ML20126K985
| ML20126K985 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 12/31/1992 |
| From: | CAROLINA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20126K976 | List: |
| References | |
| NUDOCS 9301070311 | |
| Download: ML20126K985 (17) | |
Text
.
ENCLOSURE 4 BRUNSWICK STEAM ELECTRIC PLANT. UNITS 1 AND 2 NRC DOCKET NOS. 50 325 & 50 324
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OPERATING LICENSE NOS. DPR-71 & DPR 62 REQUEST FOR LICENSE AMENDMENT CORE ALTERATIONS PAGE CHANGE INSTRUCTIONS UNIT 1 Removed Pan 2 Inserted Palla j
12 1-2 3/405 3/4 9 5
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B 3/4 9 1 0 3/4 9 1 UNIT 2 Romgygi3J12
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t ENCLOSURE 5.
DRUNSWICK STEAM ELECTRIC FLANT, UNITS 1 AND 2 -
NRC DOCKET NOS. 50 325 & 50 324 OPERATING LICENSE NOS, DPR 71 &'DPR-02 REQUEST FOR LICENSE AMENDMENT CORE ALTERATIONS TECHNICAL SPECIFICATION PAGES - UNIT 1 f
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- In addition, control rod movement with other than the normal control rod drive is not considered a CORE ALTERATION provided there are no fuel assemblies in the associated core cell. Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe position.
DEFINITIONS CHANNEL FUNCTIONAL TEST (Continued) b.
Bistable channels - the injection of a simulated signal into the channel sensor to verify OPERABILITY including alarm and/or trip functions.
Componenh, or other component.s CORE ALTER ATION affee Hn3 reacgVjty w.g8 i
n CORE ALTERATION shall be t he edd+wwenmoval crelos444w movement of cmy t uel, source s, +newednew*::nt :, ee reac t i vi ty cont rol/ i* the reactor ecceV6S5e;l with the vessel head removed and fuel in the vessel..S**pene:cn ef COPS 41rTERAHON&-sha! ! net-pree4*de-cemp!et en ef t he rc; cat-of
- ccepenent te4
-6als een**evet x 66 mm dich.
r Movement of sarce range morufor@calperu.c ranje men;+cr.9 nhrr,edMe ru i
gndonessel rerl cemon+)is nef consid,erspecialmovealde dekac4e rnaders, +roersin in-coru proba monHors erect a CofW ALTERAT/d4 EORE OPERATING LIMITS REPORT The CORE OPERATING LIMITS REPORT is the unit-specific document that provides core operating limits for the current reload cycle. These cycle-specific core operating limito shall be determined f or each reload cycle in accordance with.
Specifications 6.9.3.1, 6.9.3.2, 6.9.3.3, and 6.9.3.4.
Plant operation within these core operating limits is addressed in individual specifications.
CRITICAL POWER RATIO The CRITICAL POWER RATIO (CPR) shall be the ratio of that power in an assembly which is calculated, by application of an NRC approved CPR. correlation, to cause some point in the assembly to experience boiling transition, divided by the actual assembly operating power.
DOSE EQUIVALENT I-131 DOSE EQUIVALENT I-131 shall be concentration of I-131,-LCi/ gram, which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131. I-13 2, I-13 3, I-134, and I-135 actually present. The following is defined equivalent to I uCi of 1-131 as determined from Table III of.
TID-14844, " Calculation of Distance Factors for Power and Test Reactor Sites":
I-132, 28 uCi; I-133, 3.7 uCi; I-134, 59 uci; I-135, 12_uci.
E -AVERACE DISINTECRATION ENERCY E shall be the average, weighted in proportion to the concentrat ion of each radionuclide in the reactor coolant at the time of sampling, of the sum of the average beta and gamma energies per disintegratior, (in MeV) tor isotopes with half lives greater than 15 minutes making up at least 95% of the total non-iodine activity in the coolant.
E BRUNSWICK - UNIT l-2 Amendment No. 147 4
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REFUELING OPERATIONS 3/4.9.3 CONTROL ROD POSITION LIMITING CONDITION FOR OPERATION 3.9.3 All control rods shall be fully inserted *.
CONDITION 5, during CORE--ALTERAT-ION 6% lcading of [uef APPLICABILITY:
CS o
Core #U ACTION:
With all control rods not fully inserted, immediately -deensegiaa-tha-control!'
-rod-seram-solenold--valve %,-
The provisions of Specifi ation 3.0.3 are not applicable.
susgeha toad;ng of fuel assemblies ink +he core.
('.
SURVEILLANCE REQUIREMENTS 4.9.3 Verify all control rods to be fully inserted within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. prior-to the start of and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during 40RFr-AirTERAT-IONS3 loading c>f fuel assembhas ink the core
- Except control rods removed ~per Specification 3.9.10.1 or 3.9.10.2.
- See Special Test Exception 3.10.3.
~
i RETYPED TECH. SPECS.
BRUNSWICK - UNIT 1 3/4 9-5 Uedated Thru. Amend. 53
4 3/4.9 REFUELING OPERATIONS BASES 3/4.9.1 REACT _OR uoDE SWITCH Locking the reactor mode switch in the refuel position ensures that the restrictions on rod withdrawal and refueling platform movement during the refueling operations are properly activated. These conditions reinforce the refueling procedures and reduce the probability of inadvertent criticality, damage to reactor internals, fuel assemblies and exposure of personnel to excessive radioactivity.
3/4.9.2 TNSTRUMENTATION The OPERA 1ILITY of the source range monitors ensures that redundant monitoring capability is available to detect changes in the reactivity condition of the core.
During a SPIRAL UNLOAD, the count rate of the SRM will decrease below 3 cps before all of the fuel is unloaded.
The count rate of 3 cps is not necessary since there will be no reactivity additions during the spiral unload. The SRMs will be required to be OPERABLE prior to the SPIRAL UNLOAD, and each SRM will be verified operational by r.aising the count rate to 3 cps prior to the SPIRAL RELOAD by inserting up to four fuel assemblics around each' SRM.
This will ensure that the SRMs can be relied upon to monitor core reactivity during the reload.
Oadin Of 4e( 365embbeS 3/4.9.3 CONTROL ROD POSITION I t1 YO d le CGTrEL The requirement that all control rods be u n s e r t ed d u r i n g GOR E ALT-ERATEGNS-ensures that fuel will not be loaded into a cell without a control rod and prevents two positive reactivity changes from occurring simultaneously.
3/4.9.4 DECAY TIME The minimum requirement for reactor suberiticality prior to fuel movement ensures that sufficient time has elapsed to allow the radioactive decay of the short lived fission products. This decay time is consistent with the assumptions used in the accident analyses.
3/4.9.5 COMMUNICATIONS The requirement for communications capability ensures that refueling station persannel can be promptly informed of significant changes in the facility status or core reactivity condition during movement of fuel within the reactor pressure vessel.
BRUNSWICK - UNIT 1 B 3/4 9-1 Amendment No. 89
ENCLOSURE 6 BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 NRC DOCKET NOS. 50-325 & 50 324 OPERATING LICENSE NOS. DPR-71 & DPR-62 REQUEST FOR LICENSE AMENDMENT CORE ALTERATIONS TECHNICAL SPECIFICATION PAGES - UNIT 2
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DEFINITIONS CHANNEL FUNCTIONAL TEST (Continued) b.
Bistable channels - the injection of a simulated signal into the channel sensor to verify OPERABILITY including alarm and/or trip functions.
Or Ch8FCoryon6Mf5 CORE ALTERATION COMf)onen 7 9
affech reachi+y wdhIn 9
a movement of W CORE ALTERATION shall be the additiony w smovskr-retocat' fuel, sources, iaeore-instausents, ee reactivity control / 4 the reactor 40se-VBMd with the vessel head removed and fuel in the vessel. Suspensie of CORE-
. ALTERATIONS-shall - as gecivde-completion-of-the-movement-of-e-oomponent-ce -saf a, e.nnservetive-iac.ticr.
- ^%
CORE OPERATING LIMITS REPORT The CORE OPERATING LIMITS REPORT is the unit-specific document that provides core operating limits for the current reload cycle. These cycle-specific core operating limits shall be determined for each reload cycle in accordance with Specifications 6.9.3.1, 6.9.3.2, 6.9.3.3, and 6.9.3.4.
Plant operation within these core operating limits is addressed in individual specifications.
CRITICAL POWER RATIO The CRITICAL POWER RATIO (CPR) shall be the ratio of that power in an assembly which is calculated, by application of an NRC approved CPR correlation, to cause some point in the assembly to experience boiling transition, divided by the actual assembly operating power.
DOSE EQUIVALENT I-131 DOSE EQUIVALENT I-131 shall be cone.entration of I-131, uCi/ gram, which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134, and I-135 actually present. The following is defined equivalent to 1 uCi of I-131 as determined from Table III of TID-14844, " Calculation of Distance Factors for Power and Test. Reactor Sites":
I-132, 28 uCi; I-133,.3.7 pCi; I-134, 59 ucil I-135, 12 uCi.
E -AVERACE DISINTECRATION ENERCY E shall be the average, weighted in proportion to the concentration of'each radionuclide in the reactor coolant at the time of sampling, of the sum of the average beta and gamma energies per disintegration (in MeV) for isotopes with halt lives greater than 15 minutes making up at least 95% of the total non-iodine activity in the coolant.
-- Movement ofsource r$e unarsdocd Per r9e menRors3 ink menitors, traver. sin in-core p robe. rnonibrs, or speaaInade deMrs Oncludin underrenelrephcemanh is ne+ensdereda CORE ALTERhTIM In additi n, control rod movement with other than the normal control rod drive is not considered a CORE ALTERATION provided there are no fuel assemblies in the as oci te co e cell.
Suspension of C0g ALTERATIONS shall noggego,168 comnletion of movement of a component to a safe position.
d REFUELING OPERATIONS 3/4.9.3 ' CONTROL ROD POSITION LIMITING CONDITION FOR OPERATION 3.9.3 All control rods shall be fully inserted *.
APPLICABILITY: _ CONDITION 5, during GOR &-ALTERATIONS **i fCacd'in O
C-G ef n COFC M8 ACTION:
With all control rods not fully inserted, immediatelyjdoenergias-the w ntrol---
rod-ec ram-solenoid-valvek The provisions of Specif fi ation 3.0.3 are not applicable.
USSeinb BS5hSO N C0Y8 S4Sfend l0Bchn} O 4e SURVEILLkNCE REQUIREMENTS 4.9.3 Verify all control rods to be fully inserted within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> prior to the start of and at of fue.l aSSernblies in}o Oc core-.least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during 4
- Except control code removed per Specification 3.9.10.1 or 3.9.1.2.
"See Spe:Lal Test Exception 3.10.3.
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RETYPED TECH. SPECS.
U dated Thru. Amend.-78 BRUNSWICK - UNIT 2 3/4 9-5 P
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, A. : c 3/4.9 REFUELING OPERATIONS BASES 3/4.9.1 REACTOR MODE SWITCH Locking the reactor mode switch in-the refuel position ensures'that the restrictions on rod withdrawal and refueling platform covement during the refueling operations are properly activated.. These conditions reinforce the refueling procedures and reduce the probability of inadvertent criticality, damage to reactor internals, fuel assemblies and exposcte of personnel to excessive radioactivity.
3/4.9.2 INSTRUMENTATION The OPERABILITY of the source range monitors ensures that redundant monitoring capability is available to detect changes in the reactivity condition of the core.
During a SPIRAL UNLOAD, the count rate of the SRM will decrease b'elow 3 cps before all of the fuel:is unloaded. The count rate of 3 cps is not necessary since there will be no reactivity additions during the spiral unload. The SRMs will be required to be OPERABLE prior to the SPIRAL UNLOAD,--
and each SRM will be verified operational by raising the count rate to 3 cps prior to the SPIRAL RELOAD by inserting up to four fuel assemblies around each SRM.
This will ensure that the SRMs can be relied upon to monitor core.
reactivity d,uring the reload.
OB ind O U6 $ 658.YT)3 l6.3 3/4.9.3 CONTROL ROD POSITION
. Tido h.e. Core g l
The requirement that all control rods be inserted duringTCORE-ALTERATION &
ensures that fuel will not be loaded into a cell without-a control-rod and prevents two positive reactivity changes from occurring simultaneously.-
3/4.9.4 DECAY TIME t
The minimum requirement for reactor suberiticality prior to fuel movement ensures that sufficient time.has elapsed'to allow the radioactive decay of the short lived fission products. This decay time is consistent with the assumptions used in the accident-analyses.
3/4.9.5 COMMUNICATIONS The requirement for communications capability ensures that refueling station personnel can be.promptly informed of'significant changes in the.
facility status or core reactivity condition during movement of fuel within the reactor pressure vessel.
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l l-BRUNSWICK - UNIT 2 B 3/4 9-1 Amendment No. ll4 i
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e ENCLOSURE 7-BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 NRC DOCKET NOS. 50 325 & 50 324 OPERATING LICENSE NOS. DPR 71 & DPR 62 REOUEST FOR LICENSE AMENDMENT-CORE ALTERATIONS TYPED TECHNICAL SPECIFICATION PAGES UNIT 1 n
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- DEFINITIONS' 2
- CHANNEL FUNCTIONAL TESI -(Continued) b.
B1 stable channels the injection of a simulated signal'into the channel sensor to verify.0PERABILITY including alarm and/or trip-functions.
CORE ALTERATION CORE ALTERATION shall be the movement of any fuel, sources, reactivity control-components, or other components affecting reactivity within the reactor vessel with the vessel head removed and fuel in the vessel.
Movement of source range monitors, local power range monitors, intermediate range monitors, traversing in-core probes, or special moveable detectors (including undervessel replacement) is not considered a CORE ALTERATION.
In addition, control rod movement with other than the normal control rod drive is not considered a CORE ALTERATION provided there are no fuel assemblies in the associated core cell.
Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe position.
CORE OPERATING LIMITS REPORT The CORE OPERATING LIMITS REPORT is the unit-specific document that:provides core operating limits for the current reload cycle.
These cycle specific core operating limits shall be deta 'ined for each reload cycle in accordance with Specifications 6.9.3.1, 6.9.3.2, 6.9.3.3, and 6.9,3,4.
Plant operationLwithin these core operating limits is addressed in individual specifications.
CRITICAL POWER RATIO The CRITICAL POWER-RATIO (CPR) shall be the ratio of_that power in-an-_ assembly which is calculated, by application of an NRC approved CPR correlation, to cause some point in the assembly-to experience boiling transition, divided by the actual assembly operating power.
DOSE EOUIVALENT I-131 DOSE EQUIVALENT I-131 shall be concentration of I-131,-)Ci/ gram, which alone would produce the same thyroid dose as the quantity and isotopic mixture of-I-131, I 132, I-133, I 134, and I-135 actually present.
The following is
' defined equivalent to 1 )Ci of I-131 as determined from Table III of TID 14844,." Calculation of Distance Factors for Power and; Test' Reactor Sites":
1-132, 28-)Ci; I-133, 3.7 )Ci; I-134, 59 )Ci;.I-135 12 )Ci, E -AVERACE DISINTEGRATION ENERGY E shall be the average, weighted in: proportion to the-concentration'of each?
radionuclide in the reactor coolant at the time of sampling, of the sum of the average beta and gamma energies per disintegration (in MeV) for isotopes with half lives greater than 15 minutes making up at least 95% of the total-non-iodine activity in the-coolant.
BRUNSWICK UNIT 1 1-2.
Amendment No.
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.i REFUELING OPERATIONS 3 /4 '. 9. 3 CONTROL, ROD POSITION.
-LIMITING CONDITION FOR OPERATION 3.9.3E All control rods shall be fully inserted *.
ATPl.ICABILITY:
CONDITION 5, during loading of fuel assemblies into the core **.
ACTION:
With all control rods not fully inserted, immediately suspend loading of fuel assemblies into the core.
The provisions of Specification 3.0.3 are not.
applicable.
1 SURVEILLANCE REQUIREtjfliNTS 4.9,3 Verify all control rods t o be fully inserted within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> prior. to the start of and at least once par 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during loading of fuel ~ assemblies into the core.
- Except control rods removed per Specification 3.9.10.l'or 3.9.1,2.
- See Special Test Exception 3.10.3.
i
. BRUNSWICK - UNIT 1 3/4 9-5 RETYPED TECH. SPECS.
UPDATED THRU.-AMEND. 5 e
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3/4.9' REFUELING OPERATIONS
-BASES 3/4.9.1 REACTOR' MODE SWITCH-Locking the reactor modo switchEin the. refuel position ensures that the-restrictions on rod withdrawal _and refueling platform movement during the refueling operations are properly activated.
These conditions reinforceLthe-refueling procedures and reduce the probability of inadvertent criticality, damage to reactor internals, fuel assemblies and exposure of personnel to s.xcessive radioactivity.
3/4.9.2 INSTRUMENTATION The OPERABILITY of the source range monitors ensures that redundant monitoring capability is.available to detect changes in the reactivity condition of the core.
During a SPIRAL' UNLOAD, the count rate of the SRM will decrease below 3 cps before all of the fuel is unloaded.
The count rate of 3 cps is not necessary since. there will be no reactivity additions during the spiral unload.
The SRMs will be required.to be OPERABLE prior to the SPIRAL UNLOAD, and each SRM-will be verified operational by raising the count rate to 3 cps prior to L he~ t SPIRAL RELOAD by inserting up to four _ fuel assemblies around each-SRM.
This will ensure that the SRMs can be relied upon to monitor core reactivity during the reload,
>3/4.9.3 CONTROL ROD POSITION-The requirement that all control rods be inserted.during loading of fuel assemblies into the core ensures that fuel will not be loaded into a cell without a control rod and prevents two positive reactivity changes from occurring simultaneously.
' 3 /4. 9. 4 - DECAY TIME
.The minimum requirement for reactor suberiticality prior-to_ fuel movement ensures that sufficient time has_ elapsed to allow the radioactive-decay-of the short lived fission products.
This decay. time is consistent with the assumptiens used in the. accident analyses.
3/4.9.5 -COMMUNICATIONS The requirement for communications capability ensures that refueling station personnel can be-promptly informed of significant' changes in the facility status._or. core reactivity condition.during movement of fuel-within the react'orl pressure vessel.
' BRUNSWICK - UNIT B 3/4 9-1 Amendment No.
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.,e ENCLOSURE 8 DRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 NRC DOCKET NOS. 50 325 & 50 324 OPERATING LICENSE NOS. DPR 71 & DPR 02 REOUEST FOR LICENSE AMENDMENT CORE ALTERATIONS 1
TYPED TECHNICAL SPECIFICATION PAGES UNIT 2 1
e D.[FINIT1oSS r3 NNEL FTNCTIONAL TEST (Continued) b.
Bistable channels - the injection of a simulated signal into the channel sensor to verify OPEPABILITY including alarm and/or trip functions.
cnRE ALT [ PAT 10N CORE ALTERA"IGN shall be the moveu.ent of any fuel, sources, reactivity control components, or other components affecting reactivity within the reactor vessel with the vessel head removed and fuel in the vessel.
Movement of source range monitors, local power range monitors, intermediate range monitors, traversing in-core probes, or special moveable detectors (including undervensel replacement) is not considered a CORE ALTERATION.
In addition, control rod movement with other than the normal control rod drive is not considered a CORE ALTERATION provided there are no fuel assemblies in the associated core cell.
Suspension of CORE ALTEP.ATIONS shall not preclude completion of movement of a component to a safe position.
c0RE OPERATING LIMITS REPORT The CORE OPERATING LIMITS REPORT is the unit specific document that provides core operating limits for the current reload cycle.
These cycle specific core operating limits shall be determined for each reload cycle in accordance with Specifications 6.9.3.1, 6.9.3.2, 6.9.3.3, and 6.9.3.4 Plant operation within there core operating limits is addressed in individual specificationn.
CRITICA1. E0WER RATIO The CRITICAL POWER RATIO (CPR) shall be the ratio of that power in an assembly which is calculated, by application of an NRC approved CPR correlation, to
~
cause some point in the assembly to experience boiling transition, divided by the actual assembly operating power.
DOSE EQUIVA1.ENT I-131 DOSE EQUIVALENT I-131 shall be concentration of I 131, )Ci/ gram, which alone would produce the same thyroid dose as the quanti *y and isotopic mixture of 1 131, 1-132,1-133, I-134, and 1-135 actually present.
The following is defined equivalent to 1 )Ci of 1 131 as determined from Table III of TID-14844, " Calculation of Distance Factors for Power and Test Reactor Sites"*
1 132, 28 )Ci; I 133, 3.7 )Ci; I-134, 59 )Ci; I 135, 12 )Ci.
[ AVERACE DISINTECRATION ENERGY E shall be the average, weighted in proportion to the concentration of each radionuclide in the reactor coolant at the time of sampling, of the sum of the average beta and gamma energies per disintegration (in MeV) for isotoper with half lives greater than 15 minutes making up at least 95% of the total non-iodine activity in the coolant.
BRUNSWICK - UNIT 2 1-2 Amendment No.
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jiFITE1ING OPERATIONS 3/4.9.3 CONTR01. ROD POSITION 1,1MITING CONDITION FOR-OPERATION I
3.9.3 All control rods shall be fully inserted *,
APPLICAfPl.1TY:
CONDITION 5, during loading of fuel assemblics into the i
core **.
ACTION:
With all control rods not fully inserted, immediately suspend loading of fuel assetablies into the core. The provisionn of Specification 3.0.3 cre not applicable.
i SURVEilJANCE REQUIREMENTS 4.9.3 Verify all control rods to be fully inserted within 2 heuro prior to the start of and at least once per -12 hours during loading of fuel assemblies into the core.
- Except control rods removed per Specification 3.9.10.1 or 3.9.1.2.
E
- See Special Test Exception 3.10.3.
a BRUNSWICK - UNIT 2 3/4 9-5 RETYPED TECH. SPECS.
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314.9 REFUELING OPERATIONS EASES 3/4.4.1 PEACTOR MODE SWITCl]
Locking the reactor mode switch in the refuel position ensures that the restrictions on rod withdrawal and refueling platform movement during the j
refueling operations are properly activated.
These conditions reinforce the refueling procedurou and reduce the probability of inadvertent criticality, I
damage t.o reactor internals, fuel assemblics and exposure of personnel to excessive radioactivity.
J/_4. 9. 7 INSTRUMENTATION The OPERABILITY of the source range monitors ensures that redundant monitorin5 capability is available to detect changes in the reactivity condit. ion of the core, During a SPJRAL UNIDAD, the count rate of the SRM will decrease below 3 cps
-before all of the fuel is unloaded. The count rate of 3 cps is not necensary since there vill be no reactivity additions during the spiral unload. The SRMs will he required to be OPERABLE prior to t.he SPIRAL UNLOAD, and each SRM will be verified operational by raising the count rate to 3 cps prior to the SPIRAL RELOAD by inserting up to four fuel assemblies around each SRM.
This will ensure that the SRMs can be relied upon to monitor core reactivity during the reload.
3 /4. 9. 'l CONTROL ROD POSIT 1 M The requirement that all control rods be inserted during loading of fuct assemblics into the core ensures that fuel will not bo loaded into a cell without a control rod and prevents two positive reactivity changes from occurring simultaneously 3/4.9.4 DECAY TIME The minimum requirement for reactor suberiticality prior-to fuel movement ensures that sufficient time has elapsed to allow the radioactive decay of the short lived fission products.
This decay time is consistent with the asstunptions used in the accident analyses.
3/4.4.5 COMMUNICATIONS The requirement for communications capability ensures that refueling station personnel can be promptly informed of significant changes in the facility status or core reactivity conditlen during movement of fuel within the reactor pressure vessel.
I l
BRUNSWICK - UNIT 2 B 3/4 9-1 Amendaient No4
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