Proposed Tech Specs,Providing Guidance on Calculational Methods for Determining Effects of Fuel DensificationML20024G592 |
Person / Time |
---|
Site: |
Monticello |
---|
Issue date: |
02/28/1974 |
---|
From: |
NORTHERN STATES POWER CO. |
---|
To: |
|
---|
Shared Package |
---|
ML20024G589 |
List: |
---|
References |
---|
NUDOCS 9102130441 |
Download: ML20024G592 (6) |
|
|
---|
Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20217C6321999-09-30030 September 1999 Proposed Tech Specs 3/4.17.B, Control Room Emergency Filtration Sys, Eliminating Unnecessary in-place Testing of HEPA & Activated Charcoal Filters Based on Sys Operating Time ML20203B3191999-01-28028 January 1999 Proposed Tech Specs Page 60d,incorporating Approved Amend 103 Changes for Use by NRC in Issuing SER ML20206P1331998-12-31031 December 1998 Proposed Tech Specs,Revising pressure-temp Limit Curves Contained in Figures 3.6.1,3.6.2,3.6.3 & 3.6.4,deleting Completed RPV Sample SRs & Requirement to Withdraw Specimen at Next Refueling Outage & Removing Redundant SR for SLCS ML20154L9551998-10-12012 October 1998 Proposed Tech Specs Re Rev of Statement on Normal Shift Length & Other Misc Changes ML20154L9041998-10-0909 October 1998 Proposed Tech Specs,Incorporating Proposed Changes Re Surveillance Test Interval/Aot Extension Program ML20153F0191998-09-25025 September 1998 Proposed Tech Specs Pages Re Condensate Storage Tank Low Level Hpci/Rcic Suction Transfer ML20236P5421998-07-0101 July 1998 Proposed Tech Specs Pages 30,50 & 53 Containing Administrative Changes Re Power Rerate Program ML20249C5121998-06-19019 June 1998 Proposed Tech Specs Pages Re Rev 2 to 960726 LAR to License DPR-22,to Establish TS Requirements That Are Consistent W/Analysis Inputs Used for Evaluation of Radiological Consequences of MSLB Accident ML20247K6341998-05-12012 May 1998 Proposed Reprinted Tech Specs Bases Pages,Containing Spelling & Grammatical Corrections ML20216D0021998-03-19019 March 1998 Proposed Tech Specs,Providing Consistent Wording Throughout TS & Providing Sound Basis for Frequency of Actions Required Each Shift ML20248L2001998-03-13013 March 1998 Proposed Tech Specs Revising SLMCPR ML20248L4101998-03-0606 March 1998 Revised Page 39 to Proposed TS Change ML20202H7061997-12-0404 December 1997 Proposed Tech Specs Increasing Plant Max Power Level from 1670 Mwt to 1775 Mwt ML20203A9771997-11-25025 November 1997 Proposed Tech Specs Re Condensate Storage Tank Low Level Hpci/Rcic Suction Transfer ML20211J9801997-09-29029 September 1997 Proposed Tech Specs Page 249b & Cleaned Typed Page 249b, Adding Footnote to Topical Rept NEDE-24011-P-A Stating That Topical Rept Is Approved for Cycle 18 Only ML20210Q2971997-08-21021 August 1997 Proposed Tech Specs Re Safety Limit Min Critical Power Ratio ML20141B9181997-06-19019 June 1997 Proposed Tech Specs Re Update of Design Basis Accident Containment Temp & Pressure Response ML20137W2201997-04-11011 April 1997 Proposed Tech Specs 3.6.C Re Coolant Chemistry & TS 3/4.17B Re Control Room Emergency Filtration Sys ML20149M7281997-01-23023 January 1997 Proposed Tech Specs 3.5/4.5.C of TS Bases Describing Min RHR & RHRSW Pump Requirements for Post Accident Containment Heat Removal & Submit Update to Design Basis Accident Containment Temp & Pressure Response ML20132C6531996-11-25025 November 1996 Proposed Tech Specs,Sections 2.1.A Re SLMCPR & 3.11.C Re Olmcpr.Changes Revise SLMCPR Values & Deletes Sentence Re OLMCPR Limit Penalty for Single Recirculation Loop Operation ML20117A1551996-08-15015 August 1996 Proposed Tech Specs Re Revision to TS Administrative Controls Section 6.1.F.1 Stating That Either 8 or 12 H Shifts Will Be Considered Normal & 40 H Will Be Considered Nominal ML20116G8951996-07-26026 July 1996 Proposed Tech Specs Increasing Max Power Level by 6.3% to 1,775 from 1,670 Mwt.Summary of Plant Mods for Power Rerate Implementation & Power Rerate Environ Evaluation Encl ML20116D8361996-07-26026 July 1996 Proposed TS Sections 3.6.C & 3/4.17.B Re Reactor Coolant Equivalent Radioiodine Concentration & CR Habitability ML20100Q3861996-03-0101 March 1996 Proposed Tech Specs Re Periodic Replacement of Containment Purge & Vent Valve Seat Seal ML20095J4341995-12-20020 December 1995 Proposed Tech Specs Re Main Steam Isolation & App J Leak Rate Test Requirements ML20095E7121995-12-11011 December 1995 Proposed Tech Specs,Removing TS SR 4.7.D.4 & Replaces Seat Seals for Drywell & Suppression Chamber Purge & Vent Valves Every Five Yrs ML20094M1981995-11-14014 November 1995 Proposed Tech Specs,Incorporating Requirements of Option B, Section Iii.A for Type a Testing (Primary Containment ILRT) ML20091K6821995-08-18018 August 1995 Proposed Tech Specs Section 3.7/4.7 SGTS ML20087J4251995-08-15015 August 1995 Proposed Tech Specs,Revising Max Individual MSIV Leak Rate Acceptance Criteria of 11.5 Scfh to Overall Criteria That Encompasses Four Main Steam Lines Into One Limit of 46 Scfh ML20086D8011995-07-0505 July 1995 Proposed Tech Specs Extending Surveillance Test Intervals & Allowable out-of-svc Times for Selected Instrumentation ML20085N0991995-06-22022 June 1995 Proposed Tech Specs Supporting Implementation of BWR Thermal Hydraulic Stability Solution ML20082N8711995-04-20020 April 1995 Proposed Tech Specs Re SBGTS & Secondary Containment ML20069J1061994-06-0808 June 1994 Proposed TS Re SGTS & Secondary Containment ML20065B6691994-03-28028 March 1994 Proposed Tech Specs Re Approved Analytical Methods for Developing Core Operating Limits Rept ML20065B6991994-03-28028 March 1994 Proposed Tech Specs Re Standby Gas Treatment Sys Initiation Instumentation ML20063C9941994-01-26026 January 1994 Proposed Tech Specs,Requiring Valves to Be Tested at Pressure Greater than or Equal to Calculated Peak Containment Internal Pressure Re Design Basis LOCA ML20062N8731994-01-0404 January 1994 Proposed Tech Specs 3.11, Reactor Fuel Assemblies & Bases Re Methodology for MCPR ML20059E6041994-01-0303 January 1994 Proposed Tech Specs,Revising Surveillance Requirement 4.6.E.1.a to Require Valves to Be Tested Per Section XI Inservice Testing Requirements of ASME Boiler & Pressure Vessel Code ML1132102881993-11-30030 November 1993 Proposed Tech Specs Re Removal of Chlorine Detection Requirements & Changes to Control Room Ventilation Sys Requirements ML20056E1081993-08-10010 August 1993 Proposed Tech Specs Providing Clarification of Sampling & Analysis Requirements,Updating Liquid Effluent Sampling & Requirements & Correcting Typographical Errors in TS Section ML20045G6091993-07-0707 July 1993 Proposed TS 4.0.d Re Recording Unidentified & Identified Leakage Rates & 3/6/4.6 Re Analyzing Grad Samples of Primary Containment Atmosphere Once Per 12 H ML20128M7191993-02-12012 February 1993 Proposed TS Increasing Minimum Core Spray Pump Flow to More Conservatively Account for ECCS Bypass Leakage Paths ML20237G2081987-08-14014 August 1987 Proposed Tech Specs,Eliminating Certain Requirements for Plant Mgt & Support Staff to Hold Current Senior Reactor Operator Licenses ML20065E2121982-09-24024 September 1982 Proposed Tech Specs Re Surveillance,Reactor Protection Monitoring Sys,Jet Pump Surveillance,Organization & Steam Line Area Temp Switch Deviation ML1129708531982-07-0202 July 1982 Proposed Tech Spec Changes Allowing Plant to Remain at Substantial Power Level W/One Recirculation Pump in Operation & Equalizer Valve Closed ML1129708181981-03-19019 March 1981 Proposed Revisions to Tech Specs,App A,Pages 26,89-90 & 213-14 for Reactor Protection Sys ML20024G6491978-08-16016 August 1978 Proposed Tech Specs Raising Permissible Setpoint of Eight Safety/Relief Valves Installed at Plant to 1,108 Psig ML20127H2171978-08-10010 August 1978 Proposed Tech Specs to Authorize Use of Partial Drilled Model of Fuel Type for Plant Future Use ML20024G7051978-03-21021 March 1978 Proposed Tech Specs Re Application of Partial Drilled Model for Analyzing Retrofit Fuel Design Scheduled to Be Installed in Plant Reactor in Fall 1978 Refueling Outage ML20024G7031978-03-20020 March 1978 Proposed Tech Specs Clarifying Certain Sections of Interim Radioactive Effluent Tech Specs 1999-09-30
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217C6321999-09-30030 September 1999 Proposed Tech Specs 3/4.17.B, Control Room Emergency Filtration Sys, Eliminating Unnecessary in-place Testing of HEPA & Activated Charcoal Filters Based on Sys Operating Time ML20211G0391999-02-10010 February 1999 Revised ODCM, Including Revs to Revised ODCM Index,Odcm 01.01 Page 2 Paragraph 1,ODCM 02.01 Page 2 Section 1.0,ODCM 05.01 Page 2 Sections 1.0,2.0 & 3.0 & ODCM 13.05 Page 2 ML20203B3191999-01-28028 January 1999 Proposed Tech Specs Page 60d,incorporating Approved Amend 103 Changes for Use by NRC in Issuing SER ML20206P1331998-12-31031 December 1998 Proposed Tech Specs,Revising pressure-temp Limit Curves Contained in Figures 3.6.1,3.6.2,3.6.3 & 3.6.4,deleting Completed RPV Sample SRs & Requirement to Withdraw Specimen at Next Refueling Outage & Removing Redundant SR for SLCS ML20154L9551998-10-12012 October 1998 Proposed Tech Specs Re Rev of Statement on Normal Shift Length & Other Misc Changes ML20154L9041998-10-0909 October 1998 Proposed Tech Specs,Incorporating Proposed Changes Re Surveillance Test Interval/Aot Extension Program ML20153F0191998-09-25025 September 1998 Proposed Tech Specs Pages Re Condensate Storage Tank Low Level Hpci/Rcic Suction Transfer ML20237E9771998-08-20020 August 1998 Rev 4 to EWI-09.04.01, Inservice Testing Program ML20236P5421998-07-0101 July 1998 Proposed Tech Specs Pages 30,50 & 53 Containing Administrative Changes Re Power Rerate Program ML20249C5121998-06-19019 June 1998 Proposed Tech Specs Pages Re Rev 2 to 960726 LAR to License DPR-22,to Establish TS Requirements That Are Consistent W/Analysis Inputs Used for Evaluation of Radiological Consequences of MSLB Accident ML20247K6341998-05-12012 May 1998 Proposed Reprinted Tech Specs Bases Pages,Containing Spelling & Grammatical Corrections ML20216D0021998-03-19019 March 1998 Proposed Tech Specs,Providing Consistent Wording Throughout TS & Providing Sound Basis for Frequency of Actions Required Each Shift ML20248L2001998-03-13013 March 1998 Proposed Tech Specs Revising SLMCPR B210059, Rev 1 to GE-NE-B2100594-1, Radiological Analyses of Design Basis Accidents1998-03-0909 March 1998 Rev 1 to GE-NE-B2100594-1, Radiological Analyses of Design Basis Accidents ML20248L4101998-03-0606 March 1998 Revised Page 39 to Proposed TS Change ML20202H7061997-12-0404 December 1997 Proposed Tech Specs Increasing Plant Max Power Level from 1670 Mwt to 1775 Mwt ML20203A9771997-11-25025 November 1997 Proposed Tech Specs Re Condensate Storage Tank Low Level Hpci/Rcic Suction Transfer ML20199H5281997-11-0606 November 1997 Software Requirement Specification (SRS) ERDS-SRS-1-3, Process Computer Sys - Emergency Response Data Sys (ERDS) - Data Point Library ML20211J9801997-09-29029 September 1997 Proposed Tech Specs Page 249b & Cleaned Typed Page 249b, Adding Footnote to Topical Rept NEDE-24011-P-A Stating That Topical Rept Is Approved for Cycle 18 Only ML20210Q2971997-08-21021 August 1997 Proposed Tech Specs Re Safety Limit Min Critical Power Ratio ML20141B9181997-06-19019 June 1997 Proposed Tech Specs Re Update of Design Basis Accident Containment Temp & Pressure Response ML20137W2201997-04-11011 April 1997 Proposed Tech Specs 3.6.C Re Coolant Chemistry & TS 3/4.17B Re Control Room Emergency Filtration Sys ML20137B5081997-03-12012 March 1997 Rev 2 to Inservice Insp Exam Plan ML20149M7281997-01-23023 January 1997 Proposed Tech Specs 3.5/4.5.C of TS Bases Describing Min RHR & RHRSW Pump Requirements for Post Accident Containment Heat Removal & Submit Update to Design Basis Accident Containment Temp & Pressure Response ML20132C6531996-11-25025 November 1996 Proposed Tech Specs,Sections 2.1.A Re SLMCPR & 3.11.C Re Olmcpr.Changes Revise SLMCPR Values & Deletes Sentence Re OLMCPR Limit Penalty for Single Recirculation Loop Operation ML20117A1551996-08-15015 August 1996 Proposed Tech Specs Re Revision to TS Administrative Controls Section 6.1.F.1 Stating That Either 8 or 12 H Shifts Will Be Considered Normal & 40 H Will Be Considered Nominal ML20116G8951996-07-26026 July 1996 Proposed Tech Specs Increasing Max Power Level by 6.3% to 1,775 from 1,670 Mwt.Summary of Plant Mods for Power Rerate Implementation & Power Rerate Environ Evaluation Encl ML20116D8361996-07-26026 July 1996 Proposed TS Sections 3.6.C & 3/4.17.B Re Reactor Coolant Equivalent Radioiodine Concentration & CR Habitability ML20115D8621996-06-28028 June 1996 Rev 3 to Engineering Work Instruction (Ewi) EWI-09.04.01, Inservice Testing Program ML20100Q3861996-03-0101 March 1996 Proposed Tech Specs Re Periodic Replacement of Containment Purge & Vent Valve Seat Seal ML20095J4341995-12-20020 December 1995 Proposed Tech Specs Re Main Steam Isolation & App J Leak Rate Test Requirements ML20095E7121995-12-11011 December 1995 Proposed Tech Specs,Removing TS SR 4.7.D.4 & Replaces Seat Seals for Drywell & Suppression Chamber Purge & Vent Valves Every Five Yrs ML20094M1981995-11-14014 November 1995 Proposed Tech Specs,Incorporating Requirements of Option B, Section Iii.A for Type a Testing (Primary Containment ILRT) ML20100M4821995-08-29029 August 1995 Revised Sections to Odcm,Including Rev 1 to ODCM-03.01,Rev 1 to ODCM-12.05 & Rev 1 to ODCM-13.05.5 ML20091K6821995-08-18018 August 1995 Proposed Tech Specs Section 3.7/4.7 SGTS ML20087J4251995-08-15015 August 1995 Proposed Tech Specs,Revising Max Individual MSIV Leak Rate Acceptance Criteria of 11.5 Scfh to Overall Criteria That Encompasses Four Main Steam Lines Into One Limit of 46 Scfh ML20086D8011995-07-0505 July 1995 Proposed Tech Specs Extending Surveillance Test Intervals & Allowable out-of-svc Times for Selected Instrumentation ML20085N0991995-06-22022 June 1995 Proposed Tech Specs Supporting Implementation of BWR Thermal Hydraulic Stability Solution ML20083Q8411995-05-18018 May 1995 Rewrite of Rev 2 to Engineering Work Instruction (Ewi) EWI-09.04.01, Inservice Testing Program ML20082N8711995-04-20020 April 1995 Proposed Tech Specs Re SBGTS & Secondary Containment ML20077S4551995-01-0909 January 1995 Startup Physics Testing Rept,Cycle 17 ML20069J1061994-06-0808 June 1994 Proposed TS Re SGTS & Secondary Containment ML20072P8011994-05-17017 May 1994 Rev 8 to Process Control Program, Installed Atcor Solidification Sys ML20065B6691994-03-28028 March 1994 Proposed Tech Specs Re Approved Analytical Methods for Developing Core Operating Limits Rept ML20065B6991994-03-28028 March 1994 Proposed Tech Specs Re Standby Gas Treatment Sys Initiation Instumentation ML20072P8101994-02-22022 February 1994 Offsite Dose Calculation Manual, Rev 0 ML20063C9941994-01-26026 January 1994 Proposed Tech Specs,Requiring Valves to Be Tested at Pressure Greater than or Equal to Calculated Peak Containment Internal Pressure Re Design Basis LOCA ML20062N8731994-01-0404 January 1994 Proposed Tech Specs 3.11, Reactor Fuel Assemblies & Bases Re Methodology for MCPR ML20059E6041994-01-0303 January 1994 Proposed Tech Specs,Revising Surveillance Requirement 4.6.E.1.a to Require Valves to Be Tested Per Section XI Inservice Testing Requirements of ASME Boiler & Pressure Vessel Code ML1132102881993-11-30030 November 1993 Proposed Tech Specs Re Removal of Chlorine Detection Requirements & Changes to Control Room Ventilation Sys Requirements 1999-09-30
[Table view] |
Text
i 3.0 LIMITING CONnITIOE FOR OPERATIM 4.0 c'mlT.IttrCE REQUIPE!iENTS 1 T. Rectreulation System Recirculation System I.
1 Except as specified in 3.5.1.2 below, whenever 1. Once per month. when irriat ed fuel is in t;i-irradiated fuel is in the reactor, with reactor I coolant tenperature nreater than 212"F and both reactor with 0
reactor coJiant temperature nrs reactor rect re'ilatfor pumps operatint, the than 212 F and both reactor recirculation pumps operating, the recirculation svnten cre recirculation system cross tie valve interlocks shall be operabic.. tie valve interlocks shall be demonstrated to 3
be operable by verifying that the cros tie
- 2. The recirculation system cross tie valve inter-valves cannot he opened using the normal cont:
switch.
Iocks may be Inoperable if at least one cross tie valve is maintained fully closed. 2. When a recirculation system cross tie valve interlock is inoperable, the position of at least one fully closed cross tie valve shall J. Average Planar LHCR be recorded daily. j During steady state power operation, the average linear heat generation rate (LHGR) of all the J. Average Planar LHGR rods in any fuel a sembly, as a function of average planar exposure, at any axial location, Daily during power operation, the averate shall not exceed the maximum average planar LHCR planar LHCR shall be checked. ~
- l shown in Figure 3.5.1.
}
i 3.5/4.5 10Si i
REi' DOCkO g3 P
, _ _- - % =
. .-. . . - . . _ - . - . .- . _ _ . . - . . _ _ . _ - - - = _ _ . _ . . _ _ - _ . _ - ~ . _ - - . .
i l
t i
t 3.0 LIMITING CONDIT10?!3 FOR OPERATIO*: 4.0 SURVET T IA!!CE REQJIRPJTl.'TS K. Incal DIGR K. Tecal UIGR t During steady state power operation, the linear Daily during reactor power operation. the heat generation rate (UIGR) of any rod in any local TXR shall be checked.
fuel assembly at any axial location shall not exceed the maximum allowable DIGR ao calculated i l
by the following equation- i U!GR S UIG;l I- OF ,
!L \
max d j P[ max
} LT[
UIGR d = Design U!GR I
= 17.5 kw/f t for 7x7 fuct
, = 13.4 kw/f t for 8x8 fuel i f 1
.' bl max = Maximum power spiking penalty i
= 0.033 for 7x7 fuel
= 0.024 for 8x8 fuel LT = Total core length = 12 ft L = Axial position above bottom core 3.5/4.5 108F REV i
~ _
3 8 A 0_
1_ 3D*
,3 H r: .mtT J!rb ;
- I,iI
-. . n! . t1 .r ti t+.
t ; r.
,i r r 'i ,k' iiiii' r rp7,.
i ri
, t T ,. 3 '- r
_rr.
i1iTTr,74
. P n M,. T,Trc+ r,;1Ti: -
i! ,7 H r
8 3
. t ; .t -
r .,.m r.W > pa m 0 . T,i
? ,
i1,'
- - .- 1 *i r
, ; 1 ti Tn E
- c. ++-
,.r r7.. r4 m', T' T ,i
- - r
~i .r .. *n,.
. c+H
- g
T'iT 'Tr? r i: . . W, :-
7 -
-. 9.7
+ .;,? rrr -
O _
,,r -
, Ti T r 4- - - C
- c, _ - -- 7r i r .
- -, ~ .
- r 7, q rr,JTT. 'Ti + t,T,7~?.r.7 5 TlA.,,4rr4 .
T , i%..ym,e,.~7 +r-b t: .
F . ; , :i
.rinnnT,7H i1 J
, T j
mh;r ". e
,19
.P.
- TN - t:
tiw7d r 7, g
TTt. . i M,: i i,
- ,rT,- 7-
~, - ' ;? t .
7; -
i,
- 0rrh ir: ~r.+.h -
h;,T t d=. i!
r>
'. c7. r , r.Tr th;,1iih ;; ,}~F T7t t - 1TT
- 3 g r:7
.ti rt , - 7 T1
- .[
rri3 - .-
tit m r. r 1,;Eii<h
- r
- ~- +[ c h n.-r S tTr
, E y}iT '~ i 1;l 4r Tli r! f r. ,,., 4T: 4_
- nh (
- p nm.ttr,ri
_ T,nN r - ,T r1 [ . .
iTi 6i!
,Tf .
+ N i+ Tt tt i'*iirmh
,1i,l
}1 r,
_t1 4 r g_ i,:.i
TTT T , *:
O I
,- ,1i -
l1 /
1, . -
.T
- . PT ' t Q
7; r 7T r;7
,
- *: 1i1 t
i1N ?nj d t
r i
! 2
,'iii~,:l : ~ )
- , f > t*1; nI .
'. i:
ciinTM 0
- r. ' - ; , 3
,dr * '
rt. ;FI f a I .
. :r,1
,1f
,t ,-Tiir TT- b- i ,
i' 2 2 *
!l'rm+H Th ,TTt TT.
7 t1p
- ri
>i r!
- o] r, ; n;r7'"T , ! i "iii t ".
iT rii' rr, -t '
n s
S o
nr T-P!; ,H .ril,j'T; y ~tt C
.vN i1r irr r ,
, - r7 it : -
rTTTr d ti -
ar i i iir .
a jr4F!mcet- .Tri*!
e r . -l * - ,
tet a
- i t. _
.- ._,. -;' r: ET Tr h>i!
rTTi T,g rriQ:-
i n
t -
E
}Tr r', .lfl
. -i- t r .d 2 s rc rj;F f,rH S e u
t -
. l:, . I u
~
~ *1 3 + +,4 ~
- r. i_ rT Tiv
-1 -
i tf tI' e T
1T1 r f"T
,A 4 ". ,ii rr ,++ f *.4ii imf t 6 ti - .
% r,
.i " H ,4 r7
- iir - I _
' 6 d
ih, n1 -
F1ir: .I irnt Tcr r !'ib
- i,!
t.7 nt.tr t{ ,
';l T, a 1t.Th.I
. 4 ' e.
F
~:T.1 r 'i,Qi Tt r
t .-t, -
+ r
! t:
.ttr
.1:i
'i
~~
0 nTTnTTrTi ~
~
- rrTt j i ',;.4 S
e
'!+
2 ni' irg'T TFi:i
.; t1f .
, ' , -l i c -
r TI"i:h *r~n* Mr a
-I
=
- F!I i
- ir:t t i ', ' t A i v L+f,r
'i1i
- iI:i 0
1 y
+
<f :n. n r rr ; -
r.
+C t ~P ~ 4 1~
2.T-
~
~ 'Tf'I -
- '~j - t T7+V 'q Fr%iIMnf
- , . ,. i rf - - rrrrF FttH c, {. i 4 -
~
,rit ~ttr - -
i-irn: ' "
i tH -
1
' TF . I I
.wi t1i t 'riT *;,rH ,r ,MP -r",!
ttr : i r,.b7 +, j - -
7 rN
,+r t t1T ~
- r. ftrf
~ .
tI t;r.;,r ,+p,,ligi1!! i.CI1T'rrT t4 .
' i}cT+' brii?7f~
T
.hi trri T.
irt.qi tt '. - '~ ;
ipH Mr.aj-J i -'
~ 7V- Trri- 5
' r r; r E rtti t "
~3
+ii['Y~
- ~
' - b T tit
."i{ r gl'. T r a,/~r
.jH M tqTiTyi F
g7r - 3}T tTH Jr t
e t
~T
~
"H 1T1h1'r r 1i 3I'in t t ni +
~~ t ti s :t lt -
tL rfT1i1tIb i rr t t
- ' 41rrl 7n h- !
i,i;m,,TH,s.tI
~- -
]'n fN 7rtj' - ~cp71H f* '
sit 4 17i1F. f, -
3h -
ti' ?rr TAP f* .
. 4 pi -
_7 ti r 4ri *r rb rr'7f1 !F E i t t,; 1 rIT. II1
~ _t - j
~
g N '
I G I I
- a ( g
' 8
- I e
t
,2 u g /
g g U 9
^
^
^
W
)
, r; !: , 'r '!-
1 - - - - -
Bases Continued 3.5:
, J. Average Planar L'tCR This Spacification assures that the peak cladding tmerature following the postulated desis;n basir loss-of-coolant accident will not exceed the 2300"F limit specified in the Interim Acceptance Crit ria (LAC) issued in June 1971 coneidering the postulated effects of fuel pellet densification.
The peak cladding temperature following a postulatei f oss-of-coolant accident is primarily a functinn of the average heat generation rate of all the rods of a fuel assembly at any axial location and is only dependent secondarily on the rod to rod power distribution within an sasembly. Since expected local variations in power distribution within a fuel assembly affect the calculated peak clad temper-ature by less than + 200 F relative to the peak temperature for a typical fuel design, t'te limit on the average IInear heat generstion rate is sufficient- to assure that calculated temperatures are below the IAC 11mit.
The maximum average planar UIGR curves shown in Figure 3.5.1 were calculated for the various Morticello fuel- types in. the manner discussed in Section 4.3 of Gener'al Electric topical report. "GEGAP-III: A Model for the Prediction of Pellet-Cladding Thermal Conductance in BW Fuel Rods". NEDO-20181. Revision 1, November 1973. These cur.res show the composite limitation based on the design U1GR of the fuel and the peak cladding temperature in the event of a IDCA. Calculations based on the AEC 'hodified CE Model for Fuel Densification" attached to a December 5,1973 letter from D J Skovhoir (USAEC) to L 0 Mayer (T4P).
The possible effects of fuel pellet densification were: (1) creep collapse of the caldding due to axial gap formation; (2) increase in the UIGR because of pellet column shortening; (3) power spikes due to exial gap formation; and (4) changes in stored energy due to increased radial gap size. Cal-culations show that clad collapse is conservatively predicted not to occur currently or prior to September 1974. Therefore, clad- collapse is not considered in the analyr.cs. Since axial thermal expansion of the fuel pellets is greater than axial shrinkage due to densification, the analyses of peak clad temperature do not consider any change in UIGR due to pellet column shortening. Although.
the formation of axial gaps might produce a local power spike at one location on any one rod in a l fuel assembly, the increase in local power density would-be less than 27. at the axial midplane. S irc e small local variations in power distribution have a small effect on peak clad temperature, power spikes l were not considered in the analysis of loss-of-coolant accidents. Changes in radial gap size affect 3.5 BASES II 3 #-
RE"
. . _ _ _ . _._ _ _ _ _ .__ _= _ _ _ _ _ _ _ _ _ _ _ _ _ . _ . . _ _ _ ___ _ _ _ _.__.__ _ _
i i
Bases continued 3.5:
the peak clad temperature by their effect on pellet clad thermal conductance and f*rel pellet stored ;
energy. The pellet-clad thermal conductance ownmed for each rod is dependent on the steady st ete operating linear heat generation rate and gap sinc. As discussed in NEDO-20181, Revision 1, the or l size was calculated with the assumption that he pellet densified from its rw asured value to 9".x,
The curves used to deternine pellet-clad thermal conductance as a function of linear heat gener, tion !
are based on experinental data and pradict with a 95L conf 1 der ce that 907. of the population excaed ;
the predictions.
i K. Incal UICR i
Ihis Specification assures that the linear heat generation rate in any rod is less than the design Linear heat generation even if fuel pellet densification is postulated. The power spike penalt:- '
specified is based on the analysis reported 1.n IEDO-20181, Revision 1, and assumes a linearly ,
increasing variation in axial gaps between core bottom and top, and assures with a 937. confidence, j that no more than one fuel rod exceeds the design linear heat generation rate due to power spiking. j f
l 4
{
f 1
I 1
i 3.5 BASES 113B REY i
AEC DISTP ' TION TOR PART 50 DocrET MATERV
? 1724 (TDiPORARY PORM) CONTROL NO:
PILE:
pry : DATE CT DOC DATE REC'D
- .ortliern htates ) we r Connanv LTR l'.D:0 Kl'T OIlu.R
!!inneapoli s , '!! n t, . 55401 Mr. L.O. !'e r r 2-28-74 3-4-74 X TO: ORIG CC OTIER SENT AEC PDR XXX 1.F . O' Leary 3 signed SENT LOCAL PDR XXX
~
CLASS UNCLASS PROP IliTO INPUT NO C)S REC'D DOCKET I;0:
XXX XXX 40 50-263 DESCRIi' TION : ENCLbURES:
Lt r t rans the f ollowing. . .propnacd channen to PROPOSED C}lANGES to tech specs, notarized tech apeen..... 2-28-74 (40 cys encl rec'd)
PLANT NMm : enticen, ' ACKNOWLEDGED FOR ACTION /INFORMATION 3-4-74~ JU EUTLER(L) SCIT4E!;CER(L) /ZIC'M;N(L) REGAN(E)
W/ Copict W/ Copier W/7 Copics CLARK (L) S~OLZ(L) DICKER (E)
W/ Copico DO NOT REUOVE W/ Copict W/ Copice W/ Copict W/ Copies GOLLER(L) VASSALLO(L) KNIGHION(E)
W/ Copics W/ Copics W/ Copics W/ Copies KNIEL(L) SCED:EL(L) YOUNGELOOD(E)
W/ Copier W/ Copics W/ Copics W/ Copics INTERNAL DISTRIEUTION rc rII L TECH REVIE" DD; TON
~A/T It'D vAEC PDR IENDRIE GRI!!ES LIC ASST ggg77ug; c/OGC , ROOM P- 506 A SCIIROEDER GM' iILL / DIGGS (L) S ALE'AN
/l!UNTZING/ STAFF MACCARY PASTNER B. HURT GEARIN (L)
CASE K!;IGHT BAL1J C 00ULEOUR!;E (L) ptggg GIdiBUSSO PAULICKI SPANGLER LEE (L) liCDONALD BOYD SHA0 MAIGRET (L) / DUBE v/ Input
}t00RE (L)(BAR) STELLO ENVIRO SERVICE (L)
DEYOUNG(L)(PWR) HOUSTON MULLER SHEPPARD (E) JNPO
/SKOVHOLT (L) NOVAK DICKER SMITH (L) C. MILES P. COLLINS '
ROSS PHIGHTON TEE 1S (L) B FING DLMISE IPPOLITO YOUNCE; WD WADE (E) A. Cabell
/ItEG OPR TEDESCO REGAN WILLIAMS (E)
PILE & REGION (3) LO';0 PROJECT LDR WILSON (L) liORRIS LAINAS S. REED (L)
STEELE BO;AROYA ilARLESS VOLUEP EXTERNAL DISTRI DUTION l'A
- 1 - LOCAL PDR__ !!innen tio l i s . ifi g A - DTIE( APE 'M ) (1)(2)'10). NATIONAL L;E'S 1-PDR S A';/LA/NY f A - NSIC(LUCi % N) 1- ASLBP(E/W Bldg,R 529) 1-GERALD LELLCUCHE 1 - ASIB(YORE,SAYRE/ I-W. PENNINGTON, in E-201 GT EROOKHAVEN MAT. LAL WOODARD/"H" ET. 1-CONSULTM;T' S
'16 - CYS ACRS HOLDING 1-AGMED(Ruth Gussran)
NEkHARK/BLUME/AGBABIAN FF- B-12 7. GT.
1-GERALD ULRIFSON...ORNL I-RP . . MULLER. . T- 30 9 GT
_ _ _ _ _ _ - _ _ _ _ _ _ - _ _ _ _ _ _ _ - _ _