ML20246P555

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Proposed Tech Specs Re ESFAS Instrumentation,Combustible Gas Control Hydrogen Analyzers & Total Dose of Radioactive Effluents
ML20246P555
Person / Time
Site: Farley  Southern Nuclear icon.png
Issue date: 03/20/1989
From:
ALABAMA POWER CO.
To:
Shared Package
ML20246P552 List:
References
NUDOCS 8903280251
Download: ML20246P555 (28)
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ATTACHMENT 1 E. Proposed Changed Pages '

Unit 1 Revision Page 3/4 2-6 Replace Page 3/4 3-18 Replace Page 3/4 3-28 Replace Page 3/4 3-28a Delete  !

Page 3/4 3-45 Replace '

Page 3/4-6-19 Replace Page 3/4 11-19 Replace Page 6-15a Replace Page 6-19 Replace Page 6-20 Replace i

Unit 2 Revision j Page 3/4 2-6 Repltce Page 3/4 3-18 Replace Page 3/4 3-28 Replace Page 3/4 3-28a Delete Page 3/4 3-45 Replace Page 3/4 6-19 Replace Page 3/4 11-19 Replace Page 6-15a Replace Page 6-19 Replace Page 6-20 Replace c

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POWER D_IyIRIBUTION LIMITS SURVEILLANCE REQUIREMENTS-(Continued)
2. When the F
  • is Irc.,s than or equal to 'the FR TP -limit for the appropriatFmeasured core plane, additional p5veg distribution maps j shall be taken and F*** compared to F*RTP
  • and F*#

at least once per 31 EFPD.

e. The F limit for RATED THERMAL POWER (FRTP) shall be provided.for all u '

core planes containing bank "D" control 5bds and all unrodded core planes in a Radial Peaking Factor Limit Report per Specification 6.9.1.11.

f. limits of e, above, are not applicable in the following core The planeF,fegions as measured in percent of core height from the bottom of l the fuel:
1. Lower core region from 0 to 15%, inclusive.
2. Upper core region from 85 to 100%, inclusive.
3. Grid plane regions within + 2% of core height around the midpoint

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of the grids. 1

4. Core plane regions within + 2% of core height (+ 2.08 inches) about the bank demand position oI the bank "D" controT: rods.

g.

exceeding F *' the effects of F on F (Z) shall be Vith F,Ed to determine if F, (Z) is withiF its l$mits.

evaluat 4.2.2.3 When F (Z) is measured for other than F determinations, an overall measured F, (Z),shall be obtained from a power distribution map and increased by 3% to account for manufacturing tolerances and further increased by 5% to account for measurement uncertainty.

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F' CONTAINMENT SYSTEMS I

3/4.6.4 COMBUSTIBLE GAS CONTROL HYDROGEN ANALYZERS LIMITING CONDITION FOR OPERATION

================================================================================  ;;

3.6.4.1 Two independent containment hydrogen analyzers shall be OPERABLE.

APPLICABILITY: MODES 1 and-2.

ACTION:

a. Vith one hydrogen analyzer inoperable: 1 L

i) restore the inoperable analyzer to OPERABLE status within 30 days or be in at least HOT STANDBY vithin the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, or ii) establish an alternate hydrogen sampling capability.

The provisions of Specification 3.0.4 are not applicable. 1 3

b .' With both hydrogen analyzers inoperable, restore at least one analyzer'to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or.be in at least HOT STANDBY vithin the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

SURVEILLANCE REQUIREMENTS assamammmmmmmmmmmmamanummmmmmmmmm=================================s=============  ;

4.6.4.1 Each hydrogen analyzer shall be demonstrated OPERABLE at least once per 92 days on a STAGGERED TEST BASIS by performing a CHANNEL CALIBRATION using sample gases containing

a. Ten volume percent hydrogen, balance nitrogen, for zero check.  ;
b. Ten volume percent hydrogen, balance nitrogen, mixed with compressed air, for span check.

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FARLEY-UNIT 1 3/4 6-19 AMENDMENT NO.

RADIOACTIVE EFFLUENTS 3/4.11.4 TOTAL DOSE o

' LIMITING CONDITION FOR OPERATION  ;

3.11.4 The dose or dose commitment.to any member of the public, due to relenses of radioactivity and radiation, from uranium fuel cycle sources shall be limited to less than or' equal to 25 mrem to-the total body or any organ (except the I thyroid, which shall be limited to less than or equal to 75 mrem) over 4 consecutive quarters.

APPLICABILITY: At all times.

ACTION:

a. With the calculated doses from the release of radioactive materials in liquid.or gaseous effluents exceeding twice the limits of Specification 2.11.1.2.a, 3.11.1.2.b, 3.11.2.2.a, 3.11.2.2.b, 3.11.2.3.a, or 3.11.2.3.b, prepare and-submit a Special Report to the commission, pursuant to Specification 6.9.2, within 30 days, which defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding.the limits of Specification 3.11.4. This-

'Special Report shall include an analysis which estimates tne radiation exposure (dose) to a member-of the public from uranium fuel cycle sources (including.all effluent pathways and direct radiation) for e consecutive quarter period that includes the release (s) covered by tuis report. If the estimated dose (s) excecds the limits of Specification 3.11.4, and if the release condition resulting in violation of 40CFR190 has not already been corrected, the Special Report'shall include a request for a variance in accordance with the previsions of~40CFR190 and including the specified information of $ 190.11(b). Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.' The variance only relates to the limits of 40CFR190, and does not apply in any way to the requirements for dose limitation of 10CFR Part 20, as addressed in other sections of this technical specification.

b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

l SURVEILLANCE REQUIREMENTS t

4.11.4 Dose Calculations Cumulative dose contributions from liquid and gaseous- g l effluents shall be determined in accordance with Specifications 4~11.1.2,.

4.11.2.2, and 4.11.2.3, and in accordance with the ODCM.

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FARLEY-UNIT 1 3/4 11-19 AMENDMENT NO.

L______---_____________________

i

-ADMINISTRATIVE CONTROLS 6.9 REPORTING REQUIREMENTS ROUTINE REPORTS l 6.9.1 In addition to the applicable reporting requiremen'ts of-Title'10, Code of d Federal Regulations, the following reports shall be submitted to the Commission, d

. pursuant to 10CFR50.4. I)

I STARTUP REPORT 6.9.1.1 A summary report of plant startup.and power escalation testing shall.be submitted following (1) receipt of an operating license, (2) amendment to'the license involving a planned increase in power. level, (3) installation of fuel that has a different design or has been manufactured by_a different fuel supplier, and (4) modifications that may have significantly altered the nuclear,  ;

thermal, or hydraulic performance of the plant. 1

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9:

6

-FARLEY-UNIT 1 6-15a AMENDMENT NO.

ADMINISTRATIVE CONTROLS

e. Type of container (e.g., LSA, Type A, Type B, Large Quantity), and
f. Solidification agent (e.g., cement, urea formaldehyde).

The radioactive effluent release reports shall include unplanned releases from ,

the site to unrestricted areas of radioactive materials in gaseous and liquid i effluents on a quarterly basis.

The radioactive effluent release reports shall include any changes to the PROCESS CONTROL PROGRAM (PCP) made during the reporting period.

MONTHLY OPERATING REPORT 6.9.1.10 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the PORV's or safety valves, shall be submitted on a monthly basis to the Commission, pursuant to 10CFR50.4, l no later than the 15th of each month following the calendar month covered by the report.

Any changes to the OFFSITE DOSE CALCULATION MANUAL shall be submitted with the Monthly Operating Report within 90 days in which the change (s) was made I effective. In addition, a report of any major changes to the radioactive vaste treatment systems shall be submitted with the Monthly Operating Report for the period in which the change was implemented.

l RADIAL PEAKING FACTOR LIMIT REPORT 6.9.1.11 The F limit for Rated Thermal Power (FRTP) shall be provided to the  ;

Commission,purs[sant to 10CFR50.4, for all core plafies containing bank "D" l I centrol rods and all unrodded core planes at least 60 days prior to cycle initial criticality. In the event that the limit vould be submitted at some other time during core life, it vill be submitted 60 days prior to the date the limit vould )

become effective unless otherwise exempted by the Commission.

]

AnyinformationneededtosupportF{P will be by request from the NRC and need not be included in this report.

ANNUAL DIESEL GENERATOP RELIABILITY DATA REPORT l 6.9.1.12 1he number of tests (valid or invalid) and the number of failures to e; start on demand for each diesel generator shall be submitted to the NRC annually. This report shall contain the information identified in Regulatory 0 Position C.3.b of NRC Regulatory Guide 1.108, Revision 1, 1977.

FARLEY-UNIT 1 6-19 AMENDMENT NO.

m-I

. 4 ADMINISTRATIVE CONTROLS ANNUAL REACTOR COOLANT SYSTEM SPECIFIC ACTIVITY REPORT

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6.9.1.13 This annual report is only required when the results of specific j activity analyses of the primary coolant have exceeded the limits of Specification 3.4.9 during the year. The following information shall be included (1) Reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded (in graphic and tabular format); (2) Results of ,

the last isotopic analysis for radioiodine performed prior to exceeding the limit, results of analysis while limit was exceeded and results of one analysis after the radioiodine activity was reduced to less than the limit. Each result should include date and time of sampling and the radioiodine concentrations; (3)

Clean-up flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; (4) Graph of the I-131 concentration (micro Ci/gm) and one q other radioiodine isotope concentration (micro Ci/gm) as a function of time for the duration of the specific activity above the steady-state level; and (5) The time duration when the specific activity of the primary coolant exceeded the l radioiodine limit. 1 i

ANNUAL SEALED SOURCE LEAKAGE REPORT j

l 6.9.1.14 A report shall be prepared and submitted to the Commission on an l l

annual basis if sealed source or fission detector leakage tests reveal the presence of greater than or equal to 0.005 microcuries of removable J contamination.

SPECIAL REFORTS 6.9.2 Special reports shall be submitted to the Commission in accordance with the requirements of 10CFR50.4 vithin the time period specified for each report.

Reports should be submitted to the U. S. Nuclear Regulatory Commission, ATTN:

Document Control Desk, Washington, D.C. 20555.

6.10 RECORD RETENTION In addition to the applicable record retention requirements of Title 10, Code of Federal Regulations, the following records shall be retained for at least the minimum period indicated.

6.10.1 The following records shall be retained for at least five years:

a. Records and logs of unit operation covering time interval at each power level.

L. Records and logs of principal maintenance activities, inspections, 'l repair and replacement of principal items of equipment related to .i nuclear safety. t

c. ALL REPORTABLE EVENTS submitted to the Commission.
d. Records of surveillance activities, inspections and calibrations required by these Technical Specifications.
e. Records of changes made to the procedures required by Specification 6.8.1. p
f. Records of radioactive shipments. L
g. Records of sealed source and fission detector leak tests and results.

FARLEY-UNIT 1 6-20 AMENDMENT NO.

l

l POWER DISTRIBUTION LIMI13 SURVEI' LANCE REQUIREMENTS (Continued)

....n...........................................................................

2. When the F
  • is less than or equal to the FRTP limit for the appropriate #measuredcoreplane,additignalphve{distributionmaps at least once per shall be taken and F,y* compared to F% and F,y 'I 31 EFFD.
e. The F limit for RATED THERMAL POVER (FRTP) shall be provided for all core planes containing bank "D" control reds and all unrodded core planes in a Radial Peaking Factor Limit Report per Specification 6.9.1.11.
f. limits of e, above, are not applicable in the following core  !

The planeF,fegions as measured in percent of core height from the bottom of l the fuels

1. Lover core region from 0 to 15%, inclusive.  !

l

2. Upper core region from 85 to 100%, inclusive. j
3. Grid plane regions within 1 2% of core height around the midpoint ,

of the grids. l l 1

4. Core plane regions within + 2% of core height (+ 2.88 inches) about l the bank demand position oI the bank "D" control rods.  ;

i

g. With F exceeding F ' the effects of F on F Z) shall be evaluated to determine *if F, (Z) is within#itsl$m('ts. i 4.2.2.3 When F (Z) is measured for other than F determinations, an overall saeasured F, (Z),shall be obtained from a power di51ribution map and increased by 3% to account for manufacturing tolerances and further increased by 5% to account for measurement uncertainty.

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CONTAINMENT SYSTEMS 3/4.6.4 COMBUSTIBLE GAS CONTROL l

HYDROGEN ANALYZERS I

LIMITING CONDITION FOR OPERATION l g.

3.6.4.1 Two independent containment hydrogen analyzers shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

ACTION:

a. Vith one hydrogen analyzer inoperable: l i) restore the inoperable analyzer to OPERABLE status within 30 days or be in at least HOT STANDBY vithin the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, or
11) establish an alternate hydrogen sampling capability. l The provisions of Specification 3.0.4 are not applicable. l
b. Vith both hydrogen analyzers inoperable, restore at least one analyzer to l OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY vithin the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

SURVEILLANCE REQUIREMENTS 1

4.6.4.1 Each hydrogen analyzer shall be demonstrated OPERAEL2 at least once per 92 days on a STAGGERED TEST BASIS by performing a CHANNEL CALIBRATION using I sample gases containing:

a. Ten volume percent hydrogen, balance nitrogen, for zero check.
b. Ten volume percent hydrogen, balance nitrogen, mixed with compressed air, for span check.

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l l FARLEY-UNIT 2 3/4 6-19 AMENDMENT NO.

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l RADIOACTIVE EFFLUENTS 3/4.11.4 TOTAL DOSE i l

I LIMITING CONDITION FOR OPERATION

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3.11.4 The dose or dose commitment to any member of the public, due to releases of radioactivity and radiation, from uranium fuel cycle sources shall be limited i to less than or equal to 25 mrem to the total body or any organ (except the thyroid, which shall be limited to less than or equal to 75 mrem) over 4 consecutive quarters. i l

I APPLICABILITY: At all times. l ACTION:

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a. Vith the calculated doses from the release of radioactive materials in l liquid or gaseous effluents exceeding twice the limits of Specification 1 3.11.1.2.a, 3.11.1.2.b, 3.11.2.2.a, 3.11.2.2.b, 3.11.2.3.a, or 3.11.2.3.b, prepare and submit a Special Report to the Commission, pursuant to Specification 6.9.2, within 30 days, which defines the l

corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the limits of Specification 3.11.4. This Special Report shall include an analysis which estimates the radiation exposure (dose) to a member of the public from uranium fuel cycle sources (including all effluent pathways and direct radiation) for a 4 ]

consecutive quarter period that includes the release (s) covered by this report. If the estimated dose (s) exceeds the limits of Specification ,

3.11.4, and if the release condition resulting in violation of 40CFR190 has not already been corrected, the Special Report shall include a requect Sr a variance in accordance with the provisions of 40CFR190 and including the specified information of 5 190.11(b). Submittal of ,

the report is considered a timely request, and a variance is granted 1 until staff action on the request is complete. The variance only  !

relates to the limits of 40CFR190, and does not apply in any way to the requirements for dose limitation of 10CFR Part 20, as addressed in other sections of this technical specification. l

b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.  !

1 SURVEILLANCE REQUIREMENTS 4.11.4 Dose Calculations Cumulative dose contributions from liquid and gaseous d effluents shall be determined in accordance with Specifications 4.11.1.2, 4.11.2.2, and 4.11.2.3, and in accordance with the ODCH.

6 FARLEY-UNIT 2 3/4 11-19 AMENDMENT NO.

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ADMINISTRATIVE CONTROLS 1

6.9 REPORTING REQUIREMENTS ROUTINE REPORTS 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the Commission, I pursuant to 10CFR50.4.

STARTUP REPORT 6.9.1.1 A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured.by a different. fuel-supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant.

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6 FARLEY-UNIT 2 6-15a AMENDMENT NO.

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ADMINISTRATIVE CONTROLS

e. Type of container (e.g., LSA, Type A, Type B, Large Quantity), and
f. Solidification agent (e.g., cement, urea formaldehyde).

The radioactive effluent release reports shall include unplanned releases from the site to unrestricted areas of radioactive materials in gaseous and liquid I

effluents on a quarterly basis.

The radioactive effluent release reports shall include any changes to the PROCESS CONTROL PROGRAM (PCP) made during the reporting period.

MONTHLY OPERATING REPORT 6.9.1.10 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the PORV's or safety valves, shall be submitted on a monthly basis to the Commission, pursuant to 10CFR50.4, l no later than the 15th of each month following the calendar month covered by the report.

1 Any changes to the OFFSITE DOSE CALCULATION MANUAL shall be submitted with the t Monthly Operating Report within 90 days in which the change (s) was made j effective. In addition, a report of any major changes to the radioactive vaste j treatment systems shall be submitted with the Monthly Operating Report for the '

period in which the change was implemented.

i RADIAL PEAKING FACTOR LIMIT REPORT i 6.9.1.11 The F limit for Rated Thermal Power (FRTP shall be provided to the Commission, purs6 ant to 10CFR50.4, for all core p15Ees)containing' bank "D" l control rods and all unrodded core planes at least 60 days prior to cycle initial criticality. In the event that the limit vould be submitted at some other time during core life, it will be submitted 60 days prior to the date the limit vould become effective unless otherwise exempted by the Commission.

Any information needed to support F RTP vill be by request from the NRC arid need not be included in this report.

1 ANNUAL DIESEL GENERATOR RELIABILITY DATA REPORT 6.9.1.12 The number of tests (valid or invalid) and the number of failures to '

start on demand for each diesel generator shall be submitted to the NRC '!

annually. This report shall contain the information identified in Regulatory ,^,

Position C.3.b of NRC Regulatory Guide 1.108, Revision 1, 1977.

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1 il FARLEY-UNIT 2 6-19 AMENDMENT NO.

4 ADMINISTRATIVE CONTROLS

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ANNUAL REACTOR COOLANT SYSTEM SPECIFIC ACTIVITY REPORT 6.9.1.13 This annual report is only required when the results of specific activity analyses of the primary coolant have exceeded the Ifmits of Specification 3.4.9 during the year. The following information shall be included: (1) Reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded (in graphic and tabular format); (2) Results of the last isotopic analysis for radioiodine performed prior to exceeding the L limit, results of analysis while limit was exceeded and results of one analysis after the radioiodine activity was reduced to less than the limit. Each result should include date and time of sampling and the radioiodine concentrations; (3)

Clean-up flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in'which the limit was exceeded; (4) Graph of the I-131 concentration (micro Ci/gm) and one other radioiodine isotope' concentration (micro Ci/gm) as a function of time for the duration of the specific activity above the steady-state level; and (5) The time duration when the specific activity of the primary coolant exceeded the radioiodine limit.

l ANNUAL SEALED SOURCE LEAKAGE REPORT 6.9.1.14 A report shall be prepared and submitted to the Commission on an annual basis if sealed source or fission detector leakage tests reveal the l

presence of greater than or equal to 0.005 microcuries of removable contamination.

SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the Commission in accordance with the requirements of 10CFR50.4 within the time period specified for each report.

Reports should be submitted to the U. S. Nuclear Regristory Commission, ATTN:

Document Control Desk, Vashington, D.C. 20555.

6.10 RECORD RETENTION l In addition to the applicable record retention requirements of Title 10, Code of Federal Regulations, the following records shall be retained for at least the minimum period indicated.

6.10.1 The following records shall be retained for at least five years:

a. Records and logs of unit operation covering time interval at each power level.
b. Records and logs of principal maintenance activities, inspections, repair and replacement of principal items of equipment related to o nuclear safety. ,
c. ALL REPORTABLE EVENTS submitted to the Commission. l l d. Records of surveillance activities, inspections and calibrations required by these Technical Specifications. -
e. Records of changes made to the procedures required by Specification 6.8.1. 3
f. Records of radioactive shipments. d
g. Records of sealed source and fission detector leak tests and results. I s

FARLEY-UNIT 2 6-20 AMENDMENT NO.

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i ATTACHMENT 2 l

Significant Hazards Evaluations -

Pursuant to 10CFR50.92 1 a

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' . J Significant Hazards Evaluation Pursuant To 10CFR50.92 For The Proposed Change To FNP Units 1 and 2 Power Distribution Limits Technical Specification Proposed Change ChangeSpecification4.2.2.2.f.3tomoreaccuratelydefinethegridplangTP regions of the core for which flux map data is ignored for determining F, compliance. 4 i

Background

Specification 4.2.2.2.f.3 currently defines the grid plane regions as a percentage of core height of 17.8 + 2%, 32.1 + 2%, 46.4 + 2%, 60.6 + 2% and

~

74.9 + 2%. The location of the grTd should be ignored when determining F,R9)ofanes because determine the grid straps. th~se The regions that concern is that the grid planes appeaf to be set at a percentage of core I height based on grid locations applicable to the initial core. Subsequent changes to the end plug design have effectively raised the grid heights above the bottom of the active core. This proposed change vill define the grid plane region based on 2% of core height around the midpoint of the grids. A 2% level establishes a grid region of influence and accommodates fuel assembly ,

and rod growth and manufacturing tolerance, as well as the effective changes I in grid location due to fuel rod design changes.

Analysis l

l Alabama Power Company has reviewed the requirements of 10CFR50.92 as they j relate to the proposed power distribution limits technical specification change and considers this change not to involve a significant hazards consideration. In support of this conclusion, the following analysis is provided: j l

1. The proposed change vill not increase the probability or I consequences of an accident previously evaluated because the ,

proposed change does not affect the intent of the specification, but instead corrects a misleading statement that may not reflect existing plant configuration. The regions that should be ignored l because of anomalies created by grid straps are easily recognized '

during flux mapping. Therefore, the probability or consequences of an accident previously evaluated vill not be increased.

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Significant Hazards Evaluation Pursuant'To 10CFR50.92 For The Proposed Change To FNP Units 1 and 2 Power Distribution Limits 3 i

Technical Specification Page 2 l 1

2. The proposed change vill not create the possibility of a new or-different kind of accident from any accident previously evaluated  !

because the proposed change is only a clarification of an existing i technical specification statement. The regions that should be ignored because of anomalies created by grid straps are easily l recognized during flux mapping. Therefore, the possibility of a nev l or different kind of accident from any previously' evaluated.does not i 1

exist.

3. The proposed change vill not involve a reduction in a margin of safety because the proposed change does not relax the restrictions for determining FRTP The regions that should be ignored because of i anomaliescreated"by. grid straps are easily recognized during flux mapping. Therefore, no reduction of safety margin vill result from-this change.

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Conclusion Based upon the analysis provided herewith, Alabama Power Company has determined that the proposed change to the technical specifications vill not increase the probability or consequences of an accident previously evaluated, create the possibility of a new or different kind of accident from any 4 accident previously evaluated, or involve a reduction in a margin of safety.

Therefore, Alabama Power Company has determined that the proposed change meets the requirements of 10CFR50.92(c) and does not involve a significant hazards i l

consideration.

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Significant Hazards Evaluation Pursuant To 10CFR50.92 For The Proposed Change To FNP Units 1 and 2 Technical Specification Proposed Change Correct misspelled words and makes editoria) changes on Table 3.3-3 and Table 4.3.4. Incorporate title change in the offsite organization. Incorporate NRC ,

correspondence addressee changes per 10CFR50.4. l

Background

Item 3.c.2 of Table 3.3-3 " Engineered Safety Feature Actuation System Instrumentation" currently has the word " automatic" ntisspelled. The first i I

footnote of Table 4.3-4 " Seismic Monitoring Instrumentation Surveillance i Requirements" currently has the word " manual" misspelled and the word "of" written twice. The second footnote on Table 4.3-4 is being updated to state the current recalibration schedule for seismic instrumentation. Additionally, a third footnote is being added.for Unit 2 to provide information on the location of the sensors. The word " planes" in Specification 4.2.2.2.f has been I corrected to read " plane". 10CFR50.4 provides detailed instructions regarding the addressee of correspondence to the NRC. l l

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Analysis l

Alabama Power Company has reviewed the requirements of 10CFR50.92 as they relate to the proposed technical specification change and considers this change not to involve a significant hazards consideration. In support of this conclusion, the following analysis is provided:

l 1. The proposed change vill not increase the probability or consequences of an accident previously evaluated because the l i proposed change only corrects misspelled words and makes editorial  !

changes. Therefore, the probability or consequences of an accident previously evaluated vill not be increased.

2. The proposed change vill not create the possibility of a new or r different kind of accident from any accident previously evaluated because the proposed change only corrects misspelled words and makes editorial changes. Therefore, the possibility of a new or different kind of accident from any previously evaluated does not exist.
3. The proposed change vill not involve a reduction in a margin of safety because the proposed change only corrects misspelled words and makes editorial changes. Therefore, no reduction in a margin of safety will result from this change.
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'Significant' Hazards'Ehalua'tdonPusuantTo L10CFR50.92 For The. Proposed Change.To FNP Units 1'and 2 Technical. Specification Page 2 o

Conclusion

-Based upon the analysis provided herewith,' Alabama Power: Company.has oq determined that the proposed change to the. technical; specifications'vil1:not 3 increase the probability or consequences of an accident'previously evaluated, .l

' create the' possibility;of a new or different' kind of accidentLfrom any.

! accidentipreviously evaluated, orcinvolve a reduction 11n a' margin of-safety.~.

Therefore, Alabama Power Company has determined that the' proposed change meets the requirements of 10CFR50.92(c) and does not involve a significant hazards

, consideration.

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Significant Hazards Evaluation Pursuant to 10CFR50.92 for the Proposed FNP Units 1 and 2 Loss of Power Undervoltage Relay Trips Technical Specification Change Proposed Change

1. Remove "and" from the Unit 1 allowable value for degraded voltage.
2. Revise footnote for allowable values to eliminate reference to Figure 3.3-1. Replace footnote with a reference to appropriate relay setting sheet for calibration requirements.
3. Eliminate Figure 3.3.1, page 3/4 3-28a, from Technical Specifications.

Background

1. The use of "and" for the Degraded Voltage allovable value for Unit 1 should be removed as an editorial correction. It is redundant.
2. Figure 3.3-1 was originally placed in the Technical Specifications to show the inverse time characteristic of the Loss of Voltage and Degraded Voltage relays and was derived from the vendor's technical manual. The curve is not utilized for calibration purposes. In accordance with the vendor's technical manual, calibration is required at one point only.

Thus, Figure 3.3-1 may be removed from the Technical Specifications and calibration requirements need only be referenced to the appropriate relay

.= sting sheets which specify the manufacturer's required value for relay trip time versus a given voltage drop. In addition, design data concerning time dial settings, tap voltage and potential transformer ratio are all contained in controlled documents subject to the provisions of 10CFR50.59.

Analysis Alabama Power Company has reviewed the requirements of 10CFR50.92 as they relate to the proposed technical specification change and considers this change not to involve a significant hazards consideration. In support of this conclusion, the following analysis is provided:

1. The proposed change vill not increase the probability or consequences of an accident previously evaluated because the proposed change does not change the setpoints or the allowable values for those setpoints. It only clarifies the calibration check process. Therefore, the probability or consequences of an accident previously evaluated vill not be increased.
2. The proposed change vill not create the possibility of a new or different kind of accident from any accident previously evaluated because the proposed change is merely an editorial clarification of the original specification intent. Therefore, the possibility of a new or different kind of accident from any previously evaluated does not exist.

l' Significant Hazards Evaluation Pursuant To 10CFR50.92 for the Proposed FNP Units l'and 2 Loss of Power Undervoltage Relay Trips Technical Specification Change Page 2 l

3.- The proposed change will not involve a reduction in a margin of safety because the proposed change maintains the same margins as previously analyzed in that the allowable values remain unchanged. Therefore, no reduction in a margin of safety will result from this change.

l Conclusion Based upon the analysis provided herewith, Alabama Power Company has determined that the proposed change to the technical specificatioris,will not increase the probability or consequences of an accident previously evaluated, f create the probability of a new or different kind of accident from any_

}

accident previously evaluated, or involve'a reduction in a margin of safety..

Therefore, Alabama Power Company has determined that the proposed change meets the requirements of 10CFR50.92(c) and does not involve'a significant-hazards consideration.

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Significant Hazards E0aluation Pursuant To 10CFR50.92 For The Proposed Change To-FNP Units 1 and 2 Hydrogen Analyzer Technical Specification L

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Proposed Change Add a statement to Specification 3.6.4.1.a.that disclaims the provisions of Specification 3.0.4 which requires.that entry-into an operational mode shal1~

not be made unless the conditions of the limiting condition for operation are )

met without reservation. Also included'in this change is the ability to 1 1

establish an alternate hydrogen sampling capability with an inoperable j hydrogen analyzer. .In addition, the word monitor has been replaced by analyzer'for Unit 2.-

Background

Determination of containment hydrogen concentration during post-LOCA-J conditions is required to determine the method of. hydrogen control to be-utilized. This change vill allow startup of-the plant with.one hydrogen analyzer inoperable.

Analysis Alabama Power Compcny has re'.ieved the requirements of 10CFR50.92 as they relate to the proposed hydrogen analyzer technical specification change and considers this change not to involve a significant hazards consideration. In support of this conclusion, the following analysis is provided:

1. The proposed change vill not increase the probability or j consequences of an accident previously evaluated because the proposed change does not eliminate the requirement to monitor j hydrogen concentration inside containment during Modes 1 and.2.

This change vill allow startup of the plant with one hydrogen j analyzer inoperable. Hydrogen concentration can be determined with one analyzer inoperable by use of the redundant hydrogen analyzer and by local sampling using existing approved plant post-accident sampling procedures.-

2. The proposed change vill not create the possibility of a new or j different kind of accident from any accident previously evaluated l because the proposed change does not alter the intent of:the specification. Redundant monitoring of hydrogen-concentration can be performed with one hydrogen analyzer inoperable during plant .l startup by means of post-accident sampling procedures. Therefore, possibility of a new or different kind of accident from any

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i' previously evaluated does not exist.

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-Significant Hazards Evaluation Pursuant To 10CFR50.92 For The Proposed Change:To i

-FNP Units l'and 2 Hydrogen Analyzer Technical. Specification Page 2

3. The proposed change will not involve a reduction in a margin of safety 4 because the proposed change does not lessen the requirements for $

monitoring hydrogen concentration. The proposed change allows for an

-alternative method for monitoring hydrogen concentration with one hydrogen analyzer inoperable during plant.startup. .Therefore, no. I reduction of margin of safety will result from this change. l

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Conclusion )

Based upon the analysis provided herewith, Alabama Power Company has determined that the proposed change to the technical specifications vill not increase the probability or' consequences of an accident previously evaluated, create the possibility of a new or different kind of accident from'any j accident previously evaluated, or involve a reduction in a margin of safety.

Therefore," Alabama Power Company has determined that the proposed change meets the requirements of 10CFR50.92(c) and does not inv'olve a significant  !

' hazards consideration.

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