ML081021195
| ML081021195 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 04/11/2008 |
| From: | Gerald Bichof Virginia Electric & Power Co (VEPCO) |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 08-0151 | |
| Download: ML081021195 (29) | |
Text
VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 April 11, 2008 10 CFR 50.90 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555 Serial No.
NLOS/GDM Docket Nos.
License Nos.
08-0151 RO 50-280 50-281 DPR-32 DPR-37 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 PROPOSED LICENSE AMENDMENT REQUEST REVISED SETTING LIMITS AND OVERTEMPERATURE ~T/OVERPOWER ~T TIME CONSTANTS RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION (RAil By letter dated September 19, 2007 (Serial No. 07-0470), Virginia Electric and Power Company (Dominion) requested amendments, in the form of changes to the Technical Specifications (TS) to Facility Operating License Numbers DPR-32 and DPR-37 for Surry Power Station Units 1 and 2, respectively.
The proposed change revises various TS setting limits and the overtemperature ~T/overpower
,1.T time constants in TS 2.3, "Limiting Safety System Settings, Protective Instrumentation," and TS 3.7, "Instrumentation Settings."
The methodology for determining the revised setting limits and time constants is in agreement with Methods 1 and 2 in ISA-RP67.04, Part II.
In a letter dated March 10, 2008, the NRC staff requested additional information to facilitate their review of the proposed license amendment request.
The NRC questions and Dominion's response are provided in the attachment.
The additional information provided herein does not affect the significant hazards consideration determination or environmental assessment that was previously provided in support of the proposed license amendment request.
Serial No. 08-0151 Docket Nos. 50-280/281 Page 2 of 3 If you have any questions or require additional information, please contact Mr. Gary D. Miller at (804) 273-2771.
Sincerely, Ge£~?a/?--6 Vice President - Nuclear Engineering Commitments made in this letter: None.
Attachment:
- 1. Response to NRC Request for Additional Information 2.
Revised Proposed TS Replacement Pages (Mark-up)
- 3. Revised Proposed TS Replacement Pages (Typed)
COMMONWEALTH OF VIRGINIA
)
)
COUNTY OF HENRICO
)
The foregoing document was acknowledged before me, in and for the County and Commonwealth aforesaid, today by Gerald 1. Bischof, who is Vice President
- Nuclear Engineering, of Virginia Electric and Power Company. He has affirmed before me that he is duly authorized to execute and file the foregoing document in behalf of that Company, and that the statements in the document are true to the best of his knowledge and belief.
Acknowledged before me this 1/ Ih1 day of O-pAA My Commission Expires:
~"",J.l()~t,---,=J'-LI-;-, =Jo=.:;;..:OB::.....-
,2008.
MMQMET *. HNHm Notary PublIc 3S-c/.3Dtil-Commonweolll\\ of YltVtnIa 4 My Comtnlilion..... Aug 11. 200t
~6.!tjkDi:tf:;
Notary Public
cc:
U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW Suite 23T85 Atlanta, Georgia 30303 NRC Senior Resident Inspector Surry Power Station State Health Commissioner Virginia Department of Health James Madison Building - i h Floor 109 Governor Street Room 730 Richmond, Virginia 23219 Mr. S. P. Lingam NRC Project Manager - Surry U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, Maryland 20852 Mr. R. A. Jervey NRC Project Manager - North Anna U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, Maryland 20852 Serial No. 08-0151 Docket Nos. 50-280/281 Page 3 of 3
Serial No. 08-0151 Docket Nos. 50-280 and 281 ATTACHMENT 1 License Amendment Request to Revise Setting Limits and Overtemperature ~T/Overpower ~T Time Constants Response to NRC Request for Additional Information Virginia Electric and Power Company (Dominion)
Surry Power Station Units 1 and 2
Serial No. 08-0151 Docket Nos. 50-280 and 281 Page 1 of 7 Response to NRC Request for Additional Information Revised Setting Limits And Overtemperature ~T/Overpower ~T Time Constants Surry Power Station Units 1 and 2 By letter dated September 19, 2007 (Serial No. 07-0470), Virginia Electric and Power Company (Dominion) requested amendments, in the form of changes to the Technical Specifications (TS) to Facility Operating License Numbers DPR-32 and DPR-37 for Surry Power Station Units 1 and 2, respectively. The proposed change revises various TS setting limits and the overtemperature ~T/overpower ~T time constants contained in TS 2.3 and TS 3.7. In a letter dated March 10,2008, the NRC staff requested additional information to facilitate their review of the proposed license amendment request.
Dominion's response to the NRC questions is provided below.
NRC Question No.1, Page 2, the first full paragraph states that for complex trip functions or functions which had limited margin with respect to the safety analysis limit, other calculational methods were used.
Identify which methods were used and their justification.
Dominion Response The intent of the discussion that begins on Page 1 of Attachment 1, Section 2.0, Limiting Safety System Settings, was to provide an historical perspective regarding how the Limiting Safety System Settings (also referred to as Allowable Values and Setting Limits at Surry for Engineered Safety Feature Functions) were developed within the industry and how the development methodology evolved over time.
Section 2.0 was also included to explain the meaning/intent of the Allowable Value (AV) as it applies to TS. The first full paragraph on Page 2 of Attachment 1 pertains to plants that previously implemented Standardized TS (STS).
The current Limiting Safety System Settings (LSSS) for the Reactor Protection System (RPS) and the Setting Limits for Engineered Safety Feature (ESF) systems at Surry were not developed using any of the methods described in Section 2.0 for plants that use STS.
Consequently, since Surry has custom TS (CTS), the paragraph in question does not specifically apply to Surry and has no direct bearing on the proposed TS change.
The revised LSSS and Setting Limits included in the proposed Surry TS change were based on Methods 1 or 2 as described in Part II of ISA-67.04, which were determined by the NRC to be acceptable.
Serial No. 08-0151 Docket Nos. 50-280 and 281 Page 2 of 7 NRC Question No.2, Page 4, first item 3, states that the distance between the actual trip setpoint and the actual allowable value (AV) is equal to the Channel Operational Test (COT) error components of the total loop uncertainty without any excessive margin included. This statement implies that margin is included in determining AV.
Since the licensee is using A V as an acceptable as-found band, the addition of margin to determine the AV will mask the COT testing result.
Identify all instances where margin is included in determining A Vs and justify this deviation from the guidance provided in Regulatory Issue Summary (RIS) 2006-17.
Dominion Response Certain proposed, revised RPS LSSS and ESF Setting Limits have a small amount of margin added to the calculated Channel Operational Test (COT) error.
This additional margin is added to or subtracted from the calculated COTerror so that the AV can be rounded to a whole number.
In every case, the rounding is bounded by the available Safety Margin for the function.
To clarify the proposed TS wording, the following statement from Dominion's September 19, 2007 submittal, Attachment 1, Page 4, first item 3:
3.
The distance between the Actual Trip Setpoint and the Actual Allowable Value is equal to the COT error components of the Total Loop Uncertainty without any excessive margin included.
is revised to read as follows:
3.
The distance between the Actual Trip Setpoint and the Actual Allowable Value is equal to the COT error components of the Total Loop Uncertainty.
The Allowable Value for certain functions may be rounded to a whole number that remains bounded by the available Safety Margin.
In addition, the following statement from Attachment 1, Page 18 and Attachment 1, Page 21 of the original submittal:
3.
the distance between the Trip Setpoint and the Allowable Value is equal to the COT error components of the Total Loop Uncertainty without any excessive margin included.
is revised to read as follows:
3.
the distance between the Trip Setpoint and the Allowable Value is equal to the COT error components of the Total Loop Uncertainty.
The Allowable Value for certain functions may be rounded to a whole number that remains bounded by the available Safety Margin.
Serial No. 08-0151 Docket Nos. 50-280 and 281 Page 3 of 7 As an example of the practice noted above, on Page 95 of Attachment 4, the proposed Allowable Value for Surry's Pressurizer Low Pressure Reactor Trip is ~ 1875 PSIG. As stated in the second paragraph on Page 95 of Attachment 4, "The calculated Allowable Value for this function is ~ 1875.2 PSIG based on the revised setpoint of 1885 PSIG and using the COT error components.
The 0.20 PSIG offset is accommodated in the 12.63 PSIG Safety Margin for this trip as illustrated in Figure 4.3.7."
Using the additional 0.2 PSIG margin allows the LSSS specified for this function in TS to be a whole number.
Also, the COT error, which is one of the elements used to determine the distance between the Nominal Trip Setpoint and the Allowable Value, does not use the error terms associated with Rack Measuring and Test Equipment (RMTE) or the Rack Temperature Effects (RTE).
By eliminating these two error terms, the COT error is smaller than if these terms were included in the calculation. This is conservative when determining LSSS and Setting Limits as described on Page 27 of Attachment 4.
The proposed, revised RPS LSSS and ESF Setting Limits for Surry that include a small amount of additional margin for rounding purposes are listed in the table below.
Reactor Protection Proposed Calculated Offset Safety System Allowable Value Allowable Value Margin (RPS) LSSS Pressurizer Low
~ 1875.0 PSIG
Pressurizer High
~ 2380.0 PSIG
~ 2378.94 PSIG 1.06 PSIG 18.98 PSIG Pressure Reactor Coolant
~ 91.0 Flow
~ 90.738 % Flow 0.262 %
2.067 %
Flow Low(2)
Flow Flow Permissive P-8 37.0 % RTP 36.70 % RTP 0.30 % RTP 17.48 % RTP Engineered Safety Proposed Calculated Offset Safety Features (ESF)
Allowable Value Allowable Value Margin Setting Limits Containment
~ 18.5 PSIA
~ 18.427 PSIA 0.073 PSIA 2.763 PSIA Pressure-Hiqh Containment
~24.0 PSIA
~23. 727 PSIA 0.273 PSIA 2.763 PSIA Pressure-Hiqh High Pressurizer
~ 1770.0 PSIG
~ 1771.056 PSIG 1.056 PSIG 8.94 PSIG Pressure Low-Low Steam Line
~ 510.0 PSIG
~ 507.85 PSIG 2.15 PSIG 68.89 PSIG Pressure-Low (1)(2)
(1) This function is Dynamically Compensated.
(2) The offset for this function is conservative, Le., the Proposed Allowable Value has been moved in the conservative direction.
Serial No. 08-0151 Docket Nos. 50-280 and 281 Page 4 of 7 NRC Question No.3, Insert "C" for Table 3.7-1 and Insert "0" for Tables 3.7-2, 3.7-3, and 3.7-4, state that the channel should be brought back to within its predefined calibration tolerance before returning the channel to service.
The methodology used to determine the calibration tolerance is specified in a document controlled under Title 10 of the Code of Federal Regulations (10CFR), Part 50, Section 50.59 (10CFR50.59).
Provide the methodology used to determine the calibration tolerance for the NRC staff's review as this value is used for as-left tolerance defined in RIS 2006-17.
Dominion Response The calibration tolerances in the Instrument Periodic Test Procedures used to perform the COT at Surry match the values used in the Channel Statistical Allowance (CSA) calculation for the parameter of interest. CSA calculations are controlled in accordance with 10 CFR 50.59.
The following statement in Attachment 2 of the original submittal, Insert "C" for Table 3.7-1:
There is a Safety Analysis Limit associated with this Reactor Trip function.
If during calibration the setpoint is found to be conservative with respect to the Limiting Safety System Setting but outside its predefined calibration tolerance, then the channel shall be brought back to within its predefined calibration tolerance before returning the channel to service.
The methodologies used to determine the calibration tolerance are specified in a document controlled under 10 CFR 50.59.
is revised to read as follows:
There is a Safety Analysis Limit associated with this Reactor Trip function.
If during calibration the setpoint is found to be conservative with respect to the Limiting Safety System Setting but outside its predefined calibration tolerance, then the channel shall be brought back to within its predefined calibration tolerance before returning the channel to service. The calibration tolerances are specified in a document controlled under 10 CFR 50.59.
The following statement in Attachment 2 of the original submittal, Insert "0" for Tables 3.7-2,3.7-3 and 3.7-4:
There is a Safety Analysis Limit associated with this ESF function.
If during calibration the setpoint is found to be conservative with respect to the Setting Limit but outside its predefined calibration tolerance, then the channel shall be brought back to within its predefined calibration tolerance before returning the channel to service.
The methodologies used to determine the calibration tolerance are specified in a document controlled under 10 CFR 50.59.
is revised to read as follows:
Serial No. 08-0151 Docket Nos. 50-280 and 281 Page 5 of 7 There is a Safety Analysis Limit associated with this ESF function.
If during calibration the setpoint is found to be conservative with respect to the Setting Limit but outside its predefined calibration tolerance, then the channel shall be brought back to within its predefined calibration tolerance before returning the channel to service.
The calibration tolerances are specified in a document controlled under 10 CFR 50.59.
Revised marked-up and typed TS pages are provided in Attachments 2 and 3,
respectively, to replace the associated marked-up and typed proposed TS pages included in Dominion's September 19, 2007 submittal.
The changes are noted by double revision bars in the right hand margin.
Using the same illustration as in Response 2 above for the Pressurizer Low Pressure Reactor Trip, references are provided at the top of Page 95 of Attachment 4 of our original submittal.
Reference 5.32 on Page 95 of Attachment 4 is the CSA calculation associated with this function (i.e., Calculation EE-0514, Revision 1), and Reference 5.68 on Page 95 of Attachment 4 is the Surry Instrument Periodic Test Procedure associated with this function.
The calibration accuracies used in the Instrument Periodic Test Procedure match those used in the CSA calculation. The calibration tolerances used in the Instrument Periodic Test Procedures are taken from Reference 5.73 on Page 133 of (Technical Report EE-0068, Rev. 0 (AR), Instrument Tolerances For Westinghouse/Hagan 7100 Process Protection and Control System, Surry Power Station) and are governed by Reference 5.14 on Page 129 of Attachment 4 (Engineering Transmittal CEE 95-037, Revision 2, Surveillance Limits for Surry Power Station RPS and ESFAS Instrumentation).
CSA Calculation EE-0514, Revision 1 and Engineering Transmittal CEE 95-037, Revision 2 are controlled under 10 CFR 50.59.
The COTerror equation as illustrated on Page 95 of Attachment 4 is given below:
COTerror =.+/-. (M1 2 + M42 + M52 + RD2)1/2 The COT errors from Calculation EE-0514, Rev. 1 and from Instrument Periodic Test Procedure 1-IPT-CC-RC-P-455 are given below:
COTerror =.+/-. (0.02 + 0.52 + 0.52 + 1.02) 1/2 The next page contains excerpts from CSA Calculation EE-0514, Rev. 1 and from Instrument Periodic Test Procedure 1-IPT-CC-RC-P-455, Rev. 10. These excerpts from the actual documents show the values used in the CSA calculation and the corresponding values used in the Instrument Periodic Test Procedure.
Note that Module M1 is a Loop Power Supply Module and is not used as a signal converter at Surry; therefore, the module does not have calibration tolerance for the 4-20 MADC current output (i.e., or 1 to 5 VDC output). Only the power supply output voltage to the transmitter current loop is adjusted in the calibration procedure (this is addressed in the CSA calculation as a transmitter error component term).
For Modules M4 and M5,
+/- 0.020 VDC is equivalent to ::!: 0.5 % of span on the 1 to 5 VDC scale.
Haepnll..ambdall"eChnt99ur Ieee PO~ Supply (MIl The 1.-\\-)(., Power Supply for the Weslingbouse 7100 P'rocess Control S)'stem.1:$ us;.ed to power the-tnn.mitter eurrea'lcx,p. The Loop Power Supply i. _
...00 a.".ignnl convert"," (Ref. 5.3). TIleref",...
the calibra.t.ion accuracy is equal to 0.0 % of Sl>a.J'l:.
Serial No. 08-0151 Docket Nos. 50-280 and 281 Page 6 of 7 CSA Calculation for Module M1 Loop Power Supply PQ*1-455 Output Voltage Rear Terminal5 1 and 2 Applied Signal Desired As Found Tolerance As Left (VDC)
(VDC)
(VDC)
(VDC)
(VOC) 1.000 38.00 36.00 to 40.00 5.000 38.00 3600 to 40.00 Calibration Procedure for Module M1
[ Calc Number:
eE.o51 Rev.
1 Add.
NlA Page 1201 23 Hagan Signal Comparator Module Model 139--1II (M4)
The f'ressuri7;et I'ressure Loops use foor Hllgall Signal ComparatQl" Modules. Module M4 will cover the foor major functioo.'< performed by lhese kJops. lhey are:
1.
PrCIIsurizer High Pressure Reactor Trip 2.
Pressurizec Low Pressure Reactor Trip 3.
Pressurizer Pre.sUR: ESFAS 11litiatioo 4,
Pressurizer Pressure ESFAS Blndi; Based on References S,3 and 5.9.lhe calibration accuracy for a Hagan. Model 139*118 Signal Comparator Module is +/- 0.5 ':ll> ofspaa Therefore. M4 is equal to:
M4.. +/- o.soo % ofspan Comparator PC*1-45SC Low Pressure Reactor Trip Selpolnt Surveillance Limit Desired Proving As Found Tolerance As Left Condition (PSIG)
(PSIG)
(VDC)
(VDCI Light (VDCj (VDCl (VDCl TRIP 1875 1865.24 I 1.826 l.875 EXT 1.855 to l.S95 (INC Signal)
RESET 1883 "NOlle 1.915 lLLUM 1900 to 1 935 (DEC Signal)
Hagan I,C.MAl! Amplifier Modgle Model 131.114<MS. Calib....tion Aecurasy CSA Calculation for Module M4 Calibration Procedure for Module M4 The static tole'fl(; for thL~ module I~ +/- 0.5 % of span.
1\\15.. +/- 0.5 % ofspan Lead/Lag Amplifier PM*1-465A Ref, 5.,
CSA Calculation for Module M5 Variable A
B C
Tl =C-A T2=C-B Eout Final (DMM 2)
Desired 42 sec S1 sec 52 sec 10 Set' 1,ec 1650VDC As Found Tolerance 9.0 to 11.0 sec 0.9 to 1.1 sec 1630 to 1.670 \\iDC As Left Calibration Procedure for Module M5
Serial No. 08-0151 Docket Nos. 50-280 and 281 Page 7 of 7 NRC Question No.4 For all instances where margin has been included in the determination of an AV, a second note should be included in Tables 3.7-1 through 3.7-4 to define the operability of the instrument channel as discussed in RIS 2006-17.
Provide the discussion of how this requirement is met by Surry 1 and 2.
Dominion Response This question has been addressed in Dominion's response to Question 2 above.
In the cases where a small amount of additional margin is being added to the calculated GOTerror to determine the AV, the requirements of Methods 1 or 2 as described in Part II of ISA-67.04 are being met.
NRC Question No.5 Table 3.7-1, functions 6 and 17 do not have an asterisk by them which implies that Insert "C" does not apply to them. Justify this exclusion.
Dominion Response In Table 3.7-1, functions 6 and 17 do not have an associated Safety Analysis Limit; therefore the note defined by the single asterisk shown on Insert "G" does not apply for these two functions.
Function 6, the Overpower L1T Reactor Trip at Surry is a backup reactor trip function and is not credited in the UFSAR Chapter 14 Safety Analysis. This is discussed on Page 94 of Attachment 4 of our original submittal.
Function 17, Low steam generator water level with steam/feedwater flow mismatch, at Surry is also a backup reactor trip function and is not credited in the UFSAR Chapter 14 Safety Analysis.
This is discussed on Pages 102 and 103 of Attachment 4 of our original submittal.
However, to maintain consistency for these two reactor trip functions, an additional note will be added to Table 3.7.1 for functions 6 and 17 that will read as follows:
If during calibration the setpoint is found to be conservative with respect to the Limiting Safety System Setting but outside its predefined calibration tolerance, then the channel shall be brought back to within its predefined calibration tolerance before returning the channel to service. The calibration tolerances are specified in a document controlled under 10 CFR 50.59.
Revised marked-up and typed TS pages are provided in Attachments 2 and 3, respectively, to replace the associated marked-up and typed proposed TS pages included in Dominion's September 19, 2007 submittal.
The changes are noted by double revision bars in the right hand margin.
Serial No. 08-0151 Docket Nos. 50-280 and 281 ATTACHMENT 2 License Amendment Request to Revise Setting Limits and Overtemperature ~T/Overpower ~T Time Constants Revised Proposed TS Replacement Pages (Mark-Up)
Virginia Electric and Power Company (Dominion)
Surry Power Station Units 1 and 2
TABLE 3.7-1 REACTOR TRIP INSTRUMENT OPERATING CONDITIONS Minimum Total Number OPERABLE Channels Pennissible Functional Unit Of Channels Channels To Trip Bypass Conditions Operator Action 1.
Manual 2
2 1
1
~
2.
Nuclear Flux Power Range "*
4 3
2 Low trip setting at P-lO 2
3.
Nuclear Flux Intermediate Range *"
2 2
1 P-lO 3
~
4.
Nuclear Flux Source Range*
P-6
- a. Below P Note A 2
2 1
4
- b. Shutdown - Note B 2
1 0
5 5.
Overtemperature ilT '"*
3 2
2 6
~
4#f-3 2
2 6
II 6.
Overpower ilT L-7.
Low Pressurizer Pressure *'
3 2
2 P-7 7
~
8.
Hi Pressurizer Pressure*
3 2
2 6
~~
?S
~
- l0-S
~
- l.....zo f/J Note A - With the reactor trip breakers closed and the control rod drive system capable of rod withdrawal.
Note B - With the reactor trip breakers open.
, N S E. RT
\\\\ C II
~
~
' § I
I......
o
TABLE 3.7-1 REACTOR TRIP INSTRUMENT OPERATING CONDITIONS Functional Unit
~
- 17. Low steam generator water level with steam/feedwater flow mismatch Total Number Of Channels 2lloop-level and 2/loop-flow mismatch Minimum OPERABLE Channels llloop-level and 2/loop-flow mismatch or 2lloop-level and 1/loop-flow mismatch Channels To Trip 1/loop-Ievel coincident with 1lloop-flow mismatch in same loop Permissible Bypass Conditions Operator Action 6
f~11 I ~ SEgT llC" 8
11 13 13 13 13
~
13 13
!§
'~
tv
- 18. a. Reactor Trip Breakers 2
2 1
- b. Reactor Trip 2
1 1
Bypass Breakers - Note C
- 19. Automatic Trip Logic 2
2 1
- 20. Reactor Trip System Interlocks - Note D
- a. Intermediate range neutron flux, P-6 2
2 1
- b. Low power reactor trips block, P-7 Power range neutron flux, P-lO 4
3 2
and Turbine impulse pressure 2
2 1
- c. Power range neutron flux, P-8
- 4 3
2
- d. Power range neutron flux, P-I0 4
3 2
- e. Turbine impulse pressure 2
2 1
zo C/l
>-S
~
- s0..
~::s......
f Note C - With the Reactor Trip Breaker open for surveillance testing in accordance with Specification Table 4.1-1 (Item 30)
~ Note D - Reactor Trip System Interlocks are described in Table 4.1-A
Serial No. 08-0151 Docket Nos. 50-280 and 281 Revised Insert "e" for Table 3.7 insert at the bottom of pages TS 3.7-10, TS 3.7-11, and TS 3.7-12:
There is a Safety Analysis Limit associated with this Reactor Trip function.
If during calibration the setpoint is found to be conservative with respect to the Limiting Safety System Setting but outside its predefined calibration tolerance, then the channel shall be brought back to within its predefined calibration tolerance before returning the channel to service. The calibration tolerances are specified in a document controlled under 10 CFR 50.59.
If during calibration the setpoint is found to be conservative with respect to the Limiting Safety System Setting but outside its predefined calibration tolerance, then the channel shall be brought back to within its predefined calibration tolerance before returning the channel to service. The calibration tolerances are specified in a document controlled under 10 CFR 50.59.
Serial No. 08-0151 Docket Nos. 50-280 and 281 Revised Insert "0" for Tables 3.7-2. 3.7-3. and 3.7 insert at the bottom of pages T5 3.7-18 T5 3.7-19, T5 3.7-20, T5 3.7-20a, T5 3.7-21, T5 3.7-22, T5 3.7-25, T5 3.7-26, and T5 3.7-26a:
There is a Safety Analysis Limit associated with this ESF function.
If during calibration the setpoint is found to be conservative with respect to the Setting Limit but outside its predefined calibration tolerance, then the channel shall be brought back to within its predefined calibration tolerance before returning the channel to service.
The calibration tolerances are specified in a document controlled under 10 CFR 50.59.
Serial No. 08-0151 Docket Nos. 50-280 and 281 ATTACHMENT 3 License Amendment Request to Revise Setting Limits and Overtemperature ~T/Overpower ~T Time Constants Revised Proposed TS Replacement Pages (Typed)
Virginia Electric and Power Company (Dominion)
Surry Power Station Units 1 and 2
- I>
S (1)
- s0-Sg
.....zoen TABLE 3.7-1 REACTOR TRIP INSTRUMENT OPERATING CONDITIONS Minimum Total Number OPERABLE Channels Permissible Functional Unit Of Channels Channels To Trip Bypass Conditions Operator Action I.
Manual 2
2 I
I 2.
Nuclear Flux Power Range*
4 3
2 Low trip setting at P-1O 2
3.
Nuclear Flux Intermediate Range*
2 2
I P-1O 3
4.
Nuclear Flux Source Range*
P-6
- a. Below P Note A 2
2 I
4
- b. Shutdown - Note B 2
I 0
5 5.
Overtemperature LlT*
3 2
2 6
I 6.
Overpower LlT**
3 2
2 6
I I 7.
Low Pressurizer Pressure*
3 2
2 P-7 7
I 8.
Hi Pressurizer Pressure*
3 2
2 6
I Note A - With the reactor trip breakers closed and the control rod drive system capable of rod withdrawal.
Note B - With the reactor trip breakers open.
- There is a Safety Analysis Limit associated with this Reactor Trip function. If during calibration the setpoint is found to be conservative with respect to the Limiting Safety System Setting but outside its predefined calibration tolerance, then the channel shall be brought back to within its predefined calibration tolerance before returning the channel to service. The calibration tolerances are specified in a document controlled under 10 CFR 50.59.
- If during calibration the setpoint is found to be conservative with respect to the Limiting Safety System Setting but outside its predefined calibration tolerance, then the channel shall be brought back to within its predefined calibration tolerance before returning the channel to service. The calibration tolerances are specified in a document controlled under 10 CFR 50.59.
>-3 en w
~
I-o
TABLE 3.7-1 REACTOR TRIP INSTRUMENT OPERATING CONDITIONS Permissible Bypass Conditions Operator Action Functional Unit 9.
Pressurizer-Hi Water Level*
- 10. Low Flow*
Total Number Of Channels 3
3/100p Minimum OPERABLE Channels 2
21l00p in each operating loop Channels To Trip 2
2/100p in any operating loop 21l00p in any 2 operating loops P-7 P-8 P-7 7
7 7
- There is a Safety Analysis Limit associated with this Reactor Trip function. If during calibration the setpoint is found to be conservative with respect to the Limiting Safety System Setting but outside its predefined calibration tolerance, then the channel shall be brought back to within its predefined calibration tolerance before returning the channel to service. The calibration tolerances are specified in a document controlled under 10 CFR 50.59.
- If during calibration the setpoint is found to be conservative with respect to the Limiting Safety System Setting but outside its predefined calibration tolerance, then the channel shall be brought back to within its predefined calibration tolerance before returning the channel to service. The calibration tolerances are specified in a document controlled under 10 CFR 50.59.
~::s0..S
~g Zo
- 11. Turbine Trip
- a. Stop valve closure 4
1 4
- b. Low fluid oil pressure 3
2 2
- 12. Lo-Lo Steam Generator Water 31l00p 2/100p in each 21l00p in Level*
operating loop any operating loops
- 13. Underfrequency 4KV Bus 3-1/bus 2
2
- 14. Undervoltage 4KV Bus 3-1/bus 2
2
- 15. Safety Injection (SI) Input 2
2 1
FromESF
- 16. Reactor Coolant Pump l/breaker l/breaker per 1
Breaker Position operating loop 2
P-7 P-7 P-7 P-7 P-8 P-7 7
7 6
7 7
11 9
9
>-3 CIJ UJ
-.]
I.....
II 8
11 13 13 Operator Action 6
Permissible Bypass Conditions 1
2 1
Channels To Trip 1/100p-level coincident with l/loop-flow mismatch in same loop 1
1 2
2 3
2 2
2 2
4 Total Number Of Channels 2/100p-level and 2/l00p-flow mismatch TABLE 3.7-1 REACTOR TRIP INSTRUMENT OPERATING CONDITIONS Minimum OPERABLE Channels l/loop-level and 2/100p-flow mismatch or 2/l00p-level and 1I100p-flow mismatch 2
1 Functional Unit
- 17. Low steam generator water**
level with steamlfeedwater flow mismatch
- 18. a. Reactor Trip Breakers
- b. Reactor Trip Bypass Breakers - Note C
- 19. Automatic Trip Logic
- 20. Reactor Trip System Interlocks - Note D
- a. Intermediate range neutron flux, P-6
- b. Low power reactor trips block, P-7 Power range neutron flux, P-lO and Turbine impulse pressure 2
2 1
13
- c. Power range neutron flux, P-8*
4 3
2 13
~
- d. Power range neutron flux, P-lO 4
3 2
13 5.
- e. Turbine impulse pressure 2
2 1
13
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Note C - With the Reactor Trip Breaker open for surveillance testing in accordance with Specification Table 4.1-1 (Item 30) i Note D - Reactor Trip System Interlocks are described in Table 4.l-A o
- There is a Safety Analysis Limit associated with this Reactor Trip function. If during calibration the setpoint is found to be conservative with respect to the Limiting Safety System Setting but outside its predefined calibration tolerance, then the channel shall be brought back to within its predefined calibration tolerance before returning the channel to service. The calibration tolerances are specified in a document controlled under 10 CFR 50.59.
- If during calibration the setpoint is found to be conservative with respect to the Limiting Safety System Setting but outside its predefined calibration tolerance, then the channel shall be brought back to within its predefined calibration tolerance before returning the channel to service. The calibration tolerances are specified in a document controlled under 10 CFR 50.59.
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Functional Unit TABLE 3.7-2 ENGINEERED SAFEGUARDS ACTION INSTRUMENT OPERATING CONDITIONS Total Minimum Number OPERABLE Channels Of Channels Channels To Trip Permissible Bypass Conditions Operator Actions 3/steam line 2/steam line 1.
SAFETY INJECTION (SI)
- a. Manual
- b. High containment pressure*
- c. High differential pressure between any steam line and the steam header*
2 4
2 3
1 3
2/steam line on any steam line Primary pressure less than 2010 psig, except when reactor is critical 21 17 20
- d. Pressurizer low-low pressure*
3 2
2 Primary pressure less than 20 20I0 psig, except when reactor is critical
- e. High steam flow in 2/3 steam lines coincident with low Tavg or low steam line pressure*
- 1) Steam line flow*
2/steam line lIsteam line lIsteam line Reactor coolant Tavg less than 545 0
20 any two lines during heatup and cooldown
>3
- 2) Tavg*
lIloop l/loop any l/loop any Reactor coolant Tavg less than 545 0 20 (n
- l two loops two loops during heatup and cooldown 0..3 1/line 1/line any two 1/line any two Reactor coolant Tavg less than 5450 (n
- 3) Steam line pressure*
20
- l loops loops during heatup and cooldown Z
0:n
- f. Automatic actuation logic 2
2 1
14
- There is a Safety Analysis Limit associated with this ESF function. If during calibration the setpoint is found to be conservative with respect to the Setting Limit but outside its predefined calibration tolerance, then the channel shall be brought back to within its predefined calibration tolerance before returning the channel to service. The calibration tolerances are specified in a document controlled under 10 CFR 50.59.
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TABLE 3.7-2 (Continued)
ENGINEERED SAFEGUARDS ACTION INSTRUMENT OPERATING CONDITIONS See #1 above (all SI initiating functions and requirements) l/bus l/bus 2
2 transfer 2 transfer buses/unit buses/unit 3/steam 2/steam 2/steam generator generator generator any 1 generator 3/steam 2/steam 2/steam generator generator generator any 2 generators 3
2 2
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en Functional Unit 2.
- a. Manual
- b. High containment pressure (Hi-Hi)*
- c. Automatic actuation logic 3.
- a. Steam generator water levellow-Iow*
- 1) Start motor driven pumps
- 2) Starts turbine driven pump
- b. RCP undervoltage starts turbine driven pump
- c. Safety injection - start motor driven pumps
- d. Station blackout - start motor driven pumps
- Must actuate 2 switches simultaneously Total Number Of Channels 1 set 4
2 Minimum OPERABLE Channels 1 set 3
2 Channels To Trip 1 set*
3 1
Permissible Bypass Conditions Operator Actions 15 17 14 20 20 20 24
- There is a Safety Analysis Limit associated with this ESF function. If during calibration the setpoint is found to be conservative with respect to the Setting Limit but outside its predefined calibration tolerance, then the channel shall be brought back to within its predefined calibration tolerance before returning the channel to service. The calibration tolerances are specified in a document controlled under 10 CFR 50.59.
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Functional Unit TABLE 3.7-2 (Continued)
ENGINEERED SAFEGUARDS ACTION INSTRUMENT OPERATING CONDITIONS Minimum Total NumberOPERABLE Of Channels Channels Channels To Trip Permissible Bypass Operator Conditions Actions 20 14 23 23 24 25 14 25 14 3
1 2
2 1
2 1
2 1
2-1 each 24 MFWpump 1
22 2/bus 26 2/bus 26 3
2 2
2 2
3 2
2/bus 2/bus pump 2
1IMFW 4
2 3
3 2
4 2
3/bus 3/bus 2IMFW pump 2
zo
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AUXILIARY FEEDWATER (continued)
- e. Trip of main feedwater pumps - start motor driven pumps
- f. Automatic actuation logic 4.
LOSS OF POWER
- a. 4.16 kv emergency bus undervoltage (loss of voltage)
- b. 4.16 kv emergency bus undervoltage (degraded voltage) 5.
NON-ESSENTIAL SERVICE WATER ISOLATION
- a. Low intake canal level*
- b. Automatic actuation logic 6.
ENGINEERED SAFEGAURDS ACTUATION INTERLOCKS - Note A
- a. Pressurizer pressure, P-ll
- b. Low-low Tavg, P-12
- c. Reactor trip, P-4
- t>
(Unit 1) 7.
RECIRCULATION MODE TRANSFER S
- a. RWST Level - Low*
2..
- b. Automatic Actuation Logic and Actuation Relays
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(Unit 2) 7.
RECIRCULATION MODE TRANSFER a
- a. RWST Level - Low-Low*
4 3
- b. Automatic Actuation Logic and Actuation Relays 2
2 Note A - Engineered Safeguards Actuation Interlocks are described in Table 4.1-A
- There is a Safety Analysis Limit associated with this ESF function. If during calibration the setpoint is found to be conservative with respect to the Setting Limit but outside its predefined calibration tolerance, then the channel shall be brought back to within its predefined calibration tolerance before returning the channel to service. The calibration tolerances are specified in a document controlled under 10 CFR 50.59.
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TABLE 3.7-2 (Continued)
ENGINEERED SAFEGUARDS ACTION INSTRUMENT OPERATING CONDITIONS Functional Unit (Unit 2) 8.
RECIRCULATION SPRAY
- a. RWST Level - Low Coincident with High High Containment Pressure*
- b. Automatic Actuation Logic and Actuation Relays Minimum Permissible Total NumberOPERABLE Channels Bypass Operator Of Channels Channels To Trip Conditions Actions 4
3 2
20 2
2 I
14
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- There is a Safety Analysis Limit associated with this ESF function. If during calibration the setpoint is found to be conservative with respect to the Setting Limit but outside its predefined calibration tolerance, then the channel shall be brought back to within its predefined calibration tolerance before returning the channel to service. The calibration tolerances are specified in a document controlled under 10 CFR 50.59.
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Operator Actions Permissible Bypass Conditions Channels To Trip TABLE 3.7-3 INSTRUMENT OPERATING CONDITIONS FOR ISOLATION FUNCTIONS Total Minimum Number OPERABLE Of Channels Channels Functional Unit 14 21 17 14 21 14 15 17 4
3 3
2 2
1 2
2 1
4 3
3 2
2 1
1 set I set 1 set*
See Item #l.e Table 3.7-2 for operability requirements See Item #1, Table 3.7-2 (all SI initiating functions and requirements) 2 2
1 2
2 1
STEAMLINE ISOLATION
- a. High steam flow in 2/3 lines coincident with 2/310w Tavg or 2/310w steam pressures*
- Must actuate 2 switches simultaneously 1.
CONTAINMENT ISOLATION
- a. Phase I
- 1) Safety Injection (SI)
- 2) Automatic initiation logic
- 3) Manual
- b. Phase 2
- 1) High containment pressure*
- 2) Automatic actuation logic
- 3) Manual
- c. Phase 3
- 1) High containment pressure (Hi-Hi setpoint)*
- 2) Automatic actuation logic
- 3) Manual
- J>
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- There is a Safety Analysis Limit associated with this ESF function. If during calibration the setpoint is found to be conservative with respect to the Setting Limit but outside its predefined calibration tolerance, then the channel shall be brought back to within its predefined calibration tolerance before returning the channel to service. The calibration tolerances are specified in a document controlled under 10 CFR 50.59.
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TABLE 3.7-3 (Continued)
INSTRUMENT OPERATING CONDITIONS FOR ISOLATION FUNCTIONS Functional Unit STEAMLINE ISOLATION (continued)
Total Number Of Channels Minimum OPERABLE Channels Channels To Trip Permissible Bypass Conditions Operator Actions
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- b. High containment pressure (Hi-Hi setpoint)*
- c. Manual
- d. Automatic actuation logic 3.
TURBINE TRIP AND FEEDWATER ISOLATION
- a. Steam generator water-level high-high*
- b. Automatic actuation logic and actuation relay
- c. Safety injection 4
3 3
l/steamline l/steamline l/steamline 2
2 1
When all MFRV, SG FWIV & associated bypass valves are closed
& deactivated or isolated by manual valves.
3/steam 2/steam 2/in anyone generator generator steam generator 2
2 1
See Item #1 Table 3.7-2 (all SI initiating functions and requirements) 17 21 22 20 22
- There is a Safety Analysis Limit associated with this ESF function. If during calibration the setpoint is found to be conservative with respect to the Setting Limit but outside its predefined calibration tolerance, then the channel shall be brought back to within its predefined calibration tolerance before returning the channel to service. The calibration tolerances are specified in a document controlled under 10 CFR 50.59.
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TABLE 3.7-4 ENGINEERED SAFETY FEATURE SYSTEM INITIATION LIMITS INSTRUMENT SETTING Coincident with Low Tavg or Low Steam Line Pressure*
b) Steam Line Isolation c) Safety Injection Containment Isolation d) F.W. Line Isolation
- 135 psid
- 24 psia
~ 1,770 psig Setting Limit
- 18.5 psia
~ 541°F Tavg
~ 510 psig steam line pressure
- 40% (at zero load) of full steam flow
- 40% (at 20% load) of full steam flow
- 110% (at full load) of full steam flow Channel Action Functional Unit High Containment Pressure (High Containment Pressure Signal)*
High-High Containment Pressure (High-High Containment Pressure Signals)*
Pressurizer Low-Low Pressure*
a) Safety Injection b) Containment Vacuum Pump Trip c) High Press. Containment Isolation d) Safety Injection Containment Isolation e) F.W. Line Isolation a) Containment Spray b) Recirculation Spray c) Steam Line Isolation d) High-High Press. Containment Isolation a) Safety Injection b) Safety Injection Containment Isolation c) F.W. Line Isolation High Differential Pressure Between a) Safety Injection Steam Line and the Steam Line Header* b) Safety Injection Containment Isolation c) F.W. Line Isolation High Steam Flow in 2/3 Steam Lines*
a) Safety Injection No.
1 2
3 4
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TABLE 3.7-4 ENGINEERED SAFETY FEATURE SYSTEM INITIATION LIMITS INSTRUMENT SETTING No.
Functional Unit 6
Steam Generator Water Level Low-Low*
b.
RCP Undervoltage c.
Safety Injection d.
Station Blackout e.
Main Feedwater Pump Trip Channel Action Aux. Feedwater Initiation S/G Blowdown Isolation Aux. Feedwater Initiation Aux. Feedwater Initiation Aux. Feedwater Initiation Aux. Feedwater Initiation Setting Limit
- ?: 16.0% narrow range
- ?: 70% nominal All S.L setpoints
- ?: 46.7% nominal N.A.
7 LOSS OF POWER a.
4.16 KV Emergency Bus Emergency Bus Separation and Diesel start Undervoltage (Loss of Voltage) b.
4.16 KV Emergency Bus Emergency Bus Separation and Diesel start Undervoltage (Degraded Voltage)
- ?: 2975 volts and::; 3265 volts with a 2 (+5, -0.1) second time delay
- ?: 3830 volts and::; 3881 volts with a 60 (+/-3.0) second time delay (Non CLS, Non SI) 7 (+/-0.35) second time delay (CLS or SI Conditions)
- There is a Safety Analysis Limit associated with this ESF function. If during calibration the setpoint is found to be conservative with respect to the Setting Limit but outside its predefined calibration tolerance, then the channel shall be brought back to within its predefined calibration tolerance before returning the channel to service. The calibration tolerances are specified in a document controlled under 10 CFR 50.59.
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NON-ESSENTIAL SERVICE WATER ISOLATION a.
Low Intake Canal Level*
Isolation of Service Water flow to non-essential loads 23 feet-5.85 inches C/J V.l
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Functional Unit Channel Action Setting Limit (Unit 1) 9 RECIRCULATION MODE TRANSFER a.
RWST Level-Low*
Initiation of Recirculation Mode 212.7%
Transfer System
~ 14.3%
(Unit 2) 9 RECIRCULATION MODE TRANSFER a.
RWST Level-Low-Low*
Initiation of Recirculation Mode 212.7%
Transfer System
~ 14.3%
10 TURBINE TRIP AND FEEDWATER ISOLATION a.
Steam Generator Water Level Turbine Trip
~ 76% narrow range High-High*
Feedwater Isolation (Unit 2) 11 RWST Level Low (coincident with High Recirculation Spray Pump Start 259%
High Containment Pressure)*
~61%
- There is a Safety Analysis Limit associated with this ESF function. If during calibration the setpoint is found to be conservative with respect to the Setting Limit but outside its predefined calibration tolerance, then the channel shall be brought back to within its predefined calibration tolerance before returning the channel to service. The calibration tolerances are specified in a document controlled under 10 CFR 50.59.
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