensed operator shall be in the control room and assigned to each reactor that contains f uel.
c.
At least two licensed operators, excluding the operator on a second unit, shall be present in the control room during reactor start-up, scheduled reactor shutdown and during recovery from reactor trips.
d.
An individual qualified in radiation protection procedures shall be on sito when fuel is in the reactor.
All CORE ALTERATIONS shall be directly supervised by e.
either a licensed Senior Reactor.Cperator or Senior Peactor Operator Limited to Fuel Handling who has no other concurrent responsibility during this operation.
f.
A Fire Brigade of at least 5 members shall be maintained onsite at all times.
The Fire Brigade shall not include the minimum shift crew necessary for safe shutdown of the unit (s) (3 members) or any personnel required fcr other essential functicns during a fire emerger.cy.
-243-Amendment No. D,6T3 '
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PBAPS 6.5.2 Operation and safety Review Commitee 1
Punction 6.5.2.1 The Operation and Safety Review Committee shall function to provide independent review and audit of designated activities in the area of:
' nuclear power plant operations a.
b.
nuclear engineering c.
chemistry and radiocherdstry l
d.
metallurgy e.
instrumentation and control f.
radiological safety g.
mechanical and electrical engineering t
h.
quality assurance practices The members of the OSR Comnittee will be competent in the area of quality assurance pract.u e and cognizant of the Quality Assurance requirements of 10 CFR 50, Appendix B.
Additionally, they will be cognizant of the corporate Quality Assurance Program and will have the corporate Quality Assurance Organization available to them.
Oroanization 6.5.2.2 The Chairman, Members and alternate Members or the OsR l
Committee shall be appointed in writing by the Vice President, Electric Production, and shall have an academic degree in an engineering or physical science field: and in addition, shall have a minimum of five years technical experience, of which a minimum of three years shall be in one or more areas given in 6. 5. 2.1.
/
-249-Amendment No. J0, 37, M, 57, 68 9'
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