ML19263E712
| ML19263E712 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 05/03/1979 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19263E713 | List: |
| References | |
| NUDOCS 7906250079 | |
| Download: ML19263E712 (10) | |
Text
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,j UNITED STATES NUCLEAR REGULATORY COMMISSION O"
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.,l WAScilNGTON, D. C. 20555 e
'+9.....,o 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 NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 52 License No. DPR-44 Pursuant to a Decision (ALAB-532) by the Atomic Safety and Licensing Appeal Board dated March 23, 1979, the Nuclear Regulatory Commission has amended Facility Operating License No. DPR-44 by a change to the Technical Specifications as indicated in the attachment to this license amendment and by amending paragraph 2.C. (2) to read as follows:
2.C.(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 52 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
The license is further amended by deleting paragraph 3.(c) and adding new paragraphs 3.(c) and 3.(d) as follows:
3.(c) To the extent matters related to thermal discharges are treated therein, operation of Peach Bottom Atomic Power Station Unit No. 2 will be governed by NPDES Permit No. PA 0009733, as now in effect and as hereafter amended.
Questions pertaining to conformance thereto shall be referred to and shall be determined by the NPDES Pennit issuing or enforcement authority, as appropriate.
2218 190 790625 007p
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3.(d)
In the event of any modification of the NPDES Permit related to thermal discharges or the establishment (or amendment) of alternative effluent limitations established pursuant to 5316 of the Federal Water Pollution Control Act, the licensees shall inform the NRC and analyze any associated changes in or to the r
Station, its components, its operation or in the discharge of effluents therefrom.
If such change would entail any modification to this license, or any technical specifications which are part of this license, or present an unreviewed safety question or involve an environmental impact different than analyzed in the Final Environmental Statement, the licensees shall file with the NRC, as applicable, an appropriate analysis of any such change on facility safet.y, and/or an analysis of any such change on the environmental impacts and on the overall cost-benefit balance for facility operation set forth in the Final Environmental Statement and a request for an
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amendment to the operating license, if required by the Commission's regulations. As used in this Condition 3.(d), Final Environmental Statement.means the NRC Staff Final Environmental Statement related to Operation of Peach Bottom Atomic Power Station Units Nos. 2 and 3 dated April 1973, as modified by (1) the Initial Decision of the Atomic Safety and Licensing Board dated September 14, 1973, (2) the Supplemental Initial Decision of the Atomic Safety and Licensing Board dated June 14,1974,(3) the Decision of the Atomic Safety and Licensing Appeal Board dated July 5,1974,(4) the Memorandum and Order of the Commission dated August 8,1974,(5) any further modification resulting from further review by the Appeal Board and by the Commission, if any, and (6) any Environmenta.1 Impact Appraisal which has been or may be issued by the NRC since the FES was published in April 1973.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Y,
Thomas '/ ppolito, Chief Operating Reactors Branch #3 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications 2218 191 Date of Issuance: May 3, 1979
AT ACHMENT TO LICENSE AMENDMENT NO. 52 i
FACILITY OPERATING LICENSE NO. DPR-44 DOCKET NO. 50-277 Replace the following pages of the Appendix "B" 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 t
I 5
5 5(a) 5(a) 5(b) 2218 192 P
2.0 PROTECTION LIMITS 3.0 MONITORING REQijIREMENTS 2.1 Thermal (deleted) 3.1 Themal Objective To assure that the water temperature in the Conowingo Pond is not increased to a level that adverse effects on the aquatic biota would result.
Speci fication The bulk temperature of the condenser inlet water and of the water discharged to Conowingo Pond from the discharge canal shall be transmitted to the PBAPS control room and logged. Temperatures at Holtwood Dam and.the Pennsylvania / Maryland state line shall be transmitted to the PBAPS control room and logged.
For purposes of maintenance, the temperature monitorinc system may be inoperable for a period not to exceed 7 days.
Thermal impact upon Conowingo Pond shall be periodically monitored and reported as specified in Section 6.3.
When less than three towers are in operation and the flow of the Susquehanna River through Conowingo Pond as calculated daily is less than 15,000 cfs, thermal plume mapping, as described in Section 6.3a of these specifications, shall be performed at least once per week.
The results of this thermal mapping shall be submitted to the NRC in monthly reports along with applicable data on river flows, heat discharged from the station and the nt.mber of cooling towers in operation. Under these conditions, measurements of the bulk temperature of the water discharged to Conowingo Pond from the discharge canal and the temperature at the Pennsylvania /
Maryland state line and Holtwood Dam shall be recorded notwithstanding the maintenance provisions stated above.
A non-routine report, as specified in Sub-section 7.4.2.A, shall be made if the thermal characteristics of the discharge from cutfall serial number 001 exceed the thermal effluent limitations as described in the currently effective NPDES Permit.
2218 193
.s.
Amendment No. 52
Bases r
The purpose of these monitoring and report-ing requirements is to provide NRC with the information it needs to carry out its NEPA responsibilities. The NPDES Permit dated April 11,1977, requires, among other things, that the licensee comply with certain Interim Operating Limits described in Special Condition 9.
Subsequent revisions to the NPDES Permit, or expira-tion of the Interim Operating Limit, or revisions to other certifications will be accommodated in accordance with the provisions of Subsection 7.4.2.B.
According to Specification 2.1 as it appeared in Amendment No. 24 to DPR-56 for Peach Bottom Atomic Power Station, Unit 3, plant operation was allowed under certain environmental conditions as a result of the NrPA review process.
The NPDES Permit dated April 11, 1977 imposes similar, but not identical, conditions by means of the Interim Operating Limits set forth in Special Condition 9.
The NPDES Permit Interim Operating Limits set forth in Special Condition 9.F, relate to operation for more than three days with cooling towers out of service. The NRC's requirements in this regard under low flow conditions are dealt with in a letter from NRC to Philadelphia Electric Company dated September 11,1978.
The Intcrim Operating Limits in conjunction with the letter assure that the plant will not be operated under conditions substantially different from those evaluated in the staff FES and subsequent impact appraisals.
The licensee is required to analyze the environmental impact of changes made in the NPDES Permit and submit an analysis according to Subsection 7.4.2.B.
NRC will review the analysis for consistency with the findings of the NEPA review process.
2L218 194
-Sa-Amendment No. 52
4 UNITED STATES y%
NUCLEAR REGULATORY COMMISSION g
.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 NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 52 License No. DPR-56 Pursuant to a Decision (ALAB-532) by the Atomic Safety and Licensing Appeal Board dated March 23, 1979, the Nuclear Regulatory Commission has amended Facility Operating License No. DPR-56 by a c! ange to the Technical S9ecifications as indicated in the attachment to this license amendment and by amending paragraph 2.C.(2) to read as follows:
2.C.(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 52 are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
The license is further amended by deleting paragraphs 3.B,, 3.C., 3.D.,
3.E., 3.F., 3.G., and 3.H. and adding new paragraphs 3.B and 3.C. as follows:
3.B.
To the extent matters related to thermal discharges are treated therein, operation of Peach Bottom Atomic Power Station Unit 3 will be governed by NPDES Permit No. PA 0009733, as now in effect and as hereafter amended.
Questions pertaining to conformance thereto shall be referred to and shall be determined by the NPDES Permit issuing or enforcement authority, as appropriate.
2218 195
3.C.
In the event of any mcdification of the NPDES Permit related to thennal discharges or the establishment (or amendment) of alternative effluent limitations established pursuant to 1316 of the Federal Water Pollution Control Act, the licensees shall inform the NRC and analyze any associated changes in or to the Station, its components, its operation or in the discharge of effluents therefrom.
If such change would entail any modification to this license, or any technical specifications which are part of this license, or present an unreviewed safety question or involve an environm e.tal impact different than analyzed in the Final Environmental Statement, the licensees shall file with the NRC, as applicable, an appropriate analysis of any such change on facility safety, and/or an analysis of any such change on the environmental impacts and on the overall cost-benefit balance for facility operation set forth in the Final Environmental Statement and a request for an amendment to the operating license, if required by the Commission's regulations.
As used in this Condition 3.C., Final Environmental Statement means the NRC Staff Final Environmental Statement related to Operation of Peach Bottom Atomic Power Station Units 2 and 3 dated April 1973, as modified by (1) the Initial Decision of the Atomic Safety and
~
Licensing Board dated September 14,1973,(2) the Supplemental Initial Decision of the Atomic Safety and Licensing Board dated June 14,1974,(3) the Decision of the Atomic Safety and Licensing Appeal Board dated July 5,1974,(4) the Memorandum and Order of the Comission dated August 8,1974,(5) any further modification resulting from further review by the Appeal Board and by the Comm%sion, if any, and (6) any Environmental Impact Appraisal whic. has been or may be issued by the NRC since the FES-was published in April 1973.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 0-Yhomas polit,
'ief Operating Reactors Branch #3 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance:
May 3, 1979 22 l 0
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ATTACHMFNT TO LICENSE AMENDMENT NO. 52 B,CILITY OPERATING LICENSE NO. DPR-56 DOCKET NO. 50-278 Replace the following pages of the Appendix "B" 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 5
5 5(a) 5(a) 5(b) 2218 197
23 PROTECTION LIMITS 3.0 MONITOR!!;G REQUIREMEf;TS 2.1 Thermal (deleted) 3.1 Thennal Objective To assure that the water temperature in the Conowingo Pond is not increased to a level that adverse effects on the aquatic biota would result.
Specification The bulk temperature of the condenser inlet water and of the water discharged to Conowingo Pond from the discharge canal shall be transmitted to the PBAPS control room and logged. Temperatures at Holtwood Dam and the Pennsylvania / Maryland state line shall be transmitted to the PBAPS control room and logged.
For purposes of maintenance, the temperature monitoring syste,,i may be inoperable for a period not to exceed 7 days.
Thermal impact upon Conowingo Pond shall be periodically monitored and reported as specified in Section 6.3.
When less than three towers are in operation and the flow of the Susquehanna River through Conowingo Pond as calculated daily is less than 15,000 cfs, thermal plume mapping, as described in Section 6.3a of these specifications, shall be performed at least once per week. The results of this thermal mappin~g shall 'e submitted to the NRC in monthly reports along with applicable data on river flows, heat discharged from the station and the number of cooling towers in operation.
Under these conditions, measurements of the bulk temperature of the water discharged to Conowingo Pond from the discharge canal and the temperature at the Pennsylvania /
Maryland state line and Holtwood Dar. shall be recorded notwithstanding the maintenance provisions statec above.
A non-routine report, as specified in Sub-section 7.4.2. A, shall be made if the thermal characteristics of the discharge from cutfall serial number 001 exc ed the thermal effluent limitations as described in the currently effective NPDES Permit.
l 2218 198 2
.o
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Bases The purpose of these conitoring and report-ing requirements is to provide fiRC with the information it needs to carry out its NEPA responsibilities. The NPDES Permit dated April 11, 1977, requires, among other things, that the licensee comply with certain Interim Operating Limits described in Special Condition 9.
Subsequent revisions to the NPDES Pemit, or expira-tion of the Interim Operating Limit, or revisions to other certifications will be accommodated in accordance with the provisions of Subsection 7.4.2.B.
According to Specification 2.1 as it appeared in Amendment No. 24 to DPR-56 for Peach Bottom Atomic Pcwer Station, Unit 3, plant operation was allowed under certain environmental conditions as a result of the NEPA review process.
The NPDES Permit dated April 11, 1977 imposes similar, but not identical, conditions by means of the Interim Operating Limits set forth in Special Condition 9.
The NPDES Permit Interim Operating Limits set forth in Special Condition 9.F, relate to operation for more than three days with cooling towers out of service. The NRC's requirements in this regard under low flow conditions are dealt with in a letter from NRC to Philadelphia Electric Company dated September 11, 1978.
The Interim Ope. rating Limits in conjunction with the letter assure that the plant will not be operated under conditions substantially different from those evaluated in the staff FES and subsequent impact appraisals.
The nicensee is required to analyze the environmental impact of changes made in tha NPDES Pemit and submit an analysis according to Subsection 7.4.2.B.
NRC will review the analysis for consistency with the findings of the NEPA review process.
2218 199
-Sa-Amendment No. E2