ML20133L424
| ML20133L424 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 08/06/1985 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Carolina Power & Light Co |
| Shared Package | |
| ML20133L427 | List: |
| References | |
| DPR-62-A-114, DPR-71-A-089 NUDOCS 8508120607 | |
| Download: ML20133L424 (16) | |
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UNITED STATES
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t CAROLINA POWER & LIGHT COMPANY DOCKET NO. 50-325
~ BRUNSWICK STEAM ELECTRIC PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 89 License No. DPR-71 r-1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Carolina Power & Light Company (the licensee) dated April 9, 1985, complies with the s,tandards and re.luirements of the Atomic Energy Act of 1954, as amended (the Act) and the'Comission's rules and regulations set forth in 10 CFR Chapter I;
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B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the i
Comission; C.
There is reasonable assurance (1) 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 Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon 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.
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-71 is hereby amended to read as follows:
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(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.
89, are hereby incorporated in the license. The licensee 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 Domenic B. Vassallo, Chief 7"'
Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: August 6,1985 9
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ATTACHMENT TO LICENSE AMENDMENT NO. 89 FACILITY OPERATING LICENSE NO. DPR-71 DOCKET NO. 50-325 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by vertical lines.
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(BSEP-1-58)
DEFINITIONS SHUTDOWN MARCIN SHUTDOWN MARCIN shall be the amount of reactivity by which the reactor would be suberitical assuming that all control rods capable of insertion are fully inserted except for the analytically determined highest worth rod which'is assumed to be-fully withdrawn, and the reactor is in the shutdown condition, cold, 68,*F, and Xenon free.
. SITE BOUNDARY The SITE BOUNDARY shall be that line beyond which the land is neither owned, nor leased, nor otherwise controlled by the licensee, as defined by Figure 5.1.3-1.
' SOLIDIFICATION SOLIDIFICATION shall be the conversion of wet wastes into a form that meets shipping and burial ground requirements.
SOURCE CHECK A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to radiation.
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A SPIRAL RELOAD is the reverse'of a SPIRAL UNLOAD.
Except for fuel bundles around each of the four SRMs, the fuel'in the interior of the core, symmetric to the SRMs, is loaded first.
Up to four fuel bundles may be loaded around l
each of the four SRMs.
l SPIRAL UNLOAD A SPIRAL UNLOAD is a core unload performed by first removing the fuel from the outermost control cells (four bundles surrounding a control blade). Unloading, continues in a spiral fashion by removing fuel from the outermost periphery to the interior of the core, symmetric about the SRMs, except for fuel bundles around each 'f the four SRMs. Up to four fuel bundles may be left around each o
SRM to maintain adequate count rate.
STACCERED TEST BASIS A STACCERED TEST BASIS shall consist oft a.
A test schedule for n systems, subsystems, trains or other designated components obtained by dividing the specified test interval into a equal subintervals.
b.
The testing of one system, subsystem, train or other designated component at the beginning of each subinterval.
BRUNSWICK - UNIT 1 1-7 Amendment No. 89
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(BSEP-1-58)
REFUELINC OPERATIONS 3/4.9.2 INSTRUMENTATION LIMrTINC CONDITION FOR OPERATION 3.9.2 During CORE ALTERATIONS, the requirements for the source range monitors (SRMs) shall bet a..
Two SRMs* shall be OPERABLE, one in the core quadrant where fuel is being moved and one in an adjacent quadrant.
For an SRM to be considered OPERABLE, it shall be inserted to the normal operating level,and shall have a minimum of 3 cps except as specified in d and a below.
b.
The SRMs shall give a continuous visual indication in the control Room.
c.
The " shorting links" shall be removed from the RPS circuitry prior to and during the time any control rod is withdrawn ** and shutdown margin demonstrations.
d.
During a core SPIRAL UNLOAD the count rate may drop below 3 cys.
e.
Prior to a core SPIRAL RELOAD, up to four fuel assemblies shall be
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loaded into different control cells containing control blades around each SRM to obtain 3 cps. Until these assemblies have been loaded, the 3 cps count rate is not required.
APPLICABILITYt OPERATIONAL CONDITION 5 ACTION:
With.the requirements of the above specifica' tion not satisfied, immediately suspend all operations involving CORE ALTERATIONS or positive reactivity
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changes and fully insert all insertable control rods.- The provisions of i
- Specification 3.0.3 are not applicable.
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- The use of special movable detectors during CORE ALTERATIONS in place of the normal SRM nuclear detectors is permissible as long as these special detectors are connected to the normal SRM circuits.
- Not required for control rods removed per Specifications 3.9.10.1 or l
3.9.10.2.
J BRUNSWICK - UNIT 1 3/4 9-3 Amendment No. 89 0
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SURVEILLANCE REQUIREMENTS 4.9.2 Each of the above required SRM channels shall be demonstrated OPERABLE by:
a.
At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />; 1.
Performance of a CHANNEL CHECK,
- 2.'
Verifying the detectors are inserted to the normal operating
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- level, 3.
During CORE ALTERATIONS, verifying that the detector of an OPERABLE SRM channel is located in the core quadrant where CORE ALTERATIONS are being performed and one is located in che adjacent quadrant, 4.
During CQRE ALTERATIONS, verifying that the channel count rate is at least 3 eps (except as noted in Specification 3.9.2.d and 3.9.2.e),
5.
During a core SPIRAL UNLOAD or SPIRAL RELOAD, verifying that the fuel movement sheet is being.followed.
b.
Verifying prior to the start of a SPIRAL RELOAD that the SRMs have been raised to a count rate of at least 3 cps by the insertion of up to four fuel assemblies around each of the four SRMs.
c.
Performance of a CHANNEL FUNCTIONAL TEST:
1.
Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to the start of CORE ALTERATIONS, and 2.
At least once per seven days.,
BRUNSWICK - UNIT 1 3/4 9-4 Amendment No. 89
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(BSEP-1-58) 3/4.1 REACTIVITY CONTROL SYSTEMS
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BASES i-3/[.1.1 SHUTDOWN MARCIN k
A sufficient SHUTDOWN MARCIN ensures that 1) the reactor can be made i
suberitical from all operating conditions, 2) the reactivity transients associated with postulated accident conditions are controllable within acceptable limits, and 3) the reactor will be maintained sufficiently i
suberitical to preclude inadvertent criticality in the shutdown condition.
Since core reactivity values will vary through core life as function of fuel depletion and poison burnup, the demonstration of SBUTDOWN NARCIN will be performed in the cold zenon-free condition and shall show the core to be suberitical by a least R + 0.38% delta k/k. The value of R in units of
% delta k/k is the difference between the calculated value of maximum core i
reactivity during the operating cycle and the calculated beginning-of-life t
core reactivity.
The value of R must be positive or zero and must be determined for each fuel loading cycle. Satisfaction of this limitation can be best demonstrated at the time of fuel loading, but the margin must be
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determined anytime a control rod is incapable of insertion.
During the SPIRAL RELOAD deviations from the scheduled core loading are permitted in order to achieve the required 3 cps needed to gain SRM operability provided the cold reactivities (zero voids) of the fuel bundles temporarily loaded around the SRMs are individuall respective bundles scheduled for those locations. y less than that of the The cold shutdown margin calculation performed for the scheduled core loading bounds the partially loaded core during the SPIRAL RELOAD process.
This reactivity characteristic has been a basic assumption in the analysis of plant performance and can best be demonstrated at the time of fuel loading, but the margin must also be determined anytime a control rod is incapable of insertion.
3/4.1.2 REACTIVITY ANOMALIES Since the SHUTDOWN MARCIN requirement for the reactor is small, a careful check on actual conditions to the predicted conditions is necessary, and the changes in reactivity can be inferred from these comparisons of rod patterns. Since the comparisons are easily done, frequent checks are not an imposition on normal operations. A 1% change is larger than is expected for
' normal operation so a change of this magnitude should be thoroughly evaluated. A change as large as 1% would not exceed the design conditions of the reactor and is on the safe side of the postulated transients.
"During the first startup following CORE ALTERATIONS" implies that the specified surveillance should be performed upon the initial attainment of a hash equilibrium power level, preferably of at least 90% of RATED THERMAL POWER, during the unit startup.
3/4.1.3 CONTROL RODS The specifications of this section ensure that 1) the minimum SHUTDOWN MARCIN is maintained,ident analysis, and 3) the
- 2) the control rod insertion times are consistent with those used in the acc 7
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k (BSEP-1-58) 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 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 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 eps 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 during the reload.
3/4.9.3 CONTROL ROD POSITION-The requirement that all control rods be inserted during CORE ALTERATIONS 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 issumptions 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.
BRUNSWICK - UNIT 1 B 3/4 9-1 Amendment No. 89
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CAROLINA POWER & LIGHT COMPANY DOCKET NO. 50-324 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 2 AMENDHENT TO FACILITY OPERATING LICENSE Amendment No.114 License No. DPR-62 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Carolina Power & Light. Company (the licensee) dated April 9,1985, 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 Comission; C.
There is reasonable assurance (i) that the. activities authorized by this amendment can be conducted without endangering the health dnd safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the l
comon defense and security or to the health and safety of the l
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.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, l
and paragraph 2.C.(2) of Facility Operating License No. DPR-62 is hereby amended to read as follows:
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(2) Technical Specifications The Technical Specifications contained in Appendices A and B as revised through Amendment No.114, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FORTHENUCLEARREGULATORYCOMMISSIbh Domenic 8. Vassallo. Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: August 6, 1985 4
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ATTACHMENT TO LICENSE AMENDMENT NO.114 FACILITY OPERATING LICENSE N0. DPR-62 DOCKET NO.' 50-324 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by vertical lines.
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DEFINITIONS SPIRAL RELOAD A SPIRAL RELOAD is the reverse of a SPIRAL WLOAD.
Except for fuel bundles l
around each of the four SRMs, the fuel in the interior of the core, symmetric to the SRMs, is loaded first. Up to four fuel bundles may be loaded around each of the four SRMs.
SPIRAL WLOAD A SPIRAL WLOAD is a core unload performed by first removing the fuel from the outermost control cells (four bundles surrounding a control blade). Unioading continues in a spiral fashion by removing fuel from the estermost periphery to the interior of the core, symmetric about the SRMs, escept for fuel bundles around each of the four SRMs.,Up to four fuel bundles may be left around each SRM to maintain adequate coun't rate.
7 STACCERED TEST SASIS A STACCERED TEST BASIS shall consist of s.
A test schedule for n systems, subsystems trains er other designated components obtained by dividing the specified test interval into n equal subintervals.
b.
The testing of one system, subsystem, train or other designated component at the beginning of each subinterval.
THEMAL POWER THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.
, TOTAL PEAKING FACTOR The TOTAL PEAKINC FACTOR (TPF) shall be the ratio of local LNCR for any specific location on a fuel rod divided by the average LNCR associated with the fuel bundles of the same type operating at the core average bundle power.
WIDENTIFIED LEAKAGE WIDENTIFIED LEAKACE shall be all leakage which is not IDert!FIED LEAKACE.
WRESTRICTED AREA An WRESTRICTED AREA shall be any area at or beyond the g!TE BOUNDARY access to which is not controlled by the licensee for purpose of protection of individuals from esposure to radiation and radioactive meterlate er any area
, within the SITE 80WDARY used for residential quarters er industrist, seassercial. Institutional and/or recreational purposes.
BRUNSWICK - WIT 2 1-8 Amerdoent No.114
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(BSEP-2-53) l REFUCLINC OPERATIONS 3/4.9.2 INSTRUMENTATION LIMITINC CONDITION FOR OPERATION 3.9.2 During CORE ALTERATIONS, the requirements for the' source range monitors (SRMs) shall bet Two SRMs* shall be OPERABLE, one in the core quadrant where fuel is a.
being moved and one in an adjacent quadrant. For an SRM to be considered OPERABLE, it shall be inserted to the normal operating level and shall have a minimum of 3 cps except as specified in d and a below.
b.
The SRMs shall give a continuous visual indication in the Control Room.
The " shorting links" shall be removed from the RPS circuitry prior to c.
and during the time any control rod is withdrawn ** and shutdown margin demcnstrations.
d.
During a core SPIRAL UNLOAD the count rate may drop below 3 cys.
e.
Prior to a core SPIRAL RELOAD, up to four fuel assemblies shall be loaded into different control cells containing control blades around each SRM to obtain 3 cps. Until these assemblies have been loaded, the 3 cps count rate is not required.
l APPLICABILITY: OPERATIONAL CONDITION $
ACTION With the requirements of the above specification not satisfied, immediately suspend all operations involving CORE ALTERATIONS or positive reactivity changes and fully insert all insertable control rods. The provisions of specification 3.0.3 are not applicable.
9 The use of special movable detectors during CORE ALTERATIONS in place of the normal SRM nuclear detectors is permissible as long as these specist detectors are connected to the normal SRM circuits.
I Not required for control rods removed per Specifications 3.9.10.1 or l
3.9.10.2.
3/4 9-3 Amendment No. 114 BRUNSWICK = UNIT 2 O
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(BSEP-2-53)
SURVEILI.ANCE' REQUIREMENTS 4.9.2 Each of the above required SRM -hannels shall be demonstrated OPERABLE byn s.
At least once per 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />st 1.
Performance of a CHANNEL CHECK, 2.
Verifying the detectors are inserted to the normal operating
- level, 3.
During CORE ALTERATIONS, verifying that the detector of an '
OPERABLE SRM channel is located in the core atuadrant where CORE ALTERATIONS are being performed and one is located in the adjacent quadrant, 4.
During CORE ALTERA*.* IONS, verifying that the channel count rate is at least 3 cps (except as noted in Specification 3.9.2.d and 3.9.2.e),
5.
During a core SPIRAL UNLOAD or SPIRAL RELOAD, verifying.that the fuel movement sheet is being followed.
b.
Verifying prior to the start of a SPIRAL RELOAD that the SRMs have been raised to a count rate of at least 3 cps by the insertion of up to four fuel assemblies around each of the four saMs.
c.
Performance of a CHANNEL FUNCTIONAL TEST 1.
Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to the start of CORE ALTERATIONS, and 2.
At least once per seven days.,
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3/4.1-REACTIVITY CONTROL SYSTEMS BASES 3 /4.~1.1 SHUTDOWN MARCIN A sufficient SHUTDOWN MARCIN ensures that 1) the reactor can be made subcritical from all operating conditions, 2) the reactivity transients associated with postulated accident conditions are controllable within acceptable limits, and 3) the reactor will be maintained sufficiently suberitical to preclude inadvertent criticality in the shutdown condition.
Since core reactivity values will vary through core life as a function of fuel depletion and poison burnup, the demonstratton of SHUTDOWN MARCIN will be performed in the cold xenon-free condition and shall show the core to be subcritical by at least R + 0.38% delta k/k. The value of R in units of
% delta k/k is the difference between the calculated value of maximum core reactivity during the operating cycle and the calculated beginning-of-life core reactivity. The value of R must be positive or zero and must be determined for each fuel loading cycle. Satisfaction of this limitation can be best demonstrated at the time of fuel loading, but the margin must be determined anytime a control rod is incapable of insertion.
During the SPIRAL RELOAD deviations from the scheduled core loading are permitted in order to achieve the required 3 cps needed to gain SEM operability provided the cold reactivities ('zero voids) of the fuel bundles temporarily loaded around the SRMs are individually less than that of the respective bundles scheduled for those locations. The cold shutdown margin calculation performed for the scheduled core loading bounds the pa'rtially loaded core during the SPIRAL RELOAD process.
This reactivity characteristic has been a basic assumption in the analysis of plant performance and can best be demonstrated at the time of fuel loading, but the margin must also be determined anytime a control rod is incapable of insertion.
3/4.1.2 REACTIVITY ANOKALIES Since the SHUTDOWN KARCIN requirement for the reactor is small, a careful check on actua1' conditions to the predicted conditions is necessary, and the changes in reactivity can be inferred from these comparisons of rod patterne. Since the comparisons are easily done, frequent checks are not an imposition on normal operations. A 1% change is larger than is aspected for normal operation so a change of this magnitude should be thoroughly evaluated. A change as large as 1% would not exceed the design epuditions o,f-the reactor and is on the safe side of the postulated transients.
"During the first startup following CORE ALTERATIONS" implies that the specified surveillance should be performed upon the initial attainment of a high equilibrium power level, preferably of at least 90% of. RATED THERMAL POWER, during the unit startup.
3/4.1.3 CONTROL RODS The specifications of this section ensure that 1) the minimum SHUTDOWN KARCIN is maintained,ident analysis, and 3) the
- 2) the control rod insertion times are consistent with those used in the acc BRUNSWICK - UNIT 2 B 3/4 1-1 Amendment No. 114 e
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l 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 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 end exposure 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 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 spirh1 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 during the teload.
s 3/4.9.3 CONTROL ROD POSITION' The requirement that all control rods be inserted during CORE ALTERATIONS 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.
l 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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i BRUNSWICK - UNIT 2 8 3/4 9-1 Amendment No. 114 4