ML20151Y561
| ML20151Y561 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood, 05000000 |
| Issue date: | 08/05/1988 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20151Y549 | List: |
| References | |
| NUDOCS 8808260451 | |
| Download: ML20151Y561 (9) | |
Text
[g. neg'6 UNITED STATES
"*g 8
NUCLEAR REGULATORY COMMISSION o
(
E WASHINGTON, D. C. 90655
\\...../
SAFETYEBLUATIONBYTHEOFFICEOFNUCLEARREACTORREGULATION SUPPORTING TO AMENDMENT NOS. 22 TO FACILITY OPERATING LICENSE NOS. NPF-37, NPF-66 AND AMENDMENT N0. 11 TO FACILITY OPERATING LICENSE NOS. NPF-72, NPF-77 COMMONWEALTH EDIS0N COMPANY BYRON STATION, UNITS 1 AND 2 DOCKET NOS. 50-454 AND 50-455 BRAIDWOOD STATION, "PITS 1 AND 2 DOCKET N05. 50-456 AND 50-457
1.0 INTRODUCTION
By letter dated January 12, 1988, Commonwealth Edison Company, the licensee, made application for amendment to Facility Operating License Nos. NPF-37 and NPF-66 for the Byron Nuclear Plant Units No. I and No. 2, and to Facilitv Operating License Nos. NPF-72 and NPF-77 for the Braidwood Nuclear Plant Units No. I and No. 2.
The proposed changes concorn revisions to the Technical Specifications (TS) to modify the existing liquid radwaste affluent line flow monitor.
A Notice of Consideration of Issuance of Amendment to Facility Operating License and Proposed ho Significant Hazards Consideration Determination and Opportunity for Hearing related to tha requested action was published in the Federal Register on March 9, 1988 (53 FR 7587). No requests for hearing and no public coments were received.
2.0 EVALUATION The licensee has proposed to add a new liquid radwaste discharge flowrate monitor to TS Table 3.3-12 an/ TS Table 4.3-8, which specify radioactive liquid effluent monitoring instrumentation operability and surveillance requirements, respectively. The TS changes would reflect the licensee's modification of their existing liquid radwaste effluent line flow rate monitoring system, involving installation of a 3-inch diameter bypass line containing a flow element and accompanying flow control / isolation valves.
The modification, which will bypass the existing flow element mounted in the 6-inch discharge line, will provide more accurcte measurement of low flow rates (0-150 gpm).
The added bypass flow elerrent will perform the same functions as the existing 8808260451 080005 PDR ADOCK 0D0004%,
P pp;
.. flow element, but it will be more accurate at low flow rates.
Keylocks en the isolation valve operator switches will be used to assure that only one flow loop is used at a time. The existing radiation monitor will provide isolation signals on high radiation to the new bypass line isolation valves in addition to the existing isolation valves.
The staff's review of the above proposed change indicates that the proposal is acceptable and does not affect the reliability or operability of safety systems as required for safe plant operation, shutdown, or accident mitigation.
The staff finds the above changes acceptable.
3.0 ENVIRONMENTAL DETERMINATION This amendment relates to an upgrading of liquid radioactive effluent flow monitoring capabilities and thus changes an inspection or surveillance requirement. There is no significant hazards consideration, there is no change in the types or increase in the amounts of any effluent that may be released offsite, and there is no significant increase in individual or cumulative occupational radiation exposure. Accordingly, this anendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of this amendment.
4.0 CONCLUSION
The staff has concluded, based on the considerations discussed above, that:
(1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Corr. mission's regulations, and (3) the issuance of this amendment will not be inimical to the common defense and security.
5.0 ACKNOWLEDGEMENT This evaluation was prepa'ad by L. R. Greger, Region III.
Dated: August 5, 1988
~,
. (2) Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 11 and the Environment Protection Plan contained in Appendix B, both of which are attached to License No.
NPF-72, dated July 2,1987, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance.
FOR THF NUCLEAR REGULATORY COMMISSION flb.i' or Daniel R. Muller, Director Project Directorate III-2 Division of Reactor Projects - III, IV, Y and Special Projects
Attachment:
Changes to the Technical Specifications Date of Issuance: August 5, 1988 l
i.
l l
l l
1
=-
ATTACHMENT TO LICENSE, AMENDMENT NOS.11 AND 11 FACILITY OPERATING LICENSE NOS. NPF-72 AND NPF-77 DOCK T NOS. 50-456 AND 50-457 Revise Appendix A as follows:
s Remove Pages Insert Pages 3/4 3-60 3/4 3-60 3/4 3-62 3/4 3-62
'. ~,
TABLE 3.3-12 Bg RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 5g MINIMUM CHANNELS INSTRUMENT OPERABLE ACTION cz h
1.
Radioactivity Monitors Providing Alarm and Automatic Termination of Release y
[
a.
Liquid Radwaste Effluent Line (ORE-PR001) 1 31 b.
Fire and Oil Sump (0RE-PR005) 1 34 c.
Condensate Polisher Sump Discharge (ORE-PR041) 1 34 2.
Radioactivity Monitors Providing Alarm But Not Providing Automatic Termination of Release s
a.
Essential Service Water
1 32 b) RCFC 18 and ID Outlet (1RE-PR003) 1 32
)
~
Station Blowdown Line (ORE-PR010) 1 32 3.
Flow Rate Measurement Devices i
a.
Liquid Radwaste Effluent Line (Loop-WX001) 1 33 b.
Liquid Radwaste Effluent Low Flow Line (Loop-WX630) 1 33 c.
Station Blowdown Line (Loop-CWO32) 1 33 i
TABLE 4.3-8 RADI0 ACTIVE LIQUID EFFLUEriT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS DIGITAL ANALOG o
CHANNEL CHANNEL CHANNEL SOURCE CHANNEL OPERATIONAL OPERATIONAL
[
INSTRUMENT CHECK CHECK CALIBRATION TEST TEST-z Z
1.
Radioactivity Monitors Providing Alarm and Automatic Termination
[
of Release m
a.
Liquid Radwaste Effluent Line (0RE-PR001) D P
R(3)#
Q(1)
N.A.
b.
Fire and Oil Sump Discharge (ORE-PR005)
D M
R(3)
Q(1)
N.A.
t c.
Condensate Polisher Sump Discharge D
M R(3)
Q(1)
N.A.
(ORE-PR041) 2.
Radioactivity Monitors Providing Alarm But Not Providing Automatic Termination
{
of Release
,T a.
Essential Service Water
D M
R(3)#
Q(2)
N.A.
b) RCFC 18 and 1D Outlet (1RE-PR003)
D M
R(3)#
Q(2)
N.A.
D M
R(3)#
Q(2)
N.A.
j b) RCFC 28 and 20 Outlet (2RE-PR003)
D M
R(3)#
Q(2)
N.A.
b.
Station Blowdown Line (ORE-PR010)
D M
R(3)#
Q(2)
N.A.
3.
Flow Rate Measurement Devices E
a.
Liquid Radwaste Effluent Line 1
(Loop-WX001)
D(4)
N.A.
R#
N.A.
Q 5
b.
Liquid Radwaste Effluent Low Flow
~
Line (Loop WX630)
D(4)
N.A.
R N.A.
Q d
c.
Station Blowdown Line (Loop-CWO32)
D(4)
N.A.
R N.A.
Q
r p ar UNITED STATES 8
NUCLEAR REGULATORY COMMISSION g
E WASHINGTON, D. C. 20555
%,...../
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING TO AMENDMENT NOS. 22 TO FACILITY OPERATING LICENSE NOS. NPF-37, NPF-66 AND AMENDMENT N0. 11 TO FACILITY OPERATING LICENSE NOS. NPF-72, NPF-77 COMMONWEALTH EDIS0N COMPANY BYRON STATION, UNITS 1 AND 2 DOCKET NOS. 50-454 AND 50-455 BRAIDWOOD STATION, UNITS 1 AND 2 DOCKET NOS. 50-456 AND 50-457
1.0 INTRODUCTION
By letter dated January 12, 1988, Comonwealth Edison Company, the licensee, made application for amendment to Facility Operating License Nos. NPF-37 and NPF-66 for the Byron Nuclear Plant Units No. I and No. 2, and to Facility Operating License Nos. NPF-72 and NPF-77 for the Braidwood Nuclear Plant Units No. I and No. 2.
The proposed changes concern revisions to the Technical Specifications (TS) to modify the existing liquid radwaste effluent line flow monitor.
A Notice of Consideration of Issuance of Amendment to Facility Operating License and Proposed No Significant Hazards Consideration Determination and Opportunity for Hearing related to the requested action was published in the Federal Register on March 9, 1988 (53 FR 7587).
No requests for hearing and no public coments were received.
2.0 EVALUATION l
The licensee has proposed to add a new liquid radwaste discharge flowrate monitor to TS Table 3.3-12 and TS Table 4.3-8, which specify radioactive liquid i
effluent monitoring instrumentation operability and surveillance requirements, respectively. The TS changes would reflect the licensee's modification of their existing liquid radwaste effluent line flow rate monitoring system, I
involving installation of a 3-inch diameter bypass line containing a flow element and accompanying flow control / isolation valves.
The modification, which will bypass the existing flow element mounted in the 6-inch discharge line, will provide more accurate measurement of low flow rates (0-150 gpm).
The added bypass flow element will perform the same functions as the existing l
r
.. flow element, but it will be more accurate at low flow rates.
Keylocks on the isolation valve operator switches will be used to assure that only one flow loop is used at a time. The existing radiation monitor will provide isolation l
signals on high radiation to the new bypass line isolation valves in addition to the existing isolation valves.
The staff's review of the above proposed change indicates that the proposal is acceptable and does not affect the reliability or operability of safety systems as required for safe plant operation, shutdown, or accident mitigation.
The staff finds the above changes acceptable.
3.0 ENVIRONMENTAL DETERMINATION This amendment relates to an upgrading of liquid radioactive effluent flow monitoring capabilities and thus changes an inspection or surveillance requirement. There is no significant hazards consideration, there is no change in the types or increase in the amounts of any effluent that may be released offsite, and there is no significant increase in individual or cumulative occupational radiation exposure. Accordingly, this amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of this amendment.
4.0 CONCLUSION
The staff has concluded, based on the considerations discussed above, that:
(1) there is reasonable assurance that the health and safety of the public will not be endangered by cperation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of this amendment will not be inimical to the common defense and security.
5.0 ACKNOWLEDGEMENT This evaluation was prepared by L. R. Greger, Region III.
Da ted: August 5, 1988
j.
Document Name:
BYRON 1 AMEND 7/12 Requestor's ID:
OT1 Author's Name:
01shan/ Sands Document Connents:
Byron 1 Amendment