ML16173A395
| ML16173A395 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 06/21/2016 |
| From: | Jim Barstow Exelon Generation Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| SC05-03 | |
| Download: ML16173A395 (32) | |
Text
Exelon Generation 200 Exelon Way Kennett Square. PA 19348 www.exeloncorp.com 10 CFR 50.90 June 21, 2016 U.S. Nuclear Regulatory Commission A TIN: Document Control Desk Washington, DC 20555-0001 Limerick Generating Station, Units 1 and 2 Renewed Facility Operating License Nos. NPF-39 and NPF-85 NRC Docket Nos. 50-352 and 50-353
Subject:
License Amendment Request - Supplement Proposed Revision to Technical Specifications in Response to GE Energy - Nuclear 1 O CFR Part 21 Safety Communication SC05-03
References:
- 1. Letter from James Barstow (Exelon Generation Company, LLC) to U.S.
Nuclear Regulatory Commission, "License Amendment Request -
Proposed Revision to Technical Specifications in Response to GE Energy-Nuclear 10 CFR Part 21 Safety Communication SC05-03,"
dated January 15, 2016 (ADAMS Accession No. ML16015A316).
- 2. Letter from David P. Helker (Exelon Generation Company, LLC) to U.S.
Nuclear Regulatory Commission, "Response to Draft Request for Additional Information Regarding Proposed Revision to Technical Specifications in Response to GE Energy - Nuclear 10 CFR Part 21 Safety Communication SC05-03," dated April 19, 2016 (ADAMS Accession No. ML 1611 OA392).
By letter dated January 15, 2016 (Reference 1 }, Exelon Generation Company, LLC (Exelon) submitted a license amendment request (LAR) for Limerick Generating Station (LGS}, Units 1 and 2. The proposed amendment would reduce the reactor vessel steam dome pressure associated with the Technical Specifications (TS) Safety Limits (SLs) specified in TS 2.1.1 and TS 2.1.2. The amendment would also revise the setpoint and allowable value for the main steam line low pressure isolation function in TS Table 3.3.2-2.
The proposed changes address a 10 CFR Part 21 issue concerning the potential to violate the SLs during a pressure regulator failure maximum demand (open) (PRFO) transient.
Reference 2 provided a response to a draft request for additional information (RAI). Upon review of the response, the NRC staff determined that a full copy of Loop Uncertainty Calculation Ll-00032, "LU Calculation for PT-001-2N076C," portions of which were provided in Attachment 4 to the RAI response, was required to complete their review. The attachment to this letter provides a copy of the full calculation.
U.S. Nuclear Regulatory Commission License Amendment Request - Supplement Proposed Revision to Technical Specifications in Response to GE Energy - Nuclear 10 CFR Part 21 Safety Communication SC05-03 Docket Nos. 50-352 and 50-353 June 21, 2016 Page2 Exelon has reviewed the information supporting a finding of no significant hazards consideration, and the environmental consideration, that were previously provided to the NRC in Attachment 1 of the Reference 1 letter. Exelon has concluded that the information provided in this supplement does not affect the bases for concluding that the proposed license amendment does not involve a significant hazards consideration under the standards set forth in 1 o CFR 50.92. In addition, Exelon has concluded that the information in this supplement does not affect the bases for concluding that neither an environmental impact statement nor an environmental assessment needs to be prepared in connection with the proposed amendment.
There are no regulatory commitments in this supplement.
In accordance with 10 CFR 50.91, "Notice for public comment; State consultation,"
paragraph (b), Exelon is notifying the Commonwealth of Pennsylvania of this supplement by transmitting a copy of this letter with its attachment to the designated State Official.
If you have any questions or require additional information, please contact Glenn Stewart at 610-765-5529.
I declare under penalty of perjury that the foregoing is true and correct. Executed on the 21 51 day of June 2016.
James Barstow Director, Licensing and Regulatory Affairs Exelon Generation Company, LLC
Attachment:
Loop Uncertainty Calculation Ll-00032, "LU Calculation for PT-001-2N076C," Revision OA cc:
Regional Administrator - NRC Region I NRC Senior Resident Inspector - Limerick Generating Station NRC Project Manager, NRR - Limerick Generating Station Director, Bureau of Radiation Protection - Pennsylvania Department of Environmental Protection wl attachment II II
ATTACHMENT License Amendment Request - Supplement Proposed Revision to Technical Specifications in Response to GE Energy - Nuclear 10 CFR Part 21 Safety Communication SC05-03 Limerick Generating Station, Units 1 and 2 Docket Nos. 50-352 and 50-353 Loop Uncertainty Calculation LI-00032, "LU Calculation for PT-001-2N076C," Revision 0A
Attachment License Amendment Request - Supplement Docket Nos. 50-352 and 50-353 Nuclear Group l,tJ Cl\\I,Cl.lJ,}\\TION FOR PT-001-2N076C DOCT 'i PE :
0 0 0 SECTION 01 Cale No LI-00032 Page 001 of 029 Orig. HUMPHREYS GD Rev.
WHITE.'\\J Apr.
GEORGE RT TABLE OF CONTENTS Rev Dat.:
Date Date 00 07/12/94 07/12/94 07/13/94 PAGE 1.0 PURPOSE....................................................
2 2.0 DESIGN 8,1\\SIS............................. * *. *..............
4
- 3. 0 ASSUMP'.l'IONS... * *. *.. *... *.. *.. * * * * * * * * * * * * * * * * * * * * * * * * * *...
5
- 4. 0 REFERENCES.................................................
6
- 5. 0 ATTACH~IEI,lTS..................................................
¥7 6.0
.Z\\.NALYSIS................*................ *.... *... *........
7
- 7. 0 RESOL'I'S...... *......... *.. *.. * * * * * *............ * * * * *. * *....
15 Supporting Data Sheet Attac~nents Attacl1.m.ent 1:
Loop Uncertainty Session Data.........................
18 :
Calculation Results..............................
19 :
Loop Data and Configurat:ion......................
20 :
Loop CaJ.i.brat..i.on Cata............................
21 :
In.strumE:nt Data..................................
22 :
Vendor Data......................................
26 :
Location Data....................................
27 :
Process Concerns.................................
28 Attachm,~.nt 9:
Device Dependenc.i.~.:s..............................
29
Attachment License Amendment Request - Supplement Docket Nos. 50-352 and 50-353 IECR LG 15-00017 Rev. 0 Altachment 7 Page 6of14 Cale No LI-00032 OA Nuclear Group LU CALCULATION FOR PT-001-2N076C 01 Page 002 of 029 Ori(-::~~~~~f9:::::::C:::::C::::::C:~~re:::Ci~~~~
- 1. 0 DOCTYPE:
aoo PURPOSE This section Conclusions*,
calculation.
1.1 Objective Update header with Orig.
Rev. Apr. and dates.
includes the Objective, Limitations, and the Applicability Statement of this The objective of this calculation is to determine the Nominal Trip Setpoint (NTSP), Actual Trip Setpoint IATSP) and the Allowable Value {AV) for the Main Steam Line Low Pressure Isolation Actuation Instrumentation as described in the Limerick Unit 2 Technical Specifications Table 3.l.2-2, Item l.c (Ref. 4.2). This calculation analyzes the PT-00l-2N016C instru.~entation loop. This calculation was performed utilizing normal environmental conditions (see Section 2.2.3).
The normal NTSP, ATSP and AV results of this calculation are documented in Section 7.
Results of this "base calculation~ are also applicable to the loops listed in Section 1.4.
1.2 Limitations The MaX and Min Acceptable Limits calculated in Section 7.8 are not authorized for use in the PECo maintenance program by this revision of the calculation.
This calculation is run for a normal environment and does not account for any uncertainties associated with accident scenarios tsee Section 2.2.3).
The. appropriate use of this calculation to support design or Station activities, other than those specified in Section l.l of this calc*
ponsibility of the user.
1.3 Conclusions SIG was calculated d includes operational 2 2 of this calculation.
.._,_,..._....._.'-""'"'.......,--"~sJult displayed in Section The :"t4!4,,11,i;aa.1~-t..~~~ Analytical Limit~ utilized in this calculadon ette-9.A c:ee::>K~~
... ~~~
The results of this calculation suppo!'~the o~:'ect station setpoint o~~
PSIG.
/
__,/
is based on TOOi ES1400026 (Ref. 4.17) and Ge:Jnral Electric Safety Concern SC05-03 (Ref 4.18).
..._.,,'--""'._.,,_,~
QA OA
Attachment License Amendment Request - Supplement Docket Nos. 50-352 and 50-353 Nuclear Group LU CALCULATION FOR Cale No LI-00032 PT-001-2N076C 01 Page 003 of 029 Orig. HUMPHREYS GD DOCTYPE:
000 Rev.
WHITE AJ Apr.
GEORGE R'r Rev 00 Date 07112 I 9 Date 07/12/9 Date 07/13/9 The current station Loop Leave Alone Zone (LAZ) was calcula l:ed utilizing the Square Root of the Sum of the Squan,:s Method (SRSS).
The calculated LAZ is+/- 6.708.?SIG.
This LAZ has been evaluated and is consistent with both the IISCP Program Plan requirements (to provide at least one LAZ between AV and 1\\TSP) and the Surv~:.illance Test. LAZ requirements (Ref. 4.4).
From the above statements it is concluded that the Loop LAZ (as documented on.'\\ttachment 4 of this calculation) and the currant station setpoints are appropriate and acceptable for contirn1ed use at Limerick Generating Station.
1.4 l>.pplicability A data evaluation has b~en performed in order to determine which, if any, redundant/mirror instrument loops are bounded by the results of this calculation (the "base" calculation). The data evaluation results validate that this "base" calculation i.s applicable to the foll ov1ing Loop Affiliation Numbers:
PT-001-lN076A Configuration 01 PT-001-1N076B Configuration 01 PT-001-1N076C Configuration 01
- k PT-001-1N076D Configuration 01
- r
.?.T-001-2M076A Configuration 01 PT-00l-2N076B Conf:i.gur.a t ion 01
- k PT-001-2N076D Configuration 01 The results of this 0 base" calculation are bounding values for the instrurnent loops listed above based on such factor.:s as :i.nstrume:n.t manufacturer and model number, in::it:rument location envi1:onmenta..i. para.meters, actual. i.nsta.J..lation and use of the instrument in the measurement of the process variable.
There is a difference in the model numbers for the trans-mitters listed above.
The Unit 1 transmitters are Rose-mount. Model 1151GP9 and th*~ Unit. 2 transmitters are Model 1153GB9.
A review of the vendor information indicates that the Model 1153G89 has the more conser-vative parameters.
Therefore a Unit 2 transmitter was chosen to represent the bounding case.
In addition, differences were found concerning the head corrections of the transmitters.
The Master Calibration Sheets and Master Loop Sheeets for the transmitters indicated the following for the head corrections:
Unit 1,
+5.2 FSIG; Unit 2 1 +4.4 PSIG (P,ef. 4.8).
These head cor:r:ections were not in agreement with the actual fie ld
Attachment License Amendment Request - Supplement Docket Nos. 50-352 and 50-353 Nuclear Group lECR LG 15-00017 Rev. 0 Attachment 7 Page 7 of 14 LU CALCULATION FOR PT-001-2N076C DOCTYPE; 000 01 Cale No LI-00032 Page 004 of 029 Orig. HUMeHREYS GD Rev.
WHITE AJ Apr.
GEORGE RT Rev Date Date Date
-Mo OA 07 /12/94 07/12/94 07 /13/94 installations which result in a head correction of +S.6 PSIG for both units.
- rhis was documented by the issuance of IISCP Anomaly No. 114, "Head Corrections for PT-00l-l12)N076A/B/C/D" (Ref *. 4.14) which describes the issuance of Action Requests A0851879 (Ref. 4.151 and A0852289 (Ref. 4.16) (Type CM-NCR) for correcting these discrepancies.
These discrepancies have no affect on this calculation as the head correction pertains only to the scaling of the transmitter.
The scaling of PT-001-2N076C was done using +5.5 ?SIG in accordance with the field installations.
2.0 DESIGN *BASIS This section inciudes the Technical Background and Design Input information relevant to the calculation.
2.1 2.2 Technical Background Low steam pressure at the turbine inlet while the reactor is operating could indicate a malfunction of the steam pressure controller in which the turbine control valves or turbine bypass valves become fully open and cause rapid depressurization of the reactor vessel.
Instrumentation is installed to monitor the steam line pressure in order to mitigate the consequences of this type of occurrence.
The signals generated by this monitoring instrumentation input into the NSSSS isolation logic which automatically closes the Main Steam Isolation Valves IMSIVs) whenever the Mode Sw
.:.s s
a i l
e e th ?r-001-2N076C loop is analyzed by this calculation.
2. 2.
2.2.3 TOOi ES 1400026 (Ref. 4.17) and General Input BOS.OD ~~ctric Safetv Cancer~ SCOS-03 (Ref. 4.18). 7 An Analytical/Process Limit o~~PSIG has been I.
utilized for this calculation based on -e-hz ~:1
'i'azbine 'Fhx:ottle Frc:-..+~!SI S;-r £1een
~) p~s2mntns srnslf1cs ie tsc 5a~] e~~ J f~~
4-t-l.9 I "
l'lie 720 !'lE'Y.3....¢-!:~~;i;~~.~.:.~itaa
.@s~~~~~
1=Rd. e
- 11+.
T is calcu at~on inc u es any appl1ca le System Rerate Design/Operating Conditicns and Impacts as a result of the Power Rerate analyses per the g"Jidelines contained in Specification NE-177 (Ref.
4. 12).
This calculation was perfomed under normal oA OA
Attachment License Amendment Request - Supplement Docket Nos. 50-352 and 50-353 jECR LG 15-00017 Rev. 0 Attachment 7 Page 8 of 14 LU CALCULATION FOR PT-00l-2N076C 01 Rev OA Nuclear Group OOCTYPE:
000 Cale No LI-00032 Page 005 of 029 Orig. HUMPHREYS' GD Rev.
WHITE A.J Apr.
GEORGE RT Date Date Date 07/12/94 07/12/94 07/13/94 2.2.4 environmental conditions based on the design information contained in Section lS.l.3 of the Limerick Generating Station Updated Final Safety Analysis Report (UFSAR)
(Ref. 4.l).
UFSAR.Section 15.1.3 indicates that the design bases event for the isolation of the main steam line as a result of low steam line pressure is a failure of the main turbine pressure regulator.
This failure will result in no release of steam to the Turbine Enclosure environment.
Therefore PT-001-2N076C will not be subjected to any harsh environmenr effects when accomplishing its intended safety function.
Process c9nsideration has been included to provide support for additional operational flexibility. This process consideration appears within the calculation as consideration 51.
This consideracion is based on engineering judgement and reflects an amount approximately twice the accuracy of the transmitter plus an additional amoW1t which results in a conservatively rounded 2.2.5 The delta between the Allowable Value (AV) and the Actual Trip Set Point (ATSPl within this 19 calculation i~~ PSIG which satisfies the IISCP Leave Alone Zone Requirement to provide at least one LAZ between AV and ATSP.
k'--17.345 2.2.6 Additional margin of~
PSIG was added to this calculation to support the current station setpoint Of thi~~
PSIG, 8. 406 PSIG is "assigned 17.345 margin" used to support the IISCP LAZ requirements as discussed in Section 2.2.5.
The remaining 8.939-7 3-~PSIG is *unassigned margin" which is considered additional conservatism that may be utilized in future analyses.
All other design inputs* to this calculation are documented on the Supporting Data Sheet Attachments.
3.0 ASSUMPTIONS 3.1.1
!I!h..gd.pa~&..J£;t1 1 Proct:u::e 1 imit for the M?in 5 team
/iJige 1 A'-' Pressure rsg 1 ?tion far 1 i 000rjck? js
__,,/
,a.scqmod t? be.,tE::t,t;~zd 11tl0 pt tO th8 =7i 1!l9 j Q tbp a?: *.:_, iek-i.:if!.~~~:7'~'"'"""
.... ~
None.
OA OA OA
' i
Attachment License Amendment Request - Supplement Docket Nos. 50-352 and 50-353 IECR LG 15-00017 Rev. 0 Attachment 7 Page 9 of 14 j LU CALCULATION FOR Cale No LI-00032 Nuclear Group PT-00l-2N076C 01 Page 006 of 029 Orig. HUMPHREYS GD Rev QA Date 07/12/94 Date 07/12/94 Date 07/13/94 4. 0 DOCTYPE:
000 Rev.
WHITE AJ Apr.
GEORGE RT jpsl"deS 9 Q"'9r Berate jgfQ!?Pitigp> QQd j5
<!~a i~ae!seea '.! 2 l e.f t~is C"l C"'J "tj CA
~he easis ef lahis ass~Heiii is IIS@P has ee~
~
9oi!.01i>-H r;z lilS991 ou;i mes
~ ia l 3.2 Assumptions Requiring Confirmation 3.2.1 None REFERENCES Current revision is 16 dated September 2012.
t.ed Final Safety 1/
4.1 Limerick Generating Station Up Analysis Report (UFSAR), Revisi n -Ho (dated ~1-4.2 4.J
- 1. 4 4.5
-Section Pressure*
-Section 15.
(Design Bas
.3 Pressure Regulator F ilure - Open reference).
S2 rating l?-~~hnica-Sp~cifications, ent ~
Table 3.3.2-2 tem l.c (dated Limerick Gen Unit 2, ~en 02/17/94) (op reference).
rations and Surveilla e requi~~i'rt'"l!!V'-V--v-..~-.....
Limerick Generating Station Units 1&2 System Design Baseline Document (DBD) L-S-16, Revis Section 3.2.9, Reactor Instrumentation Syst Basis reference).
0007 k) n~.
(Design t:he 4.7
-M Deleted_//~"9i;.;
.._........._.,'"---U.."
.. ~~el;~'a.i;,A~"IU"-ORl~~Ll.We.A~.D.A..../'...../
PECO procedure IC-11-50014 for PT-001-2N076C dated 06/28/BB, PIS-001-2NG76C dated 01/16/87.
Master Loop Sheet for PT-001-2N076C dated 06/28/88 (Applicability reference).
OA QA OA
Attachment License Amendment Request - Supplement Docket Nos. 50-352 and 50-353 IECR LG 15-00017 Rev. 0 Attachment 7 Page 10of14 I LU CALCULATION FOR Cale No LI-00032 Rev Nuclear PT-00l-2N076C 01 Page 007 of 02.9 OA Group Orig. HtJNPHREYS GD Date 07/12/94 DOCTYPE; 000 Rev.
- WHITE P.J Date 07 /12/94 Apr.
G 0 G R '
Date 07/13/94 4.9 4.10
~0017 Calculation M-75-12, Revis on -&St "Turbine Building Cooling Loadn (Location Da a reference).
4 11 B21-4020-L-001, Revision 0022 - General Electric Nuclear Boiler System Design Specification Data Sheets (DSCS) f Besi§n i*~~k~ (Rev. O historical reference) 0 - 1uclear e
e Specification for Limerick Generating Station Units 1&2 Power Rerate Operating Conditions (Power Rerate Information reference).
4.13 IISCP Project Letter to File M-P-PEOOl-0152 - Utilization of OPL-3 (Assumptions reference!.
4.14 IISCP Project Anomaly No. 114. Head Corrections for PT-OOl-l(2lN076A/B/C/D (Applicability reference).
for q.15 Action Request (Type CM NCR) A0851879 - Head Correction for PT-001-1N076A/B/C/D (Applicability reference).
4.16 Action Request ITVPe CM NCR) A08522B9 - Head Correction for PT-001-2N076A/B/C/D (Applicability reference).
5
- 0 ATTACHMENTS 5.1 See Supporting Data Sheet Attachments located within this calculation.
6.0 ANALYSIS 6.1 Loop Effects 6.1.l Loop IO No.
PT-00l-2N076C Config 01 6.1.2 Loop Function MAIN STEAM L!NE c LOW PRESSURE - NS4 ISOLATION 6.1. 3 Configuration Description MN STN LN C PRESS INDICATION 6.1.4 Loop Instrument List I OA OA OA Add new references shown below. ------*---------/
4.17 Transmittal of Design Information (TOOi) ES1400026, Rev. 0, "Low Pressure Isolation Setpoint for the Limerick Station Loop Uncertainty Calculation"
- 4.18 General Electric Safety Concern SC05-03, dated 3/29/2005, "Potential to exceed Low Pressure Technical S ecification Safety Limit."
OA
Attachment License Amendment Request - Supplement Docket Nos. 50-352 and 50-353 Nuclear Group LU CAI.CULl1TTON PT-001-2N076C DOCTYPE:
000 Device 01 02 FOR Cale No LI-00032 01 Page 008 of 029 Orig. HUMPHREYS Rev.
WHITE Apr.
GEORGE ID Number PT-001-2N076C PIS-001-2N676C AJ R"'
i 6.1.5 Device Dependency R.;;:v GD Date Date Date T
s Device Envi.ronrnent Power Calibration Radiation 01 02 6.1.6 Device Dependency References Environmental:
N/l\\
Power:
N/A Calibration:
N/A Radiati.on:
N/!.:..
6.1.7 PMA and PEA Effects Type Magnitude FMA PMA IR References PMA:
PEA:
0.00000 0.00000 0.00000 A/N N
N A
A B
S.ign 6.1.B Miscellaneous Random and Bias Effects ll.
B 00 07/
07/
07 I Type Magnitude Dependent:
Dt?.pe.ndent Uncertainty
.VN Sl S2 S3 R2 R3 0.01300 0.00000 0.00000 0.00000 0.00000 0.00000 References Instrument Sl:
SEE DESIGN INPUT 2.2.4 S2:
S3 :
El:
1'2:
R3 :
6.J..9 Basis Point of Interest:
!\\r::cident:
Pressure Effect s :
0.000 Normal Independent N
N N
N N
N 2/94 2/94 3/94 Sign
Attachment License Amendment Request - Supplement Docket Nos. 50-352 and 50-353 tluclear Group LU CALCUL."IT:::ON FOR Cale No LI-00032 PT-001-2N076C 01 Page 009 of 029 Orig. HUMPHREYS GD DOCTYPE:
000 Rev.
WHITE AJ Apr.
GEORGE RT 6.2 Device Effects 6.2.l Device Accuracy (CA)
Rev 00 Date 07/12/94 Date 07/12/94 Date 0 7 I 13 / 9 4 CA = va/S or Setting Tolerance (whichever is greater) nhere:
va vendor's stated accuracy S
instrument's calibrated span R
inst:rurnent's range 6.2.1.01 PT-001-2N07 6C va (0.25%*0.661*S S
1200.GC R
3000.00 Setting tolerance 0.0 1 CA '*"'
0. 00500 6.2.1.02 PIS-001-2N676C va
[0.13%~0.66J~s s
16.00 R
20.00 Setting tolerance 0.00 CA =
0.00250 6.2.2 Device M&TE Allowaru:e MTE = CA + margin i'Vhere:
CA = device calibration accuracy rnarqin = additional margin supplied by calculati..on originator 6.2.2. 01 PT-001-2N076C ra 0.00500 + 0.00000 MTE 0.00500 6.2.2.02 PIS-001-2N676C CA 0.00~50 +
0.00000 MTE 0.00250
Attachment License Amendment Request - Supplement Docket Nos. 50-352 and 50-353 Nuc.1.ear Group LU C.Z\\.LCUL!1TION FOR PT-001-2N076C DOCTYPE:
000 6.2.3 Device Drift CaJ.c No LI-00032 01 Page 010 of 029 Orig. HUMPHREYS GD Rev.
WHITE AJ Apr.
GEORGE RT D
= vd *
{~ (tc
- 1.25 I tdll Is Where:
vd vendor's stated drift specification td vendor's drift: time specification tc instrument's caLibration period S
instrument's ca.l:i.brated span R
instrument's range 6.2.3.01 PT-001-2N076C vd 0.2%"R td 900 tc 731 c*
.)
1200.00 R
3000.00 D
0.0050'1 6.2.3.02 PIS-001-2N676C vd 0.0 td l
tc 731 s
- 16. 00 R
20.00 D
- 0. 00000 6.2.4 Device Static Pressure Rev Date Date Date i3PE
- ~ ( SPz z ** SPs 2 l (for inclepenclent. pressure effects)
SPE SPz + ~Pc
{for dependent pressure effects)
SPz spz
- JPo Pel ; S SPs sps * !Po -
Pel / S Where:
spz vendor's stated zero static pressure effect sps vendor's stated span static pressure effect Po normal op(.;:rating pressure Pc calibrated pressure S
instrument's calibrated span R
instrument's ranqe NOTE: Static pressure effects are relevant t.o sensors only.
00 07/ 2 94 07/ 2 94 07/ 3 94
Attachment License Amendment Request - Supplement Docket Nos. 50-352 and 50-353 Nuclear Group LU CALCULZ\\TION FOR PT-001-2N076C Cale No LI-00032 01 DOCTYPE:
000 6.2.4.01 PT-001-2N076C Sf)S 0.0 sp::
o.o Po 0.00 Pc 0.00 s
1200.00
[{_
3000.00 SPs 0.00000 Sl?z 0.00000 SPE 0.00000 Page Orig.
Rev.
Apr.
6.2.4.02 PIS-001-2N676C sps 0.0 spz 0.0
?o o.oo o~
-*~
0.00 s
16.00 R
20.00 Sl?s 0.00000 SPz 0.00000 en-.
.....,;.":l':.t 0.00000 6.Z.5 Device Over Pressure 011 of 029 HUMPHREYS GD m-II'l'E AJ GEORGE RT OPE vope
- IPa -
Pml I S [for linear devices)
Rev Date Date Date OPE vope I S (for non-linear devices)
~a7here:
vope Pa Pm s
R vendor's stated over pressure effect maximum operating pressure instrument's desi.~;n pressure instrument's calibrated apan instrument's ranqe
!Pa -
Pml 00 07/12/94 07/12/94 07 /13/94 NOTE: Over pressure effects are relevant to sensors only, where the maximum operating pressure :Ls qreat.;,r than instrument's design pr:essur:e.
G.2.5.01 PT-001-2N076C vope Pa.
Pm s
i<.
OPE (O.S:r.*C.66) kR/L 0.00 4500.DO 1200.00 3000.00 0.00000
Attachment License Amendment Request - Supplement Docket Nos. 50-352 and 50-353 Nuclear Group LU CALCULATION FOR PT-001-2N076C Cale No LI-00032 01 DOCTYPE:
000 6.2.5.02 PIS-001-2N676C
'lOpe 0.. 0 Pa N/A Pm N/A s
- 16. 00 R
20.00 OPE 0.00000 Page Orig.
Rev.
Apr.
012 of 029 HUMPHREYS GD WHITE AJ GEORGE: RT 6.2.6 Device Drift Temperature DTE vte
- dT I S (for linear devices)
DTE vte I S (for non-linear devices)
Wher:e:
vte vendor specified temperature effect dT (Normal Temp -
68° F)
S instrument's calibrated span R
instrument's range 6.2.6.01 PT-001-2H076C vte
(((0.75%*R)+(0.5%*SJ)*0.66)/100 s
1200.00 R
3000.00 norm temp=
104.00 DTE =
0.00564 6.2.6.02 PIS-001-2N676C vte R
{60<=X<=90, o.o%~S} (90<X<=210, (0.:l'J.k0.66) "S}
- 16. 00 20.. 00 norm tr:!mp =
- 82. 00 DTB C. 00000 Device Accuracy 'l'emoeratu.re ATE vte
- dT ! S (for linear devices)
ATE vte I S (for non-linear devices)
Where:
vte vendor speci.f:i.ed t£omperature effect dT
!accident t emperature - normal temp12ratur:el S
- i. nstrument' s calibrated span R
instrument's range Rev 00 D.:ite 0 /12/94 Date
() /12/9'1 Date 0 /13/94
Attachment License Amendment Request - Supplement Docket Nos. 50-352 and 50-353 Nuclear Group LU CALCULATION FOR Cale No LI-00032 PT-001-2N016C 01 Page 013 of 029 Orig. HUMPHREYS GD DOCTYPE:
000 Rev.
WHITE AJ l"pr.
GEORGE RT 6.2.7.01 PT-001-2N076C vte
~' (((0.75%*R)+(0.5%*S))""0.66)/100 s
1200.00 R
3000.00 norm temp 104.00 accid temp=
104.00 J>..TE =
- 0. 00000 6.2.7.02 PIS-001-2N676C vte
{ 60<,,,X<,*,90, o. 0'1.. 'S f { 90<X<*:,210, (0. 4%*0. 66) **sJ
- 3 16.00 P.
20.00 norm_temp tl2.0G acc:id temp=
82.00 ATE = 0.00000 6.2.B Device Humidity HE dH
- vhe I S (for linear functions)
HE vhe I S lfor nan-linear functions)
Where:
vhe vendor's stated humidity specification S
instrument's calibrated span R
instrument's range clH
!ac:c:ident humidity - normal humidity!
6.2.8.01 PT-001-2N076C vhe 0.0 s
1200.00 R
3000.00 norm h 90.00 acci2 h =
90.00 HE 0~00000 6.2.8.02 PIS-001-2N676C
'-'he = 0. 0
- 3 16.00 R
20.00 norm h 90.00 accid h 90.00 HE 0.. 00000 Re!V 00 Date 07 / 2/94 Date 07/ 2/94 Date 07/ 3/94
Attachment License Amendment Request - Supplement Docket Nos. 50-352 and 50-353 Nuclear G1:oup LU C.l\\LCl.Jl:.iiYl' ION FOR PT-001-2N076C 01 DOCTYPE:
000 Cale No LI-00032 Page Oriq.
Rev.
fl..pr.
014 of 029 HUMPHREYS GD WEITE AJ GEORGE RT 6.2.9 Device Accuracy Radiation ARE AEE vre
- DeltaRad I S
'ire
- I S (for linear devices)
(for non-linear devices}
vendor specified radiation effect Rev 00 Date 0'7/12i94 Date en /12/94 Date 07;'13/94 Where:
vre DeltaRad s
(accident radiation level -
normal radiation level) instrument's cal.ibrat.ed span R
instrument's range 6.2.9.01 PT-001-2N076C vre
!O<=X<5,1.0%*R}(5<=X<55,4.0%*R}
~)
1200. 00 R
3000.00 norm rad 0.00000 acci~ rad= 0.00000 ARE = 0.00000 6.2.9.02 PIS-001-2N676C vre
{0<=X<0.22,0.0%*S){0.22<=X<55,0.5%*S}
s 16.00 E
20.00 norm rad 0.00018 accid rad= 0.00018 ARE =
0.00000 6.2.10 Device Seismic VSE SRS
- vse I S (for linear functions)
VSE vse I S (for non-linear functions)
~~Jh e:ce :
vse vendor's stated seismic specificat ion S
- i.nst r ument 's c<:,libr:ated span R
instrument's range SRS seismic response envelope (see Attachmt:nt 7) 6.2.10.01 PT-001-2N076C vse (0<=X<4,0.0 ~*R }{4 <=X<l0 0,0.5 ~*RI s
1200.00 R
3000.00 SRS See Attachment 7 V~:3E 0.00000
Attachment License Amendment Request - Supplement Docket Nos. 50-352 and 50-353 tJuc.lear Group LU CALCULATION FOR Cale No LI-00032 PT-001-2N076C 01 Page 015 of 029 Orig. HUMPHREYS GD DOCTYPE:
000 Rev.
WHITE AJ i\\pr.
GEORGE RT 6.2.10.02 PIS-001-2N676C vse 0.0 s
16.00 R
20.00 SRS See Attachment 7 VSE 0.00000 6.2.11 Device Power PSE = pss
- pse I S i*Jhe:1re:
pse vendor's stated power supply specification pss device power supply stability S
i.nstrurnent's calibrated span R
instrument's range 6.2.11.01 PT-0Cl-2N076C pse (0.005%*0.66)*S/1 s
1200.00 R
3000.00 pss 2.500 PSE 0.00008 6.2.11.02 PIS-001-2N676C pse 0.0 s
i6. 00 R
20.00 pss 2.500 PSE 0.00000 7 4 0 P..SSULTS 7.1 AL
/.\\L norm i\\L acc:i.d l\\L accid L c:r:.i TE r
.l\\TE~:!
OP Z OPE'-
- l. SP.E' HE E ARE 2 i\\HE b HE;:
S
£ PSE 2 A + OPE + SP + PE l~L n.orrn + S, AL norm + TS + RE + AHE, AL 0.00003 (for s > TE (for s ~ TE Rev 00 Date 07/l2i94 Date 07/12/94 Date 07/13/94 RE + AHE;)
RE + l'.HE)
Attachment License Amendment Request - Supplement Docket Nos. 50-352 and 50-353 Nuclear Group 1.2 7.J IECR LG 15-00017 Rev. 0 Attachment 7 Page 11 of 14 I LU CALCULATION FOR Cale No LI-00032 PT-001-2N076C 01 Page Orig.
DOCTYPE:
000 Rev.
Apr.
= £ o:i DT
= E OTE 2 DL = 0.00006 CL CL ""v + M where:
v
= E (setting tolerance11 M
.: t MTEl CL
= 0.00006 016 of 029 HU14PHREYS GD WHITE AJ GEORGE RT Rev Date Date*
Date QA 07 /12/94 07/12/94 07/13/94 7.4 TLU (Positive)TLUp = (IR + PMAp + PEAp + PCp + PMJ\\o + PEAo + ?Co +
~(AL+ CL+ DL + PMAr + PEAr + PCrlJ *Loop span (Negative)TLUn = [-
PMAn -
PEAn -
PCn -
PMAo - PEAo -
PCo +
-v(AL +CL+ DL + PMAr + PEAr + PCrll *Loop span All other variables as previously defined.
TLOp =
TLUn =
7.S NTSP
- 21. 47 PSIG
-21.47 PSIG (increasing) NTSP *- limit + {- PMAn - PEI\\n -
!?Cn -
PMJ\\o -
PEAO PCo + (1.645 /sigma I * -~(AL +CL + DL +
PMAr + PEAr + PCr)) *Loop span (decreasing) NTSP = limit + [IR
~ PMAp + PEAp + PCp + PMAo +
PEAo + PCo + (1.6~5 /sigma) * ~(AL+ CL+
"Nhere:
DL + PMAr
~ PEAr + 2Crl 1
- Loop span loop analytical or process limit 1ii9"+oa.Q* PSIG 1~-805.00 sigma..
2 NTSP
~
PS!G I~ L822.66 joA OA
Attachment License Amendment Request - Supplement Docket Nos. 50-352 and 50-353 Nuclear Group 7.6 7.7 IECR LG 15-00017 Rev. 0 Attachment 7 Page 12of14 I LO CALCULATION FOR Cale No LI-00032 Rev --* OA PT-001-2N076C 01 Page 017 of 029 Orig. HUMPHREYS GD Date 07/12/94 DOCTYPE:
000 Rev.
WHITE AJ Date 07/12/94 Apr.
GEORGE RT Date 07/13/94 ATSP (increasing! ATSP = NTSP + margin (decreasing) ATSP = NTSP - margin where:
margin additional margin suppl calculatiqn originator margin
~~-17.345 ATSP
~PSIG Allowab Value '----840.00 (Decreasing) AV = limit + [IR + PMAp + PEAp + PCp + PMAo + PEAo +
PCo + (1.645 /sigma )
- V(AL +CL+ PMAr +
PEAr + PCr)J *Loop span (Increasing) AV = limit + l-PM.An -
PE.An "' PCn -
PM.Ao -
PEAo -
PCo + (1.645 /sigma ) * -v(AL +CL + PMAr +
PEAr + PCr)l *Loop span AV 7.8 Accep Max :
Min
,,.-...;-...,-"'-...?'""'~..--....-.....r-..:;--.r....,.-""-....
All ther variables fined
~----
Max -
76S.87ij ~SIG Min
- u: 9i9 ?SIG
" \\ '----830.923 joA OA OA
Attachment License Amendment Request - Supplement Docket Nos. 50-352 and 50-353 Nuclear:
Group LU C.l\\LCULAT ION FOR PT-001.-2N076C DOCTYPE:
000 01 Cale No LI-00032 Page Or::Lg.
R(~V.
Apr.:.
018 of 029 HUMPHHEYS GD WHITE l\\J GEORGE RT ATTACHMENT 1:
Session Data Cal.culaUon Number LI-00032 Station LG Unit 2
Initiating SCR:
00 Rev Responsible Branch SEEI Safety Related (Y/N)
Y Date 07/12/94 Date 07/12/94 Date 07/13/94 Description NSSBS-M!'.lN STEAM LINE LOvJ PRESSURE: PT-001-2N076C LOOP System Number 001 Structure TURB. ENCL Component PIS-001-2N676C Revision A Description NIA Vendor Cale Number NI 1\\
Other Calculations N Provides info TO N/A Receives info FHOM.M-75-12 SupercedE~s N/ A R0vi.s:i.on Nl\\
Attachment License Amendment Request - Supplement Docket Nos. 50-352 and 50-353 IECR LG 15-00017 Rev. 0 Attachment 7 Page 13of14 Nuclear Group LU CALCULATION rOR Cale No LI-00032 PT-ooi-2N076C 01 Page 019 of 029 Orig. HUMPHREYS GD OOCTYPE:
000 Rev.
WHITE AJ Apr.
GEORGE RT Rev -tliT QA Dace 07/12/94 Date 07/12/9~.
Dace 07/13/94 ATTACHMENT 2:
Ca culation esults Device Accuracy Temperature Humidity Tol..
Pwr Supp Norm Ace id Ace id PT-001-2N076C PIS-001-2N676C T
s 0.00500 0.00564 0.00000 0.00000 0.00500 0.00008 o.002so 0.00000 0.00000 0.00000 0.00250 o.oacoa Device SPE Rad.
M&.TE Ace id Drif~ over Pres Seismic l?T-001-2M076C PIS-00l-2N676C T s 0.00000 0.00000 0.00500 0.00000 0.00000 0.00250 0.00504 0.00000 0.00000 0.00000 0.00000 0.00000 Process Concerns:
NORMAL Positive Negative Offsetting PMA 0.00000 0.00000 0.00000 PEi\\
0.00000 0.00000 0.00000 IR Other 0.00000 0.00000 0.00000 Loop Results:
NORI1AL TLU"'
AL NTSP*
AV*
AC:C Limits
-21.4656 21.46566 0.00003 Increasing N/A N/A Decreasing 737.5555 735.9990 t1in*:
N/A -17.3450 746. 9227 ATSP*
N/A 756.0004 Additional t*largin:
-~4§..Cl OL:
0.00006 ACCIDENT Positive Negative Offsetting 0.00000 0.00000 0.00000 0.00000 0.00000 0.00000 0.00000 0.00000 0.00000 0.00000 21.46566 ACCIDENT
-21.4656 0.00003 Increasing N/A N/A Decreasing 737.6555 735.9990 NIA NIA N/A CL:
- 0. 00006 746.9227 765.0781 756.0004 Ma.x*:
N/A~
765.0781
- These values are n
~
"-See section 2.2.6.
~
\\-Replace with new llSCP software calculation results.
I OA OA
Attachment License Amendment Request - Supplement Docket Nos. 50-352 and 50-353 UJ C.l\\I,CUU*\\'l'ION FOR Cale No LI-00032 PT-001-2N076C 01 Page 020 of 029 Rev 00 Nuclear Group Orig. HUMPHREYS GD DOCTYPE:
000 Rev.
WHITE AJ Apr.
GEORGE ?.T Date 07/12/94 Date 07/12/94 Date 07 /13/94 ATTACHMENT 3:
Loop Data A.Efiliation Number PT-001-2N076C Instruments PT-001-:i.N076C PIS-0Ql-2N676C
?IS-0Cl-2N676C Loop Description Function T
s I
Instruments Function MAIN STEAM LINE C LOW PRESSURE -
NS4 ISOLATION Originator HUMPHREYS GD 05/09/94 Reviewer WHITE A<<J Loop ID(*):
PT-001-2N076C Component ID(')
PT-001-2N076C T
PIS-001-2N67GC PIS-00l-2N676C Configuration Descriptions(*):
1: MN STM LN C LO PRESS NS4 ISOL 2: MN STN LN C PRESS INDICATION 3:
4:
5:
1 x x
2 x x
3 6:
8:
~):
10:
Configurations(*)
4 5
6 7
8 9
10 06/01/94
Attachment License Amendment Request - Supplement Docket Nos. 50-352 and 50-353 IECR LG 15-00017 Rev. O Attachment 7 Page 14 of 14 j LU CALCULATIOM FOR Cale No LI-00032 Rev NUclear PT-001-2N076C 01 Page 021 of 029 Group Orig. HUMPHREYS GD Date DOCTYPE:
000 Rev.
vJHITE AJ Date Apr.
GEORGE RT Date ATTACHMENT 4:
Loop Calibration Data Process Temperature Units Min 0.00 Max 0.00 Normal 0.00 Trip 0.00 Process Radiation Units DA 07 /12/94 07 /12/94 07/13/94 Min o.oooe+ooo Max O.OOOe+OOO Normal O.OOOetOOO Trip o.oooe+ooo Process Hwnidity Units Min 0.00 Max 0.00 Normal 0.00 Trip 0.00 0
p Sigma 2
Setpl::
~:o&eUnits: PS!GResec:
O.OOUnits:
Allw:,
~&...e.QUnits PSIG Oes/Sfty Lm~'fo..
0.00 Units Calibration Frequency
/.\\'731 Loop SettindTolerance 0.000 Loop Leave Alone Zone
- \\
6.708 Loop Cal Act:
0.000 Analytical/ProTc Lmt:
-~S~g0unitsPSIG \\
Originator(HUMPHREYS GD 05/09/
wer WHITE AJ 06/0l/9 840.00 821.00 Replace 720.00 with 805.00 (New Analytical Limit from TOOi).
I OA OA
Attachment License Amendment Request - Supplement Docket Nos. 50-352 and 50-353 Nuc.lear Group LU CJ\\LCULATION FOR PT-001-2N076C 01 DOCTYPE:
OOG Cale No LI-00032 Page 022 of 029 Orig. HUMPHREYS GD Rev.
WHITE AJ Apr.
GEORGE RT ATTACHMENT 5:
Instrument Data UNIT-SYSTEM CMP 'I"fPE LG2 001 I T CMP NUMBER PT-001-2N076C CMP DESCRIPT MAIN STEAM LINE C (821)
Manufacturer Code R369 Model Number ll5.3GB9R,J Serial Number 418005 Location 005239461 Power Supply Requirements 24.000 Power Supply Tolerance 2.500 QA Class Q Operating Time N/A DBE/Transient 23 REG GOE 1.97 N
Service Life 000 Environmental Qualification N
Se:i.smic. Class Installation Detail M-0830 SHT 0001 DETl\\Il, P044 HEVISION 0140 Originator HUMPHREYS GD 05/09/94 Reviewer WHITE AJ UNIT-SYSTEM CMP TYPE CMP NUMBER CMP DESCRIPT LG2 001 I T PT-001-2N076C MP..IN STE.AM LINE C R~v Date Date Date 00 07/12i94 07/12/94 07 /13/94 Function T 06/08/94 Function T Leep Diagram N/A Su.r.ve:i.llance Pree N/A Purchase Order Number M-206-!-.C Calibration Proc ST-2-001-411-2 Tech Spec Reference T3.3.2-2 ITEM l.C Computer Addr N/l\\
Mod Nurnber P&ID Number M-0001 FacilityLG Sheet.
0003 Subtype DWG Rev 0010 Rev Location Drawing Number M-1508 Cacili tylJG Sheet 0001 Subtype CWG Eev iJOlO Electrical Schematic Electrical Location Drwg E-0101 E-1209 LG 0001 0023 Board Location N/A LG 00001 DI-JG 0020 Fore.ign Print Number B21-1090-E-0;::7 LG 0006A DWG 0005
Attachment License Amendment Request - Supplement Docket Nos. 50-352 and 50-353 LU CALCUL}\\'l'ION FOR NuclE~ar PT-001-2N076C Group DOCTYPE:
000 Cale 01 Page Orig.
Rev.
II.pr.
No LI-00032 023 of 029 HUMPHREYS GD WHITE AJ GEORGE R
J.
ATTACHMENT 5:
Instrument Data Component IO PT-001-2N076C Function T lvlin Max Units Head Cori.:ect:i.on:
In.put Range:
0.00 1200.00 PSIG R*2!V 00 Da e 07 2/94 Da e 07 2194 Da e 07 3/94 Output Range:
4.00 20.00 MADC Setting Tolerance:
0.00500 HC Corrected:
SP Corre cted:
Leave Alone Zone :
0.00500 MTE Device MTE !KCUJ:acy Additiona l Margi n:
0.00000 Period:
731 Head Correction Re f e r ence:
Ml\\STER CAL SHEET Static Pressure Correction
Reference:
N/A Originator HUMPHREYS GD 05/09/94 Reviewer WHITE AJ 06/08/94
Attachment License Amendment Request - Supplement Docket Nos. 50-352 and 50-353 LU Ci\\LCUL.i\\TION FOR Cale No 11-00032 Nuclear Group PT-001-2N076C 01 Page 024 of 029 Orig. HUMPHREYS GD DOCTYPE:
000 Rev.
WHITE AJ Apr.
GEORGE RT ATTACHMEN'l' 5:
Instrument Data UNIT-SYSTEM CMP TYPE LG2 001 I S PIS-001-2N676C CMP NUMBER CMP DE SC RI P'l'
( B2 l)
~L.21IN STEAM LINE C PRESSURE Manufacturer Code R369 Model Nurober 510DU1 Serial Number 9458 Location 008289542 Power Supply Requirements Power Supply Tolerance QA Class Q Operating Time N/A DBE/Transient 23 REG GOE 1.97 N
Service Life 000 Environmental Qualification N Seismic Class Installation Detail N/A 24.000 2.500 Originator HUMPHREYS GD 05/09/94 Reviewer WHITE AJ UNIT-SYSTEM CMP TYPE CMP NUMBEH CMP DESCRIPT LG2 001 I S PIS-001-2N676C (821) MAIN STEAM LINE C PRESSURE Rev 00 Date 07/12/91]
Date 07/12/94 Date 07/13/94 Function I ;3 06/01/94 Function I S Loop Di.agram N/A Purchase Order Number MOOl Surveillance Pree ST-2-041-659-2 Tech Spec Reference T3.3.2-2 ITEM 1 ('
Calibration Pree ST-2-001-4 11-2 Computer l\\ddr N/A Mod Number Rev l?t~ ID Number M-0001 F'a.c.i lit yLG Sheet 0003 Subtype DWG Rev 0010 Locat.i..cn fJrawi ng Humb<~1:
M- 0603 Fac:i.li tyLG
- 3heot 0001 Subtype ewe Rev 0014 Elec trical Sche mat ic Electrical LocatLm Drwg E-0101 E-1183 LG 0001 m1G 0023 Board Location El 2-P609-C-012 LG 0001 DWG 0009 LG 0002 D\\i1G 0021 r.*or.e1gn Pr i nt: Number B21-1090-E- 027 LG 0006!\\.
DWG 0005
Attachment License Amendment Request - Supplement Docket Nos. 50-352 and 50-353
'Lt) CALCULATION E'OR Nuclear PT-001-2N076C Grnup DOCTYPE:
000 Cale 01 Page Orig.
Hev.
Apr.
No LI-00032 Rev O-
,:..,) of 029 HUMPHREYS GD Date WHITE l\\,J Date GEORGE RT Date ATTACHMENT 5:
I nstrument Data Component ID PIS-001-2N67 6C Input Range:
Output Range:
HC Corrected:
SI? Cor rected:
MTE Oevir.::e Min 4.00 0
.~ccu rac y Head Correcti on Reference :
Max 20.00 1
Funct :i.on. S lJn:i. ts M.ADC N/ A Head Correction:
Setting Tolerance:
Leave Alone Zone:
Additional Mar gin:
Period:
Static Pressure Correction Ref erence:
N/A Originator HUMPHREYS GD 05/09 / 94 Revi0wer WHITE AJ 00 07/ 2/94 07/ 2/94 07 I 3/94 0.000 0.0025()
0.00250 O.QOOOO 731 OG/Ol/94
Attachment License Amendment Request - Supplement Docket Nos. 50-352 and 50-353 LU CALCULATION FOR Nuclear:
PT-001-2N076C Group DOC:TYPE:
000 Cale 01 I? age Orig.
Rev.
Apr.
No LI-00032 02 6 of 029 HUMPHf/,EYS WHITE i-\\T GEORGE R'i' -
ATTACHMENT 6:
Vendor Data Instr Manuf R369 Model no 1153GB9RJ B.eference Function: T Rev 00 GD Date 07/12/94 Date 07/12/94 Date 07/13/94 IISCP PRC,JECT LETTER TO FILE M-P-PEOOl-0056, REFLECTS 2 SIGMA Vl\\LUES Rng Min O.OOOe+OOO Max 3.000e+003 Units PSIG Design Pressure 4500.00 1------------------Accuracy Inf ormation----------------i Accuracy St:;isrni.c T~~mpera ture Radia.t:i.on Over Pressure Humidity Drift Time Power Supply Pressure Zero (0.::'.5%*0.66) *S
{0<=X <4,0.0%* R}(4<=X<10 0,0. 5~*R I
(((0.75%*R)+(0.5%*S))*0.66)/100
{0<=X<5,l.O.*R){5<=X<55,4.0 "*R}
0.0 0.2 'P.
900 (0.005%*0. 66) kS/l 0.0 Pressure Span 0.0 Originator HUMPHREYS GD 04/27/94 Reviewer WHITE AJ Instr Marmf R369 Model no 510DU1 Refereni:::e Function: S 06/01/94 IISCP PROJECT LETTER TO FILE M-P-PEOOl-0057, REFLECTS 2 SIGMA VALUES Rng Min 4.000e+OOO Max 2.000e+OOl Units MADC Design Pressure 0.00 1-----------------.Accuracy Inf or.mation----------------1 (D.13~1*0. 66) *~ s 0.0 Accuracy Seismic Temperature Radiation Over Pressure
{60<=X<=90,0.0'l;+S/{90<X<=210, (0.4. *kQ.66)'S}
(0<=X<0.22,0.0%'S} {0. 22<=X<55,0. 5 *S}
Humid:i.t:y Drift Time Power Supply o.o 0.0
\\). ;j 0.0 Pressure Zero 0.0 Pressure Span 0.0 Originator THOMAS RT 03/18/93 Reviewer CRABBS BL 05/05/94
Attachment License Amendment Request - Supplement Docket Nos. 50-352 and 50-353 LU CAI.Ctn.11T I ON FOR Nuclear PT-001-2N076C Group DOCTYPE:
000 Ca.le 01 Page Orig.
Rev.
Apr.
No I.iI-00032 Rev 0'"'7
'-. of 029 HUMPHREYS GD Date i~JHITE :D..J Date GEORGE RT Date ATTACHMENT 7:
Location Data Location Code: 005239461 COOLING WATER EX & PP TRIP Mi.n Normal LOCA HELB MSLB Temp 65.00 104.00 104.00 104.00 104.00
?.ad O.OOOe+OOO O.OOOe+OOO
- 0. OOOe*;-000 O.OOO<a+OOO O.OOOe+OOO Humid 10.00 90.00 90.00 90.00 90.00 Press 14.70 14.70 14.70 14.70
- 14. 70 Seismic Response Envelope:
0.00 Originator HUMPHREYS GD 05/02/94 Reviewer WHITE AJ Location Cede: 008289542 Desr;r.i.ption:
ROOfv.1 542, AUXTLITIHY EQUIHtfENT ROOM TP.IP Min Normal LOCA HELB MSLB Temp ht1
- v.00 82 00 82 00 82.00 82. 00 Had 5 OGOE:-004 1.760e+002 1 890e+002 1.7G0e+002 1.760e+002 Humid 30 DO 90 00
- 90. 00 90.00 90.00 Press 14 70 14. 70 1'J. 70 14.70
- 14. 70 Seismic Response Envelope:
0.00 Originator THOMAS RT 03/31/93 Reviewer CP~L;BBS BL 00 v /12 94
" /12 94 0 /13 94 Max 104.00 O.OOOe+OOO 90.00 14.70 06/01/94 Max 82.00 1.760e+002 90.00
- 14. 70 1)5/05/94
Attachment License Amendment Request - Supplement Docket Nos. 50-352 and 50-353 LU CALCULATION FOR Nuclear PT-001-2N076C Group DOCTYPE:
000 01 Cale No I..I-00032 Page 028 of 029 Orig. HUMPHP.EYS GD Rev.
WHIT'E AJ Apr.
GEO EGE ET ATTACHMENT 8:
Process Concerns Con~1:i.deration 1 PM.I\\
2 PEA 3 IP.
4 Sl 5 S2 6 S3 7 Rl 8 R2 9 R3 Contribution to Unc~:;rta.1nty S.ign 0.00000 O.GOOOO 0.00000
- 0. 01.300 R
0.00000 0.00000 0.00000 0.00000 0.00000 Consideration References l
2 3
4 SEE DESIGN INPUT 2.2.4 5
6 7
8 9
A/N N
N N
N N
N N
N Dependent Device Rev 00 Date 07/ 2/94 Date 07/ 2/94 Date 07/ 3/94 Dependent Uncertainty
Attachment License Amendment Request - Supplement Docket Nos. 50-352 and 50-353 LU CALCULZ\\l' I ON E'OR Nuclear PT-001-2N076C Group DOCTYPE:
000 Ol Cale No LI-00032 Page 029 of 029 Orig. HUMPHREYS GD Rev.
WHITE A,J Ap'r.
GEORGE RT ATTACHMENT 9:
Device Dependencies Calibration Dev.ices Dc.::pendency Static Env Pwr:
Cal Rad Press PT-001-2N076C T
l; A
A A
0 PIS-001-2N676C
,~,,
B B
B B
0 Dependency References EnvN/A Cal N/A PwrN/A Rad N/A Cal Cond Reference N/A Just Maximum Normal Hum.idi.ty for the Location Code Rev 00 Date 07/12/94 Date 07 /12/94 Date 07/13/94 Conditions/Data Cali.b Hum.id Sensor 90 y
90