ML20235F537
| ML20235F537 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 09/22/1987 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20235F541 | List: |
| References | |
| NUDOCS 8709290187 | |
| Download: ML20235F537 (9) | |
Text
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'o UNITED ST ATEs
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',i NUCLEAR REGULATORY COMMISSION E
W ASHINGTON, D. C. 20555
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gv f 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 STATIOM, UNIT NO. 2 i
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 124 License No. DPR-44
)
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Philadelphia Electric Company, et 1'
al. (the licensee) dated December 17, 1986, 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; j
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 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 l
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 I
Specifications as indicated in the attachment to this license amendment, and paragraph 2.C(2) of Facility Operating License No. DPR-44 is hereby i
amended to read as follows:
4 B709290187 g h 77 PDR ADOCK PDR P
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4 (2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.124, 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 (2
v v
Walter R. Butler, Director
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Project Directorate I-2 i
Division of Reactor Projects I/II
)
Attachment:
Char.ges to the Technical Specifications Date of Issuance: Septenber 22, 1987 e.
W
1 (2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.127, 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
/s/
Walter R. Butler, Director Project Directorate I-2 Division of Reactor Projects I/II l
Attachment:
l Changes to the Technical Specifications Date of Issuance: September 22, 1987 l
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ATTACHMENT TO LICENSE AMENDMENT N0.124 FACILITY OPERATING LICENSE NO. OPR-44 DOCKET N0. 50-277 Replace the followina page of the Appendix A Technical Specifications with the enclosed pace.
The revised areas are indicated by marginal lines.
Remove Insert 207 207
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i PEAPS Unit 2 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS may_be used to estimate flow.
f.
If the requirements of q
3.8.B.3.a, 3.8.B.3.b, 3.8.B.3.c, 3.8.B.3.d, or 3.8.B.3.e, cannot be met, suspend release of radio-active effluents via this pathway.
)
9 With less than the minimum j
number of radioactive liquid V
radwaste monitors OPERABLE iN exert best efforts to C'
return the instruments to OPERABLE status within 30 "j
days and if unsuccessful 4
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explain in the next-Semi-Ar...ual Radioactive Ef fluent Release Report why the incperability was not cor rected in a timely manner.
4.
All liquid effluent releases 4a.
Doses due to liquid at and beyond the SITE BOUNDARY effluent releases to shall be processed through one of areas at and beyond the the F.dwaste subsystems or SITE BOUND /.RY shall be combinations of these subsystems projected once per month j
listed below, prior to release *:
in accordance with the jL methodology and parameters 1l (1)
The Waste Collector Filter in the ODCM.
9 and Demineralized (ii)
The Floor Drain Filter 4b.
The waste collecter filter
,y (iii) The Fuel Pool Filter and demineralized and the Demineralized Floor Drain Filter shall te (iv)
The Chemical / Oily demonstrated operat:c once Waste Cleanup Subsystem per quarter, unless utilized to process
- Whenever the reletae(s) would liquid waste during the cause the projected dose, when it previous 13. weeks, by
.i 1s averaged over one month to analyzing the liquid j
exceed 0.12 mrem to the total processed through the 1
bcdy or 0.4 mrem to any organ subsystem and de.ermining I
(c;mbined total from the two that it meets the j
reactors at the site).
~ requirements of Specification 3.8.B.l.
The fuel pool With liquid waste being filter demineralized
~ J discharged without treatment as and the chemical /
,l required above, prepare and oily-waste cleanup 1
submit to the Commission within subsystem are exempt 21 working days pursuant to from this requirement Specification 6.9.2, a Special l
because they are alternate Report which includes the treatment subsystems and/cr following information:
are used only periodically 1
a.
Explanation of why liquid for batch treatment of liquids radwaste was which are analyzed prior j
to being released and are j
Amendment No. 102, 124 A
-207-3 0l
y UNITED STATES
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WASHINGTON, D. C. 205S5 E
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PHILADELPHIA ELECTRIC COMPANY PUBLIC SERVICE ELECTRIC AND GAS COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY t
DOCKET NO. 50-278 PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 3 N
AMENDMENT TO FACILITY OPERATING LICENSE sj Amendment No. 127
,f, License No. OPR-56 f
?
1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by Philadelphia Electric Company, et al. (the licensee) dated December 17, 1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the i
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 j
this amendment can be concucted without endangering the health and i
safety of the public, and (ii) that such activities will be conducted
{
I al" in compliance with the Comission's regulations; s
The issusnce of this amendment will not La inimical to the comon i
D.
defense and security or to the health or scfety of the public; and
}
The issuance of this amendment is in accordance with 10 CFR Part 51 of 9
E.
the Comission's regulations and all cpplicable requirements have been 1
El satisfied.
j Accordingly, the license is amended by changes to the Technical jj 2.
Specifications as indicated in the attachment to this license amendment, l11 and paragraph 2.C(2) of Facility Operating License No. OPR-56 is hereby amended to read as follows:
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Technical Specifications The Technical Specifications' contained'in Appendices A and B,.as revised through Amendment No.127, are hereby incorporated in the
-license. <PECO shall' operate the facility in accordance with the-j
-Technica1 ' Speci fications.
- 3. 'This license amendment is effective as of its date of issuance.
FOP THE NUCLEAR REGULATORY COMMISSION Jk lg/&k?k.-
Walter R. ' Butler, Director Project Directorate I-2
~
l Division of Reactor Projects I/II
Attachment:
Changes to the Technical i
Specifications Date of Issuance:
September 22, 1987 L-:.
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1 ATTACHMENT TO LICENSE AMENDMENT NO. 127' FACILITY OPERATING LICENSE NO. DPR-56 DOCKET NO. 50-278 Replace the following page of the Appendix A Technical Specifications with
~
the enclosed page.
The revised areas are' indicated by marginal lines.
Pemove Insert 207 207 F;
W
.I 1
A
'a I
l
1 l
PEAPS Unit 3 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS i
may be used to estimate ficw.
f.
If the requirements of 3.8.B.3.a, 3.8.B.3.b, 3.8.B.3.c, 3.8.B.3.d. or 3.8.B.3.e, cannot be met, suspend release of radio-active effluents via this pathway.
g.
With less than the minimum number of radioactive liquid j
radwaste monitors OPERABLE exert best effcrts to r'eturn the instruments to OPERABLE status within 30 days and if unsuccessful explain in the next Semi-Annual Radioactive Effluent Release Report why the incperability was not corrected in a timely manner.
4.
All liquid effluent releases 4a.
Deses due to liquid at and beyond the SITE BOUNDARY effluent releases to shall be processed through one of areas at and beyond the the Radwaste subrystems or SITE BOUNDARY shall be combinations of tnese subsystems project +d once per month listed below, prior to release *:
in accordance with th-methodology and parameters
(.1 )
The Waste Collector Filter in the ODCM.
and Demineralized (ii)
The Floor Drain Filter 4b.
The waste collector filter (iii) The Fuel Pool Filter and demineralized and the Demineralized Floor Drain Filter shall be ww.
(iv)
The Chemical / Oily demonstrated operar once Waste Cleanup Subsystem per quarter, unless utili:($ t: process
- Whenacer the release (s) would liquid waste during the cause the projected de;>, when it previc.s 13 weeks, by is averaged over one month to analyt.ng the liquid e," teed 0.12 mrem to the tc.al processed through the bcdy or 0.4 mrem to any organ subsyste.i and determining l
(co.'.ined total from the two that it meets the reactors at the site).
requirements of Specification 3.8.B.1.
The fuel pool With liquid waste being filter demineralized discharged without treatment as and the chemical /
required above, prepare and oily-waste cleanup submit to the Commission within subsystem are exempt 21 working days pursuant to from this requirement Specification 6.9.2, a Special l
because they are alternate Report which includes the treatment subsystems and/or i
following information:
are used only periodically Explanation of why liquid for batch treatment of liquids a.
radwaste was which are analyzed prior to being released and are Anendment No. % 127 j
-207-
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