ML20151B692
| ML20151B692 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood, 05000000 |
| Issue date: | 07/11/1988 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20151B675 | List: |
| References | |
| NUDOCS 8807210069 | |
| Download: ML20151B692 (8) | |
Text
.
POWER OISTRIBUTION LIMITS SURVEILLANCE REOUIREMENTS (Continued) is less than or equal to the F,R 2)
When the F limit for the appropriate measured core plane, additional power distribution R
maps shall be taken and F compared to F and F, at least x
once per 31 EFPO.
provid ed The F,y limits for RATED THERMAL POWER (F p) shall be tEEfor all e.
3 core planes containing Bank "0" control rods and M*=+m' all unrocced core planesp;n a Radial Peak.ing Facher Lienit Reperb pe.c-S peci fi coH on /. 9. l. 9 )
f.
The F,y limits of Specification 4.2.2.2e., above, are not applicable in the following core planes regions as measured in percent of core height from the bottom of the fuel:
1)
Lower core region from 0 to 15%, inclusive, 2)
Upper core region from 85 to 100%, inclusive, 3)
Within 2% of grid plane regions such that no more than 20% of i
the total core heignt in the center core region is affected, and l
4)
Core plane regions within 2 2% of core height (* 2.88 inches) about the bank demand position of the Bank "0" control rods, g.
With F, exceeding F,, the effects of F on F (Z) shall be g
evaluated to determine if F (Z) is within its limits.
g 4.2.2.3 When F (Z) is measured for other than F,y determinations, an overall q
measured F (Z) shall be obtained from a power distribution map and increased 9
by 3% to account for manufacturing tolerances and further increased by 5% to account for measurement uncertainty.
8807210069 880711 PDR ADOCK 05000454 P
+
BYRON - UNITS 1 & 2 3/4 2-7 AMENCHENT NO. $
ADMfNISTRATfVE CONTROLS REPORTING REQUIREMENTS (Continued)
"Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof.
For solid wastes, the format for Table 3 in Appendix B shall be supplemented with three additional categories: class of solid wastes (as defined by 10 CFR Part 61),
type of container (e.g., LSA, Type A, Type B, Large Quantity), and SOLIDIFICA-TION agent or absorbent (e,g., cement, urea formaldehyde).
The Semiannual Radioactive Effluent Release Reports shall include a list and description of unplanned releases from the site to UNRESTRICTED AREAS of radioactive materials in gaseous and liquid effluents made during the reporting period.
The Semiannual Radioactive Effluent Release Reports shall include any changes made during the reporting period to the PCP, pursuant to Specifications, 6.13, as well as any major cht.nges to Liquid, Gaseous or Solid Radwaste Treat-
~
ment Systems, pursuant to Specification 6.15.
The Semiannual Radioactive Effluent Release Reports shall also include the following: 'an explanation as to why the inoperability of liquid or gaseous effluent monitoring instrumentation was not corrected within the time specified in Specifications 3.3.3.lt or 3.3.3.
respectively; and description of the events leading to liquid holdup tanks or gas storage tanks exceeding the limits of Specification 3.11.1.4 or 3.11.2.6, respectively.
9 MONTHLY OPERATING REPORT 6.9.1.8 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the PORVs or RCS safety valves, shall be submitted on a monthly basis to the Director, Office of Resource Management, U.S. Nuclear Regulatory Commission, Washington, D.C.
20555, with.a copy to the Regional Administrator of the NRC Regional Office, no later than the 15th of each month following the calendar month covered by the report.
RADIAL PEAKING FACTOR LIMIT REPORT 6.9.1.9 '" -- n d he F limits for Rated Thermal Power (F
) shall be R
xy x
provided to the NRC Regional Administrator with a copy to Director of Nuclear Reactor Regulation, Attention:
Chief, Ce 0:rier= m- % =4, U. S. Nuclear Regulatory Commission, Washington, D. C. 20555 for all core planes containing Bank "D" control rods and all unrodded core planes and the plot of predicted 1
T (F
.P,)) vs Axial Core Height with the limit envelope at least 60 days prior q
g to cycle initial criticality unless otherwise approved by the Commission by letter.
In addition, in the event that the limit should change requiring a new j
Reacter Systems Branch, DPL-A 1
_d BYRON - UNITS 1 & 2 6-21
POWER DISTRIBUTICN LIMITS SURVEILLANCE REOUIREMENTS (Continued) i RTP 2)
When the F is less than or equal to the F limit for the x
appropriate measured core plane, additional power distribution RTP maps shall be taken and F compared to F and F at least x
x x
once per 31 EFPD.
l B
W 'd e.
The F limits for RATED THERMAL POWER (F P) shall be b for all xy core planes containing Bank "D" control rods and 55-for all unrodded core planes)/ n a fdencil &hny f6 der (_,,nN ffport per i
Speci fre_anch C. 9' t. <i; f.
The F ifmits of Specification 4.2.2.2e., above, are not applicable xy in the following core planes regions as measured in percent of core height from the bottom of the fuel:
1)
Lower core region from 0 to 15%, inclusive, 2)
Upper core region from 85 to 100%, inclusive, 3)
Within 2% of grid plane regions such that no more than 20% of k
the total core height in the center core region is affected, and 4)
Core plane regions within i 2% of core height (1 2.88 inches) about the bank demand position of the Bank "D" control rods.
g.
With F exceeding Fx, the effects of F n F (Z) shall be x
xy q
evaluated to determine if F (Z) is within its limits, q
i 4.2.2.3 When F (Z) is measured for other than F determinations, an overall i
q xy measured F (Z) shall be obtained from a power distribution map and increased q
by 3% to account for manufacturing tolerances and further increased by 5% to account for measurement uncertainty.
BRAIDWOOD - UNITS 1 & 2 3/4 2-7
I
. ADMINISTRATIVE CONTROLS 1
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[?ORTING REQUIREMENTS (Continued)
"Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1. June 1974, with data summarized on a quarterly basis following tne format of Appendix B thereof.
For solid wastes, the format for Table 3 in Appendix B shall be supplemented with three additional categories: class of solid wastes (as defined by 10 CFR Part 61),
type of container (e.g., LSA, Type A, Type B, Large Quantity), and SOLIDIFICA-TION agent or absorbent (e.g., cement, urea formaldehyde).
The Semiannual Radicactive Effluent Release Reports shall include a list and description of unplanned releases from the site to UNRESTRICTED AREAS of radioactive materials in gaseous and liquid effluents made during the reporting period.
i The Semiannual Radioactive Effluent Release Reports shall include any changes made during the reporting period to the PCP, pursuant to Specifications 6.13, as well.as any major changes to Liquid, Gaseous or Solid Radwaste Treat-ment Systems, pursuant to Specification 6.15.
The Semiannual Radioactive Effluent Release Reports shall also include the following:
an explanation as to why the inoperability of liquid or
- gaseous effluent monitoring instrumentation was not corrected within the time specified in Speci fications 3.3. 3.-1g or 3.3.3. H', respectively; and description of the l
events leading to liquid oldup tanks?or gas storage tanks exceeding the limits of Specification 3.11.1.4 r 3.11.2.6, respectively.
MONTHLY OPERATING REPORT
- 6. 9.1. 8 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the PORVs or RCS safety. valves, shall be submitted on a monthly basis to the Director, Office of Resource Management, U.S. Nuclear Regulatory Commission, Washington, D.C.
20555, with a copy to the Regional Administrator of the NRC Regional Office, no later than the 15th of each month following the calendar month covered by the report.
RADIAL PEAKING FACTOR LIMIT REPORT j
T
- 6. 9.1. 9 -Ghugu-to-Ahe F limits for Rated Thermal Power (FRTP) shall be l
provided to the NRC Regional Administrator with a copy to Director of Nuclear Reactor Regulation, Attention:
Chief, Reactor System = Branch, OPL-A, U.S.
Nuclear Regulatory Commission, Wasnington, D. C. 205.
for all core planes con-taining Bank "0" control rods and all unrodded core planes and the plot of pre-T dicted (F
.Pgg) vs Axial Core Height with the limit envelope at least 60 days q
prior to cycle initial criticality unless otherwise approved by the Commission by letter.
In addition, in the event that the limit should change requiring a new BRAIDWOOD - UNITS 1 & 2 6-21
ATTACleistiI h BACEGROUND INFORMATIN The proposed amendment requests the deletion of the.fix3d Fxy limits from Specification 4.2.2.2.e and requires the cycle specific Txy limits be submitted to the NRC in a Radial Peaking Factor Limit Report.
It
~
was previously felt that variable F limits would not be required for nach x
limits'to cycle and the flued limits would. eliminate the~need to report Fxy the NRC on a reload basis.
It has been found that the F valves for xy subsequent cycles are higher than first cycle valves.-
-j The current specification wording does not allow Byron and Braidwood Stations to use existing F margin when calculating the F limits. This.
l q
xy can result in entering the F Technical Specification action statement for q
artificially low F limits.
In addition, the specification currently-xy limits the stations to F values for only two core regions; one for core x
planes containing Bank "D control rods and one for the unrodded ctre planes.
It may be advantageous to establish more than two F limits depending on xy the margin to the F limit as a function of height using actual calculated q
F valves.
l ry The current specification does not allow the flexibility of sending a Radial Peaking Factor Limit Report to the NRC to revise the F limits.
xy
- limits, EveniftheReportwasissuedperSpecification6.9.1.9withnewF(lon x
the limits would be inconsistent with the fixed limits in Specifica j
4.2.2.2.
To avoid the need for a Technical Specification unendment for each revision to the limits in Specification 4.2.2.2.e, Commonwealth Edison 3
requests this proposed amendment to the Technical Specifications. This change is consistest with the Standardized Technical Specifications and the Technical Specificatior for other plants such as Callaway, Wolf Creek, Catawba, and Seabrook.
Two other changes are also requested for this amendment.
In Specification 6.9.1.9, "Chief, Core Performance Branch" should be revised to "Chief, Reactor Systems Branch, DPL-A" to reflect the current title.
In j
a l
addition, Specification 6.9.1.7, references Specifications 3.3.3.10 and 3.3.3.11, tisis should be revised to reference, Specifications 3.3.3.9 and 3.3.3.10.
This revision is to correct these typographical errors.
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ATTACHMENT _C EYALUATION OF SIGNIFICANT HAZARD CCHSIDMTLQt(S Commonwealth Edison has evaluatet this proposed amendment and determined that it involves no significant hasards consideration. According to 10 CFR 50.92(c), a proposed snen&nent to an operating license involvos no significant hasards considerations if operation of the facility in accordance with the proposed unendment would not 1.
Involve a significant increase in the probability or consequences of an accident previously evaluated; or 2.
Create the possibility of a new or different kind of accident from any accident previously evaluated; or 3.
Involve a significant reduction in a margin of safety.
The proposed Technical Specification snendment requests several changes. The first change removes the existing, fixed F limits in xy Specification 4.2.2.2.e and substitutes a requirement to submit the F xy limits to the NRC via a Peaking Factor Limit Report in accordance with Specification 6.9.1.9.
The second change revises the position title to whom the Radial Peaking Factor Limit Report is submitted per Specification 6.9.1.9.
The title is changed from "Chief, Core Performance Branch" to "Chief, Reactor Systems Branch, DPL-A" which is consistent with the title listed in Braidwood's Technical Specifications.
Finally in Specification 6.9.1.7, the references to Specifications "3.3.3.10 and 3.3.3.11" are being changed to Specifications "3.3.3.9 and 3.3.3.10" respectively because an incorrect Specification is referenced.
All the changes requested are administrative in nature and do not affect the probability of an accident occurring. The proposed revision to Specification 4.2.2.2.e does not change the current F limits used at the plant.
ItsimplyrevisesthemethodbywhichchangesfotheF x
limits can xy be requested and implemented. The other changes correct a typographical error and change a position title. None of these changes affect the assumptions or results of any accidents previously analyzed. Therefore the consequences of any accidents are not impacted.
The proposed changes do not involve any equipment additions er modifications at the plant or cause the plant to be operated in a different manner. Therefore, the possibility of a new or different kind of accident from any accident previously evaluated is not created.
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, The Radial Peaking Factor, Fxy (Z) is me'3ured periodically to provide assurance that the Heat Flux Hot Channel Factor Fq (Z) remains within its limit.
The limits on Heat Flux Hot Channel Factor help to ensure j
the design limits on peak local power density and minimum DNBR are not exceeded and in the event of a LOCA, the peak fuel clad temperature will not i
exceed the 2200*F mceptance criteria. The proposed change to remove the j
fixed F limits t..m the Technical Specification and replace the xy requirement with a submittal of a Radial Peaking Factor Limit Report does not change the F limits. The remaining changes are administrative in nature.
xy The changes proposed for this amendment do not affect any margins of safety.
For the reasons stated above, Commonwealth Edison believes this proposed amendment involves no significant hazards consideration.
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