BVY 08-087, Attachment 2, Technical Specification Proposed Change No. 273, Supplement 6, Sample Set-Point Calculations
| ML083650008 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 12/18/2008 |
| From: | Entergy Nuclear Operations |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| BVY 08-087 | |
| Download: ML083650008 (161) | |
Text
Docket 50-271 BVY 08-087 Technical Specification Proposed Change No. 273, Supplement 6 Vermont Yankee Nuclear Power Station Sample Set-point Calculations
VY CALCULATION CHANGE NOTICE (CCN)
'&jc. -
4(*2. Cd
- ccM -Oj.
CCN Number:
01 Calculation Number:
VYC-462C Rev. No.
0 454w Calculation
Title:
Reactor Core Isolation Cooling Steam Line Areas H-igh Temperature Setpoint Initiating Document:
PO 99-59110-00; Commitment VYC-0462CR0-03 VYDC/MM/TMISpec. No./ other I
UNCONTROLLED COPY Safety Evaluation Number:
N/A JFR IFR A IN O L Superseded Document:
N/A Reason for Change:
Provide a basis for increase in Technical Specification Surveillance Interval from Monthly to Quarterly.
Description of Change:
I. Evaluate CTS Quarterly testing interval on calculation outputs.
- 2. Address commitment memo issues.
SEE PAGE 4 FOR DETAILS Technical Justification for Change:
Technical Specification proposed change No. 217 requests surveillance test interval change from monthly to quarterly.
==
Conclusions:==
For CTS Quarterly:
- 1. Existing setpoint and uncertainties supports Quarterly functional testing of logic.
- 2. Setpoint, calibration attributes remain unchanged.
SEE PAGE 5 FOR ADDITIONAL CONCLUSIONS Prepared By/Date Interdiscipline Review By/Date Independent Review By/Date Approved By/Date c~4~~2/3/00 Installation Vcrification Signature Date Note:
VYAPF 0017.07 should be included immediately following this form.
VYAPF 0017.08 (Sample)
AP 0017 Rev, 5 Page I ofl DI #99-381
VY CALCULATION DATABASE INPUT FORM I yC. - i?
C.. -C
- o01_
P, z. -j' 4,"2g 2-f P72 1 k,d VYC-462C-CCN-01 0
N/A VY Calculation/CCN Number Revision Number Vendor Calculation Number R
Vendor Name:'
N/A PO Number:
N/A Calculation Type (Originating Department):-
VY Design Eneineering (EI&C)
Implementation Requi-red?'W es-No '4Zýg5.4,It L~
Asset/Equipment ID Number(s):
Various Asset/System ID Number(s):
13 Keywords:
No New Keywords General References Refe~rencc #
Reference Title (including, Rev. No. and Date. if annlicable) (Sihe Ann. A. Section 3.1.7 for Guidancc'*
N/A 1 P"'
evision Number Critical Reference (")
1 Technical Specification Proposed Change #217 Design Input Documents - The following documents provide design input to this calculation.
Document ft Document Title (including Rev. No. and Date, if applicable)
Critical Reference L.
No New Design Input Docutents Design Output Documents - This calculation provides output to the following documents.
Document #
Document Title Critical Reference (U No New Design Output Documents VYAPF 0017.07 (Sample)
AP 0017 Rev. 5 Page I of I
Page of Calculation Number:
VYC-462C Open Item VY CALCULATION OPEN ITEM I Revision Number:
0 Resolution CCN Number:
01 Method of 01 Tracking or Date Closed I
J 1FAo I-jsConIF4ok
ýj TC +.d%~ ORG-qk 4NA AL\\
(
7r-t5-13-N,?,0A,8jA ~~
- 4.
-b 19 1'r--
A6.
L-'
Ts-1 Y71
. YPch R. Q Sqck-, f
+b >7oP.CAJorchwn%
-t C',
(jJ 0
S I
I' 2~.
0 VYAPF 0017.05 (Sample)
AP 0017 Rev. 5 Page 1 of I
VY CALCULATION SHEET i.Jiin Mmher:
0 Calculation Number'
'4 o'(f CCN Number:
0 A- -
c~~pje cLý5 e.
j~ V A
medV 0-' cý MoAA-tuAoqS e.*.
0-4 oo. v_
c, rjr e v- ', e.
c.*
isC4e-rcoL C~o 4-W4-6 -o r - et v' t o -
tkoL 1
ev, c
? o e4'~
v.
- Vi9, c.r o C 243(cY3 v-- c C;4
\\-,ý
-00 c-CC,-I o
LA..
0 cv-:
L A A
-4 VYAPF 0017.03 AP 0017 Rev. 5
vyc-4 i.e- -CoC
- 0&
VY CALCULATION SHEET Calculation Number:
'04L - 44(Z, C Revision Number:
0 CCN Number:
C.
Page 0 of
> 2.0 coA CL.s; o 45 A. Vo v- 'P
-vl A~4Ct..-,
A,
-V s
5, Ce CA L o-.Sc--
,loA*,t-:
A.
,u V.. r
- e 4-roa,,,,- c,_,,-,.
t A e;.,0;,.
",-s -*,
F.
5V,.,.
b.,...
Le..."A.
L
=PlC-o4-4?~CeZo
-3 c,,A'e:i.
,~.~"
-NA--
$ee.. VYCV-4K C,
\\-o F
-,5 H., ?? 4-L A
S*
S5 C.'G,-
V-.f be VYAPF 0017.03 AP 00A17 Rev. 5
V G
a'~ 2~iL2
%I,,
RCIC Steam Line Areas Hinh Temperature Setvoint r '1 ~
VYC-462C.. Rm,. 0 RCIC Stegm Line An= High J-eauvEgm[e-Setpoint VYC-"2C Rev. 0 1.0 PURPO-SE I.I Cal'M Oices This calclation is performed in support of the Vamnont Yankee Setpoint Progran and has the following mae objectives:
I.
Document the loop function and the basis for the sepomnt and operator decision points associated with that function.
- 2.
Determine the normal and total loop unceiainty and verify consistency with the design basis.
- 3.
Calculate the limiting setpoint and operator decision points.
- 4.
Evaluate the adequacy of the existing setpoint, calibration limits and procedural decision points.
- 5.
Provide aleft and as-found tolerances for use in calibration procedures; deemine Meuting and Test BRpippmaut selection and accuracy criteria document process corrections instrumnt scaling, calibration methods.
- 6.
VYDEP-I 5 requires dial applicable operating procedures, alarm responses, Mandard, off-normal and emergency operating procedures be included in the evaluation. This requirement is accomplished by the inter-disciplinary review which supplements the WE-103 review process and is documented in Attachment 0.I 1.2 Sysocommnntts This calculation applies to the Reactor Core Isolation Cooling (RCIC) Steam Line Area's High EnMe
/
Line Break (HELB) detection switches in the RCIC System..The specific cumpontats to be addressed a "e:
'1'1 I I
I PAL ITAG Number Loratlon MGM_____
6.6, TS-13-79A Steam Tunnel TemperaUr Fenwal 01-170230090 1179,I18 6.1, TS-13-BOA El. 25T 6" Switch 1oll*o3 9
9 6.14 TS-13-SIA
_____J TS-13-42A 6.6, ITS-13-79B Rx Bldg. El.
Temperature Fenwal 01-170230-090 1179, 1180 6.7, TS-13-S0B 213'9" Switch 6.14 TS-13-8IB
._--- TS-13-82B 6.6, TS-13-79C Rx Bldg. E*.
Temperature Fenwal 01-170230-090 1179, 10so 6.7, TS-13-O 213' 9" switch 6.14 TS-13-41C L____ TS-13-f2C 6.6, TS-I3-79D 6.7, TS-13-SOD 6.14 TS-13-SID
.TS-13-82D Ri Bldg. El.
213' 9" '
RCIC Room Temperature Switch Fenwal 01-170230-090 1179.1180 I
~~.A.7 2t-ov
~
~
~
~
~
Pag 0-\\A5s-C5 of~~~c~~
31~
~OW\\
~O
~evA
v........
.CII RCIC Steam Line Ares ffgh-Teapmmvrte Setpint VY)C-462C. Rev. 0 2.I.A Calibration Effect Considerations Per the Design Guide, CE is typically taken as the sum of the vendor's Rated Accuracy (RA) and the As-Left Calibration Tolerance (CT). Based on the number of samples used to determine DA (count = 199 as per VYC-1599, Table 4), a test will be applied to determine if credit can be taken for RA being encompassed by DA. Test methodology is described in detail in Reference 6.13. In essence:
- If DA < IRA' + CTr + vendor's rated drift2 + MTE2}1, then CE - CT I if DA ; [RAz + CT2 + vendor's rated drift+ + MTE'fV, then CE= CT + A where:
= Present Calibration Tolerance DA
= Analyzed Drift from VYC-1599 RA Vendor's Rated Accuracy MTE
= the Measuring & Test Equipment used in calibration and where the vendor's rated drift is valued at 0 bccause the vendor has no published drift specifications.
2.1.5 Simn Convention The sign convention used in the Design Guide is based on the effect of uncertainties on an instrument (or loop's) output signal. For this type of device. where there is no analog process inputisignal output relationship the effect of uncertainties are manifested as a shift in the setpolnt away from the ideal value. This results in a sign convention which is the reverse of that which is generically defined in the Design Guide.
2.1.6 Class 3 Assessment This analysis will. determine the95%/95% (single-sided/lS ctid 2.1.3) uncertainty applicable to a Class 1 setpoint. Appendix R/Station Blackout considerations do not require the same level of rigor and can be evaluated as a Class 3 selpoint (95A750, single sided). In accordance with the Design Guide, the Class I uncertainty va 'e can be converted to a Class 3 uncertainty (eC.). From the design guide (reference 6.1, Appendix. Table 1), a multiplier is determined as follows:
0.6St.96 = 0.35 Appendix R/Station Blackout support is an NNS function. Therefore, accident parameters do not apply.
Page 9 of 31
VY CALCULATION SHEET Calculation Number: *i1C-4GI,-
Revision Number:
0 CCN Number:
Page B
of 4q00o e S;.
e-a, Q,,-evA-ej M 0,4, v oTes o,e, IAa, J
o4. Z IC o: Ce*,.-
t" e-At C.A~,V-AObA
-rwk VYAPF0017.03 AP 0017 Rev. 5 rczJ-oI
,41(-_ 4,roZ-
- c-CýA.- 0 A, RCIC Steam Line Areas High Temperature Setoint VYC-462C-.Rev. 0 ' Zfr'o 2.2.9 Per Reference 6. 1, no uncertainty is credited against the relays controlled by these devices.
2.2.10 Based on the design location of these devices (see FSAR Sections 7.3.4.8.7 and 7.3.5) the nonconservative afilcts of Process Measurement (PM) are negligible.
2.2.11 Per CTS, the specified calibration interval is 'each refueling outage." Per Reference 6.9, this interval is typically bounded by II months and is taken as limiting (by the refueling eyL not calendar days).
To allow for a refueling cycle extended to beyond a nominal 18 months, this calculation will base extrapolated DA on a maximum interval of 684 days (using the criteria of once per operating cycle +25% as a convenience). If the calibration interval extends, for whatewver reason, beyond 684 ca dar days, an evaluation to determine the interval increase effect on setpoint is REQUIRED.
cc4 2.2.12 Per VYC-1599. Section 5.4, he analyzed drift dafa for these devices (pooled ProceduresOP 4322 1,.
and OP 4366) indicated little time dependency. Consequently, it is assumed the RSS extrapolation IZ/,/ 7 of calibration interval is appropriate.
qk 2/3/00 ell
-W...4 K aL rv.vi iWerM4L 011-o~~e 44
~yc.
Ye 5
e, Page 1I of 31
V.,
I oijc -4,(Z
.- C. - CCA - 01. I VYC-462C. R-ev. 0 * '44*
RCW' ~t~am I jap Ari'u~ l4iah Tpmwwsihn~ ~tnnint Rriv Stem Line Arms Riah 1-1--raft"Is' qP-Imint MTE2 = t4.00*F Consequently.
- MTE,
, = +[I.0052 + 4.0O2]'F
=.*4.13*F 4.1.5 Analyzed Drift (DA)
From VYC-1 599 (Attachment H), switches calibrated per OP 4366 (the scope of this calculation) and OP 4322 (Main Steam HELD Detection) met the criteria for pooled data. T"le output of VYC-5"9 (per Section 41)is a 95% probabitity/95% confidence level value, which meets the criteria of a Class I selpoint as per Reference 6.1. The following data applies to DA:
Average time interval is 544 days DA is I7.S40 F Data is evenly distributed about zero with a slope on the time dependency line equivalent to
<0.2 % per approximately 550 days showing, consequently, little time dependency.
' The data is nornally distributed with a highly peaked narrow distribution.
The average drift value for this group is -0.008% CS; since this value is less than 0.1% CS, bias effects are considered negligible.
Per assumption 2.2.11, extrapolation of DA from a baseline of 544 days to a maximum of 684 days take the form:
= +/-DAu, (684/544)'m
= +/-7.54oF(684544)02 4.1.6 Temperature Effect (TE)
Typically, DA accounts for a 20°F AT TE during calibration conditions. In this case, TE has the following considerations:
The measured process parameter is temperature, for which the device is designed.
Calibration technique is to preheat the switch (and associated calibraton TIC) and use a prefabricated test heater assembly to minimize any external influences and approximate nonnal operating conditions prior to temperature ramp-up to setpoint. Consequently, normal TE as an er*' r determinant is considered to be negligible.
TE = 0 Page 16 of 31
VIC, -
c-c
'iVYC7ý*2c' Raýo RCIC Steam Line Aro_
High Tenmerature Setpoint 4.1.7 Radition Effect (E)
Per Reference 6. 1. normal radiation effect is encompassed by DA.
RE= 0 4.1.8 Humidity Effect (HE)
No humidity effect is specified by the vendor. In addition, per Reference 6. 1, normal humidity effect is encompassed by DA.
HE=0 4.2 10UL~ncertiw~igf From Refetence 6.1 for this type of de'vice. and where there are no significant testing condition biases:
Initially.
ei =:b4 CE+ DA2 ]11(
Substituting:
= *9.82F--/
Accounting for a single side of interest approach as per Section 2.1.3:
e, = *t[9.82oF x 0.851
= *8.347oF To facilitate the calibration process. e, is conservatively rounded (with regard to setlpoint development) to:
4.3 Normal ModuletUncertainty (e..)
c.CM-j
.13/W In this cae, there are no additional terms to those accounted for in the un-rounded e, e.=en
- 8:3470F, conservatively rounded to:
e,= :8.40*F Page 17 of 31
NJ 'I (- - /t(
- Cc-A -
0 A,
?&I. i 4
Z 2.8 -
ViC-462C. Pmw. 0 If 24110t RCIC Steam Line Areas Hinh Temnemtur~ Setnoint RCIC -Stewn Line Arem High Temnend= Setwint Substituting-
- [5.00*F + 8-45TF162 (0.85) + 0.20°F
= + 8.SFI-8.35OF 4.4.3 - Seismic Module Uncertainty (eL,)
For HELB mitigation channels, em, is determined by HELB conditions of over-pressure coincident with, or subsequent to seismic effect. From Reference 6.7.1 (Attachment P),
post-seismic effect ranged from -3.1F to +4.20F. For conservatism, the post-seismic simulation flimutional crieria of +/-56F is taken as limiin e
Initially:
(5eerLi
(?oule.)
"I,'-3 SE - *5.00*F Accounting for uncertainties introduced by a seismic event followed by switch actuation caused by a RCIC turbine steam line HELB:
e,, = * [CE2 + DA2 + SEI]0 + OP Substituting:
e,, =1 [5.00OF2 +.45OF2 + 5.000 FI]* (0.85) + 0.20°F
-+ 9.570F/-9.37°F 4.4,4 Appendix MStation Blackout Considerations From Section 2.1.6, a multiplier of 0.35 is applied to the normal module uncertainty to obtain a Class 3 normal uncertainty (ea). From Section 4.3, the normal module uncertainty (ej)
= *8.40*F.
Applying the 0.35 multiplier.
e,
-8.40*F
4.5 Soetmint Evaluations 4.5.1 Custom Technical Specification (CTMl LSP S -I TU I However, because AL < T'S, the AL becomes the more limiting condition. Therefore:
4.5..I TS-13-79.80.1.82 (B.C.D1 LSPIUcO = AL - I TLU I Where:
Page 19 of 31
v-4c-4(g.Lc%_ - cc.*
VY CALCULATION SHEET Calculation Number:,Jc4y - 4(Z Revision Number:
o CCN Number:
0 J4.
Page
- ,3 of 4
of,*° C-~
ve~u~s VYAPF 0017.03 AP 0017 Rev. 5
r Vic
-4LZC - C-c-IJ - 0 Wj.e... 14-. oý -V-Q Q46 C.
VY RXV. 0
.. CIC St~iarn, Line Areas Hitrh Temneatr Setnoint VC42.Rv f.2~c 4.6.1.3 HELB/Seismic Safety Manin (Mi) to ElIs AL From Section 4.4.3 e8 s (positive vector)
TS-13-79.80.11.92 (B.,D)
Consequently:
Mm = 196-F - [I85*F + 9.570F]
- +1.43*F Iccza/-
-115160) 4.6.2 TS-13-79.80.8t,2 (A)
Consequently:
MIA = 200*F - 118?5F + 9.57*F]
- +5.43OF Improved.Tochnical Snecifications (ITS)
From References 6.18 (Attachment B) and 6.22, the current AL is 196°F for outside the steam tunnel and 200°F inside the steam tunnel. For ITS:
By inspection, it can he seen that the limiting nominal margin from LSPmco (tg6*F) to existing SP (I 85°F) is +l°F.
By inspection, it can be seen that the limiting nominal margin from LSPA (I 90*F) to existing SP (185-F) is +5°F.
Per Reference 6.16 (Ataechment MW, the original plant design was for an SP which was 200*F. From a review of plant area teinperahtu trends (Aachmsat G), maximum base temperature is assumed to be 1406F. Since LSPm accounts for the combined effects of HELB (as applicable) and seismic effect, no additional safety margin relative to LSPr is required 4.61.1.
Immroved. Tedmical Specific~ation Q~ogertI a.)
For an e" of(-)8.40F (non-worst case vector), and a maximum base temperature of 140*F (Tmx), operating margin is expected to be:
M4=[LSp-le.(1-T.,.
TS-13-79,80, 1.82 (B.C.D)
Substituting:
M4 i=t 86°F-I.-.4-F] 140-F
+37.60F Page 23 of 31
(
V
%,/YC -
Z ZC, - Cx_. 4 - o A, VYC-46IC. Rev
... I RVIC.team Line Areas Hiah Temnemitim Setntiint IL.
P OP 4366 Revision 12
- 2.
For TS the AV is the TS Limit
- 3.
From (SP + em.. toAL
- 4.
From(SP +
toAL From (SP, - e) to maximum normal tempeature 5.2.1 T'S-13-79..0,41.82 (B.C.DI - Outside Stem TwuLnel From the above table it can be seen that to support ITS and the current AL of 196F the existing setpoint of 1950F is acceptable for both CTS and ITS considerations.
5.2.2 TS-3-79.80.8t.82 (A) - Swith Inside the Steam Tunnel.
The existing 185*F setpoint is acceptable for both the EQ Program limit of 200*F, the Technical Specification limit of 2120F, and the Appendix R/Station Blackout temperature limit of 1740F.
5.3 Giahic Renesentation of Setnoint Data FIGUME I Graphic Representation of Setpolnt (CTS)
Technical Specification 212°F Analytical Limit (inside steam tunnel) 2006F Analytical Limit (outside steam tunnel) 196°F LSPA 191OF LSP.
187°F SPV &
Setpoint is retamed) t85OF LSP1 179 0F SRO Main Steam Tunnel Heatup 174,F Normal (MAX) - steam tunnel 140-F
- 1.
Calculated for normal conditions (to include OPmaa)
- 2.
Existing setpoint per OP 4366, Revision 12
- 13.
Not to scale, provides relative position only
'LZ6/1 Page 27 of 31
R oC Steam Line Aresm Hiah Temneratre Sennint0 e,
- 2. t VYC RmQ 'ý.216 9
1 " 1,06 FIGURE 2 Graphic Ropreseta~b of 8ton IS Andy" LUnit (inside sem
,mn e) e 20ooF Analytical Limit (outside stam tunnl) 196F Allowable Value' (AVA) 19rF Alowable Value (AV.,)
194e.vO..
30 I4F LSPUA 190*F LSP 0 D
196OF Spi epiti eand ISS5OF LSP) 179OF SBO Man Steam Tunnel He*tp 1740F Normal (MAX) - steam twmnel 140OF I.
For ITS, the Allowable Value is the ITS value.
- 2.
Not to scale; provides relative position only.
In order to support end implement the results of this calculation, the temperature switches are to be calibrated according to the following table:
VcA-'.
91-Ct4/jc 4/-,o IqI..
-1..
C,
-5 Testing is accomplished with the following equipment Monitorming thermocouple (Type K) (Installed)
T(C Reader (Digital Thermometer)
Heat source (Test Heater)
Digital Multhreter Variac
ý1510-1 Page 28 of 31
-pic, 4(.zc- - cc VY CALCULATION SHEET Calculation Number:
V-4 &C-- 4G2-.-
Revision Number:
0 CCN Number:
- 0) t Page An of j 2.L 43)cc1 5.4.4-Ca~-;LA-,
1 Te 5
.136 A -
A V-140w4~-
%5A" ie i
IC.ýioI VYAPF 0017.03 AP 0017 Rev. 5
(1 Memorandum
\\HL( - 4tG, _. - e_.-
- o:.
TO:
James Allen FROM:
Mark McKinley RE:
Commitment VYC-0462CR003 DATE:
December 23, 1999
- Jimr, The Setpoint Database has been updated per Commitment VYC-0462CR0 03. Attached are the printed forms from the Database for the components listed by the commitment.
The following discrepancies were noted during review:
EMPAC:
The following EMPAC equipment should have applicable calculation added to EMPAC
References:
TS-l3-79A-D/80A-D/81A-D/82A-D: (VYC-462C)
This item has been addressed with submittal of an EMPAC Equipment Change Form.
The EMPAC model number for the identified instruments needs to be corrected from 01-170230-09 to 01-170230-090.
This item.has been addressed with submittal of an EMPAC Equipment Change Form.
Surveillance / Calibration Procedure: OP 4366 (Revision 15) o Surveillance Procedure identifies an As-Found Tolerance of 11 Deg. F. The correct As-Found Tolerance should be +/- 8 Deg. F.
The VYC Limiting Setpoint is identified as 187 Deg. F for all identified switches. This is correct for the B,C, and D switches. However, the LSp for the A switches is 191 Deg. F.'
PP 7007, Interdepartmental Review Form:
Section 3.1.a (la) specifies to add the L.Sp value of 187 Deg. F for all switches tothe surveillance procedure. The LSp associated with the "A" switches should he 191 Deg. F.
o Section 3.l.a (Lb) specifics to add the As-Found Value of.+. I I Deg. F to the surveillance procedure.
Mhe correct As-Found value should be +/- 8 Deg. F.
Calculation: VYC-462C (Rev 0)
Section 4.1.5 identifies the DA term to be +/- 8.54. This is a typographical error and should be 8.45 (Note: the correct value was used in subsequent calculation steps).
q Section 4.2 identifies the DA term as 5.45. This is a typographical error and should be 8.45. The,
calculated value for e, is correct based on an 8.45 DA term.
t..
111 Section 4.6.1.3 indicates that the eCHs (positive vector) is 12.80.
This is a typographical error and w-"
should be 9.57. The 9.57 value was correctly used in subsequent calculation steps.a1,1111 Drift Calculation VYC-1599 was revised on 6/7/98. VYC-462C Rev. 0 was completed, reviewed and approved after this date but did not use the updated drift values.
Thanks N/la rk.N'lc K i i Ic y
Compilation of ISP A --.;
Errors ER99-0-7 3 aý,
[ tem C a.co.l
,.*,i
\\7 C-462C Rev 0 RCIC Terp Switches Approved: 1 1-5-98
?reparer: 'IA Description of Error Resolution How Identified I.
Database Entry
- 2.
DBD Validation
- 3.
Engineering Review
- 4.
Other Type of Error A = Administrative T = Technical Note:
Operabiftrj Concern Yes/No OP.4366 & IRF - Shows AF = I V F.
Should be 8' F.
This information is provided in the procedure discussion section and is used by the E&C engineer as an aid in evaluations. The AF values are not used for calibration acceptance criteria. The correct AF values were used in the calculation.
Action Required: None immediately. E&C to DI OP-4366 prior to next scheduled calibration.
I A
N DA'C462C Rev 0 RCIC Temp Switches ApProved: I I-5-99 Preparer: MLA OP-4366 & IRF-Shows LSP = 1870 F. This is correct for the B, C & D switches. The A switch LSP = 191' F.
I Use of a single LSP is more limiting and is conservative.
This was done intentionally. However, for accuracy, the LSP associated with the A switch should also be shown.
Action Required: None immediately. E&C can include the LSP at their discretion via DI to OP-4366.
I A
N
- VYC-462C Rev 0 Calculation Text - Typographical These typographical errors occurred as part of the A
N RCIC Temp Switches errors Were noted as follows:
conversion of Word Perfect to Microsoft Word. Similar issue Approved: 11-5-98 Section 4. t.5 shows DA = 854.
was addressed in ER99-0462. In this case, the correct values
/
Preparer. NIA Should be 8.45 were used in the analysis.
Section 4.2 shows DA = 5.45.
Action required: None immediately. VYC-462C will correct Should be 8.45 the typographical errors when next revised.
Section 4.6.1.3 shows error i
_12.80.
Should be 9.57 A
VyC-1596 Rev0 Section 4.6 identifies switches as PS-This is a typographical error that cannot be confused with I
A N
IHead Catculation 115-134A through D. Should be PS any other switch evaluation.
Approved: 2-15-97 134A through D.
Action Required: None immediately. VYC-1596 will correct I
Preparer: RR the typographical error when next revised.
V'YC-466 Rev 3 Calculation Text & OP-4324 -
The discussion is confusing. In particular, the head I
A N
NMSL Pressure Discussion on serpoint in regards head correction identified in Table 13 implies it is negative.
Approved: 2-27-98 correction is confusing and appears to However, the note associated with the head correction is Preparer: DK be incorrect, specific in it being a positive head correction - the negative value provided to indicate where the process trip would i
occur. The 835-psig field setting will result in a process trip Sof 833-psig. The field setting is referenced instead of the process trip throughout the calculation. This is specified to be the case by the statement in VYC-466 Attachment B
'Section 4.0 (head correction is not included in the analysis).
ý'Action Required: OP-4324 is correct as is - no change required.
Action Required: VYC-466 should be revised to clarify the difference between the field setting and the process setting.
Although the values shown throughout the calculation are I[
correct for field setting the head correction needs to be Sconsidered to clarify the process trip point.
-U 0
7..)
0' 5,.
7-Page 3 of 3
REVIEW CHECKLIST o
(ER 96109001) 20e~VZ A N/A any items not applicable to the calculation or CCN.
Requirement Preparer Reviewer
- 1.
Ensure the title page is properly filled out (items that are applicable).
Calculation or CCN number on cover Title reflects subject Correct QA record status box checked Page numbering and count is correct Cycle number is included ("NA" if not applicable)
Initiating document is listed SSC I.D. numbers listed Vendor calculation and revision number listed Vendor safety class P.O. number listed Superseded calculations listed Keywords assigned Computer codes (input/output) listed Signatures and dates are included and are in correct chronological order. The title page reviewer and approver dates do not predate other dates in the calculation
- 2.
The following forms are properly filled out and attached (if applicable):
Review forms VYAPF 0017.04 (Ensure dated signatures form the preparer and reviewer are included and all comments have been addressed)
,v.. '
Open Item Listing VYAPF 0017.05 Evaluation of Computer Code Use VYAPF 001 7.06 r4 A
,u !
Calculation Database Input VYAPF 0017.07 Calculation Change Notice VYAPF 0017.08
- 3.
Ensure review of the calculation can be done without recourse to the originator.
- 4.
Screening Evaluation/Safety Evaluation included.
t4 /A
- 5.
Ensure individuals responsible -for each portion of the calculation are identified when multiple preparers and/or reviewers are used.
- J(A Appendix H AP0017 Rev. 5 Page 1 of 3
APPENDIX H (Continued)
VIC Requirement ItIv*g'
-*r*,1
- 6.
Ensure that the calculation contains a title page, table of contents, calculation objective,method of solution, design inputs and sources, assumptions, calculation, results, conclusions and references.
,- "I-r-c-(-F,,0 Preparer Reviewer 7.
Ensure that each page has a page number, calculation number, revision number and CCN number, if applicable.
- 8.
Ensure that every page of every attachment (or Appendix) contains its attachment (or Appendix) number.
- 9.
Ensure that the methods for revising and correcting the calculation meet the requirements of App. C of AP 0017.
- 10.
Ensure that the legibility requirements of App. D of AP 0017 have been met.
- 11.
Ensure that the appropriate design inputs (e.g. QA records) were used and the source of these inputs are clearly referenced.
1 2.
Ensure that the calculation design information, both external and internal requirements have been met.
1 3.
Ensure that if design specifications were used as input to the calculation the performance characteristics are independently verified and documented.
- 14.
Ensure that all reviewers' comments have been addressed.
1 5.
Ensure that input and modeling uncertainties are explicitly addressed in the calculation. (ER 961090_02)
- 16.
Ensure that any restrictions and/or limitations on the use of the calculation are clearly stated.
- 17.
Ensure that computer codes are used in accordance with App. E of AP O017.
1 8.
Ensure that the applicable input considerations from App. C to AP 6008 have been incorporated and are explicitly addressed within the calculation.
- 19.
Ensure review of 10CFR50.46 reporting requirements has been documented for analyses which assess conformance to 1 OCFR50.46.
t4A
~~WIA ofA Appendix H AP 0017 Rev. 5 Page 2 of 3
APPENDIX H (Continued) vicP 4reace -
Rv e-wer A
Preparer Reviewer Reguirement 20.
Ensure relevant conditions/limitations have been reviewed for their effect on this calculation and the review is noted in the calculation.
PREPARER REVIEWER Name (print).
v V4 Name (print)
Zak,,
Organization Tr I y i Organization DE rtc (5ci Sg--t_)
Signature Signature 4,
Date itL~f~
Date I I A5 oo Appendix H AP 0017 Rev. 5 Page 3 of 3
Page
[
of I
VY CALCULATION REVIEW FORM Revision Number:
0 Calculation Number:
VYC-462C CCN Number:
01
Title:
Reactor Core Isolation Cooling Steam Line Areas High Temperature Setpoint Reviewer Assigned:
John Lewis Required Date:
1/29/2000 Comments*
Resolution a I,. V a, e "I Date Ki IA D 9W AM6, a keviewer Signature Calculati'n Preparer (Comments Resolved)
Daztil-10 Datý '-
.j 4
C'P p'J V
Method of Review:
ZCalculation/Analysis Review 11 Alternative Calculation Qu Qualification Testing (14 X"~
Reviewer Signare (Comments Resolved)
Date
- Comments shall be specific, not general. Do not list questions or suggestions unless suggesting wording to ensure the correct interpretation of issues.
Questions should be asked of the preparer directly.
ý-
VYAPF 0017.04 (Sample)
AP 0017 Rev. 5 Page 1 of I
Page __ofj VY CALCULATION REVIEW FORM Calculation Number:
.-t4(.v.C...
Revision N
Title:
RC-I--
S k
Legw.-
A,,,
W" i,*._
rumber:
CCN Number:
) I Reviewer Assigned: -
Required Date:
(1/Z9/aoo0 Comments*
Resolution I
kCa3io P (3
)6d Calcul ~ion Preparer (Comments Resolved)
IDite Reviewer Signatu Date I.
Method of Review:
[Týaiculation/Analysis Review Cl Alternative Calculation 0 Qualification Testing Revieter Signature (Comments Resolved)
'Date Vx 1ýr L;ý
- Comments shall be specific, not general. Do not list questions or suggestions unless suggesting wording to ensure the correct interpretation of issues. Questions should be asked of the preparer directly.
r
- 4ý VYAPF 0017.04 (Sample)
AP 0017 Rev. 5 Page I of I
VY CALCULATION REVIEW FORM Calculation Number:
0Prt.-4(..c..
Revision Number:
)
Title:
RC-jEC S+
La,, &m.*, 1 rt -r., k,,.,
5tioi4 Reviewer Assigned: "F.e1,6, Fc--nrL'r e.,
Required Date:
I/IZI2ooc Comments*
Resolution A/D Page _L of 'L CCN Number:
01' 0 (20 7ot C6-4'A 51-r4i-L, n o r fx, zý-i- -t F-Avr-AeFRecAsup EcT 6ýý T*-S CALCOLAJ?01--ý Pc-,)AZý,
43100 LAA4K-RXck 1z3/00 IDite Calculatl~n Preparer (Comments Resolved)
Method of Review:
X Calculation/Aayssiei-11 Alternative Calculation 1/4 0 Qualification Testing Aeviewer Signature (Comments Resolved)
Idate
- Comments shall be specific, not general. Do not list questions or suggestions unless suggesting wording to ensure the correct interpretation of issues. Questions should be asked of the preparer directly.
co
'it,
!r'*2 VYAPF 0017.04.(Sample)
AP 0017 Rev. 5 Page I of I
Page of,/-
o VY CALCULATION REVIEW FORM Calculation Number:
M.-4-*oZ.C.
Title:
Rctc S$+mji-- Le-A,.-.-.
Revision Number:
0(
CCN Number:
01" 1
'-.3 I
Reviewer Assigned:
Required Date:
Cornments*
,&?o//~i C Resolution M'3A L(\\z N
CalculatiA Preparer (Comments Resolved) tatk heviewA Signature (Comments Resolved) 1D te 1
0
/C) C)
Reviewer Signa4e-.
Date Method of Review:
,K Calculation/Analysis Review El Alternative Calculation 0 Qualification Testing NZ
- Comments shall be specific, not general. Do not list questions or suggestions unless suggesting wording to ensure the correct interpretation of issues. Questions should be asked of the preparer directly.
w VYAPF 0017.04 (Sample)
AP 0017 Rev. 5 Page 1 of I
VY CALCULATION R]
Calculation Number: v'r,-4C.Z.C..
Revision Number:
Tie C-c $Sfax-L'rj 6 ]U4 J;ýx4
- Sdz4 Page -J-of VIEW FORM C-CCN Number:
0j.
Reviewer Assigned:
-r
-A
,Required Date:
i/21/2000 Comments*
Resolution A,
I Pb K90.
6&e r
at e Method of Review:
,(CalculationJAnalysis Review El Alternative Calculation
[ Qualification Testing
ý3 [A -ý)13, CA~culaticUPreparer (Comments Resolved)
Date r.
[fA 0LAQ Reiewer ignature (Comments Resolved) tn
- Comments shall be specific, not general. Do not list questions or suggestions unless suggesting wording to ensure the correct interpretation of issues. Questions should be asked of the preparer directly.
r
_r VYAPF 0017.04 (Sample)
AP 0017 Rev. 5 Page 1 of I
Page __J of 14_1 VY CALCULATION REVIEW FORM Calculation Number: V'4(-.-
Revision Number:
)
CCN Number:
0 1
Title:
RC L sy.4 Laij IArvoc~ H
-re Y1 *-r agL c
&1va Reviewer Assigned:
N, E -D Required Date:_ I/_1/__ _
Comments*
Resolution x
2-1_
/1 Reviewer gnature Date Calculat~n Preparer (Cotmments Ptsoved)
D~te Method. of Re'ie*v:
3aC'alculation/Analysis Review E A.1terative Calculation eW &u(2.-
/
El Qualification Testing Seviewdiignature (Comments Resolved)
'Dtie
- Comments shall be specific, not general. Do not list questions or suggestions unless suggesting wording to ensure the correct interpretation of issues. Questions should be asked of the preparer directly.
00 VYAPF 0017.04.(Sample)
AP 0017 Rev. 5 Page I of I
Compilation of ISP A-]yses Errors ER99- 0-7 3 aý,
Item Calcua~i; Description of Error Resolution How Identified I.
Database Entry
- 2.
DBD Validation
- 3.
Engineering Review
- 4.
Other Type of Error A = Administrative T = Technical Operability Concern Yes/No Note:
VYC-462C Rev 0 OP-4366 & IRF - Shows AF = 11 F.
This information is provided in the procedure discussion I
A N
RCIC Temp Switches Should be 80 F.
section and is used by the E&C engineer as an aid in Approved: 11-5-98 evaluations. The AF values are not used for calibration Preparer: MA acceptance criteria. The correct AF values were used in the calculation.
Action Required: None immediately. E&C to D1 OP-4366 prior to next scheduled calibration.
2 VYC-462C Rev 0 OP-4366 & IRF - Shows LSP = 1870 Use of a single LSP is more limiting and is conservative.
I A
N RCIC Temp Switches F. This is correct for the B, C & D This was done intentionally. However, for accuracy, the LSP Approved: 11-5-98 switches. The A switch LSP = 191 0 F.
associated with the A switch should also be shown.
Preparer: MA Action Required: None immediately. E&C can include the LSP at their discretion via DI to OP-4366.
3 VYC-462C Rev 0 Calculation Text - Typographical These typographical errors occurred as part of the 1
A N
RCIC Temp Switches errors were noted as follows:
conversion of Word Perfect to Microsoft Word. Similar issue Approved: 11-5-98 Section 4-1.5 shows DA = 8.54.
was addressed in ER99-0462. In this case, the correct values Preparer: MA Should be 8.45 were used in the analysis.
Section 4.2 shows DA = 5.45.
Action required: None immediately. VYC-462C will correct Should be 8.45 the typographical errors when next revised.
Section 4.6.1.3 shows error=
12.80. Should be 9.57 4
VYC-1596 Rev 0 Section 4.6 identifies switches as PS-This is a typographical error that cannot be confused with t
A N
Head Calculation I 15-134A through D. Should be PS any other switch evaluation.
Approved: 2-15-97 134A through D.
Action Required: None immediately. VYC-1596 will correct Preparer: RR the typographical error when next revised.
S VYC-466 Rev 3 Calculation Text & OP-4324 -
The discussionis confusing. In particular, the head I
A N
MSL Pressure Discussion on setpoint in regards head correction identified in Table 13 implies it is negative.
Approved: 2-27-98 correction is confusing and appears to However, the note associated with the head correction is Preparer: DK be incorrect, specific in it being a positive head correction - the negative value provided to indicate where the process trip would occur. The 835-psig field setting will result in a process trip of 833-psig. The field setting is referenced instead of the process trip throughout the calculation. This is specified to be the case by the statement in VYC-466 Attachment B Section 4.0 (head correction is not included in the analysis).
Action Required: OP-4324 is correct as is - no change required.
Action Required: VYC-466 should be revised to clarify the difference between the field setting and the process setting.
Although the values shown throughout the calculation are correct for field setting the head correction needs to be considered to clarify the process trip point.
1~
1~
1~
+
I I
~1-
~1~
.t
+
+
I
+/-
.j.
.r
.j.
+
Page 3 of 3
/
QA RECORD?
_X_2 YES
-NO VYC-462C Attachment A Attachment B Attachment C Attachment D Attachment E Attachment F Attachment G Attachment H Attachment I Attachment J Attachment K Attachment L Attachment M Attachment N Attachment P Attachment Q Total Pages ORIGINAL: PAGE 1 of 2-PAGES 3
8 8
4 36 RECORD TYPE NO.
09.C16.004 17 2
3 4
Safety Class/P.O. NO.
SCE I
(if applicable)
I UNCONTROLLED COPY 3
31 FOR INFORMATIONONLY YANKEE NUCLEAR SERVICES DIVISION CALCULATION/ANALYSIS FOR TITLE REACTOR CORE ISOLATION COOIJNG STEAM LINE AREAS HIGH TEMPERATURE SETPOINT PLANT VERMONT YANKEE CYCLE 20 CALCULATION NUMBER YCAUC PREPARED BY REVIEWED BY APPROVED BY SUPERSEDES
/DATE
/DATE
/DATE CALC./REV. NO.
ORIGINAL
/r*'
VYC-4621 Rev.2 M. Anderson D. Willis e-rT 0,86R7T (Partial)
KEYWORDS RCIC. PCIS. Setpoint. Uncertainty. Steam Tunnel. -IELB COMPUTER CODES:
EQUIP/TAG Nos.:
SYSTEMS:
REFERENCES:
None TS-13-79A. B. C. D: TS-13-80A. B. C. D: TS-13-81A. B C D:
TS-13-82A. B. C. D Reactor Core Isolation Cooling (RCIC). System 13 OP 4366: Technical Specification Section 3.2/4.2.B. Tables 3.2.2 & 4.2.2 UNCONTROLLED COPY FOR INFORM.4 i I ) k WpMAxDERsONA~3IaKI S3'M FORM WE. 103-1 Revision 4
RCI(' Steam I'Ane Areas High Terrineratime Setnoint
..t m.L.ne
.A.e.. i-.
e.....I-..........
Se -
V.C.462C.. v 0 Table of Contents Page LIST OF TABLES LIST OF FIGURES 3
.............................................................................. 3 HISTORY OF REVISION.....................................................................................................................
4 1.0 PURPOS 1.1 1.2 1.3 SE 5
Calculation Objectives
.5 System/Components
............................................................................................ 5 Instrument Loop Function............................................................................................ 6 2.0 METHODS AND ASSUMPTIONS 8
2.1 C riteria.................................................................................................................. 8 2.2 Assumptions..........................................................................................................
10 3.0 IN PU T D A TA
.................................................................................................................... 12 3.1 Process and Loop Data........................................................
12 3.2 Environmental Conditions............................................................................................ 12 3.3 Switch Data........................................................................................................... 13 4.0 CALCULATION DETAILS 13 4.1 4.2 4.3 4.4 4.5 4.6 4.7 4.8 Normal Condition Uncertainties
............................................................................... 13 Test Uncertainty (eJ
.............................................................................................. 17 Normal Module Uncertainty (e.)
............................................................................... 17 Accident Condition Uncertainties............................................................................... 18 Setpoint Evaluations 19 Margin Evaluation
......................................................................................... 22 Allowable Value (ITS) 24 Calibration Tolerances
.............................................................................................. 25 5.0 RESULTS/CONCLUSIONS
.......................... 26 5.1 5.2 5.3 5.4 5.5 5.6 5.7 5.8 Total Loop Uncertainty 26 Setpoint Evaluation
........................................................................................... 26 Graphic Representation of Setpoint Data
.................................................................... 27 Calibration Criteria 28 Measuring & Test Equipment Requirements........................................................................ 28 Recommendations
........................................................................................... 29 VYDEP-15 Criteria 29 Evaluation of Existing Setpoint......................
............................ 30
6.0 REFERENCES
30 7.0 ATTACHMENTS 31 Page 2 of 31
RCIC Steam Line Areas High Temperature Setpoint VYC-462C, Rev. 0 LIST OF TABLES Page TABLE I Eomoa ntIdata Ce........................................................
5 TABLE 2 EQ Matrix Data 7
TABLE 3 Process/Loop Inputs.
.......................................................................................... 12 TABLE 4 Environmental Input Data..........................................................................
12 TABLE 5 Temperature Switch Input Data I........................................... 13 TABLE6 Total Loop Uncertainty Results...................................................................................
26 TABLE 7 Setpoint Results..
26 TABLE 8 Calibration Attributes
.......................................................................................... 28 TABLE 9 Recommended M&TE 29 LIST OF FIGURES FIGURE I Graphic Representation of Setpoint (CTS)
.................................................................... 27 FIGURE 2 Graphic Representation of Setpoint (ITS)
........................................................................ 28 Page 3 of 31
V T
Qfý I ;ný Arone 14; h Tom i-nihirA IQ
^;"*
XrTV( AKIOf D*.
n
~t.iTi~
r~
-ThT vrtup f~~nf~v 1~"f~,A LA If 5 ALMAtf'.
L'~S V__
!t I.-U', -IXV.
HISTORY OF REVISION Rev. No.
]
Approval Date Reason and Description of Change 0
10-30-98 Initial issue; incorporate plant-specific analyzed drift data and new setpoint methodology; support Improved Technical Specification submittal; VYC-462C Revision 0, supersedes VYC-462, Revision 2, (Calculation subset "C" addresses the loop function of Reactor Core Isolation Cooling Line HELB detection).
2 Page 4 of 31
RCIC Steam Line Areas High Temrierature Sethoint VYC-46?C_ Rev_ 0 1.0 PURPOSE 1.1 Calculation Objectives This calculation is performed in support of the Vermont Yankee Setpoint Program and has the following major objectives:
- 1.
Document the loop function and the basis for the setpoint and operator decision points associated with that function.
- 2.
Determine the normal and total loop uncertainty and verify consistency with the design basis.
- 3.
Calculate the limiting setpoint and operator decision points.
- 4.
Evaluate the adequacy of the existing setpoint, calibration limits and procedural decision points.
- 5.
Provide as-left and as-found tolerances for use in calibration procedures; determine Measuring and Test Equipment selection and accuracy criteria; document process corrections, instrument scaling, calibration methods.
.6.
VYDEP-15 requires that applicable operating procedures, alarm responses, standard, off-normal and emergency operating procedures be included in the evaluation. This requirement is accomplished by the inter-disciplinary review which suppements the WE-103 review process and is documented in Attachment 0.
1.2 System/Components This calculation applies to the Reactor Core Isolation Cooling (RCIC) Steam Line Area's High Energy Line Break (HELB) detection switches in the RCIC System. The specific components to be addressed are:
TABLE 1 Component Identiflcation Re.
TAG Number.
Location Description MFG Model CWD 6.6, TS-13-79A Steam Tunnel Temperature Fenwal 01-170230-090 1179, 1180 6.7, TS-13-80A El. 252' 6" Switch 6.14 TS-13-81A TS-13-82A 6.6, TS-13-79B Rx Bldg. El.
Temperature Fenwal 01-170230-090 1179, 1180 6.7, TS-13-80B 213' 9" Switch 6.14 TS-13-81B TS-13-82B 6.6, TS-13-79C Rx Bldg. El.
Temperature Fenwal 01-170230-090 1179, 1180 6.7, TS-13-80C 213' 9" Switch 6.14 TS-13-81C TS-13-82C 6.6, TS-13-79D Rx Bldg. El.
Temperature Fenwal 01-170230-090 1179, 1180 6.7, TS-13-80D 213'9" Switch 6.14 TS-13-81D RCIC Room TS-13-82D Page 5 of 31
R CICStpArri I.ine Areas Migh Temnerature Setnoint VYC-462C-Rev- 0 1.3 Instrument Loop Function 1.3.1 Normal Operations There are no indicators or anticipatory alarms associated with these channels. Instrument output is a contact change-of-state at the setpoint; therefore, these channels have no normal operational function.
1.3.2 Off-Normal/Accident Operations High temperature in the space in which the RCIC steam lines are located outside of primary containment could indicate a breach of an RCIC steam line. Isolation Signal K (steam line high space temperature OR high steam flow OR low steam line pressure) results in automatic closure of the Class A valves which isolate the RCIC Turbine Steam Supply Line.
High temperature in the vicinity of the RCIC steam lines or equipment is detected by four sets (of four) of bimettalic temperature switches. The detectors are located or shielded such that they are sensitive to the air temperature but not the radiated heat from hot equipment. The trip setpoint is set far enough above the temperature expected during operations at rated power to avoid spurious PCIS isolation yet low enough to provide early indication of a steam line break.
Associated with each set of detectors is an additional temperature loop (TE-1 3-77A to D) monitoring the same space (Reference 6.19.4) and which provides:
Remote temperature indication Alarm on HIGH temperature Alarm on loss of power (Reference FSAR Sections 7.3.4.7.7, 7.3.4.8.7 and FSAR Figure 7.3-6.)
Note that a RCIC isolation signal from sensors located in the steam tunnel are permissive through a nominal 30 minute time delay relay (Ref. 6.19 and FSAR Figure 7.3.5b).
1.3.3 Accident Mitigation (Harsh Environment)
From Reference 6.7 and Table 2:
0 Components will experience a Loss-of-Coolant Accident (LOCA) harsh environment but are not required to function, nor be LOCA qualified.
For RCIC HELB, components are required to function and are EQ qualified, with an operability duration of one hour for auto PCIS actuation. While a Small Break LOCA (SBLOCA) may exceed the one-hour qualified duration, operator action is credited for SBLOCA detection and manual isolation.
For other HELBs outside the RCIC Steam Line Areas, the components will either not experience a harsh environment or, if in a harsh environment, are not required to function for that scenario.
Page 6 of 31
TABL T
EQ-Mari Data "
Il
- I
"_A410"
- D,*,A SLJ C..IL X~tcw.
53~.O
- AU 1.A1 W
S'LLL.A,.
- jttVJ1, VI
?
L' V.
TABLE 2 EQ Matrix Data Loop Location Accident CAT TBNI,2 FI,2,3 Duration TS-13-79A, 80A, Vol. 41 LOCA E
36, 22 6
N/A 8 IA, 82A MS-HELB C
36,23 0
N/A HPCI-HELB C
23,36 0
N/A RCIC-HELB A
36,4 1
1 hr.
RWCU-HELB C
23, 36' 0
N/A HHS-HELB C
23, 36' 0
N/A TS-13-79B, 80B, Vol. 42 LOCA E
22, 36 6
N/A 81B, 82B MS-HELB C
23,36 0
N/A TS-13-79C, 80C, HPCI-HELB C
23,36 0
N/A 81C, 82C RCIC-HELB A
4,36 1
1 hr.
RWCU-HELB C
23 0
N/A HHS-HELB C
23 0
N/A TS-13-79D, 80D, Vol. 52 LOCA E
22, 36 6
N/A 81D, 82D MS-HELB E
23,36 0
N/A HPCI-HELB C
23,36 0
N/A RCIC-HELB A
4,36 1
1 hr.
RWCU-HELB E
23, 362 0
N/A HHS-HELB E
23, 362 0
N/A
- This set, Note 36, does not apply to TS-13-80A 2 This set, Note 36, does not apply to TS-13-80D, -81D, -82D 1.3.4 Post-Accident or EOP Functions These channels do not provide any indication or any further function once PCIS isolation actuates when the protected areas reach the trip setpoint. These channels are not identified as post-accident instrumentation in Technical Specification Table 3.2.6.
1.3.5 Appendix R/Station Blackout Considerations During a station Blackout the Main Steam Tunnel will heat up to approximately 1741F (Reference 6.20). RCIC is relied on to bring the plant to a cold shutdown condition. To do this, the RCIC high temperature switches located in the steam tunnel cannot be set so low as to cause the RCIC Isolation valves to close unnecessarily. To preclude this, the RCIC line high temperature switches should be set as high as reasonably possible. This is not a safety related function (Reference 6.21).
Page 7 of 31
RCIC Ste.nm Line Area-, Hiph Temnernihire Setnoint
.............A.e
.i-
- e.
C 4 62C R ev 0 2.0 METHODS AND ASSUMPTIONS This calculation has been prepared in accordance with the "Vermont Yankee Instrument Uncertainty and Setpoint Design Guide" (Reference 6.1), and WE-103, "Engineering Calculations and Analysis" (Reference 6.2). Standard methods employed in this calculation are explained in the Design Guide; special techniques and criteria are explained below. The requirements of VYDEP-15 (Reference 6.5) are accomplished through the Interdisciplinary Review process.
2.1 Criteria 2.1.1 Setpoint Class As shown in Table 2, these components are associated with Safety Function 1, "HELB Detection and Isolation." Consequently, per the Design Guide, these components' trip setpoints are Class 1, Nuclear Safety-Related.
The switch function in support of Appendix R/Station Blackout is not nuclear safety related.
Consequently, per the Design Guide, the need to not inadvertently trip in support of a Station Blackout is Class 3.
2.1.2 Scaling Considerations Per VYC-462, Revision 2, and VYC-1599 (Reference 6.15 and 6.10, respectively), the range of these switches is (-)I00°F to (+)600°F. Therefore, Calibrated Span (CS) is:
CS =600-(-)100
= 700*F Individual error determinants will be calculated to two (2) decimal points, the degree of resolution used for Analyzed Drift (DA) output in VYC-1599.
Output values (calibration tolerances, Allowable Value, calculated setpoint) will be resolved to the most conservative whole degree F.
2.1.3 Single Side of Interest In order to avoid impacting both the analysis value (module uncertainty e+) and plant operating margin (e'), and since the loop approaches setpoint only in one direction (i.e., there is no low temperature setpoint), a single side of interest factor will be utilized as per Reference 6.1, Appendix F. For a 95% proportion the following "J/K" factor (t) will be used:
()
=*J/K
= 1.65/1.96
= 0.85 (Rounded Value)
Note that (/) is applicable only to random terms.
Page 8 of 31
DPW(*TT Qi#nm T iný A r~ck
-lN;
'~
nrhr 1k Qtn
- .t ATVt"_AIA" ID-,
A
=o I
AL~.*,.AXl..
Jt.. WAA.l~l~il tJflfilt., J*l,*.W,.l J. fl...*lARl *t~flhfl lJ~it~~lt~.fllll ILr..rLl,,tJ~fLil
'V A
'-.C"lS,,ll.t.,J. fL*.t.,.Y 2.1.4 Calibration Effect Considerations Per the Design Guide, CE is typically taken as the sum of the vendor's Rated Accuracy (RA) and the As-Left Calibration Tolerance (CT). Based on the number of samples used to determine DA (count = 199 as per VYC-1599, Table 4), a test will be applied to determine if credit can be taken for RA being encompassed by DA. Test methodology is described in detail in Reference 6.13. In essence:
If DA < [RA2 + CT2 + vendor's rated drift' + MTE2]1/2, then CE = CT If DA Ž [RA2 + CT2 + vendor's rated drift + MTE2]'12, then CE = CT + A where:
= Present Calibration Tolerance DA
= Analyzed Drift from VYC-1599 RA Vendor's Rated Accuracy MTE'
= the Measuring & Test Equipment used in calibration and where the vendor's rated drift is valued at 0 because the vendor has no published drift specifications.
2.1.5 Sign Convention The sign convention used in the Design Guide is based on the effect of uncertainties on an instrument (or loop's) output signal. For this type of device, where there is no analog process input/signal output relationship the effect of uncertainties are manifested as a shift in the setpoint away from the ideal value. This results in a sign convention which is the reverse of that which is generically defined in the Design Guide.
2.1.6 Class 3 Assessment This analysis will determine the 95%/95% (single-sided/Section 2.1.3) uncertainty applicable to a Class I setpoint. Appendix R/Station Blackout considerations do not require the same level of rigor and can be evaluated as a Class 3 setpoint (95%f75%, single sided). In accordance with the Design Guide, the Class 1 uncertainty value can be converted to a Class 3 uncertainty (e,). From the design guide (reference 6.1, Appendix F, Table 1), a multiplier is determined as follows:
0.68/1.96 = 0.35 Appendix R/Station Blackout support is an NNS function. Therefore, accident parameters do not apply.
Page 9 of 31
D I'Tl Qfý*r T ;mr-Ar,-n Nigh TFomrs*nairo Q.*r ^;nf AVitr-Af.1"*
airw A DOTC' ~
I np A ~
Hmah T~mipr,~hr~ ~~trr~nt
- '.t~L~..' tJ L'.,(AJIA A.J.Aa. £ fl~flAO
- A1~.1t * ~
4J~.~flflI.
V A ~
~
- v.
is 2.2 Assumptions 2.2.1 The error term "Temperature Effect" (TE) is not applicable because temperature is the measured parameter of the device.
2.2.2 The effect on setpoint of harsh environmental conditions caused by LOCA/HELB are negligible (Attachment G&P). These include:
Setpoint Shift Radiation Effect (RE)
Contact Resistance Insulation Resistance (IRE)
Humidity Effect (HE)
(Reference 6.7.1, Section X-2.3) 2.2.3 For Custom Technical Specification (CTS) applications, the CTS value is typically assumed based on normal operating conditions. However, in this case during the event for which these switches are credited (HELB) a pressurization may occur (see Section 2.2.6). Consequently, for CTS as well as ITS, this pressurization effect will be accounted for.
2.2.4 Per Reference 6.1, for Improved Technical Specification (ITS) applications, the ITS value is assumed based on the most limiting of HELB with TE and HE or Seismic Effect (SE).
2.2.5 Deleted 2.2.6 Per Reference 6.7.1, there is a pressure effect of +3'F per 100 psi. Per Reference 6.7.2, the maximum protected area pressure rise is +5.1 psi (RX Bldg. Bounding pressure is +2 psig). Where HELB pressure effect (OP,,,,) is:
PtE.B
=
(30F/100 psi) x 5.1 psi
+0.20*F (Conservatively Rounded) and is manifested as a (+) bias in the nonconservative (relative to safety function) direction.
2.2.7 Per Reference 6.1, the following normal condition uncertainty terms are encompassed in the DA value:
Measuring & Test Equipment Accuracy (MTE)
Drift (as a function of time) (DR)
Temperature Effect (AT 20°F) (TE)
Pressure Effect (PB)
Humidity Effect (HE)
Radiation Effect (RE)
Vibration Effect (non-seismic)
Based on recalibration, the above terms are taken as noncumulative.
2.2.8 For this type of device, the following normal condition uncertainty terms are not applicable:
Static pressure effects on span and zero Power supply effect Page 10 of 31
RCIC Swain Line Areas Hhzh TemDerature Setnoint VVr-AA')r A
2.2.9 Per Reference 6. 1, no uncertainty is credited against the relays controlled by these devices.
2.2.10 Based on the design location of these devices (see FSAR Sections 7.3.4.8.7 and 7.3.5) the nonconservative affects of Process Measurement (PM) are negligible.
2.2.11 Per CTS, the specified calibration interval is "each refueling outage." Per Reference 6.9, this interval is typically bounded by 18 months and is taken as limiting (by the refuieling event, not calendar days).
To allow for a refueling cycle extended to beyond a nominal 18 months, this calculation will base extrapolated DA on a maximum interval of 684 days (using the criteria of once per operating cycle +25% as a convenience). If the calibration interval extends, for whatewver reason, beyond 684 calendar days, an evaluation to determine the interval increase effect on setpoint is REQUIRED.
2.2.12 Per VYC-1599, Section 5.4, the analyzed drift data for these devices (pooled Procedures OP 4322 and OP 4366) indicated little time dependency. Consequently, it is assumed the RSS extrapolation of calibration interval is appropriate.
Page 11 of 31
RCIC Steam Line Areas Hi ph Temperature Setnoint
~V'A)'O.
3.0 INPUT DATA Data used to calculate loop uncertainties, setpoints and decision points are tabulated below with the applicable reference or basis.
3.1 Process and Loop Data F
TABLE 3 Process/Loop Inputs Reference Description Data (*F) 6.18 Analytical Limit 196 (outside steam tunnel) 6.22 200 (inside steam tunnel) 6.4, Table 3.2.2 Custom Technical Specification Limit
<212 6.6 Existing Calibration Procedure Setpoint 185 d5 6.4, Table 4.2.2 Calibration Interval Once/Refueling Cycle 6.4, Table 4.2.2 Functional Test Interval Once/Month 6.20 Station Blackout Reliability
> 174 (inside steam tunnel) 3.2 Environmental Conditions TABLE 4 Environmental Input Data Reference
" Description Data (*F) 6.7.1, 6.7.2 Normal Temperature 140 (MAX)
(Steam Tunnel is Limiting)
TS-13-79A to 82A - Steam Tunnel TS-13-79B to 82B - RB TS-13-79C to 82C - RB TS-13-79D to 82D - RB 6.7.1, 6.7.2 HELB Temperature 300 (Steam Tunnel is Limiting)
TS-13-79A to 82A - Steam Tunnel TS-13-79B to 82D - RB TS-13-79C to 82C-RB TS-13-79D to 82D - RB 6.7.1 Radiation Exposure 40 year normal exposure 3.5 x 106R (steam tunnel is limiting)
I 2 year normal exposure 1.75 x 105R Page 12 of 31
RCIC Stearn Line Areas Hip-h Temerature Setnoint UVr-AK')r
ý%Y A
....Se Lie.A.a H ihTe ert e Set
- n...
....?~
i.....
3.3 Switch Data TABLE 5 Temperature Switch Input Data Reference Description Data 6.10, 6.14 Range
-100'F to +600'F Section 2.1.2 Calibration Span 700°F 6.8 Output Signal Contacts close on temperature rise 6.8, Section 4.1.3.1 Accuracy
+/-50F 6.7.1 Pressure Effect
+30F/100 PSI 6.10 Analyzed Drift 7.54°F/544 days 4.0 CALCULATION DETAILS 4.1 Normal Condition Uncertainties 4.1.1 Process Measurement Effects (PM)
From Assumption 2.2.10, PM (thermal stratification) is taken as negligible.
PM-0 4.1.2 Primary Element Accuracy (PEA) f f
I I
There is no primary element associated with these channels.
PEA = N/A 4.1.3 Calibration Effect (CE)'
Per Reference 6.1, CE typically takes the form:
CE = Net calibration effect A
= Device rated accuracy CT = Calibration procedure tolerance Page 13 of 31
RCIC Steam Line Areas Hihh Temperature Setpoint VYC-462C, Rev. 0 4.1.3.1 Rated Accuracy (A)
From Reference 6.7.1 (Attachment P) the factory temperature setting tolerance for units that close on temperature rise is the greater of +/-5*F or +/-3% of setpoint (+60F for a postulated maximum setpoint of 2001F.) However, the calibration technique described in Reference 6.8 (Attachment D) infers an average repeat accuracy of +/-50 F.
For the purpose of this calculation:
A = +/-5.000 F 4.1.3.2 Calibration Tolerance (CT)
Per Reference 6.1, the basis for CT is the rated accuracy of the device, or +/-5°F. This is also the calibration tolerance presently in use in Reference 6.6 (Attachment E).
CT = +/-5.00°F 4.1.3.3 Expected Performance vs. Actual Performance As discussed in Section 2.1.4 and where there is no vendor-rated drift:
S If DA< +/-[A2 +CT 2 +MTE 2]J2 (Eq. 1) then CE = CT S
If DA > +/-[A2 +CT 2 + MTE2]'a (Eq. 2) then CE = CT + A Initially:
A =+/-5.00°F (Section 4.1.3.1)
CT = +/-5-F (Table 3)
MTE = MTEAcIrJA, (Section 4.1.4.2)
= +4.120F DA = +/-7.54°F (Section 4.1.5)
Thus:
+/-[A2 + CT2 + MTE2]"2 = +/-1[5.00245
+2 + 4.122]" 'F
= +/-8.18'F Equation 1 is satisfied, consequently credit is taken for A being encompassed by DA.
Page 14 of 31
PrIC 4ZfAnrn I ;n#- Arpne Ni h T,-m rnihiri- %-t int VV("_A.<*TP Vow A
4.1.3.4 CE used in Uncertainty Determination Based on the results of Section 4.1.3.3:
= +/-5.00OF 4.1.4 Measuring & Test Equipment Accuracy (MTE)
From Reference 6.6 (Attachment E), calibration is accomplished with an Omega Digital Thermometer (or equivalent), a Type K Thermocouple and a test heater. A review of previous calibrations indicates the typical use of an Omnical 8A digital thermometer (MTE). From Reference 6.11 (Attachment F), total error for the Omnical 8A is expected to be:
L-MTE, = +/-1.005°F From Reference 6.17 (Attachment N), standard limits of error for a Type K T/C (nonspecial) in the application range of 0°F to (+)530°F is:
MTE = +/-40F 4.1.4.1 MTE Requirements Per Reference 6.1:
MTE uncertainty is encompassed by DA Total MTE uncertainty shall be < rated accuracy of the device under test.
Given the relationship:
MTE =
-[MTE, 2 + MTE 2 2]'/
where:
MTE = A (Limiting)
= +/-50F MTE, = +/-40F (Type K T/C, Limiting) then it can be seen by inspection that any MTE, with a total accuracy up to and including +/-3°F satisfies the 1:1 total MTE accuracy criteria.
4.1.4.2 Implemented MTE In support of Section 4.1.3.3 and from Section 4.1.4. 1, the following is assumed to be representative of MTE used for calibration:
MTE, =l1.005'F Page 15 of 31
RCIC Steam Line Areas High Temtnerature Setpoint VYC-462C. Rev. 0 MTE2 = +/-4.00'F Consequently, MTEAcrAL = +/-[1.0052 + 4.002] 1120F
=+/-4.13OF 4.1.5 Analyzed Drift (DA)
From VYC-1599 (Attachment H), switches calibrated per OP 4366 (the scope of this calculation) and OP 4322 (Main Steam HELB Detection) met the criteria for pooled data. The output of VYC-1599 (per Section 4.2)is a 95% probability/95% confidence level value, which meets the criteria of a Class I setpoint as per Reference 6.1. The following data applies to DA:
Average time interval is 544 days DA is +/- 7,54°F Data is evenly distributed about zero with a slope on the time dependency line equivalent to
<0.2 % per approximately 550 days showing, consequently, little time dependency.
The data is normally distributed with a highly peaked narrow distribution.
The average drift value for this group is -0.008% CS; since this value is less than 0. 1% CS, bias effects are considered negligible.
Per assumption 2.2.11, extrapolation of DA from a baseline of 544 days to a maximum of 684 days take the form:
= +/-DA:A (684/544)"a
= +/-7.540F(684/544)ln
=+/-8.540F 4.1.6 Temperature Effect (TE)
Typically, DA accounts for a 200F AT TE during calibration conditions. In this case, TE has the following considerations:
The measured process parameter is temperature, for which the device is designed.
Calibration technique is to preheat the switch (and associated calibration T/C) and use a prefabricated test heater assembly to minimize any external influences and approximate normal operating conditions prior to temperature ramp-up to setpoint. Consequently, normal TE as an error determinant is considered to be negligible.
TE = 0 Page 16 of 31
RCIC -Steam Line Areas High Temperature Setpoint VYC-462C, Rev. 0 4.1.7 Radiation Effect (RE)
Per Reference 6.1, normal radiation effect is encompassed by DA.
RE=0 4.1.8 Humidity Effect (HE)
No humidity effect is specified by the vendor. In addition, per Reference 6.1, normal humidity effect is encompassed by DA.
HE=0 4.2 Test Uncertainty (e.)
From Reference 6.1 for this type of device, and where there are no significant testing condition biases:
Initially, e, =-[CE2 + DA2]'1 Substituting:
e, = +/-[5.00°F 2 + 5.45-F 2]1 /2
= +/-9.820F Accounting for a single side of interest approach as per Section 2.1.3:
e= +/-[9.82°F x 0.85]
= +/-8.347OF To facilitate the calibration process, e, is conservatively rounded (with regard to setpoint development) to:
e, = 8.00*F 4.3 Normal Module Uncertainty (eW)
In this case, there are no additional terms to those accounted for in the un-rounded e,
- e. =et
= +/-8.3470F, conservatively rounded to:
- e. = +/-8.40'F Page 17 of 31
RCIC Steam Line Areas High Temperature Setpoint VYC-462C. Rev. 0 4.4 Accident Condition Uncertainties 4.4.1 LOCA Uncertainties (e, cj Per Reference 6.7.1, these switches do not mitigate a LOCA and, while they may experience a harsh environment, need not function during a LOCA. A LOCA coincident with a HELB is not considered to be a credible scenario. Consequently:
eLtICA = N/A 4.4.2 HELB Uncertainties Per Reference 6.7.1 Section X-2.3 (Attachment P) following both the LOCA/HELB simulation and Humidity/Cycling Test, the specimens (Test Item Nos. 2 and 5) remained within the test acceptance criteria of U6°F.
Indeed, the post-accident shifts were of minimum magnitude (+2.2'F and -0.2°F, respectively).
For conservatism, this calculation postulates that the pressure effect, discussed in Assumption 2.2.6, is only manifested during the accident condition and would have been unmeasurable during post-accident testing.
4.4.2.1 HELB Temperature Effect(T_._
Per Reference 6.7.1 (Attachment P), the switch trip setpoints remained bounded by the test acceptance criteria after LOCAiHELB simulation. In addition, temperature itself is the measured process parameter for switch actuation. Consequently, for the purpose of trip setpoint uncertainties:
TEB = N/A 4.4.2.2 HELB Humidity Effect aEm Per Reference 6.7.1 (Attachment P), the switch trip setpoints remained bounded by the test acceptance criteria after LOCA/HELB simulation and humidity/cycling.
Consequently:
I-E,,, = 0 4.4.2.3 Overpressure Effect (OPBuj)
Per Reference 6.7.1 (Attachment G), a HELB can result in an area pressure rise. The worst-case pressure increase is (+)5.1 psi, and results in a (+) bias shift in the setpoint, proportional to the extent of pressurization. From Assumption 2.2.6:
OPH,,a = +0.20-F 4.4.2.4.
HELB Module Uncertainties (ear.LB._)
Accounting for uncertainties which are negligible or not applicable:
e-HLB = [CE2 + DA2j"' + OP,,L, Page IS of 31
RCIC Steam Line Arews High TerrineratureSetnoint
.......St m.Line Area Te r.......e S -..
YC.-462C Rev 0 Substituting:
eHELB = +/- [5.00F 2 + 8.45 OF2I]l (0.85) + 0.20°F
= + 8.55 0F/-8.35OF 4.4.3 Seismic Module Uncertainty (eH__)
For HELB mitigation channels, ews is determined by HELB conditions of over-pressure coincident with, or subsequent to seismic effect. From Reference 6.7.1 (Attachment P),
post-seismic effect ranged from -3. 1OF to +4.2°F. For conservatism, the post-seismic simulation functional acceptance criteria of +/-5°F is taken as limiting.
Initially:
SE = +5.00°F Accounting for uncertainties introduced by a seismic event followed by switch actuation caused by a RCIC turbine steam line HELB:
e 5s
[4CE2 + DA 2 + SE 21J1 +- OP Substituting:
errs = +/- [5.00°F2 + 8.45°F2 + 5.OOOF 2]1t2 (0.85) + 0.20°F
= + 9.57°F/-9.37°F 4.4.4 Appendix R/Station Blackout Considerations From Section 2.1.6, a multiplier of 0.35 is applied to the normal module uncertainty to obtain a Class 3 normal uncertainty (e,). From Section 4.3, the normal module uncertainty (e) = +/-8.400F.
Applying the 0.35 multiplier:
e,
-8.40 0F
4.5 Setpoint Evaluations 4.5.1 Custom Technical Specification (CTS)
LSP- =TS-ITLUI However, because AL < TS, the AL becomes the more limiting condition. Therefore:
4.5.1.1 TS-13-79,80,81,82 (BCD)
LSP,,c, = AL - I TLUI Where:
Page 19 of 31
RCIC Steam Line Areas High Temperature Setpoint VYC-462C, Rev. 0 LSP, cD= The Limiting Setpoint TS
= CTS Table 3.2.2 Trip Setting
< 212'F (Not Used)
AL = 196"F (Table 3)
TLU = Total Loop Uncertainty which, in this cases reduces to:
= eIII (+errat is the worst case vector)
Substituting:
LSPBc = 196°F - 8.55°F
= 187.45*F, conservatively rounded to:
LSPcD = 1870F 4.5:1.2 TS-13-79,80,81,82 (A)
LSPA=AL-ITLUI Where:
LSPIA= The Limiting Setpoint TS
= CTS Table 3.2.2 Trip Setting
<212'F (Not Used)
AL = 200*F (Table 3)
TLU = Total Loop Uncertainty which, in this cases reduces to:
= e.,
(+e,,,
is the worst case vector)
Substituting:
LSPIA = 2000 - 8.55°F
= 191.450F, conservatively rounded to:
LSPA = 1910F 4.5.2 Improved Technical Specification (ITS)
LSP2 = AL -I TLUI 4.5.2.1 TS-13-79,80,81,82 (B,C,D)
Where:
LSP 8cn = The Limiting Setpoint Page 20 of 31
RCIC Steam Line Areas High Temnerature Setnoint AL The Analytical Limit TLU = Total Loop Uncertainty which, in this case reduces to:
= e,, (+e.
is the worst-case vector)
Substituting:
LSP20CD
= 196 0F - 9.57°F
= 186.437F, conservatively rounded to:
LSP 211
= 186 0F 4.5.2.2 TS-13-79,80,81,82 (A)
Where:
LSP2A = The Limiting Setpoint AL
= The Analytical Limit TLU Total Loop Uncertainty which, in this case reduces to:
em (+es is the worst-case vector)
Substituting:
LSP*
= 200°F - 9.57°F
= 190.43"F, conservatively rounded to:
LSP2A = 190°F 4.5.3 Appendix R/Station Blackout Considerations The maximum heatup of the Main Steam Tunnel during this scenario is 174°F. The uncertainty associated with this evaluation (e,) is 5*F. For this scenario, the LSP3 is:
LSP3 = 174°F + 5F = 179°F LSP 3 = 179°F Page 21 of 31
RCIC Steam Line Areas High Temperature Setnoint VYC-4,62C, Rev. 0 4.6 Margin Evaluation 4.6.1 Custom Technical Specification 4.6.1.1 Nominal Margin (M,) to Existing Calibration Setpoint (SP)
M, = LSP-SP TS-13-79,80,81,82 (B,C,D)
Substituting:
M,1 cD = 187TF-185TF
= +20F TS-13-79,80,81,82 (A)
Substituting:
MIA = 191°F - 185TF
= +60F 4.6.1.2 HELB Safety Margin M, to Existing Analytical Limit (AL)
Per Reference 6.18 (Attachment B), the existing AL inside the steam tunnel ("A" switches) is 2000F and outside ("B, C & D" switches) is 196°F and includes a 60F allowance for instrument error. The existing setpoint from Reference 6.6 is 185°F.
The "normal condition" uncertainty applicable to CTIS M2 to existing AL still must consider the HELB OP effect, therefore en, (positive vector) is used. Thus:
M2 =AL-[SP + I 1I TS-13-79,80.81,82 (B.C.D)
Substituting:
M,9cD = 196°F - [185°F +8.55°F]
= +2.450F TS-13-79,80,81,82 (A)
Substituting:
M,, = 200°F - [185°F +8.55 0F]
= +6.45OF Page 22 of 31
RCIC-Steam Line Areas High Temperature Setpoint VYC-462C, Rev. 0 4.6.1.3 HELB/Seismic Safety Margin (M,) to Existing AL From Section 4.4.3 em (positive vector) is 12.80°F.
TS-13-79,80,81.82 (BC.D)
Consequently:
M3 cD = 196'F - [185°F + 9.570Fj
= +1.43°F TS-13-79,80,81,82 (A)
Consequently:
M3, = 200*F - [185'F + 9.57*F]
=+5.43OF 4.6.2 Improved Technical Specifications (ITS)
From References 6.18 (Attachment B) and 6.22, the current A.L is 196°F for outside the steam tunnel and 200'F inside the steam tunnel. For ITS:
By inspection, it can be seen that the limiting nominal margin from LSP2CD (I 860F) to existing SP (185 0F) is +I0F.
By inspection, it can be seen that the limiting nominal margin from LSP2A (1 90'F) to existing SP (185°F) is +5°F.
Per Reference 6.16 (Attachment M), the original plant design was for an SP which was 2000F. From a review of plant area temperature trends (Attachment G), maximum base temperature is assumed to be 140°F. Since LSPs accounts for the combined effects of HELB (as applicable) and seismic effect, no additional safety margin relative to LSPrr is required.
4.6.2.1 Improved Technical Specification Overating Margin (K)
For an eN of (-)8.4*F (non-worst case vector), and a maximum base temperature of 140°F (Tm*J, operating margin is expected to be:
M4 =[LSP-IeNII-T,.x TS-1 3-79,80,81.82 (B.C,D)
Substituting:
M4111 = [1860F -
8.40F]- 140 0F
= +37.6 0F Page 23 of 31
RcrC Steam Line Areas High Temperature Setpoint VYC-462C. Rev. 0 TS-13-79,80,81,82 (A)
Substituting:
M,,=[190°F-I-8.4°FI]- 140-F
= +41.6 0F 4.7 Allowable Value (ITS) 4.7.1 Loop Acceptance Value (ACV)
For a single component loop, the determination of ACV (the algebraic sum of each component's as-found tolerances) is not applicable.
4.7.2 Allowable Value (AV)
From Reference 6.1:
4.7.2.1 TS-13-79,80,81,82 (B,C.D)
AV = LSPmcD + e, Substituting:
AV,,, = 186°F + 8.00-F
= 1940F 4.7.2.2 TS-13-79,80,81,82 (A)
AV = LSP2A + e, Substituting:
AVA = 190F + 8,00F
= 198*F Page 24 of 31
RCIC Steam Line Areas Hiah Temperature Setpoint VYC-462C-Rev. 0 4.8 Calibration Tolerances 4.8.1 As-Left Calibration Tolerance (CT)
As developed in Section 4.1.3.2:
CT = -5.OOF 4.8.2 As-Found Calibration Tolerance (AFT)
From Reference 6. 1:
AFT =e As developed in section 4.2:
e,= +/-8.00*F Consequently:
AFT=+ 8.000 F Page 25 of 31
RCIC qteam Line Areas F 4iLyh Terrinerature.Setnoint VVC-462f-Rev -1) 5.0 RESULTS/CONCLUSIONS 5.1 Total Loop Uncertainty Total Loop Uncertainty (TLU) has been evaluated for the RCIC turbine steam line HELB detection switches within the context of both Custom and Improved Technical Specifications and the results are presented below:
TABLE 6 Total Loop Uncertainty Results Cal. Interval CTS-HELB ITS-HELB/SEISMIC Refueling Cycle
+8.?55°F/-8.35-F
+9.57°F/-9.37°F 5.2 Setpoint Evaluation For protected areas inside and outside the steam tunnel, results are presented below for the limiting setpoint (LSP), Allowable Value (AV), relevant Margins (Mj and baseline data.
TABLE 7 Setpoint Results Description Results (OF)
CTS ITS Analytical Limit (ALA) 200 200 Analytical Limit (ALscD) 196 196 Allowable Value (AVA)
N/A 198 Allowable Value (AVm)
N/A 194 Technical Specification Limit (TS) 212 1982 (inside) 1-_
1942 (outside)
Existing Setpoint' (SP) 185 N/A Limiting Setpoint (LSPA.)
191 190 Limiting Setpoint (LSP 1c*,McD) 187 186 Recommended Setpoint (SPA) 185 185 Recommended Setpoint (SPm) 185 185 Appendix R/Station Blackout Maximum Temperature 174 174 Appendix R/Station Blackout Setpoint LSP, 179 179
("A" switches only)
Margin LSP to SP (MA)
+6 N/A Margin LSP to SP (MMc)
+2 N/A Safety Margin to Existing AL(MZA) 3
+6.45 N/A Safety Margin to Existing AL(M2,c) 3
+2.45 N/A HELD/SEISMIC Safety Margin to Existing AL(MIA) 4
+5.43 N/A HELB/SEISMIC Safety Margin to Existing AL(MlcD)'
+2 ITS Operating Margin (MA)5 ITS Operating Margin (M4ECD)5 N/A N/A
+4 1.6
+37.6 Page 26 of 31
RCIC Steam Line Areas High Temperature Setpoint VYC-462C. Rev. 0 1.I Per OP 4366 Revision 12 For ITS the AV is the TS Limit From (SP + elm,) to AL From (SP + e w
c) to AL From (SP, - e*j to maximum normal temperature 5.2.1 TS-13-79,80,81.82 (BCD) - Outside Steam Tunnel From the above table it can be seen that to support ITS and the current AL of 196"F the existing setpoint of 185°F is acceptable for both CTS and ITS considerations.
5.2.2 TS-13-79,80,81,82 (A) - Switches Inside the Steam Tunnel The existing 185"F setpoint is acceptable for both the EQ Program limit of 200'F, the Technical Specification limit of 212"F, and the Appendix R/Station Blackout temperature limit of 174°F.
5.3 Graphic Representation of Setpoint Data FIGURE 1 Graphic Representation of Setpoint (CTS)
Technical Specification 212°F Analytical Limit (inside steam tunnel) 200°F Analytical Limit (outside steam tunnel) 196 0F LSPI-191OF LSP,,c, 1870F SP2 & SPA (Setpoint is retained) 185"F LSP3 1790F SBO Main Steam Tunnel Heatup 174"F Normal (MAX) - steam tunnel 140*F
- 1.
Calculated for normal conditions (to include OPma)
- 2.
Existing setpoint per OP 4366, Revision 12
- 3.
Not to scale, provides relative position only Page 27 of 31
RCTC Ste am Line Areas Highlemperature Se1p2int
'VYC-462C Rev. 0 Sea Lei Tem ratI C
FIGURE 2 Graphic Representation of Setpoint (ITS)
Analytical Limit (inside steam tunnel) 200°F Analytical Limit (outside steam tunnel)
A960F Allowable Value' (AVA) 198°F Allowable Value' (AVBCD) 1940F LSP2A 190OF LSP2BCD 1860F SP 2 & SPA (Setpoint is retained) 1850F LSP3 179 0F SBO Main Steam Tunnel Heatup 174 0F Normal (MAX) - steam tunnel 140°F
- 1.
For ITS, the Allowable Value is the ITS value.
- 2.
Not to scale; provides relative position only.
5.4 Calibration Criteria In order to support and implement the results of this calculation, the temperature switches are to be calibrated according to the following table:
TABLE 8 Calibration Attributes.....
Description Value Units Setpoint (CTS)
Inside steam tunnel 185 OF Outside steam tunnel 185 OF Setpoint (ITS)
Inside steam tunnel 185
'F Outside steam tunnel 185 OF As-Left Tolerance
+/-5 OF As-Found Tolerance
+/-8 OF 5.5 Measuring & Test Equipment Requirements Testing is accomplished with the following equipment:
Monitoring thermocouple (Type K) (Installed)
T/C Reader (Digital Thermometer)
Heat source (Test Heater)
Digital Multimeter Variac Page 28 of 31
RCIC Steam Linie Areas High Temperature Setpoint VYC-462C, Rev. 0 For calculation purposes, only the TIC and Reader have relevant associated uncertainties, developed in detail in Section 4.1.4. Since the T/C is an installed sensor calculation recommended MTE reduces to the T/C Reader.
TABLE 9 Recommended M&TE Description Required Accuracy Actual Accuracy Reference Omega Omnical 4A & 8A
+/-30F
+1.005°F 6.11 Omega CL-505A
+/-30F
+/-1.0050F 6.11 5.6 Recommendations 5.6.1 Subsequent to this calculation's approval, revise FSAR Table 7.3.2 as per Attachment K.
5.6.2 In order to support Analytical Limits of 200IF and 1961F, revise OP 4366 in accordance with Table 8 and Table 9.
5.6.3 Ensure that a calibration tracking system ex;sts to evaluate consequences of a calibration interval greater than 684 days. [Note: There are no plans to extend the calibration interval beyond 684-days].
5.6.4 Revise the minor FSAR Figure 7.3-5b discrepancy regarding HPCI/RCIC temperature switch sets. The following discussion relates to RCIC; HPCI is comparable. There are four sets of four sensors, each set providing HELB detection protection to specific plant areas (one set covers the steam tunnel and three sets cover various zones of the Reactor Building.) This is shown in block diagram form in FSAR Figure 7.3-5b. The block diagram section regarding the Reactor Building sensor sets refers parenthetically to "typical of four located outside steam tunnel." This should be "typical of three..."
5.6.5 Add VYC-462C to the List of References in OP-4366.
5.6.6 Evaluate the acceptability of an analysis limit that is less than the Technical Specification Limit for an increasing trip setpoint.
5.6.7 Revise Section 7.5.3 of theEQ manual, various places, which, indicates 2000F as the isolation trip setting. This should be the nominal setpoint of 196°F as implemented by the HELB analysis. The 200*F applies to the steam tunnel only.
5.6.8 Close PORC follow item PF19604 101 (Attachment R).
5.7 VYDEP-15 Criteria VYDEP-15 requires the impact to plant programs, procedures and licensing and design documents are considered. This calculation has been reviewed for impact considerations. To fully satisfy VYDEP-15 requirements, this calculation undergoes a review of all departments and programs that could be impacted by the results and conclusions.
Page 29 of 31
RCIC Steam Line Areas Hicb Temperature Setnoirit Vvr..419)r R.-u n The following has been considered and is either addressed in this analysis or via the interdepartmental review process:
FSAR changes Technical Specifications (custom and improved Technical Specifications)
Procedures Technical programs Prints Related Design Basis Calculations (input/output)
Design Basis Documents Based on the above, all impact considerations of VYDEP-15 are addressed.
5.8 Evaluation of Existing Setpoint The temperature switches located inside and outside the steam tunnel are acceptable for the full surveillance interval with a setpoint of 185*F.
6.0 REFERENCES
6.1 "Instrument Uncertainty and Setpoint Design Guide," Vermont Yankee, Revision 0.
6.2 WE-103, "Engineering Calculations and Analyses," Revision 17.
6.3 -
Vermont Yankee Final Safety Analysis Report. Section 7.3.4.
6.4 Vermont Yankee Technical Specifications, through Amendment 150.
6.5 Vermont Yankee Project Procedure VYDEP-15, "Calculations," Revision 2.
6.6 OP 4366, "RCIC Steam and Space High Temperature Functional/Calibration Test," Revision 12.
6.7 Vermont Yankee Environmental Qualification Program Manual, Revision 36.
6.7.1 QDR 9.4, Revision 10.
6.7.2 EQDI95-55, "Draft EQ Manual Revision."
6.8 VYEM 0029, "Instructions for Patel Temperature Switches," Revision 0.,
6.9 "Selected Definitions and Clarifications Associated with the Vermont Yankee Technical Specification."
6.10 VYC-1599, "Drift Calculation for Fenwal Temp SW Models 01-I170020-090 and 0 1-170230-090," Revision 1.
6.11 VYC-1758, "Measuring and.Test Equipment Uncertainties Calculation," Revision 0.
6.12 Memo, Hengerle to File, "Improved Setpoint Program/CTS vs ITS Setpoint Evaluation," VYI 37/97, dated April 25, 1997.
Page 30 of 31
R(I T.
ti-nm T nin-Arpa Hiaoh Tt-m ernthiri- %-tr~int VVr-Af%')I-ID,-xr A RCTC S~t~n, I ~np Ar~i~ I-Fob Tpmni~r~iIizr~ ~~,e'trinirit vvr~t~r p~
6.13 Memo, Hengerle to Distribution, "Application of CT, CE and A for Single Point Devices," VYI 92/97, Revision 1, dated June 26, 1998.
6.14 MPAC.
6.15.
VYC-462, "Fenwall (sic) Temperature Switch Loop Accuracy Review," Revision 2.
6.16 "Instrument Data Sheets," GE Drawing 225A5600, Sheet 98, Revision 0.
6.17 "Nuclear Power Reactor Instrumentation Systems Handbook," Volume 1, Joseph Harrer and James Beckerly.
6.18 NED Analysis Matrix, dated January 21, 1998.
6.19 Plant Drawings:
6.19.1 Flow Diagram, RCIC System, G-191174, Sh 1, Revision 33.
6.19.2 CWD-1179, "RCIC Logic System," Revision 15.
6.19.3 CWD-1 180, "RCIC Logic System," Revision 16.
6.19.4 CWD-748, "Steam Leak Detection System," Revision 5.
6.20 VYC-1347 Revision 0, "Main Steam Tunnel Heatup Calculation" 6.21 Safety Class Worksheet [for RCIC temperature switches dated 10-20-98]
6.22 Memo VYE 98/214, G.J. Hengerle/E. Goodwin to R.T. Vibert, "Assessment of VYC-462A,C & D Temperature Limits", October 5, 1998.
7.0 ATTACHMENTS Attachment A, Loop Block Diagram Attachment B, NED Analysis Matrix Excerpt Attachment C, MPAC Data Excerpt Attachment D, Vendor Data, VYEM 0029 Excerpt Attachment E, Calibration Data, OP 4358 Excerpt Attachment F, MTE Accuracies, VYC-1758 Excerpt Attachment G, EQ Manual and QDR Excerpt Attachment H, Analyzed Drift Data, VYC-1599 Excerpt Attachment I, CTS Data Attachment J, FSAR Data Attachment K, FSAR Table 7.3.2 Proposed Markup Attachment L, VY Project Memorandum VYI 37/97 and VYI 92/97 Attachment M, GE Instrument Data Sheets Attachment N, Type K T/C Accuracies, Reference 7 Excerpt, WE-103 Review Sheets and Associated Interdisciplinary Reviews.
Attachment P, Additional QDR Data Attachment Q, Telecon Record with VYE&C Attachment R, Procedure Review PORC Memorandum, May 20, 1996 Attachment S, Memo VYE 98/214 and Safety Class Worksheet dated 9-29-98 Page 31 of 31
VYC - 462C Attachment A Page 1 of 1 BLOCK DIAGRAM RCIC HELB TS XXXY To Relays in CRP 9 - 30 and 9 - 33 TS
-13
-79A
-80A
-81A
-82A 79B 80B 81B 82B 79C 80C 81C 82C 79D 80D 81D 82D
?tcdAmty2kmmIft-Cm&md IlSiM
-AO VAU*S SI u
M-toCfO
____11R TA~2220-Th~24to
~
momw~nWptnIS~
55h A)U W1
.1jr~pw M
W____
.. J!L......
ri___
____m
____l DA
ý IumAS
-a tThsW
. t" wcvac
-M hh1 icI
_________RAX
[UAW______________
-"L M
U"lS A.4C
-m ns."L INSTZ.M
____________________III__
MOM____
~~~
H1OSLMAL~~t4A&iwI ia-A biaw 11.~.ti4§tA4 cc~V*W Imosm MU A_
-AY nu
_lS I
-=fff"TwMYA~WS MITlUOV U*
i~~~
MAW tic N!DUI Pgu1111 P4 1lotll
YAWM~ATOmieammRIco~RN
%"NO 4Lc.
_0~tl E r p p i 15:53:34 Mar 10 1997 EQUIPMENT INQUIRY PAGE I OF 11 EQUIPMENT NO TS-13-79A
- 1. KEYWORD SWITCH
- 2.
QUALIFIER......
TEMPERATURE
- 3.
DESCRIPTION RCIC STEAM LEAK DETECTION; FLOW DIAG: G-191174 SH 1i MFG: FENWAL; MODEL: 01-170230-09; SERIAL NO.:
YA-58s CWD: 1180
- 4.
LOCATION........
REACTOR 2871 W 5.
6.
7.8.
9.
10.
11.
12.
13.
14.
15.
SYSTEM ID......
PARENT XD NO EQUIPMENT TYPE.
INSPECTION TYPE.
PRIORITY........
PM NOTICE (Y/N).
MANUFACTURER...
SERIAL NO......
MODEL NO........
DRAWING NO LAST REVISION..
RCIC TEMIP SWITCH 1
N YA-58 01-170230-09 G-191174 SH 1, L-2
- 16.
DESIGN PRESS.....
- 17.
DESIGN TEMP.......
- 18.
SIZE........
- 19.
ERPIS.............
- 20.
-21..
CWD................
1180
- 22.
SURV PROCEDURE OP4366
- 23.
MNT PROCEDURE
- 24.
VYEI 0029 WHICH ONE ? AE=EXIT, P#-PAGE)
It
)1
YANXEEA7MWe&,MC rOW4NV vo r¸ L5:53:55 Mar 10 1997 EQUIPMENT NOTES INQUIRY PAGE 6 OF 11 4 LINES SCREEN 1 OF 1 EQUIPMENT NO TS-13-79A SWITCH,TEMPERATURE CABLE #118OB NAME PLATE DATA:
RANGE:
-100 DEG F TO +600 DEG F CONTACTS CLOSE ON HIGH TEMP RAT2NG: 5K -
115 VAC.5A -
115 VDC T1RSWITCH WHICH ONE ?
(E=EXIT, P#=PAGE, S#=SCROLL) a
.2
- 3
YANK ATOecAW mc CALcoNo "I'(L OC ATTXHD--AGýO%ý 15:54:26 Mar 10 1997 EQUIPMENT NO DESCRIPTION EQUIPMENT ENGINEERING DATA INQUIRY TS-13-79A 000 SWITCH, TEMPERATURE, MASTER EQUIPMENT PAGE 10 OF 11 1.
SAFETY CLASS SCE
%VERIFIED BY SAFETY CLASS BASIS: QDR-9.4 APPLICABLE PROGRAMS 4.
5.6.
7.
8.
9.
EQ PROGRAM......
Y APPENDIX J......
N 1S.............
N IST............
N FIRE PROGRAM.
NOV PROGRAM
- 10.
SEISMI
.C
- 11. SQU.G
- 12. APP..R SAFE S/D....
- 13.
REG.
GUIDE 1.97.....
- 14.
MECHANICAL RAD QUAL.
4H*CH ONE ?
(E=EXIT, P#'-PAGE, N=NEXT, H=SCREEN HELP, H#=ITEM HELP) 3
YANI ATOaMIC e jCTR jOMPA CALCUIAA7ONNO Vyt -4Cz.
ATTAHMEN I)PAGk.f OF EQUIPMENT MANUAL COVER SHEET EQUIPMENT MANUAL TITLE:
Instructions for Patel Temperature Switches MObEL:
01-170020-090 & 01-170230-090 VYEM No.:
0029 Vendor: 'Patel Engineers Vendor. Manual No.:
N/A Rev.:
N/A Date:
N/A System Title (s):
Nuclear Boiler (2),
Reactor Water Cleanup (12),
Reactor Core Isolation Cooling (13),
High Pressure Coolant Iniection (23)
Safety Classification of Manual:
Safety Related Tag No. (s): See Applicability List VYEM Cover Sheet:
VYEM Rev. No.:
0 VYEM Rev. Date: 05/26/89
YANKEEATOM1 QJCELCTIC CO ~PAY CALCMJArKNNO flYc.- &
ZVoL APPLICABILITY LIST INSTRUMENT NO.
MODEL NO.
COMPONENT DESCRIPTION TS-2-121 A,B,C,D 01-170020-090 TS-2-122 A,B,C,D 01-170020-090 TS-2-123 A,BC,D 01-170020-090 TS-2-124 A,BC,D 01-170020-090 TS-12-(101-103)A,B 01-170230-090 TS-12-(106-112)A,B 01-170230-090 TS-13-79 A,B,C,D 01-170230-090 TS-13-81 A,B,C,D 01-170230-090 TS-13-80 Ai,,C,D 01-170230-090 TS-13-82 A,BC,D 01-170230-090 TS-23-101 A,B,C,D 01-170230-090 TS-23-102 AB,C,D 01-170230-090 TS-23-103 A,B,C,D 01-170230-090 TS-23-104 A,B,C,D 01-170230-090.
Thermoswitch Temperature Controller Steam Leak Detection Thermoswitch Temperature Controller Steam Leak Detection Thermoswitch Temperature Controller Steam Leak Detection Thermoswitch Temperature Controller Steam Leak Detection Thermoswitch Temperature Controller Steam Leak Detection Thermoswitch Temperature Controller Steam Leak Detection Thermoswitch Temperature Controller Steam Leak Detection Thermoswitch Temperature Controller Steam Leak Detection Thermoswitch Temperature Controller Steam Leak Detection Thermoswitch Temperature Controller Steam Leak Detection Thermoswitch Temperature Controller Steam Leak Detection Thermoswitch Temperature Controller Steam Leak Detection Thermoswitch Temperature Controller Steam Leak Detection Thermoswitch Temperature Controller Steam Leak Detection V
YANKEE ATOMIC ELECTRIC COMPANY CALCULATION NO. IY',( -46Z"2-.
"?-Cv 0 ATTA*AHEfr_._.*AGE.L-OFB EQUIPMENT MANUAL VENDOR CONTACT SHEET WEM1 No.,
O__ ___
Manual Title CTwSFoR Prvaai- -rem PI-p14ig5 p
c't~
Vendor Address 3O1 Suite
)50Let~-
eo Street City State P.O. Box Zip coktact C-A,4El-4 ffi~
DDept.
Phone No.
rO.S 7*,=Z
-- ?s'O
- 1.
Is the vendor still in business? Ak,
- 'T1"L-
- 2.
Is the vendor, information/VYEN up to date for currently installed components?
- 3.
Are there supplemental data sheets, tech.
bulletins, etc.?
Will vendor send the required data?
- 4.
Indicate below data necessary to update manual.
(Y/N)A'
( YIN )
( Y/N )
YIN)i" j
ITEM MFG.
NO.
DATE COST Comments (Attach Additional' Sheets if eqi
.~)-
Cognizant Person:
Date:
PagelIof I
YANK.E ATOMIC ECEIGR COMPANY CAL.ULAmON NO.L
(.-4" (,..
ATTACrr,..MEN.PAG o:-_8_
,a,
.1 --..-r
-," -1 C!:*
INSTRUCTIOmS FOR PATEL TEHPERA-TURE SWITCHES I
Testing and Adjustment The arrow on the head of the temperature switch unit indicates the direction to turn the adjusting screw to increase the temperature setting.
(Torque in excess of 15 inch pounds on adjusting screw will deform slot )
Each full turn of the adjusting screw - viii change the temperature the approximate number of degrees as follows:
(Important:
Before making temperature adjustments, release locking device (112 turn) othervise adjusting screw threads will be damaged.)
Adjustmeat Rates for Temperature Switches Tension Operated atalog Number Approx.
0 F per full turn of adi. screw
,i-170020-090 1
175 uio ompe 'n Oerate Catalog Number Compression Operated Approx. 0F per full turn of adi.screv
-l0--170230-090 101 After the temperature switch unit has been installed, final adjustment can be made by allowing the unit to operate for several cycles to permit the controlled system to stabilize and then adjust-to desired temperature.
After adjustment the system should be allowed to recycle several more times before checking the setting.
Where extremely accurate temperature control is
- desired, several readjustments may be necessary to stabilize the temperature switch after which the adjustment will be maintained.
Contact Protection Capacitors are not required under average conditions.
For smoother control at small, loads, on D.C. applications, or to prevent contact bounce due to vibration, the following chart is recommended as a guide:
Current Service Capacitance MID 120VAC Re sistance Hone required 120VAC or DC Relays.
KaRnetic contactors
.001 to.01 5-25VAC or DC Relays
.02 120VAC Motor Use relay W4TE.:
J.@
Capacitors should be wired in parallel with thermostat lead connections.
01
YANK(EE ATOMIC ELECTM~C COMRRAN MZLULATbO NO. VYC-40-c.
If ?,eating Temperature Set Point is Required All Temperature Switch units are ect at room temperature (75*F
+
15 0 F) unless otherwise specified.
Testing the temperature set point of Z Temperature Switch in an application or under conditions shere the heat source is remotely located from the Temperature Sic, or 0where ambient temperature conditions are significantly above or below 75 F.
may give misleading results.
I r
~'-
Ti
~
)
02
YANKEE ATOMIC EC*TJC COMPAN.y CALCULATONNO. VyC -4tzd*-
W o
0 0
9 or-f 7pt5~
7UT ffý.c-cY-4r ATTACHE NT 1 CALIBRATION AND VERIFICATION PROCEDURE FOR PATEL TEMPERATURE SWITCHES
- 1.
Insert the THERNOSWITCH (adjusting screw end down) into the standard (5/8")
hole in the heater block of the Fenwal Test Kit Model Number 80001-0.
- 2.
Connect the receptacle leads to the THERHOSWITCH unit leads.
- 3.
Install a calibrated thermocouple in the heater block access hole.
- 4.
Set control switch
- 2 on "Regular" for P/N 01-170020-090 and on "Inverse" for P/H 01-170230-090.
- 5.
Set -the control switch
- 3 on "LOW" for switches with set points 68 0F to 200 0 F and oan "HIGH" for set points greater than 200 0 F.
- 6.
Set control switch #1 on the "ON" position.
The line pilot light will light.
- 7.
When the temperature approaches the set point of the 7HERHOSWITCHt the system will begin to cycle-as denoted by the heater pilot light going "ON" and "OFF."
Allow the THERMOSWITCH o.stabilize at set point for 10 to 15 minutes; then take six. (6) successive readings at mke of.
contacts (heater light "OFF"
- for inverse unit, P/N 01-170230-090; heater light "ON" for regular units, P/N 01-170020-090).
Average of six (6) readings Indicates set point of the ItERKOSWITCHES.
- 8.
If any tr of the six (6) readings recorded in Step 7
than S F, the THEROSWITCH should be *returned recalibration, or replacement, during the standard warranty. period.
vary by more to.Patel for eighteen-month Pfc-%cAALG PlumWk V'ft.,-cetWCLG rom.
'rJALAS
'l0I 03
YANKEE ATOMIC ELECTRIC COMPANY CALCUL'nONNo VY'c-4 z...
Wc.V o
-. 0 WrfAfW lIN!Or)
MAJVSAPSt, ANDO PROPER P1Afo""IA'C 09AP WISEM(SMjClsONyS 1.10.N THERMOSWITCH TEMPERATURE CONTROLLERS INSTRUCTIONS GENERAL INFORMATION The shell of each T* 4 OSITCH uni contoins the catalog numbe.. the current rang.
tes tesmerature rmnge end dhe coantdct morogese like Nrdit-of thise catalg numb*r descibes whether cantocft ope nr close on emup.
emwte rSe. 9 contacts open on temperature rise. the fifth digit of the catalog number Ih e*van number each as 17000. 171M. etc. o contacts cose on oempraturse,ld.
she fiVS dg0 Is an odd number sudch. 17e 1.s 1 03. etc.
MI. Cospone*d recognized units will elher hove a ""as the anrs digit (702. ec.) or will bear the new UL logo Va eW utillse a 17000 *ades catalog number (17021. etcj.
The fourth digit of the catalog number wil quickly determine whether he unit is tension or compession op*erted.
Tension operated Indicates that the contocts Ore,.. ýered by "exerting, enslon on the ends of the sut mechnism.i f the fourth digit Is other than '2' -. -r (such as 17000.
1703Q. etc.) It Is ltenlon operoted. Tenmson operated units may be sublected Io momen.
ory temperatwe exposure of 100F above their set point within their empamture range, or subj(ected to any termperture below their set pain without damag.
Comressl operated indalias hat the contacts *to operated by varying the cam.
presive force on the ends oS the strut m
'chonsm. 9 the fourth digit Is "r or "I (such os 17021. 1071. etc. it Is onmpression operated. Compression units ore recommended V overshoots ore to'be encountese*d l ompresslon feature lows overshooting low tetserosure wats up to 50P and high tea turoe units up so 700'F for Intervals not cedrng one hour.
INSTALLATION nowa THE.MOSWITC units ore supplied In live bask heed conliguratlons -
Cartridge.
.ldck Heoad. lex Head. Coupling Heod and oCku* flo".
T avoId resricting shell expansion or conetac-Ion wen making Istalloatins In solid metal blods. o Wr diamete amed hale for W4" diamet units or e 1A6, diamete reomed hole, for 131MC da&Mete heaV" duty 40nite8 IS, reosme..nded. See specifi cant-1lA style list.
Ing Er aolaoInstallao 1,11-Instructians.
I -, I ms0A6moisture neiston Itig end low Aemperoe wats. A end C. Hale should have short epleto re lcelve the Wi 80a006g pkkt hils prevens the cartirdge unit from rotaing when the osling aleet is lumed. ft may ebe be uoed forufce entol N Ifserte intoe Fen aseurface mounting mlock.
- o.
m Ia IO.*
2 WNecOW-IsHeosmIntedineesimlormonner io th coridge be. a the umt is to be Inserted Into a reaned hoe. two short pine should be mounted an eithr se E the hole. The pins should rest against th sides of th block head to prevenl rotation ot the unit.
3 end4 Hex end Coupling Heod (includes hex.
head moisture resistant high and low tmera.oI ture units. 8 and 0)-- con be Installed like any Pipe, litting, Avoid oppk* ingudue torque to the ut Torue in ecess of 5.loot paund for the
=ton 7rd 7els (Wtr dm, shell) or mfoot pounds for the heavy dut unit (13/11C dinm.
sloll) will offset the present tempersu*re oS the control.
When Teflon tape ricont is used, torque in esces of 4oo paond for the standard site Intrle'er or 41oa pounds for the heavy duty Alwloffsett the prest tensperoture of the S Cka Mfleaelt Three holes in IoVn snow le4 easy motiog en any flat sudece.
- Mo*tr Keshletet Un*t MOUNTING STYLES CAUTIONI Do canned TImmmmOSiT cantrolle lead In seoris V4t the loed end power suppl.
Do be certain that ther Is eufildent Wa not
,excess roam Wr the Istalled TIEMAO.
SWITOI 0ni to eandIn diameterm endý 0O use stainless ste bhtiom welded therm.
swans. (seode mm00 11200 or various platings or coatings which may Incree controller lie where corosion or elecral-ysh Is sspect.
Co insulate head of th TH8RMOSMICI4 unit where large external temperature varlo Sian may Oaccr.
- Thi precaution Is not necessary on the functian bax pe. (Serie 1770, 1600)..
004 Immerse you unit in iqids'or vapors unless It was spedie for that *b.
0011T exceed the ratigos Indicoted on 11TAM-LOSwTCII unit shell.
00111 thermally sh"l unit ftwm medium OO-rNI.i~tf assti 50ev *or An ad.
WN 7AW
.W WIN l
Oref the 8%-
flea smay imnef1~ Ewag thfen ioiand may VON stndr Feasia waffentyl 04ihummpfoerl 00th 'r ourun,..Ioroun.d o+usim ecrw i flow bnlde. tg contacts.
0owo llow moisture.,d in head Aity area oe 37.OC00 MAaskt* Reslstant Uns. Where emessive moilure Is a
- problem, specify Special
- Featre, 0IoS20..ox when ordern.
00"I1 try to repair unit yourself.
0ON0t handle unit'with pliers or force It Into poition either by hand or Waofs, or apply excessiv torquve In sighiening theaded units.
001fF sbjecd shell of unit to deformallon.
NOTE Coertan gases or liquids kwAcldIng water of el#vated temperature could be cotroslve end may also cause electrofrtlk action. which.
could severely shorten the 1i1e of the con-eorl.
iTh afte ofiOMrrSlA0 or eiecto&Wss IS ks/lk#
- eaed by a gat t'
? 80144em parameters such ss chemwa makeup Wnd lensratwife of the $obd/o% stray electrc C01ats' etOM Consuif She suppluer or you chemicals or the facto05 for suggestions.
fl A
YAN EEATO C
MTRI CTMPA CALCULATION NO.
YL-46.
7W 0 ATrA09UJEKWflPAWBOF e TESTING AND ADJUSTMENT ta On"Ow on the haod of TIHElJOSWNITCH unit nbd-.cot s direction to turn adilscino srew to Increase tlemPefotur. setting.
Torque.in excess o 1IS inch pounds on Odjustlng strew wýll defotrm slot.
Eoch full turn of adjustng $sClow will thonge the temperoture the opperosmot. number of degrees os Ioilows:
ADJUSTMENT RATES for THEAMOSWITCHI UNITS Tension Operated Compression Operated Catalog Appoe.
F* per lull turn Catalog Approx. F" per full lurn Series Number of adJ. screw Series Number of adi. screw 13121-1 1000 I505010 So6051.
163 17000 to 1703 70-115 17020 3 7523 J
90-100 17700 to 17701 145 17720 to 17721 85 IT2 so 17703 10 17722 to 17723 100.I50 180 so 17601 125 17820 to 17821 7S 17M0to 17803 160 7822 so 17823 1 IS l30003 0o 02 80.100 I0s0 to III0 70-135 01*.*W W0-0s 90 1
Alter the nt CmosviT4 umit Ihs been InsI1od. final ociusttne can be m*de by allowing the unit to operate 1for 5veral cydes to permit th controlled systota so soblUbe and ten odaust to dehdred tempe*vraues. Tme sysiem should then be coaled to ambient reheated end sabklllhd to lsdb the setng.
To adIusf a bigh tempeiaturv moisture resistant 114ERMOSW7CO unitl (Cat. No. 01470020-0) It Is necessary to remove h eal Cap. A screw.
drive adjustment Is fen moade Internoly. Use cauflon when m~ang adlustmeals at temperature extretmes.
WIeer extremely oc.uoe 1. temperoture control Is desired several reNodustments mnay be necessaoy to stablioze the T'HERMAOSWITCH controtlaer hdwch toh*e dustmet wall be moinkan".
CONTACT PROTECTION Capadtors ore not required under overage conditIons. FW soather control ot smoll loods, on D.C. opplicaltan or so prevent conlto bounce due to vibratIon the following c*ort is recommended as co o
Capacitance MFD Volft service WIMOVAC Ratin 120 VA.C..
Ressistace None requed I 240 V.A.C.
Resiksta
.3 120 f 240 V-4-.
or.D.C.
tA N-2
.W or c.
4 ous tRemy TESTING TEMPERATURE S6T POINT YUe et POWe TeepnatIre W
e t O ef pa at W
Mch e Ofo ntaW on a TH5UOS Wr Wont t t "ae'"
fc.OW A i'HERMO.
SWCH0I1" osre t etoal
- oe;:, (1*F
- SV1) wnless odhetlse spoeded In vwld me te ore d
oy amWw presea taly sitec*f*ed 1em er
,r tln Ise temperature rte ad t I
en TI4 MOSII U 111attloaierrequires testIng sfl tepertr se0p-a, fib*0 Is recsommeondle!d thalt testinevices be used lishelleroatoseathel dlaclctr. An Ideal thermal Instdalalmay sretiquire that the THERAOSWIlIunt haleated s nesr poible so the eat sourft. Tvst th temperature "et P
of. aI IRMoSstal uill In aapp kloonounderOanoSsps wier beoa s*w* e Is renmoey localeld kro
?uIMOSW3T~4 aniot hen
-min tempeakratur conctlflns w Sare r b go-, eareqv 75%' may gve mkdeodeW results. In some eases this hol;led so relectIlon of units wiel s
w mer c
lywttllnpropel teigh taerncWTs refore werecommend ethe us lta Feel ModelS000l1-Teat3l. for lesting tietmp alure se points on Fe*n*sl EMOSWIC unit of tihe 170XXX 1300C= end 67XX Series lypes.
For cus"nons who wks to buIld ther own tle equtiapmn we recommend tha yot conictd your ne*awes Fenw Representlet. He o equIpped
- 1. iveyou furtherguidnceIn settingup agoodd-thravest ssteam.
LIMITED WARRNTY STATEMENT Fenwal Incorpotetd repmemsent that shIs prod h free from cdefects In moatalof and worunonshtip. and It will repair or replace t
we or poll hereo* wl pro*v to be detective In wornranshlp or material for a period of twelve (12) monthe from th eelt o purchas but not to exceed elgbter (10) months alote shipment by the sellr. For a full descrition of Fenwols LImITE WARRANTY. which amon ote "ns. tmft the duration of worranties of MEROA1TA8PJW ad FITNS FOR A FARTICLAR
.PUPOSE ond EXatUDES y for CONSECAMNIM DAMAGES. pleose reod th entire LMITED WARRAUNY on the Fenwol tuotaton.
Acceptonce of Order cndfor OrIgina Invokce whic will become a part of your sales agireement. Defecive unbits should breturned to the factory. Asldand. M*ssadcuselts. sdhpment prepald. F*nwol Incorporated wig repair or replace ond ship M.10.".
7/5/75 IFENWAL INCORPORATED IaDO t"We le A company. In&
A11111d. Uassecfasusd flint.
05
VANWATO#aECTjPJC CAWO~TIMt~ No, Vye.-I Dept. Mgr.
PORC -A Plant Mgr.
Proc. No.
A.Rev. No.
Issue Date Review Date
~12~
07/02/98 RCIC STEAM LINE TUNNEL/SPACE HIGH TEMPERATURE FUNCTIONALICAUBRATION TEST PURPOSE To provide the Information necessary for Instrument and Control Department personnel to perform a functIonal/calibratIon of the RCIC Steam Une Tunnel and Space High Temperature instruments.
Performance of the Functional Section of tfds procedure satisfies the Rinctional Test requirements specified by Technical Specifications in Table 4..2.
Performance of the Calibration Section of this procedure satisfies both the Functional and Calibration Test requiremdnts specified by Technical Specifications In Tabke 4.2.2.
The use classification of this procedure Is Continuous Use.
DISCUSSION The RCIC Steam Une/Space High Temperature monitoring instruments are designed to continuously monitor temperatures around the RCIC Steam Lines and RCIC Area Spaces for steam leaks end Isolate RCIC If setpoint temperatures exoeeded. The Instruments Installed for this purpose are FENWAL Thermoswitch Temperature Controllers. These devices have contacts that will actuate from the expanslon/contracon response characteristics of metals when exposed to changes In tomperatur.
This Isolating system consists of sixteen (16) temperature switches located In four (4) locations with four (4) switches each. The RCIC Steam Line/Space High Temperature Instruments are designated as follows:
Instrument Number 13-79A 13-80A 13-81A 13-82A Main Steam Line Tunnel (North)
Auto Isolation Signal Auto Isolation Signal Auto Isolation Signal Auto Isolation Signal Associated Relay 13A-K3 CRP 9-30 13A-K38 CRP 9-33 13A-K4 CRP 9-30 13A-K39 CRP 9-33 13-79B Torus-West Auto Isolation Signal 13A-K44 CRP 9-30 13-80B (5 ft above catwalk)
Auto Isolation Signal 13A-K45 CRP 9-30 13-81B Auto Isolation Signal 13A-K29 CRP 9-33 13-828 Auto Isolation Signal 13A-K40 CRP 9-33 79C 13-SOC 13-81C 13-82C Torus-West (16 ft above catwalk)
Auto Isolation Signal Auto Isolation Signal Auto Isolation Signal Auto'lsolatlon Signal 13A-K44 CRP 9-30 13A-K45 CRP 9-30 13A-K29 CRP 9-33 13A-K40 CRP 9-33 OP 4396 Rev. 12 Page I"of 6
YAN"EEAOMO MI AN CLUATTIONT NO, E(0 Instrument Number 13-79D 13-SOD 13-810 13-82D Loation RCIC Pump Room (16 ft above flood Auto Isolation Signal Auto Isolation Signal Auto Isolation Signal Auto Isolation Signal Associated Relay 13A-K44 CRP 9-30 13A-K45 CRP 9-30 13A-K29 CRP 9-33 13A-K40 CRP 9-33 II.
II I
The functional test Is performed by energizing an Installed test heater to simulate a stearn ine break. The calibration test uses a portable test heater Installed over the temperature switch that has a permanenty mounted thermocouple. The switch is Initially preheated'to simulate the more uniform heating of the metal sensor that would be experienced with a steam leak/break. The mounted thermocouple Is used to measure the actual trip point of the temperature switch.
SURVEILLANCE SETPOXNT CRITERIA Intinnt Meaau~red Tech Spec VTZ Tr-ip INmber Parameter Action setting seeting TS-SO3-80AB,c,D ARONUD ISOLATION TS-13-S8ASC,D RCIC SIGNAL Ts-13-"2ABCD STEM LIM I
ATTACHMENTS
- 1.
VYOPF 4366.01
- 2.
VYOPF 4366.02 RCIC Steam Une Area High Temperature Functional Data Sheet RCIC Steam Uine Area High Temperature Calibration Data Sheet REFERENCES
- 1.
Technical Specifications
- a.
Tables 3.2.2 end 4.2.2
- 2.
Administrative Uimits
- a.
AP 0125, Plant Equipment Control
- 3.
Other
- a.
GEK-32441. RCIC System
- b.
WNPS FSAR, Sections 4.7. 7.3.4.7.7, 7.3.4.8.7 and Figure 7.3.6 C.
CW Sheets 1179,1180
- d.
EQ File 013-1
- a.
AP 6807, Collection. Temporary Storage and Retrieval of QA Records
- f.
AP 0310, Surveillance, Preventative and Corrective Maintenance Program
- g.
AP 0047, Work Order Request
- h.
RP 4394, Process Temperature Monitoring/Steem Leak Detection System FunctionaliCallbration*
I OP 4368 Rev. 12 Page 2 of 6
YAN1EEATOMI~aEMM CjDW ATTACIENTE PAGEOJQf.j PRECAUTIONS
- 1.
Only one (1) Instrument will be calibrated at a time.
- 2.
Ensure that the associated Instrument relay Is DE-ENERGIZED prior to actuating another temperature switch.
- 3.
If the need for corrective maintenance Is determined during the performance of this procedure, Initiate a Work Order Request per AP 0047.
- 4.
If this procedure cannot be completed as written, hold at the most secure point, notify the Shift Supervisor and discuss the possible resolution with an I/C supervisor.
I PREREQUIS 1.
2.
3.
PROCEDURE A.
FTES Measurement and Test Equipment Required:
- a.
Test key (13A)
- b.
Omega digital thermometer or equivalent for K type (calibration only)
- c.
Variac (calibration only)
- d.
Test heater (calibration only)
- a.
DVM/DMM (calibration only)
The station will be In a shutdown condition to perform a calibration test.
Environmental Qualification (calibration only):
- a.
Review the File EQ 13-1 for any maintenance requirements necessary to ensure continued qualification.
- b.
Obtain any parts required to be changed per EO File Instructions.
0.
FUNCTIONAL TEST
- 1.
The Shift Supervisor Is fully knowledgeable of the scope of this procedure end by Initialing the data sheet, grants his permission to perform the work.
- 2.
Verify that the following associated Instrument relays are DE-ENERGIZED:
CRP 9-30 CRP 9-33 13A-K3 13A-K29 13A-K4 13A-K38 13A-K44 13A-K39 13A-K45
- 13A-K40
- 3.
Insert the panel test Jack Into the test connection for the Instrument to be tested at the heater test panel.
OP 4366 Rev. 12 Page 3 of 6
YANKEEATOMI ECBTRICID ANY ATTAC*WAENTPAGE O-7FT
- 4.
Turn power switch ON.
- 5.
Momentarily depress and release the panel test switch.
- 6.
Verify that the panel test lamp Is ON.
- 7.
Verify that the CRP 9-30 or 9-33 associated Instrument relay ENERGIZES.
- 8.
Immediately upon energization of the CRP 9-30 or 9-33 relay, turn the power switch to OFF.
- 9.
After the temperature switch has cooled down, verify that the CRP 9-30 or 9-33 associated instrument relay DE-ENERGIZES.
- 10.
Remove the panel test Jack from the switch test,onnection.
- 11.
Repeat Steps A.3 through A. O for the remaining Instruments.
- 12.
After functional testing Is 6ornplete, ensure power is OFF and test lead Is disconnected on the heater test panel.
- 13.
On completion of functional test, proceed to Final Conditions.
B.
CALIBRATION Calibration will be done In conitnotion with applicable sections of RP
- 4394,
- 1.
The Shift Supervisao fuly knowledgeable of the scope of tifs procedure and by Initialing the data sheet, grants his pemilssion to perform the work.
- 2.
Establish phone communleatlon between the temperature switch location, CRP 9-30 and 9-33.
- 3.
Verify that the following associated Instrument relays are DE-ENERGIZED:
CRP 9-30 CRP 9-M 13A-K3 13A-K29 13A-K4 13A-K38 13A-K44 13A-K39 13A-K45 13A-K40 0P4366 Rev. 12 Page 4 of 6.[
YANKEE ATM B.LE07MMMANY*
AT1ATMW2NTEPrEJ-F9 Calibration of temperature switches can be subject to the influence of test conditions such as orientation.of the heater, thermocouple location and speed of temperature change. Be as consistent as possible with testing methodology In order to minlmlze unwanted influences.
- 4.
Connect the MITE to the thermocouple (which is attached to side of temperature switch) for switch being tested.
- 5.
Place test heater over Fenwal temperature switch being tested.
- 6.
Turn the Vearac ON with an AC power setting of 30 volts AC (measured with DVM).
- 7.
When switch actuates, turn OFF Variac and remove test heater.
- 8.
Set Variac to an AC power setting of 26 volts AC (measured with DVM).
- 9.
Allow Fenwal temperature switch to reset and cool to, 160 OF.
- 10.
Re-Install test heater and turn on Variac.
- 11.
Record the As-Fmund reading when switch actuates.
Required: 185
- 66F
- 12.
Verify the associated instrument relay ENERGIZES.
- 13.
Turn the Varles OFF and remove Test Heater (allowing switch to cool down) and verify the associated Instrument relay DE-ENERGIZES after temperature switch resets.
- 14.
If recalibratlon Is necessary, adjust the switch to trip at the temperature settings specified In Step 9.11. Repeat Steps 9.8 through 9.14 as required.
Record the "As-Left" readings.
- 15.
Repeat Steps 8.3 through B. 14 for the remaining temperature switches.
- 16.
After all calibrations are complete, ensure Varlac Is OFF and Test Heater is removed.
- 17.
Applicable environmental qualification requirements, listed in the Reference EQ File, have been satisfied.
- 18.
On completion of the calibration, proceed to Final Conditions.
OP 4366 Rev. 12 Page 6 of 6
YAWMEATOMM Et.m*CTRIC V
ATTAMýj~
ACCEPTANCE CRITERIA
- 1.
Successful operation of all temperature switches and relays.
- 2.
Setpoint values shal be Within the tolerance as specified on the data sheet.
- 3.
All applicable EQ requirements are satisfied.
FINAL CONDMONS
- 1.
Notify the Shift Supervisor on completion of functlonal/callbration test and of any discrepancies.
- 2.
Return the completed VYOPF 4366.01 andlor VYOPF 4366.02 to an I/C supervisor for review (AP 0310) and filing In accordance with iP 6807.
OP 4366 Rev. 12 Peas 6 of 6
YANKEEATOMICBJ Mift 71LEVATINMD V C A1'caPG4 TIThZv RCIC STEAM LINE MREA HIGH TEMPERATURE FUNCTIONAL DATA SMET I
- 1.
88 a
eus sc 2.
I I
OR i
9-3i/9-33 Iassociated Relays T
Switch 13-79A 13-OA 13-81 23-2A 13A 13A 131 131
- 7.
Relay ENERgIZEZ) 13 K138 X4 39 13A 13A 13A 13A
- 9.
Relay DE-N*ERGIZED K3 I
8 14 K_.
Tmp Switch 1 13-798 13-808 13-818 13-828 R3y D
133 13A 131
- 7.
Relay ENERGIZED 144.
U5 1X29 X40 13A 13A 13 123A
.9.
Relay
-ENERGZED X44 MS 4
I 129 X40 Tp Switch f 13-79C 13-80C 13-81C 13-82c 13A 13A 13i 1 13
- 7.
Relay ENMWIWUI 144 X45 129 40 13A 13A.
13A 13A
- 9.
Relay DR-aNERinoI 144 145 19 M
K40 sep Switch 1 13-79D 13-80D 13-810 13-820 13_
LT 131 7o Relay MMIZED F
4 45 129 140 131IMa 1311
.Relay DKI-ZNZITZRD 144 4S X29 40 DiIcrepancLes)%emarkiiW Tested Bys
- Date, hiLft Supervisor Reviews Dates I/C supervisor Review:
Dates ViOPi 4366.01 (Sample)
OP 4366 Rev. 12 Page I of 1 R2 No. 04.03.216
YANMEEATOMaC aEc11MCOMAWf
,JCA1 1Tj4,OVYC icv0 TITI,,I UCIC MTEAH LIM AREA HIGH T"EMPERATuz CALIBRATIUN DATA SHO1ET STEP I
LlEkUi RE
- l I Ce 54.4...
1 I
I.
168----------
CRP 9-30/9-33 ID-E-ERGIZEDL 3.
______ Switch 0 13-79A 13-80A 13-81A 13-82A
- 11.
As-Found Temperature 23A 13A.
13A 13A
- 12.
Relay ENERGIZES X3 X38 X4
]39 13A 13A
- 13A, 13A*
- 13.
Relay DE-ER*EIZES 3
K38 X4 X39 As-Left Temperature
- 14.
180 to 190F
_ Tep Swltch 0 13-79B 13-808 13-812 13-828
- 11.
As-Found Temperature 13A131
- 12.
Relay ZENERIZES
-44 13A.
sl is s
- 13.
Relay DE-EIfEMIZES 44 42 AS-Left Temperature
- 14.
180 to 190"F Temp Switch I 13-79C 13-000 13-81 13-82C
- 11.
As-Found Temperature 13 in 3
13A
- 12.
Relay ENERGIzES 445 X29.
40 13M 13A 13 A
I a
- 13.
Relay DZ-ENG*UES 445
]29 1140 As-Left Temperature
- 14.
180 to 1900?
Tep Switch 0 23-79D 13-8OD 13-8lD 13-82D
- 11.
As-Found Teamerature 113A 313.13A
- 12.
Relay ENERGIZES 44 X4 290 13A3 131 13A
- 13.
Relay DE-ENERGIZES 144 X4290 As-Left Temperature
- 14.
180 to 1901F 117.
EQ Req.
WORT 4366.02 (Sample)
OP 4366 Rev. 12 Page I of 2 RT No.
04.T03.216
ATrActawm s:
,P 3 P ORIGINAL PAGE 1 OF..*.
Es i
i P
3 Rev 1: PAGE I OF
-PAGES 25 P98 It 4 Pp 32 4 Poe R-OD*N.
0~1 1a P 121:8 Pps 34 1 PsRev 3*PAGE IOF -PAGES
- Po 2
Pg 1
Pps 243 2Pgs 37 1 Pg.
I10 S POO 24 3 Pps 37 Pg.
RECORD TYPE NO.
O9(lQ.0O4 112U19 Pp 254 Pg.
38 Pg f3 4 Pp 29 12 Pps safe CtassiP.O. NO.
ITbwPag.. 63.
YANKEE NUCLEAR SERVICES DIVISION CALCULATIONANALYStS FOR MFARI IRInI I TFqT F.'
Hp~ANNr" IINPLIRTAINTY ('ALCLII ATION TITLE PLANT VERMONTYANKE-CYCLE 19 CALCULATION NUMBER WC-1758 NEWORDS COMPUTER COOES.
EQUIP/TAG NOs.:
SYSTEMS:
REFERENCES:
MODELS:
Refer to Sedlton A Ashcrot, 1082AS% BRuwMv Thennmejmef R~dbm.Sde4nrhfE~~a6 kw.-
82 6
655 677-DOW,7 Fluke 27,7787-80082& 8520k-Heise CU. CUM 730- 9M,1 HP S4A. 34401Ak Joft SM05 Ome, 4A_ RA. CLW6A_ 8MFP 2178k, RflosmotiWt Readnt Aweft Tmansmalk'n 1040 FORM WE-103-1 Revisgon 4 WE-103-24
YAWEEATO MI0 jO CALC(AADMtNO VYr Measuring & Test Equipmnet Uncertahty Calculafon VYC-1768 Rev. 0 2.3.9.3. Ten atre EFe* Is based on Max ReadV of de*ed cafbration spa and not ie rangeoflhe DMM.
M 2 2.3.9.4. The uncectiessted by HP Ibrvos and as AC av squency dependent This cabdalGon used the fivquency ranges cdos Iti 60Hz fIr Swdetumwo dwm tay for vb andampsAc. The f tow te pr&ides a Isleg of fiqencles at wre used b cacuab ie umoertaak forvots and an AC.
If,.)
Table.- HP 0MM AC Frequency Used HP344 I
VAG I
I, N -G.
i
- An" 1,56 E A
2.3.10. Onea 4A& AkOmnlWl Teperate Cahx-aW 2.3.10.1. Referncecuracy Includes acuracy. stab
. onbmft.
nang. and reference junctio en~wuerabu w
ognation. Thei1year Refwerec Accuracy secificalon icudes nl cetaintesfor thedevic MAl 28 &371 2.3.10. The spedG f
rlhe4A&Maslhesanie. Theditieno between lihe nilts is at ie 4A cowme ocq* types J. K and T ee the 8A covr J. K T. F, R. Sandd a tV 28& 371 23.10.& Range bmperaa ec-tconnsad, apples 4 iU 104,F(-101Oi4O*C and Is asuwuied to be Include In die ReferncmourAacy.
V&L 281 2+/-.0.,4.m rmelon ipensal*nOM.O17'perdwf*m3Ue I
96 U9 (35in IW-C)ond Isesssansdtobe Inckded In to Rlfefoe.
Aacaq.
[Art 281 2.&1. Omega 8WF w hd
) TDhmome~
- 2.
Ref.r. eneM oW.raW &IWk dals
. DIN4376W0 =
c, tomporakwo oooedeits (542 Sm deaM wiltxhrup bi o
0
- f.
600 lad
,esistauce e yew-fesuuce omxW opedcdon Incxds any umoertainties forliet device If *Mtn specified. wange ofleqrakue.
VA 371 2.3.11. Thrue%*ea=raV.Isfl
,anieas nfotw RiD tg,-,lst IPAe enors o
remod by rnfhig of Insumepb fps obe @ 32F.
IftL,30 2.3.12. Omega C"M Precision Temperftwe Calbrator 2.3.12.1. Reference Accuacy Indudes ewaoqy. maxinin inedizain enuw. Alp
-mesin Itena snument nclsA and eo~djunalo eoopensatIon. The I year Referenoe Aocuracy specificato Includes at unceraines for Im dovkc.
(AL 29 & 37]
2.3.12.2. The reslution spedcifictin Includes repeatabilt and othe varibles NAt is bmonded by W 1 year accuracy specficafto JAM 29& 371 2.3.13. Omega 2176A Mulipon Digital mme 2.3.13.1. RefermnceAoracy Indudes aocumacy. ret oeroxJuc comnpesaon (if wihln range of 6945*F). repeatabW and confrmd efrmrs. E~des owmocoupi caws. The I year Referec Ac~xaW specification cludes
)of wal ceinties for the devce I wlhin specified ranges d mpe*ah*
A31& 371 Vermont Yw"a, Design &Vneft pace1 if o
kpatturt Test EWDmwA UncerdIft CoWafth
, 41
- Tet E entueulanh' abaion c-1758 1%ev.
0 5.1.9.
J1ofra Temperature CallIbato 10100.2I00UI 1.2702 1.81%
ISO I
U319 I
.9 LIM1 1.56 161%
200 1
1 L102%
14.9 202 32 35 1M 176M6 LIM90 1.240W' 4100 "14
.9%
24.44 2.1107 L.130%
450 3411 2A 23.9 I43 V.041
~
s 227.42 0"92%
5.1.10. Omega Temperatur Devices 1434121 I
[-
()2M to 137MC 1 AS (6) 4w ft7 ftl" AVC~2W I&
- f. 7. Ref. &.1.21 (At 8, Ref. 6.121 Venmont Yankee Design Engineeing
-~g 48 Pg4of 63
'I.
I V.<
- Klv, Jd,..est FEqulpt Unoeftlnty Cabj*
enC-1758 riev. 0 Table 80 Omec, Omnlc41 -A vhermeeunl. CalibratorTotal Device "rrat MAttachment MI nt i601 21a teP 14001M I2 mnM3C l
12f 2414 0toPI20C IL97WC
-4 r
Table II Omeea Omflel SA IV fllaevtor T Devfe Rrmm IAttsebhment 81 MOM
=M M
(.Mt*2uv 20 0110 aft tot 0="
-OM64 OMM 02110 WOMM
&OS13 QMm_
I omil I
Table 8"2 ftee MFe RM'r enp1mm erobtsl DBwfee I~rroi (Attachme -AtM Vermont Yankee Design Englnefng Page47 of 53 qF I
FACILITY:
VERMONT YANKEE DOCKET NO.:
50-271 PRV NO. 9X4 APPENDIX II YANKEEATOWMICELECiC Oi~r I1 NO.:
TS-13-79A WJORKSHEET 5145 1
STEM.
A U T-ENVIRONMENT DOCL1MENTATION REFERENCE QUALIFICATION OUTSTANDING METHOD ITEMS PARAMETER SPECIFIED QUALIFIED SPECIFIED QUALIFIED Operating RCIC-lH
)>H 001 004 Sequential No Time Test and Eng. Analysis Temperature 300 0 F 355°F 002 004 Simultaneous No (Peak).
Test Pressure 4 psig 26 psig 002
.004 Simultaneous No (Peak)
Test Relative 100%
100I 002 004 Simultaneous No Humidity Test Chemical N/A Spray Radiation 3.5 x 10 6 R 5 x 10 7 R 003 004 Sequential No Test Aging 40Y 40Y Note 1 004
.. Sequential No Note 2 Test and EngS Nnalysis Subme'rgence N/A Component:
Temperature Switch flanufacturer:
Patel-Fenwal Model or Type:
01-170230-O90 (NO)
Location:
Area: Reactor Building -
- Vol, 41 Elevation:
2521-6" Flood Level:
Elevation:
N/A Above Flood Level:
N/A Previous Worksheet Number:
RCIC-4 System:
Reactor Core Isolation Cooling Function:
Steam Leak Detection Service:
TS-13-79A 0627T/18.ISOPGi
APPENDIX II 9
SYSTEMI cOMPONENT EVALUATION WR)KSHET I
FACILITY:
VER.MOT YANKEE OOCKET NO.:
50-271 ENVIRONMENT DOCUMENTATION REFERENCE QUALIFICATION OUTSTANDING METHOD0 ITEMIS PARAMETER SPECIFIEO QUALIFIED SPECIFIED
.QUALIFIED Operating RCIC-IH
)IH 001 004 Sequential No Time.
Test and Eng. Analysis-Temperature RCIC-42 3550F 002 004 Simultaneous No (Peak)
Test' Pressure RCIC-42 26 plig 002 004 Simultaneous No (Peak)
Test Relative 100 100I 002 004 Simultaneous No Humidity Test Chemical N/A Spray Radiation 1.4 x.10 6 R 5 x 107R 003 004 Sequential No Test Aging 40Y 40Y Note 1 004 Sequential No Note 2 Test and Eng. Analysis Submergence N/A Teoi"rature Switch Manufacturer:
Patel-Fenwal mlodel or Typo:
01-170130-090 (NO)
Location:
Area:
Reactor Building -
Vol.
42 Elevation:
2131-9" Flood Level:
Elevation:
N/A Above Flood Level:
N/A Previous Worksheet Number:
N/A System:
Reactor Core Isolation Cooling Function:
Sfteam Leak Detection service:
TS-13-798 I
S"0627TPGS
QOR NO. 9.4~
REVISIO AT
/APPENDIX IX SYSTEM cW1ýfENT EVALUATION WORI(SHEE 10 NO0.: TS-13-79C "ACILITY:
VERMONT YANKEE
,OCKCr NO. :
50-271 ENVIRONMENT DOCUMENTATION REERENrCE QUALIFICATION OUTSTANDING
&rTHOO ITEMS PARAMETER SPECIFIED QUALII'IFIED SPECIFIED QUALIFIED Operaiting RCIC-1N
>IH 001 004 Sequential No Time Test and Eng. Analysis Temperature RCZC-42 355°F 002 004 Simultaneous No (Peak)
Test Pressure RCIC-42 26 psig 002 004 Simultaneous No (Peak)
Test Relative 1001 1001 002 004 Simultaneous No Humidity" Test Chemical N/A Spray Radiation 1.4 x 10 6R 5 x 10 7 R 003 004 Sequential No Test Aging 40Y 40Y Note 1 004 Sequential No Note z Test and Eng. Analysis Submergence N/A Temperature Switch hianufacturer:
Pate l--Fenwal Model or Type:
01-170230-090 (NO)
Location:
Area: Reactor Building -
Vol. 42 Elevation:
213'-9" Flood Level:.
Elevation:
N/A Above Flood Level:
N/A Previous Worksheet Number:
N/A System:
Reactor Core Isolation Cooling Function:
Steam Leak Detection Service:
TS-13-79C I
062 TPG9
FACILITY:
VERMONT YANKEE DOCKET NO.:
'50-271 9OR NO.
9.4 REVISION 6 APPENDIX II SYSTEM COMPONENT EVALUATION WOR YAUEETOM U 'tECU !M*0u~u 1D NO.:
IS-13-79D KSHEET I
SYSTEM COMPONE EVALUATION WOR ENVIRONMENT DOCUMENTATION REFERENCE QUALIFICATION OUTSTANDING M-I HOC ITEMS PARAMETER SPECIFIED QUALIFIED SPECIFIED QUALIFIED Operating RCIC-1H
)IH 001 004 Sequential No Time lest and Eng. Analysis Temperature RCIC-52 355OF 002 004 Simultaneous No (Peak)
Test Pressure RCIC-SZ 26 psig 002 004 Simultaneous No (Peak)
Test Relative 100 1001 002 004 Simultaneous No Humidity Test Chemicad N/A Spray Radiation 3.5 x 10 6R S x IO07 003 004 Sequential No Test Aging 40Y 40Y Note 1 004 Sequential No Note 2 Test and Eng. Analysis Submergence N/A QRoEMmnt:
Temperature Switch Manufacturer:
Patel-Fenwal Model or Type:
01-170230-O90 (NO)
Location:
Area:
Reactor Building - Vol. 52 Elevation:
213'-9"
,Flood Level:
Elevation:
N/A Above Flood Level:
N/A Previous Worksheet Number:
N/A System:ý Reactor Core Isolation Cooling function:
Steam Leak Detection TS-13-79D I
0627TP'*I
YANKEEATOMIC EL ICCOMPANY cALcuLAnONNO VWYC-46.
_C>
PRtEtD@ 03/oo194 VW4ONT TAM=* 300I2i3634 9".IfIC.AION LATAIX (so"3 "3 S"S art.
A"a No)
, AZSI*,
=s I PSV DATE, 03Jat/94 SYSTEM lls0 R0I1C, AEACTOA r6Z ISOLATION. COMINrG SrVIZD
. 0016?T QUALIr
- .TIam MATRIX DATA SERVICES L
TION E3CWT 3"11 T32 r1 12 W3 DUR0ATION TAG NO.
sV sACHO WORM TRrP/aOL VOL 52 LOC¢L a 22 m*[*
23 RcICs C 23 RWCMs 2 23 0
0 a
00 TS-13-TIA al SPACE TWO, TRIP VOL 41 to*=$ 4 22 36 6
MS c C, 36 23 0
ICM tC 36 23 0
P.CZC, A
4 36 1
um RUCM,tO 23 36 0
Mgt C
23 36 0
tS-13-798 Rl SPAcE TEMP TRIP VOL 42 LOCAi t 22 36 6
MS a C 36 23 0
3Cl, C 23 36 a
=C6 A 4
36 1
1213 XVCU: C 23 a
ass 1 23 a
TS-13-79C III SPACE I-ZP TRIP VOL 42 LOCA:
- 22 36 6
Ks 23 36 0
PIsPCO 23 36 0
ILC8 A 4
36 1
In 31eal C 23 0
Us ag 23 0
TS-13-790 ol SPACE 3234 TRIP VOL S2 LOCAs
- 22
.36 6
KS 1 9 23 36 a
66015 23 36 0
AltIes 4
36 1
McIM#
23 36 0
=es It 23 36 0
TS-13-SOA or SPACE TEMP TRIP VOL 41 LOCAl 9 22 36 6
HS s C 23 36 0
SPCI C
23 36 0
CIt¢CI A 4
36 1
1mm M*IcU JrC 23 0
MR s C 23 0
TS-13-408 HI SPACE TM"P TRIP VOL 42 LOCAl I
22 36 6
KS
& C 23 36 0
lPC#
Cl 23 36 0
a XCICI a 4
36 1
12 1WCUs C 23 0
lMS e C 23 0
I I
FAGE S-100 EQDI g5; PA G E XL OFJ-o
YANKEEATOMIC ELEICRG OMPANY C~AJLCUAT.ONNo V4IC.
2L Lc.Vo miTE., 02/061i4 VZPNO" T AXKEE EglPMiT QUALIFICATION IIATIRlX ISO-tE. $I SITuE a T" No)
"EVision.2~
9Ev DATE, p~oehi96 Il SXUTEN IDS XCIC. REACMO ConW ISOLATIoll 40OLING STEMZ TAG NO.
SamVcts LO~2Zoh TS-13-SOC 82 SPACE It"u
]UP VOL 42 vQ=FMREj QOALLPICAEIIO 4AuT= DATA 01Thu A
"11 n
2 12 PORATION Loms X 22 36 6
HS I C 22 26 a
IOC01 C 23 36 0
xCIC A 4
26 1
IN 3lC5 C
aw f C 23 23 0
0 TS-13-80D NI SPACE TEHI TRIlP VOL 12 LOCAg 9 22 36 6
mS 1 Z 23 36 0
apeI: C
¢ 3
36 0
Itc1c A
6 36 1
11W
.13c:
2 23 0
USE 23 0
TS-13-81A as SPACE TOMP TRIP VOL 41 LOCAos 22 36 6
KS I C 22 36 0
PCZ0 1
23 36 0
ftc1
,1 4
36 1
urn M=: Z 2C32 36 0
IMS 23 326 0
SPACE 19113, "Tlil VOL 42 LOCAl 9 22 36 6
ut
- C 23 36 0
am$p C 23
-36 0
800C.a 4
34 1
in
,.,: C 23 0
m soC 23 0
TS-13-SIC II SPACE TE TRIP VOL 42 LoCAd z 22 36 6
XS I c 23 36 0
o t c 233 36 0
02TC0 A 4
36 1
11W Niwu C
22 0
RUts #o 23 0
TS-13-OLfD HI SPACE IEM "IF VOL 12 LOCA# Z 22 36 6
NSI 2
26 0
3
..01 C 23 26 0 :
RCIC A
4 36 1
I13 115*C00 22 0
ElS i 23 0
TS-13-82A MII SPACE TlUl TAXIP VOL 41 LOCOK I 22 36 6
Id o0 23 34 0
HI0CI C 23 36 0
I0C10 A 4
36 1
131 RwCu. SrC 23 26 0
VHS m C 23 36 0
PACE 9-101 EQDI q5-55 PAGE 3 5 OF:/;t
EaiOMKi E C1OMIWd Cm$j~LA11mo, voc-467c.
?.V 0 AP H
9 blYAGP) - W PRINTW 10/06/9S VERMONT YAM=E.QUIPHENT QUALIFICATION MATRIX (sOTzD or sys*M a TAaO NO)
SYSTEM IDS ACIC. REACTOR CUFZ ISOLATION COOLING SYSTEM REVISIONS 16 I
REV DAS,
.10/os/95 TI" NO.
SGrjYTS LOCATION
.e a e
e n
Sl~
flsm m
EQUIPMENT QUALIFICATION malah DATA CAT TUN1 TDN2
?I P2 P3 DOWLTION TS-13-82B HI 8PA&C TZHP TRIP VOL 42 LOWC*S ms S C PChIs C AMC$c A awcOs C 22 23 23 4
23 36 36 36 36 6
0 0
1 0
INN onSa C 23' 0
TO-13-82C iii gram TZ0 TRIP VOL 42 14OCal 22 36 6
MS s C 23 36 0
am$, C 23 36 0
ACICSA 4
36 1
im1 Nwcul C 23 0
US sC 23 0
TS-13-820 HI SPAM3 TZMP TRIP VOL 52 LOCAs X 22 36 6
MS 2X 23 36 0
'ILCI C
23 36 0
RcICl A 4
36 1
1H RwCUl S 23 0
13 8I 23 0
VIS-23 1/AZl', DC STARTED VOL 30 LoChe a 67 3
6 LT M*
I 67 0
51I0 C
67 0
AICI A 67 1
8L RNCUs C 67 0
I=
IeC 67 0
VAO-,P GLAN Buz vac fP/NTAR VOL 52 Loire 2 22 6
)48s 23 0
NIl sC 23 0
RO*We 23 o
80 v 2 23 0
PACE 5-101
"eAf.1.1 5
ga ft WtIG6 tk ma ue m 9"A alrntmas t*
ob"etas nOM.- I t-onl W&
1-- 1 m
m IMn Ill in ou a-f t nw M1
.in
- goaft, vastal g
oq.wp hl.
"Mob.
,...w, twine.
n "U.N.
mam IM64 hwg k a
ft*mh
- h.
ft. fto. *A. rigt'. ow ig. II.
no. ft. Pig. f fg.sm mom nooZ ftni.
- s. it noig., ft f ft. f
,.wtti.ft.
,g.vS V". 3:10 at N
so-a b1651-
~
it. ni1 "I.a Be I"
to
&I in%
a IN A~v Ui 0
Iona VA. 3%
1 we Io Ieta a
Rem I
menu Me."
01544 51O-N Mci-m GrnI-M mmvu low" Vol. 39 39 o
o f
t o
sm-*
Oim-omel stIA m
0s aa I
on VA V
I3W Wasl tin my weZ 4
m0woa maf Ut Is Oct t
In
,w, W6_________&-NM
_:set" 62" "o-teat
$1
-I Va" II
-3 on i
lowl" "
9&-a.
rn-4I maC-a, ma-al mt-ft M"
g Oct
-somrn at. Its tIam wea.
ta IS atl a*
Or a
- i.
a PAGE
-fO2A0F,
Tau1 741. (eAbatmdA "aftr sa0? t u.11 gh f14bt"" uma &Mk btwieftwu A- ~
~
~
~
~
a HWiK.f 11 I
A--NW51 I
I n 3 I I NW MMi A
I I 1 RaKUIO
?04k P.0k 5.4ek ak a 0 Illad fo
.O.
7"09-n fa.
NmiOAip IOP.M Ims*4.
Kmeldltl tamp.[
fl em$. Koeldity ?OMP.W Imsk.
xmiti1y imp.tn7 ftaas.
NU10Aky 110avai.
PA,. go.
I'll. "I.. ell, ft.
Al,. ft.
r14. go.
ftl.
ft.
Pig. ft.
PA,. ft.
ftg. M..
Pig. f..
P~q. No. rig. ft.
rig. ft.
rig. "4.
rig. g..
9.4. 44 120 100%
244 logo 114 loot in 14k 1it If 100k Tom. ft.
Mt444 "1.44 XKtC-44 OMc-44 MO1-44 RC-4A4 ILV-44 WWCU-44 O4 cl. 213.
ti.
- 322, 9,ft. 4 14k 1034 214 K
N N
M1 ton4 144 11 10 ftrua An.
M$-44 NS-46 IC1-46 K?1144 XM1-44 ROCU-46 SWCU-46 IN3-44
- 91. 211 Vo.1.41 H
H M
K H
N A
H 11 K
H H
st on N-6
- 91. 232-9,". 411 117 to" M2 113 loot in IM0 121 HIt 0
lena ".
x4-4 30.4$
33-811
-46 NIC-E 31-449 "a1 I
am1 I rnAl aV.-48 MIS-A u
s-a1c1 C0-N-48 T". 40 1ot
- tow, 214 110 loot 214 100%
142 H
loot Cox " O..
W3-0 X2-49 XM1-40 KCI-49 NM-140 301 I NMI "CI-49 59C10-44 WA3-49 HI. 232' Saa0.4 MO-49 Vo1. so122#
Vol.
$1 1K1 100%
144 134 loot 14 lee$
lit ft lobk VA 0310m MM-3 H0.11 0411-$1 xMC-51 amit-IM1 I sm1 I 5049-fl
- 049-11 M-411
- 91. 2121
.41a-I MC-61 v".1.2 K
H" 1"
on0 Ma 44 Ml N
N
- 93. 213,Nt 1041. 1 K
PAGE OF.3
YANKEE ATOMIC ELEcTRIC COMPANY CALCULA77ON No. VYt¢ - 4G Z. t-
?Cv o S E C E C
I >
7 9
-Rev For environmental qualification purposes the Steam Tunnel includes Volume 41, as illustrated in Appendix D.
HPCI TURBINE ROOM (Turbine in Standby)
Below Elev. 230' Elev. 230' and Above Average Temperature (°F): (Ref.
- 58) 100 120 Average Humidity (%):
60 60 Peak Allowable Temperature (OF):
106 140 Pressure:
Ambient Ambient For environmental qualification purposes the HPCI Turbine Room includes Volume 50, as illustrated in Appendix D.
FCIC TUBINE ROOM (Turbine in Standby) r Average Temperature (OF):
100 Average Humidity (%):
60 Peak Allowable Temperature (OF):
112 Pressure:
Ambient For environmental qualification purposes the RCIC Turbine Room includes Volume 52, as illustrated in Appendix D.
TURBINE BUILDING -
OCCUPIED AREAS ONLY (EXCEPT AREAS NOTED BELOW)
(Operating and Hot Standby Modes)
Average Temperature (OF):
100 Average Humidity (%):
60 Peak Allowable Temperature (OF):
105 Pressure:
Ambient TURBINE BUILDIWG -
HEATER BAY AREA (Elev. 272'-6)
(Operating and Hot Standby Modes)
Average Temperature (OF).:
1256F Average Humidity.(%)t 60%
Peak Allowable Temperature (OF):
130OF Pressure:
Ambient TURB"NM *BUIL~
FRONT STANDAD AE Eev. 22-"
[Operating and Hot Standby Modes)
Average Temperature (OF).
12SoF Average Humidity (t)s 60%
Peak Allowable Temperature (OF):
130OF Pressure:
Ambient TURBINE BUILDING -
LUrE OIL HALLWAY AREA (Elev. 248')
(Operating and Hot Standby Modes)
Average Temperature (eF):
1000F Average Humidity (%):
60%
Peak Allowable Temperature (OF):
104 0F Pressure:
Ambient Note:
For components in the vicinity of steam piping, the steam tunnel conditions listed on the previous page should be utilized for aging analysis. Actual measured values (properly documented) may be utilized for specific components when desired.
7.4.2 Radiation Normal radiation conditions extracted from Reference 4 are listed in Appendix A.
This data represents bounding conditions accounting for local, 7-13
YANKEE ATOMIC ELECTIRIC COMpAWv CALCULAMIN NO. VIC - 46. 2 4-ATrAcOI._x Re*
hot spots.
Actual measured values (properly documented) may be utilized for specific components when desired.
7.5 DESIGN BASIS ACCIDENT ENVIRONMENTS 7.5.1 IntroduCtion The tables, figures, and associated notes in Appendix B provide the environmental conditions in many areas of the Reactor Building after a LOCA, MS HELB, HPCI HELB, RCIC HELB, or RWCU HELB.
Note:
The Reactor Building temperature and pressure profiles included in Appendix B represent average conditions throughout the applicable volume (or area) of building.
When a component is located in the vicinity of a high energy line, it should be reviewed to insure the average volume conditions are appropriate for that component.
Section 7.5.2 summarizes the controlling analyses that form the basis for the HELB environments listed In Table 7.5.1 of Appendix B.
Section 7.5.3 discusses the environmental consequences associated with the HELBs postulated in the steam tunnel and Turbine Building.
Section 7.5.4 addresses all other design basis accidents within the scope of IOCFR50.49.
7.5.2 Summary of Controlling Analyses for HELB Environments v,.
3 DELI Main Steam Feedwater HPCI (DEG)
HPCI/RCIC (10 GPM)
HPCI HPCI RCIC RCIC RWCU Steam Tunnel Steam Tunnel Steam Tunnel Steam Tunnel Torus Room Turbine Room Torus Room Turbine Room Pump Cubicles (El. 2801)
Heat Exchanger Room (El.
280')
Qgmuter Ru ABGQAEBO N/A ABGQAUtI ABGQAFVR ADOUSER ABGUAAO ABGUHME ABGUAYZ ABGUMOB Remarks See Note 5 See Note 6 See Note 7 See Note 4 See Notes 2 and 3 RWCU ABGUHPD 7-14
YANKEE ATOMIC ELECTRIC COMPANY CALCULATION NO. V.IC -4 42.-
ATTA.CH~ :r-.*7
_ _ri -:3p REV 6 Locat ion eo2trRnRemarks RWCU Phase Sep. Room ABGUSEI (El.
303')
RWCU Elev. 318' ABGUSFX RWCU Return Line ABGUHYF (El. 252')
HBS 6" at Elev. 252' ABGQAJFZ HIS 4" at 1lev. 252' ABGQAXJH RHS 3" at Elev. 280' ABGQAEBI HHS 3" at Elev. 303' ABGQAEBU EBS 3" at Elev. 318' ABGQABWW HHS 3" at Elev. 345',
ABGQAGBQ Notes:
- 1)
Unless otherwise noted, an initial average Reactor Building temperature of 1000 F was used in analysis.
- 2)
This computer analysis used an initial average Reactor Building temperature of 90 0F. The difference between 90OF and 1000 F starting temperatuze has been either incorporated into affected curve (Appendix B) or, the effect of using this lower initial temperature has been judged to be minimal in regard to calculated peak HELD temperatures. See Table 7.5.2, Appendix B.
- 3)
This RWCU HELD analysis postulated a break in the pump suction piping and assumed forward flow only due to the pump discharge check valve. All other RWCU analyses assumed a system blowdown after isolation valve closure.
- 4)
This analysis assumes the concrete block walls of NW stairwell enclosure fail on all floors. A design change to strengthen the block walls and provide a vent path to El.
3451 has been done. The environments from this analysis are equal to or more severe in all areas of the Reactor Building than the environments calculated based upon the block wall fix.
- 5)
A main steamline break in the steam tunnel (Volume 41) was analyzed by the RELAP4/MOD5 program, described in Section 7.3, with the results summarized in Appendix B.
This analysis showed a Vnak temperature of 3000 F. This peak temperature is bounding for all other HELB events in the steam tunnel. This includes the Feedwater, HPCI, and RCIC piping systems. However, the duration of the event, temperature decay rate, and resulting temperature/pressure profile versus time will be different for each event (See Appendix B, Table 7.5.1).
7-15
YANKEE ATOMIC ELECTRIC COMPANY CALCULATION NO. V'c -,4*
ATTACHMENT (-
PAGE,. *, 0_
- 6)
The isolation characteristics of the HPCI and RCIC systems for a HELB in the steas tunnel are identical, I.e.
excessive flow (0300%) initiates immediate isolation, excessive area temperature 02000F) isolation is delayed 30 minutes. However HELBs in the HPCI system, being the larger system, will result in greater mass energy release, therefore environments resulting from HPCI HELBs in the steam tunnel should be considered to bound the affects of RCIC HELBs.
- 7)
This break is of a magnitude applicable to either HPCI or RCIC.
7.5.3 Steam TMnel and Turbine Buildini MEL~ s Sections 7.5.3.1, 7.5.3.2, and 7.5.3.3 address the postulated HELBs that could occur in the steam tunnel.
For any size leak, the worst case steam tunnel flooding is not expected to build up to the elevation of the main steam lines (approximately Elevation 253'-6").
The door between the steam tunnel and the CRD Repair Room is designed to blow out at 2 psig, therefore any large size breaks will blow out this door, and drainage out the door will limit any appreciable level buildup in the tunnel.
For smaller leaks that do not pressurize the tunnel, water level buildup will be at a slow rate and the leak would be detected and isolated before the water level in the steam tunnel reached the steam lines.
7.5.3.1 Main Steam Line Break in Steam Tunnel As described in Section 7.5.2, Note 5, the main steam line break in the steam tunnel (Volume 41) was analyzed to have a peak temperature and pressure in accordance Appendix B, Figure MS-41.
Many areas of the Reactor Building and the Turbine Building will experience some heatup following this HELD, but the essential electrical components in these locations necessary to mitigate this accident are environmentally qualified.
7.5.3.2 HPCI and RCIC Steam Line Leaks in the Steam Tunnel In order to realistically compare and assess the environmental conditions resulting from a HPCI or RCIC steam line break in the steam tunnel the following cases were analyzed:
- 1)
A double ended guillotine HPCI steam line break with subsequent isolation initiated by high flow. This case represents a large potential mass energy release, similar to the MSLB for which immediate isolation is initiated, but requires a longer time to isolate.
- 2)
A "small" HPCI/RCIC steam leak with flow equivalent to 10 gpm.
condensate. This break is representative of a significant small break well within detection capability for which time delayed isolation on high temperature would apply and which is of sufficient size to impact areas beyond the steam tunnel.
(It is not credible for the HPCI/RCIC steam lines in the steam tunnel to fail such that a leak greater than 10 gpm (condensate), but less than the 3001 high flow trip flow rate suddenly develops.)
7-16
YANKEE ATOMIC ELECTRIC COMPAr y CALCULA77ON NO. VYL -4,z..
REV 5 For the above postulated breaks the steam tunnel temperature reached the 200OF high temperature trip isolation set point. For the double ended break steam tunnel temperature reached the high temperature trip point almost instantaneously. For the 10 gpu break the high temperature isolation trip value was reached in less than 15 minutes.
In all cases the resultant peak temperatures in affected areas outside the steam tunnel were less than for the HSLB but elevated temperature durations were longer.
Existing instrumentation located in the steam tunnel together with operator surveillance is sufficient to detect and isolate a small leak (less than 10 gpm condensate) and take steps to isolate the leak before it could develop into a large break.
Note:
The temperature detectors will automatically close the main steam isolation valves immediately upon reaching the 200OF trip point and the EPCI/RCIC isolation valves after a 30 minute time delay if operator action does not isolate 'he break earlier.
Based on the above there are three limiting cases to be considered:
- 1)
Large sudden break greater than 300% KPCI flow with high flow isolation. (Run ABGQAU1)
- 2)
Small leak (HPCI/RCIC) at a maximum flow equivalent to 10 gpm condensate with 30 minute delayed isolation. (Run ABGQAFVR)
- 3)
A small leak (HPCI/RCIC/MS) that raises temperature to just below the.,high temperature trip and may not be discovered by operator surveillance for up to 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> (See SB-ST-41).
7.5.3.3 Feedwater Line Break in Steam Tunnel A feedwater line break in the steam tunnel will create a harsh environment.
However. unlike the main steam system, there is no automatic leak isolation feature (except pump runout protection) in the Feedwater System.
In fact, should a leak occur in any pipe in the steam tunnel, it is the task of the operators to evaluate the plant symptoms and take steps to isolate the leak while maintaining the plant in a safe condition.
- 1)
The feedwater leak can be isolated by components located in a mild environment.
- 2)
If the steam tunnel temperature reaches 2000 F, the MSIVs will close and a reactor scram will occur.
- 3)
Although not required to be environmentally qualified for this event, HPCI and RCIC, if available, would be utilized for shutdown purposes.
Alternatively, the ADS and core spray systems are relied upon as the qualified redundant path available for safe shutdown.
Note:
Analysis of the more restrictive MS HELB with only ADS and core spray shows that no fuel failure will occur (Reference 53).
7-17
YANKEE ATOMIC ELECTRIC COMFANt CALCULATION NO. vc - 4 C Z "R-.v o EVATrAcM4ENJTY(AGE
.ORA-+/-.
REV 5
- 4)
The steam tunnel is well isolated from other areas of the plant with vital equipment.
With a timely diagnosis and isolation of a leak, areas of the Reactor Building where vital components are loc ated should not become significantly more severe than normal for small leaks or cracks (see Section 7.5.3.4 for further discussion of the mitigation of small leaks in the steam tunnel).
- 5)
For the design bases double-ended rupture of a feedwater line in the Steam Tunnel, the resulting environmental conditions are judged to be enveloped by the Main Steam Line Break environments analyzed in Reference 28.
This judgement is based on the analysis done for the 1973/74 pipe whip study (Reference 2) which concludes that a single Main Steam Line Break in the Tunnel is more limiting than either the single Feedwater Line Break or the Combined Feedwater and Main Steam Line Break Cases.
7.5.3.4 Small Leaks in Steam Tunnel The steam tunnel is a relatively small space and any high energy-release into it will significantly raise its temperature.
A major leak would increase the' space temperature above 200OF almost instantly causing HSIV closure and resultant reactor scram.
Small leaks do not have the significance of a major leak but they have the potential of becoming a major leak.
Therefore, operator evaluation and action is mandatory.
Small leaks from any source can be classified and detected as follows:
- 1)
A small leak that initiates the high space temperature alarm of 160OF and a short time later initiates the MSIV close/scram signal at 200 0 F.
The operator would be immediately alerted by these eventi.
The HPCI/RCIC 30-minute. delay signal is also set at 200 0 F.
If HPCI or RCIC are being utilized post-scram, the operators would have 30 minutes to evaluate plant status, isolate leak, and assure a core cooling and decay heat removal path is maintained.
- 2)
A small leak that initiates the high space temperature alarm of 160 0 F, or is detected by the operator readings, but may not reach the 200OF signal.
Such a leak would be detected and isolated within 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> allowing for operator evaluation and leak isolation.
All the steam tunnel equipment required to initiate a
safe shutdown is environmentally qualified for this scenario.
- 3)
A small leak that raises the steam tunnel temperature slowly, but may not initiate the 160OF space temperature alarm.
This type of leak would be detected by the operators due to increasing space temperature readings.
Sufficient time is available for the operators to evaluate and repair or isolate since operator action' for plant safety is not imediately required and essential electrical equipment is environmentally qualified and available for plant safety action.
7.5.4 High Energy Line Break in the Turbine Buildinf Turbine, turbine auxiliary, and feedwater and heating steam piping in the Turbine Building is routed in many areas.
If a reactor safety action is 7-18
SYA*IKEE ATOMIC ELECTRIC COMPANY CALCULAION NO. vc..- 4 c-..-.
ATTACHMENT tkPAGE 4.OF I-6 REV 5 needed, all emergency systems required to safely shut down the plant, given a lons of off-site power and a single failure, are located in the Reactor Building and Diesel Generator Rooms.
For a Turbine Building HELB, a mild environment would exist in the Reactor Building.
A harsh environment would exist in the Diesel Generator Room only for a HHS HELB in the room, however, a loss of off-site power is not anticipated for this break.
The only components located in the Turbine Building that warrant environmental qualification for this event are those associated with the Reactor Protection System (RPS) and Main Steam Isolation.
These components are not required for the direct mitigation of a Turbine Building HELD, but they are important to reactor fuel integrity during certain plant transients combined with worst case single failures.
Although specific HELM analyses have not been performed for the Turbine Building, RPS and Main Steam Isolation components in the Turbine Building should be qualified to the bounding Turbine Building environmental profile (Appendix C, Figure TB-39) unless otherwise documented as an exception. This profile envelopes, with a margin, a large Main Steam line break in the steam tunnel which is quickly isolated and small leaks t.hat are isolated approximately 30 minutes after detection. Because the steam tunnel is a
significantly smaller and more confl-ned volume in comparison to the turbine building environmental conditions following a HELB in the steam tunnel are expected to be more severe than conditions in the turbine building, therefore this profile should envelope all open areas in the turbine building.
In accordance with Reference 34, certain RPS/MS isolation components in the Turbine Building were further reviewed and, on a case-by-case basis, it was determined that a specified environment of 212°F and 100% relative humidity was appropriate.
Since the Turbine Building is easily accessible, small leaks would be detected by plant personnel due to changes in the usual Turbine Building humidity, temperature, and noise levels.
7.5.5 Small Leaks in Reactor Building Other than the primary containment, the Reactor Building has five basic areas (steam tunnel, torus area, RCIC Room, BPCI Room, RWCU Rooms) that are somewhat confined and contain high energy lines which could produce a small leak.
In addition, the north side of Elevation 252' contains the RWCU return line which must also be considered.
All of the above areas have temperature sensors that provide indication to the Control Room.
This temperature data is logged daily.
Also, all of the above areas except the primary containment and steam tunnel are visually inspected by operators at least once per shift.
A small leak in the steam tunnel was discussed in 7.5.3.4.
The RWCU areas (except Elevation 252') are termed high radiation areas requiring radiation work permits for personnel access.
Qualified temperature switches were installed by Reference 33 to provide automatic RWCU isolation on high space temperature.
This temperature switch, set at 125 0F, will provide isolation of a small leak in the RWCU piping which results in a leak below the high flow isolation setpoint.
Also. as discussed above, the operators can 7-19
- YANKEE ATCMIELECTRIC COMPANY CALCULATlON NO. VYIC-4 "4Z. d Rev. 3 obtain the actual cubicle temperature remotely, from other temperature detectors which also have an alarm setpoint of 110OF or 115OF (nominal).
The HPCI cubicle and torus area are low radiation areas with unrestricted personnel access.
As discussed above, these areas are readily accessible having continuous remote temperature indication, with an alarm set at 1750F.
Operator detection of small leaks is most likely well before the space high temperature detector HPCI/RCIC alarm/isolation signal setpoint of 2000F.
The HPCI cubicle is well ventilated with a large door opening near the SW stairwell where steam could escape in to contiguous areas of the-Reactor Building.
The torus area is a large space with several hatchways and many pipe chase openings where steam could escape.
This lowers the probability that a small leak would raise the local space temperatures, to the trip setpoint of 200OF and increases the probability that the operators would discover a leak.
The RCIC cubicle is a low radiation, high security, locked room used by an operator to control the cooling of the reactor in the event of a terrorist attack.
Leak detection is by operator surveillance and remote temperature indication, including an alarm at 175 0 F, in the control room.
The space high temperature detector HPCI/RCIC alarm/isolation signal is set at 200OF for automatic isolation.
7.5.6 Other Design Basis Accidents The control rod drop and refueling accidents, as described in FSAR Sections 14.6.2 and 14.6.4, respectively, have been reviewed for environmental qualification concerns.
In both cases, the-environmental consequences are not harsh from an equipment degradation standpoint.
The oniy environmental parameter that will change is radiation.
Per Reference 0, the cumulative radiation dose for any area of the plant will not exceed 1 x 10 4R due to either of these accidents.
Since this level of radiation is considered mild for mast materials, and all components qualified for the DB LOeA environment would also be qualified for these accidents, all electrical equipment relied upon to mitigate these accidents and achieve a safe shutdown are qualified since the qualification requirements for a LOCA are satisfied.
7.6 ENVELOPE ACCIDENT ENVIRONMENTAL DESIGN DATA The following accident environmental conditions are recome-nded for procurement of new equipment important to safety.
These conditions envelope worst case accidents and should be specified for new and replacement components, as well as spare parts.
7.6.1 Reactor Building (Excluding Primary Containment. Steam Tunnel. and CRD Repair Room)
Temperature Profile:
Figure TE-l - Appendix C Pressure:
2 psig maximum for 70 seconds Humidity:
Above 212OF:
Superheated Steam Below 212 0 F:
100% RH Saturated Steam/Air Mixture 7-20
YANKEE ATOMIC ELECTRIC COMPANY CALCULATION NO. VC-4 (*7.
L ATTACIW0ENT&CrPAGkiBOf2+/-d Rev.
3 Radiation:
See Table 7.6.1 -
Appendix C Submergence:
Not applicable, large area and timely leak isolation preclude significant flooding concerns.
7.6.2 Primary Containment (Drywell and Torus)
Temperature Profile:
Above El. 264'-2":
Figure DWH-Tl -
Appendix C Below El. 264'-2":
Figure DWL-T1 -
Appendix C Pressure Profile:
Figure DW-Pl -
Appendix C Humidity.,
Dryell Above El. 239'-8" 100% (saturated steam and spray)
Below El. 239'-8" Submerged (Reference 1)
Torus Above El. 228' 100% (saturated steam, splashing, and spray)
Below El. 227' Submerged (turbulence)
Note:
Torus water level is maintained between approximately 228' and 227'.
Components near this interface range could be exposed to both conditions of submergence or saturated steam during course of event.
In addition, subsequent long-term recovery activities (e.g., removing fuel from reactor vessel) may involve flooding of the entire torus and drywell to above the top of core level, but such recovery activities are not within the scope of 10CFR50.49.
Radiation:
See Table 7.6.1 -
Appendix C Submergence:
See Humidity 7.6.3 ateaM Lmnn Temperature Profile:
STE Appendix C Pressure:
STE-41' -
Appendix C Humidity:
Above 212 0 F Superheated Steam Below 212OF : Saturated Steam / Air Mixture Radiation:
See Table 7.6.1 -
Appendix C Submergence:
Any flooding in the Steam Tunnel will be confined to below steam lines (approximately Elevation 253'-6"). See Section 7.5.3.
7-21
YA1 CAI AT, Re' 7.6.4 CRD Repair Room. and Turbine Buildina Temperature Profile:
TB-39
- Appendix C Pressure:
STE Appendix C Hunidity:
Above 212OF : Superheated Steam Below 2120F : Saturated Steam / Air Mixture Radiation:
See Table 7.6.1 - Appendix C Submergence:
In the Turbine Building the large area and timely leak detection preclude significant flooding concerns.
WKEE ATOMIC ELECTRIC COMPAM CULAVON NO. VY. -4 Gz. d
"?-V 4
- v. 4 7-22
400
[]-
__265 F- -
300 AVERAGE TEMPERATURE (OF) 200 K!
-f 232 I -
A
.1.
1 A -
100 0
20
-19.8Kzzzz VERMONT YANKEE NUCLEAR POWER STATION TIME HISTORY FOR LIMITING BREAKS IN THE STEAM TUNNEL ELEVATION 252'-6" VOLUME NO.
41 STEAM TUNNEL SEE SECTION 7.5.3.2 and TABLE 7.5.1 in Appendix B (This curve is bounding for Steam Tunnel.)
Note: The 70-1800 second portion of this curve which represents the 10gpm break contribution has a 20 OF added margin to account for uncertainties such as break size, time to isolate & condensation.
AVERAGE PRESSURE (PSIA) 18 16 I
14 20 40 60 80 I
0 I
'1 I
'i 20 100 500 1000 1800 5400 9000 60000 62800 TIME AFTER BREAK INITIATION (SECONDS)
FIGURE STE-41 C-4 M~
C, Q
-0 g
M 0
r-M
.4 n C, 34 10
-P,(q
YANKEE ATOMIC ELECTRIc COMPANY CALCULA7)OHNO. V'YC -
AT'AcHMENT 6-EYA.t2 DT1 FACILITY:
Vermont Yankee TYPE:
COMPONENT:
DESCRIPTION 9.4, Revision 7 Temperature Switch AND SERVICES:
See Section B MANUFACTURER:
MODEL/SERIAL NO.:
Fenwal, Inc.
See Section B PARAMETER:
QUALIFICATION STATUS:
Temperature Qualified REMARKS:
I
-Normal Ambient Temperature The worksheets (Tab B) of this QDR indicate that the subject switches are located in various areas outside of primary containment, including nonoccupied areas of the plant.
As specified in Volume I, Section 7.0, of the Environmental Qualification Program Manual, the maximum normal ambient temperature of these switch locations does not exceed 40 0 C (104.0OF) for various areas in the Reactor Building and 60 0 C (140.0°F) for steam tunnel and Turbine Building Heater Bay general area locations.
These average temperatures will be used as the basis of the aging analysis in Tab DA.
Accident Temperature The worst case temperature profile for any area in the Reactor Building, excluding the steam tunnel and CRD Repair Room, is shown on Figure TE-l which is reproduced on QDR Page DT3.
The worst case temperature profile for the CRD Repair Room, the steam tunnel, and the Turbine Building is shown on Figure STE-41 which is reproduced on QDR Page DT4.
Only the first hour of the accident needs to be enveloped; however, a 24-hour post-accident operability requirement has been assumed for conservatism (refer to Tab DO).
As indicated in Section X of Report PEI-TR-831200-1 (QDR Page Ci-286), the switches were LOCA/HELB tested to the profile shown in Figure 1 (QDR Page GI-299).
This profile (reproduced on QDR Page DT5) indicates a test duration of 2 days with a peak temperature in excess of 355 0 F.
As indicated in the Rockbestos LOCA profile reproduced as QDR Page DT6, the wire was subjected to peak temperatures of 3460 F. This profile indicates a test duration of 30 days.
The required temperature profiles STE-41 and TE-1 have been redrawn onto the Patel and Rockbestos test profiles (QDR DT5 and DT6).
It illustrates that the test profiles exceed the required profiles, with margin, in both severity and duration.
YANKEE ATOMIC ELECTRIC COMPANY CALCULATIONNO v', ' -4'A-V<v 0 A'rA*GM-LUEN & PAGEZ.'L-OF.._..
El QDR /NO.
9.4 RE__ SIO__ s Installation and Maintenance Requirements Fenwal Temperature Switch I.
Maintenance Requirements/Intervals This equipment does not require special maintenance/surveillance as the basis for qualification.
The manufacturer recommends that a calibration schedule with a maximum 5-year interval be instituted (see QDR Page Gl-23, Paragraph r-3.3.1).
- 2.
Replacement Requirements Not applicable.
- 3.
Storage Requirements Not applicable.
- 4.
Installation Requirements Per manufacturer's instructions.
Equipment installed under QA program assuring installation meets requirements.
YANKEE ATOMIC ELECTRIC COQMf CALCULATOtNNO. V'4W---4&£22 ATDP1IiENT-.YAGZ, 3 OF2.
DPI FACILITY:
Vermont Yankee TYPE:
COMPONENT:
DESCRIPTION 9.4, Revision 5 Temperature Switch AND SERVICES:
See Section B MANUFACTURER:
MODEL/SERIAL NO.:
Fenwal, Inc.
See Section B PARAMETER:
QUALIFICATION STATUS:
Pressure Qualified REMARKS:
As indicated in the worksheets and the EQ matrix, this equipment need only function through the first hour of a HELB (a 24-hour post-accident duration has been used for conservatism).
As indicated in the Summary Report of Plant Environmental Conditions (EQ Program Manual, Volume 1), the envelope accident pressure design data is 2 psig (70 seconds) for the Reactor Building and 5.1 psig (10 seconds) for the steam tunnel.
Testing by the Vendor indicates that the switches were tested to the pressure profiles described in Appendix X-B of Report PEI-TR-831200-1 (QDR Pages GI-297 to 01-298).
These profiles (summarized on QDR Page DP3) show that the maximum test pressure of 26 psig and the test duration envelop the pressure conditions for all areas outside primary containment.
I I
YANKEE ATOMIC ELECTRIC COMPANY CACULTMN NO. W4 - 4r(62C A J T A % W - T _L P A C *
-Z 4 71; DR2 Qo No. 9.4 REVISION 4 The basis of the radiation value required is the 40-year operating doses as indicated in Appendix A of the Vermont Yankee EQ Program Manual.
The one-hour post-accident operating time requirements are for HELBs in the Reactor Building only.
The accident radiation increases caused by a primary containment LOCA are not applicable to these switches.
Conclusion Qualified with margin.
YANKEE ATOMIC ELECTRIC COMPANy CALCULAnONNO. VYc-4(,u-_
DH1 FACILITY:
Vermont Yankee TYPE:
COMPONENT:
DESCRIPTION 9.4, Revision 2 Temperature Switch AND SERVICES:
See Section B MANUFACTURER:
MODEL/SERIAL NO.:
Fenwal, Inc.
See Section B PARAMETER:
QUALIFICATION STATUS:
Relative Humidity Qualified REMARKS:
REVIEW A 100% worst case relative humidity condition is assumed due to saturated steam conditions following an accident for the areas in which these switches are located (see worksheet. Tab B).
Vendor testing included a humidity/cycling test where the switches were cycled under rated load by subjecting them to 100% relative humidity in a controlled humidity chamber.
Refer to Report PEI-TR-831200-1, Paragraph 1-3.10 (QDR Page Gl-31), and Report Section XI (QDR Page GI-305).
The Vendor also performed the LOCA/HELB test under-, both superheated steam conditions and saturated steam conditions.
Refer to Report PEI-TR-831200-1, Paragraph X-1.0 (QDR Page Gl-286).
In addition, the NRC has recently reached the same conclusion as industry
- that, it has not been demonstrated that the time-dependent variation in humidity will produce any differences in degradation of electric equipment as stated in comments to 10CF 50.49" (Federal Register, Volume 48, No.
15, Page 2732. Comments).
Furthermore, the rule itself (10CFR5O.49(e)(2)I states, humidity during design basis accidents must be considered."
As indicated above, the accident simulation profiles include a steam environment that meets I
the new rule requirements.
Conclusion Qualified for 100% relative humidity.
I YA4,(EE ATOMIC ELECTRIC COMPANy CALCLLATnONNO. VY*- 46z.c.
DC1 FACILITY:
Vermont Yankee TYPE:
COMPONENT:
DESCRIPTION 9.4, Revision 2 Temperature Switch AND SERVICES:
See Section B MANUFACTURER:
MODEL/SERIAL NO.:
Fenwal, Inc.
See Section B PARAMETER:
QUALIFICATION STATUS:
Chemical Spray Not Applicable REMARKS:
REVIEW The switches are located outside of primary containment and are not subject to chemical spray or demineralized water spray.
This parameter is therefore not applicable.
Conclusion Not applicable.
YANKEE ATOMIC ELECTRIC COMPANY CALCULATIONNO. Vv-4467,.
DR1 FACILITY:
Vermont Yankee TYPE:
COMPONENT:
DESCRIPTION 9.4, Revision 4 Temperature Switch AND SERVICES:
See Section B MANUFACTURER:
MODEL/SERIAL NO.:
Fenwal, Inc.
See Section B PARAMETER:
QUALIFICATION STATUS:
Radiation Qualified REMARKS:
REVIEW As indicated in the worksheets, the required worst case integrated radiation dose for these temperature switches must be 3.5'x 106 rads.
The Vendor's test documentation includes qualification for accident conditions to 5.0 x 107 rads (refer to Report PEI-TR-831200-1, Paragraph 1-3.8 (QDR Page G1-29); and Paragraph IX-3.0 (QDR Page G1-277); and certification by Georgia Institute of Technology, QDR Page GI-283.
I The metallic outer shell of the switches (see Paragraph 1-1.3 of Vendor's report. ODR Page G1-11) protects them from degradation due to beta radiation.
Therefore, the qualification margin is:
Margin a (Capability - Requirement)/Requirement x 100%
= (5.0 x 107 -
3.5 x 106)/3.5 x 106 x 100%
I
= 1,328%
YANKEE ATOMIC ELECTRIC COMPANY CALCULAON NO. VYL-44e.
0 ATTAC'PEJT&JPAGEZ-ei _(F~
DP2 QDR NO, 9.4 REVISIro 4
(note:
Only the first hour of the accident conditions need to be enveloped.)
Therefore, the switches are qualified with significant margin.
Conclusion Qualified for this parameter.
YANKEE ATOMIC ELECTRIC COMPANY CALCULATION NO. Vi(-- 4 U
ATTACHMEN1T&Pj3 o
E2 QDR NO.
9.4 REVISION 5 Review of Equipment Cable/Racewy Interface Sealing Requirements PROJECT:
QDR NO.:
COMPONENT:
MANUFACTURER:
MODEL/SERIAL NO:
Vermont Yankee Nuclear Power Plant 9.4 Temperature Switch Fenwal, Inc.
01-170020-090 (NC) and 01-170230-090 (NO)
I SPECIAL SEALING REQUIRED:
Yes X
No REMARKS These switches are specifically procured and designed for detection of high energy line breaks outside containment.
The switches come complete with seals and pigtails and have been tested and qualified to peak temperatures (e.g.,
355 0 F) and pressures (e.g.,
26 psi&) which far exceed the Vermont Yankee requirements.
i
YANKEE ATOMIC ELECTRIC COMPANY CALCULAIONNO. V.L-4*,...c.
DT2 QDR NO.
9.4 REVISION 5 A close review of the vendor tests indicate that the temperature rise times to not envelop the rise times indicated in Figures STE-41 and TE-l.
However, due to the severity and duration of the vendor tests, the effects of heat rise time is considered negligible.
Conclusion Qualified with significant margin for post-accident temperatures and duration.
As indicated in theRockbestos LOCA profile reproduced as QDR Page DT6, the wire was subjected to peak temperatures of 3460F. This profile indicates a test duration of 30 days.
YANKEE ATOMIC ELECTRIC COMpAM CALCULAM.io.VYL -4 6,.c Interoffice Memorandum TO:
FILE FROM:
John Lewis RE:
Changes to VYC-1599 Rev. 0 (Drift Calculation for Fenwal Temperature Switches Modes 01-170020(230))
DATE:
September 8, 1997 VYC-1599 Was reviewed to determine the impact of the non-conservative method used to eliminate outliers from the sample pool(s). The changes are as follows:
- 1.
Replace page 12 of 20 In the body of the callmatlon due to additional sample
=es In Table 3 -
Critical Values For t-est.
- 2.
Replace pages 1, 5, 6 & 7 of Attachment 2 to reflect the OP-4358 re-run of outlier tests on the stittistis The changes do not affect the outcome of the calculation due to the data being combined with data from OP-4370 in Attachment 4. The combination of OP-4358 and 4370 exceeded 150 points that kept the orginal outlier test of Attachment 4 conservatie.
The changes in Attachment 2 of VYC-1599 do warrant an immediate revision to the calculation. VYC-1599 Is used as the software validation baseline for the use of Microsoft Excel in the drift calculations. Manual verification of the outliers or lack there of will eliminate the need to re-run the base line.
CC:
George Hengerle From the desk of:
Jam JEL LWIS 1&C gineer Y(802 (CS-5
YANKEE ATOMIC ELECTRIC COMPANJ CALCULATION NO. VYM - 4 z.c.-
-PW
ýO-Lvo Drift Calculation For Fenwal Temperature Switches Models 01-170020(230)
VYC-1599 Rev.)
Approval Reason & Description of Change No.
Date I
0 Initial Issue.
VYC.-1599 was reviewed to detenmine the Impact of the non-conservative MehOW used to ellmnate outliers from the sample pool(s). The changes are as follows:
- 1.
Update Table 3 - Critical Values Fort-Test. page 12 of 20 In the body of the calculation.
- 2.
Replace pages 1. 5. 86 & 7 0f Attachment 2 to reflect the OP-4358 re-run of outlier tests on the statistics.
Yankee Nuclear Services Page 3 of 20 Yankee Nuclear Services Page 3 of20
YANKEE ATOMIC ELECTRIC COMPANY CALCUlATION NO.VYL - 4(6z.d.
ATIAOI-IM 2An Drift Calculation For Fenwal Temperature Switches Models 01-170020(230)
VYC-1599 2.4.7 Outlier tests were performed on the data until either 5% of the original sample was expelled or no other outliers were detected.
Table 3 - Critical Values For t-Test A-91e47-Upeir
-5%ASU,*
4-914613e
,Upe8 rS*
guka=,a S
,md plefS Upp-SIA S9cewe 3
3.15 16 244 45 2392 4
lA4 17 2.47 30 216 1.67 Is 2.15 60 3.03 S
3t2 19 2.53 70 3.09 7
1.94 20
.L2.5 75 3.1 8
2.03 21 2.58 80 3.14 9
2.33 22 2.6 90 3.18 I0 2.38 23 2.62 100 3.21 11 2.23 24 2.64 125 3.28 12 2.29 23 2.66 150 3.33 133 2.33 30 2.7.
>10 "4.00 14 2.37 33 2.82 135 2.41 40 2.87 2.4 Pooling the Drift Data Note: Refer to the 'Vermont Yankee Instrument Drift Analysis Design Guide" for methodology used in this section.
(Ref. 6.11 2.4.1 The standard deviations and variances of the various sub-groups were evaluated to determine the data's suitability for combining.
2.4.2 The model numbers, spans and setpoints listed in Table I (Equipment Summary) were evaluated to determine the suitability for combining the data.
2.4.3 A t-Test as.uming unequal variances was performed on all potential groupings using the following equation In Microsoft Excel:
'=
0 V 1 11 (All. 21
[Aft. 3]
Where;
- test statistic n
- Total number of data points.
x
- Mean of the samples.
s2
- Pooled vadance 0
- Hypothesized mean difference.
[Ref. 6.1 & 6.61 2,4.3.1 The test performs a two-sample student's t-test which assumes that the variances of both ranges of data are unequal and is referred to as a heteroscedastic t-test. This t4est is used to determine whether two sample means are equal and when the groups under study are distinct.
Yankee Nuclear Services Page 12 of 20
YANKEE ATOMIC ELECTRIC GOMPAN CALCULATKON NO PyL -4.(c-A -c*Vo ORIGINAL:
PAGE I OF..20_ PAGES 7-3
/Re 1: PAGE I OF-PAGES 7V ii Rev 2: PAGE I OF PAGES 7.X
/'S Rev 3: PAGE I OF.
PAGES QA REI&D?
IM/So.
YES RECORDTYPE
/-f 02 1.-
5 NO W.O. / P.O. NO.
4994 YANKLd, NUCLEAR SERVICES DIVISION CALCULATION/ANALYSIS FOR TITLE DRIFTICALInILATION FOR FENWAL TEMP SW MODELS 0I-170020-090 & OI-170230)090" CYCLE le'lo9 ow-PLANT VERMONT YANKEE CALCULATJON NUMBER VYC-1599 ArrKuvw UT aurcJ~ac.ueo '-J*u-'-.
PREJPARiJ.U BY MAITM Kb*VIJ*WUJ Y
A.PP."IKUV E:l~lIrI
/RE'V. NO.
ORIGINAL I. It Lewis 2A79*7 0J..
2gakIV3i R.T. Vib0wt'
___1_7_
REVISION I REVISION 2 REVISION 3 KEYWORDS:
INSTRUMENTS:
DESIGN DOCS:
MODELS:
T/S or FSARI PROCEDURES:
RWC¶J/M*lH CWCI f*f efmDnon/*alcu~lnrlon/TMahvRfd TS-12-101-103A. B, 106-112A- & T&I3479-82A--DfTS-2-12-124A-D None Fenwal101-170020090 & 01-170230-090 TS Table 3-21. FSAR 7.4.7.3-7,IA.715. 7.4 OP-4322-OP-4359, OP-4366 and OP-4370 FORM WE-103-1 Revision 2 WE-103-20
ANKEE ATOMIC ELLXEC I
(0MPAIN?
..ALCULATION 'o. VYCI -
Z WV 0 Drift Calculation For Fenwal Temperature Switches Models 01-170020(230)
VYC-1599.
CALCULATION OBJECTIVES This calculation documents the drift analysis pedormed on the Fenwal Temperature Switches at Vermont Yankee for the Steam Leak Detection System of the Main Steam Unes, HPCI Steam Line, RCIC Steam Unes and RWCU Areas. This calculation has been developed in support of the Vermont Yankee Improved Technical Specifications Project with the following major objectives:
Detenndne the drift characteristics for the Fenwal Model 01-170020-090 &
01-170230-090 temperature switches listed In Table 1(Equipment Summary).
Document the analyses performed on the components In accordance with the "Vermont Yankee Instrument Drift Analysis Design Guide.,
(Re(. 6.11 Provide the standard deviation, variance, 95%/95% Tolerance Interval Factors (TIF) for the device groups covered.
Evaluate the data for normality, tirre dependency and provide the 95%/95%
Analyzed Drift Term (ADR) for the components covered in this calculation.
1.1 Systems & Components This calculation applies to the Main Steam Line, HPCI Steam Line, RCIC Steam Une and RWCU Space steam leak detec temperature swiches.
The specific components addressed are listed below in the equipinent summary table.
TABLE 1 -Equipment Summary 12~101A ~2J Ln.1470230-M0 1001212*'fDC 51 7
52209 O
LkDde~~d~m Iri 70 12.23A ft.ULS
. iO12 =
41Ari0*,
I 21DC TS-2M06 IRWCU Sto&
2aDdecdagSr j 1
17230 03-60040 1201D24C.
T-2-106A IRWC*J Leak[
2140230490 1004001 1201DEC 51 7
r 12-1079 A IL eA 01.r702304M 10040 12-V FDC 5(2 Fea wa0 1-1702304-0 2000*0" 12013DC S
TM34-104 Finwdk 01 17023009 100400 1201DC 1
-47 TS149 Sridak Pentl127023049 0"W 0401 2201DC ST 47 Ts'lg A DPcswd 01470230-09 1004001 2201 DEC SI P.07 M1-10 1r ewl02-17023009 0040 LWR 51 57 mmi2A!lS.2l r
Pnu 1-170230409 1040VP08C 5
T2-2-112A MAW=J StnLa de1o52Fiw 220349'2060 12(r1NC SIT 7
M IAMI RCIC Si uk3aa Si Pum
@120*
0 00 01 4lIM DC 51 3
3.79 R~ISM.
Lesk Detdudw Panu 170230.09 1.)040 235i DEC 57F Yankee Nuclear Services Paae 4 of 20
YANKEE ATOMIC ELECTRIC COMPANY CALCULATMON NO. v,/. -. 4(,.-
ATrPAlHMENAt 4PAGEj..A Drift Calculatlon For Fenwal Temperature Switches Models 01-170020(230)
VYC-1599 rs lrs In 1-134WAO Q
W.$l a
I1E IMANUF CE 1vD on Lei* Dgeaftet W L,& Dftaem Iftno~w 1,II4IC ROC MIF=.d QI 13
- I, lI.Il PI.7U3049 "t470=4 I
3.
0 I5r4 il m
MS~
~I04OO~
~-)I0o.4orp
',13-=
IRCC meek Ddintkin
-170230490 Ii 4-I-8 IhaC w Lciý DcOdo
'a 14A daca~mi M LU* Dosed=
= Link 0Dde M &d~o 1004WF
.s~zaem IW.)O
"-o at It It it It lit It Is, ii IRS ii3 Ti~
ii~
'35 ru am, t~* ~ar 16W Ms FR 1, '
Mac t'"
PR4C I* rI W43" I-MaNc 1*5 Mi!:f FMc t*57*
P-43" W
I INC I5,y FINC 1*57 P.4322 P-4322 121D IMS
-427A4 tM I..~
.470020490 1(41004007
'57 i
.£.,-* M na Linki Now~
b490 I(MOO4OVF 48 a LAnk Ddegia R490 P1
~322 iS Vinwd
%4M?2
~-23C 3.123D 3.1248 Is 24240 23-IOtA 23-1013 117(1 23-1010 117(1 U-tOlD
~34*38
.wa 13-102C 1170 13-1028 100 1(41004007 af Lea0000e
'a
,PII4C rF
-4322
$7 57 57 5?
57 5F 58 57
.4358 57 S.,
sly S.,
S.,
S.F IL!!
13-10,M Pa S49O~~~
1(4tO~.6OOY WINC 4358 Sem to& kDmdim VCo
.ot I
~3-lf3JC a
15-103D I1' Rc:aI
-1M702, W
,) K)1004007 I3-IO4A 13-104B I3-104*
- i*,
lo, 4702304M0 i0 ILU 7lM.~
.435t 4Mt L4353i
=
ni 1.2 Instrument Loop Function (Abbreviated) 1.2.1 The temperature switches covered by OP-4322 monitor the Main Steam Une Areas for high temperatures caused by steam leaks (Setpolnt 185"F Increasing). High temperature in the Main Steam Une Areas provides Inputs Into the Primary Containment Group I Isolation circuitry.
Yankee Nuclear Services Page 5 of 20
IVItKEE ATOMIC ELECTRIC COMPANY CALCULmAnONNO Yic..--4ft.Z.
U-L__m Drift Calculation For Fenwal Temperature Switches Models 01-170020(230)
VYC-1599 1.2.2 The temperature switches covered by OP-4358 monitor the HPCI Steam Une Areas for high temperature caused by steam leaks (Selpoint 185"F Increasing). High temperature In the HPCI Steam Une Areas provides an automatic Isolati6n signal to the HPCI Steam Line Isolation Valves.
1.2.3 The temperature switches covered by OP-4366 monitor the RCIC Steam Line Areas for high temperature caused by steam leaks (Setpoint 185"F Increasing). High temperature In the RCIC Steam Une Areas provides an automatic Isolation signal to the RCIC Steam Une Isolation Valves.
1.2.4 The temperature switches covered by OP-4370 monitor the RWCU Steam Une Areas for high temperature caused by steam leaks (Setpoint 120°F Increasing). High temperature In the RWCU Steam Une Areas provides an automatic Isolation signal to the RWCU Steam Line Isolation Valves.
1.3 Governing Procedures And Programs 1.3.1 Vermont Yankee Instrument Drift'Analysis Design Guide, Rev. 0.
(Ref. 6.11 1.3.2 Vermont Yankee Instrument Uncertainty and Selpoints Design Guide, Rev. 0.
(Ref. 6.21 1.3.3 Yankee huclear Services Engineering Instruction, WE-103, Rev. 15, Analyses and Calculations,'
(Ref. 6.31 1.3.4 Vermont Yankee Engineering Procedure, AP-0017, Rev. 4, Calculations and Analyses.
(Ref. 6.41 1.3.5 Yankee Nuclear Services Engineering Instruction, WE-108, Rev. 5, Computer Codes.
[Ref. 6.51 2
METHOD OF SOLUTION This calculation has been prepared in accordance with the Governing Procedures and Programs listed In step 1.3. Standard methods employed in this calculation are explained In the "Veiriont Yankee Instrument Drift Analysis Design Gulde, an overview of the methodology Is explained below.
(Rel. 6.11 2.1 Data Entry and Determination of Drift Values 2.1.1 Calibration data was collected from the applicable Surveillance Test for the components listed In Table 1 (Equipment Summary).
2.1.2 The data was then entered into Microsoft Excel Spreadsheets titled after the Surveillance Test (e.g. OP4322.XLS) noting any discrepancies found with the data (e.g. As Found out of tolerance, illegible data, etc.).
(Att. 11 Yankee Nuclear Services Page 6 of 20
YANKEE ATOMIC ELECTRIC COMPAt CALCULATION NO VYC-i
- 4 ATTACH ejrA-PAGE 8OF~j7 Drift Calculation For Fenwal Temperature Switches Models 01-170020(230)
VYC-1599 4.1.2 A change In setpoint was made in OP-4370 between 1987-1989 and the calibration data for all components in that time frame was expelled from the pool.
[AiL 11 4.2 Statistics Calculations 4.2.1 The statistics calculation for each surveillance test and the grouped components Is documented in Attachments 2 and 4.
[Alt 2 & 4]
4.2.2 The TIF used in 'his analysis is for a 95*/%195% level of confidence and Is listed In Tab:e 4 (Statistical Summary) for each surveillance test and the grouped data.
4.2.3 The Analyzed Drift value Is listed In Table 4 (Statistical Summary) for each surveillance test and the grouped data.
4.2.4 The statistics summary for each surveillance test and the two groupings can be found In Table 4 (Statistical Summary) and at the beginning of Attachments 2 and 4.
[AM. 2 & 41 4.3 Plots 4.3.1 The XY scatter plots. Regression lines. Histograms and Probability plots used for determining the characteristics of the data are contained In Attachment 5 for Group OP-4322 & 66 and Attachment 6 for Group OP-4358 & 70 Itn 5 & 6e 4.32. The plot statistics are located at the end of the plot groups-in Attachments 5 & 6.
[Al. 5& 6 5
RESULTS AND CONCLUSIONS 5.1 Groupings 5.1.1 Refer to Table 4 (Statistical Summary) for the summary of the statistical analysis for each surveillance and the resulting groupings.
5.1.2 The data from OP-4322 and OP-4366 was able to be pooled Into one group due to the components passing the t-Test performed.in step 2.4.3. having the same ranges, similar model numbers, same setpoints and essentially equal standard deviations and variances.
Refer to Table I (Equipment Summary) for component information and Table 4 (Statistical Summary) for statistical Information.
[Att. 31 5.1.2.1 The pooled data provides a group. of 209 sample points with a standard deviation of 0.502% 6f span with an average time interval of 544 days. As discussed in Section 3 of this calculation a 95%/95% TIF will be applied to the standard deviation for the group which equates to an ADR term of 1.077% of span (7.54°F). Refer to Table 4 (Statistical Summary).
Yankee Nuclear ServIces Page 17 of 20 Yankee Nuclear Services Page 17 of 20
"AiNC, IT;-
' " ELECTIj4G COMPANY CALC(ILATION NO. "lc.- -
.z--
AKriACHMEN r1 14 PAC-i~C*:A2)Fr(
Drift Calculation For Fenwal Temperature Switches Models 01-170020(230)
VYC-1599 5.1.3 The data from OP-4358 and OP-4370 was able to be pooled into one group due to the components passing the t-Test performed In step 2.4.3. having the same ranges, same model numbers, similar setpoints and essentially equal standard deviations and variances.
Refer to Table I (Equipment Summary) for component information and Table 2 (Statistical Summary) for statistical Information.
MAt 3]
5.1.3.1 The pooled data provides a group of 199 sample points with a standard deviation of 0.648% of span with an average time interval of 775 days. As discussed in Section 3 of this calculation a 95%/95% TIF will be o.pried to the standard deviation for the group which equates to an ADR term of 1.391% of span (9.74"F). Refer to Table 4 (Statistical Summary).
5.2 Time Dependency 5.2.1 Group OP-4322 and OP-4366 As seen from the.XY Scatter plots, Regression lines and Regression statistics in Attachment 5 it can be concluded that the data is evenly distributed about zero with a slope on the time dependency line equivalent to < 0.2 % / -50 days.
[At. 5]
5.2.2 Group OP-4358 and OP-4370 As seen from the XY Scatter plots, Regression lines and Regression statistics In Attachment 6 it can be concluded that the data is evenly distributed about zero with a slope on the time dependency line equivalent to < 0.3 % /-2000 days.
[AtL 6]
5.3 Normality 5.3.1 Group OP-4322 and OP-4366 As seen from the Probability plots, Probability statistics and Histogram in Attachment 5 it can be concluded that the data is normally distributed with a highly peaked narrow distribution.
[Alt 5]
5.3.2 Group OP-4358 and OP-4370 As seen from the Probability plots, Probability statistics and Histogram in Attachment 6 it can be concluded that the data Is normally distnrbuted with a highly peaked narrow distribution.
(At. 61 Yankee Nuclear Services Page 18 of 20 Yankee Nuclear Services Page 18 of 20
YANKEE ATOMIC ELECTRIC COMPAN.
CALCU'ATIONNO. IC..-4 Z.E-ATrACMENTAiPA Drift Calculation For Fenwal Temperature Switches Models 01-170020(230)
VYC-1599 5.4 Summary The data contained Is normally distributed, showing little time dependency and is acceptable for use In Setpolnt/Uncertainty calculations. The 95%/95% ADR value Is:
5.4.1 Group OP-4322 and OP-4366 = 1.077% of Span (7.54°F).
5.4.2 Group OP-4358 and OP-4370 = 1.391% of Span (9.74°F).
TABLE 4 - Statistical Summary OP4322 OP4358 OP436*
OP4370 OP4370 Group OP4323 Group OP4358 Sotpoint Racsc
&6
& 70 11NT 333 110 95 44 43 209 199 VERAGE
-0.014%
-0.065%
00hl%
-0.071%
-0.021%
0.008%
- 4083%
EV 0.543%
0.607%
0.425%
0.640%
0.605%
0.502%
0.648%
ARIANCE 0.003%
0.004%
0.002%
0.004%
0.004%
0.003%
0.004%
EURT 0.347 3.658 0.173 0.758 0.221 0.627 1.599 4RIOMS.S
-0.118
-0.248
-0.1350 0.072 038 I
.038
-0.349 1.457%
3957%
0.929%
1.400%
1.571%
1.571%
1.9S7%
-1.600%
-2.100%
-1.143%
-I.786%
1.337%
-. 600%
-2.400%
STIF 2.218 2.218 2.241 2.445 2.445 2.143 2.148 DLyV x 9"5J9 TIF 1.204%
1347%
0*953%
165%
.4I78%
1.077%
1.391%
UNIS oF 843 9.43 6.60 10.5 10.35 7.54 9.74 OF ORIGiNAL 99.12%
99.10%
98.96%
100.00%
97.73%
)9-52%
100.00%
Yankee Nuclear Services Page 19 of 20
Drift C,.. -.uion For Fevrwal TS Models 01-170020(230)-090
,-1599 XY Scaer (Raw) - Group OP4322 & 66 Attacbmenz 5 XY Scatter - Fenwal Temperature Switch Group OP4322 & 66 2.000%
1.500%
1.000%.:
t*4 0.000%
l I
l a
100 200 300 400 S 00 f* $1'$ 600
-40 5W
-I.000%
-4}.500%*
9 40
-.1.O0%
4
-2.000%
ftrWa,-.Days
Q C4 q-ý Q>.10 O>
zZrI Drift OCaauadon Por Fenwal TS Models 01-170020(230)-MgO XY Scatter (Abs Value) - Group OP4322 & 66 v C-1599 AnadMefde 5
XY Scatter (Absolute Value) - Fenwall Temperature Switch Group OP4322 & 66 1.600%
1.400%
1.200%
0
- 4 1.000%
0.800%
0.600%
F.
.i.
9 *9 9
9
- .M.
.1*
~.1!
.4.
10%dI VbgV-0.400% +
0.200% +
0.000%
0 100 200 1
.300 Interal - Days I
400 500 600 Yankee Nuclear Services FENGRP.XLS
Did "-dad For en:wal TS Modtb 01-170020(230)-090 Raw Regression - Grup 0P4322 & 66 Regression Line (Raw Data) - Fenwal Temperature Switch Group OP4322 & 66
. X-1599 Auacbmnt 5 2.000%
1.500%-
1.000% +
0.500%
lot$
0.000%
I I
I I
I I
[
100 200
-0.500% -
300 400 Mo 600 t*
S
%DdA 700
-Pndieted
-i.000% -
4
-1.500%
-2.000% L Interv. Days L"Myr-ID01 VT C 6...
¶.2
- f,
Drift C~adution For Fenwal TS Models 01-170020(230-090 Abs Val Regression - Group OP4322 & 66 Regression Line (Asolute Value) - Fenwal Temperature Switch Group OP4322 & 66 1.600%
0 II 1.400%
1.200%
1.000%
0.800%
0,600%
0.400%
0.200%
0.000%
- ~
4'
- S.
p.
L
, iC-1599 Auachmex 5
%Ddt (Abe Vid
-Adia S Ddft (AM ala) 0 100 200 300
.400 Intaval -Days 500 600 700 P1lWGrRP I.XLS A -Ir I C
Drift Cha For Penwal "IS Models 01-170020(230)-090 Cumuladve Probability - Group OP4322 & 66 Cumulative Probability Plot - Fenwal Temperature Switch Group OP4322 & 66
, 4C-1599 Atacb-cut 5 140 120 100 80 60 UQ ProbdbIit
-2.000%
-0.500%
0.400%
1.000%
1.500%
2.000%
-20
-60
% Dr~ft WV OfVT c 1-1
.1
Drift C... iadon For Penwul TS Models 01.170020C230)-90
- -1599 Nomalized Prombblity. Group OP4322 & 66 A=uaCnm= 5 Normalized Probabilty Plot -Fenwal Temperature Switch Group OP4322 & 66 4.0 3.0 2.0 1.0
-2.000%
-1.500%
-1.000%
-0.500%
0.500%
1.000%
1.500%
2.000%
- 000S1DEV 4 /
-2.0
-4.0
% DriM Yankee Nuclear Services FMNOVI.)CLS Ae6 of1'
0 0I-Drift C ion For Fenwal TS Models 01-170020(230)-090 Histora-Grup 0P4322 & 66 Histogram - Fenwal Temperature Switch Group OP4322 & 66 1 I(C-1599 Attacbment 5 70 60, 50 40 30 N
10 0
II l
0.000W-I 0.0
-1.600%
-1.200%
-0.800%
-0.400%
0.000%
0.400%
0.800%
1.200%
1.600%
Bin
)
WYNPS TABLE 3.2.2 (Cont ' d)
REACTOR-CORA ZEIS=10t COOLINO SYSTD4 !SOLATION INSTRUMENTATION Minimum Number of Operable Instrument Channels per Trip 2
1 2 per set of 4 4 tNote 5) 1 I.
1.
Triv Punctlon Main Steam Line Tunnel Te**rature Time Delay (13A-K41)
(13A-K42)
High Steam Line Space Temperature High Steam Line d/p (Steam Line Break)
Low Steam Supply Pressure Bus POWr Monitor Trip System Logic Time Delay (13A-K7)
(13A-K31)
Tr]ip Level Sotting
_2120P
<3S minutes
- 212oF
<19S inches of water Z5O paig 3< t <7 seconds Required Action When Minimum Conditions for Operation are not Satisfied (Note 2)
Note, 3 Note 3 Note 3 Note 3 Note 3 Note 3 Note 3 Note 3 i
)
VYNPS TABLE 4.2. 2 (Cont Id)
)4fIXUM TEST AMD CALIBRATON FREOOENCIBS REACrog CORIE ISOLATIOti COOLMN EYTM ISO1&T10N -INSTRMENATION
.-Trip Function Main Steam Line Tunnel Temperature High Steam Line Space Temperature
.High Steam Line d/p including time delay relays (Steam Line Break)
Low RCIC Steam Supply Pressure Bus Power Monitor Trip System Logic b'unctional Test (8)
(Note 1)
(Note 1)
(Note 1)
(Note 1)
(Note 1)
Once/operating cycle Calibration(S)
Each refueling outage Each refueling outage Every three months Every three months None Once/operating cycle (Note 3)
Instrument Check Once each day Amendment No. 64, 64. 4.". i44. 111
YAEXAAGrOEjMajpi A ITbO W VYNPS RHRs reactor shutdown cooling supply Dry-1l equipment drain discharge Drywall floor drain discharge
,Traversing 4nore probe tubes Drywell purge inlet Drywall. and suppression chamber purge suipply RUR drywall spray Suppression chamber spray suppression chamber cooling and spray Containment air coupressor suction Containment Air Sample System Drywall purge and vent outlet Suppression chamber purge and vent outlet Drywell and suppression chamber main exhaust Drywell makeup Drywell and suppression chamber makeup Suppression chamber. exhaust valve bypass suppression chamber purge inlet Suppression chamber makeup 2)-rwall exhaust valve bypass Reactor Duilding
- tilati inlet nd e t
RUM discharge to radwaste*
The primary cocta.Lmnt. high pressure isolation setting was selected to be an low as possible without imdnci spurious isolation trips.
- 7.
RCXC Equipment Righ Temperature (Table 7.3.1, Signal K)
A High temerature in the vicinity of the HCIC equipment could indicate a break in the I*IC steam line.
The automatic closure of the RCIC steam line valves prevents the excessive loss of reactor coolant and the release of significant amounts of radioactive material from the nuclear system process barrier.
When high temperature occurs near the RCZC equipment, the RCIC turbine steam line is isolated.
The high temperature isolating setting was selected far enough above anticipated normal RCIC System operational levels to avoid spurious operation, but low enough to provide timely detection of an RCIC turbine steam line break.
This
"/7 3-17 Reis.. ion 12
YAWME ATOMIC 1TRC A Y signal has nonfail-safe logic.
The high teeerature isolation initiation circuitry is designed to meet the intent of 133 279 criteria.
- a.
WCC Turbine nigh Steam-,low (Table 7.3.1, Signal X)
RCZC turbine high steam flow could Indicate a break in the RCZC turbine steam line., The automatic closure of the RCrC steam line valves prevents the excessive loss of reactor coolant and the release of significant amounts of radioactive materials fr the nuclear system process barrier.
Upon detection of RCIC turbine high steam flow, the RIFC turbine steam line is isolated.
The high steam flow trip setting was selected high enough to avoid spurious isolation yet low enough to provide timely detection of a RCIC turbine steam line break.
A time'delay is introduced in the isolation logic to prevent isolation due to differential pressure spikes that occur during startup.
The logic arrangen t used for this function is shown in Figure 7.3-Sb and is en exception to the usual logic requirement because high steam flow is the second method of detecting an RCZC turbine steam line break.
I 9.
=CIC Trbi=e Steam Line Low Pressure (Table 7.3.2. Signal K)
= IC turbine steam line low pressure is used to automatically laose the PMo StOam suplY isolaton v'alves iLA the RMC tUine steam LIM so that steam and radioactive gases will not escape from the F=C turbine shaft seals into the Reactor Building after steam pressure has decre*sed to such a low value that the turbine cannot be operated.
The isolation setpoint is chosen at a pressure below that at which the RCMC turbine can operate effectively.
- 10.
PCX Eouiment Space ttih Temper*a*ue (Table 7.3.1, Signal L)
High temperature in the vicinity of the HPCI equipment could indicate a break in the HFCI turbine steam line.
The automatic closure of certain Class A valves prevents the excessive loss of reactor coolant and the release of significant amounts of radioactive material from the nuclear system process barrier.
When high temperature occurs near the HPCZ equipment, the HPCI turbine steam supply line is isolated.
The high temperature isolation setting was selected far enough above anticipated 7.3-18 Revision 12
WJ ME ATOMI E CTJ CQA0A provides the input signal for the 40t rated flow PCZS input whenever the Reactor Mode Switch (RWO) in out of RON.
S.
Main steam line low pressure is sensed by four pressure switches which sense pressure downstream of the outboard main a~s*o isolation valves..
The sensing point is located at the header that connects the four steam lines upstream to the turbine stop valves.
Each switch is part of an independent channcl.
Each channel provides a signal to one isolation Logic.
The N!L low pressure trip signals are bypassed with the reactor mode switch out of the MRU mode.
- 6.
Primary containment pressure is monitored by four pressure transmitters which are mounted on instrument racks outside the drywell.
Pipes that terminate in the Reactor Building connect the transmitters with the drywell interior.
Each transmitter is connected to an electronic trip unit which provides the trip.
Cables are routed from the trip unit to the Main control Room.
The instruments are electrically grouped in pairs, physically separated, and electrically connected to the Isolation Control System so that no single event will prevent isolation due to primary containment high pressure.
- 7.
High teoperature in the vicinity of the V=C equipment is sensed by four sets of four bimetallic teerature switches.
Each set is arranged as two trip system.
Each trip system receives Invut signals from two teiarature trip channels.
both trip systm mst trip to initiate isolation.
Figure 7.3-6 illustrates the arrangement.
- 8.
High flow in the RCIC turbine steam lia is sensed by two differential pressure switches which monitor the differential pressure across elbow taps installed in the RCIC turbine stem supply pipeline.
The arrangement is illustrated in Figure 7.3-10.
The tripping of either trip channel initiates isolation of the RCIZC turbine steam line.
This is an exception to the usual channel arrangement.
The reason for the exception was given in the discussion of the RCIC turbine high steam flow isolation function.
Keylock test switches are provided to block operation of the isolation valves as a result of testing the differential pressure switches.
P.
Low pressure in the RCIC turbine steam line is sensed by four pressure switches from the RCIC turbine steam line upstream of the isolation 7.3-24 Revision 12
I YAM-AroAgcacm-fco AITACý vmwFS TABLE 7.3.2 0
00--
'f k---.C4 -AJt+/-Lf
.'f~l.-l 0XOL.
Isolation SFunction Reactor Vessel Low Water Level Trip T
Z17 inches above top of enriched fuel Level Transmitter Level Transmitter Reactor Vessel Low-Low Water Level Main Steam Line
- igh Radiation Main Steam Line Space High Temea.ature Radiation
-Monitor Temperature switch
+/-3.3% °in.
t3*.3% in.
Not Applicable
+/-120?
+/-2.4 paid
+/-L1.2 paid
+/-t20 psig
+/-.05 psig
>82.S iaches above top of enrize*d fuel
<13 times normal background at rated power 2120r
<140% in RUN mode. and
.40% in all modes but RUN main Steen. Line High Flow Differential Pressure Transmitter/
Electronic Trip unit Main Steam Line Low Pressure Primary Containment Nigh Pressure RCXC Turbine Ste*m Line Space High Tmerature Pressure Switch Pressure Tranttar/
Electronic Trip unitI Temperature Switch
.te0 psig a-.5 psig
.12120?
RCIC Turbine Differential Steam Line High Flow Pressure Switch RCIC Turbine Pressure Switch Steam Line Low Pressure
+/-g in. N.c.
<l9S inches* W.C.
+/-1 psig z50 psig
,3 S519.000 lb/hr Revision 12
MEMORANDUM AaTA M=
~
CMATMx~io 1.O~ye -46Z e-YANKEE ATOMIC - BOLTON 1icv o To: File Date:
April 25, 1997 Group #: WI 37/97 a From: G.J. Hengerle WO#: 4894
Subject:
Improved Setpoint Program/CTS v.s. ITS IMS #:
Setpoint Evaluation File #: s-ETrrA,1248A
References:
- a.
Vermont Yankee Setpoint Design Guide (Draft)
Background:
The Vermont Yankee Setpoint Design Guide (reference a) addresses the manner in which setpoints should be determined. However, additional guidance Is needed to clarify the manner In which the Custom Technical Specification (CTS) evaluation and Improved Technical Specification evaluations should be conducted. The manner In which this issue should be addressed Is discussed below.
Discussion:
The setpoints being determined have two goals; to identify the Allowable Value for use in the ITS and to determine the acceptability of the existing setpoints In regards the CTS limits. Sketches are attached for clarification.
rrs The starting point in the ITS setpoint determination is the Analytical Limit The Analytical Limit Is Identified as a "proposed" limit, provided to YNSD Nuclear Engineering, for use in their reload and safety analysis. The Analytical Limit Is available from the Selpoint Matrx. A copy of the matix from where the Analytical Limit was obtained should be attached to the calculation (as the Analytical Limit Is still "proposed" and Is subject to change).
The Limiting Selpoint (LSP) Is established by calculating the Total Loop Uncertainty (TLU). The LSP is determined by adding the TLU to the Analytical Limit. The Allowable Value Is then determined by adding the testable (observable) uncertainties to the LSP.
There are two ITS evaluations associated with each evaluation; a monthly surveillance cycle and a quarterly surveillance cycle. The Analyzed Drift (DA) Is typically based on monthly survellances. The calculation extends the DA for an equivalent quarterly surveillance. As such, the TLU and the testable uncertainties will be larger. However. the Analytical Limit remains unchanged.
Page I of 3
YAN*(EEATOMICELECTRIO COMPANY.
VYI 37/97 C
Lo V C..
NO.
GJH to FILE..
v.. ITS S po# n Evaklbafiof The starting point for the CTS evaluation Is the trip setting Identified In the CTS.
The Umiting Setpolnt (LSP) Is established by first calculating the Total Loop Uncertainty (TLU) for the normal operating environment and adding It to the Technical Specification Limit. There Is no Allowable Value term. The actual setpoint must be <LSP or a change to the setpolnt will be required.
The next step Is to identify the Impact of harsh environments (if applicable). A TLU for harsh environments must be calculated and added to the actual setpolnt The potential trip point Is then established and must be less than the Analytical Umit used In current safety analysis.
==
Conclusion:==
The above discussion provides general guidance for ITS and CTS evaluations.
The guidance provided In this memorandum will be incorporated Into a future revision of the Vermont Yankee Setpoint Design Guide (as appropriate). Until then, this memorandum Is an interim change to the design guide.
/e rg-a-"J. 144rng~e -.I Senior l&C Engineer Vermont Yankee Design Engineering Interim DesIrn Guide References
- 1.
Memo VYI 31197. "improved Setpolnt ProgramlApplication of Analyzed Drift Values in Setpolnt Determination t
, April 2, 1997.
- 2.
Memo Vyi 32f97, "Improved Setpolnt Program/Relationship of HELB Environments to RPS SetpointsW, DRAFT
- 3.
Memo VYI 41197, "improved Setpolnt Program/FSAR Table Revisions and M&TE AccuracyW, April 23, 1997.
- 4.
Memo VYI 37/97, "Improved Setpolnt Program/CTS v.s. ITS Setpoint Evaluation',
April 25, 1997.
Page2 of 3
MEMORANDUM YAWEEAr0WcaEypMcwu Vermont Yankee Design Engineering - BOLTON__
To:
Distribution, Date:
June 26, 1998 Group N:
VYI 92/97 Rev I From:
GJ. Hengerle/R.T. Vibert
%NO N:
4894
Subject:
Application of CT, CE and A for Single Point Devices IMS #:
File N:
SETPOINT\\MEMO-20R 1.489
Background:
Currently the Vermont Yankee Instrument Uncertainty and Setpoint Design Guide states:
Section 3.6.2 Calibration Effect (CE) and Calibration Tolerance (Cr)
Section 3.6.2.A Analog L=op Components:
CE - CT+A, Where A is taken as a dependent term when, during calibration testing, less than a full traverse is performed Stion 3.6.2.B Ristables/Switches:
CE - CT+A, Where A is taken as a dependent term when during calibration testing, actuation is only tested once.
For bistable components this has been viewed as overlyconservative, especially where drift data over numerous calibrations would imply that repeatability in a single direction of interest is addressed. The following discussion provides additional guidance in this area.
Revision I addresses the inclusion of calibration tolerance.
Discualon:
ISA S67.04 Section 6.2.6.2 States,
'Ifthemedtodofcalibratioa orperformace verification does not verify all attributes ofthe reference accuracy, the potential exists to introduce an offset In the instrument channels performance charactetics that is not Identified In the calibration or performance verification of the instrument channel".
Reference Accuracy Is normally assumed to consist of vendor stated accuracy, linearity, hysteresis, and repeatability. Since the timer operates In only one direction hysteresis is not a consideration. The linearity of the measurement is not a concern since the point of interest remains constant. Therefore only repeatability and accuracy areconsidered. A single calibration will not confirm the accuracy or repeatability ofthe instrument However, each of several different calibrations occurring within the limits of vendor defined performance does verify the accuracy and repeatability.
Page l of3
Memo VY1 92t97 Rev I GJH/RTV to Distributior/Application OICT. 0-. 1,1d A fr S.. k. I'mt I)
Do k..
Where Vermont Yankee has performed a drift analysis for a given component type the multiple calibrations evaluated for this analysis verifies performance within assumed values assuming that this historical value is compared to expected values for performance. Additionally, it may be inappropriate to perform multiple setpoint checks for the tiine delay relays.
Forsingle point devices (i.e. bistables/switches/time delays relays) used in a single direction, where repeatability is the primary contributor to RA, and where drift analysis has been performed, determine if the value for analyzed drift is within expected performance characteristics. To simplify verification within performance characteristics, combine (via SRSS) the vendor's published reference accuracy term, the vendor's stated drift term, calibration tolerance, and the M&TE terms. This value will be compared to the plant specific drift. Where plant specific drift is less than the expected performance, CE - CT will be used for Calibration Effect In other words:
If Plant Specific Drift < (
+DA2+CT 2+M&TE2); CE - CT If Plant Specific Drift k (RA'+DA3+CT'+M&TE')"' ; CE = CT + A
==
Conclusion:==
The intent of the design guide is adequately addressed with the guidance provided in this correspondence. It will be incorporated in a future revision of the design guide.
77/
S IRoger T. Vibert Principal Engineer Lead Electrical/l&C Engineer Vermont Yankee Design Engineering Vermont Yankee Design Engineering YAMMMr02MC0*
OMAW GLtATPDMWj=~
4-C:
ATT T1i.O Tea M. Anderson D. Dauzat D. Clinton
- 3. Voss Page 2 o( 3
YANI*EEATOMIC ELECTRIC COWANY, c=A*o*wc m
¥-.4.LC.m
. l-y.v o ATTXMArYAAW
- . ;...'-j..
GENEHAL ELECTUIC
- 225AS600,
. I w,
0 I
u
, I..
la~y..
I NSTRMEN DATA SHEET 225AS600
- em on 98m flRS? mAD Fox ~IERTR SWITCH (VERN YANKEE) m il I
ITEM (TAM) INO-.'
I2-I~ ~
1<-U
`-
- ~~7j.i I
I 41 I~U dk EWIfUTT:
.. a
+
.EV c,e..i...
.1 L
- _i,:
,L.
.. 2;.
'SCALE RANGE/UNITS 11
- I'- DtV F
-W"P I -bVF CIO,
- REQO RANGE (AD.)
o-a:obF c.-3.c0o 4F 0-3ooo
.COfNTACT 41OPER AT l°d-itelr 2-001,
-F",n*
- CONTACT 12 OPER AT PURCHASE RANGE(ADJ)
IO3°-
4COF-I,.,cOF I.F to tolrF" RESET SPAN DIFF
" PROCESS-FLUID
" DESIGN TEM"_
- -OESIGN PRESS *_..
NORMAL-TEIP
'-,°_-_of.:
- NORMAL PRESS
- LINE SIZ.E/SHAT".
NIPPLE IA NTG SIZE & TYPE COHN TO ITEM NO 7
- REO0 ACCURACY t 2 qS*
474.
qo RATED ACCURACY t b517,Ok PURCHASE SPEC z,.Poo I
I-a-
9
.lPOol I3&BIq;azpo)E V E N D O R '
.f-_
-F e
.'1 _
CAT NO
!1 -P.;
I1O7.
.4 4-LUV*ATTflN or._9 I
fl.d1
-a jg,-I6Jf1
~
7 1 fg4l E
I NOTES:
- TO BE FILLED IN BY APED
__4 1 4.
6*-'
27/;+
SM CALIFmm 99 mm.98 I
YANKEEATQ0M1W JTjM IMPAMP C-ALCULATION NO VYeC-0.2.c Rev ATTACHMWtA -
PROCESS INSTRUMENTA7rON 61
- uhie r
.2-ou A kaymld =mi d fUmef tot Commmdby A-A" T~k 1-Ter" ofApmbft aud Ett Tlow-c-pla
-IxuseMuo wke Mbw
.dm.
01mm LIm.
o co,
- F Type 7=
70,F
- ,dd Spedd mC..
F Suadmwd Speeh C"ppa-coeut
-300 to-IS
- 7
-150 to
- -IS 216 11%
-7S to,200
%*eF to.20o tI20 200so700 a I*%
fro.-eoamaatan 0330o 5,
tp, 0 w 400
- 4
- 2 Slow 1400 ty%
- X%
]c..md-quimd Ot*SlO W4F 0 to 400
- 6 Sl0to 2300
- Y,%
10%
loodum or pd*om
- 13%
0 to 1000
.t$*f 75 to 400.
- 12 rhodum 1000 to 2700
- 0.$%
- Doft fo d uchde wo*e orsroimomaram.
IIO*e.eioo Sadety of Me.dud, L ev. P -a Tea CO& I9.J. p. 23.2961.
T"bi 43J-El.caooodw. Yom W&
v Teprcm Cp) f..Tb pke..~
OI It.
ý-
C"n-t-
Ot kd.m-domd ve.mof n
eemnm iom
. phl no 10%d &dki phdoom+ 13% dhm IF (typeK)
(cpuf)
- type?)
(type) Ic(peS)
(type t) 0 0.00 0.00 0.000 0.00 IO IJA 139 1.059 3,63
'0.O.6 0.154.
lc0 2.20 2.3 2.167 1.29 0321 0."19
,50 J.34 4.30
$Ji n
.6 0.501 0.499 200 4.30 S.80 4.61" 6.39 0A695 o.6gs S
US 131
$.950
&78 a,"0 0.906 me 11 6
8.3 us ill 10.73 t.111 1.129 350 1.i'.
0.37 8.134 111 IJ.342 1.340 400 8.99 I 1.9 10.195 14.717 1.74 1.601 430 N0.3 3 I346 11.700 14.86 1412 1.8IS So0 1.25 35.01 31245 18.91 26 2.111 S
10 1209 t6.$4 "444.827.
21.13 2.305' Lies 600 3S.34' 18.M M6.443 23.2 2.5s8 2
4 650 14.70 19.33 18.091 25.46 2.116 L M.92 700 1S.86 2.3$
19.770 21.67 J.07-5.202 750 1.03 22.68 21.475 29.88 3.M40 S.48A moo 8.21 24.21 12.11 3.606 9.176 61O 9t.8 2S.74 HM4.4 3.875 4.069 900 20.7 271.29 3J.39 4.146 4.363 950 21.73 28.34 3884 4.419 4.A62 1000 22.94 30.41 41.08 4.696 4.967 3030 24.12 32.01 43.13 4.974 5.275 t100 23.3I1 33I.
43.38
$256 5.547 1150 26.49 33.23 47.83
$.$40 S.104 1200 27.66 36.90 30.06 3.826 6.224 1230 26.33 36.60 52.29 6.333 6.54S 3lo0 J0.00 40.12 34.32 6.407
&6.872 I3so 33.37 42.08 6.713 6.701 7.202 1400 M2I3 43.3S S8.94 6.997 1i$1 1430 33.48 43.64 61.133 7.269 7.8'11 30 34.61 47.4 63JJ2 7.598 8$its ts30 33.75 49.20 6S.4
.9j0 LsS9 ro m smwdrme Sodety of Awým. reoeoia" ftctim $.I. Aug. 1.3954.
ATTACHMENT 0 VYC-462C REV 0 PAGE 1 OF 6 CALCULATION/ANALYSIS REVIEW CALCULATION NO.
VYC-462C REVISION NO.
COMMENTS RESOLUTION This callatim ba been *viewed IAW WE-103. Non-4edmical comn s have corIm.rs.
been made to a mark-up copy and do not require formal reolutiom.~f~
C'"~/11A4
-A&c 7(A e-
.9
.9
.5
.5
.5 4
4.
4.
4.
4.
4.
4.
4.
Ideutfy mehod(s) of iww
)Calcuwatiowanaiis reiew
" Altanafive calalcuiona method o Quatification tesing Resohit ion Byr W
Nq-er/Daft Cowmsats Continued on Page:_4 Conmffen with Resolution Revicww/Date FORM WE-103-3 Revision 5
VERMONT YANKEE SETPOINT CONTROL PROGRAM INTERDEPARTMENTAL REVIEW OF CALCULATION: VYC-462C Revision 0 A T"
(
VYC-462C Revision 0 has been prepared and independently reviewed. The Departments impacted by this calculation are requested to review the results of this calculation, concur with the results and/or recommendations, and document the department's acceptance prior to the calculation being approved.
- 1. Summary:
This calculation evaluates the uncertainty & setpoint for RCIC Steam Line High Temperature (HELB Detection).
- 2.
Calculation Open Items:
AP-0028 to be Assigned 2.1.
None
- 3.
Department Review - contact the Setpoint Program Manager (G. Hengerle) if not in agreement with the conclusions/statements.
3.1. Vermont Yankee E&C
- 3. L.a.
Procedure OP-4366 Revision 12 will require the following (based on Custom Technical Specifications Istandard surveillance cycle):
- 1. Add the following in the procedure discussion:
- a.
Limiting Setpoint:
A TS-13-79A-D/80A-D/81A-D/82A-D 187 OF C,*,-
L-q 4-r
- b.
As Found values:
TS-I3-79A-D/8OA-D/81A-D/82A-D
.-t j
- c.
Revise Head to reflect:
NA
- d. Insert the following M&TE requirements:
Omega Omnical 4A, 8A, or CL-505A, or T/C reader
- 2.
In the body of the procedure and the data sheet revise as follows:
- a.
Calibration Tolerance From To TS-13-79A-D/80A-D/81A-DI82A-D
+/-S OF
+/-5 OF
- b.
Trip Setpoint From To TS-13-79A-D/80A-D/81A-D/82A-D 185 OF 185 OF
- c.
Revise calibration data to reflect head correction of:
NA D
??-o733 Page
- 29. of 4,
Vermont Yankee Setpoint Control Program Interdepartmental Review of Calculation VYC-462C Revision 0
, A*777. 'o
- d.
Insert a 9-point calibration for all analog instruments:
NA Transmitter Recorder Indicator Square Root Converter Other (Equipment ID]
[Equipment ID]
(Equipment ID]
[Equipment ID]
[Equipment ID]
Input Output Input Output Input Output Input Output Input Output o%
mA 25%
mA 500h mA 75%
mA 1000/
mA
- 3. i.b.
The following comments/recommendations apply:
Concur
- 1. Incorporate the above changes.
Sign & Date 3.2. Vermont Yankee Reactor Engineering Concur 3.2.a.
None Sign & DatAlb T'-z
-I I,,,4 ( /
Vermont Ydnkee RE Representative 3.3:
Vermont Yankee Operations fi.44rCL If A)111 r&_
urd 3.3.a.
Operations should adý i
vey "4,f the maximum acceptable selpoint to 1960 F in lieu of the 212° F presently allowed by the Vermont Yankee Technical Specifications. An ER has been genehi issue.
/
maxiumaceptalesepoin le S ig n & D a te
=__
/__
Vefmont Yankee Onerations Representative 3,4. Vermont Yankee Systems Manager Concur Comments 3.4.a.
This analysis supports the design bases for the RCIC System.
664a Sipn & Date X~f wiltati/
V* erifont'Yikee l*y's~m Engineering Representative 3.5. YNSD Nuclear Engineering Concur Comments 3.5.a.
Custom Technical Specifications
- 1. Analytical Limit used in setpoint determination:
- 2.
Potential accident trip (LOCA):
- 3.
Potential accident trip (HELB):
3.5.b.
Improved Technical Specifications
- 1.
Analytical Limit used in setpoint determination:
- 2.
Potential accident trip (LOCA):
- 3.
Potential accident trip (HELB):
- See Section 3.1 and comment I (2o0o' a'./ed
,C*,
V'tsqign & Date 1960 F*
NA 196 0 F*
1960 F NA 1960 F
/
YNSD NED Representative Page._3 of go
Vermont.Yankee SetpointControl. PrOgram.
Interdepartmental Review of Calculation VYC-462C Revision 0 9 7 7, a 3.6. Vermont Yankee DBD Manager 3.6.a.
The RCIC DBD should reference this analysis.
The DBD is complete (an AP-0028 to follow)
The DBD is not complete. Incorporate reference to this analysis as appropriate.
Yes No
/ /O-,,29.9?*
Sign & Date R
I 3.7. Vermont Yankee Licensing Impact Yes No 3.7.a.
FSAR Changes (AP-0028 to follow)
Table 7.3.2 C3 3.7.b.
Other impact on licensing basis:
1 0 0 The C7S has a limit of *212 *F. TheAnalytical Limit is 196"F. It is not acceptable to have an AL <
C7S as this would allow the instrument setpoint to be above, 196'F (outside the analysis limits). Either the NED analysis needs to be revised to use a value of Ž212 *F or the CMS Limit needs to be lowered to 196°F. An ER has been generatedto address this condition. 4'
,Ploo28 o1 ctJ2*"
/ SOC 4 -0 v~
00~~7A6 7x,45 Sign & Date 1.
ISP Irogranm Mdnager 3.8. Vermont Yankee ITS Manager Yes No (a
0j 3.8.a.
This analysis provides an input to the ITS. An Allowable Value applies.
Allowable Value = 194 E (cyjrslbhl 7ZI1AA' a4 3.8.b.
This analysis provides an input to Technical Requirements Manual.
Incorporate as appropriate.
Sign & Date
'1 3.9. Other Department(s)/Program(s) ( None) 3.9.a.
Impact assessment/recommendations:
NA Concur ISP Pro-gram Manager Sign & Date
/,i.ap.9"
- 4.
Setpoint Program Manager
- 4.
Setpoint Program Manager Completed 4.1. Concurs with above.
EF 4.2. Interdepartmental Review form (copy/steps 1 through 3) incorporated into calculation.
4.3. Calculation has been approved.
g AI 4.4. AP-0028 commitments have been assigned and forwarded for incorporation into the Commitment Tracking System.
Sproved on 9
///99 19i'r&rm ~aaer Sign & Date
.Page /1 of 6
Vermont Yankee Setpoiirt Control Program A7
.7-Interdepartmental Review of Calculation VYC-462C Revision 0
- 5.
Post-Approval Requirements
- a.
E&C (perform as appropriate):
Initiate AP0022 Setpoint Change Request Update MPAC Revise calibrationlfiinctional/logic test procedure Inform the following after changes are implemented:
- Setpoint Coordinator
- Setpoint Program Manager
- Training (notified via AP-0022 if initiated)
- Operations (notified Via AP-0022 if initiated)
- Design Engineering
- b.
Setpoint Program Manager: Update Program Manual (after step 5.a).
- c.
Setpoint Coordinator: Update Setpoint Data Base (after step 5.a)
- d.
Design Engineering: Initiate FSARIDBD changes, as appropriate (if DBD has been completed Comments:
AP0028 VYC0462CRO-01 AP0028 VYC0462CRO-02 AP0028 VYCO462CRO-03 AP0028 VYCO462CRO-04
- 1) An ER has been generated to address the condition where AL<C'I S
- e.
Design Engineering: Investigate need to revise EQ Program Manual temperature limits (2000 F applies inside steam tunnel, 1960 F applies outside steam tunnel) for HPCI, RCIC & MS small break HELBs.
AP0028 VYC0462CRO-05 Page 6 of 4-
16 " VMEE D]ESIGN ENbuxt.,...
-SYSTEM ENGINEERINGrREVIEW FORM WlAIowg Nin Document V/YC-i't ý 3
,/
Comment Resolution A/
Document Originator Date ileviewer Sieture Date Reviewer Signature D
Date I
Iport go.
nI-TU-831200-1 Pass
- 0. zX-,
G V".I-2S9V I
"ell~~fa VYM-4L2.e.,
2-2.3 Post-Aecido".
runc-iou-Tests QDR 9.4 X-2.3,.
Visual,0
,ec.ion REV.3 The test Items wre visually inspected per Paragraph KoI.3.
The only aoted observation was a slight discoloration on m of the Amphesol connector@
(surface tarnish through protective coatiug).
The dtscoloration does nat affect the operation of the test LCes.
The Inspection sheets are presente4d I AppendLz X-A.
X-2.3.2 Fuoctional Tests The follovwng functional tests wmer performed per Fasagraph X-1.3.2 on Items #2 asd #5 (the Items that were subjected to the LOQ/WELM simulat*on).
1-2.3.2.1 Set Point Determlnatiou The set points of Items #2 and 05 v*Se measured and found to be vithin the orvigiat1 specified
- 6 r acceptance criterion. This is 8 spocially notevorthy in itWac the set points changed by
+2.2 7 (item
- 2) and
-0.21F (item 0S) %bon comparing the functional teat values before and after the WCA/ILUS simulation.
in
- fact, the witches remained to calibration throughout the entire test program without any adjustments (calibracions).
Thil perforuance also continued through the tests of Section X1, Humidity/Cycling.
Data is presented in Appendix X-A.
X-2.3.2.2 Contact Resistance The contact resistance of items i2 and 15 yes measured at 0.039 and 0.037 ohs, respectively.
Tbhese are acceptable values.
Date Lo presented In Appondix 1-A.
X-2.3.2.3 tnsulatLon Resistors The iasulation resistance of both test Ltems was 210 12 ohms (wire to case and wire to vire with open contacts).
These are acceptable values. Date is presented in Appendix X-A.
1-3.0 SWlA C
The teast items (#2 and 15) were subjected to environzmntsl condi-tions as described In the test report in Appendiz X-S.
The test items were powered and monitored to required with no problems experienced.
The functional tests following the accident steula-tio were esatIsfled (all acceptance criteria ware me).
patel engncers hurwtvsvI Wabom
MCLcuATIONuoVYLý-44z~c.
K"Ort NO.
SO-3668-1
- la,-tr PS,,1+.Erine,,r,,
QDR 9.4 QR 9o.4o._
Test. late_/2/-
FMLTU4EROM Mf=
IWTEPIN 01-UMI0
-FWCTIONAL TUST3 Post Seisic Sinuletion Tar~o Taarit Set Point, f
°1 NO..
2+
2 33513
£I S
212*
Ire-Test Rom Tem.
r at reak" Tat
. Contact K,., ohm,,
st 2nd 3rd
_&Y 2
.036 137.1 13,.0.
137.0 137.0 s, _
-7._
-.__1-.--i 4
So* note fa 1IM.
176.9 176.3 176.9 0
s
.041 216.2 216.1 216.2 216.2 LsosxLav ale.sista
. @SO0 V'DC'..ohgas.lO'F abcwe reakpoi.*
Tat No.
3etven WITe 0r* Wire to Case Other Wire to Cue 4
2000K 2000K 20009 S
20001 2000.
20009
&3 No0. 4 IAe*d wvre into sw~itch has Intermitctent conacte.
Rece;ivedl at RW Lin danaged condition dfter seismic test, spparently pulled Irm seismic test fIxture by lead wires.
To Vlvt@d byDate NMIDTIIERM ICOOR DI ICO iPO t
IOM Si
- ' ' " '+ala.s A-^
. ILOU",3" 1-- -
YANKM ATOMiCELECRCOPAIWJ c~ATgA NoýY+/-L ATrAWT
-PAW_-3LOF_3
-100 to 6000 F/-73 to 316°C ON.'
COW4ACC RlAIM 0"iAIO
.1000d0
.100 to 0*fl I
t
-72 selN4C
- l0000OrWj
.73 so SUN 401-I Oft
.100 so AWN*7
.72s.~r
- s. sr
.400$06*00'F
"~32 l00h 4.300WC are. NOWW.*IW 47310.4c sa
- IObOV T-.2 100W5*ftC 0.1..6.
Ska.N.
op-u 73749 2fe~oc 7rp,4to No WAI O4et 1%).r opS.S0ddL
.7369316*C C6 I
Ut. ml NO. 14"A 94 #A*dgmodl - A dw r4..Ud0d-P 0 fw4(AJ CSA Ml No. L*7373
.4 C9.dftjW tl C....d.. Sbnd..d. Al..dwl.. fG.d. H.. 400404 3 týc
ýk XeVIt4L4 4 ?
F~~:MoJcAAL A,4Jec5.oa YAMMEAwMIaECTtcof4?.e I~V
- WMW_
PAW~Q.
3 V(:,
.% t. =,
"I ti,*p(C &I.....
N..*-
co4.1-.ISA:
I.ve
'L WV Eke 400- TX V44.J 5
i's 2.7w 3.4w 4.d..4 S o %h,.,,.,c.-.-,o~
I
~ev 4
PROCEDURE REVIEW PORC MEMORANDUM /Yc-y( ý
- To PORC From" R; A. Barfield Date _
12.:
Procedure No.: OP4366 Rev: 12
[X]Biennial Review
]
JPartial Review 1
Title:
RCIC STEAM LINE TUNNEL/SPACE HIGH TEMPERATURE FUNCTIONAL I
CALIBRATION TEST The procedure was reviewed against Technical Specification section(s) 3.2/4.:
for applicability, with no concerns noted.
The procedure was reviewed against FSAR section(s) 4.7 & 7.3 for applicability, with no concerns noted.
Review of YOQAP-lA is not required.
Procedure is written to AP 031(
requirements, with AP 0310 reviewed to YOQAP requirements.
These changes do not require a 10CFR50.59 (a) (2) based upon the 10CFR50.59 (a) (1) screening criteria in AP 6002.02.
WIinMOMGMEM Summary of changes:
P3CaIIJo.L In the Surveillance Setpoint Criteria table, changed TS-13-81A,B,C,D in the bottom row to TS-13-82AB,C,D.
elhanged Reference g. from AP-0021 to AP-0047 (Work Order Request).
Same change ade for Precaution #3.
Added "Associated Relays" to step 2 of VYOPF 4366.01 to match procedure step.
Added to VYOPF 4366.02 "MITE (VY SN/Due Date)" for recording of M/TE used for calibration. None needed for Functional Test.
Added a paragraph at the end of the Discussion section to discuss how the functional and calibration are performed. Also added why the temperature switch is preheated when performing the calibration. Tech Spec Procedure review project comment PC-2 and PC-5.
Added Acceptance Criteria #3, "All applicable EQ requirements satisfied". Tech Spec Procedure Review Project comment PC-4.
Other procedures include this requirement when working on EQ related components.
The following addition Tech Spec Procedure Review comments did not result in any procedure changes and are documented here.
Comment PC-I concerning influences of test conditions. The procedure contains a note to alert the performer to be as consistent with his testing as possible.
The calibration is performed by installation of a test heater that is prefabricated. This minimizes the effect of any external influences since the heater is placed directly over the temperature switch and the thermocouple is already attached to the temperature switch. The speed of temperature change is omewhat limited since the voltage to the heater is controlled. No new procedure nhancements are made due to this comment.
Page 1 of 2
Comment PC-3 concerning calculation VYC-462 and the calibration equipment error of. 5% versus up to 4 Deg F for.;ype.K thermocouple i1 a valid concern. This additional error will not affect the actual trip point since the trip point is qet conservative in relation to the tech spec value. The total error is also elow the FSAR accuracy limit if the 4 Deg is added to the present total loop
-. rror.
Calculation VYC-462 will need revision by YNSD to incorporate thermocouple errors different from that presently stated in the error analysis.
No procedure change is made by this comment and the present setpoints satisfy.
the Tech Spec.setpoint. A copy of this PORC memo sent to Roger Vibert (YNSD) O Ilk a
Training required:
Formal ( ]
Departmental ( ]
None (x]
VinRMMUMBOOM
-M-MI--
ibmitted By 4/o, Date 5,2 iEý :;
Page 2 of 2
MEMORANDUM.-.
VERMONT YANKEE DESIGN ENGINEERING - BOLTON Ve"ONTSIUDEMItENGINEERING To:
R.T. Vibert m, aI.
oxin.-
Date: October 5, 1998 WM NO.
Group#:
VYE98/214 From:
G.J. Hengerle ATTACWtgS PAGE. 0FP WO #:
Subject:
Assessment of VYC-462A,C & D Temperature IMS #:
Limits File #M MEMO-VYC-462AC,D
Background:
VYC-462A, C & D evaluate the setpoint & uncertainty associated with the Main Steam, RCIC & HPCI steam line area high temperature switches. The Technical Specification limit associated with these switches is 212 F. DE&S THSAG used an analytical limit of 196 F in support of the EQ Program for evaluation of High Energy Line Breaks. The Appendix R/Station Blackout analysis assumes a limiting high temperature of 174 F in the Steam Tunnel. The following provides a discussion on how these limits interact.
Discussion:
The DE&S THSAG ran a small break steam line break analysis was completed to support of the EQ Program. The analytical limit used in the analysis is 196 F. The analysis assumes that when temperature reaches 196 F the steam line will isolate on high temperature by tripping the associated high temperature switches (following the appropriate time delay). YC-462A, B & C address the high temperature trip requirements associated with the Main Steam, RCIC & HPCI steam line areas. The limiting condition for these analyses is not the existing Technical Specification limit of 212 F, but the 196 F in the small break HELB analysis.
VYC-462D (HPCI steam line area temperatures) requires a setpoint change to support the 196 F limit. However, the setpoint change must also support the lower limit of 174 F. The 174 F limit is based on the Appendix R/Station Blackout scenario where the Main Steam tunnel can heat up but HPCI & RCIC must not isolate. VYC-462D determined that the Limiting Setpoint is 183 F, with a recommended setpoint of 180 F. The two limits (>174 F and <196 F) make a setpoint change that accommodate both conditions difficult.
An evaluation of the DE&S NED THSAG analysis was conducted. The following has been concluded:
- 1.
The 196 F limit used in the analysis is relied on to isolate the HPCI & RCIC steam lines for small breaks outside the Main Steam Tunnel. These analys~es were developed to directly support the EQ Program.
Page 1 of 2
Memo VYE 98&214 GJH/EG to RTV/VYC-462AC & D Temperature Switch Assessment ATACHMT T
-;" PfAE
- F_.
- 2.
Analyses of HELBs in the Main Steam Tunnel were completed using a 196 F analytical setpoint. The results of these analyses are not directly used in the EQ Program. The EQ Program uses a enveloping temperature profile for evaluation of small steam line breaks in the Main Steam Tunnel (EQ Program Figure SB ST-41).
Per the EQ Program Manual (Section 7.5.5 paragraph 5), the limiting temperature that applies is 200 F.
==
Conclusion:==
VYC-462A, C & D will use an analytical limit of 196 F for the temperature switches located outside the steam tunnel and 200 F for the switches located within the steam tunnel.
G sor geJ.l-Ie erie Principal Engineer Vermont Yankee Design Engineering Ed G win Project Manager II Duke Engineering & Services C:
R.G. January D.E. Yasi R.T, Vibert Page 2 of 2
COMPONENT SAFETY C ICATION WORKIHEET Component I.0.
No.
______7_
System:
i ac, 9-Does the component perform a Mechanical function?
If 'yes*, proceed to Part I.
If *no'. proceed to Part IV.
Yes No I. Ooes the component perform any of the following functions?
- a. Forms part of the reactor coolant pressure boundary such that failure Q could result in leakage of reactor coolant greater than that from a 3/4' nominal pipe size.
- b. Provides mechanical support to any portion of the reactor coolant Q
' 0 pressure boundary.
If any of the Items above are checked *yes*. component. is Safety Class 1 (SCI).
If component Is Safety Class 1. check box and proceed to Part IV.
If all responses are *no', proceed to Part II.
II. Does the component perform (or could its failure prevent) any of the foI owi ng functIons
- a. Inserting negative reactivity to shut down the reactor.
10 (3
- b. Prevents rapid Insertion of positive reactivity 13 13
- c. Maintains core geometry appropriate to all plant conditions.
-o
- d. Provides or maintains primary or secondary containment integrit 3 0
- e.
Removes residual heat from the reactor and reactor core.
- f. Stores spent fuel or prevents uncovering spent fuel.
3 0
- g. Piping and components which form part of the reactor coolant p e
boundary but whose rupture would not result in leakage grerter th from a 3/4* nominal pipe size.
03 03
- h. Provides mechanical support to any of the above.
(11. a-9)
[]
[]
If any items above are checked 'yes'. component is Safety Class 2 (SC2)
If component is Safety Class 2. check box and proceed to Part IV.
If all responses are *no*. proceed to Part I11.
==
Description:==
S,.
ZC ' *
/. '
1.je" VYSC."
. Rev. 6 IV. Is the component Electrlcal/I&C relatedf d
Yes No' If 'yes'. proceed to Part V. If,o. proceed to PArt VII.,' "3n V. Is the component essential in performing or perm4tting an associated component to perfom'sa safety function?
bI Is the instrument used for a Post Accident Monitoring function required to be Safety Class?
If above is checked *yes*, then component is Safety Class Electrical (SCE)
If component Is Safety Class Electrical. check box and proceed to Part VII.
If response Is 'no*, proceed to Part VI;.
V1. If all of the response In Parts I. II. and III are answered no.*;
the component is Non-Nuclear Safety INNS) for mechanical functions.
Check box and proceed to Part VII.
If a4l of the responses in Part V are answered *no*, the component is Non-Nuclear Safety INNS) for Electrical functions.
Check box and proceed to Part 'II.
VII. Other Items Requiring OA (OQA) is an optional subset of the NKS classification category.
If the component is subject to non-safety related regulatory requirements or other special requirements, check box and' provide, special requirements In Section IX. Proceed to Part VIII.
L:m3 VIII. Summary:
From the above, the component sbeen:
determined to be (check one box In each section).
Mechanical Function Electrical/l&C Function scI3 SC2D n
sc3 C0 SCE*
NNS n NNS [3 No Function a
OoAKr No Functfont3 OGAI'3 IX. Basis:
Use Siheet 2 of 2 if necessary.
Check box if Sh 2o0 2 is ud*
.a Originator:
Reviewer Date:
9 dDate:
c./V7, Entered into MPAC Database:
C Date VYSCM-1 Ill. Does the component perform (or could its failure prevent) any of the following functions?
- a. Processes or houses radioactive wastes where failure of that single component or structure would result in a whole body dose (or equivalent to any part of the body) to a person at the site boundary of 00 mrem or greater.
- b. Provides or supports any safety system function.
- c. Removes decay heat from the spent fuel pool.
- d. Provides mechanical support to any of the above (Ill.a-c)
If any items above are checked *yes*. component Is Safety Class 3 (SC3)
If component is Safety Class 3. check box and proceed to Part IV.
If all responses are 'no% proceed to Part IV.
00 0.0 0
0 00
cERcWUiwI'vc. vEz
=, WA0 ~
FEV N S
Safety Class Worksheet RCIC Steam Line Area High Temperature Trip Switches TS-33-79A-D/80A-D/8IA-D/82A-D These switches monitor the temperature in the vicinity of the RCIC steam lines (including the RCIC lines in the Main Steam Tunnel). On a high temperature, associated with a small break RCIC UELB, the switches will sense high temperature and cause the RCIC isolation valves to close. This function is necessary to support the RCIC HELB temperature profiles in the VY EQ Program and also isolates a radiological release path. In addition, the VY Technical Specification bases describe the ability to isolate a 5 to 10 gpm leak in the Main Steam Tunnel. These functions are Safety Class Electrical (SCE).
Appendix R/Station Blackout relies on RCIC availability. Analysis indicates that the Main Steam Tunnel heats up during this scenario. The temperature switches cannot be set to trip such that RCIC reliability is challenged. Appendix R/Station Blackout support is Non-Nuclear Safety related (NNS).