GNRO-2019/00028, Supplement to Revise Technical Specification (TS) 3.3.1.1, Reactor Protection System (RPS) Instrumentation, and TS 3.3.4.1, End of Cycle Recirculation Pump Trip (EOC-RPT) Instrumentation

Supplement to Revise Technical Specification (TS) 3.3.1.1, Reactor Protection System (RPS) Instrumentation, and TS 3.3.4.1, End of Cycle Recirculation Pump Trip (EOC-RPT) Instrumentation

ML19164A281
Person / Time
Site:	Grand Gulf
Issue date:	06/13/2019
From:	Gaston R Entergy Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
GNRO-2019/00028
Download: ML19164A281 (27)

Text

• *

• ===*Ent ergx GNR0-2019/00028 June 13, 2019 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Entergy Operations, Inc.

1340 Echelon Parkway Jackson, MS 39213 Tel 601-368-5138 Ron Gaston Director, Nuclear Licensing 10 CFR 50.90

Subject:

Supplement to Revise Technical Specification (TS) 3.3.1.1, "Reactor Protection System (RPS) Instrumentation," and TS 3.3.4.1, "End of Cycle Recirculation Pump Trip (EOC-RPT) Instrumentation" Grand Gulf Nuclear Station, Unit 1 NRC Docket No. 50-416 Renewed Facility Operating License No. NPF-29 By "GNRO-2019/00003, Application to Revise Technical Specification (TS) 3.3.1.1, Reactor Protection System (RPS) Instrumentation, and [[TS" contains a listed "[" character as part of the property label and has therefore been classified as invalid., End of Cycle Recirculation Pump Trip (EOC-RPT) Instrumentation|letter dated January 23, 2019]] (Reference 1 ), Entergy Operations Inc. (Entergy) requested an amendment to Renewed Facility Operating License NPF-29 for Grand Gulf Nuclear Station, Unit 1 (GGNS). The proposed amendment revises the Allowable Value (AV) for the Turbine Stop Valve Closure Trip Oil Pressure Function and Turbine Control Valve Fast Closure Trip Oil Pressure Function. Additionally, the proposed amendment adds new Notes to assess channel performance during testing that verifies instrument channel setting values established by the Entergy setpoint methodology.

The Nuclear Regulatory Commission (NRC) transmitted three clarification questions concerning the license amendment request to Entergy in the Reference 2 emails. This supplement provides responses to the three clarification questions and a corrected Technical Specifications (TS) page that supplants the equivalent page provided in Reference 1.

Subsequent to the submittal of Reference 1, Entergy performed additional reviews of the three pressure transmitters described in the Enclosure to Reference 1 and identified potential risks associated with these transmitters. As a result, Entergy will utilize a different safety related pressure transmitter for transmitting the trip signals to the RPS. Therefore, this supplement also provides a revision to the pressure transmitter setpoint information originally provided in the Enclosure to Reference 1.

GNR0-2019/00028 Page 2 of 3 The Enclosure to this letter provides the responses to the three clarification questions. provides corrections made to the originally submitted marked-up TS page. provides corrections made to the originally submitted clean-typed TS page. provides a corrected TS Bases page marked to show the proposed changes, for information only. Attachment 4 provides a rewrite of Sections 3.1.1 and 3.1.2 of the Enclosure to Reference 1.

No new regulatory commitments are made in this submittal. The responses to the three clarification questions do not impact the No Significant Hazards Consideration analysis that was provided in Reference 1.

In accordance with 10 CFR 50.91, "Notice for public comment; State consultation," a copy of this application, with attachments, is being provided to the designated State officials.

This letter contains no new regulatory commitments. If you have any questions or require additional information, please contact Thomas Fay, Acting Regulatory Assurance Manager, at 601-437-2103.

I declare under penalty of perjury that the foregoing is true and correct. Executed on June 13, 2019.

Respectfully, iJ/4uv;l~

Ron Gaston RWG/rws

Enclosure:

Supplement to Revise Technical Specification (TS) 3.3.1.1, "Reactor Protection System (RPS) Instrumentation," and TS 3.3.4.1, "End of Cycle Recirculation Pump Trip (EOC-RPT) Instrumentation" Attachments: 1. Corrections Made to Original Submittal Technical Specifications (Mark-up)

2. Corrections Made to Original Submittal Technical Specifications (Clean-Typed Pages)

3. Corrected Technical Specification Bases Changes (Mark-up) (For Information Only)

4. Rewrite of Sections 3.1.1 and 3.1.2 of Enclosure to GNR0-2019/00003

GNR0-2019/00028 Page 3 of 3

References:

1. Entergy Operations, Inc. (Entergy) letter to the Nuclear Regulatory Commission (NRC), "Application to Revise Technical Specification (TS) 3.3.1.1, 'Reactor Protection System (RPS) Instrumentation,' and TS 3.3.4.1, 'End of Cycle Recirculation Pump Trip (EOC-RPT)

Instrumentation'," dated January 23, 2019 (ADAMS Accession No. ML19023A555)

2. Electronic messages (emails) from S. Lingam (NRC) to D. A. Neve (Entergy), "Grand Gulf - Clarifications for LAR Regarding TCV Fast Closure Setpoint Change, TS 3.3.1.1 (RPS Instrumentation) and TS 3.3.4.1 (EOC Recirculation Pump Trip Instrumentation) (EPID L-2019-LLA-0007)," dated April 25, 2019 and May 9, 2019 cc:

NRC Regional Administrator, Region IV NRC Senior Resident Inspector, Grand Gulf Nuclear Station, Unit 1 Dr. Thomas Dobbs, State Health Officer, Mississippi State Department of Health NRC Project Manager, Grand Gulf Nuclear Station, Unit 1

Enclosure GNR0-2019/00028 Supplement to Revise Technical Specification (TS) 3.3.1.1, "Reactor Protection System (RPS) Instrumentation," and TS 3.3.4.1, "End of Cycle Recirculation Pump Trip (EOC-RPT) Instrumentation" Grand Gulf Nuclear Station, Unit 1.

Corrections Made to Original Submittal Technical Specifications (Mark-up).

Corrections Made to Original Submittal Technical Specifications (Clean-Typed Pages).

Corrected Technical Specification Bases Changes (Mark-up) (For Information Only).

Rewrite of Sections 3.1.1 and 3.1.2 of Enclosure to GNR0-2019/00003

GNR0-2019/00028 Enclosure Page 1 of 5

1.

Background

In Reference 1, Entergy Operations, Inc. (Entergy) requested an amendment to Renewed Facility Operating License NPF-29 for Grand Gulf Nuclear Station (GGNS) Unit 1. The proposed amendment revises Technical Specification (TS) Table 3.3.1.1-1, "Reactor Protection System Instrumentation," Function 9, "Turbine Stop Valve Closure, Trip Oil Pressure - Low," and Function 10, "Turbine Control Valve Fast Closure, Trip Oil Pressure -

Low," and TS 3.3.4.1, "End of Cycle Recirculation Pump Trip (EOC-RPT) Instrumentation,"

Surveillance Requirement (SR) 3.3.4.1.2 and SR 3.3.4.1.3. The proposed change revises the Allowable Value (AV) for the Turbine Stop Valve Closure Trip Oil Pressure Function and Turbine Control Valve Fast Closure Trip Oil Pressure Function. Additionally, the proposed amendment adds new Notes to assess channel performance during testing that verifies instrument channel setting values established by the Entergy setpoint methodology.

The Nuclear Regulatory Commission (NRC) transmitted three clarification questions concerning the license amendment request (LAR) in the Reference 2 emails. The following provides the Entergy response to the clarification questions.

2.

NRC Clarification Questions EICB Question-1 The LAR proposes to add two new Notes (d) and (e) to SR 3.3.1.1.8 and SR 3.3.1.1.12 for Functions 9 and 1 O in GGNS TS Table 3.3.1.1-1 to meet the guidance of TSTF-493, as described below:

l\\PPLICl\\BLE MODl::S OR O'rHER SPECIFIED f'UNC'r!ON COND!TIONS

9.

TurC>ine Stop Valve Cl()sure 1

~ 3S.4 '~ R':'P 7ci9 Oi l Pressuc~ -

Low

10.

Tur~in~ Control ~~lve Fast Closure, ~rip Oil Pres.:; UI"(! -

LOW

~ 35.4\\ RTP REQUIRED Clil\\NNELS nR TRIP SYS'rEM CONDIT!ONS REf't:RENCED FROM REQU I RED ACTION D. l E

SCRVEI LLANCI:

ALLOWABLE REQUIREMEN~S VAL~U E

644 psig SR J.J.1.1.8~>

37 poi~

SR J. 3. J. 1. 9 SR 3.3.1. l. l~

SR 3. 3.1. 1.13 d)(e)

SR J. J.1. 1. H SR

3. 3.1.l. 15 SR SR SR SR SP.

SR However, in Attachment 2 of LAR, "Revised Technical Specification Page (Clean), TS Table 3.3.1.1 -1 version showed that Note ( d) is proposed to add to SR 3.3.1.1.8 and Note ( e) is proposed to add to SR 3.3.1.1.12, as described below:

GNR0-2019/00028 Enclosure Page 2 of 5 FUNCflON 9

T urll,ne Slop Valve CIOSl,J& Trip Oif Pressure -Low 10 Turoine Cantre, Valve Fas1 cios,re T"P o,*

Pressu r6 Low APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS

, 35 4% RTP

, 35.4% RTP REOURED CH.'-NNELS PER TRIP SYSTEM CONDITIONS REFEREt,CE DFROM REQUIRED SURVEILLANCE ACTION D 1 REQUIREMENTS F

SR 3 3.1 1.6 (d)

SR33119 SR 331112 /eJ SR331113 SR 3 3 1.1 14 SRJ.3.1.1.15 E

SR 3 3 1.1 8 (<:)

SR331.19 SR 3 3 1 1 12 <ei SR331.113 SR3 31.1 14 SR 3.3 1 1 15 ALLOWABLE VALUE

' 644 ps,g

' 938 ps1g Entergy, please clarify why both Notes (d) and (e) are not included for SR 3.3.1.1.8 and SR 3.3.1.1.12.

Entergy Response to EICB Question-1:

The revised (clean) TS page 3.3-8 (TS Table 3.3.1.1-1, page 4 of 4) was in error (typographical). Attachment 2 provides a corrected revised (clean) TS page 3.3-8 and includes the changes discussed in the response to EICB Question-2 below.

EICB Question-2 In this LAR, the new Notes (d) and/or (e) are proposed adding to SR 3.3.1.1.8 (Perform Channel Functional Test) and SR 3.3.1.1.12 (Perform Channel Calibration) of Functions 9 and 10 in TS Table 3.3.1.1 -1. In addition, the new Notes 1 and 2 (similar to new Notes (d) and (e) in proposed Table 3.3.1.1-1) are proposed to add to TS SR 3.3.4.1.2 (Calibrate the trip units) and TS SR 3.3.4.1.3 (Perform Channel Calibration).

In this LAR, Entergy stated, in part, that "The proposed change also incorporates Technical Specification Task Force (TSTF) Traveler TSTF-493-A, Revision 4, "Clarify Application of Setpoint Methodology for LSSS Functions"." In Section 2.5 of LAR "Variations", Entergy provided the following table to summarize the differences between the TSTF-493-A, Rev. 4 numbering and the GGNS TS numbering:

GGNS TS 3.3.11 Table TIU::,---.

NUREG-1434, General Electric BWR-6 Plants Reactor Protection System Instrumentation TSTF-493-A, Revision 4

~

Specification 3.3.1.1 "Reactor Protection Sy(:;temJRPSlJ.n$lrumer,talion" __

, Function 9: Notes (a) and (b) are applied to Function 9. Notes (d) and {e) are applied to I SR 3.3.1.1.~~~~ ~R_ 3_:_~:_!.:]_:_~.!____ l SR 3.3.1.1.8 and _S_R_3_3_.1_.1_.1_2 _ ____

1 Function 10: Notes (a) and (b) are applied to I Function 10: Notes (d) and (e) are appfied to SR 3.3.1.1.8 and SR 3.3. 1.1.11 SR 3.3. 1.1.8 and SR 3.3.1.1.12 The NRC staff reviewed the GGNS TS, the Transmittal of Revised TSTF-493, Revision 4 (ML100060064) and NUREG-1434 (ML12104A195) and founds the variations described below (do not include the differences between the TSTF-493-A, Rev. 4 numbering and the GGNS TS numbering):

GNR0-2019/00028 Enclosure Page 3 of 5 TSTF-493-A, Revision 4 NUREG-1434, General Electric BWR-6 Plants Specification 3.3.1.1 "Reactor Protection System (RPS) Instrumentation" Function 9: Notes (a) and (b) are applied to SR 3.3.1.1.8 (Calibrate the trip units) and SR 3.3.1.1.11 (Perform Channel Calibration)

Function 1 O: Notes (a) and (b) are applied to SR 3.3.1.1. 8 (Calibrate the trip units) and SR 3.3.1.1.11 (Perform Channel Calibration)

GGNS TS 3.3.1.1 Table 3.3.1.1-1 Reactor Protection System Instrumentation Function 9: Notes (d) and (e) are applied to SR 3.3.1.1.8 (Perform Channel Functional Test) and SR 3.3.1.1.12 (Perform Channel Calibration)

Function 10: Notes (d) and (e) are applied to SR 3.3.1.1.8 (Perform Channel Functional Test) and SR 3.3.1.1.12 (Perform Channel Calibration)

Entergy to clarify why there are variations between the TSTF-493-A and LAR.

Entergy Response to EICB Question-2:

Upon further review of TSTF-493-A, Revision 4, and the GGNS TSs, Entergy has identified that the proposed TS page 3.3-8 changes (markups) in Attachment 1 of Reference 1 were in error. The proposed TS changes should have had Notes (d) and (e) applied to SR 3.3.1.1.9 instead of SR 3.3.1.1.8 for Functions 9 and 1 O. GGNS TS surveillance SR 3.3.1.1.9, "Calibrate the trip units" is equivalent to SR 3.3.1.1.8 in NUREG-1434. A revised TS markup page is provided in Attachment 1. Revised TS Bases changes (for information only) are provided in Attachment 3 and replace pages B 3.3-26 and Insert B 3.3-26 of Reference 1.

GNR0-2019/00028 En~losure Page 4 of 5 EICB Question-3 LAR Paragraphs 3.1.1 (Calculation for Function 9) and 3.1.2 (Calculation for Function 10),

Entergy provided 2 Tables, "Summary of Results" and "Summary of Calibration Tolerances" for each of the two Functions 9 and 10.

The NRC staff restated the relationships of the values in the diagram below:

Grand Gulf Allowable Value, Nominal Trip Setpoints with As-Left and As Found Loop Tolerance, and Analytical Limit Relationships Row Function Function

1. 9

1. 10 Pressure (psiq) 1 Low-AL 614.00 2

NTSP (?:)

666.00 3

AV(?:)

643.61 4

C: ALTL(:i:)

16.16 5

D: AFTL (:i:)

29.45 6

NTSP + C 682.16 7

NTSP-C 649.84 8

NTSP + 0 695.45 9

NTSP

• D 636.55 t\\TSF fv:,-nrs Tr pS-':'~:,,..t ;.~, /.. ': 1~C-: \\ *s.... -:-..:.t\\*.:.. _ _ :,,\\ ks ;<~...,Mt C A7-'='~...:,,ocToe-rs.r:e-..:.._r_ C.:.:-F~... --c..c,.,pT:,~-~":e-AF'".

908.00 960.00 937.61 16.16 29.45 976.16 943.84 992.32 930.55 Respect to AV

>AV

>AV

>AV

>AV

>AV

>AV

>AV This diagram shows that the proposed AFTL goes beyond the proposed AV.

In the GGNS TS Bases, Bases B.3.3.1.1, "Reactor Protection System (RPS) Instrumentation,"

states:

"Allowable Values are specified for each RPS Function specified in the Table. Nominal trip setpoints are specified in the setpoint calculations. The nominal setpoints are selected to ensure that the actual setpoints do not exceed the Allowable Value between successive CHANNEL CALIBRATIONS. Operation with a trip setpoint less conservative than the nominal trip setpoint, but within its Allowable Value, is acceptable. A channel is inoperable if its actual trip setpoint is not within its required Allowable Value."

However, the proposed AFTL goes beyond the proposed AV. Please explain the discrepancy between the LAR and the TS Bases.

GNR0-2019/00028 Enclosure Page 5 of 5 Entergy Response to EICB Question-3:

Reference 1 identified that the transmitter manufacturer and model number was not finalized and was to be one of three models (Hydac Model HDA4700, STW Model M01, and Measurement Specialties Model P981/4). Subsequent to the submittal of Reference 1, Entergy performed additional reviews of the three transmitters and identified potential risks associated with these transmitters. As a result, Entergy will utilize safety related Rosemount pressure transmitters for transmitting the trip signal to the RPS. Calculations JC-01 C71-N606-1, Revision 2, "Instrument Loop Uncertainty and Setpoint Determination for System 1C71 Loop N606, Reactor Scram on Turbine Stop Valve Closure," and Calculation JC-01 C71-N605-1, Revision 4, "Turbine Control Valve Fast Closure Scram Setpoint Validation,"

have been further revised to reflect the use of the Rosemount pressure transmitters. The revisions to the calculations impact Sections 3.1.1 and 3.1.2 in the Enclosure to Reference 1. provides new Sections 3.1.1 and 3.1.2 and replaces in its entirety these Sections in the Enclosure to Reference 1.

The below table summarizes the results of the information in the revised Section 3.1.1 and Section 3.1.2 for TS Table 3.3.1.1-1 Function 9, "Turbine Stop Valve Closure, Trip Oil Pressure - Low," and Function 10, "Turbine Control Valve Fast Closure, Trip Oil Pressure -

Low." The use of the Rosemount pressure transmitters and the revised calculations result in the proposed AFTL being greater than the proposed AV. As such, a discrepancy between the LAR and the TS Bases will not exist.

Function 9 Function 10 Value Pressure (psig)

Respect to AV Pressure (psig)

Respect to AV Low-AL 614.00 908.00 NTSP (~)

675.00 970.00 AV(~)

643.08 937.08 ALT LAV(+/-)

9.60 9.60 AFTL AV(+/-)

23.63 23.63 NTSP + ALTL 684.60

~AV 979.60

~AV NTSP - ALTL 665.40

~AV 960.40

~AV NTSP + AFTL 698.63

~AV 993.63

~AV NTSP-AFTL 651.37

~AV 946.37

~AV REFERENCES

1.

Letter GNR0-2019/00003 from M. K. Halter (Entergy Operations, Inc.) to the USNRC, "Application to Revise Technical Specification (TS) 3.3.1.1, 'Reactor Protection System (RPS) Instrumentation,' and TS 3.3.4.1, 'End of Cycle Recirculation Pump Trip (EOC-RPT) Instrumentation'," January 23, 2019. (ADAMS Accession No. ML19023A555)

2.

Electronic messages (emails) from S. Lingam (NRC) to D. A. Neve (Entergy Operations, Inc.), "Grand Gulf - Clarifications for LAR Regarding TCV Fast Closure Setpoint Change, TS 3.3.1.1 (RPS Instrumentation) and TS 3.3.4.1 (EOC Recirculation Pump Trip Instrumentation) (EPID L-2019-LLA-0007)," dated April 25, 2019 and May 9, 2019.

Enclosure, Attachment 1 GNR0-2019/00028 Corrections Made to Original Submittal Technical Specifications (Mark-up)

TS PAGE 3.3-8

RPS Instrumentation 3.3.1.1 Table J.3.1.1-1 (page 4 of 4)

Reactor Protection Systern I~strument3ticn APPLIO,ELE CONDITIONS HO!JES CR REQUIREL' REf'ERENCED OTHER CnANNELS FROM SPE::IF'!ED PER TR!P F'UNCT : ON COND!T IONS SYSTEM REQUIRED ACTLON D.l Sl'P.\\'E I LLAtlCE REQU IREMEN':'S ALLOWABLE VALUE

9.

Turbi~e Stor Valve Clcsure,

~rip 011 Pre~surc -

Lo~

~ 35.H R':'P SR SR SR SR SP.

SR

/

0

=-=..,. _t:::.'

a. J. l. I. o

<!, *.-G->~

J. J. 1. 1.;, :'E---..

~

3. 3. l. l. l ~~

3. J. 1. 1. 13 \\""

(d)(e)

).].l.l.1'1 3.3.1.1.15

10.

Turhine :o~trol Valve rast Closure, ~rip Oil Pressure -

Low

~ 35. H R':'P E

SR J.3. 1.1.8 SR J.3.1.1.,

SR J. 3. l. l. L:

SR

3. 3. l.1.13 *,

5P.

3.3.1.1.1'1 SR 3.J.l.1.1 5

11.

Reil::lor Mode Switch -

Shutd~wn P~siti~c l, ~

H SR 3.3.1.1.11 NA

.3R 3.3.1.1 13 S (a I SR 3.3.l. l. ll NA SR 3.J.1.l.13

12.

Manuai Se r~~

1, 2 H

SR 3.3.l.1.~

NA 1'11

/di SR 3. 3. 1 :. 1 3 SR 3. 3. l. :. q N.~

Sfi 3.3. 1.:.1 3 W1Lh a ny c~ntro l rod withdrawn fro~ a c o re c~ll c~ntaining o~c or mo r~ tuel a~s smblics.

If the as-found channel setpoint is outside it, pre-defined as-found tolerance then the channel shall be evaluated to veniy that 1t is functioning as required before returning the chanrel to service The instrument channel setpoint shall be reset to a value that is within the as-left tolerance around the Non1ina! Trio Setpoint (NTSP) at the completion of the surveillance otherwise. t11e ct1arnei shall be declared inoperable. Setpoin!s more conservative than the NTSP are acceptable provided the as-found and as-left tolerances apply to tl1e actual setpoint implemented in the Surveillance procedures to confirm channel performance The NTSP and the methodologies used to determine the as-found and as-left tolerances are specified 1n tt1e Technical Requirements Manual GRAND GULF 3.3 - 3 Amendment No. ~

, 1 ::i :

644 psi~

Enclosure, Attachment 2 GNR0-2019/00028 Corrections Made to Original Submittal Technical Specifications (Clean-Typed Pages)

TS PAGE 3.3-8

RPS Instrumentation 3. 3. 1.1 Table 3.3.1.1-1 (page 4 of 4)

Reactor Protection System Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION D.1 REQUIREMENTS VALUE

9.

Turbine Stop Valve 2 35.4% RTP 4

E SR 3.3.1.1.8 2 644 psig Closure.Trip Oil Pressure -Low SR 3.3.1.1 9sd)~e)

SR 3.3.1.1.1 (d (e)

SR 3.3.1.1.13 SR 3.3.1.1.14 SR 3.3.1.1.15

10.

Turbine Control Valve 2 354% RTP 2

E SR 3.3.1.1.8 2 938 psig Fast Closure, Trip Oil SR 3.3.1.1.9sd)~e)

Pressure -Low SR 3.3.1.1.1 (d (e)

SR 3.3.1.1.13 SR 3.3.1.1.14 SR 3.3.1.1.15

11.

Reactor Mode Switch -

1,2 2

H SR 3.3.1.1.11 NA Shutdown Position SR 3.3.1.1.13 5(a)

SR 3.3.1.1.11 2

SR3.3.1.113 NA

12.

Manual Scram 1,2 2

H SR 3.3.1.1.4 NA SR 3.3.1.1.13 5(a)

SR 3.3.1.1.4 2

SR 3.3.1.1.13 NA (a)

With any control rod withdrawn from a core cell containing one or more fuel assemblies.

(d)

If the as-found channel setpoint is outside its pre-defined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.

(e)

The instrument channel setpoint shall be reset to a value that is within the as-left tolerance around the Nominal Trip Setpoint (NTSP) at the completion of the surveillance; otherwise. the channel shall be declared inoperable. Setpoints more conservative than the NTSP are acceptable provided the as-found and as-left tolerances apply to the actual setpoint implemented in the Surveillance procedures to confirm channel performance. The NTSP and the methodologies used to determine the as-found and as-left tolerances are specified in the Technical Requirements Manual.

GRAND GULF 3. 3-8 Arr.endmen t No. H-t+, -+/--9-+/--,

Enclosure, Attachment 3 GNR0-2019/00028 Corrected Technical Specification Bases Changes (Mark-up) (For Information Only)

TS Bases Page B3.3-27

BASES SURVEILLANCE REQUIREMENTS (continued)

GRAND GULF SR 3.3.1.1.9 RPS Instrumentation B 3.3.1.1 The calibration of trip units provides a check of the actual trip setpoints.

The channel must be declared inoperable if the trip setting is discovered to be less conservative than the Allowable Value specified in Table 3.3.1.1-1.

If the trip setting is discovered to be less conservative than accounted for in the appropriate setpoint methodology, but is not beyond the Allowable Value, the channel performance is still within the requirements of the plant safety analysis.

Under these conditions, tre setpo i nt must be readjusted to be equal to or more conservative than accounted for in the appropriate setpoint methodology.

The Frequency of 92 days for SR 3.3.1.1.9 is based on the

/V._,.....,....~1~*1~*.......,..._..._n.alysis of Reference 9.

SR 3.3.1.1.10. SR 3.3.1.1.12 and SR 3.3.1.1.17 A CHANNEL CALIBRATION is a complete check of the instrument loop and the sensor.

This test verifies the channel responds to the measured parameter withir the necessary range and accuracy.

CHANNEL CALIBRATION leaves the channel adjusted to account for instrument drifts between successive calibrations consistent with the plant specific setpoint methodology.

Note 1 states that neutron detectors are excluded from CHANNEL CALIBRATION because of the difficulty of simulating a meaningful signal.

Changes in neutron detector sensitivity are compensated for by performing the 7 day calorimetric calibration (SR 3.3.1.1.2) and the 2000 MWO/T LPRM calibration against the TIPs (SR 3.3.1.1.7).

A second Note is provided that requires the APRM and !RM SRs to be performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of entering MODE 2 from MODE 1.

Testing of the MODE 2 APRM and IRM Functions cannot be performed in MODE 1 without utilizing jumpers, lifted leads or movable links.

This Note allows entry into MODE 2 from MODE 1 if the associated Frequency is not met per SR 3.0.2.

Twelve hours is based on operating experience and in consideration of providing a reasonable time in which to complete the SR.

(continu d B 3.3-27 LDC 07045

INSERT B 3.3-27 SR 3.3.1.1.9 for the designated function is modified by two Notes identified in Table 3.3.1.1-1.

The first Note requires evaluation of channel performance for the condition where the as-found setting for the channel setpoint is outside its as-found tolerance but conservative with respect to the Allowable Value. Evaluating channel performance will verify that the channel will continue to behave in accordance with safety analysis assumptions and the channel performance assumptions in the setpoint methodology. The purpose of the assessment is to ensure confidence in channel performance prior to returning the channel to service. Performance of these channels will be evaluated under the Corrective Action Program. Entry into the Corrective Action Program ensures required review and documentation of the condition to establish a reasonable expectation for continued OPERABILITY.

The second Note requires that the as-left setting for the channel be within the as-left tolerance of the Nominal Trip Setpoint (NTSP). Where a setpoint more conservative than the NTSP issued in the plant surveillance procedures, the as-left and as-found tolerances, as applicable, will be applied to the surveillance procedure setpoint. This will ensure that sufficient margin to the Safety Limit and/or Analytical Limit is maintained. If the as-left channel setting cannot be returned to a setting within the as-left tolerance of the NTSP, then the channel shall be declared inoperable. The second Note also requires the NTSP and the methodologies for calculating the as-left and the as-found tolerances to be in the Technical Requirements Manual.

Enclosure, Attachment 4 GNR0-2019/00028 Rewrite of Sections 3.1.1 and 3.1.2 of Enclosure to GNR0-2019/00003

GNR0-2019/00028 Enclosure, Attachment 4 Page 1 of 10 3.1.1 Calculation for Function 9, "Turbine Stop Valve Closure, Trip Oil Pressure - Low" Calculation JC-01 C71-N606-1, Revision 2, "Instrument Loop Uncertainty and Setpoint Determination for System 1 C71 Loop N606, Reactor Scram on Turbine Stop Valve Closure,"

determines the instrument loop uncertainty and limiting AV and setpoints for instrument loops 1 C71-N606A-H. The values generated by this calculation are in accordance with Standard GGNS-JS-09.

The nomenclature of Standard GGNS-JS-09, Section 1.6, is used. Errors associated with the transmitter will be subscripted with a "1 ", errors associated with the trip unit will be subscripted with a "2", while loop errors will be subscripted with an "L". For example, DR1 would be the transmitter drift, DR2 would be the trip unit drift,. and DL would be the loop drift.

Transmitter (1 C71-PT-N006A-H) Uncertainty Effects Manufacturer Model Reference Accuracy (RA)

Temperature Effect (TE)

Humidity Effects (HE)

Radiation Effects (RE)

Power Supply Effects (PS)

Seismic Effects (SE)

Static Pressure Effects (SPE)

Overpressure Effects (OVP)

Drift (DR)

Temperature Drift (TD)

Rosemount 3152NG, Range Code 6, Output Code A Upper Range Limit (URL) 4000 psig Span 3000 psig

+/- 0.25% span

+/- (0.15% URL+ 0.6% Span) per 100°F N/A-Humidity Limits Oto 100% relative humidity

+/- 0.25% URL

+/- 0.005% Span per Volt

+/- 0.20% URL During, Within Reference Accuracy After N/A for all models per Assumption 1 O N/A - The maximum pressure the transmitter will be exposed to is 3000 psig. This is less than the range of the transmitter, which is 4000 psig. Therefore, the transmitter will not be exposed to overpressure conditions.

+/- (0.1 % span + 0.1 % URL) per 30 months See Assumption 3 for all models

GNR0-2019100028 Enclosure, Attachment 4 Page 2 of 10 Manufacturer Model Trip Unit (1 C71-PIS-N606A-H) Uncertainty Effects Rosemount (Units A, C, D, E, F, G, H) 51 ODU (Unit B) 710 DU Reference Accuracy (RA)

+/- 0.20% span Temperature Effect (TE)

NIA - Included in Reference Accuracy Humidity Effects (HE)

NIA - Included in Reference Accuracy Radiation Effects (RE)

NIA-Included in Reference Accuracy Power Supply Effects (PS)

NIA-Included in Reference Accuracy Seismic Effects (SE)

NIA-Included in Reference Accuracy Static Pressure Effects (SPE)

NIA for instrument type Overpressure Effects (OVP)

NIA for instrument type Drift (DR)

NIA - Included in Reference Accuracy Temperature Drift (TD)

NIA-Included in Reference Accuracy The assumptions used in calculation JC-Q1 C71-N606-1 are as follows:

1. Assume all uncertainties given are to two standard deviations (2cr) unless otherwise specified.

2. Since the Turbine Building environment is not addressed in GGNS-E100.0, "Environmental Parameters for GGNS," the environmental specifications listed in the original purchase specification will be assumed as the ambient environment for the transmitters.

3. No Temperature Drift effect (TD) is specified by the transmitter vendor. The vendor published Temperature Effect (TE) will be assumed to be applicable as Temperature Drift (TD) over the temperature range of 65°F to 90°F and over a calibration interval of 30 months (nominal 24 months with a 25% grace period).

4. The accuracy of the Rosemount trip units (+/-0.20% span) is valid for six months. Therefore, drift is included for the first six months after calibration. The trip units are calibrated every 115 days (Assumption 13). Therefore, the drift is included in the Reference Accuracy (RA).

5. Insulation Resistance Effects (IR) are assumed to be negligible since the loop cabling is located in a mild environment (Turbine Building and Control Building).

6. The transmitter Temperature Effect (TE) will be assumed to be applicable from 90°F (the maximum expected calibration temperature) to 150°F (the expected maximum abnormal temperature).

7. The maximum power supply variation is assumed to be+/- 4 volts. This assumption bounds the variation given in vendor documentation for the power supply (24 volts nominal I 22 volts minimum).

GNR0-2019/00028 Enclosure, Attachment 4 Page 3 of 10

8. The radiation drift effect (RD) of the transmitters is assumed to be zero as they are calibrated every 30 months (Assumption 13) and are located in a "B" (mild) radiation zone under normal conditions. However, radiation effects (RE) will be applied for conservatism.

9. Per standard GGNS-JS-09, the M& TE error is normally assumed to be equal to the reference accuracy of the transmitter. Further elaboration and details related to M&TE error are provided below.

10. Static Pressure Effects are not applicable to gauge type transmitters.

11. Process Measurement Effects (PM) are assumed to be zero. Since the transmitters are calibrated during outage conditions, the calibration will occur at a lower ambient temperature than that which will exist during normal operation. Therefore, any variation in EHC fluid density in the reference leg due to ambient temperature changes would result in a bias in the conservative direction with respect to the trip.

12. Drift calculation JC-01111-09014, "Drift Calculation for Gulton/Statham Gage and Differential Pressure Transmitters," was previously used to establish a drift value based on long-term actual calibration results. Since these transmitters are a new installation, there are no long-term actual calibrations results to use. Thus, the drift values are as provided by the manufacturer and JC-01111-09014 is revised to remove the associated transmitters.

13. A transmitter calibration interval of 30 months will be assumed, which is a nominal 24-month period, plus a 25% grace period. A calibration interval of 115 days will be assumed for the trip units, which is a nominal 92-day period, plus a 25% grace period.

14. Since the Rosemount 510DU model is obsolete, they may be replaced with 710DU's in the future. The performance specifications for the 71 ODU are equal to or better than those of the 510DU.

Transmitter Uncertainties Using the vendor data from above:

URL SPAN RA1 (Reference Accuracy)

= 4000 psig

= 3000 psig

= +/- 0.25% span

= +/- (0.25/100)*(3000) psig

= +/- 7.50 psig

GNR0-2019/00028 Enclosure, Attachment 4 Page 4 of 10 Temperature effect will be broken into Temperature Drift (TD) (65-90°F) and Temperature Effect Normal (TEN) (90-150°F) per GGNS JS-09 and Assumption 3.

Span

= 65-90°F = 25°F TD1

= +/- (0.15% URL+ 0.6% Span) per 100°F Span TEN1 RE1 (Radiation Effect)

PS1 (Power Supply Effects)

SE1 (Seismic Effect)

= +/- (((0.15/100)*4000 psig) + ((0.6/100)*3000 psig)))*((90°F -

65°F)/100°F0)

= +/- 6.00 psig

= 90-150°F = 60°F

= +/- (((0.15/100)*4000 psig) + ((0.6/100)*3000 psig)))*((150°F-900F)/100°F)

= +/-14.40 psig

= +/- 0.25% URL

= +/- (0.25/100)*4000 psig

= +/- 10.00 psig Per Assumption 7, the worst power supply variations are+/- 4.0 volts

= +/- 0.005% Span per Volt

= +/- ((0.005/100)*3000 psig))/4 Volts

= +/- 0.0375 psig

= +/- 0.20% URL

= +/- (0.20/100)*4000 psig

= +/- 8.00 psig Drift. The worst case calibration period is 30 months (Assumption 13).

Therefore:

DR1

= +/- (0.1 % span + 0.1 % URL) per 30 months

= +/- ((0.1/100)*(3000 psig)) + ((0.1/100)*(4000 psig))

= +/- 7.00 psig Summarizing for the transmitter:

A1 (Device=+/- SRSS(RA1, TEN1, SE1, RE1, PS1,)

Uncertainty)

= +/- SRSS(7.50, 14.40, 8.00, 10, 0.0375)

= +/- 20.68 psig L 1 (Negative Bias M1 (Positive Bias

= +/- SRSS(DR1, TD1)

= +/- SRSS(7.00, 6.00) psig

= +/- 9.22 psig

= - o.o psig

= + 0.0 psig

GNR0-2019/00028 Enclosure, Attachment 4 Page 5 of 10 RA1 M&TE:

= +/- 7.50 psig (from above)

Per NEDC-31336, "General Electric Instrument Setpoint Methodology," a DMM or equivalent (+/- 0.08 mA) and an equivalent test gauge (.333% of 3000 = +/- 10.00 psig) are used to calibrate the transmitters.

(0.08 mA)(3000 psig/16 mA) = +/- 15.00 psig C1 = SRSS (15.00, 10.00)

= +/- 18.03 psig The setting tolerance from NEDC-31336 is+/- 0.08 mA (0.08 mA)(3000 psig/16 mA) = +/- 15.00 psig The test equipment error, +/- 18.03 psig, is larger than the setting tolerance error, +/-

15.00 psig or the transmitter reference accuracy, so+/- 18.03 psig will be the M&TE error (C1).

Trip Unit Uncertainties Using the vendor data from above:

Span

= 3000 psig RA2

= +/- 0.20% span

= +/- (0.002)*(3000 psig)

= +/- 6.00 psig L2

= - 0.00 psig M2

= + 0.00 psig M&TE:

Per Specification J301.2, "Technical Specification For Electronic Instruments (Fast Response Transmitters)," a Rosemount readout assembly (+/-0.01 mA) is used to calibrate the Rosemount trip units.

(0.01 )(3000)/16 = +/- 1.88 psig Specification J301.2 specifies a setting tolerance of+/- 0.04 mA (0.04)(3000)/16 = +/- 7.50 psig The larger value,+/- 7.50 psig, will be the M&TE error (C2).

(Assumption 4, 13)

GNR0-2019/00028 Enclosure, Attachment 4 Page 6 of 10 Loop Uncertainties The random and bias components of:

Primary Element errors: PE= N/A (This loop does not employ a primary element separate from the transmitter. Therefore, no additional errors due to inaccuracies in the primary element are required for this calculation.)

Process Measurement Accuracy: PM= N/A (Assumption 11)

Insulation Resistance Bias: IR= N/A (Assumption 5) will be quantified, the loop error equation given, and the device and loop uncertainties combined to produce:

AL - SASS of all device random uncertainties except drift AL

= +/- SRSS(A1, A2)

= +/- SRSS(20.68, 6.00)

= +/- 21.54 psig LL - The sum of all negative bias uncertainties LL = - L1 - L2 = 0.0 psig ML - The sum of all positive bias uncertainties ML = + M1 + M2 = 0.0 psig CL - SASS of all M& TE inaccuracies used for calibration.

CL

= +/- SRSS(C1, C2)

= +/- SRSS(18.03, 7.50)

= +/- 19.53 psig DL - SRSS of all drifts DL

= +/- SRSS(D1, 02)

= +/- SRSS{9.22, 0.0)

= +/- 9.22 psig LU (Loop Uncertainty)

LU

= +/- SRSS(AL, CL, PM, PE, IR)

= +/- SRSS(AL, CL)

= +/- SRSS(21.54, 19.53)

= +/- 29.08 psig TLU (Total Loop Uncertainty)

TLU

=LU+ DL

= +/- (29.08 + 9.22) psig

= +/- 38.30 psig The Analytical Limit {AL) is 614.00 psig. The AL was determined in calculation WNA-CN-00532-GGF1, "Reactor Protection System (RPS) Transmitter Pressure Setpoint." The AL is the minimum pressure in the trip header that will maintain the valve open. The TS AV is calculated using the below equation.

AV

~AL+LU

~ 614.00 psig + 29.08 psig

GNR0-2019/00028 Enclosure, Attachment 4 Page 7 of 10

~ 643.08 psig

~ 644 psig NTSP

~ AL + TLU + margin for Licensee Event Report (LER) avoidance

~ 614 psig + 38.30 psig + 22.7 psig

~ 675 psig Note: the "margin for LER avoidance" is a value selected to ensure the final LER avoidance value is acceptable.

Tabulated Results The NTSP and AV provide adequate spurious trip and Licensee Event Report avoidance probability. Note that the NTSP is in TRM Table TR 3.3.1.1-1.

SUMMARY

OF RESULTS TOTAL LOOP UNCERTAINTY TLU

+/- 38.30 LOOP UNCERTAINTY LU

+/- 29.08 LOOP DRIFT ALLOWANCE DL)

SPECIFIED

~ 675.00 Allowable Value Anal tical Limit

• • Values specified in the TS or TRM

SUMMARY

OF CALIBRATION TOLERANCES As-Left Transmitter (AL T1)

+/- 7.50 psig

+/- 0.04 mA As-Left Trip Unit (AL T2)

+/- 6.00 psig

+/- 0.03 mA As-Found Transmitter (AFT1)

+/- 21.60 psig

+/- 0.11 mA As-Found Trip Unit (AFT2)

+/- 9.60 psig

+/-0.05 mA As-Left Loop Tolerance (AL TL)

+/- 9.60 psig

+/- 0.05 mA As-Found Loop Tolerance (AFT L)

+/- 23.63 psig

+/- 0.12 mA

GNR0-2019/00028 Enclosure, Attachment 4 Page 8 of 10 3.1.2 Calculation for Function 10, "Turbine Control Valve Fast Closure, Trip Oil Pressure - Low" Calculation JC-01 C71-N605-1, Revision 4, "Turbine Control Valve Fast Closure Scram Setpoint Validation," determines the AV and setpoints for the Turbine Control Valve Fast Closure Scram Function. The values generated by this calculation are in accordance with Standard GGNS-JS-

09.

The transmitter (1 C71-PT-N005A-D) vendor data is the same as specified in Section 3.1.1 above.

1. Assume all uncertainties given are to two standard deviations (2o) unless otherwise specified.

2. Since the Turbine Building environment is not addressed in GGNS-E100.0, "Environmental Parameters for GGNS," the environmental specifications listed in the original purchase specification will be assumed as the ambient environment for the transmitters.

3. No Temperature Drift effect (TD) is specified by the transmitter vendor. The vendor published Temperature Effect (TE) will be assumed to be applicable as Temperature Drift (TD) over the temperature range of 65°F to 90°F and over a calibration interval of 30 months (nominal 24 months with a 25% grace period). The transmitter Temperature Effect (TE) will be assumed to be applicable from 90°F (the maximum expected calibration temperature) to 150°F (the expected maximum abnormal temperature).

4. The accuracy of the Rosemount trip units (+/-0.20% span) is valid for six months. Therefore, drift is included for the first six months after calibration. The trip units are calibrated every 115 days (Assumption 13). Therefore, the drift is included in the Reference Accuracy (RA).

5. Insulation Resistance Effects (IR) are assumed to be negligible since the loop cabling is located in a mild environment (Turbine Building and Control Building).

6. The transmitter Temperature Effect (TE) will be assumed to be applicable from 90°F (the maximum expected calibration temperature) to 150°F (the expected maximum abnormal temperature).

7. Specification PPD B159C4487 specifies a minimum output voltage of 22 vdc for the 24 vdc power supplies. No maximum voltage is specified. A value of 28 vdc will be assumed as this is the value provided in Specification PPD 184C4571 for similar power supplies. This results in an assumed voltage variation of +4, -2 vdc. For conservatism, +/-4 vdc will be used in this calculation.

8. The radiation drift effect (RD) of the transmitters is assumed to be zero as they are calibrated every 30 months (Assumption 13) and are located in a "B" (mild) radiation zone under normal conditions. However, radiation effects (RE) will be applied for conservatism.

9. Per standard GGNS-JS-09, the M&TE error is normally assumed to be equal to the reference accuracy of the transmitter. Further elaboration and details related to M& TE error are consistent with those provided in Section 3.1.1 above.

GNR0-2019/00028 Enclosure, Attachment 4 Page 9 of 10

10. Static Pressure Effects are not applicable to gauge type transmitters.

11. Process Measurement Effects (PM) are assumed to be zero. Since the transmitters are calibrated during outage conditions, the calibration will occur at a lower ambient temperature than that which will exist during normal operation. Therefore, any variation in EHC fluid density in the reference leg due to ambient temperature changes would result in a bias in the conservative direction with respect to the trip.

12. Drift calculation JC-01111-09014, "Drift Calculation for Gulton/Statham Gage and Differential Pressure Transmitters," was previously used to establish a drift value based on long-term actual calibration results. Since these transmitters are a new installation, there are no long-term actual calibrations results to use. Thus, the drift values are as provided by the manufacturer and JC-01111-09014 is revised to remove the associated transmitters.

13. A transmitter calibration interval of 30 months will be assumed, which is a nominal 24-month period, plus a 25% grace period. A calibration interval of 115 days will be assumed for the trip units, which is a nominal 92-day period, plus a 25% grace period.

14. Since the Rosemount 510DU model is obsolete, they may be replaced with 710DU's in the future. The performance specifications for the 71 ODU are equal to or better than those of the 510DU.

Uncertainties The transmitter uncertainties, trip unit uncertainties, and loop uncertainties for calculation JC-01 C71-N605-1 are the same values as in calculation JC-01 C71-N606-1 (in Section 3.1.1 above).

The AL is 908.00 psig. The AL was determined in calculation WNA-CN-00532-GGF1, "Reactor Protection System (RPS) Transmitter Pressure Setpoint." The AL is the minimum pressure in the trip header that will maintain the valve open. The TS AV is calculated using the below equation.

AV NTSP

~AL+ LU

~ 908.00 psig + 29.08 psig

~ 937.08 psig

~ 938 psig

~ AL + TLU + margin for LER avoidance

~ 908 psig + 38.30 psig + 22.7 psig

~ 970.00 psig Note: the "margin for LER avoidance" is a value selected to ensure the final LER avoidance value is acceptable.

GNR0-2019/00028 Enclosure, Attachment 4 Page 10 of 10 Tabulated Results The NTSP and AV provide adequate spurious trip and Licensee Event Report avoidance probability. Note that the NTSP is in TRM Table TR 3.3.1.1-1.

SUMMARY

OF RESULTS TOTAL LOOP UNCERTAINTY TLU

+/- 38.30 LOOP UNCERTAINTY LU

+/- 29.08 LOOP DRIFT ALLOWANCE DL M&TE CL

+/- 19.53 si SPECIFIED CALCULATED Allowable Value Anal tical Limit

• • Values specified in the TS or TRM

SUMMARY

OF CALIBRATION TOLERANCES As-Left Transmitter (AL T1)

+/- 7.50 psig

+/- 0.04 mA As-Left Trip Unit (AL T2)

+/- 6.00 psig

+/- 0.03 mA As-Found Transmitter (AFT1)

+/- 21.60 psig

+/- 0.11 mA As-Found Trip Unit (AFT2)

+/- 9.60 psig

+/- 0.05 mA As-Left Loop Tolerance (ALTL)

+/- 9.60 psig

+/- 0.05 mA As-Found Loop Tolerance (AFTL)

+/- 23.63 psig

+/- 0.12 mA