ML20059J037
| ML20059J037 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 11/01/1993 |
| From: | Larry Nicholson Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20059J042 | List: |
| References | |
| NUDOCS 9311100326 | |
| Download: ML20059J037 (14) | |
Text
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UNITED STATES f.jh%j NUCLEAR REGULATORY COMMISSION
- p ;.
WASHINGTON, D.C. 20566-0001 V;,'; /
PHILADELPHIA ELECTRIC COMPANY PUBLIC SERVICE ELECTRIC AND GAS COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET N0. 50-277 i
PEACH BOTTOM ATOMIC POWER STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.180 License No. DPR-44 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Philadelphia Electric Company, et.
al. (the licensee) dated February 25, 1993 as supplemented by letter dated September 1, 1993, complies with the standards and requiremrnts 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.
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 E.
The issuance of this amendment is in accordance with 10 CFR Par. 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-44 is hereby amended to read as follows:
9311100326 931101 PDR ADDCK 05000277 p
4
. (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.180, 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 Q)"
~
Larry.. Nicholson, Acting Director Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: November 1, 1993 I
e
_ _. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _. _ _ _ _ _ _ _ _ _ _ _ _ _. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _j
1 j
l ATTACHMENT TO LICENSE AMENDMENT NO.180 FACILITY OPERATING LICENSE NO. DPR-44 i
DOCKET NO. 50-277
{
Replace the following pages of the Appendix A Technical Specifications with j
the enclosed pages. The revised areas are indicated by marginal lines.
Remove Insert i
207 207 212 212 216b-2 216b-2 l
259 259 l
1
PBAPS Unit 2 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REOUIREMENTS may be used to estimate flow.
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 radioactive effluents via this pathway.
g.
With less than the minimum number of radioactive liquid radwaste monitors OPERABLE exert best I
efforts to return the instruments to OPERABLE status within 30 days and if unsuccessful explain in the l
next Annual Radioactive Effluent Release Report why the inopera-bility was not corrected in a timely manner.
i 4.
All liquid effluent releases at 4a.
Doses due to liquid effluent j
and beyond the SITE BOUNDARY shall releases to areas at and beyond be processed through one of the the SITE BOUNDARY shall be Radwaste subsystems or combina-projected once per month in 1
tions of these subsystems listed accordance with the methodology below, prior to release *:
and parameters in the ODCM.
(i)
The Waste Collector Filter and 4b. The waste collector filter and Demineralizer demineralizer and the Floor (ii)
The Floor Drain Filter Drain Filter shall be (iii) The Fuel Pool Filter demonstrated operable once per Demineralizer quarter, unless utilized to (iv)
The Chemical / Oily Waste Cleanup process liquid waste during the Subsystem previous 13 weeks, by analyzing the liquid processed through the j
- Whenever the release (s) would cause subsystem and determining that the projected dose, when it is it meets the requirements of averaged over one month to exceed Specification 3.8.B.1.
The fuel O.12 mrem to the total body or 0.4 pool filter demineralizer and mrem to any organ (combined total the chemical / oily-waste cleanup from the two reactors at the site).
subsystem are exempt from this requirement because they are i
With liquid waste being discharged alternate treatment subsystems without treatment as required above, and/or are used only prepare and submit to the Commission periodically for batch treatment within 21 working days pursuant to of liquids which'are analyzed Specification 6.9.2, a special prior to being released and are Report which includes the following information:
a.
Explanation of why liquid radwaste was Amnndment No. -is+, W,180
-207-e e
1 Unit 2 PBAPS l
l LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REOUIREMENTS l
continue provided samples are continuously collected with auxiliary sampling equipment for i
periods on the order of 7 days and analyzed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after the end of the sampling period.
- d. One reactor building exhaust vent flow rate monitor and one main stack flow rate monitor shall be operable and set to alarm in accordance with the methodology and parameters in the ODCM.
From and after the date that both reactor building exhaust vent flow rate monitors or both main stack flow rate monitors are made or found to be inoperable i
for any reason, effluent releases via their i
respective pathway may j
continue provided the I
flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
- e. with less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE exert best efforts to return the instruments to OPERABLE status within 30 days and if unsuccessful explain l
in the next Annual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.
Sa.
Doses due to gaseous 5.
Gaseous effluents shall effluent releases to be processed through the areas at and beyond the appropriate gaseous waste SITE BOUNDARY shall be treatment system as projected at least once described below prior to per discharge Amendment No. -192., ibu 212 s
Unit 2 PBAPS 2.
A batch release is the discharge of 11guld wastes of a discrete volume.
Prior to sampling for analysis, each batch shall be isolated and thoroughly mixed to assure-representative sampling.
3.
A composite sample is one in which the quantity of the sample is proportional to the quantity of liquid waste discharged and in which the method of sampling results in a sample representative of the liquids released.
4.
The principal gamma emitters for which the minimum detectable level specification will apply are exclusively the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144.
This list does not mean that only these nuclides are to be detected and reported.
Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported.
Nuclides which are below the sample detectable limit for the analyses.should not be reported as being present at the sample detectable limit level. When unusual circumstances result in sample detectable limits higher than required, the reasons shall i
be documented in the Annual Ef fluent Report.
The values i
listed are believed to be attainable.
i 5.
Certain mixtures of radionuclides may cause interference in the measurement of individual radionuclides at their detectable limit especially if other radionuclides are at much higher concentrations.
Under these circumstances j
use of known ratios of radionuclides will be appropriate to calculate the levels of such radionuclides.
r 216b-2 Amendment No-102. 180 o
E
[
. Unit 2-l E
a PBAPS environmental monitoring program including sampling methods for each sample type, size and physical j
characteristics of each sample type,.. sample preparation methods, and measuring equipment used; at least two maps of all sampling locations keyed I
to a table.giving distances and directions from the midpoint between reactor vents; the results of land use censuses required by Specification 3.8.E.2; the
- results of the Interlaboratory Comparison Program and discussion of all analyses in which the LLD required by Tables 4.8.1 and 4.8.2 was not i
achievable.
(2)
Annual Radioactive Effluent Release Report j
Routine radioactive effluent release reports
(
covering the previous calendar year shall be submitted prior to May 1 of each year.-
.j The Radioactive Effluent Release Reports shall I
include a summary of the quantities of radioactive-i I
liquid and gaseous effluents and solid waste released from-the site.
The Radioactive Effluent Release Reports 'shall include the following information for each class of solid waste (as defined by 10 CFR Part 61) shipped offsite during the report period:
?
a.
Container volume, r
b.
Total curie quantity (specify whether determined by measurement or estimate),
i c.
Principal radionuclides (specify whether determined by measurement or estimate),
j 1
d.
Source of waste and processing employed (e.g., dewatered spent resin, compacted dry.
I waste, evaporator bottoms), and l
1 1
t Amendment No. iOE, 180
-259-l l
'l L
l
.j i
ff UNITED STATES
[
j NUCLEAR REGULATORY COMMISSION
- '(
WASHINGTON. D.C. 20556-0001 h, '.... #
PHILADELPHIA ELECTRIC COMPANY PUBLIC SERVICE ELECTRIC AND GAS COMPANY i
EELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-278 PEACH BOTTOM ATOMIC POWER STATION. UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.185 License No. DPR-56 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Philadelphia Electric Company, et.
al. (the licensee) dated February 25, 1993 as supplemented by letter dated September 1,1993, 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.
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; 1
D.
The issuance of this amendment will not be inimical to the comon i
defense and security or to the health or safety of the public; and j
i E.
The issuince of this amendment 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:
t t :
i (2) Technical Snecifications -
The Technical Specifications contained in Appendices A and B, as revised through Amendment No.185, are hereby incorporated in the '
license.
PECO shall operate the faci'ity in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date.of issuance.
l FOR.THE NUCLEAR REGULATOR COMMISSION
[
$l f [
Nicholson, Acting Director Larr Project Directorate I-2 Division of Reactor _ Projects - I/II Office of Nuclear Reactor Regulation l
Attachment:
Changes to the Technical Specifications Date of Issuance: November 1, 1993 t
i
^
.i i
.i i
u i
l i
ATTACHMENT TO LICENSE AMENDMENT NO.185 i
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 areas are indicated by marginal lines.
Remove Insert 207 207 212 212 216b-2 216b-2 259 259 4
i e
4 PBAPS Unit 3 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REOUIREMENTS may be used to estimate flow.
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 radioactive effluents via this pathway.
g.
With less than the minimum number of radioactive liquid radwaste monitors OPERABLE exert best efforts to return the instruments to OPERABLE status within 30 days and if unsuccessful explain in the j
next Annual Radioactive Effluent Release Report why the inopera-bility was not corrected in a timely manner.
4.
All liquid effluent releases at 4a.
Doses due to liquid effluent and beyond the SITE BOUNDARY shall releases to areas at and beyond be processed through one of the the SITE BOUNDARY shall be Radwaste subsystems or combina-projected once per month in tions of these subsystems listed accordance with the methodology below, prior to release *:
and parameters in the ODCM.
(i)
The Waste Collector Filter and 4b. The waste collector filter and Demineralizer demineralizer and the Floor (ii)
The Floor Drain Filter Drain Filter shall be (iii) The Fuel Pool Filter demonstrated operable once per Demineralizer quarter, unless utilized to (iv)
The Chemical / Oily Waste Cleanup process liquid waste during the Subsystem previous 13 weeks, by analyzing the liquid processed through the
- Whenever the release (s) would cause subsystem and determining that the projected dose, when it is it meets the requirements of averaged over one month to exceed Specification 3.8.B.l.
The fuel 0.12 nrem to the total body or 0.4 pool filter demineralizer and mrem to any organ (combined total the chemical / oily-waste cleanup from the two reactors at the site).
subsystem are exempt from this requirement because they are With liquid waste being discharged alternate treatment subsystems without treatment as required above, and/or are used only prepare and submit to the Commission periodically for batch treatment within 21 working days pursuant to of liquids which are analyzed Specification 6.9.2, a Special prior to being released and are Report which includes the following information:
a.
Explanation of why liquid radwaste was Amendment No. 04,127,185
-207-4 e
?
~
Unit 3 PBAPS
~
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REOUIREMENTS continue provided samples are continuously collected with auxiliary sampling equipment for periods on the order of 7 days and analyzed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after the end of the sampling period.
- d. One reactor building exhaust vent flow rate monitor and one main stack flow rate monitor shall be operable and set to alarm in accordance with the methodology and parameters in the ODCM.
From and after the date that both reactor building exhaust vent flow rate monitors or both main stack flow rate monitors are made or found to be inoperable for any reason, effluent releases via their respective pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
- e. with less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE exert best efforts to return the instruments to OPERABLE status within 30 days and if unsuccessful explain l
in the next Annual Radioactive Effluent Release Report why the inoperability was not l
corrected in a timely manner.
Sa.
Doses due to gaseous 5.
Gaseous effluents shall effluent releases to be processed through the areas at and beyond the appropriate gaseous waste SITE BOUNDARY shall be treatment. system as projected at least once 1
described below prior to per discharge Amendment No. 104, 185 212 l
6
Unit 3 PBAPS 2.
A batch release is the discharge of liquid wastes of a discrete volume.
Prior to sampling for analysis, each batch shall be isolated and thoroughly mixed to assure representative sampling.
3.
A composite sample is one in which the quantity of the sample is proportional to the quantity of liquid waste discharged and in which the method of sampling results in a sample representative of the liquids released.
4.
The principal gamma emitters for which the minimum detectable level specification will apply are exclusively the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144.
This list does not mean that only these nuclides are to be detected and reported.
Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported.
Nuclides which are below the sample detectable limit for the analyses should not be reported as being present at the sample detectable limit level. When unusual circumstances result in sample detectable limits higher than required, the reasons shall I
be documented in the Annual Effluent Report.
The values listed are believed to be attainable.
5.
Certain mixtures of radionuclides may cause interference in the measurement of individual radionuclides at their detectable limit especially if other radionuclides are at much higher concentrations.
Under these circumstances use of known ratios of radionuclides will be appropriate to calculate the levels of such radionuclides.
)
Amendment No. % 185 216b-2
)
Unit 3 PBAPS environmental monitoring program including sampling methods for each sample type, size and physical characteristics of each sample type, sample preparation methods, and measuring equipment used; at least two maps of all sampling locations keyed to a table giving distances and directions from the midpoint between reactor vents; the results of land use censuses required by Specification 3.8.E.2; the results of the Interlaboratory Comparison Program and discussion of all analyses in which the LLD required by Tables 4.8.1 and 4.8.2 was not achievable.
(2)
Annual Radioactive Effluent Ralaase Report Routine radioactive effluent release reports covering the previous calendar year shall be submitted prior to May 1 of each year.
The Radioactive Effluent Release Reports shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the site.
The Radioactive Effluent Release Reports shall include the following information for each class of solid waste (as defined by 10 CFR Part 61) shipped offsite during the report period:
a.
Container volume, b.
Total curie quantity (specify whether determined by measurement or estimate),
c.
Principal radionuclides (specify whether determined by measurement or estimate),
d.
Source of waste and processing employed (e.g., dewatered spent resin, compacted dry waste, evaporator bottoms), and Amendment No. -b}P,185
-259-
)