ML20049H810
| ML20049H810 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 02/09/1982 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Philadelphia Electric Co, Public Service Electric & Gas Co, Delmarva Power & Light Co, Atlantic City Electric Co |
| Shared Package | |
| ML20049H811 | List: |
| References | |
| DPR-44-A-083, DPR-56-A-082 NUDOCS 8203040099 | |
| Download: ML20049H810 (12) | |
Text
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%,h UNITED STATES
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NUCLEAR REGULATORY COMMISSION g,
oE WASHINGTON, D. C. 20555
\\*****
PHILADELPHIA ELECTRIC COMPANY PUBLIC SERVICE ELECTRIC AND GAS COWANY DELMARVA POWER AND LIGHT. COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-277 PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 2 I
l AMEN 0 MENT TO FACILITY OPERATING LICENSE i
Amendment No.83 l
License No. DPR-44 1.
The Nuclear Regulatory Commission (the Commission) has found that:
1 A.
The application for amendment by Philadelphia Electric Company, et al. (the licensee) dated October 1,1981, complies with the standards and req)uirements of the Atomic En.ergy Act of 1954, as amended (the Act, and the Comission's rules and regulations set j
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 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 in compliance with the Cpmmission's regulations; 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 Spec-ifications 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:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 83, are hereby incorporated in the license. PEC0 shall operate the facility in accordance with the Technical Specifications.
0203040099 820209 DR ADOCK 05000
r 2-3.
This license amendment is effective as of the date of its issuance.
R THE NU REG LATO,RY COMMISSION dt\\
John'F. St olz, Chief 0
rating Reactors Bra ch #4 ision of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: February 9,1982 4
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ATTAC8iMENT TO LICENSE AMENDMENT NO. 83 FACILITY OPERATING LICENSE NO. DPR-44 DOCKET NO. 50-277 Replace ^.he following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
Remove Insert 65 65 248 248 254a 254a i
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TABLE 3.2.3 (CONTINUED) rt INSTRUNENTATION TH4T INITIATES OR CONTROLS THE CORE AND CONTAINNENT CDCLING SYSTEMS
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Minimue No.
Of Operable Number of Instru-Instrument Trip runction Trip Level Setting ment Channela Pro Remarks m
w charnels Per vided by Destgri Trip systeell) 2 Reactor High Water 1+45 in. indicated 2 Inst. Channele Tripe HPCI & RCIC Level level turbines 1
Reactor Low Level 2+312 in. above 2 Inst. Channels Prevents inadvertent
=
(inside shroud) vessel aero (2/3 operation of contain-core height) ment spray during accident condition.
2 Containment High 1<p( 2 psig 4 Inst. Chtnnels Prevents inadvertent Pressure operation of contain-ment spray during accident condition.
1 Confirmatory Low 2+6 in. indicated 2 Inst. Channels ADS Permissive Q
Level level 2
High Drywell i 2 psig 4 Inst. Channels
- 1. Initiates Core Sprays Pressure LPCIsHPCI
- 2. Initiates starting of Diesel Generatore
- 3. Initiates Auto Blow-down (ADS) in conjunction with Low-Low-Low Reactor i
water level, 120 second time delay, and LPCI or Core Spray pump running.
48 3
PBAPS 6.5.1.6 Continued 1
h.
Review of t,he Plant Security Plan and implementing procedures and shall submit recommended changes to the Plan, to the Chairman of the Operation and Safety Review Committee.
i.
Review of the Emergency Plan and implementing procedures and shall submit recommended changes to the Plan, to the Chairman of the Operation and Safety Review Committee.
Authority 6.5.1.7 The Plant Operation Review Committee shall:
a.
Recommend to the Station Superintendent written approval or disapproval of items considered under 6.5.1.6(a) through (d) above.
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 l
question, as defined in 10 CFR 50.59.
c.
Provide immediate written notification to the Superintendent, Generation Division-Nuclear or, in his absence, the Superintendent, Generation Division--
Fossil-Hydro, and the Operation and Safety Review Committee of disagreement between the PORC and the Station Superintendent; however, the Station Superintendent shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above.
Records l
6.5.1.8 The Plant Operation Review Committee shall maintain written minutes of each meeting and copies shall be provided to the Superintendent, Generation Division-Nuclear..and Chairman of the Operation and Safety Review Committee.
-Amendment No. X, g, 83
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PBAPS 6.9.1.a Continued Startup reports shall be submitted within 50 days following resumption or commencement of commercial full power operation.
b.
Annual Occupational Exposure Tabulation (1)
A tabulation shall be made on an annual basis of the number of station utility and other personnel (including contractors) receiving exposures greater than 100 mrem /yr and their associated man-rem exposure according to work and jco function, (2) e.g.,
reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), vaste processing, and refueling.
This tabulation shall be submitted for the previous calendar year prior to March 1 of esch year.
The dose assignment to various duty functions may be estimated based on pocket dosimeter, TLD, or film badge measurements.
Small exposures totalling less than 20% of the individual total dose need not be accounted for.
In the aggregate, at least 80% of the total wholebody dose received from external sources shall be assigned to specific major job ft.netions.
(.1) A single submittal may be made for a multiple unit station.
(2) This tabulation supplements the requirements of 10 CFR 20.407.
1 a
1 Amendment No. X, 83
- 254a -
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'9, UNITED STATES'
[
3
',g NUCLEAR REGULATORY COMMISSION a
wassic.cTON. D. C. 20555
...../
PHILADELPHIA ELECTRIC COMPANY PUBLIC SERVICE ELECTRIC AND GAS COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY l
DOCKET NO. 50-278 PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.82 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 October 1,1981, 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 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; D.
The issuance of this amendment will*'not be inimical to the common 2
defense and security or to the heafth 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 Spec-ifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License flo. 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. 82, are hereby incorporated in the licepse. PECO shall toerate the facility in accordance with the Technical Specificat ons.
O
2 3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION r
~
i Jo F. Stolz, C ief 0 rating Reactors Branch #4 ivision of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
February 9,1982 0
l l
L.
f
ATTACHMENT TO LICENSE AMENDMENT NO. 82 FACILITY OPERATING LICENSE NO. DPR-56 DOCKET NO. 50-278 Replace the following pages of the Appendix "A" Technical Specifications
- with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
Remove Insert 65 65 248 248 254a 254a
'l 3
g i
l.
I
!I TABLE 3.3.3 (CONTINUED)
INSTRUMENTATION THAT INITIATES OR Cott?ROLS THE' CORE AND CONTAINMENT
- s COOLING SYSTEMS r+
se j)
Minimus No.
Of Operable Number of Instru-Instrument Trip Function Trip Levet setting ment Channels Pro Remarks Channels Per vided by Design Trip systealt) as ru 2
Reactor High Water fp45 in. indicated 2 Inst. Channels Trips HPCI & RCIC Level level turbines 1
Resctor Low Level 2*312 in, above 2 Inst. Channels Prevents inadvertent (inside shroud) vessel aero (2/3 operation of contain-core height) ment spray during accident condition.
2 Containment High 1 < p < 2 psig a Inst. Channels Prevents inadvertent Pressure operation of coatain-ment spray during accident condition.
8 1
Confirmatory Low 2+6 in. indicated 2 Inst. Channels ADS Permissive Level level en us 2
High Drywell i 2 peig 4 Inst. Channels
- 1. Initiates Core Sprays e
Pressure LPCIpHPCI
- 2. Initiates starting of Diesel Generators
- 3. Initiates Auto Blow-down (ADS) in conjunction with Low-Low-Low Reactor I
water level, 120 second time delay, and LPCI or Core Spray I
pump running.
~
l l
o 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 Operation and Safety Review Committee.
i.
Review of the Emergency Plan and implementing procedures and shall submit recommended changes to the Plan, to the Chairman of the Operation and Safety Review Committee.
Authority 6.5.1.7 The Plant Operation Review Committee shall:
a.
Recommend to the Station Superintendent written approval or disapproval of items considered under 6.5.1.6(a) through (d) above.
I 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.
c.
Provide immediate written notification to the Superintendent, Generation Division-Nuclear or, in his absence, the Superintandent, Generation Division--
Fossil-Hydro, and the Operation and Safety Review Committee of disagreement between the PORC and the l
Station Superintendent; however, the Station I
superintendent shall have responsibility for i
resolution of such disagreements pursuant to 6.1.1 above.
i Records 6.5.1.8 The Plant Operation Review Committee shall maintain written minutes of each meeting and copies.shall be provided to the Superintendent, Generation Division-Nuclear..and. Chairman of the Operation and Safety Review Committee.
l Amendment No. E, X, 82
~M-4 I
t.
r o
PBAPS 6.9.1.a Continued Startup reports shall be submitted within 90 days following resumption or commencoment of commercial full power operation.
b.
Annual Occupational Exposure Tabulation (1)
A tabulation'shall be made on an annual basis of the number of station utility and other personnel (including contractors) receiving exposures greater than 100 mrem /yr and their associated man-rem exposure according to work and job function, (2) e.g.,
reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe tnaintenance), ion shall be waste processing, and refueling.
This tabulat submitted for the previous calendar year prior to March 1 of each year.
The dose assignment to various duty functions may be estimated based on pocket dosimeter, TLD, or film badge measurements.
Small exposures totalling less than 20% of the individual total dose need not be accounted for.
In the aggregate, at least 80% of the total wholebody dose received from external sources shall be assigned to specific major job functions.
(1) A single submittal may be made for a multiple unit station.
(2) 'Ihis tabulation supplements the requirements of 10 CFR 20.407.
i l
l l
Amendment No. JP', 82
- 254a -
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