ML20205S997
| ML20205S997 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 04/19/1998 |
| From: | SOUTHERN NUCLEAR OPERATING CO. |
| To: | |
| Shared Package | |
| ML20205S953 | List: |
| References | |
| FNP--M-11, FNP-0-M-011, NUDOCS 9904270108 | |
| Download: ML20205S997 (10) | |
Text
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- FNP-0-AP-1
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. PROCEDURE REOUEST FORM
- 1. Procedure Number FmP-o- H-oll /I O Procedure Title 04 sat Ocx C. A e i<A a., /1cie.7 vision Number R
U N SafetyRelated
[] Non-Safety Related
[] New Procedure Request R Procedure Revision.. ....
[] Procedure To Be Voided
..New Revision Number /b
[] Temporary Change Effective Until Next Permanent Revision... .. ..TCN
[] Temporary Change To Be Voided.. .... .
. . . . . . . ..TCN
[] Temporary Change One Time Only or Reg'd by Plant Conditions.. ..TCN Dates this temporary change is effective: From Through
[] This Procedure is an infrequently performed test or evolution.
- 2. Change Summary 2.1 Procedure Page Num
/0-1 +v / 09 r ) Affecte{+by 4suf e Change (s)_
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2.2 Description of Change (s) w <Nad d UNCONTaOLLEO COPY 0 CAUTION: m.copywmewn.o 2.3 Reason (s) for Change (s) 54r o b h *W .; g .__-ye - o-mg v
- 3. Prepared By^~
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'l(ijle Date i l
- 4. Reviewed By Signature 3 M_( Title _ c2 0 18 date
- 5. Cross-Di:ciplinary/PORC Review
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- 6. Temporary Change Approval (Signature /Date)
[] Member Group Staff / i
[] Shift Foreman -/
[] Senior Reactor Operator )
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[] Nuclear Plant General Manager /
- 7. Final Approval (Signature /Date, required within 60 days of temporary approval)
[ Group Supervisor a.., i _ 1 /
Manager /r# U/ mil #' N.'e V(7 SAERM " /
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[] Vice President - Project /
Nuclear Plant General Manauer /LG/A./> /4,//1 /
9904270108 990421 i PDR ADOCK 05000348 Page1of1 Revision 35 !
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' 02/04/98 12:06:37 FNP-0-AP-1 FIGURE 3 PROCEDURE: FNP-0-M-011 REVISION: 16
2.2 DESCRIPTION
OF CHANGE - 2.3 REASON FOR CHANGE PG.1-1 Changed name of" Annual To correct the name of the report. !
Radiological Environmental Surveillance '
Report"to " Annual Radiological Environmental Operating Report" PG. 4-4 Deleted " yearly" from the Type and This sample collection and analysis frequency Frequency Analysis for Sediment Samples is semiannually; this change is made to correct the analysis frequency.
PG. 4-14 Sample Identification for the North To correct sample location identification (it is a Boundary Forage Indicator Station changed to one mile distant sample point.)
"FI-1601" from "FI-1606" '
PG. 4-13 and 4-14 Changed River Mile The normal sampling location has been River location for Control Station Sediment and Fish Mile 47.8 but this has been incorrectly rounded from 47 to 48. down to 47. This change makes the sampling location more ac.arate by rounding up to 48.
PG. 4-13 and 4-14 Added explanatory - To improve procedural guidance and to address footnotes for the collection of river sediment SAER finding as documented in CAR #2283 and fish samples. Renumbered existing and OR #973050, and # 973114 due to the footnote for forage samples. need for a sample area range as opposed to a :
specific sample point. i PG.10-2 & 10-3 Modified definition of To modify the definition to match that
" Member of the Public". provided in 10CFR 20.1003.
PG.10-4 to 10-7 Rollover Rollover changes only- no text changes made.
O Page1of1 Revision 35 J
lFARLEY NUCLEAR PLANT 10 CFR 50.59 EVALUATION FORM SHEET 1 OF 5 SECTION A: IDENTIFICATION O Unit Number: O One OTwo e Shared DOCUMENTTITLE OR NUMBER: REVISION /TCN#: .lfi.
Offsite Dose Calculation Manual (ODCM)
SECTION B: 10 CFR 50.59 SCRFFNING Does the document to which this evaluation applies represent:
- 1. O Yes a No A change to the facility as described in the FSAR?
Basis for Answer:
The proposed changes for the ODCM are in reference to the Radiological Environmental Monitoring Program (REMP). None of these changes involve any physical change to the facility as described in the FSAR.
- 2. m Yes O No A change to procedures described in the FSAR?
Basis for Answer:
The ODCM is referenced in the FSAR and thereby in accordance with NEI %-07 (Guidelines for O- 10 CFR 50.59 Safety Evaluations), the ODCM is regarded indirectly as a procedure described in the FSAR. The changes on pages 1-1, & 10-2 to 10-7 are administrative in nature. The change on page 4-4 changes the analysis frequency ofsediment samples, and the changes on pages 4-13
& 4-14 enhance the description of fish and sediment sample locations on the river.
- 3. O Yes a No A test or experiment not described in the FSAR7 Basis for answer:
These proposed changes to the ODCM do not involve putting the plant in a unique or abnormal condition or configuration and thereby do not constitute a text or experiment.
- 4. O Yes a No A change to the Technical Specifications?
, Basis for answer:
While the Technical Specifications do mention and briefly describe the ODCM, these,, changes to the ODCM do not change the programmatic controls for radioactive effluents contained in the Technical Specifications. The proposed changes will not affect the availability or operational characteristics of any equipment, structure or component governed by the Technical Specifications. i If questions 1,2, or 3 in Section B are answered "Yes", then PORC review of the safety evaluation (Section D) is required prior to implementation. If question 4 in section B is answered "yes", contact Nuclear Licensing before continuing.
]
Gen. Rev. 3 j j
lFARLEY NUCLEAR PLANT 10 CFR 50.59 EVALUATION FORM SIEET2 OF 5 j SECTION C: SIGNATURES P sy-si. bd ate: /2-2*f7 Approved By: Date:
Reviewer: Date: D-lM FNP Approved: 'b Date: 2-/*f7 l Reviewed By: Date: PORC Review: gg/ $1 Y?s
, cDate: regy o Reviewed By: Date: NORB Review: Date:
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Gen. Rev. 3
FARLEY NUCLEAR PLANT 10 CFR 50.59 EVALUA'I1ON FORM SHEET 3 OF 5 SECTION D: 10 CFR 50.59 SAFETY EVALUATION .
- 1. O Yes e No May the proposed activity increase the probability of an accident previously evaluated in the FSAR7 Basis for answer:
The proposed changes to the ODCM are administrative in nature to correct or clarify information contained in the ODCM. The proposed activity does not involve physical changes to the plant nor changes to instrument set points or operating parameters. The proposed activity will not degrade the ability of any system, structure or component to perform its designed function.
Therefore, the proposed activity will not increase the probability of occurrence of an accident previously evaluated in the FSAR.
- 2. O Yes E No May the proposed activity increase the consequences of an accident previously evaluated in the FSAR7 Basis for answer:
The proposed changes are admini*ative in nature and involve the REMP program described by the ODCM. The proposed changes do not cause changes in the processing of radiological effluents. The proposed changes will not alter any conditions or assumptions on which the FSAR accident analyses are based nor will they affect a structure, system or component which is required to mitigate the consequences of an accident. Thus, the proposed changes will not increase the consequences of an accident previously evaluated in the FSAR.
- 3. O Yes W No May the proposed activity increase the probability of occurrence of a malfunction of equipment important to safety previously evaluated in the FSAR7 Basis for answer:
The proposed activity consists of administrative changes to the ODCM and does not change the way safety-related equipment is operated or maintained. The proposed activity will not introduce any new system interaction or adversely impact the reliability of any equipment important to safety. The proposed activity will not degrade the ability of any system, structure or component to perform the safety functions described in the FSAR. Thus, the proposed changes will not increase the probability of occurrence of a malfunction of equipment important to safety previously evaluated in the FSAR.
- 4. O Yes E No May the proposed activity increase the consequences of a malfunction of equipment important to safety previously evaluated in the FSAR?
Basis for answer: .
The proposed changes are admini*ative in nature and do not change the processing of radiological effluents. The proposed changes do not change any conditions or assumptions previously made in evaluating the consequences of a malfunction of equipment important to safety as discussed in the FSAR, nor will they affect any structure, system, or component which is required to mitigate the radiological consequences of an accident. Thus, the proposed changes to !
the ODCM will not increase the consequences of a malfunction of safety-related equipment )
previously evaluated in the FSAR Gen. Rev. 3
lFARLEYNUCLEAR PLANT 10 CFR 50.59 EVALUATION FORM SHEET 4 OF 5 SECTION D: 10 CFR 50.59 SAFETY EVALUATION (CONTINUED)
- 5. D Yes a No May the proposed activity create the possibility of an accident of a different type than any previously evaluated in the FSAR7 Basis for answer:
The proposed changes to the ODCM are administrative in nature to correct information contained in the ODCM and to enhance the REMP sampling program. The proposed changes do not involve any physical change to the plant or to the way in which any system, structure or component is operated or maintained. Consequently, the proposed changes do not introduce a different type of failure or make any existing failure probability more credible. Therefore, the proposed changes will not create the possibility of an accident of a different type than any previously evaluated in the FSAR.
- 6. O Yes u No May the proposed activity create the possibility of a malfunction of equipment important to safety of a different type than any previously evaluated in the FSAR7 Basis for answer.
The proposed changes to the ODCM are administrative in nature and do not result in any new system interactions or change the way in which any system, structure or component is operated or maintained. The proposed changes do not introduce any new failure modes or limiting single failures. Therefore, the proposed changes will not create the possibility of a malfunction of equipment important to safety of a different type than any previously evaluated in the FSAR.
- 7. O Yes a No Does the proposed activity reduce the margin of safety as defined in the basis for any Technical Specification?
Basis for answer:
The pieposed changes to the ODCM are administrative in nature and w:.ll not adversely impact the availability or capability of any system, stmeture or component that is govemed by or required to be operational in the Technical Specifications. Therefore, the proposed changes will not reduce the margin of safety as defined in the basis for any technical specification.
If the answer to ANY of the seven questions in Section D fa "YES", an unreviewed safety question may be indicated. Approval from the NRC is required haforc the document / activity may be implemented.
O O
Gen.Rev.3
(iTJtLEY NUCLEAR PLANT 10 CFR $0.59 EVALUATION FORM SHEET 5 OF 5 l SECTION E SAFETY EVALUATION WRITTEN DESCRIPTION O Unit Number: O One DTwo e Shared a
DOCUMENT TITLE OR NUMBER: REVISION /TCN#: 16.
References:
- 1. NRC Regulatory Guide 4.8 (For Conunent) " Environmental Technical Specifications for Nuclear Power Plants", December 1975.
- 2. NRC Radiological Assessment Branch Technical Position, "An Acceptable Radiological Environmental Monitoring Program", Revision 1, November 1979.
- 3. NUREG-1301, "Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Pressurized Water Reactors", April 1991.
Rekomima On ODCM Page 1-1 (near the middle of the page), the Annual Radiological Environmental Operating Report is inconectly referred to as the Annual Radiological Environmental Surveillance Report. The correct name of the report should be given.
On ODCM Page 4-4 (the first sheet of Table 4-1) regarding the Sediment Samples, the collections frequency is listed as semiannually and the frequency of analysis is listed as yearly. The word " yearly" should be deleted so that the Type and Frequency of Analysis Column should read " Gamma isotopic analysis of each sample" On ODCM Page 4-14 (the third sheet of Table 4-4) regarding the Forage Indicator Station on the North Perimeter, the Sample Identification is incorrectly listed as FI-1606. The Sample Identification for this sampling location should be changed to FI-1601.
The locations for the collections of the various samples in the REMP are provided in ODCM Table 4-4. The locations for the collections of river sediment and fish samples on ODCM Pages 4-13 and 4-14 respectively, need to be described more accurately. The Control Station - Sediment and Fish samples have normally been taken at river mile 47.8 although the mileage in the Table 4-4 had been mistakenly rounded down to 47. This change makes the mileage location more accurate by rounding up to 48. Explanatory footnotes should be inserted on page 4-14 to indicate that stretches of the river up to a few miles are permitted to obtain adequate samples.
On ODCM Pages 10-2 and 10-3, the definition of Member of the Public is modified to match that provided in 10 CFR 20.1003.
ODCM Pages 10-4 to 10-7 changed due to word processor pagination realignment.
O The ODCM a.es P referenced abeve have been ma,*ed un te shew the ,re,esed chan.es:
these pages are attached.
Gen. Rev. 3
FNP-0-M-011 es December 2, 1997 V)
( Revision 16 l
l l
I i
SOUTHERN NUCLEAR OPERATING COMPANY j JOSEPH M. FA*.tLEY NUCLEAR PLANT FNP-0-M-011 I
i OFFSITE DOSE CALCULATION MANUAL S
A !
PROCEDURE USAGE REQUIREMENTS-per FNP-0-AP-6 SECTIONS F l E !
/"N Continuous Use T k Y Reference Use l R
Information Use ALL E L
A T l E
UNCONTROLLED COPY D Approved: CAUTION:n==eyamim nu cunent. Do not use h a Safety Related ActMty.
Nuclear Plant - General Manager
~
Date Issued:
List of Effective Paces Page Rev.
i to 4-13,4-15 to 4-16,4-18 to 10-8 13 4-14,4-17 14 viii,4-10,7-2 15
,-~. 1-1, 4-4, 4-13, 4-14, 10-2 to 10-7 16 N,_,1
FNP-0-M-011 Table 4-4 (contd). Radiological Environmental Monitoring Locaticus (h 1 mummmmmuumm LI Exposure Pathway Sample and/or Sampling Locations, Identifi-Sample cation
- 4. INGESTION Milk Indicator Station:
None (There are no milk animals within 5 miles per the current land use survey)
Control Station:
Bruce Ivey Dairy MB-1212 Webb, AL (W-12 miles)
Fish Indicator Station:
Smith Bend (River Mile - 41)4 Game Fish FGI l Bottom Feeding Fish FBI Control Station:
Andrews Lock & Dam Reservoir (River Mile - 48)4 l Game Fish FGB Bottom Feeding Fish FEB Forage or Indicator Stations:
Leafy South Southeast Perimeter (SSE-1.0 miles) FI-0701 Vegetation North Perimeter (N-0.8 miles) FI-1601 South Perimeter (S-1.0 miles)$ pr.ogot l g-w Northeast Perimeter (NE-1.0 miles)5 FI-0201 k, / Control Station:
Dothan, AL (W-18 miles) FB-1218 l Distance and direction as measured from the centerpoint between Unit 1 and Unit 2 plant vent stacks.
- 1. Not required by Section 4.1.1. Used as a spare station.
- 2. Not required by Section 4.1.1. Use for comparison purposes with State of GA EPD.
- 3. These collections are normally made at river mile 41.3 for the indicator station and mile 47.8 for the control station; however, due to river bottom sediment shif ting caused by high flows, dredging, etc., collections may' be made from river mile 40 to 42 for the indicator station and from river mile 47 to 49 for the control station.
- 4. Since a few miles of river water may be needed to obtain adequate fish samples, these river mile positions represent -
the approximate locations about which the catches are taken.
Collections for the indicator station should be from river mile 37.5 to 42.5 and for the control station from river mile 47 to 52. (CAR 2283)
- 5. Alternate forage plots.
O 4-14 Rev. 16
FNP-0-M-011
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