ML20006C036
| ML20006C036 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 01/12/1990 |
| From: | Murphy T DETROIT EDISON CO. |
| To: | |
| References | |
| NUDOCS 9002060222 | |
| Download: ML20006C036 (58) | |
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4 b. r.* * * * * * * * ' UFSAR CONTROLLED
- 5) Sect 6on(s), Table (s), F6aure(s), etc. Affected (Attach marked-up poses)
Ficevets S /- S (6, S./-S (t),5.I-s (s L4.1-27,7. 5 -12 (r ) 7. 5 -12(2) . *1. 5 -12 (5 )
C) Reesen for Change t.0 C W50 VALv55 r, n st - om 6 m e t -an4o . i.mul . q w mm-wK cmM w5 cmh t-2ce isncs D) Reference and sourse Documents (identify)
EDP Tech Spec PDC Procedure ABN / 0 9 0 5 - / , PS v. O SE (Attached) SS-0200 DER 5 5 - / 5 /. '? PE (Attached)
Test Effectiveness Review (Attached) I JYes PqNo Other '
Drawines, Design Calculations. Correspondence, etc.
p..... ... . ....... ........... . PAR T 2 : OPERATING LICENSE CHANGE 5 I ]NA ";;""";;";";;"I A) Document
[ ] Operating License [ ] Tech Specs [ ] Environmental Protection Plan
) Tech Spec Clarification
- 5) Hection(s), Table (s), F6gure(s), etc. Affected (Attach marked-up pages)
C) Reference and Source Documents Attached Significant Herards Consideration [ ] Environmental Evolustion
(( )) Enviromental impact / Categorical Exclusion [ .! M-C. D) is UFEAR ehenge required? ElA#Ud
]Yes [ ] No LCR No. ... r r. , ':
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E) I'riority NRC epproval required by (date): ricT ,3 A1) 1 7-iI H O An [ ) Emergency [ )Exleent condition will occur if not approved by:
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UFSAR Volume XI Distribution ) 1 l J LCR 89-231-UFS was distributed with Index 90-01, but was incomplete. , Please reissue this corrected copy of LCR 89-231-UFS to replace the old i one. J (' f s i-i
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EDP Tech Spec PDC Procedure ABN /0908-t,EEv.O SE (Attached) 89-0200 DER 8 5 - / B /,7 PE (Attached)
' Test .
Effectiveness Review (Attached) [ ]Yes yo Other i Drawings, Design Calcutations, Correspondence, etc, l pe......neu..n.w....u..* PART 2: OPERATING LICENSE CHANGES [ ]NA "*"'*";"""";""1 l A) Document [ ] Operating License [ ] Tech Specs [ ] Environmental Protection Plan 1 Tech Spec Clarification B) Hection(s), Table (s), Figure (s), etc. Affected (Attach marked-up pages) C) Reference and Source Documents Attached [ ] Environmental Evaluation (( )) Significant EnviromentalHazards impact / CategoricalConsideration Exclusion ( )Other C D) is UFSAR change required?
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E) l'riority ^ pep 4g
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p.,, NRC approval required by (datt): An [ ) Emergency [ ) Exigent condition will occur if not approved by:, U:... _QLh,)__,thfido._., i (State date): s .. . . .-- l Explanation 5r E d) F) implementation DER No. , p ........ ... ..... .. . . . . . . *
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^$ Revision k Page / of k 7 y ,
;x xn__x - :---- " FART 1: UFSAR. PLAN, OR PROGRAM REVISION IJNA "-""""-""--"i A) Document UFMR (lid,1 iders) CONTROLLED
, etc. Affected (Attach marked-up pages) ,
. B) Section(sn, Table (s), Figure (s)4. 2 - z o F/4vec ,
~
C) Reason for Change 1D SHouj vptvES jA) TH E/2 Alo/2ry)AL l DDE2 A rt AJ 6 POSIT /OA). D) Reference and Source Documents (identify) EDP Tech Spec I PDC Procedure ABN /D 904 -/ Re V 6 SE (Attached) 6 9- O/O B DER MB - /6 6 ~7 PE (Attached)
. Test ,
Effectiveness Review (Attached) fYes [ ]No Other Drawings. Design Calculations. Correspondence, etc. l**** * * * * * * * ***** *** *** ** * ***
- P A R T 2 : OPERATING LICENSE CHANGES [ ] N A "*"* *** **" *"*** " " l A) Document
[ ] Operating License [ ] Tech Specs [ ] Environmental Protection Plan
-[ } Tech Spec Clarification U) Section(s), Table (s), Figure (s), etc. Affected (Attach marked-up pages)
C) Reference and Source Documents Attached [ ] Significant Hazards Consideration [ ] Environmental Evaluation [ ] Enviromental Impact / Categorical Exclusion [ } Other D) is UFSAR change required? [ ] Yes [ } No LCR No. c. m , , _ E) Priority *'"8WO NRC approval required by (date): ASB A m, 1_ , l A ., _ An [ ] Emergency [ ] Exigent condition will occur if not approved y (State date):
- 4 ' I$40 REV.-
Explanation
& E Du a.uk .
F) Implementation
- j. .h****h*0 *** **** * **** * ****
- P A R T 3 : A P P R O VA L S***** *** ******** ****** "****** " *****"*****""* l A) Originator 7 Alu/2.Phb/E kN Date /f-//-6 9 B) Technical Expert [ [ m
~8 Date /2- N-pa C) Nuclear Generation Unit Head J> -
3 di O WSJ k Date ( Z. -(TM D) General Director. Nuclear Engine ng [ ]NA A/ Date ,G f E) Plant Manager N' Date bl'M M 1 r j F) Other Date G) Director. Nuclear Licensing #- Date / /%dd , H) OSRO Approval (Tech Spec Amendments) bd NA4 Od6 ,2.f 5-f Date I II) NSRG Approval (Operating License Amendments) [y] N/L).S r) M 4-f.,.f m Date l l Corm FIP-RA2-01 Att 1 P1/1030189 DTC: W TCLtR for UFSAR File: 1735 DTC: [ ] TOLCR for other
A~ EFFECTIVENESS REVIEW
'- Reference LCR l b 9 l-l l2 bl1 l- l l l6l Revision d Page of H " " = ** * * ** * ** * * ** * ** * * *** * * * * * ** *" ** P A R T 1 : UFSAR [ ]NA************"********************l A) Quality Assurance Program
[ )Yes No Does the change (s) cease to satisfy the criteria of 10CFR50, Appendix B and the UFSAR program commitments previously accepted by the NRC? Provide the basis for each change on Attachment 2. Page 2. B) F6re Protect on Program [ }Yes No Does the change (s) significantly decrease the level of fire protection in the plant? [ ]Yes No Does the change (s) result in failure to complete Fire Protection Program approved by the NRC prior to license issue? Provide the basis for each change on Attachment 2. Page 2. l***** PART 2: RADIOLOGICAL EMERGENCY RESPONSE PREPAREDNES PLAN MNA **************** l A) [ ] Yes [ ] No Does the change (s) decrease the effectiveness f>f the RERP Plan? . [ ] Yes [ ] No Does the RERP Plan, as changed, cease to meet the standards of 10CFR50.47(b) and 10CFR50 Appendix E? Provide the basis for each change on Attachment 2. Pagq 2. [** *****"** ********* *** * *** *
- P A R T 3 : $ECURITY PLANS CQiA*"*************"**********"********I
/
A) Document , A) [ ] Yes [ ] No Does the change (s) decrease the effectiveness of the Physical Security Plan or Security Personnel Training and Qualification Plan prepared pursuant to 10CFR50.34(c) or 10CFR737 [ ] Yes [ ] No Does the change (s) decrease the effectiveness of the first four categories of informational Background, Generic Planning Base, Licensee Planning Base and/or responsiblity matrix of the Safeguards Contingency Plan prepared pursuant to 10CFR50.34(d) or 10CFR737 Provide the basis for each change on Attachment 2. Page 2. _ g ....... ..........* *
- P A R T 4 : PROCESS CONTROL PROGRAM MNAr"*"**"****"*"**"" l A) [ ] Yes [ ] No Does the change (s) reduce the overall c6nformance of the solidified waste product to existing criteria for solid wastes in accordance with Technical Specification 6.137 Provide the basis for each change on Attachment 2. Page 2.
l****"""* * *""* * * * * * ** * * * * * * * * * * * * *
- P A R T 5 : ODCM M NA*""******"*"*********"***"**"**"*l A) [ ]Yes [ ] No Does the change (s) reduc ( th'e accuracy or reliabihty of the dose calculations or setpoint determinations in in accordance with Technical Specification 6.14?
Piovide the basis for each change on Attachment 2. Page 2. [* * ** ** ** " **" * ** * * ** * * **** *
- P A R T 6 : A P P R O V A L S* * " "" """ * * * * " " * " * * * * " " " " * * * ""* " """ l A) Originator N LM2P W D k I!L Date /'2-//-69 B) Technical Expert Date it-((U C) Quality Assurance (For Security Plans only) M/4 gsd.4 ,m.5,, Date ID) OSRO (Not required for UFSAR Changes) v/A y sd.ge , m . Date l Form FIP-RA2-01 Att 21/2 030189 DTC: [ ] TCLCR for UFSAR File: 1735 DTC: [ ] TDLCR for other
, EFFECTIVENESS REVIEW D*CUMENTATCN- ,
Reference LCR l81 9l- l Z l E lh l- ldlFl6l Revision M PaDe80f . ABU - /O9 04 - / , REV. A Listed below is each cnange by section and page; the reason for the change; and the basis for concluding that the revised plan or program continues to satisfy the criteria for that plan or program. Section/Page Change Basis U/~6AR l~/ S VEG SHotd (/ALVG6 T4400- /D THE AJO/2m A L. l 1 4 2 -20 F02/4, 502/6, fo224 P L A d r O P E R A T/AJ Q AUD f*0226 /U THE COWft G vg A 71 oQ CLOSED Po Si r/ o A) THESE VA L V E S ARG
&Los EO, THE VM VGS A CE OUr80ARD .CSO-LA rtod VALVES OAJ THE f/LL AND EOVAL -
/2/UG L.tr/ES FO:e OAR-Oo/ VES 6 EG S 7'44 o O E o o I 9' T4600-2002 ADO Aec OPEUED ONLy' DvotsdQ 601200y VES S G'L.
F~/ LLiu G CPERA MUS. SHo/0/D& THGSE I VAcvES As ctosED ly/u Nur APPECT THE OP E!2 6 7~to A OR PERfoEmAWCG l Of THe /=/ /t G SvPP R E SS f o ^ > OAL l Srnposy (awr'o, PG.9) Form FIP-RA2-01 Att 2 P2/2 030189 DTC: [ ] TCLCR for UFSAR File: 1735 DTC: [ ] TDLCR for other _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _: e
J
. EFFECTIVENESS REVIEW DOCUMENTATl*N )
Reference LCR 1 8 91- 'l bl1lkyl-1 l l l l
.. 7_
Revision M Page Tof 9 l
/969- /09 04- / , 12Ev. M Listed below is each change by section and page; the reason for the change; and the basis for f ecncluding that the revised plan or program continues to satisfy the criteria for that plan or program. !
L Section/rege Change Basis {
/
~
(C4WrO) CsAS 772t A T~ Mear sn rea s .
/MAidrA/d/A)q THESE VALV64 /A) TH t='t it.
['; A I W2rhALLy' C40 S ED , a toNFIG u /ZA rtO A) Pt2D- . VIDES ADD / ri oMA L ASSUIEAWC2 AGAir)S T L E A xt-? 6 6 REDM THE CA/E00/ TMA)K. ' 6f 8AcridG vp TH E
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' ' A) Document OF54R B) Section(s), Table (s), Figure (s), etc. Affected (Attyh marked-up pages)
S.2.3 ~2. , t 2_ _ s.13.1. l .S e. 5 2 "62. ( . dis-C) Reason for Change Waitr:"> cdhv4 TO e464AL ""f.1PtGMnorG 4 05 hat . . acre m wr-erwn nr t r=4e ta wh D) Reference and Source Documents (identify) Tech Spec 4.0.T EDP Procedure PDC SM--CD 4 6 g SE (Attached) ABN 8%-cot 9r PE (Attached) DER CB -o24 l 4.
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]Yes [ JNo Review (Attached) ( ; St4 . N m a / L+n uh men 0 0 .c X) a EbA Other tupti W.nMA ' '-
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- P ART 2 : OPERATING LICENSE CH*NGE5 D Document perating License [6tTech Specs [ ] Environmental Protection I M'
[ ] Te ec Clarification s), Figure (s), etc. Affected (Attach marked-up parles' e a =e a n e B) SectiJon1.6), . - D '' " f ments Attached c/A C) Reference and Source tion ! n 6./A 4AS9 Environmental Ei slu_s l [ ] Significant Hazards Consi W.lOther [ ] Enviromental Impact / Categorical sion 0/A uw l /\ l D) is UFSAR change required? @ - l(,0N- prv I d es [ ]No LCR No NRC approv required by (date): An [ ) Emergency [ ) Exigent condition will occur if not approved C N N (State date)' A A,k9 , Explanation n f F) DERImplementa@ No. tion-OM l d $ -MF . p..........................,,,1,.,,,,oy,t,.............................=======.=i Re7M DateI N A) Orialnator D.te p-as-n
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3 2 OF.3 (*,i . FERNI 2 WSAR i: to the shop for solution annealing and for application of a nonsusoeptible inlay to the ends. n e inlay extends beyond the heat-affected mone from field welds. Thus, no sensitised 12-in. pipe is exposed to reactor coolant.' . 5.2 3 2.1.2 Recirculation Inlet uossle The recirculation inlet nozzle configuration for Fermi 2 is shown in Figure , 5.2-8. The thermal- sleeve is type 304 stainless steel; the weld buildup pad on the nozzle is type 308.
. h is configuration is different from the ones which have developed (IGSCC).
- a. De thickness of the pressure retaining boundary at the i attachment is 6 in, on Fermi 2 versus 0.5 in.; therefore, >
stresses are very such lower L ' u ff b. Se pad material on Fermi 2 is type 308-stainless steel versus Inconel. Type 308,is basically not susceptible to IGSCC. Compared to the configuration that developed IGSCC, the lower stress and decreased vulnerability of the Fermi 2 configuration will greatly increase , the time to IGSCC initiation (if any occurs at all)' and slow the rate of growth if IGSCC is initiated. The configuration of Fermi 2 recirculation line vessel nozzles is essentially the same as'that on five other operating plants: Millstone, Pilgrim, Cooper, FitzPatrick, and Hatch 1. .
~
The safe-end welds are scheduled to be examined as part of the ASME Section XI Inservice Inspection Program. In addition, welds selected in acoordance
-with the rules of Section XI will receive examination commensurate with the requirements of NUREG-0313 (Revision 2) and Generic Letter 88-01.
5.2 3 2.1 3 Induction Heating Stress Improvement Operating experience has shown that many BWR plants have had problems with IGSCC in large-diameter recirculation system piping. To minimize the likelihood of IGSCC in portions of the recirculation systes piping that had not received IGSCC remedies, IHSI was performed during July 1983 Induction heating stress improvement is recommended by both GE and gPRI as ! an effective IGSCC countermeasure, especially for plants un<.er construction. On evapletion of IHSI, only four welds in the recirculation system piping did not receive some IGSCC countermeasure. These welds have been included in the inservice inspection program and will be inspected on the inspection cycle detailed in NUREG-0313, Revision 2, and Generic Letter 88-01. 5.2-27
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pg 3, og. 3 i4U - FERMI 2 USFAR , retainer tube any be increased by a factor of 100 with this reduction in dissolved oxygen content. , 5 2 3 2.1.5 Inservice Inspection and Leak Detection . NUREG-0313, Revision 2, and Generic istter 88-01 (G.L-88-01), January 1988, present the Technical bases for the NRC staff positions on asterials, .' processes, and primary coolant chemistry to minimize and control IGSCC problems. Inspection schedules are comparable to those specified in Section II of the ASME Boiler and Pressure Vessel Code in cases where the piping material is IGSCC resistant. The modifications discussed in the previous subsections significantly reduce susceptibility to IGSCC. As detailed in G.L.-88-01, inspection schedules and inspection sample sizes are based on the susceptibility of 3, weldsents to initiation and propagation of IGSCC. Varying amounts of augmented inspections are specified for piping, with a greater susceptibility to cracking. All applicable welds at Fermi 2 have been evaluated and classified according to the requirements of NUREG 0313, Revision 2, and Generic Letter , l 88-01. As required selected welds are included in the ASME Section II Inservice Inspection Program. The leak detection capability on Fermi 2 discussed in Subsection 5.2.7 3 is consistent with the 5-gpa rate discussed in NUREG-0313, Revision 2. As stated in Subsection 5 2 7 3, the unidentified leakage rate limit is established to allow time for corrective action before the nuclear system process barrier can be significantly compromised.
- . 5.2 3 2.2 Steps To Maintain Occupational Exposure As Low As Reasonably Achievable Steps taken in the selection of material to minimize and control the buildup, transport, and deposition of activated corrosion products in the reactor coolant and auxiliary systems follow
The primary coolant systes consists primarily of carbon steel (very low L nickel and cobalt content), except for the use of austenitic stainless steel (in the recirculation loops) and low alloy steel. The nickel content of these materials is low and is controlled in accordance with the applicable ASME anterial specifications. Because the cobalt in steel usually appears as a saall-percentage component of the nickel (usually, 2 percent of the nickel), the amount of cobalt in the primary system components is also very low. L A small amount of nickel base material (Inconel 600) is used in the RPV internals. Inconel 600 is required where components are attached to the reactor vessel shell, and the coefficient of expansion must match the thermal expansion characteristics of the low alloy vessel steel. Inconel 600 was selected because it 1. 5.2-29
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- P ART 1 :
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)No NNN Effectiveness Review (Attached) I ]Yes [St 4 - m/. ( 0,m uh aca 9 0 ao X) a f mA Other im p <iits - / sala . '
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- P AR T 2 : OPERATING LICENSE CHANGES D Document perating License [doch Specs [ ] Environmentet Protection I M
[ ] Te ec Clarification
), s). F6gur_e(s), etc. Affected (Attach marked-up pagesi e=P A *ta l R e
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ments Attached O/A C) Reference and Source [ ] Significant Hazards Consi n GA @ <AS$ Environmental Evalus tion sion O/A W._lOther [ ] Enviromental Impact / Categorical N ( D) is UFSAR change required? LCR No %-ld- Arv i *TTfes [ ] No u N C approvat required by (date) An ( ) Emergency [ )Eugent condition will occur if not approved (State date) O \ N e d in D/.[24 Explanation n
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- 9) Technical Expert dm - M C) Nuclear Generation Unit Head 8 dM $ Date /4d#dP7-
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tor, Nuclear EnDinee ing ( )NA D) General Date /2. d E) Plant Manager ' k- Date I F) Other _ _ , Date//h/98 ( G) Director. Nuclear Licensing Date H) OSRC Approval (Tech Spec Amendments) ()NA Date l ( ) NA File: 1735 ( ll) NSRG Approval (Operating License Amendments)DTC B TCLCR for UFSAR r Form FIP-RA2-01 Att 1 P1/1030189 DTC: ! ) TDLCR for other
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. to' the shop for solution annealing and for application of a nonsusomptible inlay to the' ends.- The, inlay extends beyond the heat-affected none from field welds. Thus, no sensitized 12-in. pipe is exposed to reactor coolant.
5.2 3 2.1.2 Recirculation Inlet Nozzle the recirculation inlet nozzle configuration for Feral 2 is shown in Figure 5 2-8. The thermal sleeve is type 304 stainless steel; the weld buildup-o pad on the nozzle is type 308.
.c this configuration is different from the ones which have developed (IGSCC).
- a. The thickness of the pressure retaining boundary at the attachment is 6 in, on Fermi 2 versus 0.5 in.; therefore, stresses are very such lower !
- b. The pad material on Fermi 2 is type 308 stainless steel versus Inconel. Type 308 is basically not susceptible to IGSCC.
l_ Compared to. the configuration that developed IGSCC, the lower stress and decreased vulnarability of the Fermi 2 configuration will greatly increase .! the time to IGSCC initiation (if any occurs at all) and slow the rate of growth if IGSCC is initiated. The configuration of Fermi 2 recirculation line vessel nozzles is
; essentially the same as that on five other operating plants: Millstone, Pilgria,. Cooper, FitzPatrick, and Hatch 1. i The safe-end welds are scheduled to be examined as part of the A3NE Section XI Inservice Inspection Program. In addition, welds selected in accordance !
-with the rules of Section XI will receive examination commensurate with the !
requirements of NUREG-0313 (Revision 2) and Generic Letter 88-01. 5.2 3 2.1 3 Induction Heating Stress Improvement l Operating experience has shown that many BWR plants have had problems with , IGSCC in large-diameter recirculation system piping. To minimize the likelihood of IGSCC in portions of the recirculation systes piping that had
.not received IGSCC remedies, IHSI was performed during July 1983 Induction heating stress improvement is recommended by both GE and gPRI as an effective IGSCC countermeasure, especially for plants under construction.
On completion of IHSI, only four welds in the recirculation system piping did not receive some IGSCC countermeasure. These welds have been included in the inservice inspection program and will be inspected on the inspection cycle detailed in NUREG-0313, Revision 2, and Generic Letter 88-01. 5.2-27
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dissolved oxygen content. , 5 2 3 2.1.5- Inservice Inspection and Leak Detection . NUREG-0313, Revision 2, and Generic 14tter 88-01 (G.L-88-01), January 1988, present the Technical bases for the NRC staff positions on asterials, processes, and primary coolant cheatstry to minimise and control IGSOC > problems. Inspection schedules are comparable to those specified in Section II of the ASME Boiler and Pressure Vessel Code in cases where the piping material is IGSCC resistant. The modifications discussed in the previous subsections significantly reduce susceptibility to IGSCC. As detailed in G.L.-88-01, inspection . f schedules and inspection sample sizes are based on the susceptibility of weldsents to. initiation and propagation of IGSCC. Varying amounts of augmented inspections are specified for piping, with a greater i susceptibility to cracking. 'L All applicable welds at Fermi 2 have been evaluated and classified according to the requirements of NUREG 0313, Revision 2, and Generic Letter 88-01. As required selected welds are included in the ASME Section XI Inservice Inspection Program. The leak detection capability on Fermi 2 discussed in Subsection 5.2.7 3 is consistent with the 5-gpa rate discussed in NUREG-0313, Revision 2. As stated in Subsection 5.2.7 3, the unidentified leakage rate limit is established to_ allow time for corrective action before the nuclear systes process barrier can be significantly compromised. 5 2 3 2.2 Steps To Maintain Occupational Exposure As Low As Reasonably Achievable Steps taken in the selection of material to minimize and control the
. buildup, transport, and deposition of activated corrosion products in the reactor coolant'and auxiliary systems follow:
The primary coolant system consists primarily_of carbon steel (very low nickel and cobalt content), except for the use of austenitic stainless steel (in the recirculation loops) and low alloy steel. The nickel content of these materials is low and is controlled in accordance with the - ! applicable ASME anterial specifications. Because the cobalt in steel usually appears as a small-percentage component'of the nickel (usually, 2 percent of the nickel), the amount of cobalt in the primary system components is also very low. A small amount of nickel base material (Inconel 600) is used in the RPV internals. Inconel 600 is required where components are attached to the reactor vessel shell, and the coefficient of expansion must match the thermal expansion characteristics of the low alloy vessel steel. Inconel 600 was selected because it 5 2-29
ucENSIND CHANGE REQUEST.
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. Effectiveness Review (Attached)
Other DCRDR HED 855 Drawings. Design Calculations. Correspondence, etc. p . ..... . . . . . . . . . . . . . . . . * * " PAR T 2 : OPERATING LICENSE CHANGES IX]NA """" *"* """*" l A) Daumont [ ] Operating License [ ] Tech Specs [ ] Environmental Protection Plan CONTROLLED [ ] Tech Spec Clarification B) Section(s), Table (s), Figure (s), etc. Affected (Attach marked-up pages) , l' C) Reference and Source Documents Attached STATUSi_ T N
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[ ] Significant Hazards Consideration ! [ ] Enviromental impact - Categorical Exclusion ASB p clath6 mq C l [] ironmental Evaluation gg g I D) is UFSAR change required? 5 IYes ( ) No LCR No REV.
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- 1) section(s) Table (s), F6eure(s), etc. AfWated (Attach marted-up pages)
UP1AA.FCGioAt '),9%le . C) Reason for Change rysa AasaAsmao ar-v9-os tf #pene s res 7_M'n rarw ewa YTs An#r'en AwArt 9/bru varE AW ke.L enAVE LAtod 9lB6 /NTAAW terneAv7=d La&&, D) Reference end Source Documents (Identify) Town spec EDP PDC Procedure _
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= = = = = = _ _ n = = = = = : PART 2 : OPERATING LSCENSE C".*NGES yyetA - ;"";;"";"- - ";l A) Document
[ ] Operating License [ ] Tech Specs [ ] Environmental Protection Plan
] Tech Spec Clarification B) %ction(s), Table (s), Figure (s), etc. Affected (Attach marked-up pages)
C) Reference and Source Documents Attached ! ) Environmental Evaluation
'[ ] Significant Hazards Consideration
! ) Enviromental impact / Categorical Exclusion [ ] Other
( '-~ gyg7yg _ D) is UFSAR shange required?
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neu (Stato date): _ Explanation F) implementation ' DER No. p = = = .. . .... . . .. .... ... . . pany g : app;ovgi .. . = = _ = ::-= = = :: = =... = =:.= = = = : = = = i, ,_ .Ms A) Originator M C AArf4(L5e# [ bdb,d Date//Urbh~ .... . -
- 8) Technical Expey R.C Aupt/Lle0 e DatM' /* 4eUN c-i f s'
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- 5) Plant Manager d,e* Date F) Other , ,
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- 9) NsRO _^=reval (Operatino License Amendments) ' ) NA File: 1735 Form FIP-RA2-01 Att 1 P1/1030189 DTC: I4 TCLCR for UFSAR
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[ JYes [ ] No Does the change (s) eesse to settsfy the criteria of 10CFR50 Appendix 8
- and the UFSAR program commitments prov6ously essepted by the NRC7 Provide the bests for each chance on Atte_chment 2, Pese 2.
- 5) Fire Protection Program
[ JYes IN3 No Does the change (s) significantly decrease the level of fire protect 6on in j J the plant? [ IVes jdl No Does the change (s) fosult in tellure to complete Fire Protection Program opproved by the NRC prior to lloones lasue? Provide the basis for each cc: on Attachment 2, Pane 2. r _ _-GV -:--;--- 5 _ -^r- - PLAN L""^ -"=--="l PN*PART3:? ^ N.C-2 -1^1Does A)[ ] Yes I ~ No the change (s) decrease the . ri;..;ss of the RERP Plan? Does the RERP Plan, as changed, cease to meet the standards of l [ ] Yes [ ] No 10CFR50.47(b) and 10CFR60 Appendix E? Provide the basis for each chance on Attachment 2, Page 2. - " " = --- = " "- ";" " " - "I p - : = " "="" "" PART 3: 55CUvuiv PLANS D(".' A) Document , Does the change (s) decrease the effectiveness of the Physical Security W I ] Yes [ ] No Plan or Security Personnel Training and Qualification Plan prepared pursuant to 10CFR50.34(c) or 10CFR737 Does the change (s) decrease the effectiveness of the first four categories [ ] Yes [ ] No of Informational Background, Generic Planning Base, Licensee Planning Base, and/or responsiblity matrix of the Safeguards Contingency Plan ( prepared pursuant to 10CFR60.34(d) or 10CFR73? Provide the basis for each change on Attachment 2. Pas e 2. 72;-2:^*8 p(,NdA " " " " " " " " " " " ** I P"""" *** *""** ** ** * * ** *
- PART 4 : FF.C-CESS CONTROL Does the change (s) reduce the overall conformance of the solidified A)I ] Yes [ ] No weste product to existing criteria for solid wastes in accordance with Technical Specification 6.137 Provide the basis for each change on Attachment 2. Pas e 2.
p n x = = = :....u n.....17.....** **** PART 5: ODCM DQ hlA """";";""""" ";"""""";" l Does the change (s) reduce the accuracy or reliability of the dose A)I ] Yes I ] No calculations or setpoint determinati,ons in in accordance with Technical Specification 6.147 Provide the basis for each change on Attachment 2, Page 2. ' p5 a n n : x =.. ........**** PART 6: APPROVALS""""- ;- -- "- " - " " W"=-
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