ML20064A136
| ML20064A136 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 08/20/1990 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20064A137 | List: |
| References | |
| GL-88-06, GL-88-6, NUDOCS 9008270089 | |
| Download: ML20064A136 (23) | |
Text
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- ps nea pf UNITED STATES
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NUCLEAR REGULATORY COMMISSION 7.
j WASHINGTON, D. C. 20555
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PHILADELPWIA. ELECTRIC.CONPANY PUBL I r.. sE RVI CE. ELE 6 mI r,. AND. EA5. COMPANY DE,MARVA POWER ANll.IENT. COMPANY AFLANTIC.CITT EL[G RIC COMPANY DOCKET NO.-50 277 PEACH.BOTTON. ATONIC. POWER. STATION.. UNIT WO. -2 ANENDNENT.TO.FACTLITY.0PERATING.LICEMSE Amendment No.155 License No. DPR-44 1.
The Nuclear Regulatory Comission (the Comissfon) has found that:
~
A.
The application for amendment by Philadelphia Electric Company, et al. (the licensee) dated July 11,1989 as supplemented on April 20, 1990, complies with the 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 Chapter I.
B.
The facility will_ operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Connission; I
C.
Thereisreasonableassurance(1)thattheactivitiesauthorizedby this amendment can be conducted without endanpring 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 or safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of l
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:
4 9008270089 900820 AliOCK 0500g7 DR
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. (2)
Technical r ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.155, are hereby incorporated in the license. PECO shall operate the facility in accordance with the Technical Specifications.
3.
This licenso amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/s/
Walter R. Butler, Director Project Directorate 1-2 Division of Reactor Projects - 1/11
Attachment:
Changes to the Technical Specifications Date of Issuance:
August 20, 1990 a
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Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 155, are hereby incorporated in the license. PEC0 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 COMMISSION
(.'El ofbG Walter R. Butler, Director Project Directorate 1-2 Division of Reactor Projects - I/II
Attachment:
Changes to the Technical Specifications Date of Issuance: August 20, 1990 l
l
ATTACHMENT.TO. LICENSE AMENDMENT.NO.155 FACILITY OPERATiflG LICENSE.NO. DPR-44 i
DOCKET N0. 50-277 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.
Remove Insert iva iva vii vii 243 243 244 244 245 245 245a 245a 246 246 252 252 b
I a
p l
Unit 2
'a PBAPS-LIST OF FIGURES,
i Fioure Title g
3.5.1.1 DELETED 142g 3.5.1.J DELETED 142g
- 3. 5.1. K DELETED 142g
- 3. 5.1. L DELETED 142g
- 3. 5.1. M DELETED 142g 3.5.1.N DELETED 142g 3.5.1.0 DELETED 142g 3.6.1 Minimum Temperature for Pressure Tests 164 such_as required by Section XI 3.6.2 Minimum Temperature for Mechanical Heatup 164a of Cooldown following Nuclear Shutdown 3.6.3 Minimum Temperature for Core Operation 164b 4
(Criticality) 3.6.4 Deleted 164c 3.6.5 Thermal Power and Core Flow Limits 164d 3.8.1 Site Boundary and Effluent Release Points 216e 6.2-1 Deleted 6.2 Deleted
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Amendment No. 86,102,123,150,15&.155 -iva-t c, i
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4 4-t 44-1g t..o
'aa b I
PBAPS UNIT 2 LIST OF TABLES Table Title Page 4.8.3.c Maximum Values for Minimum Detectable 216d-6 Levels of Activity 3.14.C.I Fire Detectors 240m 3.15 Seismic Monitoring Instrumentation 240u 3.15 Seismic Monitoring Instrumentation Surveillance 240v Requirements 6.2.1' Shift Crew Composition - Minimum
-245 Requirements l
i Amendment No. 102, 105, 197 155
-vij.
1 r
PBAPS I
6.0 ADMINISTRATIVE CONTROLS 6.1 Responsibility S. l.1 The Plant Manager shall be responsible for overall facility operation.
In the absence of the Plant Manager, the Superintendent - Operations (or i
any other person that the Plant Manager may designate in writing) shall j
assume the Manager's responsibility for overall facility operation.
6.1.2 The Shif t Supervisor (or, during his absence from the control room, a 1
designated individual) shall be responsible for the control room command I
function.
A management directive to this effect, signed by the Vice President, Peach Bottom Atomic Power Station shall be reissued to all station personnel on an annual basis.
6.2 Organization 6.2.1 Offsite and Onsite Organizations Onsite and offsite organizations shall be established for unit operation and corporate management, respectively.
The onsite and offsite organiza-tions shall include the positions for activities affecting the safety of the nuclear power plant.
a.
Lines of authority, responsibility, and communication shall be established and defined for the highest management levels through intermediato levels to and including all operating organization positions.
These relationships shall be documented and updated, as appropriate, in the form of organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equiva-lent forms of documentation.
These requirements shall be documented in the Peach Bottom Quality Assurance Plan.
b.
The Plant Manager shall be responsible for overall unit safe operation and shall have control over those onsite activities necessary for safe operation and maintenance of the plant.
c.
The Vice President, Peach Bottom Atomic Power Station shall have l
corporate responsibility for overall piant nuclear safety and i
shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety, d.
The individuals who train the operating staff and those who carry out health physics and quality assurance functions may report to-the appropriate onsite manager; however, they shall have suffi-cient organizational freedom to ensure their independence from operating pressures.
j.
Amendment No. 39, 69. IIS, Z37,155
-243-
PBAPS Continued 6.2.2 Facility Staff The facility organization shall be subject to the following:
a.
Each on-duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2.1, except that the shift crew l
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 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 room and assigned to each reactor that contains fuel.
c.
At least two licensed operators, excluding the operator on the second unit, shall be present in the control room 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 reactor.
All CORE ALTERATIONS shall be directly supervised by either a e.
licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent respon-sibility 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.
g.
In addition to the requirements of 6.2.2.a. the following shall hold a senior reactor operator license:
- 1) Plant Manager or Superintendent-Operations, 2) Assistant Superintendent-Operations and 3) Superintendent-Technical or Engineer-Systems.
1 Amendment No. 37, 67, IIS,132,155
-244-
Table 6.2.1 Shift Crew Composition - Minin.um Requirements One or Both Units Operating *: 1 Shift Manager (SRO) 1 Shift Supervisor (SRO) 3 Reactor Operators (RO) 5 Operators 1 Shift Technical Advisor Both Units not Operating
- 1 Shift Manager or Shift Supervisor (SRO) 2 Reactor Operators (RO) 5 Operators SRO - NRC licensed senior reactor operator R0 - NRC licensed reactor operator
- For the purpose of this table, a unit is considered not to be operating when it is-in a Cold Condition with the reactor mode switch in shutdown or refuel.
P b
Amendment No. 10, 39, 67, 74, 9$,
-245-JJ8, 126, 132, 155
- I e
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This page intentionally left blank.
A l.
1.
l l
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l 1
l 1,
Arnendment No, 132. 155
-245a-
PBAPS l
6.3 Facility Staff Qualifications I
6.3.1 Each member of the facility 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 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 i
6.4.1 A retraining and replacement training program for the facility staff shall be maintained under the direction of the Superintendent-Training and shall nivet 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 int,truction program within a two year period.
Regularly planned meetings will be held every 3 months.
l 6.5 Review and Audit 6.5.1 Plant Operations Review Committee (PORC) 6.5.1.1 Function The Plant Operations Review Committee shall function to advise the Plant Manager on all matters related to nuclear safety.
l 6.5.1.2 Composition The Plant Operations Review Committee shall be composed of the:
Superintendent - Operations (Chairman)
Superintendent - Technical Superintendent - Maintenance / Instrumentation and Controls Superintendent - Plant Services Assistant Superintendent - Operations Maintenance Engineer Engineer-Systems Regulatory Engineer Shift Manager 6.5.1.3 Alternates Alternate members shall be appointed in writing by the PORC Chairman to 4
serve on a temporary basis; however, no more than two alternate members shall be used to. satisfy a PORC quorum (See 6.5.1.5).
Amendment No. 27, 39, 6I, 73, 96'
-246-IIS, I32, 155 a
PBAPS 6.5.2.8 Continued The Facility Emergency Plan and implementing procedures at e.-
least once per year.
f.
The Facility Security Plan and implementing procedures at least once per two years, g.
The Offsite Dose Calculation Manuai and implementing procedures at least once per two years, j
h.
The performance of activities required by the Quality Assurance Program'regarding the radiological monitoring.
program to meet the provisions of Regulatory Guide 4.1,-
Revision 1, April 1975., at least once per calendar year.
1.
Any other area of facility operation considered appropriate by the NRB or the Executive Vice President - Nuclear.
Authority 6.5.2.9 The NRB shall report to and advise the Executive Vice President -
Nuclear on those areas of responsibility specified in Section l
6.5.2.7 and 6.5.2.8.
Records 6.5.2.10 Records of NRB activities shall be prepared, approved and distributed as indicated below:
Minutes of each NRB meeting shall be prepared, approved and a.
forwarded to the Executive Vice President - Nuclear within 10 working days following each meeting, b.
Reports of reviews encompassed by Section 6.5.2.7.e, f, g and h above shall be prepared, approved and forwarded;to the Executive Vice President - Nuclear, within 10 working days following completion of the review.
Amendment No. 22, 37, 102, III, 114,
-252-132.'155
. [f'ps ttoy%,
+
UNITF0 STATES 1
-g NUCLEAR RFGULATORY COMMISSION j
WASHINGTON, D, C. 20655
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PHILADELPHIA. ELECTRIC. COMPANY PUBLIC.5ERVICE ELEGINIC AND-GA5 C0plPANY DELMARVA-POWER-AND-LIGHT GOM @ t ~
ATLANTIC CITY. ELECTRIC COMPANY DOCKET NO.-50-278 PEACH. BOTTOM. ATOMIC POWER STATION. UNIT.NO. 3 AMENDMENT-TO FACILITY OPERATING LICENSE Amendment No.
157 License No. DPR-56 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The ap111 cation for amendment by Philadelphia Electric Company, et al. (tie licensee) dated July 11, 1989 as supplemented on April 20, 1990, complies with the 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 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.
Thereisreasonableassurance(i)thattheactivitiesauthorizedby 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 common defense and security or to the health or safety of the public; and E.
The issuance of this anendment 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-56 is hereby amended to read as follows:
~l
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L
-?-
(2)
Technical Specifications The Technical Specificationi contained in Appendices A and B, as revised through Amendment No.157, are hereby incorporated in the license. PECO shall opera'te the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/s/
Walter R. Butler, Director Project Directorate I-2 Division of Reactor Projects - 1/II
Attachment:
Changes to the Technical Specifications Date of Issuance: August 20, 1990 I
A' PDI-2 MQ OG PDI-2/D 1
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WButler / q 90 7/(q/ )
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(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.157, 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 COMMISSION o C Walter R. Butler, Director Project Directorate 1-2 Division of Reactor Projects - 1/11
Attachment:
Changes to the Technical Specifications Date of Issuance:
August 20, 1990
ATTACHMENT TO LICENSE AMEN 0 MENT NO.157 FACILITY OPERATING LICENSE NO. DPR-56 DOCKET NO. 50-278 Replace the following pages of tne Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.
Remove Insert iv iv iva vii vii 243 243 244 244
.245 245 245a 245a 246 246 252 252
'Ficure Title h
-1.1-1 APRM Flow Bias Scram Relationship to Normal Ope' rating.
16 Conditions 4.1.1 Instrument Test' Interval Determination Curves 55 4.2.2 Probability of System Unavailability vs. Test Interval 98 3.3.1' SRM Count Rate vs. Signal-to-Noise Ratio 103a 3.4.1 DELETED 122 3.4.2 DELETED 123 3.5.K.1 DELETED 142 3.5.K.2 DELETED 142 3.5.1.A DELETED 3.5.1.5 DELETED
- 3. 5.1. C DELETED 3.5.1.0 DELETED 3.5.1.E DELETED 142
- 3. 5.1. F DELETED 142 3.5.1.G DELETED 142 3.5.1.H DELETED
, 142 3.5.1.I DELETED 142 3.5.1.J DELETED 142
- 3. 5.1. K DELETED 142 3.6.1
- Minimum Temperature for Pressure Tests such as required 164 by Section XI 3.6.2 Minimus Temperature for Mechanical Heatup or Cooldown 164a following Nuclear Shutdown 3.6.3 Minimum Temperature for Core Operation (Criticality) 164b 3.6.4 Transition Temperature Shift vs. Fluence 164c 3.6.5 Thermal Power Limits of Specifications 3.6.F.3, 3.6.F.4, 164d 3.6.F.5, 3.6.F.6 and 3.6.F.7
- 3. B.1-Site Boundary and Effluent Release Points 216e 6.2-1 DELETED 6.2-2 DELETED Amendment No.
I#, #I, #5, #6, iv-87, 79, 97, IO#, 197, II#, 126, 242,. 150, 155, 157
PBAPS UNIT 3 LIST OF TABLES Table Title pg 4.8.3.c Maximum Values for Minimum Detectable 216d-6 Levels of-Activity 3.14.C.1 Fire Detectors 240m-3.15 Seismic Monitoring Instrumentation 240u 4.15 Seismic Monitoring Instrumentation Surveillance 240v Requirements 6.2.1 Shift Crew Composition - Minimum 245 Requirements si
)
Amendment No.104, IOS, III,157
.yjj.
1
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PBAPS i 6.0' ADMINISTRATIVE CONTROLS 6.1 Responsibility 6.1.1 The Plant Manager shall be responsible for overall facility operation.
In the absence of the Plant Manager, the Superintendent - Operations (or
-any other person that the. Plant Manager may designate in writing) shall assume the Manager's responsibility for overall facility operation.
6.1. 2 The JShif t Supervisor (or, during his absence from the control room, a
~
designated individual) shall be responsible for the control room command
- function, A' management directive to this'effect, signed by le Vice-President, Peach Bottom Atomic Power Station shall be reissued to all station personnel.on an annual basis.
6.2 Organization 6.2.1 Offsite and Onsite Oraanizations Onsite and offsite organizations shall be established for unit operation and corporate management, respectively.
The onsite and offsite organiza-tions shall include the positions for activities affecting the safety of the nuclear power plant.
a.
Lines of authority, responsibility, and communication shall be establisned and defined for the highest management levels through intermediate levels to and including -all operating organization positions.
These relationships shall be documented and 'Jpdated, as appropriate, in the form of organization charts, functional descriptions of departmental responsibilities and relationships, and' job descriptions for key personnel positions, or in equiva-lent forms of documentation.
These requirements shall be documented in the Peach Bottom Quality Assurance Plan, b.
The Plant Manager shall be responsible for overall unit safe operation and shall have control over those onsite activities-necessary for safe operation and maintenance of the plant, c.
The Vice President, Peach Bottom Atomic Power Station shall have corporate responsibility for overall plant-nuclear safety ana shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety.
d.
The individuals who train the operating staff and those who carry out health physics and quality assurance functions may report to the appropriate onsite manager; however, they shall have suffi-cient organizational freedom to ensure their independence from operating pressures.
l l
l Amendment No. 29, BS, I22, 135, 157 243-
= -
?E-.
" Continued.
6.2.2'
< Facility Staff
~
The facility organization shall be subject to the following:
Each on-duty shift shall be composed of at.aW, the mMmum shift a.
c ew composition shown in Table 6.2.1, ed.ce. < an the
.,1f t crew composition may be less than the minimum recuiram ts for a period l 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 tc acct u w.te unexpected absence of on-duty shift crew members provided..ted-l ate action-is taken to restore the shift crew = composition i.o wit.11n the minimum requirements.-
a b.
At least one licensed operator shall be in the centrol room and assigned to each. reactor that containa fuel.
At least two licensed operators,' excluding the operator on the c.
second unit,.shall be present in the' control room during reactor i
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 reactor.
All CORE ALTERATIONS shall'be directly supervised by either a e.
licensed Senior Reactor Operator or. Senior Reactor Operator Limited to Fuel Handling.who has no other concurrent respon-sibility 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 l-shift crew necessary for safe shutdown of the unit (s) (3 members) or any personnel required for other essential functions during a fire emergency.
g.
In addition to the requirements of 6.2.2.a, the following shall hold a senior reactor operator license:
- 1) Plant Manager or i
Superintendent-0perations', 2) Assistant Superintendent-Operations and 3) Superintendent-Technical or Engineer-Systems.
ll l
t' l
Amendment No. 29, 6S,122,135,157
-244-
'l
+4
s h
P Table 6.2.1 i
l Shift Crew Composition - Minimum Requirements E
One or Both Units Operating *: 1 Shift Manager (SRO)-
i
.1 Shift Supervisor (SRO) 3 Reactor Operators (RO) 5 Cperators l'
1 Shift Technical Advisor Both Units not Operating
SR0 - NRC licensed senior reactor operator
'R0 - NRC licensed reactor' operator
- For the purpose of this table, a unit:is considered not to be operating when it is in a Cold Condition with the reactor mode switch in shutdown or refuel, l-i l'
l Amendment No. 10, 29, 61, 73, 96,
-245-122, 129.-13E, 157 l
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This-page intentionally left blank, s
1 e-Amendment No. 135, 157
-245a-
PBAPS F*
6.3 Facility Staff ~ Qualifications 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of. ANSI N18.1-- 1971 for enmparable 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 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 Trainino 6.4.1 A retraining and replacement training program for.the facility staff shall be maintained under the direction of the Superintendent-Training
.and'shdll 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 Operations Review Committee (PORC) 6.5.1.1 Function The Plant Operations Review Committee shall function to advise the Plant Manager on all matters selated to nuclear safety.
6.5.1.2 Composition The-Plant Operations Review Committee shall be composed of the:
Superintendent.- Operations (Chairman)
Superintendent - Technical Superintendent - Maintenance / Instrumentation and Controls Superintendent - Plant Services Assistant Superintendent - Operations Maintenance Engineer Engineer-Systems l
Regulatory Engineer i
Shift Manager 6.5.1.3 Alternates Alternate members shall be appointed in writing by the PORC Chairman to serve on a temporary basis; however, no more than two alternate members shall be used to satisfy a PORC quorum (See 6.5.1.5).
Amendment No. 27, 39, 61, 74, 9#, 122' -246-135, 157 l
PBAPS F,
- 6.5.2.8 Continued.
The Facility Emergency Plan and implementing procedures at e.
least once per year.
f.
The Facility Security Plan'and implementing procedures at least once per. two years.
- . ju g.
The Offsite Dose Calculation Manual and implementing
" procedures ~~at least once per two years.
h.
The perforr.ance of activities required by'the Quality Assure To Program regarding the' radiological' monitoring progri io meet +.he provisions of Regulatory Guide'4.1,.
. Revision
'975, at least once per calendar year.
i.
Any oth'er area of faci'lity operation considered appropriate by the NRB or the Executive Vice President - Nuclear.
1 Authority 6.5.2.9 The NRB shall report to and. advise the Executive Vice President -
4 Nuclear on those~ areas'of responsibility specified in Section l
6.5.2.7 and 6.5.2.8.
Records 6.5.2.10
' Records of NRB activities shall be prepared, approved and distributed as indicated below:
Minut'es of'each_NRB meeting shall:ue prepared, approved and a.
forwarded to the ' Executive Vice President - Nuclear within 10 working days following each meeting.
i b.
Reports.of reviews encompassed by Section 6.5.2.7.e, f, g and.h above shall be prepared, approved and forwarded to the Executive Vice President - Nuclear, within 10 working days following completion of the review.
i r
l Amendment No. 10, 37, 109, 115. IIS, -252-135, 157
_