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{{#Wiki_filter:I~~j~I)~~0 6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The Plant Manager shal 1 be responsible for overal 1 facil | {{#Wiki_filter:I ~ | ||
f.A Fire Brigade of at least 3 members sha'I 1 be maintained onsite at all times.The Fire Brigade shall not include 3 members of the minimum shift cr ew necessary for safe shutdown of the unit or any personnel required for other essential functions during a fire emergency. | ~ | ||
8202220357-. | j | ||
8202''6 PDR ADOCK 05000335 P | ~ | ||
LEFT BLANK INTENTIONALLY 6-2 2/16/82 e~i,~E" 4~C r(ANT MAKAC(h~I W om o%M eo e%%0+~Racon W~e STAff H(AL' | I | ||
~O~MAINT(NANC(surtnlkrtkotkr 1( | ) ~ | ||
-St, L(tcf(5 Plant, Unit 1 QNLICtksto | ~0 6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The Plant Manager shal 1 | ||
QUORUM 6.5.2.6 A quorum of CNRB shall consist of the chairman or his designated alternate and four members including alternates. | be responsible for overal 1 | ||
No more than a minority of the quorum shall have line responsibility for oper ation of the facility.6-9.2/;6/82 | facil ity operation and shall delegate in writing the succession to this responsibil ity during hi s absence. | ||
.eo~0"e("4 P v~I(~v,kv | : 6. 2 ORGANIZATION OFF SITE 6.2.1 The offsite organization for facility management and technical support shall be shown in Appendix A of the Florida Power 5 Light Company Topical guality Assurance Report. | ||
FACILITY STAFF 6.2.2 The Facility organization shall be as shown on Figure 6.2-1 and: | |||
a. | |||
Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1. | |||
b. | |||
At least one licensed Operator shall be in the control room when fuel is in the reactor. | |||
c. | |||
At least two licensed Operators shall be present in the control room during reactor start-up, scheduled reactor shutdown and during recovery fr om reactor trips. | |||
d. | |||
An individual qualified in radiation protection procedures shall be on site when fuel is in the reactor. | |||
e. | |||
ALL CORE ALTERATIONS after the initial fuel loading shall be directly supervised by either a | |||
licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation. | |||
f. | |||
A Fire Brigade of at least 3 | |||
members sha'I 1 | |||
be maintained onsite at all times. | |||
The Fire Brigade shall not include 3 | |||
members of the minimum shift cr ew necessary for safe shutdown of the unit or any personnel required for other essential functions during a fire emergency. | |||
8202220357-. 8202''6 PDR ADOCK 05000335 P | |||
PDR 4A 4 6-1 2/16/S2 | |||
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MAINT(NANC( | |||
surtnlkrtkotkr 1(CIIKICA( | |||
5IAIr AOMINIS'fILATIV( | |||
A51ISIANT Oh(ITv <<okr Ro SIArf l | |||
l 01 tnhllalls Sur(ILLNI(NO(NT INsrhuU(K( | |||
AILD CONIROL SurtnvI$ dll ASSL51AN1 SurthlklfNotkf tltCIILLCAL MAIKT(NAN<<t A55ISTANT SUT(RLNT(KO(kl M(CKKICAL MAIN'I(NAKC't STCUILITT surtnvlson Cnt UI$1ILV surtnvlsdn H(ALIH INTSLCS surtnvLSQR 100 Or(ILA1IONS SUrtnvlson TRAIXINO surtnvlson R(ACTOR Sur(ILVLSON tkCHL(flls 1( CLLNICLANS tkalktths 1( CILNLCIANS tkclkttns | |||
'I(CHNICIANS GUARQ5 CL(RXS tkclkttns ANO T(CHNLCANS fkCIK(ills AKO 1( CHNICIANT lh0 r(AIIT surfnvlson 115 5 | |||
1 Nark( TILS AND Ttc>AIL(LANS CHI(r (Lt<<IRLCLAK Mhlkl(KANC( | |||
I 0 IIIALAN Trh I CH faalkftn lll 5 | |||
I Ch I | |||
LA) | |||
IKSTILUM(kl AXO CONIROL Sr(CIA(IS'15 Err IL(NII<<(5 | |||
('Lt C I ILL C I AN 5 Arrll\\Nrlcfs nfLrln5 MACHINIST MlCKAKIC5 ArrntkrICtS nrlrtn no CQNTILOL 'CfNlfR ortnhron M | |||
Co ILO rani(du nllt (IT 5 | |||
SAO Alc LIAIOAOIIAh(Oh LIC(hlt AO AICILIACIOAOI(hh'IOALL(lan AVLLIIAAIOOLALOrra Marr | |||
'I 10 IAl 0 UMII0 Lh CL AMLILCAI ION OAILI(AILIDVLLIILLLVIOhllhl IAOIICILOVIAOCAAM | |||
'I Figure 6,g-l Foclllty Oroonlzatl(rn - St, L(tcf(5 Plant, Unit 1 QNLICtksto QrtnhlanS 0/5 IO | |||
1 ~ | |||
H | |||
ADMINISTRATIVE CONTROLS COMPOSITION 6.5.2.2 The composition of the CNRB shall be as shown in Appendix A | |||
of the Florida Power 5 | |||
Light Topical equality Assurance Report. | |||
The CNRB Chairman shall be designated in writing. | |||
ALTERNATES 6.5.2.3 All alternate members shall be appointed in writing by the CNRB Chairman to serve on a temporary basis; | |||
: however, no more than two alternates shal'I participate as voting members in CNRB activities at any one time. | |||
CONSULTANTS 6.5.2.4 Consultants shall be utilized as determined by the CNRB Chairman to provide expert advice to the CNRB. | |||
MEETING FRE UENCY 6.5.2.5 The CNRB shall meet at least once per calendar quarter during the initial year of facility operation following fuel loading and at least once per six months thereafter. | |||
QUORUM 6.5.2.6 A | |||
quorum of CNRB shall consist of the chairman or his designated alternate and four members including alternates. | |||
No more than a | |||
minority of the quorum shall have line responsibility for oper ation of the facility. | |||
6-9. | |||
2/;6/82 | |||
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SAFETY EVALUATION There are no safety related effects connected with the removal of the offsite management and technical support description and organization charts from the Technical Specifications. | |||
The purpose of including these descriptions is for general information of the corporate structure to those in possession of the Technical Specifications. | The purpose of including these descriptions is for general information of the corporate structure to those in possession of the Technical Specifications. | ||
However, the same information is also contained in the Florida Power 8 Light Company Topical Quality Assurance report (FPLTQAR). | : However, the same information is also contained in the Florida Power 8 Light Company Topical Quality Assurance report (FPLTQAR). | ||
The FPLTQAR is required to be updated to reflect all changes to the organization which affect quality within 30 days by letter and one year by amendment. | The FPLTQAR is required to be updated to reflect all changes to the organization which affect quality within 30 days by letter and one year by amendment. | ||
It is our opinion that duplication of material between the two documents is unnecessary and that processing the same change twice is an uneeded burden on the time and manpower resources of both FPL and the NRC.Should the need arise for information on the organization, the FPLTQAR will be available to the same people who previously would have had the organizational description in the Technical Specificatins. | It is our opinion that duplication of material between the two documents is unnecessary and that processing the same change twice is an uneeded burden on the time and manpower resources of both FPL and the NRC. | ||
The non FPL organizations which receive controlled copies of the St.Lucie Unit 1 Technical Specifications also receive controlled copies of the FPLTQAR, with only the Southwest Research Institute (SWRI)and Region II of the NRC receivi ng uncontrolled copies.SWRI is responsible for supplying our inservice inspection services.Their use of the Technical Specifications, therefore is limited to the ISI portions.Organizational questions, should they arise, can be handled through their FPL contact.The other non-FPL receipient of controlled Technical Specifications is the NRC Reactor Project Office of Region II.The Region is forwarded an uncontrolled copy of the QA Manual, and should the need arise requiring the verification of the organization status, questions could be answered by the Resident Inspector. | Should the need arise for information on the organization, the FPLTQAR will be available to the same people who previously would have had the organizational description in the Technical Specificatins. | ||
In a similar fashion the composition of the CNRB is duplicated in both the Technical Specifications and FPLTQAR.For the same reasons as stated above, we propose to remove the specific composition of the CNRB from the Technical Specifications. | The non FPL organizations which receive controlled copies of the St. | ||
0~,f,.r s-t r,r~~I II~I Ill~-~}} | Lucie Unit 1 Technical Specifications also receive controlled copies of the | ||
: FPLTQAR, with only the Southwest Research Institute (SWRI) and Region II of the NRC receivi ng uncontrolled copies. | |||
SWRI is responsible for supplying our inservice inspection services. | |||
Their use of the Technical Specifications, therefore is limited to the ISI portions. | |||
Organizational questions, should they | |||
: arise, can be handled through their FPL contact. | |||
The other non-FPL receipient of controlled Technical Specifications is the NRC Reactor Project Office of Region II. | |||
The Region is forwarded an uncontrolled copy of the QA Manual, and should the need arise requiring the verification of the organization status, questions could be answered by the Resident Inspector. | |||
In a similar fashion the composition of the CNRB is duplicated in both the Technical Specifications and FPLTQAR. | |||
For the same reasons as stated | |||
: above, we propose to remove the specific composition of the CNRB from the Technical Specifications. | |||
0 | |||
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~ | |||
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Latest revision as of 15:44, 8 January 2025
| ML17212B395 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie |
| Issue date: | 02/16/1982 |
| From: | FLORIDA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML17212B394 | List: |
| References | |
| NUDOCS 8202220357 | |
| Download: ML17212B395 (10) | |
Text
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~0 6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The Plant Manager shal 1
be responsible for overal 1
facil ity operation and shall delegate in writing the succession to this responsibil ity during hi s absence.
- 6. 2 ORGANIZATION OFF SITE 6.2.1 The offsite organization for facility management and technical support shall be shown in Appendix A of the Florida Power 5 Light Company Topical guality Assurance Report.
FACILITY STAFF 6.2.2 The Facility organization shall be as shown on Figure 6.2-1 and:
a.
Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1.
b.
At least one licensed Operator shall be in the control room when fuel is in the reactor.
c.
At least two licensed Operators shall be present in the control room during reactor start-up, scheduled reactor shutdown and during recovery fr om reactor trips.
d.
An individual qualified in radiation protection procedures shall be on site when fuel is in the reactor.
e.
ALL CORE ALTERATIONS after the initial fuel loading shall be directly supervised by either a
licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation.
f.
A Fire Brigade of at least 3
members sha'I 1
be maintained onsite at all times.
The Fire Brigade shall not include 3
members of the minimum shift cr ew necessary for safe shutdown of the unit or any personnel required for other essential functions during a fire emergency.
8202220357-. 82026 PDR ADOCK 05000335 P
PDR 4A 4 6-1 2/16/S2
V
~I VV \\
~ ~ v ~ I
~
~ U V ~
LEFT BLANK INTENTIONALLY 6-2 2/16/82
e~
i,
~
E" 4
~C
r(ANT MAKAC(h
~I W om o% M eo e% %0+
~Racon W~e STAff H(AL'IHrIITSI(s 511<<IALIST ch<<LL<<(ALVf.'ci< 5 IAr1 tlnr raoltcILak AOMIKLSIRAIOR
~ O~
MAINT(NANC(
surtnlkrtkotkr 1(CIIKICA(
5IAIr AOMINIS'fILATIV(
A51ISIANT Oh(ITv <<okr Ro SIArf l
l 01 tnhllalls Sur(ILLNI(NO(NT INsrhuU(K(
AILD CONIROL SurtnvI$ dll ASSL51AN1 SurthlklfNotkf tltCIILLCAL MAIKT(NAN<<t A55ISTANT SUT(RLNT(KO(kl M(CKKICAL MAIN'I(NAKC't STCUILITT surtnvlson Cnt UI$1ILV surtnvlsdn H(ALIH INTSLCS surtnvLSQR 100 Or(ILA1IONS SUrtnvlson TRAIXINO surtnvlson R(ACTOR Sur(ILVLSON tkCHL(flls 1( CLLNICLANS tkalktths 1( CILNLCIANS tkclkttns
'I(CHNICIANS GUARQ5 CL(RXS tkclkttns ANO T(CHNLCANS fkCIK(ills AKO 1( CHNICIANT lh0 r(AIIT surfnvlson 115 5
1 Nark( TILS AND Ttc>AIL(LANS CHI(r (Lt<<IRLCLAK Mhlkl(KANC(
I 0 IIIALAN Trh I CH faalkftn lll 5
I Ch I
LA)
IKSTILUM(kl AXO CONIROL Sr(CIA(IS'15 Err IL(NII<<(5
('Lt C I ILL C I AN 5 Arrll\\Nrlcfs nfLrln5 MACHINIST MlCKAKIC5 ArrntkrICtS nrlrtn no CQNTILOL 'CfNlfR ortnhron M
SAO Alc LIAIOAOIIAh(Oh LIC(hlt AO AICILIACIOAOI(hh'IOALL(lan AVLLIIAAIOOLALOrra Marr
'I 10 IAl 0 UMII0 Lh CL AMLILCAI ION OAILI(AILIDVLLIILLLVIOhllhl IAOIICILOVIAOCAAM
'I Figure 6,g-l Foclllty Oroonlzatl(rn - St, L(tcf(5 Plant, Unit 1 QNLICtksto QrtnhlanS 0/5 IO
1 ~
H
ADMINISTRATIVE CONTROLS COMPOSITION 6.5.2.2 The composition of the CNRB shall be as shown in Appendix A
of the Florida Power 5
Light Topical equality Assurance Report.
The CNRB Chairman shall be designated in writing.
ALTERNATES 6.5.2.3 All alternate members shall be appointed in writing by the CNRB Chairman to serve on a temporary basis;
- however, no more than two alternates shal'I participate as voting members in CNRB activities at any one time.
CONSULTANTS 6.5.2.4 Consultants shall be utilized as determined by the CNRB Chairman to provide expert advice to the CNRB.
MEETING FRE UENCY 6.5.2.5 The CNRB shall meet at least once per calendar quarter during the initial year of facility operation following fuel loading and at least once per six months thereafter.
QUORUM 6.5.2.6 A
quorum of CNRB shall consist of the chairman or his designated alternate and four members including alternates.
No more than a
minority of the quorum shall have line responsibility for oper ation of the facility.
6-9.
2/;6/82
. eo
~0 "e(
"4 P
v
~
I(~
v,kv f
+Pl ~
+
~ >I1 I
VP ~ 1 1
U
~ &I
- lilgl, k
II I~~'~k
~
<<4h W
lt
SAFETY EVALUATION There are no safety related effects connected with the removal of the offsite management and technical support description and organization charts from the Technical Specifications.
The purpose of including these descriptions is for general information of the corporate structure to those in possession of the Technical Specifications.
- However, the same information is also contained in the Florida Power 8 Light Company Topical Quality Assurance report (FPLTQAR).
The FPLTQAR is required to be updated to reflect all changes to the organization which affect quality within 30 days by letter and one year by amendment.
It is our opinion that duplication of material between the two documents is unnecessary and that processing the same change twice is an uneeded burden on the time and manpower resources of both FPL and the NRC.
Should the need arise for information on the organization, the FPLTQAR will be available to the same people who previously would have had the organizational description in the Technical Specificatins.
The non FPL organizations which receive controlled copies of the St.
Lucie Unit 1 Technical Specifications also receive controlled copies of the
- FPLTQAR, with only the Southwest Research Institute (SWRI) and Region II of the NRC receivi ng uncontrolled copies.
SWRI is responsible for supplying our inservice inspection services.
Their use of the Technical Specifications, therefore is limited to the ISI portions.
Organizational questions, should they
- arise, can be handled through their FPL contact.
The other non-FPL receipient of controlled Technical Specifications is the NRC Reactor Project Office of Region II.
The Region is forwarded an uncontrolled copy of the QA Manual, and should the need arise requiring the verification of the organization status, questions could be answered by the Resident Inspector.
In a similar fashion the composition of the CNRB is duplicated in both the Technical Specifications and FPLTQAR.
For the same reasons as stated
- above, we propose to remove the specific composition of the CNRB from the Technical Specifications.
0
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~
~
I II
~ I Ill~-~