ML20087D335

Proposed TS Pages 6-19 Re Radial Peaking Factor Limit Rept

ML20087D335
Person / Time
Site:	Farley
Issue date:	01/10/1992
From:	SOUTHERN NUCLEAR OPERATING CO.
To:
Shared Package
ML20087D332	List: ML20087D330 ML20087D335
References
NUDOCS 9201160098
Download: ML20087D335 (5)

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ATTACHMENT 1 Unit 1 EcX1LLQn Page 6-19 Replace Unit 2 Revision Page 6-19 Replace l

+9201160098 920110

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e. Type of container (e.g., LSA, Type A, lype B, large Quantity) and l

f. Solidification agent (e.g., cement, urea formaldehyde).

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

effluents on a quarterly besis.  !

The radioactive effluent release reports shall inclu<'e any changes to the PROCESS CONTROL PROGRAM (PCP) made during the reporting portod.

MONTHLY OpERATil{Q JEp0RT 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 10 CfR 50.4, no ,

later than the i5th of each month following the calendar month covered by the i 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 effect;vo. In addition, a re) ort of any major changes to the radioactive waste trettment systems shall be su)mitted with the Monthly Operating Report for the perti in which the change was implemented.

RADJAL PEAKING EACTOR LIMIT REPORT i 6.9.1.11.The fx# l"imit for Rated Thermal power FEf)forallcore) lanes  !

containing bank D control' rods and all unrodde core planes shall se ,

established and documented in the Radial Peaking factor Limit Repor+ before  :

and provided to the Commission, pursuant f each to 10 CFRreload cycle 50.4, upon(prior to MODE issuance. in t 2) he event that the limit would be submitted at some other time during core life, it will be submitted upon issuance, unless otherwise exempted by the Commission. .

-Any-informationneededtosupportf[willbebyrequestfromtheNRCandneed not be-included in this report.

ANNUAL DIESEL QLtiERATOR RELIABILITY DATA REPORT S.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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! FARLEY-UNIT 1 '6-19 AMENDMENT NO.

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i FN((111B.ATIVE CQ11TROLS  !

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

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

i MONTHLY OpERATil1G REPORT 6.9.1.10 Routinb reports of operating statistics and shutdown experience, i including documentation of all challenges to the PORV's or safety valves, shall be submitted on a monthly basis to the Comission, pursuant to 10 CFR 50.4, 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 ef fective.- In. addition, a re) ort of any major changes to tha radioactive waste treatment systems shall be su)mitted with the Monthly Operating Report for the ,

period in which the change was implemented.

RADIAL PEAKING FAC10R LIMIT REEQB1 6.9.1.11 The Fxyl imit for Rated Thermal Power (f$ f ) for all core slanes I containing bank 'D" control rods and 611 unrodded core planes shall be established and documented in the Radici Peaking factor Limit Report before each reload cycle-(prior to MODL 2) and provided to the Commission, pursuant to 10 CFR 50.4, upon issuance, in the event that the limit would be submitted l

at some other time during core life, it will be submitted upon ism.nce, unless j otherwise exempted by the Commission.

Any information'needed to support FE}P will be by request from the NRC and need L not be included in this report.

$NNUAL DIESEL GENERATOR RLLIABillTY DATA REEQEI 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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FARLEY-UNIT 2 6-19 AMENDMENT NO.

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i Evaluation of No Significant Hazards Consideration  :

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SIGHlflCANT HAZARDS CONSIDERATION ANALYSIS Administrative Chance for Radial Peakina f actor Li.mit Reportinu The current reporting requirement for radial peaking factor limit reporting in Section 6.9.1.11 of the f ar'. y Technical Specifications is 60 days prior to criticality. To allow for more flexibility after shutdown, in particular for emergency cor redesigns, this reporting requirement has been revised to require submittal before each reload cycle. The new requirement is consistent with reporting requirements for Core Operating Limits Reports (COLRs). There are no safety analyses or design criteria that are sensitive to this administrative change, and the same reporting requirements will be continued to be met for the reporting time limit change.

Based on the information presented above, the following conclusions can be reached with respect to 10 CFR 50.92:

1. Since the reporting requirements are an administrative change, this change does not involve a significant increase in the probability or consequences of an accident previously evaluated in the Farley FSAR.

With the exception of the reporting schedule, no other changes to the reporting requirements are made.

2. This administrative char 7e in reporting requirements does not create the possibility of a new or different kind of accident from any previously evaluated in the farley FSAR since only the time for reporting requirements has changed. Therefore, the probability of a new or different kind of accident is not created.

3. Th's administrative change is not safety related and therefore does not involve any reduction in the margin of safety.

Based on the preceding information, it has been determined that the proposed change in re>orting times for the radial peaking factors does not inso've a significant lazards consideration as defined in 10 CFR 50.92 (c).

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