ML20003D296
| ML20003D296 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 03/16/1981 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20003D297 | List: |
| References | |
| NUDOCS 8103260278 | |
| Download: ML20003D296 (18) | |
Text
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0, UNITED STATES y
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NUCLEAR REGULATORY COMMISSION g*'
.. E WASHINGTON D C. 20555 o
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CAROLINA POWER & LIGHT COMPANY DOCKET NO. 50-325 i
BRUNSWICK STEAM ELECTRIC PLANT, UNIT N3. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 34 License No. DPR-71 1.
The Nuclear Regulatory Comission (the Comission) qas found that:
A.
The application for amendment by Carolina Power & Light Company dated September 16, 1980, complies with the standards and require-ments 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; 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 and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulat.Jns; 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 it in accordance with 10 CFR Part 51 of the Comission's regula'"ns and all applicable requirements have been satisfied.
2.
Accordingly, Facility Operating License No. OPR-71 is hereby amended by revising paragraph 2.C.(2) and adding paragraphs 2.I acd 2.J to read as follows:
2.C.(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 34, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
810 3 260 $N 4,
, 2.1 Systens Integrity The licensee shall implement a program to reduce leakage from systems oitside containment that would or could contain highly radioactive fluids during a serious transient or accident to as low as practical levels. This program shall include the following:
1.
Provisions establishing preventive maintenance and periodic visual inspection requirements, and 2.
Integrated leak test requirements for each system at a frequency not to exceed refueling cycle intervals.
2.J Iodine Monitoring The licensee shall implement a program which will ensure the capability to accurately detennine the airborne iodine concen-tration in vital areas under accident conditions. This program shall include the following:
1.
Training of personnel, 2.
Procedures for monitoring, and 3.
Provisions for maintenance of sampling and analysis equipment.
3.
This license amendment is effective as of the dat.e of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
(
1 l
W Thomas
. Ippolito, Chief Operating Reactors Branch #2 Sivision of Licensing l
Attachment:
Changes to the Technical Specifications Date of Issuance:
March 16, 1981 L
l
ATTACHMENT TO LICENSE AMENDMENT NO. 34 FACILITY OPERATING LICENSE N0. DPR-71 DOCKET NO. 50-325 Remove the following pages and replace with identically numbered pages.
3/4 3-51 / 3/4 3-52 i
(
B3/4 3-3 / B3/4 3-4 6-5 / 6-6 The underlined pages are changed. Overleaf pages are provided for convenience.
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TABLE 3.3.5.3-1 FOST-ACCIDENT MONITORING INSTRU'-tENTATION MIND!L?! NO.
OF OPERABLE INSTRUMENT INSTRUMENT AND INSTRUMENT NUMBER CHANNELS 1.
2 (B21-LITS-N026A, B; B21-LR-615; B21-LI-R604A, B and B21-LITS-N037) a 2.
Reactor vessel pressure 2
(B21-PI-R004A, B; C32-LPR-R608_and C32-PT-N005A, B)
- 3.. Containment pressure 2
(CAC-Pr-2599; CAC-PT-2559; CAC-?R-1257-1 and CAC-PT-2257-1) 4.
Containment pressure 2
(CAC-TR-1258-1 through 13, 22, 23, 24 and C91-P602) 5.
Suppression chamber atmosphere temperature 2
(CAC-TR-1258-17 through 20 and C91-P602) 6.
' Suppression chamber water level 2
(CAC-LI-2601-3; CAC-LA-2602; C. 2-LT-2601; CAC-LT-2602 and CAC-LY-2601-1) 7.
Suppression chamber water temperature 2
(CAC-TR-1258-14, 21 and C91-P602) 8.
Containment radiation 2
(CAC-AR-1260; CAC-AQH-1260-1, 2, 3; CAC-AR-1261;.CAC-AQH-1261-1, 2, 3; CAC-AR-1262 and CAC-AQH-1262-1, 2, 3) 9.
Containment oxygen 2
(CAC-AT-1259-2; CAC-AR-1259; CAC-AT-1263-2 and CAC-AR-1263) 10.
Containment hydrogen 2
(CAC-AT-1959-1; CAC-AR-1259; CAC-AT-1263-1 and CAC-AR-1263) 11.
Safety reliefLvalve position indication:
1./ valve Primary - Sonic (B21-FY-4157 through 4167)
Secondary - Temp. (B21-TR-R614 points 1-11)
BRUNSWICK-UNIT 1 3/4 3-51 Amendment No 34 d ii
l 5
TABT.E 4.3.5.3-1 POST-ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CllANNEL INSTRUMENT AND INSTRUMENT NUMBER CilECK CALIBRATION ~
9 a
'1.
R g
(B21-LITS-N026A,B; B21-LR-R615; B21-LI-R604A,B and B21-LITS-NO37) s
'N R
d' 2.
Reactor vessel pressure (B21-P1-R004A,B; C32-LPR-R608 and C32-PT-N005A,B)
M R
3.
Containment pressure (CAC-PI-2599; CAC-PT-2599; CAC-PR-1257-1 and CAC-PT-1257-1) 4.
Containment temperature M
R (CAC-TR-1258-1 thru 13, 22, 23, 24 and C91-P602) 5.
Suppression chamber atmosphere temperature M
R (CAC-TR-1258-17 thru 20 and C91-P602) u 6.
Suppression chamber water level M
R D
(CAC-LI-2601-3; CAC-LR-2502; CAC-LT-2601; CAC-LT-2602 and 'CAC-LY-2601-1) ud 7.
Suppression-chamber water temperatura M
R (CAC-TR-1258-14, 21 and C91-P602) 8.
Containment radiation M
R (CAC-AR-1260; CAC-AQlt-1260-1,2,3; CAC-AR-1261; CAC-AQlt-1261-1,2,3; CAC-AR-1262 and CAC-AQll-1262-1,2,3) 9.
Containment oxygen concentration M
R (CAC-AT-1259-2; CAC-AR-1259; CAC-AT-1263-2 and CAC-AR-1263) 10.
Containment hydrogen concentration M
R
{
(CAC-AT-1259-1; CAC-AR-1259; CAC-AT-1263-1 and CAC-AR-1263) u 11.
Safety relief valve position indication (Primary-Sonic)
M R
(B21-FY-4157 thru 4167)
O 12.
Safety relief valve position indication (Secondary-Temperature)
M R
(B21-TR-R614 points 1 thru 11)
INSTRUMENTATION BASES i
MONITORING INSTRUMENTATION (Continued) 3/4.3.5.2 REMOTE SHUTDOWN MONITORING INSTRUMENTATION The OPERABILITY of the remote shutdown monitoring instrumentation ensures that sufficient capability is available to permit shutdown and maintenance of HOT SHUTDOWN of the facility from locations outside of the control room.
This capability is required in the event control room habitability is lost and is consistent with General Design Criteria 19 of CFR 50.
3/4.3.5.3 POST-ACCIDENT MONITORING INSTRUMENTATION The OPEPABILITY of the post-accident monitoring instrumentation
~
ensures that sufficient information is 'available on selected plant parameters to monitor and assess important variables following an accident.
This capability is consistent with the recommendations of Regulatory Guide 1.97 " Instrumentation for Light Water Cooled Nuclear Power Plants
)
to Assess Plant Conditions During and Following an Accident," December 1975 and NUREG-0578, "DiI-2 Lessons Learned Task Force Status Report and Short-Term Recommendations."
3/4.3.5.4 SOURCE RANGE MONITORS The source range monitors provide the operator with information on the status of the neutron level in the core at very low pcwer levels during startup. At these power levels reactivity additions should not be made without this flux level information available to the operator.
~
When the intermediate range monitors are on scale adaquate information is available without the SRM's and they can be retracted.
3/4.3.5.5 CHLORINE DETECTION SYSTEM The OPERABILITY of the chlorine detection systems ensures that an accidential chlorine release will be detected promptiv and the necessary protective actions will be automatically initiated to provide protection for control rocm personel. Upon detection of a high concentration.of chlorine the control room emergency ventilation system will automatically isolate the control room and initiate operation in the recirculation mode to provide the required protection. The detection systems required by this specifications are consistent with the recommendations of Regulatory Guide.1.95 " Protection of Nuclear Power Plant Control Room Operators against.an accidental Chlorine Release.
BRUNSWICK-UNIT 1 B 3/4 3-3 Amendment No. 34
l 1-i l
l l
INSTRUMENTATION BASES l
MONITORING INSTRUMENTATION (Continued)_
3/4.3.5.6 CHLORIDE INTRUSION MONITORS The chloride intrusion monitors provide adequate warning of any leakage in the condenser or hotwell so that actions can be taken to mitigate the consequences of such intrusion in the reactor coolant system. With only a minimum number of instruments available increased sampling frequency provides adequate infonnation for the same purpose.
3/4.3.5.7 FIRE DETECTION INSTRUMENTATION OPERABILITY of the fire detection instrumentation ensure that adequate warning capabil$ty is available for the prompt detection of fires.
This capab~ility is required in order to detect and locate fires in thir early stages. Prompt detection of fires will reduce the potential for damage to safety related equipment and is an integral element in the overall facility fire protection program.
In the event that a portion of the fire detection instrumentation is inoperable, increasing the frequency of fire patrols in the affected areas is required to provide detection capability until th. inoperable instrumentation is restored to OPERABILITY.
3/4.3.6' RECIRCULATION PUMP TRfP ACTUA[ ION INSTRUMENTATION Theanticipatedtransientwithoutscram(ATWS).recirculationpump trip system provides a means of limiting the consequences of the unlikely occurrence of a failure to scram during an anticipated transient.
The response of the plant to this postulated event falls within an envelope j
of study c.ents given in General Electric Company Topical Report NEDO-10349, dated March,~1971.
T?re end-of-cycle iecirculation pump trip (EOC-RPT) system is a part of the Reactor Protection system and is a safety supplement to the reactor trip.
The purpose of the EOC-RPT is to recover the loss of thermal margin wftich occurs at the~ end-of-cycle. The physical phenomenon invr.1ved is that the void reactivity feedback due to a pressurization transient can add positive reactivity to the reactor system at a faster rate than the control rods add negative scram reactivity. Each EOC-RPT 4
system trips both recirculation pumps.. reducing coolant flow in order to reduce the void collapse in the core during two of the most limiting p.ressurization events. The two events for which the EOC-RPT protective BRUNSWICK - UNIT 2 B 3/4 3-4 Amendment No. fB, 51 JUN 11 1980
TABLE 6.2.2-1 MINIt'.UM SHIFT CREW COMPOSITION!
Ccnditien of Unit 1 - dnit 2 in CONDITION 1, 2 or 3 LICENSE APPLICABLE CATEGORY OPERATIONAL CONDITIONS 1,2,3 l
4&5 SQL**
2 l
2*
3 l
2 OL**
Non-Licensed I
4 l
0 Condition of Unit 1 - Unit 2 in CONDITION 4 or 5 LICENSE APPLICASLE CATEGORY OPERATIONAL CONDITIONS 1,2,3 l
4&5 SOL **
1 2
l 1*
OL**
3 l
2 Non-Licensed
- l 3
l 3
o Condition of Unit 1 - No Fuel in Unit 2 LICENSE APPLICABLE CATEGORY OPERATIONAL CONDITIONS 1,2,3 4&5 SOL 1
1*
OL 2
1 Non-Licensed 2
l 1
0 l
Does not include the licensed Senior Reactor Operator. or Senior Reactor l
=
Operator Limited to Fuel Handling, supervising CORE ALTERATIONS.
- Assumes each individual is licensed on both plants.
~
! Shift crew composition, including an individual qualified in radiation protection procedures. =ay be less than the minimum requirements t
i 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 accomodate i
unexpected absence of on duty shif t crew members provided imediate action is taken to restore the
- ift crew cccposition to within the minimum requirements of Table 6.2.2-1.
SRUNS'o'ICK-UNIT 1 6-5 Amendment No. 34 v
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ADMINISTRATIVE CONTROLS 6.3 FACILITY STAFF QUALIFICATIONS 6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for (1) the (Radiation Protection Manager) who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975 and (2) the Shift Technical Advisor who shall have a b-chelor's degree or equivalent in a scientific or engineering discipline with specific training in plant design, and response and analysis of the plant for transients and accidents.
6.4 TRAINING 6.4.1 A retraining and replacement training program for the facility staff shall be maintained under the direction of the Training Supervisor and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CFR Part 55.
6.4.2 A training program for the Fire Brigade shall be maintained under the direction of the Plant Fire Chief and shall meet or exceed the requirements of Section 27 of the NFPA Code-1975.
6.5 REVIEW AND AUDIT 6.5.1 PLANT NUCLEAR SAFETY COMMITTEE (PNSC)
FUNCTION 6.5.1.1 The PNSC shall function to advise the General Manager on all matters related to nuc1_ar safety.
COMPOSITION 6.5.1.2 The PNSC shall be composed of the:
Chairman:
Plant General Manager Vice Chairman:
Operations Manager, Nbintenance Manager, Technical - Administrative Manager or Director-Nuclear Safety and QA Secretary:
Administrative Supervisor Member:
- Maintenance Supervisor (ISC)
Member:
Maintenance Supervisor (Mechanical)
Member:
Engineering Supervisor Member:
Environ = ental and Radiation Control Supervisor Member:
Quality Assurance Supervisor Member:
Shif t Operating Supervisors Member:
Training Supervisor ALTERNATES 6.5.1.3 All alternate members shall be appointed in writing by the PNSC Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in PNSC activities at any one time.
BRUNSWICK - UNIT 1 6-6 Amendment No. 34 a.--ma
co ceco y
)
UNITED STATES
,; ]4(g y ) je g
NUCLEAR REGULATORY COMMISSION
/.E WASHINGTON, D. C. 20555
\\.kg f
j CAROLINA POWER & LIGHT COMPANY DOCKET N0. 50-324 BRUNSWICK STEAM ELECirilC PLANT, UNIT N0. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 55 License No. DPR-62 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Carolina Power & Light Company dated September 16, 1980, complies with the standards and re ments of the Atomic Energy Act of 1954, as amended (the Act) quire-
, and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in confomity with the application, the provisions of the Act, and the rules and regulations of the 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, Facility Operating License No.' DPR-62 is hereby amended by revising paragraph 2.C.(2) and adding paragraphs 2.F and 2.G to read as follows:
2.C.(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 55, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
. 2.F Systems Integrity The licensee shall implement a program to reduce leakage from systems outside containment that would or could contain highly radioactive fluids during a serious transient or accident tc as low as practical levels. This program shall include the following:
1.
Provisions establishing preventive maintenance and periodic visual inspection requirements, and 2.
Integrated leak test requirements for each system at a frequency not to exceed refueling cycle intervals.
2.G Iodine Monitoring The licensee shall implement a program which will ensure the capability to accurately determine the airborne iodine concen-tration in vital areas under accident conditions. This program shall include the following:
1.
Training of personnel, 2.
Procedu. s for monitoring, and 3.
Provisions for maintenance of sampling and analysis equipment.
3.
This license amendment is effective as of the date of issuarc.e.
FOR THE NUCLEAR REGULATORY COMMISSION 0
.e Thomas
. Ippolito, Chief l
Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Iss.uance: March 16,1981
(
l l
ATTACHMENT TO LICENSE AMENDMENT NO. 55 FACILITY OPERATING LICENSE N0. OPR-62 DOCKET NO. 50-324 Remove the following pages and replace with identically numbered pages.
3/4 3-51 / 3/4 3-52 B3/4 3-3 / B 3/4 3-4 6-5 / 6-6 Underlined pages are changed. Overleaf pages are provided for convenience.
l1.
l' l
l
TABLE 3.3.5.3-1 POST-ACCIDENT MONITORING INSTRUMENTATION MINIMUM NO.
OF OPERABLE INSTRUMENT INSTRUMENT AND INSTRUMENT NUMBER CHANNELS 1.
(B21-LITS-N026A,B; B21-LR-615; B21-LI-R604A,B and B21-LITS-NO37) 2.
keactor vessel pressure 2
(E21-PI-R004A, B; C32-LPR-R608 and C22-PT-N005A, B) 3.
Containment pressure 2
(CAC-FI-2599; CAC-PT-2599; CAC-PR-1257-1 and CAC-PT-1257-1) 4.
Containment pressure 2
(CAC-TR-1258-1 thru 13, 22, 23, 24 and C91-P602) 5.
Suppression chamber atmosphere temperature 2
(CAC-TR-1258-17 thru 20 and C91-P602) 6.
Suppression chamber water level' 2
(CAC-LI-2601-3; CAC-LA-2602; CAC-LT-2601; CAC-LT-2602 and CAC-LY-2601-1) 7.
Suppression chamber water temperature 2
(CAC-TR-1258-14, 21 and C91-P602)
.8.
Containment radiation 2
(CAC-AR-1260;.CAC-AQH-1260-1, 2, 3 ; CAC -AR-1261; CAC-AQH-1261-1, 2, 3; CAC-AR-1262 and CAC-AQH..262-1, 2, 3) 9.
- Contairment oxygen 2
(CAC-AT-1259-2; CAC-AR-1259; CAC-AT-1263-2 and CAC-AR-1263) 10.
Containment hydrogen 2
'(CAC-AI-1959-1; CAC-Aa-1259; CAC-AT-1263-1 and CAC-AR-1263)
,t.
Safety relief valve position indication:
1/ valve Primary - Sonic (B21-FY-4157 thru 4167)
__ _ Secondary _ _ Temp. _(B_21 -TR-R614 points 1-11) _,
BRUNSWICK-UNIT'2 3/4 3-51 Amendment No.55 Y
t' TABI.E 4. 3. 5. 3-1
' POST-ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS
'E CHANNEL CHANNEL 10 CHECK CALIBRATION 4
INSTRUMENT AND INSTRUMENT NUMBER R-1.
' Reactor vessel water level M
R i
(B21-LITS-N026A,B; B21-LR-R615; B21-LI-R604A,B and B21-LITS-NO37) g M
R 2.
Reactor vessel pressure (B21-PI-R004A,B; C32-LPR-R608 and C32-PT-N005A,B)
M R
3.
Containment pressure
-(CAC-P1-2599; CAC-PT-2599; CAC-PR-1257-1 and CAC-PT-1257-1) 4.
Containment temperature M
R (CAC-TR-1258-1 thru 13, 22, 23, 24 and C91-P602) 5.
Suppression chamber atmosphere temperature M
R (CAC-TR-1258-17 thru 20 and C91-P602)
N R
6.
Suppression chamber water level v2 (CAC-LI-2601-3; CAC-LR-2602; CAC-LT-2601; CAC-LT-2602 and CAC-LY-2601-1) 7.
Suppression chamber water temperature M
R (CAC-TR-1258-14, 21 and C91-P602) 8.
Containment radiat; ion M
R (CAC-AR-1260; CAC-AQH-1260-1,2,3; CAC-AR-1261; CAC-AQH-1261-1,2,3; CAC-AR-1262 and CAC-AQH-1262-1,2,3) 9.
Containment oxygen concentration M
R (CAC-AT-1259-2; CAC-AR-1259; CAC-AT-1263-2 and CAC-AR-1263) 10.
Containment hydrogen concentration M
R (CAC-AT-1259-1; CAC-AR-1259; CAC-AT-1263-1 and CAC-AR-1263)
I 11.
Safety relief valve position indication (Primary-Sonic)
M R
(B21-FY-4157 thru 4167) 12.
Safety relief valve position indication (Secondary-Temperature)
M R
lE (B21-TR-R614 points 1 thru 11)
j m
INSTRUMENTATION BASES M3NITORING INSTRUMENTATION (Continued) 3/4.3.5 2 REMOTE SHUTDOWN MONITORING INSTRUMENTATION The OPERASILITY of the remote shutdown monitoring instrumentation ensures that sufficient capability is available to permit shutdown and maintenance of HOT SHUTCOWN of the facility from locations outside of the control room.
This capability is required in the event control room habitability is lost and is consistent with General Design Criterion 19 of CFR 50.
3/4.3.5.3 FOST-ACCIDENT MONITORING INSTPUMENTATION The OPERASILITY of the post-accident monitoring instrumentation ensures that sufficient information is a0ailable on selected plant pa-rameters to monitor an< assess important variables following.an accident.
This capability is co..sistent with the reconnendations of Regulatory Guide 1.97 " Instrumentation for Light Water Cooled Nuclear Power Plants
}
to Assess Plant Conditions During and Following an Accident," December 1975 and NUREG-0578, "TMI-2 Lessons Learned Task Force Status Report and Short-Term Recommendations."
3/4.3.5.4 SOURCE RANGE MONITORS The source range monitors provide the operator with information on the status of the neutron level in the core at very low pcwer Svels -
during startup. At these power levels reactivity additions should not be made without this flux level information available to ths operator.
When the intermediate range moni. tors are on scale adequate information l
is available without the SR.Ts and they can be retracted.
i 3/4.3.5.5 CHLORINE DETECTION SYSTEM l
The OPERABILITY of the chlorine detection systems ensures that an accidental chlorine release will be detected prc=ptly and the necessary l
protective actions will be automatically initiated te provide protection for_ control room personnel. Upon detection.of a high concentration of -
chlorine the control room emergency ventilation system will automatically l
isolate the control room and initiate operation' in the recirculation l
mode to provide the required protection. The. detection systems required
(
by this specification are consistent with the recommendations of l
Regulatory Guide 1.95 " Protection of Muclear Power Plant Control Room Operators Against an Accidental Chlorine Release."
)
3,RU,USWICK - (" IT 2 B 3/4 3-3 Amend =ent No. 55 Y
M l
l l
INSTRUMENTATION BASES MONITORING INSTRUMENTATION (Continued) i l
3/4.3.5.6 CHLORIDE INTRUSTION MONITORS The chloride intrusion monitors provide adequate warning of any leakage in the condenser or hotwell so that actions can be taken to mitigate the consequences of such intrusion in the reactor coolant system. With only a minimum number of instruments available increased sampling frequency provides adequate information for the same purpose.
3/4.3.5.7 FIRE DETECTION INSTRUMENTATION OPERABILITY of the fire detection instrumentation ensures that adequate warning capability is available for the prompt detection of fires. This capability is required in order to detect and locate fires in their early stages.
Prompt detection of fires will reduce the potential for damage to safety related equipment and is an integral element in the overall facility fire protection program.
In the event that a portion of the fire detection instrumentation is inoperable, increasing the frequency of fire patrols in the affected creas is required to provide detection capability until the inoperable instrumentation is restored to OPERASILITY.
l 3/4.3.6 ATWS RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION The ATWS recirculation pump trip system has been addec ct the suggestion of ACRS as c. means of limiting the consequences of the unlikely occurrence of a failure to scram during an anticipated transient. The response of the plant to this postulated event falls within the envelope of study events given in General Electric Company Topical Report NEDO-10349, dated March,1971.
BRUNSWICK-UNIT 1 B 3/4 3-4 Amendment No. 24 MAY 2 1979
~
SABLE 6.2.2-1 MIND'.UM S!4IFT CREW COMPOSITION!
Condition of Unit 1 - Unit 2 in CONDITION 1. 2 or 3 LICENSE APPLICABLE CATEGORY OPERATIONAL CONDITIONS 1, 2, 3 4&5 SOL **
l 2
2*-
f OL**
l 3
l 2
Non-Licensed 4
0 Condition Of Unit 1 - Unit 2 in CONDITION 4 or 5 LICENSE APPLICABLE CATEGORY OPERATIONAL CONDITIONS 1, 2, 3 4&5 50L**
2 1*
OL**
3 2
Non-Licensed 3
0 Condition of Unit 1 - No Fuel in Unit 2 LICENSE APPLICABLE CATEGORY OPERATIONAL CONDITIONS 1,2,3 4&5 SOL 1
1*
OL 2
1 Non-Licensed 2
. l 1
0
- Does not incluoe the licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling, supervising CORE ALTEPATIONS.
- = Assumes each individual is licensed on both plants.
f Shif t crew cc= position, including an individual qualified in radiation protection procedures, may be less than the minimum recuirements 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 accom.odate' unexpected absence of on duty shift crew members provided immediate action is taken to restore the shi't crew composition to within the minimum requirements of Table 6.2.2-1.
ER"N5',.'ICK-U"IT 2 6-5 Amendment No. 55 M
-y e -
4
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ADMINISTRATIVE CONTROLS 6.3 FACILITY STAFF QUALIFICATIONS 6.3.1 Each member of the unit staf f shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for (1) the (Radiation Protection Manager) who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975 and (2) the Shift Technical Advisor who shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant design, and response and analysis of the plant for transients and accidents.
6.4 TRAINING 6.4.1 A retraining and replacement training program for the facility staff shall be maintained under the direction cf the Training Supervisor and shall meet or exceed the requirements er.d recc=mendations of Section 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CFR Part 55.
6.4.2 A training program for the Fire Brigade shall be maintained under the direction of the Plant Fire Chief and shall meet er exes;J the requirements of Section 27 of the NFPA Code-1975.
6.5 REVIEW AND AUDIT 6.5.1 PLANT NUCLEAR SAFETY COMMITTEE (PNSC)
FUNCTION 6.5.1.1 The PNSC shall function to advise the General Manager on all matters related to nuclear safety.
COMPOSITION 6.5.1.2 The PNSC shall be composed of the:
Chairman:
Plant General Manager Vice Chairman:
Operations Manager, Maintenance Manager, Technical - Administrative Manager or Director-Nuclear Safety and QA Secretary:
Administrative Supervisor Member:
Maintenance Supervisor (ISC)
Member:
Maintenance Supervisor (Mechanical)
Member:
Engineering' Supervisor Member:
Environmental and Radiation Control Supervisor Member:
Quality Assurance Supervisor Member:
Shif t Operating Supervisors Member:
Training Supervisor ALTERNATES
- 6. 5.1.*3 All alternate' members shall be appointed in writing by the PNSC Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in PNSC activities at any one time..
BRUNSWICK - UNIT 2 6-6 Amendment No. 55