ML20202H134
| ML20202H134 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom |
| Issue date: | 07/09/1986 |
| From: | Muller D Office of Nuclear Reactor Regulation |
| To: | Atlantic City Electric Co, Delmarva Power & Light Co, Philadelphia Electric Co, Public Service Electric & Gas Co |
| Shared Package | |
| ML20202H137 | List: |
| References | |
| DPR-44-A-118, DPR-56-A-122 NUDOCS 8607160212 | |
| Download: ML20202H134 (22) | |
Text
__
l gf UNITED STATES y
g NUCLEAR REGULATORY COMMISSION 3
ij WASHINGTON, D. C. 20555
%...../
PHILADELPHIA ELECTRIC COMPANY PUBLIC SERVICE ELECTRIC AND GAS COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-277 PEACH BOTTOM ATOMIC POWER STATION, UNIT N0. 2 AMENDMENT TO FACILITY OPERATING LICENSE i
Amendment No. 118 j
License No. DPR-44
- l 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by Philadelphia Electric Company, et al. (the licensee) dated November 18, 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; j
B.
d, The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the t
Commission; 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 Commission's regulations; I
D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-44 is hereby amended to read as follows:
8607160212 860709 PDR ADOCK 03000277 P
\\\\ -
Technical Specifications The Technical Specifications contained in Appendices t
A and B, as revised through Amendment No.118, are hereby incorporated in the license. PECO shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY.
ISSION M
Daniel R. Muller, Director BWR Project Directorate #2 Division of BWR Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: July 9,1985
,MO 7
(
ATTACHMENT TO LICENSE AMENDMENT N0.118 FACILITY OPERATING LICENSE N0. DPR-44 DOCKET N0. 50-277 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
Remove Insert 243 243 244 244 245 245 246 246 247 247 248 248 254 254 Appendix "B" Technical Specifications 53 53 E
l 6.0 ADMINISTRATIVE CONTROLS 6.1 Responsibility 6.1.1 The Manager - Nuclear Plant shall be responsible for overall facility operation.
In the absence of the Manager - Nuclear Plant, the Superintendent - Operations (or any other person that the Manager - Nuclear Plant may designate in writing) shall assume the Manager's responsibility for overall facility i!
opefation.
]
6.2 Organization
'l l
6.2.1 offsite i
))
The of faite organization for facility management and technical support shall be as shown on Figure 6.2-1.
6.2.2 Facility Staff t
j The facility organization shall be as shown on Figure 6.2-2
[
ano i
a.
Each on-duty shift shall be composed of at least the minimum shift crew composition shown in Figure 6.2-2, except that the shift crew composition may be less than the minimum requirements for a period of time not to-exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence i
of on-duty shift crew members provided immediate action is taken to restore the shift crew composition to within the 2
minimum requirements.
1 l-b.
At least one licensed operator shall be in the control A
room and assigned to each reactor that contains fuel.
At least two licensed operators, excluding the operator on c.
the second unit, shall be present in the control roca during reactor startup, scheduled reactor shutdown and during recovery from reactor trips.
d.
An individual qualified in radiation protection procedures shall be onsite when fuel is in the reacto'r.
s t
All CORE ALTERATIONS shall be directly supervised by e.
either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibility during this operation.
f.
A Fire Brigade of at least 5 members shall be maintained onsite at all times.
The Fire Brigade shall not include the minimum shift crew necessary for safe shutdown of the unit (s) (3 members) or any personnel required for other essential functions during a fire emergency.
Amendment!o. 39,59, 118 g
g_
,g, g y 966
- MW*
,,w r,_.,.
.y.-
---e
---..-_.rm_
-m y
_,----.m
. --, ---- --,.p
-w.y--
m
.--w
- - - --q.yy
E a
i j
h g
80ARD OF DIRECTORS e
6.
l CHAIRMAN OF THE 80ARO 8 1
i d
CHIEF EXECUTIVE OFFICER m
l PRESIDENT 8
^
CHIEF OPERATING OFFICER I
h A
NUCLEAR g
ELECTRIC HUCLEAR PRODUCTION POWER REVIEW 9
SR. VICE PRESIDENT VICE PRESIDENT BOARO i
NUCLEAR PRODUCTION MANAGER i
I I
I OUALITY ASSURANCE NUCLEAR GENERATION DIVISION OIVISION i
SUPERINTENDENT f SUPERINTENDENT REPORTING RESPONSIBILITY A CHIEF EXECUTIVE OFFICER l
l ll O CHIEF OPERATING OFFICER SUPT.
MANAGER NUCLEAR SERVICES NUCLEAR PLANT I
f RESPONSISLE FOR OVERALL FIRE PROTECTION PROGRAW j
MANAGEMENT ORGANIZATION CHART PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION - UNITS 2 AND 3 FIGURE 8.2-1
c tE seg a
gh l
sgsa sas s
s p
E 3"
I 5 5 l! il, iillidil!!!!
di F
F F
4ga
-g ggg l
gg t= II!
t=
8!
t
!B 4 3
s lEs is
- u
-a a,In g_
3.h
=
-5 3E I
su
$uj !
5
[j o5 h
E s
ll$
I
no 7
lNS E
I 3 - 5:
!"g ll-! lll-! I!l-!. gi.lg I I
=I g g I
a ll!gllll i
l
'll-ll!-!,_gs
.li I, il l
~
i i
i l..a,.E.~.
I 8a a
1 us t11 lui i
sl$
~
i
~
/cenonent No. E,M,67, b b b b.,,,,
74,94, 118
PSAPS 6.3 Facility Staff Qualification 6.3.1 Each member of tne facility staff shall meet or uxceed the minimum qualifications 'of ANSI N18.1 - 1971 for comparable positions, except for (1) Senior Health Physicist (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 Fegree 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 Manager - Nuclear Plant and shall meet the requirements of Section 5.5 of ANSI N18.1-1971 and 10 CFR 55, Appendix A.
6.4.2 A training program for the Fire Brigade shall be conducted such that Fire Brigade members complete an instruction program within a two year period.
Regularly planned meetings will be held every 3 months.
6.5 Review and Audit 6.5.1 Plant Operation Review Committee (PORC)
Function 6.5.1.1 The Plant Operation Review Committee shall function to advise the Manager - Nuclear Plant on all matters related to nuclear. safety.
Composition 6.5.1.2 The Plant Operation Review Committee shall be composed
[
of the:
i i
Manager - Nuclear Plant (Chairman)
Operations Engineer r
' Superintendent - Operations Outage Planning Engineer Superintendent - Plant Services Senior Health Physicist Technical Engineer
,3enior Chemist Maintenance Engineer Shift Superintendent Alternates 6.5.1.3 Alternate members shall be appointed in writing by the PORC Chairman to serve on a temporary basist however, no more than two alternate members shall be used to satisfy a PORC quorum (See 6.5.1.5).
-246-Icendcent No. 27,39,67,73,96,118
PBAPS Meeting Frequency 6.5.1.4 The PORC shall meet at least once per calendar month and as convened by the PORC Chairman or his designated
- - alternate (s).
Quorum 6.5.1.5 A quorum of the PORC necessary for the performance of
[
the PORC responsibilities and authority provisions of these Technical Specifications shall consist of the Chairman or his designated alternate (s) and four members or their alternates.
"o Responsibilities
!i 6.5.1.6 The Plant Operation Review Committee shall be 4
[
responsible for 1
a.
Review of 1) all procedures required by g
Specification 6.8 and changes thereto, 2) any other proposed procedures or changes thereto as i
determined by Manager - Nuclear Plant to af fect nuclear safety.
b.
Review of all proposed tests and experiments that affeet nuclear safety.
a
?
-Review of all proposed changes to the Technical c.
. Specifications.
d.
Review of all proposed changes or modifications to plant systems or equipment that af fact
~
2 nuclear safety.
Investigation of all violations of the Technical e.
Specifications and shall prepare and forward a report covering evaluation and recommendations to prevent recurrence to the Superintendent, Nuclear Generation Division, and the Chairman of the Nuclear Review Board.
f.
Review of facility operations to detect potential safety hazards.
g.
Performance of special reviews and investigations and reports thereon as requested by the Chairman of the Nuclear Review Board.
h.
Review of all reportable events required by 10 j
CFR 50.73.
-247-Amendment No. D,37,JH,118 1
l.-
~ _ - _ _
PBAPS 6.5.1.6 Continued Review of the Plant Security Plan and implementing procedures, and shall submit recommended changes to the h.
Plan to the Chairman of the Nuclear Review Board.
I Review of the Emergency Plan and implementing procedures, and shall submit recommended changes to the i.
Plan to the Chairman of the Nuclear Review Board.
Review of every unplanned release reportable under 6.9.2.b. (5) of radioactive material to the environs j.
evaluate the events specify remedial action to prevent recurrencer and document the event description, evaluation, and corrective action and the disposition of the corrective action in the plant records.
Authority The Plant Operation Review Committee shall 6.5.1.7 Recommend to the Manager - Nuclear Plant, written approval or disapproval of items considered under a.
6.5.1.6(a) through (d) above.
Render determinations in writing with regard to whether or not each item considered under 6.5.1.6(a) through (e) b.
above constitutes an unreviewed safety question, as defined in 10 CFR 50.59.
Provide immediate written notification to the i
c.
Superintendent, Nuclear Generation Division, or in his L
absence, the Superintendent, Nuclear Services, and the Nuclear Review Board of disagreement between the PORC and the Manager - Nuclear Plant; however, the Manager-Nuclear Plant shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above.
!:i l
-248-1 j
Amendment i'o. 19,37.62,M2,JH,' 118 e
--,.._,..m
._,._,,,,m.
_ _,,. _. _,,. -.,__*,,,., _.,,.,,p.,
y.w.-,...,.,,,.,m,..
PBAPS Each procedure and administrative policy of 6.8.1 above, 6.8.2 and changes thereto, shall be reviewed by the PORC and approved by the Station Superintendent or his designated alternate per Specification 6.1.1 prior to implementation and periodically as., set forth in administrative procedures.
i' Temporary changes to procedures of 6.8.1 above may be 6.8.3 made, provided:
The intent of the original procedure is not a.
alt ered.
b.
The change is approved by two members of the plant management staf f, at least one of whom holds a Senior Reactor Operator's License on the unit af fe cted.
The change is documented, reviewed by the PORC and c.
approved by the Manager - Nuclear Plant within 14 days of implementation.
6.8.4 Written procedures shall be established, implemented and maintained covering the activities of the radiological ef fluent technical specifications as referenced belows Offsite Dose Calculation Manual a.
b.
Quality Assurance Program for the environmental monitoring using the guidance in Regulatory Guide 4.1, Revision 1, April 1975.
t 6.9 Reporting Requirements In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following identified reports shall he submitted to the Administrator of the appropriate Regional Office unless otherwise noted.
-254-Amendaent No. 72,37,47,702, 118 e
+
o
_ lj T
RW N
A O
N A
E E
R O
RL I
L A
I EP V
C O S
G E
U B
I l
AR s
R N
V NA I
AE O
f MLC N
T U
O N
N I
E T
D E
A N
R E
E T
S 3
N N
E E
I C
D G
R I
N E
V A
R P
R T
A U
.E T
2 N
E S
S N
E N
L P
l U
S CO D
O C
R R
II I
I R
U S
T A
A T T I
RT S
T E
N E
TC E
C G
L R N N E
I L
I A A U
CU R
U A
C C
ED P
D N
U H P O
A N
C M U
8R R
LO N
ER E
R M
O l
E E
P C
P N C N DC C
S O
O RI I
I R
AF F
V E
I C I
1 O
OF F
C T I T
T T
BO 8O g
N A R A
1 C
N A
Z T T
E E
EE TG R
I C S 7 N
D R
HV NN U
N E O
N I
I S
A L R E TI EI D
I E
l T
DT S
G E E S
T R
A R
W F
OC SR O A O I
N U
V I
O O
E EE Y
I P I
R I
NX RP T
T H F
D AE PO O
E I
N P C R
M P
E L I L
U M E M A
RF F
A 1-O IE E
U E D O S
B AI I
T O
G A T
l HH H
N A L A CC C
E N I D
A H M I
M P O S
T R
E T
AR 0
R EE P
0
. LW CO E
H UP C
C N
I A
V E
P A
R R R LM S
I I RG I
F F EO L
F F VR I
O O OP B
I E G RN S
V N OO N
I I FI O
T T T
P U A EC S
C R LE E
E E BT R
X P IO G
E O SR NP N
FFO I
E E PE T
I I SR R
H H EI O
C C RF P
ig' E
3,6
=?
R AS8 l
I
, i
\\!l
- !!lj' i'.ili;I
+f Utu A UNITED STATES
[
p, NUCLEAR REGULATORY COMMISSION 5
- j WASHINGTON, D. C. 20555
\\...../
PHILADELPHIA ELECTRIC COMPANY PUBLIC SERVICE ELECTRIC AND GAS COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET N0. 50-278 PEACH BOTTOM ATOMIC POWER STATION, UNIT N0. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 122 License No. DPR-56 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Philadelphia Electric Company, et al. (the licensee) dated November 18, 1985, complies with tha standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Comission's rules and regulations set forth in 10 CFR
,i Chapter I; I
- j B.
The facility will operate in conformity with the application, L
the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted j
in compliance with the Commission's regulations; j
D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the i
public; and
~
The issuance of this amendment is in accordance with 10 CFR Part 51 E.
of the Commission's regulations innd'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-56 is hereby amended to read as follows:
-2 Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.122, are hereby incorporated in the license. PECO shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance.
OR THE NUCLEAR REGULATORY 0 ISSION f
A
^----
<g Daniel R. Muller, Director BWR Project Directorate #2 Division of BWR Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: July 9,1986
~
1
_,_.-_l
l ATTACHMENT TO LICENSE AMENDMENT NO.122 FACILITY OPERATING LICENSE N0. DPR-56 DOCKET N0. 50-278 1
Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by Amendment i
4 number and contain vertical lines indicating the area of change.
Remove Insert i
243 243 244 244 245 245 246 246 247 247 248 248 254 254 Appendix "B" Technical Specifications 53 53 i
.-,--n.-
.-..,n.,,
L' PBAPS 6.0 ADMINISTRATIVE CONTROLS 6.1 Responsibility
?
6.1.1 The Manager - Nuclear Plant shall be responsible for overall 1
facility operation.
In the absence of the Manager - Nuclear Plant, the Superintendent - Operations (or any other person that the Manager - Nuclear Plant may designate in writing) shall assume the Manager's responsibility for overall facility operation.
6.2 Organization l
I 6.2.1 offsite
- 1 The of fsite organization for facility management and technical I
support shall be as shown on Figure 6.2-1.
6.2.2 Facility Staf f t
!l The facility organization shall be as shown on Figure 6.2-2
- l and
't a.
Each on-duty shift shall be composed of at least the minimum shift crew composition shown in Figure 6.2-2, except that the shift crew composition may be less than the minimum requirements for a period of time not to-exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence i
of on-duty shift crew members provided immediate action is
- [
taken to restore the shift crew composition to within the
]
minimum requirements.
b.
At least one licensed operator shall be in the control j'
~
room and assigned to each reactor that contains fuel.
At least two licensed operators, excluding the operator on c.
the second unit, shall be present in the control room during reactor startup, scheduled reactor shutdown and i
i during recovery from reactor trips.
d.
An individual qualified in radiation protection procedures shall be onsite when fuel is in the reacto'r.
5 l
e.
All CORE ALTERATIONS shall be directly supervised by
/
either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibility during this operation.
f.
A Fire Brigade of at least 5 members shall be maintained onsite at all times.
The Fire Brigade shall not include the minimum shift crew necessary for safe shutdown of the unit (s) (3 members) or any personnel required for other essential functions during a fire emergency.
~
Amendment ! o. 39,6P,122
L-~.-
E i
m Ra BOARD OF OIRECTORS Fi l
M CHAIRMAN OF THE BOARO 8 CHIEF EXECUTIVE OFFICER N
PRESIDENT 8 CHIEF OPERATING OFFICER I
O A
NUCLEAR g
ELECTRIC NUCLEAR E
POWER PRODUCTION REVIEW SR. VICE PRESIDENT VICE PRESIDENT BOARO l
I
)
NUCLEAR PRODUCTION MANAGER l
a u
QUALITY ASSURANCE NUCLEAR CENERATION DIVISION DIVISION SUPERINTENDENT f SUPERINTENDENT j
REPORTINS RESPONSIBILITY i
A CHIEF EXECUTIVE OFFICER l
l 1
O CHIEF OPERATINO OFFICER
- Supt, MANAGER
{
f RESPONSIBLE FOR OVERALL NUCLEAR SERVICES NUCLEAR PLANT l
i MANAGEMENT ORCANIZATION CHART PHILADELPHTA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION - UNITS 2 AND 3 i
FIGURE 8.2-1 i
i
---e i
L'.
s t;- l ggg
,l g
gh sgsa sa s s
s I'
illl!lil!!!!
d5
~
F M
R
\\
g o
s w=8
.s g ll!
g l!
8 t
i ij_
q[g 8
8 8
's s
3 g
l*
ll ij s
h ':
n llg I
ssu 9?
gga t
o l
.~
_h ll-5 lll-511l-5 i l g
E
.i lg I9 R
.I li ili IsI,11 in I g W I ii I
8 Eg8 5
ag, as e
n 3
8 E
Ell lR
- sg
.,, e g, g g,
- g E-23 l"ggIis llg g1.
til
~
8888 ineneent no. n.u.n, n,n,122
j l
PSAPS I
h.
6.3 Facility Staff Qualification l
6.3.1 Each member of tne f acility staff shall meet or exceed the minimum qualifications 'of ANSI N18.1 - 1971 for comparable positions, except for (1) Senior Health Physicist (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 6egree 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 staf f shall be maintained under the direction of the Manager - Nuclear Plant and shall meet the requirements of Section 5.5 of ANSI N18.1-1971 and 10 CFR 55, Appendix A.
6.4.2 A training program for the Fire Brigade shall be conducted such that Fire Brigade members complete an instruction program within a two year period.
Regularly i
I planned sieetings will be held every 3 months.
6.5 Review and Audit 6.5.1 Plant Operation Review Committee (PORC)
Function 6.5.1.1 The Plant Operation Review Committee shall function to advise the Manager - Nuclear Plant on all matters i
related to nuclear safety.
i
[
Composition 6.5.1.2 The Plant Operation Review Committee shall be composed of ther i
Manager - Nuclear Plant (Chairman)
Operations Engineer
~
~ Superintendent - Operations Outage Planning Engineer Superintendent - Plant Services Senior Health Physicist Technical Engineer
. Senior Cheraist Maintenance Engineer Shift Superintendent l
1 l
1 Alternates
~
6.5.1.3 Alternate members shall be appointed in writing by the PORC Chairman to serve on a temporary basist however, no j
more than two alternate members shall be used to satisfy a PORC quorum (see 6.5.1.5).
~
~
Araendment I:o. 27,39,H,74,95,122
d..
PBAPS c.
Meeting Frequency 6.5.1.4 The PORC shall meet at least once per calendar month and as convened by the PORC Chairman or his designated
- - alternate (s).
u.
Quorum 6.5.1.5 A quorum of the PORC necessary for the performance of
[
the PORC responsibilities and authority provisions of these Technical Specifications shall consist of the Chairman or his designated alternate (s) and four members or their alternates.
Responsibilities
.i 6.5.1.6 The Plant Operation Review Committee shall be responsible fors I
f a.
Review of 1) all procedures required by Specification 6.8 and changes thereto, 2) any 4
other proposed procedures or changes thereto as r
determined by Manager - Nuclear Plant to af fect nuclear safety.
o I
b.
Review of all proposed tests and experiments j
that af fect nuclear safety.
I c.
Review of all proposed changes to the Technical j
Specifications.
d.
Review of all proposed changes or modifications to plant systems or equipment that af fect nuclear safety.
e.
Investigation of all violations of the Technical Specifications and shall prepara and forward a report covering evaluation and recommendations
~
to prevent recurrence to the Superintendent, Nuclear Generation Division, and the Chairman of the Nuclear Review Board.
f.
Review of, facility operations to detect potential safety hazards.
g.
Performance of special reviews and investigations and reports thereon as requested by the Chairman of the Nuclear Review Board.
h.
Review of' all reportable events required by 10 CFR 50.73.
/mendaent lio.19,37,J4 122
-247-
'c
~
PBAPS 6.5.1.6 Continued h.
Review of the Plant Security Plan and implementing procedures, and shall submit recommended changes to the
. Plan to the Chairman of the Nuclear Review Board.
- i. UReview of the Emergency Plan and implementing procedures, and shall submit recommended changes to the Plan to the Chairman of the Nuclear Review Board.
j.
Review of every unplanned release reportable under 6.9.2.b. (5) of radioactive material to the environs:
evaluate the events specify remedial action to prevent recurrencer and document the event description, evaluation, and corrective action and the disposition of the corrective action in the Plant records.
9 i
j Au'thority s
r I
6.5.1.7 The Plant Operation Review Committee shall 1
a.
Recommend to the Manager - Nuclear Plant, written l
il approval or disapproval of items considered under f
6.5.1.6(a) through (d) above.
ll
'b.
Render determinations in writing with regard to whether or not each item considered under 6.5.1.6(a) through (e) above constitutes an unreviewed safety question, as defined in 10 CFR 50.59.
il c.
Provide immediate written notification to the
'5 Superintendent, Nuclear Generation Division, or in his absence, the Superintendent, Nuclear Services, and the Nuclear Review Board of disagreement between the PORC and the Manager - Nuclear Plant; however, the Manager-Nuclear Plant shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above.
I i
-248-Atenc: cent No. W,37,82 JM,JJB,122
PBAPS 6.8.2 Each procedure and administrative policy of 6.8.1 above, and changes thereto, shall be reviewed by the PORC and approved by the Station Superintendent or his designated alternate per Specification 6.1.1 prior to implementation and periodically as., set forth in administrative procedures.
6.8.3 Temporary changes to procedures of 6.8.1 above may be made, provided:
a.
The intent of the original procedure is not altered.
b.
The change is approved by two members of the plant management staf f, at least one of whom holds a Senior Reactor Operator's License on the unit af fe cted.
c.
The change is documented, reviewed by the PORC and approved by the Manager - Nuclear Plant within 14
' days of implementation.
6.8.4 Written procedures shall be established, implemented and maintained covering the activities of the radiological
~
~
effluent technical specifications as referenced belows a.
Offsite Dose Calculation Manual
'~
b.
Quality Assurance Program for the environmental l
monitoring using the guidance in Regulatory Guide 4.1, Revision 1, April 1975.
6.9 Reporting Requirements In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following identified reports shall be submitted to the Mministrator of the appropriate Regional Office unless otherwise noted.
-254-Atencinent No. 70,37,#7,J0/,122
^ ~ ~ ~ -
t if 59 BOARO OF DIRECTORS t.
~
CHAIRMAN OF THE BOARD 8 CHIEF EXECUTIVE OFFICER PRESIDENT 1 CHIEF OPERATING OFFICER I
i ELECTRIC NUCLEAR A
NUCLEAR g
PRODUCTION i
POWER REVIEW g
VICE PRESIDENT BOARO SR. VICE PRESIDENT i
I NUCLEAR PRODUCTION MANAGER I
I n
OUALITY ASSURANCE NUCLEAR GENERATION DIVISION DIVISION SUPERINTENDENT f SUPERINTENDENT REPORTINC RESPONSI81LITT j
& CHIEF EXECUTIVE OFFICER l
l l
O CHIEF OPERATINC OFFICER SUPT.
MANAGER NUCLEAR SERVICES NUCLEAR PLANT l
9 RESPONSI8tE FOR OVERALL FIRE PROTECTION PROGRAM j
MANAGEMENT ORGANIZATION CHART l
PHILADELPHIA ELECTRIC COMPANY j
2 PEACH BOTTOM ATOMIC POWER STATION - UNITS 2 ANO 3 k
FICURE 7.1-1
{
2
- - - - - - -