ML19327A797
| ML19327A797 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 10/10/1989 |
| From: | Cutter A CAROLINA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML19327A798 | List: |
| References | |
| NLS-89-097, NLS-89-97, NUDOCS 8910180135 | |
| Download: ML19327A797 (15) | |
Text
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j A. B CUTTER SERIAL: NLS-89 097 j
vee Pree,sent 10 CFR 50.90
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i United States Nuclear Regulatory Cormaission A*I TENTION: Document Control Desk L
Washington, DC 20555 i
BRUNSWICK STEAM ELECTRIC PLI.NT, UNIT NOS. 1 AND 2
{
DOCKET NOS, 50 325 & 50 324/ LICENSE NOS. DPR 71 & DPR 62 1
REQUEST FOR LICENSE AMENDMENT INCREASED CONTAINMENT LEAKAGE RATE 11
. Gentlemen:
In accordance with the Code of Federal Regulations Title 10, Parts 50.90 i
and 2.101, Carolina Power & Light Company (CP&L) hereby requests a revision to the Technical Specifications for the Brunswick Steam Electric Plant (BSEP),
l Units 1 and 2.
t The proposed amendment increases the allowable primary containment leakage rates (La and L ) specified in Technical Specification 3.6.1.2, Primary t
L Containment Leakage.
La is increased from 0.5 percent to 1.0 percent by L
weight of the containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at 49 psig.
Le is increased from 0.357 percent to 0.714 percent by weight of containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at
'25 psig. The Bases Section for Technical Specification 3.6.1.2 has been revised to reflect this change and is included for your information. provides a detailed description of the proposed changes and the basis for the changes. details the basis for the Company's determination that the proposed changes do not involve a sig*11ficant hazards consideration.
' Enclosure 3 is an environmental evaluation which demonstrates that the p
proposed amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9); therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment needs to be prepared in connection with the issuance of the amendment.
4 provides instructions for incorporation of the proposed changes into the Technical Specifications for each unit.
E provides a summary of the proposed Technical Specification changes
~for each unit on a page by page basis.
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Document"Contr;l De:k NLS 89 097 / Page 2.
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Enclosures 6-and 7 provide the proposed Technical Specification pages for-Units 1 and 2, respectively.
The revised Bases Sections are also included for your information.
p' contains the calculations which form the basis for this amendment request.-
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Please refer any questions regarding this submittal to Mr M. R. Oates at (919) 546 6063.
Yours very-truly.
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A. B. Cutter
.ABC/ MAT
Enclosures:
1.
Basis for Change Request 2.
10CFR50.92 Evaluation f
3.
Environmental Evaluation 4.
Instructions for Incorporation 5.
Summary List of Revisions 6.
Technical Specification Pages Unit 1 7.
Technical Specification Pages Unit 2 8.
Supporting Calculations for Change Request cc:
Mr. Dayne H. Brown Mr. S. D. Ebneter Mr. W. H. Ruland Mr. E. G. Tourigny l
A. B. Cutter, having been first duly sworn, did depose and say that the information contained herein is true and correct to the best of his information, knowledge and belief; and the sources of his information are officers, employees, contractors, and agents of Carolina Power & Light
~ Company.
'i o Sotv Notary cal)
My commission expires:
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L ENCLOSURE 1 I
l BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 AND 2 NRO DOCKETS 50 325 & 50 324 OPERATING LICENSES DPR 71 & DPR 62 l
REQUEST FOR LICENSE AMENDMENT INCREASED CONTAINMENT LEAKAGE RATE
?
i BASIS FOR CHANGE REOUEST l
F Pronosed Channe t
The proposed amendment increases the allowable primary containment leakaE0 rates (La and L ) specified in Technical Specification 3.6.1.2, Primary.
t Containment Leakage. La is increased from 0.5 percent to 1.0 percent by r
weight of the containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at 49 psig.
Lt is increased from-0.357 percent to 0.714 percent by weight of containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at 25 psig.
The Bases Section for Technical Specification 3.6.1.2 has been revised to reflect this change and is included for your information.
Basis Increasing the allowable primary containment leakage rates (La and L ) Will t
provide significant safety benefits for the operation of the Brunswick Plant.
The current conservative limits have resulted in an increased ILRT failure rate and, therefore, performance of additional-ILRTs.
One of two Brunswick 1 11RT failures and three of five Brunswick 2 ILRT failures would have been acceptable with the revised containment leakage rates. Neither unit would be in an accelerated testing frequency if the revised containment leakage rates were in effect.
Specifically, ILRTs place an unnecessary burden on critical management, technical, and monetary resources available for Brunswick. The presence of an ILRT during an outage' introduces many work planning, staging, and accomplishment hardships which deflect management and supervisory attention from more consequential safety related work. An unnecessary ILRT increases tLe scope of an outage which can result in an increased vulnerability to humar error, has an impact on ALARA goals, and unduly stresses the primary l-containment, Activities related to an ILRT begin months in advance of the outage.
These activities involve not only preparation by those engineers directly responsible for the test but also management reviews, planning and scheduling review and incorporation with the overall outage schedule, operations involvement with preparation and planning of clearances, the budgeting process for the project, and contract development with firms outside the Company.
These activities represent an unwarranted burden on limited personnel and monetary resources when associated with unnecessary ILRTs.
Since resources are_ limited, work which is possibly more deserving must be dropped from an outage when forced to perform an unnecessary ILRT.
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Performance of an unnecessary liAT introduces undue complexity, cost, and drain on manpower during a critical time for the facility. Key individuals such as Technical Support engineers, instrumentation technicians, and mechanics are involved in-the staging of temporary instruments and equipment necessary to run the test. This equipment must be dismantled at the end of the test. Also, a significant effort is involved in properly aligning over 700 valves and establishing the associated clearances in order to prepare for an ILRT. Once again, the valve alignment must be returned to it normal configuration upon completion of the test.
Errors are more likely to occur with such a high level of_ complexity.
-A typical ILRT adds approximately one week of critient path time to an outage.
Outage activities both in the containment and the reactor building are stopped
. during performance of an ILRT. As demonstrated above, accelerated integrated leak rate testing results in elevated outage costs, increased outage scope and complexity, and unnecessarily focuses menagement attention without resulting in a significant safety benefit. Many hours of planning and scheduling precede an outage. An unnecessary ILRT diverts key personnel and resources from higher priority work both prior to and during an outage.
It is in the best interest of all concerned to see that outages are managed effectively and that critical resources are focused on safety significant tasks.
The following discussion demonstrates that the allowable containment leakage limits can be increased while maintaining offsite and control room doses within regulatory limits and environmental qualification of equipment as required by 10 CFR 50.49. As such, intent of the regulations can be achieved without a significant impact on the health and safety of either the public~or employees.
The existing allowable leakage rates (L and Lg) specified in the Brunswick a
Technical Specifications are 0.5 percent by weight per day at 49 psig and 0.357 percent by weight per day at 25 psig respectively. These values are conservatively low when compared with similar BWRs.
For example, the following table provides the La values for some other BVRs having Mark I type
-containments.
Plant Leak 4 by weighr/ day Browns Ferry 2.0%
L Brunswick O.5%
Cooper
.635%
Dresden 1.6%
L.
Duane Arnold 2.0%
li Fermi 0.5%
'llatch 1.2%
11 ope Creek 0.5%
Millstone 1.2%
Monticello 1.2%
Nine Mile 1 1.5%
Peach Bottom 0.5%
Pilgrim 1.5%
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l Quad Cities 1.0%
f Vermont Yankee 0.8%
The conservative L, limit has led to difficulties in meeting the Integrated Leakage Rate Test (ILRT) limit of (0.5)(.75) - 0.375 percent by weight per day and has resulted in an accelerated ILRT frequency at Brunswick. The proposed amendment increases La from 0.5 percent to 1.0 percent by weight of the containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at 49 psig and Le from 0.357 percent to 0.714 percent by weight of containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at 25 psig. As demonstrated in the above table, the requested L and Le limits are consistent-a with those established for other BWRs.
' Chapter 15 of the Brunswick FSAR was reviewed and it was determined that Section 15.6.4, Loss of Coolant Accident, is affected by the proposed change.
There are three analyses to be considered in this section: offsite doses, control room doses, and environmental qualification.
Sifsite Doses The limitations on primary containment leakage are intended to maintain the site boundary radiation doses within the limits specified in 10 CFR 100 during accident conditions.
The original accident analysis for Brunswick was performed using assumptions derived by General Electric calculations and source term assumptions as specified by TID 14844, J. J. DiNunno, et. al,
" Calculations of Distance Factors for Power and Test Reactor Sites," U. S.
AEC, March 23, 1962. The assumptions used in this analysis, for the most part, are less conservative than those of Regulatory Guide 1.3, June 1977.
Therefore, a new analysis, using the Regulatory Guide 1.3 assumptions, was performed to determine both the existing offsite doses and those which would result from the proposed change.
The following are the results of this re analysis.
Existing Doses for La = 0.5%
Whole Body Thyroid Site Boundary (0 2 hr) 5.61E 05 rem 7.76E-06 rem LPZ (0 30 days) 2.00E 02 rem 1.17E 04 rem Doses for L, = 0.5% - Reg Guide 1.3 Assumptions Whole Body Thyroid Site Boundary (0 2 hr) 0.803 rem 3.92 rom LPZ.(0 30 days) 0.504 rem 10.1 rem l
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-Doses for L. = 1.0% - Reg Guide 1.3 Assumptions Whole Body Thyroid Site Boundary (0 2 hr) 1.61 rem 7.84 rem LPZ (0 30 days) 1.01 rem 19.8 rem 10 CFR 100 Limits
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Whole Body Thyroid Site Boundary (0 2 hr) 25 rem 300 rem LPZ (0-30 days) 25 rem 300 rem As demonstrated in the above tables, raising the allowable containment leakage rates results in an increase in the offsite doses. However, both the site boundary and low population zone doses remain a small fraction of the limits specified in 10 CPR 100. These doses compare favorably with data available from selected plants referenced earlier.
LPZ Dose LPZ Dose Plant Whole Body Thyroid Brunswick 1.01 rem 19.8 rem Hatch
1.7 rem 147 rem Duane Arnold 2.86 rem 2.44 rem I
The analysis of offsite doses for Hatch did not use Regulatory cuide 1.3 i
methodology which results in the lower offsite doses.
Based on the above, Carolina Power & Light Company believes the calculated offsite doses resulting from the proposed increase in the allowable primary containment leakage rates La and Le are acceptable and are well within the applicable limits of 10 CFR 100.
Control Room Doses An increase in the allowable primary containment leakage can also affect the post-LOCA control room doses. The current 30 day control room doses for whole body, thyroid, and skin are 0,42 rem (8.4 percent of the 5 rem Standard Review Plan (SRP), NUREG 0800 limit), 0.41 rem (1.4 percent of the 30 rem SRP limit),
and 0.039 rem (0.13 percent of the 30 rem SRP limit), respectively. Assuming j
the worst case, increasing La from 0.5 percent to 1.0 percent by weight per day and Le from 0.357 percent to 0.714 percent by weight per day will raise these doses to no more than 0.84 rem whole body, 0.82 rem thyroid, and 0.08, skin. These dose limits remain only a small fraction of the limits specified in Section 6.4 of the Standard Review Plan. Based on the above, Carolina Power & Light Company believes the proposed increase in the allowable primary l
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containment leakage rates La and Lt is acceptable from a control room habitability standpoint.
Environmental Qualification
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Finally, the effects of. increasing the allowable primary containment leakage on environmental qualification were re analyzed.
Increasing La and Le will decrease primary containment doses since.it results in increased removal of 3
activity from containment.
It will, however, tend to increase the doses in the reactor building.
The equipment qualification doses in the reactor building were originally calculated for the Brunswick FSAR using the methodology of CP&L's Brunswick Plant calculation entitled Design Report 12. The re analysis is more realistic and removes some of the conservatisms of the original analysis.
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remains, however, a highly conservative analysis.
The following table illustrates the differences in the original assumptions and those of the re-analysis.
Oririnal FSAR Assumotions New Assumotions 5 iodine isotopes and 5 iodine isotopes and 11 noble gas isotopes 13 noble gas isotopes 1 average gamma ray energy 10 energy groups of per isotope assuming 1006 gamma ray emissions yield for each isotope including actual yield Shielding in air Shielding in air considered for average considered for each gamma ray energies energy group Absorbed dose calculated Absorbed dose-for average gamma ray calculated for each energies energy group Material used for absorbed Carbon used for dose calculation not absorbed dose specified calculation Calculate dose at center Calculate dose at and edge of spheres using center and edge of integrated equations and spheres using QAD CGGP average gamma ray energies-computer code and Point Kernel methods No credit taken for In non-uniform case, expansion of primary take credit for expan-containment leakage sion of primary cont-into reactor building ainment leakage in the El-5 m
m-__
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i l-due to differing reactor building com-temperature and pressure partment after leakage i-due to much lower c
l temperature and pres-sure in reactor building compartment L
For large and small For small compartments, compartments, compartment out flow equals primary out flow equals primary containment in leakage.
No credit in-leakage taken for removal by the standby gas treatment system.
For large compartments, y
Non Uniform Case only, take credit for 50% of p
standby gas removal capacity. Non Uniform Case only.
Note:
Uniform all Primary Leakage distributed throughout reactor building (applies above 20 foot elevation).
Non-Uniform - all Primary Leakage into a compartment adjacent to Primary (applies below 20 foot elevation).
The results of this re analysis are summarized below.
3 Non Uniform 8000 ft Uniform 90 ft Analysis Comnartment Radius Snhere Original 8.60E+06 rads 7.21E+04 rads New L - 0.5%
1.40E+06 rads 2.34E+04 rads a
New La - 1.0%
2.34E+06 radr 4.54E+04 rads Based on the above, Carolina Power & Light Company has determined that the bases for equipment qualification at Brunswick is not changed by increasing the allowable primary containment leakage rates La and L.
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c hh ENCLOSURE 2 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 AND 2 NRC DOCKETS 50 325 & 50 324 OPERATING LICENSES DPR 71 & DPR-62 REQUEST FOR LICENSE AMENDMENT INCREASED CONTAINMENT LEAKAGE RATE 10 CFR 50.92 EVALUATION The Commission has provided standards in 10 CFR 50.92(c) for determining whether a significant hazards consideration exists.
A proposed amendment to an operating license for a facility involves no significant hazards consideration if operation of the facility in accordance with the proposed amendment would not: (1) involve a significant increase in the probability or consequences of_an accident previously evaluated, (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.
Carolina
. Power & Light Company has reviewed this proposed license amendment request and determined that its adoption would not involve a significant hazards consideration.
The bases for this determination are as follows:
Proposed Chance The proposed amendment increases the allowable primary containment leakage and L ) specified in Technical Specification 3.6.1.2, Primary rates (L t
a Containment Leakage.
La is increased from 0.5 percent to 1.0 percent by weight of the centainment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at 49 psig. Le is increased from 0.357 percent to 0,714 percent by weight of containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at 25
- psig, kLik The change does not involve a significant hazards consideration for the following reasons:
1.
The proposed amendment does not involve a significant increase in the probability or consequences of an accident previously evaluated.
The proposed amendment does not involve any physical changes, additions, modifications, or deletions to existing equipment or systems.
In addition, it does not affect any operating parameters of the reactor, primary coolant system, and emergency core cooling systems. Therefore,
.the proposed change does not affect core damage frequency or system i
availability. As such, the change can not involve an increase in the probability of a previously evaluated accident.
The proposed amendment increases La from 0.5 percent to 1.0 percent by weight of the containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at 49 psig and Le from 0.357 percent to 0.714 percent by weight of containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at 25 psig.
Chapter 15 of the Brunswick FSAR was reviewed and it was E2 1 i
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L determined that Section 15.6.4, Loss of Coolant Accident, is affected by the proposed change. There are three analysis to be considered in this section:
offsite doses, control room doses, and environmental
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qualification.
i The proposed amendment wil result in a slight increase to offsite doses resulting from a design basis LOCA; however, this increase in not significant.. At the low population zone, the doses would increase from 2.0 percent to 4.0 percent of the 10 CFR 100 limit of 25 rem for the
't whole body and from 3.4 percent to 6.6 percent of the 10 CFR 100 limit of 300 ren for the thyroid. At the site boundary, the whole body and thyroid doses increase from 3.2 percent co 6.4 percent and 1.3 percent to 2.6 percent of the 10 CFR 100 limits respectively.
p Assuming the worst case, increasing La from 0.5 percent to 1.0 percent by weight per day and Le from 0.357 percent to 0.714 percent by weight per day will result in post accident control room doses of no more than 0.84 rem whole body, 0.82 rem thyroid, and 0,08, skin. These dose limits remain only a small fraction of the limits specified in Section 6.4 of the Standard Review Plan (5 rem whole body, 30 rem thyroid, and 30 rem skin). As such, the proposed increase in the allowable prirary and L ) is acceptable from a control room containment leaktge rates (La t
habitability standpoint.
Finally, the effects of increasing the allowable primary containment leakage on environmental qualification were re-analyzed.
Increasing La
-and Lt will decrease primary containment doses since it results in increased removal of activity from containment.
It will, however, tend to increase the doses in the reactor building.
The equipment qualification doses in the reactor building were originally calculated for the Brunswick FSAR using the methodology of CP&L's Brunswick calculation entitled Design Report 12.
The re-analysis is more realistic and removes some of the conservatisms of the original analysis.
It remains, however, a highly conservative analysis. This analysis oetermined that environmental qualification doses will remain within those currently specified. As such, the bases for equipment qualification at Brunswick is not changed by increasing the allowable primary containment leakage rates.
Based on the above, the Company has concluded that the proposed amendment will not result in a significant increase in the consequences of a previously evaluated accident.
2.
The proposed cmendment does not create the possioliity of a new or different kind of accident from any accident previously evaluated. As stated above, the proposed amendment does not involve any physical changes, additions, modifications, or deletions to existing equipment or systems.
In addition, it does not affect any operating parameters of the reactor, reactor coolant system, and emergency core cooling systems.
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I i-i Therefore, the proposed amendment cannot create the possibility of a new or different kind of accident.
3.
The proposed amendment does not involve a significant reduction in the margin of safety. The change does not affect the method by which any safety related equipment or systems perform their intended function.
Nor is any safety related setpoint revised as a result of the change.
Increasing La and Le will result in a slight increase to offsite doses resulting from a design basis LOCA. However, the doses remain well I
within 10 CFR 100 limits and, therefore, are not considered to be significant.
Control room doses are also increased but remain well below the applicable limits specified in Section 6.4 of the Standard Review Plan. As such, the proposed increase in the allowable primary containment leakage rates (La and L ) is acceptable from a control room t
habitability standpoint.
Finally, the effects of increasing the allowable primary containment leakage rates on environmental qualification were re analyzed.
It was determined that the bases for equipment qualification at Brunswick is not changed by increasing the allowable leakage rates.
Based on the above, the Company has concluded that the proposed amendment will not result in a significant reduction in the margin of safety.
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ENCLOSURE 3 i
BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 AND 2 NRC DOCKETS 50 325 & $0-324 OPERATING LICENSES DPR 71 & DPR 62 REQUEST FOR LICENSE AMENDMENT INCREASED CONTAINMENT LEAKAGE RATE ENVIRONMENTAL CONSIDERATION t
10 CFR 51.22(c)(9) provides criterion for and identificatien of licensing and 3
regulatory actions eligible for categorical exclusion from performing an environmental assessment. A proposed amendment to an operating license for a facility requires no environmental assessment if operation of the facility in accordance with the proposed amendment would not: (1) involve a significant hazards consideration; (2) result in a significant change in the types or significant increase in the amounts of any effluents that may be released offsite; and (3) result in a significant increase in individus1 or cumulative occupational radiation exposure. Carolina Power & Light Company has reviewed this request and determined that the proposed 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 needs to be prepared in connection with the issuance of the amendment.
The basis for this determination follows:
f EIonosed Change The proposed amendment increases the allowable primary containment leakage rates (La and Le) specified in Technical Specification 3.6.1.2, Primary Containment Leakage. La is increased from 0.5 percent to 1.0 percent by weight of the containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at 49 psig.
Le is increased from 0.357 percent to 0.714 percent by weight of containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at 25 psig.
Basis The change meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9) for the following reasons:
1.
As demonstrated in Enclosure 2, the proposed amendment does not involve a significant hazards consideration.
2.
The proposed amendment does not result in a significant change in the typca er significant increase in the amounts of any effluents that may be released offsite.
The proposed amendment will result in a slight increase to offsite doses resulting from a design basis LOCA; however, this increase in not significant. At the low population zone, the doses would increase from 2.0 percent to 4.0 percent of the 10 CFR 100 limit of 25 rem for the whole body and from 3.4 percent to 6.6 percent of the 10 CFR 100 limit of 300 rem for the thyroid.
At the site boundary, the whole body and thyroid doses increase from 3.2 percent to 6.4 percent E3 1 1
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i and 1.3 percent to 2.6 percent of the 10 CFR_100 limits respectively.
Since the resulting offsite doses remain only a very small-fraction of t
the.'O CFR 100 limits, this chaage does not result in a significant changi in the types or significant increase in-the amounts of any effluen's that may be released offsite.
3.
The propoked amendment does not result in a significant increase in i
b individual or cumulative occupational radiation. exposure. Assuming the worst case.. increasing La from 0.5 percent to 1.0 percent by weight per i
day and Le from 0.357 percent to.0.714 percent by weight.per day will result in post accident control room doses of no more than 0.84 rem j
whole body, 0.82 rem thyroid, and 0.08, skin. These dose limits remain only's small fraction of the limits specified in Section 6.4 of the l
Standard Review Plan (5' rem whole body, 30 rem thyroid, and 30 rem skin). As such, this change does not result in a significant increase in individual or cumulative occupational radiation exposure.
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ENCLOSURE-4
=ERUNSWICK STEAM ELECTRIC PLANT, UNIT NOS, l'AND 2' NRC DOCKETS 50 325 6150-324 OPERATING LICENSES DPR-71 & DPR 62
. REQUEST FOR LICENSE AMENDMENT INCREASED CONTAINMENT LEAKAGE RATE i
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INSTRUCTIONS FOR INCORPORATION
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The proposed changes to the Technical Specifications (Appendix A to Operating l
Licenses DPR-71 and-DPR-62) would be' incorporated as follows:
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Unit 1 Remove Pane-Insert Page 3/4~6 2 3/4 6 2 B 3/4 6-1 B 3/4 6 1 B'3/4 6 2 B 3/4 6-2 Unit 2 Remove Page Insert Pane 3/4 6-2 3/4 6-2 B 3/4'6-1 B 3/4 6-1 U
B 3/4(6 2 B 3/4 6 2 L3 i>
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9 ENCLOSURE 5 BRUNSWICK STEAM ELECTRIC PIANT, UNIT NOS.1' AND 2 NRC DOCKETS 50-325 &=50 324 OPERATING LICENSES DPR 71 & DPR-62 REQUEST FOR LICENSE AMENDMENT INCREASED CONTAINMENT LEAKAGE RATE
SUMMARY
LIST OF REVISIONS.
. Unit 1 Pages Descrintion of Changes 3/4'6 2~
Revised the value of La from 0.5 percent to 1.0 percent.
Revised the values of Le from 0,'357 percent to 0,714 percent.
B.3/4'6 1 Included discussion regarding La'and Le allowable leakage rates.
B 3/4 6 2
' Material relocated from previous page.
Unit 2 Pages Descrintion of Changes 3/4 6 2 Revised the value of La from 0.5 percent to 1.0 percent, Revised the values of L t from 0.357 percent-to 0.714 percent.
B 3/4'6 1 ~
Included discussion regarding L 'and Le a
allowable leakage rates.
B 3/4-6-2 Material relocated from previous page.
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