ML072700886

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Supplement 2 to Amendment Request Changes to the Condensate Storage Tank Level-Low Setpoints
ML072700886
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 09/21/2007
From: Brian W R
Entergy Corp, Entergy Operations
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
GNRO-2007/00068
Download: ML072700886 (174)
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Text

{{#Wiki_filter:En h9W Entergy P.O. Box 756 Port Gibson, MS 39150 Tel 601 437 6409 William R. Brian Vice President -Operations Grand Gulf Nuclear Station GNRO-2007/00068 September 21, 2007 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555

Subject:

Supplement 2 to Amendment Request Changes to the Condensate Storage Tank Level-Low Setpoints Grand Gulf Nuclear Station, Unit 1 (GGNS)Docket No. 50-416 License No. NPF-29 1. Letter GNRO-2007/00016 from W. R. Brian, Entergy Operations, Inc., to Document Control Desk, USNRC, "License Amendment Request Condensate Storage Tank Level-Low Setpoint Change," dated March 1, 2007 (TAC # MD 4675)

References:

2. Letter GNRO-2007/00061 from W. R. Brian, Entergy Operations, Inc., to Document Control Desk, USNRC, "Supplement to Amendment Request Changes to the Condensate Storage Tank Level-Low Setpoints," dated September 5, 2007

Dear Sir or Madam:

By the Reference 1 letter above, Entergy Operations, Inc. (Entergy) proposed a change to the Grand Gulf Nuclear Station, Unit I (GGNS) Technical Specifications (TS) to incorporate the corrected allowable values in TS Tables 3.3.5.1-1 and 3.3.5.2-1. The letter in Reference 2 above documented responses to six questions resulting from calls held with the NRC staff to discuss the technical basis for the proposed TS change.The NRC Staff has further requested copies of the surveillance procedures referenced in the supplemental letter. Copies of the requested procedures are attached.There are no technical changes proposed. The original no significant hazards consideration included in Reference 1 above is not affected by any information contained in this supplemental letter. There are no new commitments contained in this letter.If you have any questions or require additional information, please contact Matt Crawford at 601-437-2334. 740ýG070068 GNRO-2007/00068 Page 2 I declare under penalty of perjury that the foregoing is true and correct. Executed on September 21, 2007.Sincerely, WRB/MLC/amm Attachments'

1. GGNS Procedure 06-IC-1 E22-Q-0002
2. GGNS Procedure 06-IC-1 E22-R-0002
3. GGNS Procedure 06-IC-1 E51-Q-0002
4. GGNS Procedure 06-IC-1 E51-R-0002
5. GGNS Procedure 01-S-06-12 cc: Mr. Elmo E. Collins Regional Administrator, Region IV U. S. Nuclear Regulatory Commission 61 1 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-4005 U.S. Nuclear Regulatory Commission ATTN: Mr. Bhalchandra Vaidya, NRR/DORL (w/2)ATTN: ADDRESSEE ONLY ATTN: U.S. Postal Delivery Address Only Mail Stop OWFN/O-8G14 Washington, D.C. 20555-0001 Mr. Brian W. Amy, MD, MHA, MPH Mississippi Department of Health P. 0. Box 1700 Jackson, MS 39215-1700 NRC Senior Resident Inspector Grand Gulf Nuclear Station Port Gibson, MS 39150 G070068 GNRO-2007/00068 bcc: OUTLOOK MAIL: OTHER: DISTRIBUTION IS ALL ELECTRONIC Barfield A. D. .(GG-ENC-)Bottemiller C. A. (GG-NSAPL)

Bregar C. A. (ANO-NSA)Brian W. R. (GG-VP)Burford F. G. (ECH-NSL)Caery J. (GG-TRNG)Cook K. S. (W3-NSA)GGN CENTRAL FILE q1/GGN PLANT LICENSING James D. E. (ANO-NSAPL) Krupa M. A. (GG-GMPO)Lorfing D. N. (RB-NSAPL) Marlow T. A. (ANO-NSA)McCann J. F. (WP-NS&L)Murillo R. J. (W3-NSAPL) Roberts J. C. (RB-NSA)File (LRSDOCS Directory -GNRI or GNRO)G070068 NRC SUBMITTAL REVIEW Response Due: I NA Letter # I GNRO-2007/0068 Subjec t: Supplement 2 to Amendment Request -Changes to the Condensate Storage Tank Level-Low Setpoints I Date Issued for Review: 9/21/07 Correspondence Preparer / phone #: I Matt Crawford / 601-437-2334 SECTION I LETTER CONCURRENCE and AGREEMENT TO PERFORM ACTIONS (see Section 111)POSITION/NAME ACTION SIGNATURE (concurrence, certification, etc.) (sign, interoffice memo, e-mail, or telecom)Manager, Plant Licensing Concurrence S ~COMMENTS SECTION II CORRESPONDENCE SCREENING Does this letter contain commitments? If "yes," identify the commitments with due dates Yes [i in the submittal and in Section III. No [Does this letter contain any information or analyses of new safety issues performed at NRC Yes El request or to satisfy a regulatory requirement? If "yes," reflect requirement to update the No Z UFSAR in Section III.Does this letter request NRC approval of a change that may/will require UFSAR, TS Bases, Yes El or other Licensing documents to be updated if approved? If "yes," reflect requirement to No z update the applicable Licensing document in Section II1.Does this letter require procedure changes, if approved? If "yes," indicate in Section III an Yes EL action to determine affected procedures. (The Correspondence Preparer may indicate No z the specific procedures requiring revision, if known.)Does this letter contain information certified accurate? If "yes," identify the information Yes LI and document certification in an attachment. (Attachment 9.6 may be used.) No I]SECTION III ACTION ITEMS Required Actions Due Date RESPONSIBLE NOTE: Actions needed upon approval should be captured in the DEPARTMENT appropriate action tracking system.None G070068 SECTION IV FINAL DOCUMENT SIGNOFF FOR SUBMITTAL Correspondence Preparer Maft Crawford Final Submittal Review N/A (optional) Responsible DepL Head G070068 Attachment I To GNRO-2007100068 GGNS Procedure 06-IC-1E22-Q-0002 G070068 PLANT OPERATIONS MANUAL Volume 06 Section 04 06-IC-1E22-Q-0002 Revision: 101 Date: 11/18/05 SURVEILLANCE PROCEDURE CONDENSATE STORAGE TANK LOW LEVEL FUNCTIONAL TEST SAFETY RELATED Prepared: Reviewed: Approved: I&C Superin en ent List of Effective Pages: Pages 1-2 Attachments I, II List of TCNs Incorporated: Revision TCN 20 None 100 None 101 None J:\ADMSRVS\TECHPUB\REVISION\I\IE22Q02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Title: Condensate Storage Tank No.: Revision: 101 Page: i Low Level Functional Test 06-IC-1E22-Q-0002 I0CFR50.59 Review Required? (v") Yes If Yes, transmit 50.59 Review Form along with procedure to Document Control as a separate record.No Not required per LI-101 Cross-Discipline review required? (0) Yes (Note affected Departments Below)Preparer Initials >>>Department Cross-Discipline Reviews Needed Signoff Engineering (sipmed, electronic, telcon)Engineering Does this directive contain Tech Spec Triggers? C ) YES (1) NO RZQUIRZN3NTS CROSS-REINRENCZ LIST Requirement Implemented by Directive Directive Paragraph Number Name Paragraph Number That Implements Requirement Function 3.3.5.1-1.3.d

  • Tech Spec SR 3.3.5.1.2
  • Tech Spec SR 3.3.5.1.3
  • TRM SR 6.8.2.1 2.9, 5.13.24 TAM 3.3.5.1-1.3.d
    • Covered by directive as a whole or by various paragraphs of the directive.

NOTE The Equipment Database (EDB) Request statement is applicable only to Volume 06 and 0 7 maintenance directives. EDB Change Request generated and the backup documentation available for setpoint and/or calibration data only 0 Yes M N/A EDBCR #Current Revision Statement Revision 101 incorporates:

  • ER-GG-1999-0217-000 which changes transmitters and ranges of CST level instrumentation.
  • Section Revision Request # 589, which clarifies nomenclature of hand switch.* Procedure changed to Read/Write format and required numerous changes therefore no rev bars were used.J:\ADMSRVS\TECHPUB\REVISION\I\IE22Q02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Title: Condensate Storage Tank No.: Revision:

101 Page: 1 Low Level Functional Test 06-IC-IE22-Q-0002

1.0 PURPOSE

1.1 To functionally test Condensate Storage Tank Low Level Loop to ensure operability. 1.2 A Channel Functional Test is required every 92 days in accordance with Section SR 3.3.5.1.2 Function 3.3.5.1-1.3.d of GGNS Technical Specifications. 1.3 A Trip Unit Calibration is required every 92 days in accordance with SR 3.3.5.1.3, Function 3.3.5.1-1.3.d of GGNS Technical Specifications. 1.4 This functional test is associated with IE22-LIS-N654C and N654G.1.5 Verifies that MOV thermal overloads are bypassed per TRM SR 6.8.2.1.1.6 Changes required for implementation of 1994 TSIP were incorporated in Revision 100. For historical reference this statement should not be deleted.2.0 PRECAUTIONS AND LIMITATIONS

2.1 Steps

marked with a pound sign (#) are initialed on Data Sheet I as each step is completed. If steps are repeated during this functional test, they shall be reinitialed on Data Sheet I. Place an N/A on Data Sheet I for optional steps not performed.

2.2 Steps

marked with a dollar sign ($) are required to be completed for Technical Specifications Acceptance Criteria.2.3 If "As Found" values are not in tolerance, if procedural steps cannot be completed as stated, or if any other problem develops during this test, notify your immediate supervisor. 2.4 If "As Found" values exceed Technical Specifications tolerance, notify Shift Supervisor. 2.5 When HPCS is required to be Operable this test shall be performed on only one channel at a time. When one channel is being tested, remaining channels must be in Normal (untripped) condition.

2.6 Valve

1E22-F015 (Pump Suction from Suppression Pool) will Open during performance of this test.2.7 Valve 1E22-F001 (Pump Suction from Condensate Storage Tank) will Close during performance of this test.2.8 Instrument channel under test shall not remain out of service for more than six hours without entering applicable Tech Spec Action Statement. When it becomes apparent this time limit will be exceeded, immediately contact Shift Supervisor. This time limit is applicable only when instrument channel under test is required to be Operable.2.9 Placing MOV TEST switch to TEST, places overload protection in force for valves associated with Test switch. Overload protection may be left in force for up to eight hours, after which overloads must be bypassed by placing MOV Test switch to NORMAL or declaring valves Inoperable and entering applicable Tech Spec Action Statement. If it becomes apparent that MOV Test switch will be in TEST for longer than eight hours, immediately notify Shift Supervisor. J:\ADMSRVS\TECHPUB\REVISION\I\IE22Q02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Title: Condensate Storage Tank No.: Revision: 101 Page: 2 Low Level Functional Test 06-IC-1E22- -0002 2.10 Following alarms, trips and/or actions should occur from following Trip Units: INSTRUMENT NO. ANNUNCIATOR COMPUTER POINT IND LIGHT/ACTION 1E22-N654C "CST LVL LO" "CNDS STORAGE TRIP UNIT IN CAL/GR FAIL 1E22-N654G 1H13-P601-16A(C-4) TANK WTR LEVEL IH13-P601-16B (DS-5)"HPCS SYS OOSVC" LOW" E22L600 1E22-F001 will Close 1H13-P601-16A (H-5) I1E22-F015 will Open 3.0 REQUIRED MATERIALS AND TEST EQUIPMENT 3.1 Attachments I and II (as required by channel to be tested)3.2 Current Calibrator, Transmation 1040/1048 or equivalent (0-40 mAdc output)no M&TE requirements

3.3 Readout

Assembly, Rosemount 710DU or equivalent (accuracy better than+/- 0.040 mAdc at 0-20 mA)3.4 Card extender, (As Needed)4.0 PREREQUISITES AND PLANT CONDITIONS 4.1 This procedure may be performed in any Plant Mode except as modified by releasing organization.

  1. 4.2 HPCS is in Standby Readiness (E22-F001 Open, E22-FO15 Closed) in accordancE with SOI 04-1-01-E22-1.

5.0 INSTRUCTIONS

For 1E22-N654C perform instructions on Attachment I.For IE22-N654G perform instructions on Attachment II.

6.0 REFERENCES

6.1 Bechtel

Drawing No. E-1183-000, Rev 13 High Pressure Core Spray System 6.2 Rosemount Technical Manual 460000047 Rosemount 510DU Digital Trip Unit 6.3 07-S-53-181, Bench Calibration of Rosemount 510DU (710DU) Master and Slave Trip Units 6.4 UFSAR Chapter 16, Appendix 16B 6.5 ER-GG-1999-0217-000 6.6 SC-1E22-LT-N054,Rev.I e J:\ADM_SRVS\TECHPUB\REVISION\I\IE22Q02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE 06-IC-1E22-Q-0002 Revision: 101 Attachment I Page 1 of 7 Page RTYPE B6.61 XRef SURVEILLANCE PROCEDURE DATA PACKAGE COVER SHEET SAFETY RELATED Title: Condensate Storage Tank Low Level (HPCS) Functional Test Channel C Technical Specifications: SR 3.3.5.1.2 and SR 3.3.5.1.3; Function 3.3.5.1-1.3.d

1.0 IMPACT

STATEMENT 1.1 Performance of this procedure will result in swapping suction points of HPCS. Per LCO 3.3.5.1, Surveillance Requirement Note 2, when a channel is placed in an inoperable status solely for performance of required Surveillances, entry into the appropriate Condition may be delayed for up to 6 hours provided the associated function or the redundant function maintains ECCS initiation capability. Do not allow both HPCS Pump Suction valves (1E22-F001 and 1E22-F015) to be closed at the same time.1.2 One channel of condensate storage tank level instrumentation will be out of service during performance of this procedure. 1.3 The thermal overload protection 8 hour time limit LCO (6.8.2) is applicable (See Step 2.9).2.0 PROCEDURE 2.1 Plant Mode is (circle one): 1 2 3 4 5 2.2 Permission to begin test /Shift Supervisor/Date 2.3 Test Start Time: / /Performer's signature Date Time 3.0 TEST RESULTS 3.1 Test Completion: (Check one in each category.) Entire procedure completed [ ]Partial procedure completed As Found data Acceptable [ J Unacceptable As Left data Acceptable [ J Unacceptable [Tech Spec Acceptance Criteria Acceptable [ ] Unacceptable [All other steps/data Acceptable [ ] Unacceptable [3.2 TCNs in.effect during performance (list): 3.3 Comments: Rev Verified by: 3.4 Test performed by Date/Time 4.0 DEFICIENCIES CR Issued #LCO Entered # WR Issued #5.0 APPROVAL Tech Spec Operability Requirements Acceptable C ] Unacceptable Shift Supv/Manager Date Comments: CONCURRENCE I&C Superintendent Date J:\ADMSRVS\TECHPUB\REVISION\I\IE22Q02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Page RTYPE B6.61 XRef DATA SNEET I CONDENSATE STORAGE TANK LOW LEVEL (HPCS)FUNCTIONAL TEST CHANNEL C SAFETY RELATED STEP REQUIRED ACTION INITIALS 5.1 Obtain permission from Shift Supervisor to begin test.5.2 Shift Supervisor's signature is required on Cover Sheet.5.3 Verify prerequisite 4.2; HPCS is in Standby Readiness per SOI 04-1-01-E22-1 (with E22-FOO1 Open, E22-F015 Closed).5.4 Establish communications, if required, between Control Room and technician performing test.5.5 On Calibration Unit containing Master Trip Unit IE22-N654C on 1H13-P625, ensure TRANSIENT CURRENT switch knob and center knob of Calibration Select/Command switch are pulled out.5.6 Ensure Calibration Unit POWER switch and both center and outer Calibration Select/Command switches are in OFF position.5.7 Install Readout Assembly into Calibration Unit, and place Calibration Unit POWER switch to ON.5.8 Position center and outer knobs of Calibration Select/Command switch to position 3, selecting Master Trip Unit IE22-N654C.

5.9 Adjust

Stable Current to approximately 20.00 mA on Readout Unit.5.10 Complete Test Start Time on Data Package Cover Sheet.5.11 Push in center knob of Calibration Select/Command switch to activate Calibration Unit.$ 5.12 Ensure CAL LED on Calibration Unit comes On.5.13 Verify GROSS FAIL LED on Master Trip Unit comes On.N/A if selected trip unit is a Rosemount Model 710.5.14 Verify "HPCS SYS OOSVC" annunciator, 1H13-P601-16A (H-5), Alarms.$ 5.15 Verify TRIP UNIT IN CAL/GR FAIL status light, 1H13-P601-16B (DS-5), comes On.5.16 Request Operations to place, HPCS MOV TEST SWITCH, IE22-HS-M614 (1H13-P601-16B) in TEST to activate thermal overload protection devices for 1E22-FOOl and 1E22-F015. J:\ADMSRVS\TECHPUB\REVISION\I\IE22Q02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Page RTYPE B6.61 XRef DATA SHEET I CONDENSATE STORAGE TANK LOW LEVEL (EPCS)FUNCTIONAL TEST CHANNEL C SAFETY RELATED STEP- REQUIRED ACTION 5.17 Verify status light, HPCS MOV IN TEST STATUS 1H13-P601-16B (DS-3),comes On.5.18 Trip Unit Functional with Calibration (IE22-N654C on 1H13-P625) INITIALS 5.18.1 Adjust Stable Current to 20.01 mA) and record "As MASTER TRIP UNIT ANALOG DESIRED MIN 20.00 mA (allowable tolerance 19.99 mA to Found" 100% Master Trip Unit meter indication. METER 1E22-N654C AS FOUND MAX FINAL Ft. Ft. I Ft.5.18.2 40 39 NOP NOP -Not on Peg Adjust stable current to 12.00 mA (allowable tolerance 11.99 mA to 12.01 mA) and record "As Found" 50% Master Trip Unit meter indication. MASTER TRIP UNIT ANALOG METER 1E22-N654C DESIRED MIN AS FOUND MAX FINAL Ft. Ft. Ft. Ft. Ft.20 19 21 5.18.3 Notify Operations "CST LVL LO" 1H13-P601-16A (C-4)annunciator will alarm and that 1E22-F015 will Open and 1E22-F001 will Close.5.18.4 Decrease stable current until Master Trip Unit Trips (TRIP LED On).Record "As Found" trip value from upper display of Readout Assembly.LOW LEVEL TRIP CALIBRATION DATA 1E22-N654C DESIRED MIN AS FOUND MAX FINAL TECH SPEC mA mA mA mA mA VALUE mA 6.00 5.96 6.04 > 5.88 (72.9 "H 2 0) (70.5 "H 2 0) (75.3 "H 2 0) (2 4.7 Ft.)5.18.5 Verify:$ a. Annunciator, "CST LVL LO" on 1H13-P601-l6A (C-4), Alarmed.b. Valve 1E22-F015 Opens (Pump Suction from Suppression Pool)1H13-P601-16C.

c. Valve 1E22-F001 Closes (Pump Suction from Condensate Storage Tank) 1H13-P601-16C.

J:\ADM_SRVS\TECHPUB\REVISION\I\IE22Q02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Page RTYPE B6.61 XRef DATA SHEET I CONDENSATE STORAGE TANK LOW LEVEL (HPCS)FUNCTIONAL TEST CHANNEL C SAFETY RELATED STEP REQUIRED ACTION INITIALS 5.18.6 Decrease stable current to 4.00 mA (allowable tolerance 3.99 to 4.01) and record "As Found" 0% Master Trip Unit Meter Indication. MASTER TRIP UNIT ANALOG METER 1E22-N654C DESIRED MIN AS FOUND MAX FINAL Ft. Ft. Ft. Ft. Ft.0 NOP 1 NOP -Not on Peg 5.18.7 Press RESET pushbutton on.Readout Assembly.5.18.8 Increase stable current until Master Trip Unit Resets (TRIP LED Off), then record "As Found" reset value from upper display of Readout Assembly.LOW LEVEL TRIP CALIBRATION DATA (RESET) IE22-N654C DESIRED MIN AS FOUND MAX FINAL mA mA mA mA mA 6.08 6.04 6.12$ 5.18.9 Verify "CST LVL LO" annunciator, 1H13-P601-16A (C-4), Clears.5.18.10 Pull out center knob of Calibration Select/Command switch.5.18.11 Connect Current Calibrator (mA OUT, adjusted for 0 mA)positive lead (+) to J1 on Master Trip Unit and negative lead (-) to J2 on Calibration Unit.NOTE If On, reset GROSS FAIL LED. If LED does not go Off, adjust Current Calibrator until GROSS FAIL LED can be Reset.$ 5.18.12 Slowly increase milliamp output of Current Calibrator until GROSS FAIL LED on Master Trip Unit comes On.5.18.13 Reconnect Current Calibrator negative lead (-) to Jl on Master Trip Unit and positive lead (+) to J2 on Calibration Unit (mA OUT adjusted for 0 mA).J:\ADMSRVS\TECHPUB\REVISION\I\IE22Q02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Page RTYPE B6.61 XRef DATA SHEET I CONDENSATE STORAGE TANK LOW LEVEL (HPCS)FUNCTIONAL TEST CHANNEL C SAFETY RELATED STEP REQUIRED ACTION INITIALS$ 5.18.14 Reset GROSS FAIL LED on Master Trip Unit, and verify LED goes Off.$ 5.18.15 Slowly increase milliamp output of Current Calibrator until GROSS FAIL LED on Master Trip Unit comes On.5.18.16 Disconnect Current Calibrator. $ 5.18.17 Reset GROSS FAIL LED on Master Trip Unit. Verify LED goes Off.5.18.18 Push in center knob of Calibration Select/Command switch.5.18.19 If Trip Point adjustment is required, proceed to Step 5.18.19a.If not, record "Final" values and proceed to Step 5.18.20.a. Adjust Stable Current to desired value and adjust Trip Point pot as required.b. Recheck reset value. If reset requires no adjustment, proceed to Step 5.18.19e. If reset requires adjustment, proceed to Step 5.18.19c c. Install card extender between trip unit and card file if necessary.

d. Adjust Stable Current to Desired Reset values and adjust RESET DIFFERENTIAL pot on circuit board as required.e. Recheck trip and reset values. If both trip and reset require no further adjustment, record "Final" values and proceed to Step 5.18.20. If not, repeat Steps 5.18.19a through 5.18.19e until unit requires no further adjustment.

5.18.20 If Master Trip Unit meter adjustment is required, proceed to Step 5.18.20a. If not, record "Final" values and proceed to Step 5.18.21.a. If necessary, install card extender between Master Trip Unit and card file.b. Adjust meter ZERO at back of meter, then recheck 0, 50, and 100%indications. Repeat as required until unit is in tolerance.

c. Record "Final" indications.

5.18.21 If installed, remove card extender from Master Trip Unit and reinstall trip unit in card file. Otherwise, N/A.J:\ADMSRVS\TECHPUB\REVISION\I\IE22Q02 .DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Page RTYPE B6.61 XRef DATA SHUNT I CONDZNSATE STORAGE TANK LOW LEVEL (NPCS)FUNCTIONAL TEST CHANNEL C SAFETY RELATED STEP REQUIRED ACTION INITIALS 5.18.22 Adjust Stable Current to approximately 20.00 mA.5.18.23 Pull out center knob of Calibration Select/Command switch and ensure CAL LED is Off.5.18.24 Have Operations reposition Valves 1E22-F001 and 1E22-F015 to STANDBY READINESS positions and complete Valve Restoration. VALVE RESTORATION INITIALS VALVE TEST NORMAL FINAL PERFORMER VERIFIER 1E22-F001 CLOSED OPEN I1E22-F015 OPEN CLOSED 5.18.25 Request Operations to place, HPCS MOV TEST SWITCH, 1E22-HS-M614 in NORM to bypass thermal overload protection for 1E22-F001 and 1E22-F015. Complete Hardware Restoration. HARDWARE RESTORATION INITIALS DESCRIPTION TEST NORMAL FINAL PERFORMERI VERIFIER HPCS MOV TEST SWITCH IE22-HS-M614 TEST NORM$ 5.18.26 Verify status light, HPCS MOV IN TEST STATUS, IH13-P601-16B (DS-3), goes Off.$ 5.18.27 Press Master Trip Unit Gross Fail RESET pushbutton, and verify GROSS FAIL LED goes Off.5.18.28 Verify: a. The "HPCS SYS OSVC" annunciator, 1H13-P601-16A (H-5), Clears.$b. The TRIP UNIT IN CAL/GR FAIL status light, 1H13-P601-16B (DS-5),goes Off.J:\ADMSRVS\TECHPUB\REVISION\I\IE22Q02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Page RTYPE B6.61 XRef DATA SHEET I STORAGE TANK LOW LEVEL (HPCS)CONDENSATE FUNCTIONAL TEST CHANNEL C SAFETY RELATED REQUIRED ACTION Restoration. STEP 5.19 Complete Hardware HARDWARE RESTORATION INITIALS INITIALS DESCRIPTION TEST NORMAL FINAL PERFORMER VERIFIER Cal Select/Command switch center knob Pos 3 OFF Cal Select/Command switch outer knob Poo 3 OFF Cal Unit POWER switch ON OFF 5.20 Remove Digital Readout Assembly.5.21 Verify 1E22-N654C reflects current plant conditions. 5.22 Record test equipment used for this test on Data Sheet III.This step may be performed out of sequence if desired.TEST EQUIPMENT LOG TEST EQUIPMENT M&TE NO. CAL DUE DATE 5.23 Notify Shift Supervisor test is complete. Shift Supervisor's signature is required on Data Package Cover Sheet.J:\ADMSRVS\TECHPUB\REVISION\I\IE22Q02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Page RTYPE B6.61 XRef SURVEILLANCE PROCEDURE DATA PACKAGE COVER SHEET SAFETY RELATED Title: Condensate Storage Tank Low Level (HPCS) Functional Test Channel G Technical Specifications: SR 3.3.5.1.2 and SR 3.3.5.1.3; Function 3.3.5.1-1.3.d

1.0 IMPACT

STATEMENT 1.1 Performance of this procedure will result in swapping suction points of HPCS. Per LCO 3.3.5.1, Surveillance Requirement Note 2, when a channel is placed in an inoperable status solely for performance of required Surveillances, entry into the appropriate Condition may be delayed for up to 6 hours provided the associated function or the redundant function maintains ECCS initiation capability. Do not allow both HPCS Pump Suction valves (1E22-F001 and 1E22-F015) to be closed at the same time.1.2 One channel of condensate storage tank level instrumentation will be out of service during performance of this procedure. 1.3 The thermal overload protection 8 hour time limit LCO (6.8.2) is applicable (See Step 2.9).2.0 PROCEDURE 2.1 Plant Mode is (circle one): 1 2 3 4 5 2.2 Permission to begin test /Shift Supervisor/Date 2.3 Test Start Time: /Performer's signature Date Time 3.0 TEST RESULTS 3.1 Test Completion: (Check one in each category.) Entire procedure completed [ ] Partial procedure completed As Found data Acceptable [ ] Unacceptable As Left data Acceptable [ ] Unacceptable Tech Spec Acceptance Criteria Acceptable [ ] Unacceptable All other steps/data Acceptable [ ] Unacceptable [3.2 TCNs in effect during performance (list): 3.3 Comments: Rev Verified by: 3.4 Test performed by Date/Time 4.0 DEFICIENCIES CR Issued T_LCO Entered # WR Issued #5.0 APPROVAL Tech Spec Operability Requirements Acceptable [ I Unacceptable Shift Supv/Manager Date Comments: CONCURRENCE I&C Superintendent -Date J:\ADM_SRVS\TECHPUB\REVISION\I\IE22Q02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE 06-IC-1E22-Q-0002 Revision: 101 Attachment II Page 2 of 7$$Page RTYPE B6.61 XRef DATA SHUZT I CONDENSATE STORAGE TANK LOW LEVEL (HPCS)FUNCTIONAL TEST CHANNEL G SAFETY RELATED STEP REQUIRED ACTION INITIALS 5.1 Obtain permission from Shift Supervisor to begin test.5.2 Shift Supervisor's signature is required on Cover Sheet.5.3 Verify prerequisite 4.2; HPCS is in Standby Readiness per SOI 04-1-01-E22-1 (with E22-FOOl Open, E22-F015 Closed).5.4 Establish communications, if required, between Control Room and technician performing test.5.5 On Calibration Unit containing Master Trip Unit 1E22-N654G on 1H13-P625, ensure TRANSIENT CURRENT switch knob and center knob of Calibration Select/Command switch are pulled out.5.6 Ensure Calibration Unit POWER switch and both center and outer Calibration Select/Command switches are in OFF position.5.7 Install Readout Assembly into Calibration Unit, and place Calibration Unit POWER switch to ON.5.8 Position center and outer knobs of Calibration Select/Command switch to position 4, selecting Master Trip Unit 1E22-N654G.

5.9 Adjust

Stable Current to approximately 20.00 mA on Readout Unit.5.10 Complete Test Start Time on Data Package Cover Sheet.5.11 Push in center knob of Calibration Select/Command switch to activate Calibration Unit.5.12 Ensure CAL LED on Calibration Unit comes On.5.13 Verify GROSS FAIL LED on Master Trip Unit comes On.N/A if selected trip unit is a Rosemount Model 710.5.14 Verify "HPCS SYS OOSVC" annunciator, IH13-P601-16A (H-5), Alarms.5.15 Verify TRIP UNIT IN CAL/GR FAIL status light, IH13-P601-16B (DS-5), comes On.5.16 Request Operations to place, HPCS MOV TEST PWITCH, 1E22-HS-M614 (1H13-P601-16B) in TEST to activate thermal overload protection devices for IE22-FOOl and IE22-F015. J:\ADM_SRVS\TECHPUB\REVISION\I\IE22Q02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE 06-IC-1E22-Q-0002 Revision: 101 Attachment II Page 3 of 7 Page RTYPE B6.61 XRef DATA SHENT I CONDENSATZ STORAGE TANK LOW LEVEL (HPCS)FUNCTIONAL TEST CHANNEL G SAFETY RELATED STEP REQUIRED ACTION INI 5.17 Verify status light, HPCS MOV IN TEST STATUS 1H13-P601-16B (DS-3),comes On.5.18 Trip Unit Functional with Calibration (1E22-N654G on 1H13-P625) 5.18.1 Adjust Stable Current to 20.00 mA (allowable tolerance 19.99 mA to 20.01 mA) and record "As Found" 100% Master Trip Unit meter indication. MASTER TRIP UNIT ANALOG METER 1E22-N654G DESIRED MIN AS FOUND MAX FINAL Ft. Ft. Ft. Ft. Ft.40 39 NOP NOP -Not on Peg 5.18;2 Adjust stable current to 12.00 mA (allowable tolerance 11.99 mA to 12.01 mA) and record "As Found" 50% Master Trip Unit meter indication. MASTER TRIP UNIT ANALOG METER 1E22-N654G DESIRED MIN AS FOUND MAX FINAL Ft. Ft. Ft. Ft. Ft.20 19 21 5.18.3 Notify Operations "CST LVL LO" 1H13-P601-16A (C-4)annunciator will alarm and that 1E22-F015 will Open and 1E22-F001 will Close.5.18.4 Decrease stable current until Master Trip Unit Trips (TRIP LED On).Record "As Found" trip value from upper display of Readout Assembly.TIALS%.U (73.0 "H 2 0)5.18.5 Verify:$ a. Annunciator, "CST LVL LO" on 1H13-P601-16A (C-4), Alarmed.b. Valve 1E22-F015 Opens (Pump Suction from Suppression Pool)IH13-P601-16C.

c. Valve 1E22-F001 Closes (Pump Suction from Condensate Storage Tank) 1H13-P601-16C.

J:\ADM_SRVS\TECHPUB\REVISION\I\IE22Q02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Page RTYPE B6.61 XRef DATA SHEET I CONDENSATE STORAGE TANK LOW LEVEL (HPCS)FUNCTIONAL TEST CHANNEL G SAFETY RELATED STEP REQUIRED ACTION INITIALS 5.18.6 Decrease stable current to 4.00 mA (allowable tolerance 3.99 to 4.01) and record "As Found" 0% Master Trip Unit Meter Indication. MASTER TRIP UNIT ANALOG METER 1E22-N654G DESIRED MIN AS FOUND MAX FINAL Ft. Ft. Ft. Ft. Ft.0 NOP 1 NOP -Not on Peg 5.18.7 Press RESET pushbutton on Readout Assembly.5.18.8 Increase stable current until Master Trip Unit Resets (TRIP LED Off), then record "As Found" reset value from upper display of Readout Assembly.LOW LEVEL TRIP CALIBRATION DATA (RESET) IE22-N654G DESIRED MIN AS FOUND MAX FINAL mA mA mA-- mA MA 6.08 6.04 6.12$ 5.18.9 Verify "CST LVL LO" annunciator, 1H13-P601-16A (C-4), Clears.5.18.10 Pull out center knob of Calibration Select/Command switch.5.18.11 Connect Current Calibrator (mA OUT, adjusted for 0 mA)positive lead (+) to J1 on Master Trip Unit and negative lead (-) to J2 on Calibration Unit.NOTE If On, reset GROSS FAIL LED. If LED does not go Off, adjust Current Calibrator until GROSS FAIL LED can be Reset.$ 5.18.12 Slowly increase milliamp output of Current Calibrator until GROSS FAIL LED on Master Trip Unit comes On.5.18.13 Reconnect Current Calibrator negative lead (-) to J1 on Master Trip Unit and positive lead (+) to J2 on Calibration Unit (mA OUT adjusted for 0 mA).J:\ADMSRVS\TECHPUB\REVISION\I\IE22Q02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE 06-IC-IE22-Q-0002 Revision: 101 Attachment II Page 5 of 7 Page RTYPE B6.61 XRef$$$DATA SHEET I CONDENSATE STORAGE TANK LOW LEVEL (HPCS)FUNCTIONAL TEST CHANNEL G SAFETY RELATED STEP REQUIRED ACTION IN 5.18.14 Reset GROSS FAIL LED on Master Trip Unit, and verify LED goes Off.5.18.15 Slowly increase milliamp output of Current Calibrator until GROSS FAIL LED on Master Trip Unit comes On.5.18.16 Disconnect Current Calibrator. 5.18.17 Reset GROSS FAIL LED on Master Trip Unit. Verify LED goes Off.5.18.18 Push in center knob of Calibration Select/Command switch.5.18.19 If Trip Point adjustment is required, proceed to Step 5.18.19a.If not, record "Final" values and proceed to Step 5.18.20.a. Adjust Stable Current to desired value and adjust Trip Point pot as required.b. Recheck reset value. If reset requires no adjustment, proceed to Step 5.18.19e. If reset requires adjustment, proceed to Step 5.18.19c c. Install card extender between trip unit and card file if necessary.

d. Adjust Stable Current to Desired Reset values and adjust RESET DIFFERENTIAL pot on circuit board as required.e. Recheck trip and reset values. If both trip and reset require no further adjustment, record "Final" values and proceed to Step 5.18.20. If not, repeat Steps 5.18.19a through 5.18.19e until unit requires no further adjustment.

5.18.20 If Master Trip Unit meter adjustment is required, proceed to Step 5.18.20a. If not, record "Final" values and proceed to Step 5.18.21.a. If necessary, install card extender between Master Trip Unit and card file.b. Adjust meter ZERO at back of meter, then recheck 0, 50, and 100%indications. Repeat as required until unit is in tolerance.

c. Record "Final" indications.

5.18.21 If installed, remove card extender from Master Trip Unit and reinstall trip unit in card file. Otherwise, N/A.ITIALS J:\ADMSRVS\TECHPUB\REVISION\I\IE22Q02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Page RTYPE B6.61 XRef DATA SHUNT I CONDENSATE STORAGE TANK LOW LEVEL (HPCS)FUNCTIONAL TEST CHANNEL G SAFETY RELATED STEP REQUIRED ACTION 5.18.22 Adjust Stable Current to approximately 20.00 mA.5.18.23 Pull out center knob of Calibration Select/Command switch and ensure CAL LED is Off.5.18.24 Have Operations reposition Valves 1E22-F001 and 1E22-F015 to STANDBY READINESS positions and complete Valve Restoration. VALVE RESTORATION INITIALS VALVE TEST NORMAL FINAL PERFORMER VERIFIER IE22-FOOI CLOSED OPEN 1E22-FO1S OPEN CLOSED 5.18.25 Request Operations to place, HPCS MOV TEST SWITCH, 1E22-HS-M614 in NORM to bypass thermal overload protection for 1E22-F001 and 1E22-F015. Complete Hardware Restoration. HARDWARE RESTORATION INITIALS DESCRIPTION TEST NORMAL FINAL PERFORMER VERIFIER HPCS MOV TEST SWITCH IE22-HS-M614 TEST NORM INITIALS$ 5.18.26$ 5.18.27 5.18.28$Verify status light, HPCS MOV IN TEST STATUS, 1H13-P601-16B (DS-3), goes Off.Press Master Trip Unit Gross Fail RESET pushbutton, and verify GROSS FAIL LED goes Off.Verify: a. The "HPCS SYS OSVC" annunciator, 1H13-P601-16A (H-5), Clears.b. The TRIP UNIT IN CAL/GR FAIL status light, IH13-P601-16B (DS-5),goes Off.J:\ADM_SRVS\TECHPUB\REVISION\I\IE22Q02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Page RTYPE B6.61 XRef DATA SHEET I CONDENSATE STORAGE TANK LOW LEVEL (EPCS)FUNCTIONAL TEST CHANNEL G SAFETY RELATED STEP REQUIRED ACTION 5.19 Complete Hardware Restoration. HARDWARE RESTORATION INITIALS INITIALS DESCRIPTION TEST NORMAL FINAL PERFORMER VERIFIER Cal Select/Command switch center knob Pos 3 OFF Cal Select/Command switch outer knob Pos 3 OFF Cal Unit POWER switch ON OFF 5.20 Remove Digital Readout Assembly.5.21 Verify 1E22-N654G reflects current plant conditions. 5.22 Record test equipment used for this test on Data Sheet III.This step may be performed out of sequence if desired.TEST EQUIPMENT LOG TEST EQUIPMENT M&TE NO. CAL DUE DATE 5.23 Notify Shift Supervisor test is complete. Shift Supervisor's signature is required on Data Package Cover Sheet.J:\ADM_SRVS\TECH_PUB\REVISION\I\IE22Q02.DOC Attachment 2 To GNRO-2007100068 GGNS Procedure 06-IC-IE22-R-0002 G070068 PLANT OPERATIONS MANUAL Volume 06 06-IC-1I22-R-0002 Section 04 Revision: 104 Date: 11/18/05 SURVEILLANCE PROCEDURE CONDENSATE STORAGE TANK LOW LZVEL CALIBRATION SAFETY RELATED Prepared: Reviewed: Technica1 Approved: I&C Superintendent List of Effective Pages: Pages 1-3 Attachments I, II List of TCNs Incorporated: Revision TCN 0 None 1 1 2 2,3 3 None 20 None 21 None 22 4 23 None 100 None 101 5 102 None 103 None 104 None J:\Adm_srvs\TECHPUB\REVISION\I\IE22R02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Title: Condensate Storage Tank No.: Revision: 104 Page: i Low Level Calibration 06-IC-1E22-R-0002 l0CFR50.59 Review Required? (V) Yes If Yes, transmit 50.59 Review Form along with procedure to Document Control as a separate Irecord.No Not required per LI-101 Cross-Discipline review required? (4) Yes (Note affected Departments Below)( No Preparer Initialsa>> Department Cross-Discipline Reviews Needed Sigff Engineering t(siged, electronic. telcon)Does this directive contain Tech Spec Triggers? ( ) YES (V) NO REQUIRRMONTS CROSS-RBFERZNC3 LIST Recruirement Implemented by Directive Directive Paragraph Number-Name Paragraph Number That Implements Requirement Function 3.3.5.1-1.3.d _Tech Spec SR 3.3.5.1.5

  • Tech Spec SR 3.3.5.1.6 Tech Spec 3.5.1.5 5.13.3, 5.13.4c & d TRM _SR 6.8.2.1 2.8. 5.19.9.c TRM 3.3.5.1-1.3.d

_* Covered by directive as a whole or by various paragraphs of directive. NOTE The Equipment Database (EDB) Request statement is applicable only to Volume 06 and 07 maintenance directives. EDB Change Request generated and the backup documentation available for setpoint and/or calibration data only 0J Yes 0. N/A EDBCR #Current Revision Statement Revision 104 incorporates: " ER-GG-1999-0217-000 which changes transmitters and ranges of CST level instrumentation.

  • Section Revision Request # 989, which allows use of test adapter for transmitter calibration." Procedure required numerous changes therefore no rev bars were used.J:\Admsrvs\TECHPUB\REVISION\I\IE22R02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Title: Condensate Storage Tank No.: Revision:

104 Page: 1 Low Level Calibration 06-IC-1I22-R-0002

1.0 PURPOSE

1.1 To calibrate Condensate Storage Tank Low Level Logic System Channels (HPCS)to ensure operability. This CHANNEL CALIBRATION is required every 18 months in accordance with SR 3.3.5.1.5, Function 3.3.5.1-1.3.d of GGNS Technical Specifications. 1.2 To verify HPCS suction path is automatically transferred from CST to suppression pool on CST low level. This test is required every 18 months in accordance with SR 3.5.1.5 (for 1E22-F015 and 1E22-F001) of GGNS Technical Specifications. 1.3 To provide testing at least once per 18 months which satisfies requirement for LOGIC SYSTEM FUNCTIONAL TEST of ECCS Actuation Instrumentation per SR 3.3.5.1.6, Function 3.3.5.1-1.3.d of GGNS Technical Specifications. 1.4 This procedure is associated with instruments 1E22-LT-N054C/G and 1E22-LIS-N654C/G.1.5 Changes required for implementation of 1994 TSIP were incorporated in Revision 100. For historical reference this statement should not be deleted.2.0 PRECAUTIONS AND LIMITATIONS 2.1 If steps are repeated during this calibration, they shall be reinitialed on Data Sheet I. Place an N/A in Data Sheet I for optional steps not performed.

2.2 Steps

marked with dollar sign ($) are required to be completed for Technical Specifications Acceptance Criteria.2.3 If "As Found" values are not in tolerance, if procedural steps cannot be completed as stated, or if any other problem develops during this test, notify your immediate supervisor. 2.4 If "As Found" values exceed Technical Specifications tolerance, notify Shift Supervisor. 2.5 Any water drained from transmitter, test assembly, and/or associated tubing may be contaminated. Exercise caution and radiological safety precautions. 2.6 Pump suction flow path valve transfer will occur during performance of this procedure.

2.6.1 Valve

1E22-F015 (Pump Suction from Suppression Pool) will open on low level in Condensate Storage tank.2.6.2 Valve 1E22-F001 (Pump Suction from Condensate Storage Tank) will close on low level in Condensate Storage tank.2.7 Instrument channel under test shall not remain out of service for more than six hours without entering applicable Tech Spec Action Statement. When it becomes apparent this time limit will be exceeded, immediately contact Shift Supervisor. This time limit is applicable only when instrument channel under test is required to be Operable.2.8 Placing an MOV TEST switch to TEST, places overload protection in force for valves associated with Test switch. Overload protection may be left in force for up to eight hours, after which overloads must be bypassed by placing MOV TEST switch to NORMAL or declaring valves Inoperable.(Reference LCO 6.8.2, SR 6.8.2.1).J:\Adm_srvs\TECHPUB\REVISION\I\IE22R02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE STitle : Condensate Storage Tank Revision: 104 Page: 2 Low Level Calibration 06-IC-IE22-R-0002

2.9 Following

alarms, trips, and/or actions should occur from following Trip Units: TRIP UNIT ANNUNCIATOR COMPUTER POINT ACTION/IND LIGHT 1E22-N654C "CST LVL LO" E22L600 "CNDS 1E22-F015 Opens.Low Level 1H13-P601-16A (C-4) STORAGE TANK IE22-FOOl Closes WTR LEVEL LOW" IE22-N654G "HPCS SYS OOSVC" Low Level 1H13-P601-16A(H-5)"HPCS SUPP POOL SUCT VLV F015 MAN OVERRD" 1H13-P601-16A(E-5)

3.0 REQUIRED

MATERIALS AND TEST EQUIPMENT 3.1 Attachments I and II (as required by channel to be tested)3.2 DVM, Fluke 45 or equivalent (accuracy better than: +/- 0.040 mAdc at 0-20 mA; +/- 0.193 Vdc at 0-10 Vdc)3.3 Current Calibrator, Transmation 1040/1048 or equivalent (0-40 mAdc output)no M&TE requirements

3.4 Readout

Assembly, Rosemount 710DU or equivalent (accuracy better than+/- 0.040 mAdc at 0-20 mA)3.5 Pressure gauge, Heise (0-491" H.O) or equivalent (accuracy better than+/- 1.194" H.O)3.6 Pressure Source (Air)3.7 Card extender (510DU Type) (As Needed)3.8 Test fitting for vent port of Rosemount transmitter.(As Needed)3.9 Torque Wrench, capable of 90"lbs. or equivalent.

4.0 PREREQUISITES

AND PLANT CONDITIONS 4.1 This procedure may be performed in any Plant Mode except as modified by releasing organization. 4.2 HPCS is in Standby per SOI 04-1-01-E22-1 (with IE22-F015 Closed and IE22-F001 Open).5.0 INSTRUCTIONS For 1E22-N654C and IE22-N054C perform instructions on Attachment I.For 1E22-N654G and 1E22-N054G perform instructions on Attachment II.J:\Admsrvs\TECHPUB\REVISION\I\IE22R02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Title: Condensate Storage Tank No.: TRevision: 104 Page: 3 1 Low Level Calibration 06-IC-IE22-R-0002

6.0 REFERENCES

6.1 Bechtel

Drawing No. E-1183, HPCS Schematic Diagram M-1086, HPCS P&ID Diagram 6.2 Vendor Manual 460000047 Trip/Calibration System Model 510DU 6.3 Vendor Manual 460001972, Model 1153 Series B & D Alphaline Pressure Instruments (Rosemount 1153 Transmitter) 6.4 07-S-53-181, Bench Calibration of the Rosemount 510DU (710DU) Master and Slave Trip Units 6.5 UFSAR Chapter 16, Appendix 16B 6.6 CR-GGN-2001-1367 and SC-IE22-LT-N054,Rev.0 6.7 ER-GG-1999-0217-000 6.8 SC-1E22-LT-N054,Rev.I J:\Admsrvs\TECHPUB\REVISION\I\IE22R02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Page RTYPE B6.61 XRef SURVEILLANCE PROCEDURE DATA PACKAGE COVER SHEET SAFETY RBLATED Title: Condensate Storage Tank Low Level Calibration Channel C Technical Specifications: SR 3.3.5.1.5 and SR 3.3.5.1.6, Function 3.3.5.1-1.3.d SR 3.5.1.5 1.0 IMPACT STATEMENT 1.1 Performance of this procedure will result in swapping suction points of HPCS. Do not allow both HPCS Pump Suction valves (1E22-F001 and 1E22- F015)to be Closed at the same time.1.2 In Plant Mode 1, 2 or 3, when a channel is placed in an inoperable status solely for performance of required Surveillances, entry into appropriate Condition may be delayed for up to 6 hours provided associated function or redundant function maintains ECCS initiation capability. 1.3 In Plant Modes 4 or 5 when associated subsystems are required to be OPERABLE, entry into Conditions and Required Actions associated with LCO 3.3.5.1 may be delayed for up to 6 hours per Surveillance Note 2, provided associated or redundant Functions maintain ECCS initiation capability. When one of required ECCS Subsystems is MANUALLY re-aligned, above Surveillance Note 2 does not provide allowances for removing from service instrumentation associated with required automatic ECCS subsystem.

1.4 Thermal

overload protection 8 hour time limit LCO 6.8.2 is applicable.

2.0 PROCEDURE

2.1 Plant Mode is (Circle one): 1 2 3 4 5 2.2 Permission to begin test and perform system modifications. Shift Supervisor Date 2.3 Test Start Time: ___Performer's Signature Date Time 3.0 TEST RESULTS 3.1 Test Completion: (Check one in each category.) Entire procedure completed [ I Partial procedure completed I I As Found data Acceptable [ ] Unacceptable [ ]As Left data Acceptable [ J Unacceptable [Tech Spec Acceptance Criteria Acceptable [ 3 Unacceptable E All other steps/data Acceptable [ I Unacceptable C 3.2 TCNs in effect during performance (list): 3.3 Comments: Rev.verified by: 3.4 Test performed by Date/Time J:\Adm_srvs\TECHPUB\REVISION\I\IE22R02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Page RTYPE B6.61 XRef SURVEILLANCE PROCEDURE DATA PACKAGE COVER SHIRT (Continued) SAPETY RELATED 4.0 DEFICIENCIES CR Issued #LCO Entered #WR Issued #5.0 APPROVAL Tech Spec Operability Requirements Acceptable [ ] Unac4 Shift Supv/Manger _Comments: CONCURRENCE I&C Superintendent ..eptable:)ate Date _______ _Date J:\Adm_srvs\TECHPUB\REVISION\I\IE22R02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Page*RTYPE B6.61 XRef DATA SHENT I CONDENSATE STORAGE TANK LOW LEVEL CALIBRATION CHANNEL C SAFETY RBLATZD STEP REQUIRED ACTION INITIALS 5.1 Obtain permission from Shift Supervisor to begin test. Shift Supervisor's signature is required on Cover Sheet.5.2 Perform following:

5.2.1 Verify

prerequisite 4.2; HPCS is in Standby per SOI 04-1-01-E22-1 (with 1E22-F015 Closed and 1E22-F001 Open).5.2.2 Establish communications, if required, between Control Room and technician performing test.5.3 On Calibration Unit containing Master Trip Unit 1E22-N654C on IH13-P625, ensure TRANSIENT CURRENT switch knob and center knob of Calibration Select/Command switch are pulled out.5.4 Ensure Calibration Unit POWER switch and center and outer Calibration Select/Command switches are in OFF position.5.5 Install Readout Assembly into Calibration Unit. Place Calibration Unit POWER switch to ON.5.6 Position center knob of Calibration Select/Command switch to position 3, selecting Master Trip Unit lE22-N654C.

5.7 Position

outer knob of Calibration Select/Command switch to position 3, selecting Master Trip Unit 1E22-N654C.

5.8 Adjust

STABLE CURRENT knob to approximately 20 mA as observed on lower display of Readout Assembly.5.9 Perform following:

5.9.1 Complete

Test Start Time on Data Package Cover Sheet.5.9.2 Push in center knob of Calibration Select/Command switch to activate Calibration Unit.5.10 Perform following: 5.10.1 Ensure CAL LED on Calibration Unit comes On.$ 5.10.2 Verify GROSS FAIL LED on Master Trip Unit comes On.J:\Adm_srvs\TECHPUB\REVISION\I\IE22R02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Page RTYPE B6.61 XRef ,DATA SHUNT I (Continued) CONDENSATE STORAGE TANK LOW LEVEL CALIBRATION CHANNEL C SAPETY RELATED STEP REQUIRED ACTION INITIALS 5.11 Verify: 5.11.1 Annunciator, "HPCS SYS OOSVC", on 1H13-P601-16A (H-5), Alarms.5.11.2 Computer point E22L607 displays OUT SVCE.$ 5.11.3 Status light TRIP UNIT IN CAL/GR FAIL on 1H13-P601-16B (DS-5)comes On.5.12 Perform following: 5.12.1 Have Operations place HPCS MOV TEST handswitch (1E22-HS-M614) in TEST position.$ 5.12.2 Verify status light HPCS MOV IN TEST STATUS DS3, on IH13-P601-16B is On.5.13 Master Trip Unit Trip Calibration (1E22-N654C on IH13-P625) 5.13.1 Adjust stable current to 20.00 mA (allowable tolerance 19.99 to 20.01).5.13.2 Record "As Found" 100% Master Trip Unit Meter Indication. 5.13.3 MASTER TRIP UNIT ANALOG METER IE22-N654C DESIRED MIN AS FOUND MAX FINAL Ft. Ft. Ft, Ft. Ft.40 39 NOP NOP -Not on Peg Adjust stable current to 12.00 mA (allowable tolerance 11.99 to 12.01) and record "As Found" 50% Master Trip Unit Meter Indication. MASTER TRIP UNIT ANALOG METER 1E22-N654C DES IRED MIN AS FOUND MAX FINAL Ft.I Ft. Ft. Ft. Ft.20 19 21 J:\Admsrvs\TECHPUB\REVISION\I\IE22R02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Page RTYPE B6.61 XRef DATA SHUNT I (Continued) CONDENSATE STORAGE TANK LOW LEVEL CALIBRATION CHANNEL C SAFETY RELATED STEP REQUIRED ACTION INITIALS 5.13.4 Decrease stable current until Master Trip Unit Trips (TRIP LED On).Record "As Found" trip value from upper display of Readout Assembly.LOW LEVEL TRIP CALIBRATION DATA (TRIP) 1E22-N654C DESIRED MIN AS FOUND MAX FINAL mA mA mA mA mA 6.00 5.96 6.04 (72.9" H 2 01 (70.5" H 2 0 (21 75.3" H0)(2): Transfer value to corresponding location in Step 5.21.5.13.5 Verify:$ a. Annunciator, "CST LVL LO" on 1H13-P601-16A (C-4), Alarmed.b. Computer point E22L600 displays LOW.$ c. Valve 1E22-F015 Opened.NOTE Valve F015 is full open before valve F001 starts to close.(based on valve position indicating lights)d. Valve IE22-F001 Closed.e. Have Operations place Handswitch 1E22-HS-M609 HPCS PMP SUCT FM SUPP POOL to CLOSED position, verify Valve IE22-F015 Closes.f. Verify annunciator, "HPCS SUPP POOL SUCT VLV F015 MAN OVERRD", on 1H13-P601-16A (E-5), Alarmed. As soon as 1E22-F015 indicates not fully open, open Valve 1E22-F001 with Handswitch IE22-HS-M600 "HPCS PMP SUCT FM CST".J:\Adm_srvs\TECHPUB\REVISION\I\IE22R02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Page RTYPE B6.61 XRef DATA SHEET I (Continued) CONDENSATE STORAGE TANK LOW LEVEL CALIBRATION CNANNEL C SAFETY RELATED STEP REQUIRED ACTION 5.13.6 Decrease stable current to 4.00 mA (allowable tolerance 3.99 to 4.01) and record "As Found" 0% Master Trip Unit Meter Indication. MASTER TRIP UNIT ANALOG METER 1E22-N654C DESIRED MIN AS FOUND MAX FINAL Ft. Ft. Ft. Ft. Ft.01 NOP 1 NOP -Not on Peg 5.13.7 Press RESET pushbutton on Readout Assembly.5.13.8 Increase stable current until Master Trip Unit Resets (TRIP LED Off), then record "As Found" reset value from upper display of Readout Assembly.LOW LEVEL TRIP CALIBRATION DATA (RESET) IE22-N654C DESIRED MIN AS FOUND MAX FINAL mA mA MA mA mA 6.08 6.04 6.12 5.13.9 Pull out center knob of Select/Command switch.5.13.10 Connect Current Calibrator (mA OUT adjusted for 0 mA) and DVM positive leads (+) to Jl on Master Trip Unit and negative leads (-) to J2 of Calibration Unit.J:\Adm_srvs\TECHPUB\REVISION\I\IE22R02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Page RTYPE B6.61 XRef DATA SHIRT I (Continued) CONDENSATE STORAGE TANK LOW LEVEL CALIBRAT ION CHANNEL C SAFETY RBLATHD STEP REQUIRED ACTION INITIALS NOTE If On, reset GROSS FAIL LED. If LED does not go Off, adjust Current Calibrator until GROSS FAIL LED can be reset.$ 5.13.11 Slowly increase milliamp output of Current Calibrator until GROSS FAIL LED on Master Trip Unit comes On. Record "As Found" High Gross Fail trip voltage from DVM.MASTER TRIP UNIT GROSS FAIL CALIBRATION DATA IE22-N654C DESIRED MIN AS FOUND MAX FINAL Vdc Vdc Vdc Vdc Vdc 7.50 6.00 9.00 5.13.12 Reconnect Current Calibrator Trip Unit and positive lead adjusted for 0 mA). (Do not negative lead (-) to J1 (+) to J2 of Calibration disconnect DVM.)on Master Unit (mA$ 5.13.13 Reset GROSS FAIL LED on Master Trip Unit.$ 5.13.14 Slowly increase milliamp output of Current Calibrator until GROSS FAIL LED on Master Trip Unit comes On. Record "As Found" Low Gross Fail trip voltage from DVM.MASTER TRIP UNIT GROSS FAIL CALIBRATION DATA IE22-N654C DESIRED MIN AS FOUND MAX FINAL Vdc Vdc Vdc Vdc Vdc 0.694 0.500 0.887 5.13.15 Disconnect Current Calibrator and DVM from Master Trip Unit.$ 5.13.16 Reset GROSS FAIL LED and verify GROSS FAIL LED goes Off.J:\Admsrvs\TECHPUB\REVISION\I\IE22R02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Page RTYPE B6.61 XRef DATA SHEET I (Continued) CONDENSATE STORAGE TANK LOW LEVEL CALIBRATION CHANNEL C SAPETY RELATED STEP REQUIRED ACTION INITIALS 5.13.17 If Gross Failure adjustment is required, continue with Step 5.13.17a; otherwise, record them as "Final" values and proceed to Step 5.13.18.a. Install card extender between trip unit to be adjusted and card file.b. Connect DVM, negative (-) to J2 of Calibration Unit and positive (+) to J1 on Master Trip Unit.c. For Low Gross Fail adjustment, connect Current Calibrator positive (+) to J2 of Calibration Unit and negative (-) to Ji on Master Trip Unit. For High Gross Fail adjustment, connect Current Calibrator positive (+) to Jl on Master Trip Unit and negative (-) to J2 of Calibration Unit.d. Increase milliamp output of Current Calibrator until DVM reads "Desired" value for Gross Failure trip being adjusted.e. If necessary, adjust applicable CURRENT TRIP pot on circuit board ccw until GROSS FAIL LED can be reset with RESET pushbutton.

f. Very slowly turn pot cw until GROSS FAIL LED just comes On.g. Lower Current Calibrator output until GROSS FAIL LED can be reset with RESET pushbutton, then very slowly increase output until LED just comes On.h. If no further adjustment required, record value as "Final" and proceed to Step 5.13.17i; otherwise, repeat Steps 5.13.17c through 5.13.17h until unit requires no adjustment.
i. Disconnect Current Calibrator and DVM from Master Trip Unit and Calibration Unit.5.13.18 Push in center knob of Select/Command switch.J:\Admsrvs\TECHPUB\REVISION\I\IE22R02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Page RTYPE B6.61 XRef DATA SHIRT I (Continued)

CONDENSATE STORAGS TARM LOW LEVEL CALIBRATION CHANNEL C SAFETY RELATED STEP REQUIRED ACTION INITIALS 5.13.19 If Trip Point adjustment is required, continue Step 5.13.19a;otherwise, record as "Final" and proceed to Step 5.13.20.a. Adjust stable current to "Desired" value and adjust Trip Point adjustment as required.b. Recheck reset value. If reset requires no adjustment, proceed to Step 5.13.19e. If reset requires adjustment, continue with Step 5.13.19c.c. If necessary, install card extender between trip unit and card file.d. Adjust stable current to Desired Reset value and adjust RESET DIFFERENTIAL pot on circuit board as required.e. Recheck trip and reset values. If both trip and reset require no adjustment, record as "Final" and proceed to Step 5.13.20. If trip and/or reset require adjustment, repeat Steps 5.13.19a through 5.13.19e until unit requires no adjustment. 5.13.20 If Master Trip Unit Meter adjustment is required, continue with Step 5.13.20a; otherwise, record as "Final" and proceed to Step 5.13.21.a. If necessary, install card extender between Master Trip Unit and card file.b. Adjust meter ZERO at back of meter, then recheck 0, 50 and 100W indications. Repeat as required until unit requires no adjustment.

c. Record "Final" indications.

5.13.21 If installed, remove card extender from Master Trip Unit 1E22-N654C and reinstall trip unit in card file.5.13.22 Adjust stable current to approximately 20 mA.$ 5.13.23 Verify Annunciator, "CST LVL LO" on 1H13-P601-16A (C-4), Cleared.5.13.24 Computer point E22L600 displays NOT LOW.J:\Adm_srvs\TECHPUB\REVISION\I\IE22R02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Page RTYPE B6.61 XRef DATA SHEET I (Continued) CONDENSATE STORAGE TANK LOW LEVEL CALIBRATION CHANNEL C SAFETY RELATED STEP REQUIRED ACTION INITIALS 5.14 Transmitter Calibration (1E22-LT-N054C, 6.2 G, 119'Aux, Area 7)NOTE Refer to Return to Service Verification Record, for instrument valve identification. WARNING Any water drained from transmitter, test assembly, and/or associated tubing may be contaminated. Exercise caution and radiological safety precautions. 5.14.1 Perform following:

a. Remove valve seals as required.b. Close instrument Isolation Valve F01.5.14.2 Slowly loosen HP side vent plug on top of transmitter.

5.14.3 Perform one of the following:

a. Install test fitting in HP vent port on top of transmitter.

OR b. Open Test Valve F02 and ensure transmitter is vented and drained of all water.5.14.4 Perform following:

a. Connect test gauge and pressure source to either test fitting in HP vent port or HP manifold test connection.
b. Connect DVM (mAdc) to test connections on transmitter.

J:\Adm_srvs\TECHPUB\REVISION\I\IE22R02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Page RTYPE B6.61 XRef DATA SHEET I (Continued) CONDENSATZ STORAGE TANK LOW LEVEL CALIBRATION CHANNEL C SAFETY RELATED STEP REQUIRED ACTION 5.14.5 Apply SteDs 5.14.5, inputs as specified, and record "As Found" values.5.14.6/12 TRANSMITTER CALIBRATION DATA IE22-N054C INPUT OUTPUT DESIRED MIN AS FOUND MAX FINAL"H 2 0 mA mA mA mA mA 15 4.06 4.02 4.10 130 7.91 7.87 7.95 _250 11.93 11.89 11.97 370 15.95 15.91 15.99 490 19.97 19.93 20.01 370 15.95 15.91 15.99 250 11.93 11.89 11.97 130 7.91 7.87 7.95 72.9 6.00 5.96 (1) 6.04 15 4.06 4.02 4.10 NOE#il rnse vl- ocor -ond-- loa........t.5.2 91 -Jr .5.14.6 If "As Found" values requires no adjustment, record them as"Final" values and proceed to Step 5.14.13; otherwise, continue with Step 5.14.7.5.14.7 Apply 0% pressure, as specified, and adjust ZERO until output is as specified. 5.14.8 Apply 100% pressure, as specified, and adjust SPAN until output is as specified. 5.14.9 Repeat Step 5.14.7 and 5.14.8 until unit requires no further adjustment. J:\Admsrvs\TECHPUB\REVISION\I\IE22R02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Page RTYPE B6.61 XRef DATA SEUNT I (Continued) CONDENSATE STORAGE TAME LOW LEVEL CALIBRATION CHANNEL C SAFETY RELATED REQUIRED ACTION STEP INITIALS 5.14.10 Apply 50% pressure, as specified, and verify output requires no adjustment. If output requires adjustment, adjust Linearity adjustment until it is in tolerance. 5.14.11 Repeat Step 5.14.7 through 5.14.11 until transmitter requires no adjustment. 5.14.12 Reapply inputs as specified, and record "Final* values.5.14.13 Apply approximately 490" H 2 0 to transmitter. 5.15 Pull out center knob of Calibration Select/Command switch and ensure CAL LED is Off.$ 5.16 Press Master Trip Unit Gross Fail RESET pushbutton and verify GROSS FAIL LED is Off.5.17 Verify:$ 5.17.1 Status light TRIP UNIT IN CAL/GR FAIL on 1H13-P601-16B (DS-5)goes Off.5.18 CST Low Level Functional Test NOTE Various trips and/or alarms other than those stated below will occur during performance of this section. See Section 2.0.They will not require verification. 5.18.1 Establish communications between Control Room and transmitter. J:\Admsrvs\TECHPUB\REVISION\I\IB22R02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Page RTYPE B6.61 XRef DATA SBENT I (Continued) CONDENSATE STORAGE TAM LOW LEVEL CALIBRATION CHANNEL C SAFETY R.ULATED STEP REQUIRED ACTION 5.18.2 Decrease pressure to transmitter until it is near trip point.Very slowly continue to decrease pressure until TRIP LED on Master Trip Unit comes On.$ 5.18.3 Record trip value as indicated on pressure gauge.$5.18.4$ 5.18.5 LOW LEVEL TRIP FUNCTIONAL TEST DATA (TRIP) 1E22-N654C PRESS TO TEST GAUGE READING XMITTER SIDE DESIRED "H 2 0 MIN "H 2 0 TRIP "H 2 0 MAX "H20 High 72.9 70.5 75.3 Increase pressure until it is near reset point. Very slowly continue to increase pressure until Trip LED on Master Trip Unit goes Off.Record reset value as indicated on pressure gauge.LOW LEVEL TRIP FUNCTIONAL TEST DATA (RESET) 1E22-N654C PRESS TO TEST GAUGE READING XMITTER SIDE DESIRED "H20 MIN "H 2 0 TRIP "H 2 0 MAX "H20 High 75.3 N/A N/A 5.18.6 If any "As Found" values are out of tolerance, contact your immediate supervisor. 5.19 Restoration 5.19.1 Perform one of the following:

a. Vent pressure from HP section of transmitter and remove test gauge and pressure source. Install vent plug in HP vent port on top of transmitter.

OR b. Close Test Valve F02 and Vent pressure from HP section of transmitter and remove test gauge and pressure source.5.19.2 Very slowly open Instrument HP Isolation Valve F01 to admit process pressure to transmitter. J:\Admsrvs\TECH_PUB\REVISION\I\IE22R02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Page RTYPE B6.61 XRef DATA SHEET I (Continued) CONDENSATE STORAGE TANK LOW LEVEL CALIBRATION CHANNEL C SAFETY RELATED STEP REQUIRED ACTION INITIALS 5.19.3 Perform following:

a. Vent transmitter as necessary to ensure sensing leg is filled.b. Torque vent plugs on transmitter to 90 in/lbs.c. Remove DVM.5.19.4 Complete Return to Service Verification Record.INSTRUMENT NO.: 1E22-N054C LOCATION:

Column 6.2G 1A201 119'Aux.,Area 7 INSTRUMENT H L __ATMOSPHERE P002 F'Ol lI+PROCESS RETURN TO SERVICE VERIFICATION RECORD INITIALS VALVE DESCRIPTION TEST NORMAL FINAL PERFORMER VERIFIER HP TEST VLV F02 OPEN CLOSED HP ISOL VLV F01 CLOSED OPEN 5.19.5 Check all valves and fittings for leaks.5.19.6 Replace valve seals on Transmitter valves, as required.J:\Admsrvs\TECHPUB\REVISION\I\IE22R02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Page RTYPE B6.61 XRef DATA SHEET I (Continued) CONDENSATE STORAGE TANK LOW LEVEL CALIBRATZON CHANNEL C SAFETY RELATED STEP REQUIRED ACTION INITIALS 5.19.7 Have Operations close Valve 1E22-F015 using Handswitch 1E22-M609 on IHl3-P601-16C; and, as soon as Valve 1E22-F015 leaves OPEN position, open Valve 1E22-F001 using Handswitch 1E22-M600 on 1H13-P601-16C. VALVE RESTORATION INITIALS VALVE TEST NORMAL FINAL PERFORMER VERIFIER 1E22-F015 OPEN CLOSED 1E22-F001 CLOSED OPEN 5.19.8 Have Operations place HPCS MOV TEST handswitch (IE22-HS-M614) in NORM position.Operations: Verifier: 5.19.9 Verify: a. Annunciator, "HPCS SYS OOSVC. on 1H13-P601-16A (H-5), Cleared.b. Computer point E22L607 displays NORMAL.$ c. Status light HPCS MOV IN TEST STATUS on 1H13-P601-16B (DS-3) goes Off.5.19.10 Complete Hardware Restoration. HARDWARE RESTORATION INITIALS DESCRIPTION TEST NORMAL FINAL PERFORMER VERIFIER Cal Select/Command switch center knob Pos 3 OFF Cal Select/Command switch outer knob Pos 3 OFF Cal Unit POWER switch ON OFF J:\Adm_srvs\TECHPUB\REVISION\I\IE22R02 .DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Page RTYPE B6.61 XRef DATA SBHIT I (Continued) CONDENSATE STORAGE TANK LOW LEVEL CALIBRATION CHANNEL C SAFETY RELATED STEP REQUIRED ACTION INITIALS 5.19.11 Remove Digital Readout Assembly.5.19.12 Verify 1E22-N654C reflects current plant conditions. 5.19.13 Verify Annunciator "HPCS SUPP POOL SUCT VLV F015 MAN OVERRD", on IH13-P601-16A (E-5), Cleared.5.20 Record test equipment used for this test. This step may be performed out of sequence if desired.TEST EOUIPMENT LOG TEST EQUIPMENT M&TE NO. I CAL DUE DATE Y I 4 I 9 4 4 J: \Adm_srvs\TECH_PUB\REVISION\I\IE22R02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Page RTYPE B6.61 XRef DATA SHEET I (Continued) CONDENSATE STORAGE TANK LOW LEVEL CALIBRATION CHANNEL C SAFETY RELATED REQUIRED ACTION STEP 5.21 Complete "As Found" Loop Error Calculations. CAUTION: Recheck math, especially negative numbers.LOW LEVEL TRIP: 1E22-N654C XMTR mA TRIP UNIT mA mA Desired: 6.00 (2) As Found: As Found: -Desired: -6.00 6.00 (1 COMBINED Desired-f LL+ ( ) =("As Found" Loop Setpoint:*(Transfer to Step 5.22)Total Loop Error (add)mA*5.22 Complete Tech Spec "As Found" Compliance Verification. LOW LEVEL TRIP: IE22-N654C TECH SPEC: > 4.7 ft. (5.88 mA)Is following true? * > 5.88 mA (*Insert "As Found" Loop Setpoint)Initial: Yes (Complies w/Tech Spec limit)No (Does not comply -Notify Shift Supervisor) 5.23 Notify Shift Supervisor test is complete. Shift Supervisor's signature is required on Cover Sheet.J:\AdM_srvs\TECH_PUB\REVISION\I\IE22R02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Page RTYPE B6.61 XRef SURVEZLLANCE PROCEDURE DATA PACKAGE COVER SHET SAFETY RELATED Title: Condensate Storage Tank Low Level Calibration Channel G Technical Specifications: SR 3.3.5.1.5 and SR 3.3.5.1.6, Function 3.3.5.1-1.3.d SR 3.5.1.5 1.0 IMPACT STATEMENT 1.1 Performance of this procedure will result in swapping suction points of HPCS. Do not allow both HPCS Pump Suction valves (IE22-F001 and 1E22- F015)to be Closed at the same time.1.2 In Plant Mode 1, 2 or 3, when a channel is placed in an inoperable status solely for performance of required Surveillances, entry into appropriate Condition may be delayed for up to 6 hours provided associated function or redundant function maintains ECCS initiation capability. 1.3 In Plant Modes 4 or 5 when associated subsystems are required to be OPERABLE, entry into Conditions and Required Actions associated with LCO 3.3.5.1 may be delayed for up to 6 hours per Surveillance Note 2, provided the associated or redundant Functions maintain ECCS initiation capability. When one of required ECCS Subsystems is MANUALLY re-aligned, above Surveillance Note 2 does not provide allowances for removing from service instrumentation associated with the required automatic ECCS subsystem.

1.4 Thermal

overload protection 8 hour time limit LCO 6.8.2 is applicable.

2.0 PROCEDURE

2.1 Plant Mode is (Circle one): 1 2 3 4 5 2.2 Permission to begin test and perform system modifications. /Shift Supervisor Date 2.3 Test Start Time://Performer's Signature Date Time 3.0 TEST RESULTS 3.1 Test Completion: (Check one in each category.) Entire procedure completed [ I Partial procedure As Found data Acceptable u ]Unacceptable As Left data Acceptable ( ] Unacceptable Tech Spec Acceptance Criteria Acceptable ( I Unacceptable All other steps/data Acceptable [ ] Unacceptable completed[[[[[I]))3.2 TCNs in effect during performance (list): 3.3 Comments: Rev.verified by: 3.4 Test performed by Date/Time J:\Admsrvs\TECHPUB\REVISION\I\IE22R02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Page RTYPE B6.61 XRef SURVEILLANCE PROCEDURE DATA PACKAGZ COVER SHEET (Continued) SAFETY RELATED 4.0 DEFICIENCIES CR Issued #LCO Entered #WR Issued #5.0 APPROVAL Tech Spec Operability Requirements Acceptable [ ] Unacceptable [ ]Shift Supv/Manager Date Comments: CONCURRENCE I&C Superintendent Date J:\Admsrvs\TECHPUB\REVISION\I\IE22R02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Page RTYPE B6.61 XRef DATA SHBET I CONDENSATE STORAGE TANK LOW LEVEL CALIBRATION CHANNEL 0 SAFETY RELATED STEP REQUIRED ACTION INITIALS 5.1 Obtain permission from Shift Supervisor to begin test. Shift Supervisor's signature is required on Cover Sheet.5.2 Perform following:

5.2.1 Verify

prerequisite 4.2; HPCS is in Standby per SOI 04-1-01-E22-1 (with 1E22-F015 Closed and 1E22-F001 Open).5.2.2 Establish communications, if required, between Control Room and technician performing test.5.3 On Calibration Unit containing Master Trip Unit 1E22-N654G on 1H13-P625, ensure TRANSIENT CURRENT switch knob and center knob of Calibration Select/Command switch are pulled out.5.4 Ensure Calibration Unit POWER switch and center and outer Calibration Select/Command switches are in OFF position.5.5 Install Readout Assembly into Calibration Unit. Place Calibration Unit POWER switch to ON.5.6 Position center knob of Calibration Select/Command switch to position 4, selecting Master Trip Unit 1E22-N654G.

5.7 Position

outer knob of Calibration Select/Command switch to position 4, selecting Master Trip Unit 1E22-N654G.

5.8 Adjust

STABLE CURRENT knob to approximately 20 mA as observed on lower display of Readout Assembly.5.9 Perform following:

5.9.1 Complete

Test Start Time on Data Package Cover Sheet.5.9.2 Push in center knob of Calibration Select/Command switch to activate Calibration Unit.5.10 Perform following: 5.10.1 Ensure CAL LED on Calibration Unit comes On.$ 5.10.2 Verify GROSS FAIL LED on Master Trip Unit comes On.J:\Adm_srvs\TECHPUB\REVISION\I\IE22R02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Page RTYPE B6.61 XRef DATA SHBRNT I (Continued) CONDENSATE STORAGE TANK LOW LEVEL CALIBRATION CHANNEL G SAFETY RELAT STEP REQUIRED ACTION INITIALS 5.11 Verify: 5.11.1 Annunciator, "HPCS SYS OOSVC", on 1H13-P601-16A (H-5), Alarms.5.11.2 Computer point E22L607 displays OUT SVCE.$ 5.11.3 Status light TRIP UNIT IN CAL/GR FAIL on 1H13-P601-16B (DS-5)comes On.5.12 Perform following: 5.12.1 Have Operations place HPCS MOV TEST handswitch (1E22-HS-M614) in TEST position.$ 5.12.2 Verify status light HPCS MOV IN TEST STATUS DS3, on 1H13-P601-16B is On.5.13 Master Trip Unit Trip Calibration (1E22-N654G on IH13-P625) 5.13.1 Adjust stable current to 20.00 mA (allowable tolerance 19.99 to 20.01).5.13.2 Record "As Found" 100% Master Trip Unit Meter Indication. MASTER TRIP UNIT ANALOG METER IE22-N654G DESIRED MIN AS FOUND MAX FINAL Ft. Ft. Ft. Ft. Ft.40 39 NOP NOP -Not on Peg 5.13.3 Adjust stable current to 12.00 mA (allowable tolerance 11.99 to 12.01) and record "As Found" 50% Master Trip Unit Meter Indication. J:\Admsrvs\TECHPUB\REVISION\I\IE22R02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Page RTYPE B6.61 XRef DATA SHENT I (Continued) CONDENSATE STORAGE TANK LOW LEVEL CALIBRATION CHANNEL G SAFETY RELATED STEP REQUIRED ACTION INITIALS 5.13.4 Decrease stable current until Master Trip Unit Trips (TRIP LED On).Record "As Found" trip value from upper display of Readout Assembly.LOW LEVEL TRIP CALIBRATION DATA (TRIP) 1E22-N654G DESIRED MIN AS FOUND MAX FINAL mA mA mA mA mA 6.00 5.96 6.04 (73.02" H20) (70.62" H0) (2 (75.42" H20)(2): Transfer value to corresponding location in Step 5.21.5.13.5 Verify:$ a. Annunciator, "CST LVL LO" on 1H13-P601-16A (C-4), Alarmed.b. Computer point E22L600 displays LOW.$ c. Valve IE22-F015 Opened.NOTE Valve F015 is full open before valve Fool starts to close.(based on valve position indicating lights)d. Valve 1E22-F001 Closed.e. Have Operations place Handswitch 1E22-HS-M609 HPCS PMP SUCT FM SUPP POOL to CLOSED position, verify Valve 1E22-F015 Closes.f. Verify annunciator, "HPCS SUPP POOL SUCT VLV F015 MAN OVERRD", on 1H13-P601-16A (E-5), Alarmed. As soon as IE22-FO15 indicates not fully open, open Valve 1E22-F001 with Handswitch IE22-HS-M600 "HPCS PMP SUCT FM CST".J:\Adm_srvs\TECH_PUB\REVISION\I\IE22R02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Page RTYPE B6.61 XRef DATA SHENT I (Continued) CONDENSATE STORAGE TANK LOW LEVEL CALIBRATION CHANNEL 0 SAFETY RELATED STEP REQUIRED ACTION 5.13.6 Decrease stable current to 4.00 mA (allowable tolerance 3.99 to 4.01) and record "As Found" 0% Master Trip Unit Meter Indication. 5.13.7 5.13.8 MASTER TRIP UNIT ANALOG METER IE22-N654G DESIRED MIN AS FOUND MAX FINAL Ft. Ft. Ft. Ft. Ft.0 NOP 1 NOP -Not on Peg Press RESET pushbutton on Readout Assembly.Increase stable current until Master Trip Unit Resets (TRIP LED Off), then record "As Found" reset value from upper display of Readout Assembly.LOW LEVEL TRIP CALIBRATION DATA (RESET) 1E22-N654G DESIRED MIN AS FOUND MAX FINAL MA MA 6.0 MA MA 6.08 6.04 6.12 1 5.13.9 Pull out center knob of Select/Command switch.5.13.10 Connect Current Calibrator (mA OUT adjusted for 0 mA) and DVM positive leads (+) to Jl on Master Trip Unit and negative leads (-) to J2 of Calibration Unit.J:\Admsrvs\TECH_PUB\REVISION\I\IE22R02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Page RTYPE B6.61l XRef STEP DATA SHUNT I (Continued) CONDENSATE STORAGE TANK LOW LEVEL CALIBRATION CHANNEL 0 SAFETY RELATuD REQUIRED ACTION NOTE If On, reset GROSS FAIL LED. If LED does not go Off, adjust Current Calibrator until GROSS FAIL LED can be reset.INITIALS$ 5.13.11 Slowly increase milliamp output of Current Calibrator until GROSS FAIL LED on Master Trip Unit comes On. Record "As Found" High Gross Fail trip voltage from DVM.MASTER TRIP UNIT GROSS FAIL CALIBRATION DATA IE22-N6540 DESIRED MIN AS FOUND MAX FINAL Vdc Vdc Vdc Vdc Vdc 7.50 6.00 9.00 5.13.12 Reconnect Current Calibrator negative lead (-) to J1 Trip Unit and positive lead (+) to J2 of Calibration adjusted for 0 mA). (Do not disconnect DVM.)$ 5.13.13 Reset GROSS FAIL LED on Master Trip Unit.on Master Unit (mA$ 5.13.14 Slowly increase milliamp output of Current Calibrator until GROSS FAIL LED on Master Trip Unit comes On. Record "As Found" Low Gross Fail trip voltage from DVM.MASTER TRIP UNIT GROSS FAIL CALIBRATION DATA 1E22-N654G DESIRED MIN AS FOUND MAX FINAL Vdc Vdc Vdc Vdc Vdc 0.694 0.500 0.887 5.13.15 Disconnect Current Calibrator and DVM from Master Trip Unit.$ 5.13.16 Reset GROSS FAIL LED and verify GROSS FAIL LED goes Off.J:\Admsrvs\TECHPUB\REVISION\I\IE22R02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Page RTYPE B6.61 XRef DATA SHMUT I (Continued) CONDENSATE STORAGE TANK LOW LEVEL CALIBRATION CHANNEL 0 SAFETY RELATED STEP REQUIRED ACTION INITIALS 5.13.17 If Gross Failure adjustment is required, continue with Step 5.13.17a; otherwise, record them as "Final" values and proceed to Step 5.13.18.a. Install card extender between trip unit to be adjusted and card file.b. Connect DVM, negative (-) to J2 of Calibration Unit and positive (+) to Jl on Master Trip Unit.c. For Low Gross Fail adjustment, connect Current Calibrator positive (+) to J2 of Calibration Unit and negative (-) to Jl on Master Trip Unit. For High Gross Fail adjustment, connect Current Calibrator positive (+) to Jl on Master Trip Unit and negative (-) to J2 of Calibration Unit.d. Increase milliamp output of Current Calibrator until DVM reads "Desired" value for Gross Failure trip being adjusted.e. If necessary, adjust applicable CURRENT TRIP pot on circuit board ccw until GROSS FAIL LED can be reset with RESET pushbutton.

f. Very slowly turn pot cw until GROSS FAIL LED just comes On.g. Lower Current Calibrator output until GROSS FAIL LED can be reset with RESET pushbutton, then very slowly increase output until LED just comes On.h. If no further adjustment required, record value as "Final" and proceed to Step 5.13.17i; otherwise, repeat Steps 5.13.17c through 5.13.17h until unit requires no adjustment.
i. Disconnect Current Calibrator and DVM from Master Trip Unit and Calibration Unit.5.13.18 Push in center knob of Select/Command switch.J:\Adm_srvs\TECH_PUB\REVISION\I\IE22R02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Page RTYPE B6.61 XRef DATA SHEUT I (Continued)

CONDENSATE STORAGE TANK LOW LEVEL CALIBRATION CHANNEL 0 SAFETY RELAT STEP REQUIRED ACTION INITIALS 5.13.19 If Trip Point adjustment is required, continue Step 5.13.19a;otherwise, record as "Final" and proceed to Step 5.13.20.a. Adjust stable current to "Desired" value and adjust Trip Point adjustment as required.b. Recheck reset value. If reset requires no adjustment, proceed to Step 5.13.19e. If reset requires adjustment, continue with Step 5.13.19c.c. If necessary, install card extender between trip unit and card file.d. Adjust stable current to Desired Reset value and adjust RESET DIFFERENTIAL pot on circuit board as required.e. Recheck trip and reset values. If both trip and reset require no adjustment, record as "Final" and proceed to Step 5.13.20. If trip and/or reset require adjustment, repeat Steps 5.13.19a through 5.13.19e until unit requires no adjustment. 5.13.20 If Master Trip Unit Meter adjustment is required, continue with Step 5.13.20a; otherwise, record as "Final" and proceed to Step 5.13.21.a. If necessary, install card extender between Master Trip Unit and card file.b. Adjust meter ZERO at back of meter, then recheck 0, 50 and 100% indications. Repeat as required until unit requires no adjustment. C. Record "Final" indications. 5.13.21 If installed, remove card extender from Master Trip Unit 1E22-N654G and reinstall trip unit in card file.5.13.22 Adjust stable current to approximately 20 mA.$ 5.13.23 Verify Annunciator, "CST LVL LO" on 1H13-P601-16A (C-4), Cleared.5.13.24 Computer point E22L600 displays NOT LOW.J:\Adzn_srvs\TECHPUB\REVISION\I\IE22R02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Page_RTYPE B6.61 XRef DATA SHEET Z (Continued) CONDENSATE STORAGE TANK LOW LEVEL CALIBRATION CHANNEL G SAFETY RELATED STEP REQUIRED ACTION INITIALS 5.14 Transmitter Calibration (1E22-LT-NO54G, 6.2 G, 119'Aux, Area 7)NOTE Refer to Return to Service Verification Record, for instrument valve identification. WARNING Any water drained from transmitter, test assembly, and/or associated tubing may be contaminated. Exercise caution and radiological safety precautions. 5.14.1 Perform following:

a. Remove valve seals as required.b. Close instrument Isolation Valve F01.5.14.2 Slowly loosen HP side vent plug on top of transmitter.

5.14.3 Perform one of the following:

a. Install test fitting in HP vent port on top of transmitter.

OR b. Open Test Valve F02 and ensure transmitter is vented and drained of all water.5.14.4 Perform following:

a. Connect test gauge and pressure source to either test fitting in HP vent port or HP manifold test connection.
b. Connect DVM (mAdc) to test connections on transmitter.

J:\Admsrvs\TECHPUB\REVISION\I\IE22R02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Page RTYPE B6.61 XRef DATA SHEET I (Continued) rnTnWMQLaaq 9""WAtiu qh1W LOW LEVBL CALIBRATION CHANNEL Q SAFETY RELATED STEP REQUIRED ACTION 5.14.5 Apply SteDs 5.14.5, inputs as specified, and record "As Found" values.5.14.6/12 TRANSMITTER CALIBRATION DATA 1E22-N054G INPUT OUTPUT DESIRED MIN AS FOUND MAX FINAL"H20 mA mA mA mA mA 15 4.06 4.02 4.10 130 7.91 7.87 7.95 250 11.93 11.89 11.97 370 15.95 15.91 15.99 490 19.97 19.93 20.01 370 15.95 15.91 15.99 250 11.93 11.89 11.97 130 7.91 7.87 7.95 73.02 6.00 5.96 1) 6.04 15 4.06 4.02 4.10 NOTE: (1)Transfer value to corresponding location on Step 5.21.5.14.6 If "As Found" values requires no adjustment, record them' as"Final" values and proceed to Step 5.14.13; otherwise, continue with Step 5.14.7.5.14.7 Apply 0 pressure, as specified, and adjust ZERO until output is as specified. 5.14.8 Apply 100% pressure, as specified, and adjust SPAN until output is as specified. 5.14.9 Repeat Step 5.14.7 and 5.14.8 until unit requires no further adjustment. J:\Adm_srvs\TECHPUB\REVISION\I\IE22R02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Page RTYPE B6.61 XRef DATA SMHET I (Continued) CONDENSATE STORAGE TANK LOW LEVEL CALIBRATION CHANNEL 0 SAFETY RELATED STEP REQUIRED ACTION INITIALS 5.14.10 Apply 50% pressure, as specified, and verify output requires no adjustment. If output requires adjustment, adjust Linearity adjustment until it is in tolerance. 5.14.11 Repeat Step 5.14.7 through 5.14.11 until transmitter requires no adjustment. 5.14.12 Reapply inputs as specified, and record "Final" values.5.14.13 Apply approximately 490" H 2 0 to transmitter. 5.15 Pull out center knob of Calibration Select/Command switch and ensure CAL LED is Off.$ 5.16 Press Master Trip Unit Gross Fail RESET pushbutton and verify GROSS FAIL LED is Off.5.17 Verify:$ 5.17.1 Status light TRIP UNIT IN CAL/GR FAIL on 1H13-P601-16B (DS-5)goes Off.5.18 CST Low Level Functional Test NOTE Various trips and/or alarms other than those stated below will occur during performance of this section. See Section 2.0.They will not require verification. CAUTION Do not use portable radios in Control Room due to interference with surrounding electronic circuits and panels.5.18.1 Establish communications between Control Room and transmitter. J:\Admsrvs\TECHPUB\REVISION\I\IE22R02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Page RTYPE B6.61 XRef DATA SHEET I (Continued) CONDENSATE STORAGE TANK LOW LEVEL CALIBRATION CHANNEL 0 SAFETY RRLATED REQUIRED ACTION STEP INITIALS 5.18.2 Decrease pressure to transmitter until it is near trip point.Very slowly continue to decrease pressure until TRIP LED on Master Trip Unit comes On.$ 5.18.3 Record trip value as indicated on pressure gauge.$5.18.4$ 5.18.5$LOW LEVEL TRIP FUNCTIONAL TEST DATA (TRIP) IE22-N654G PRESS TO TEST GAUGE READING XMITTER SIDE DESIRED "H 2 0 MIN "H20 TRIP "H 2 0 MAX "H 2 0 High 73.02 70.62 75.42 Increase pressure until it is near reset point. Very slowly continue to increase pressure until Trip LED on Master Trip Unit goes Off.Record reset value as indicated on pressure gauge.LOW LEVEL TRIP FUNCTIONAL TEST DATA (RESET) 1E22-N654G PRESS TO TEST GAUGE READING XMITTER SIDE DESIRED "H 2 0 MIN "H 2 0 TRIP "H20 MAX "H20 High 75.42 N/A N/A 5.18.6 If any "As Found" values are out of tolerance, contact your immediate supervisor. 5.19 Restoration 5.19.1 Perform one of the following:

a. Vent pressure from HP section of transmitter and remove test gauge and pressure source. Install vent plug in HP vent port on top of transmitter.

OR b. Close Test Valve F02 and Vent pressure from HP section of transmitter and remove test gauge and pressure source.5.19.2 Very slowly open Instrument HP Isolation Valve F01 to admit process pressure to transmitter. J:\Admsrvs\TECH_PUB\REVISION\I\IE22R02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Page RTYPE B6.61 XRef DATA SHEET I (Continued) CONDENSATE STORAGE TANK LOW LEVEL CALIBRATION CHANNEL 0 SAFETY RELATED REQUIRED ACTION STEP INITIALS 5.19.3 Perform following:

a. Vent transmitter as necessary to ensure sensing leg is filled.b. Torque vent plugs on transmitter to 90 in/lbs.c. Remove DVM.5.19.4 Complete Return to Service Verification Record.INSTRUMENT NO.: IE22-N054G LOCATION:

Column 6.2G 1A201 119'Aux.,Area 7 IINSTRUMENT H L ___LI--F__ --TESTý0-2 ATMOSPHERE Fol ixiI PROCESS.INITIALS VALVE DESCRIPTION TEST NORMAL FINAL PERFORMER VERIFIER HP TEST VLV F02 OPEN CLOSED HP ISOL VLV F01 CLOSED OPEN 5.19.5 Check all valves and fittings for leaks.5.19.6 Replace valve seals on Transmitter valves, as required.J:\Adm_srvs\TECHPUB\REVISION\I\IE22R02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Page RTYPE B6.61 XRef DATA SHEET I (Continued) CONDENSATE STORAGE TANK LOW LEVEL CALIBRATION CHANNEL 0 SAFETY RELATED REQUIRED ACTION STEP INITIALS 5.19.7 Have Operations close Valve 1E22-F015 using Handswitch 1E22-M609 on 1HI3-P601-16C; and, as soon as Valve 1E22-F015 leaves OPEN position, open Valve 1E22-FOOl using Handswitch 1E22-M600 on 1H13-P601-16C. VALVE RESTORATION INITIALS VALVE TEST NORMAL FINAL PERFORMER VERIFIER IE22-F015 OPEN CLOSED 1E22-F001 CLOSED OPEN _5.19.8 Have Operations place HPCS MOV TEST handswitch (IE22-HS-M614) in NORM position.Operations: Verifier: 5.19.9 Verify: a. Annunciator, "HPCS SYS OOSVC" on 1H13-P601-16A (H-5), Cleared.b. Computer point E22L607 displays NORMAL.$ c. Status light HPCS MOV IN TEST STATUS on 1H13-P601-16B (DS-3) goes Off.5.19.10 Complete Hardware Restoration. HARDWARE RESTORATION INITIALS DESCRIPTION TEST NORMAL FINAL PERFORMER VERIFIER Cal Select/Command switch center knob Pos 4 OFF Cal Select/Command switch outer knob Pos 4 OFF Cal Unit POWER switch ON OFF J:\Admsrvs\TECHPUB\REVISION\I\IE22R02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Page RTYPE B6.61 XRef DATA SHET I (Continued) CONDENSATE STORAGE TANK LOW LEVEL CALIBRATION CHANNEL 0 SAFETY RICA&TE STEP REQUIRED ACTION INITIALS 5.19.11 Remove Digital Readout Assembly.5.19.12 Verify lE22-N654G reflects current plant conditions. 5.19.13 Verify Annunciator "HPCS SUPP POOL SUCT VLV F015 MAN OVERRD", on lHl3-P601-16A (E-5), Cleared.5.20 Record test equipment used for this test. This step may be performed out of sequence if desired.TEST EQUIPMENT LOG TEST EQUIPMENT M&TE NO. CAL DUE DATE J:\Adm_srvs\TECH_PUB\REVISION\I\IE22R02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Page RTYPE B6.61 XRef DATA SHEET X (Continued) CONDENSATE STORAGE TANK LOW LEVEL CALIBRATION CHANNEL G SAFETY RELATED REQUIRED ACTION STEP 5.21 Complete "As Found" Loop Error Calculations. CAUTION: Recheck math, especially negative numbers.LOW LEVEL TRIP: IE22-N654G XMTR mA TRIP UNIT mA mA Desired: 6.00 (2) As Found: (1) As Found: -Desired: -6.00 6.00 COMBINED Desired Total Loop Error (add)MA*( )"As Found" Loop Setpoint:*(Transfer to Step 5.22)5.22 Complete Tech Spec "As Found" Compliance Verification. LOW LEVEL TRIP: 1E22-N654G TECH SPEC: > 4.7 ft. (5.88 mA)Is following true? * > 5.88 mA (*Insert "As Found" Loop Setpoint)Initial: Yes (Complies w/Tech Spec limit)No (Does not comply -Notify Shift Supervisor) 5.23 Notify Shift Supervisor test is complete. Shift Supervisor's signature is required on Cover Sheet.J:\Adm_srvs\TECHPUB\REVISION\I\IE22R02.DOC Attachment 3 To GNRO-2007100068 GGNS Procedure 06-IC-1E51-Q-0002 G070068 PLANT OPERATIONS MANUAL Volume 06 Section 04 06-IC-1E51-Q-0002 Revision: 102 Date: 12/9/05 SURVEILLANCE PROCEDURE CONDENSATE STORAGE TANK (RCIC) LOW LEVEL FUNCTIONAL TEST SAFETY RELATED kAor Prepared: Reviewed: Approved: List of Effective Pages: Pages 1-6 Attachments I, II List of TCNs Incorporated: Revision TCN 20 None 100 1 101 2 102 None J:\ADMSRVS\TECHPUB\REVISION\I\IE51Q02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Title: Condensate Storage Tank No.: Revision:.102 Page: i (RCIC) Low Level Functional Test 06-IC-1E51- -0002 10CFR5O.59 Review Required? (V) Yes If Yes, transmit 50.59 Review Form along with procedure to Document Control as a separate record.No Not required per LI-101 Croos-Discipline review required? ( ) Yes (Note affected Departments Below)Preparer Initials>>> 4 Department Cross-Discipline Reviews Needed Signoff (signed, electronic, telcon)Engineering Does this directive contain Tech Spec Triggers? C ) YES (/) NO RZQUIRENMNTS CROSS-REFERENCE LIST Requirement Implemented by Directive Directive Paragraph Number Name Paragraph Number That Implements Requirement Function 3.3.5.2-1.3

  • Tech Spec SR 3.3.5.2.2
  • TRM SR 6.8.2.1 2.8; 5.13.30 TRM 3.3.5.2-1.3
    • Covered by directive as a whole or by various paragraphs of the directive.

NOTE The Equipment Database (EDB) Request statement is applicable only to Volume 06 and 07 maintenance directives. EDB Change Request generated and the backup documentation available for setpoint and/or calibration data only 0 Yes 0 N/A EDBCR #Current Revision Statement Revision 102 incorporates:

  • ER-GG-1999-0217-000 which changes transmitters, ranges, and setpoints of CST level instrumentation.

J J:\ADMSRVS\TECHPUB\REVISION\I\IE51Q002.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Title: Condensate Storage Tank No.: Revision: 102 Page: 1 (RCIC) Low Level Functional Test 06-IC-IE51-Q-0002

1.0 PURPOSE

1.1 To functionally test the Condensate Storage Tank Low Level Trip Systems to ensure operability. 1.2 This Functional Test is associated with instruments 1E51-LIS-N635A & E.1.3 This procedure provides testing at least once per 92 days which satisfies the requirement for a CHANNEL FUNCTIONAL TEST for the RCIC System instrumentation per SR 3.3.5.2.2, Function 3.3.5.2-1.3.

1.4 Changes

required for implementation of 1994 TSIP were incorporated in Revision 100. For historical reference this statement should not be deleted.2.0 PRECAUTIONS AND LIMITATIONS

2.1 Steps

marked with a pound sign (#) are initialed on Data Sheet I as each step is completed. If steps are repeated during this functional test, they are to be reinitialed on Data Sheet I. Place an N/A on Data Sheet I for optional steps not performed. 2.2 If "As Found" values are not in tolerance, if procedural steps cannot be completed as stated, or if any other problem develops during this test, notify your immediate supervisor. 2.3 If "As Found" values exceed the Technical Specifications tolerance, notify the Shift Supervisor.

2.4 Steps

marked with a dollar sign ($) are required to be completed for Technical Specifications Acceptance Criteria.2.5 In Plant Mode 1 (Plant Mode 2 or 3 with Reactor Steam Dome Pressure >150 psig) this test must be performed on only one channel at a time. When one channel is being tested, the remaining channels must be in the Normal (untripped) condition. 2.6 The instrument channel under test shall not be out of service for more than six hours without entering the applicable Tech Spec Action Statement. When it becomes apparent this time limit may be exceeded, immediately contact the Shift Supervisor. The time limit is applicable only when the instrument channel under test is required to be Operable.J:\ADMSRVS\TECHPUB\REVISION\I\IE51Q02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Title: Condensate Storage Tank No.: Revision: 102 IPage: 2 (RCIC) Low Level Functional Test 06-IC-1E51-Q-0002 2.7 The following alarms, trips, and actions occurs from the Units: following Trip INSTRUMENT NO. ANNUNCIATOR COMPUTER POINT IND LIGHT/ACTION CHANNEL A 1E51-N635A "CST LVL LO", E51NI00 Open Valve F031 Low Level 1H13-P601-21A SUCT FROM SUPPR POOL (B-5) VALVE OPEN/NOT OPEN"RCIC SYS OOSVC" E51N104 Close Valve F010 1H13-P601-21A SUCT FROM CONDENSATE (H-5) TANK OPEN/NOT OPEN CHANNEL E 1E51-N635E Close Valve F022 Low Level Close Valve F059 2.8 Placing a MOV TEST switch to TEST places the overload protection in force for the valves associated with that Test switch. The overload protection may be left in force for up to eight hours, after which the overloads must be bypassed by placing the MOV TEST switch to NORMAL or declare the valves Inoperable and enter the applicable Tech Spec Action Statements. (Refer to TRM 6.8.2)2.9 Valves F022 and F059 will Close, if Open, when F031 Opens.3.0 REQUIRED MATERIALS AND TEST EQUIPMENT 3.1 Attachments I, II (as required by channel to be tested)3.2 Current Calibrator, Transmation 1040/1048 or equivalent (0-40 mAdc output)no M&TE requirements

3.3 Readout

Assembly, Rosemount 710DU or equivalent (accuracy better than+/- 0.040 mAdc at 0-20 mA)3.4 Card extender (510DU Type) (As Needed)4.0 PREREQUISITES AND PLANT CONDITIONS 4.1 This procedure may be performed in any Plant Mode except as modified by the releasing organization. J:\ADMSRVS\TECHPUB\REVISION\I\IE51Q02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Title: Condensate Storage Tank No.: 7Revision: 102 Page: 3 (RCIC) Low Level Functional Test 06-IC-IE51-Q-0002

5.0 INSTRUCTIONS

5.1 Obtain

permission from Shift Supervisor to begin the test. Shift Supervisor's signature is required on Data Package Cover Sheet.5.2 Establish communications, if required, between Control Room and technician performing test.5.3 On the Calibration Unit containing Master Trip Unit (see Data Sheet I), ensure the TRANSIENT CURRENT switch knob and the center knob of Calibration Select/Command switch are pulled out.5.4 Ensure the Calibration Unit POWER switch and both the center and outer Calibration Select/Command switches are in the OFF position.5.5 Install the Readout Assembly into the Calibration Unit.5.6 Place the Calibration Unit POWER switch to ON.5.7 Position the center and outer knobs of the Calibration Select/Command switch to positions (see Data Sheet I), selecting Master Trip Unit (see Data Sheet I).5.8 Adjust STABLE CURRENT knob to approximately 20 mA on the Readout Assembly.5.8.1 Complete the Test Start Time on the Data Package Cover Sheet.5.9 Push in center knob of Calibration Select/Command switch to activate Calibration Unit.5.10 Ensure that CAL LED on Calibration Unit is On.$ # 5.11 Verify that GROSS FAIL LED on Master Trip Unit is On.$ # 5.11.1 Verify status light (see Data Sheet I) comes On.# 5.12 Have Operations place the RCIC DIV 1 MOV TEST handswitch, IE51-HS-M641, in the TEST position.# 5.12.1 Verify status light (see Data Sheet I) comes On.5.13 Master Trip Unit Functional with Calibration (see Data Sheet I for location and ID)5.13.1 Adjust Stable Current to 20.00 mA (allowable error 19.99 to 20.01).5.13.2 Record "As Found" 100% Master Trip Unit meter indication on Data Sheet II.5.13.3 Adjust Stable Current to 12.00 mA (allowable error 11.99 to 12.01)and record "As Found" 50% Master Trip Unit meter indication on Data Sheet II.5.13.4 Decrease Stable Current until Master Trip Unit Trips (TRIP LED On). Record "As Found" trip value from the upper display of the Readout Assembly on Data Sheet III.$ # 5.13.5 Verify the "(see Data Sheet I)" annunciator, (see Data Sheet I), Alarmed.J:\ADMSRVS\TECHPUB\REVISION\I\IE51Q02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Title: Condensate Storage Tank No.: Revision: 102 Page: 4 (RCIC) Low Level Functional Test 06-IC-1E51-Q-0002 5.13.6 Decrease Stable Current to 4.00 mA (allowable error 3.99 to 4.01)and record "As Found" 0% Master Trip Unit meter indication on Data Sheet II.5.13.7 Press RESET pushbutton on Readout Assembly.5.13.8 Increase Stable Current until the Master Trip Unit Resets (TRIP LED Off). Record "As Found" reset value from the upper display of the Readout Assembly on Data Sheet III.$ # 5.13.9 Verify the "(see Data Sheet I)" annunciator, (see Data Sheet I), (see Data Sheet I), Cleared.5.13.10 Pull out center knob of Calibration Select/Command switch.5.13.11 Connect Transmation (mA OUT adjusted for 0 mA) positive lead (+)to J1 on the Master Trip Unit and the negative lead (-) to J2 on the Calibration Unit.NOTE If On, reset the GROSS FAIL LED. If the LED does not go Off, adjust Transmation until GROSS FAIL LED can be Reset.$ # 5.13.12 Slowly increase milliamp output of Transmation until GROSS FAIL LED on Master Trip Unit comes On.5.13.13 Reconnect Transmation negative lead (-) to Ji on Master Trip Unit and positive lead (+) to J2 on Calibration Unit (mA OUT adjusted for 0 mA).$ # 5.13.14 Reset GROSS FAIL LED on Master Trip Unit.$ # 5.13.15 Slowly increase milliamp output of Transmation until GROSS FAIL LED on Master Trip Unit comes On.$ # 5.13.16 Disconnect Transmation from Master Trip Unit and Calibration Unit.Reset GROSS FAIL LED on Master Trip Unit. Verify GROSS FAIL LED Off.5.13.17 Push in center knob of Calibration Select/Command switch.5.13.18 If Trip Point adjustment is required continue with Step 5.13.18a.If not, record "Final" values and proceed to Step 5.13.19.a. Adjust Stable Current to desired value on Data Sheet III and adjust Trip Point adjustment as required.b. Recheck reset value. If reset requires no adjustment, proceed to Step 5.13.18e. If reset requires adjustment, proceed to Step 5.13.18c.J:\ADMSRVS\TECHPUB\REVISION\I\IE51Q02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Title: Condensate Storage Tank No.: Revision: 102 Page: 5 (RCIC) Low Level Functional Test 06-IC-1E51-Q-0002 5.13.18 (Cont.)c. Install a card extender between trip unit and card file, if required.d. Adjust Stable Current to Desired Reset value on Data Sheet III and adjust RESET DIFFERENTIAL pot on circuit board as required.e. Recheck trip and reset values. If both trip and reset require no further adjustment, record them as "Final" values and proceed to Step 5.13.19. If not, repeat Steps 5.13.18a through 5.13.18e until unit requires no further adjustment. 5.13.19 If Master Trip unit meter adjustment is required continue with Step 5.13.19a. If not, record them as "Final" values and proceed to Step 5.13.20.a. Install a card extender between Master Trip Unit and card file, if required.b. Adjust meter ZERO at back of meter, then recheck the 0, 50, and 100% indications. Repeat as required until unit requires no further adjustment.

c. Record "Final" indications on Data Sheet II.# 5.13.20 Remove card extender (if installed earlier) from Master Trip Unit and reinstall trip unit in card file.5.13.21 Adjust Stable Current to approximately 20.00 mA (allowable error 19.99 to 20.01).5.13.22 Pull out center knob of Calibration Select/Command switch.5.13.23 Ensure that CAL LED is Off.$ # 5.13.24 Press Master Trip Unit Gross Fail RESET pushbutton and verify GROSS FAIL LED is Off.$ # 5.13.25 Verify status light (see Data Sheet I) goes Off.5.13.26 Perform applicable section of Hardware Restoration on Data Sheet III.# 5.13.27 Remove Digital Readout Assembly.5.13.28 If required, have Operations close Suppression Pool Suction valve (F031) and open CST Suction valve (Fo10) in accordance with SOI 04-1-01-E51-1.

Complete Valve Restoration section on Data Sheet II documenting "Final" valve position.5.13.29 Have Operations place the RCIC DIV I MOV TEST switch to Norm and complete applicable Hardware Restoration on Data Sheet III.$ # 5.13.30 Verify status light (see Data Sheet I), goes Off.5.13.31 Record test equipment used for this test on Data Sheet II.This step may be performed out of sequence if desired.J:\ADMSRVS\TECHPUB\REVISION\I\IE51Q02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Title: Condensate Storage Tank gNo.: Revision: 102 Page: 6 (RCIC) Low Level Functional Test 06-IC-1E51-Q-0002

  1. 5.13.32 Verify reading (see Data Sheet I) is consistent with existing plant conditions.

5.13.33 Notify Shift Supervisor the test is complete. Shift Supervisor's signature is required on Data Package Cover Sheet.

6.0 REFERENCES

6.1 Bechtel

Drawings 6.1.1 E-1185, E51 -Reactor Core Isolation Cooling Sys 6.1.2 M-1065, P11 -Condensate & Refueling Water Storage & Transfer Sys 6.1.3 M-1083A, E51 -Reactor Core Isolation Cooling Sys 6.2 Rosemount Technical Manual 460000047 Rosemount 510DU Digital Trip Unit 6.3 Section Instruction 07-S-53-181, Bench Calibration of the Rosemount 510DU (710 DU) Master and Slave Trip Units 6.4 Bechtel Setpoint Calculation, E51 Calc No. J-E51-1 Rev 0, PMI 83/5655 6.5 USFAR Chapter 16, Appendix 16B 6.6 ER-GG-1999-0217-000 6.7 SC-1E51-LT-N035,Rev.1 J:\ADMSRVS\TECHPUB\REVISION\I\IE51Q02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Page RTYPE B6.61 XRef SURVEILLANCE PROCEDURE DATA PACKAGE COVER SHEET SAFETY RELATED Title: Condensate Storage Tank (RCIC) Low Level Functional Test Channel A Technical Specifications: SR 3.3.5.2.2, Function 3.3.5.2-1.3

1.0 IMPACT

STATEMENT 1.1 If no RCIC Isolation signal is present, performance of this procedure opens the Suppression Pool Suction valve (F031), closes the CST Suction valve (FO10), and closes the RCIC TEST BYPASS TO CST valves (F022 and F059).1.2 In Plant Mode 1 (Plant Mode 2 or 3 with Reactor Steam Dome Pressure >150 psig), entry into Conditions and Required Actions associated with LCO 3.3.5.2 may be delayed no more than six hours provided the associated Function maintains RCIC initiation capability. 1.3 The thermal overload protection 8 hour time limit (LCO 6.8.2) is applicable.

2.0 PROCEDURE

2.1 Plant Mode is (circle one): 1 2 3 4 5 2.2 Permission to begin test /Shift Supervisor / Date 2.3 Test Start Time: / /Performer's signature Date Time 3.0 TEST RESULTS 3.1 Test Completion: (Check one in each category.) Entire procedure completed [ Partial procedure completed As Found Data Acceptable [ I Unacceptable As Left Data Acceptable [ ] Unacceptable Tech Spec Acceptance Criteria Acceptable [ ] Unacceptable All other steps/data Acceptable [ C Unacceptable 3.2 TCNs in effect during performance (list): 3.3 Comments: Rev Verified by: 3.4 Test performed by Date/Time 4.0 DEFICIENCIES CR Issued #LCO Entered # WR Issued #5.0 APPROVAL Tech Spec Operability Requirements Acceptable ( ] Unacceptable ]Shift Supv/Manager Date _Comments: CONCURRENCE I&C Superintendent Date J:\ADMSRVS\TECHPUB\REVISION\I\IE51Q02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Page RTYPE B6.61 XRef DATA SHEET I CONDENSATE STORAGE TANK (RCIC) LOW LEVEL FUNCTIONAL TEST CHANNEL A SAFETY RELATED I I STEPS REQUIRED ACTION INITIALS 5.3 1ES1-N635A on 1H13-P629 N/A 5.7 Pos 6, 1ES1-N635A N/A 5.11 GROSS FAIL LED On Status light TRIP UNIT 1 IN CAL/GR FAIL, 5.11.1 1H13-P601-21B (DS-12), comes On ....RCIC DIV 1 MOV TEST handswitch, 1E51-HS-M641, in 5.12 TEST position Status light RCIC DIV 1 MOV IN TEST STATUS, 5.12.1 1H13-P601-21B (DS-8), comes On 5.13 Master Trip Unit IE51-N635A on IH13-P629 N/A"CST LVL LO" annunciator, 5.13.5 IH13-P601-21A (B-5), Alarmed"CST LVL LO" annunciator, 5.13.9 1H13-P601-21A (B-5), Cleared 5.13.12 GROSS FAIL LED On 5.13.14 GROSS FAIL LED Off 5.13.15 GROSS FAIL LED On 5.13.16 Transmation removed, GROSS FAIL LED Off 5.13.20 Card extender removed (1E51-N635A) 5.13.24 GROSS FAIL LED Off Status light TRIP UNIT 1 IN CAL/GR FAIL, 5.13.25 1H13-P601-21B (DS-12), goes Off 5.13.27 Digital Readout Assembly removed Status light RCIC DIV 1 MOV IN TEST STATUS, 5.13.30 1H13-P601-21B (DS-8), goes Off 5.13.32 Reading 1E51-N635A is consistent with plant conditions I J:\ADMSRVS\TECHPUB\REVISION\I\IE51Q02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Page RTYPE B6.61 XRef DATA SHEET II CONDENSATE STORAGE TANK (RCIC) LOW LEVEL FUNCTIONAL TEST CHANNEL A SAFETY RELATED MASTER TRIP UNIT ANALOG METER 1ES1-N63SA DESIRED MIN AS FOUND MAX FINAL STEP/PERCENT Ft. Ft. Ft. Ft. Ft.5.13.2 / 100 40 39 NOP 5.13.3 / 50 20 19 21 5.13.6 / 0 0 NOP 1 NOP -Not on Peg 5.13.31 TEST EQUIPMENT LOG (This step may be performed out of sequence if desired)TEST EQUIPMENT M&TE NO. CAL DUE DATE 5.13.28 VALVE RESTORATION INITIALS VALVE TEST NORMAL FINAL PERFORMER VERIFIER 1E51-F031 OPEN CLOSED lE51-F010 CLOSED OPEN J:\ADMSRVS\TECHPUB\REVISION\I\IE51Q02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Page RTYPE B6.61 XRef DATA SHEET III CONDENSATE STORAGE TANK (RCIC) LOW LEVEL FUNCTIONAL TEST CHANNEL A SAFETY RELATED TRIP CALIBRATION DATA IE51-N635A DESIRED MIN AS FOUND MAX FINAL TECH SPEC TRIP/RESET mA mA mA mA mA mA 5.60 5.56 (1) 5.64 1 5.48 5.13.4 (62.0" H 2 0) (59.6" H 2 0) (64.4" Hao) (3.7 ft.)5.13.8 5.68 5.64 5.72 N/A (1) Initial: Yes (As Found data complies with Tech Spec limit)No (As Found data does not comply -Notify Shift Supervisor) HARDWARE RESTORATION INITIALS STEP DESCRIPTION TEST NORMAL FINAL PERFORMER VERIFIER Cal Select/Command switch center knob Pos 6 OFF 5.13.26 Cal Select/Command switch outer knob Pos 6 OFF Cal Unit POWER switch ON OFF RCIC DIV 1 MOV TEST 5.13.29 switch IE51-HS-M641 TEST NORMAL J:\ADMSRVS\TECHPUB\REVISION\I\IE51Q02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Page RTYPE B6.61 XRef SURVEILLANCE PROCEDURE DATA PACKAGE COVER SHEET SAFETY RELATED Title: Condensate Storage Tank (RCIC) Low Level Functional Test Channel E Technical Specifications: SR 3.3.5.2.2, Function 3.3.5.2-1.3

1.0 IMPACT

STATEMENT 1.1 If no RCIC Isolation signal is present, performance of this procedure opens the Suppression Pool Suction valve (F031), closes the CST Suction valve (Fo10), and closes the RCIC TEST BYPASS TO CST valves (F022 and F059).1.2 In Plant Mode 1 (Plant Mode 2 or 3 with Reactor Steam Dome Pressure >150 psig), entry into Conditions and Required Actions associated with LCO 3.3.5.2 may be delayed no more than six hours provided the associated Function maintains RCIC initiation capability. 1.3 The thermal overload protection 8 hour time limit (LCO 6.8.2) is applicable.

2.0 PROCEDURE

2.1 Plant Mode is (circle one): 1 2 3 4 5 2.2 Permission to begin test /Shift Supervisor / Date 2.3 Test Start Time: / /Performer's signature Date Time 3.0 TEST RESULTS 3.1 Test Completion: (Check one in each category.) Entire procedure completed [ 3 Partial procedure completed As Found Data Acceptable [ ] Unacceptable As Left Data Acceptable [ ] Unacceptable [Tech Spec Acceptance Criteria Acceptable ( ] Unacceptable All other steps/data Acceptable [ ] Unacceptable (3.2 TCNs in effect during performance (list): 3.3 Comments: Rev Verified by: 3.4 Test performed by _Date/Time

4.0 DEFICIENCIES

CR Issued #LCO Entered # WR Issued #5.0 APPROVAL Tech Spec Operability Requirements Acceptable [ ] Unacceptable [ ]Shift Supv/Manger Date _Comments: CONCURRENCE I&C Superintendent Date J:\ADMSRVS\TECHPUB\REVISION\IE51Q02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE 06-IC-1E51-Q-0002 IjRevision: Page RTYPE B6.61 XRef DATA SHEET I CONDENSATE STORAGE TANK (RCIC) LOW LEVEL FUNCTIONAL TEST CHANNEL E SAFETY RELATED STEPS REQUIRED ACTION INITIALS 5.3 1ES1-N635E on 1H13-P629 N/A 5.7 Pos 7, 1E51-N635E N/A 5.11 GROSS FAIL LED On Status light TRIP UNIT 1 IN CAL/GR FAIL, 5.11.1 1H13-P601-21B (DS-12), comes On RCIC DIV 1 MOV TEST handswitch, 1E51-HS-M641, in 5.12 TEST position Status light RCIC DIV 1 MOV IN TEST STATUS, 5.12.1 1H13-P601-21B (DS-8), comes On 5.13 Master Trip Unit 1E51-N635E on 1H13-P629 N/A"CST LVL LO" annunciator, 5.13.5 1H13-P601-21A (B-5), Alarmed"CST LVL LO" annunciator, 5.13.9 1H13-P601-21A (B-5), Cleared 5.13.12 GROSS FAIL LED On 5.13.14 GROSS FAIL LED Off 5.13.15 GROSS FAIL LED On 5.13.16 Transmation removed, GROSS FAIL LED Off 5.13.20 Card extender removed (1E51-N635E) 5.13.24 GROSS FAIL LED Off Status light TRIP UNIT 1 IN CAL/GR FAIL, 5.13.25 1H13-P601-21B (DS-12), goes Off 5.13.27 Diqital Readout Assembly removed Status light RCIC DIV 1 MOV IN TEST STATUS, 5.13.30 IH13-P601-21B (DS-8), goes Off 5.13.32 Reading IE51-N635E consistent with plant conditions J:\ADMSRVS\TECHPUB\REVISION\IE51Q02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Page RTYPE B6.61 XRef DATA SHEET II CONDENSATE STORAGE TANK (RCIC) LOW LEVEL FUNCTIONAL TEST CHANNEL E SAFETY RELATED MASTER TRIP UNIT ANALOG METER IE51-N635E DESIRED MIN AS FOUND MAX FINAL STEP/PERCENT Ft. Ft. Ft. Ft. Ft.5.13.2 / 100 40 39 NOP 5.13.3 / 50 20 19 21 5.13.6 / 0 0 NOP 1 NOP -Not on Peg 5.13.31 TEST EQUIPMENT LOG (This step may be performed out of sequence if desired)TEST EQUIPMENT M&TE NO. CAL DUE DATE 5.13.28 VALVE RESTORATION INITIALS VALVE TEST NORMAL FINAL PERFORMER VERIFIER 1E51-F031 OPEN CLOSED IE51-F010 CLOSED OPEN J:\ADMSRVS\TECHPUB\REVISION\IE51Q02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE ,-IC-1E51-Q-0002 I Revision: 102 Page RTYPE B6.61 XRef DATA BRUNT III CONDENSATE STORAGE TANK (RCIC)LOW LEVEL FUNCTIONAL TEST CHANNEL E SAFETY RELATED TRIP CALIBRATION DATA 1E51-N635E DESIRED MIN AS FOUND MAX FINAL TECH SPEC TRIP/RESET mA mA mA mA mA mA 5.60 5.56 (1) 5.64 2: 5.48 5.13.4 (62.0" H 2 0) (59.6" H 2 0) (64.4" H 2 0) (3.7 ft.)5.13.8 5.68 5.64 5.72 1 1 N/A _(1) Initial: Yes (As Found data complies with Tech Spec limit)No (As Found data does not comply -Notify Shift Supervisor) HARDWARE RESTORATION INITIALS STEP DESCRIPTION TEST NORMAL FINAL PERFORMER VERIFIER Cal Select/Command switch center knob Pos 7 OFF 5.13.26 Cal Select/Command switch outer knob Poe 7 OFF Cal Unit POWER switch ON OFF RCIC DIV 1 MOV TEST 5.13.29 switch 1E51-HS-M641 TEST NORMAL J:\ADMSRVS\TECHPUB\REVISION\IE51Q02.DOC Attachment 4 To GNRO-2007100068 GGNS Procedure 06-IC-1E51-R-0002 G070068 PLANT OPERATIONS MANUAL Volume 06 06-IC-1E51-R-0002 Section 04 Revision: 103 Date: 12/9/05 SURVEILLANCE PROCEDURE CONDENSATE STORAGE TANK (RCIC)LOW LEVEL CALIBRATION SAFETY RELATED Prepared: __Reviewed: Approved: _ _ _ _ _ _ _ _ _I &C Sueitendent List of Effective Pages: Pages 1-3 Attachments I, II List of TCNs Incorporated: Revision TCN 0 None 1 None 2 1 3 None 20 None 21 None 22 2 23 3 24 4 100 None 101 5 102 None 103 None J:\ADM_SRVS\TECHSRVS\I\IE51R02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Title: Condensate Storage No.:06-IC-1E51-R-0002 Revision: 103 Page: i Tank (RCIC) Low Level Calibration I0CYR50.59 Review Required? (0) Yes If Yes, transmit 50.59 Review Form along with procedure to Document Control as a separate record.No Not required per LI-101 Cross-Discipline review required? (V) Yes (Note affected Departments Below)( )No Preparer Initials>>> Department Cross-Discipline Reviews Needed Signoff Engineering I/,-J.pigned, electronic. telcon)Engineering ._Does this directive contain Tech Spec Triggers? ( ) YES (v) NO REQUIREMINTS CROSS-REFERENCE LIST Requirement Implemented by Directive Directive Paragraph Number Name Paragraph Number That Implements Requirement Function 3.3.5.2-1.3

  • Tech Spec SR 3.3.5.2.4
  • Tech Spec SR 3.3.5.2.5
  • Tech Spec SR 3.5.3.5 5.16.4, 5.16.5d&e TRM 6.8.2.1 2.9, 5.22.11 TRM 3.3.5.2-1.3 1* Covered by directive as a whole or by various paragraphs of directive.

NOTE The Equipment Database (EDB) Request statement is applicable only to Volume 06 and 07 maintenance directives. EDB Change Request generated and the backup documentation available for setpoint and/or calibration data only [3 Yes 0 N/A EDBCR #Current Revision Statement Revision 103 incorporates: " ER-GG-1999-0217-000 which changes transmitters, ranges, and setpoints of CST level instrumentation.

  • Procedure required numerous changes therefore no rev bars were used.J:\ADM_SRVS\TECHSRVS\I\IE51RO2.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Title: Condensate Storage No. : 06-IC-1E51-R-0002 IRevision:

103 Page:I Tank (RCIC) Low Level Calibration

1.0 PURPOSE

1.1 To calibrate Condensate Tank Low Level Trip Channels to ensure operability. This CHANNEL CALIBRATION is required every 18 months in accordance with SR3.3.5.2.4, Function 3.3.5.2-1.3 of GGNS Technical Specifications. 1.2 To verify RCIC suction path is automatically transferred from CST to suppression pool on CST low level. This test is required every 18 months in accordance with SR 3.5.3.5 (for 1E51-F031 and 1E51-F010) of GGNS Technical Specifications. 1.3 An additional purpose of this procedure is to provide testing at least once every 18 months which satisfies requirement for LOGIC SYSTEM FUNCTIONAL TEST of RCIC System Actuation Instrumentation as per SR 3.3.5.2.5, Function 3.3.5.2-1.3 of GGNS Technical Specifications. 1.4 This procedure is associated with instruments IE51-LT-N035A/E and 1E51-LIS-N635A/E.1.5 Changes required for implementation of 1994 TSIP were incorporated in Revision 100. For historical reference this statement should not be deleted.2.0 PRECAUTION AND LIMITATIONS 2.1 If steps are repeated during this calibration, they shall be reinitialed on Data Sheet I. Place N/A on Data Sheet I for optional steps not performed.

2.2 Steps

marked with dollar sign ($) are those items which are required to be completed for Technical Specification Acceptance Criteria.2.3 If "As Found" values are not in tolerance, procedural steps cannot be completed as stated, or if any other problem develops during this test, notify your immediate supervisor. 2.4 If "As Found" values exceed Technical Specification tolerance, notify your Shift Supervisor. 2.5 Any water drained from transmitter, test assembly, and/or associated tubing may be contaminated. Exercise caution and radiological safety precautions. 2.6 In Plant Mode 1, or Mode 2 & 3 with Reactor Dome Pressure >150 psig, this test shall be performed on only one channel at a time. When one channel is being tested, remaining channels must be in Normal (Untripped) condition.

2.7 Instrument

channel under test shall not be out of service for more than six hours without entering applicable Tech Spec Action statement. When it becomes apparent this time limit will be exceeded, immediately contact Shift Supervisor. This time limit is applicable only when instrument channel under test is required to be Operable.2.8 Valves F022 and F059 will close, if open, when F031 opens.2.9 Placing MOV Test switch to TEST places overload protection in force for valves associated with that test switch. Overload protection may be left in force up to 8 hours, after which the overloads must be bypassed by placing MOV Test switch to NORMAL or declaring valves inoperable and entering applicable Action Statement. (Refer to LCO 6.8.2)J:\ADMSRVS\TECHSRVS\I\IE51R02.DOC GRAND GULF NUCLEARSTATION SURVEILLANCE PROCEDURE Title: Condensate Storage No.: 06-IC-1E51-R-0002 Revision: 103 Page: 2 Tank (RCIC) Low Level Calibration 2.10 Following alarms, trips and actions should occur from following Trips Units: TRIP UNIT ANNUNCIATOR COMPUTER POINT ACTION/IND LGT CHANNEL A "CST LVL LO" 1E51-N635A 1H13-P601-21A (B-5) E5N1N00 LOW LEVEL SUCT FROM SUPPR"RCIC SYS OOSVC" POOL VALVE 1H13-P601-21A (H-5) OPEN/NOT OPEN Open Valve F031 CHANNEL E E51N104 Close Valve F010 1E51-N635 E SUCT FROM Low Level CONDENSATE TANK Close Valve F022 OPEN/NOT OPEN Close Valve F059 1E31-N685A "RCIC DIV 1 STM E31L600A Att.I and II SPLY PRESS LO" RCIC ST LINE RTR.(See Note 1) 1H13-P601-21A (A-1) PRESS LOW/NOT LOW NOTE (1) Applies during testing in Plant Mode 3 (below 150 psig) and 4 or 5. Trip Unit 1E31-PIS-N685A must be used to facilitate testing under those conditions.

3.0 REQUIRED

MATERIALS AND TEST EQUIPMENT 3.1 Attachments I and II (as required by channel to be tested)3.2 DVM, Fluke 45 or equivalent (accuracy better than: +/- 0.040 mAdc at 0-20 mA; +/- 0.193 Vdc at 0-10 Vdc)3.3 Current Calibrator, Transmation 1040/1048 or equivalent (0-40 mAdc output)no M&TE requirements 3,4 Readout Assembly, Rosemount 710DU or equivalent (accuracy better than+/- 0.040 mAdc at 0-20 mA)3.5 Pressure gauge, Heise (0-490" H.O) or equivalent (accuracy better than+/- 1.194" H.O)3,6 Pressure Source (Air)3,7 Card extender (510DU Type) (As Needed)3.8 Test fitting for vent port of Rosemount transmitter.(As Needed)3.9 Torque Wrench, capable of 90"lbs. or equivalent.

4.0 PREREQUISITES

AND PLANT CONDITIONS 4.1 This procedure may be performed in any plant Mode except as modified by releasing organization. J:\ADMSRVS\TECHSRVS\I\IE51R02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Title: Condensate Storage No.: 06-IC-IE51-R-0002 Revision: 103 Page: 3 Tank (RCIC) Low Level Calibration

5.0 INSTRUCTIONS

For 1E51N635A and IE51N035A perform instructions on Attachment I.For 1E51N635E and IE51N035E perform instructions on Attachment II.

6.0 REFERENCES

6.1 Bechtel

Drawings: E-1185, M-1065, M-1083A 6.2 Vendor Manual 460000047 (Trip/Calibration System Model 510DU)6.3 Vendor Manual 460001972, Model 1153 Series B & D Alphaline Pressure Instruments (Rosemount 1153 Transmitter) 6.4 07-S-53-181, Bench Calibration of the Rosemount 510DU (710DU) Master and Slave Trip Units 6.5 Bechtel Setpoint Calculation E51 PMI 83/5655 Calc No. J-E51-1, Rev. 0 6.6 UFSAR Chapter 16, Appendix 16B 6.7 CR-GGN-2001-1367 and SC-1E51-LT-N035,Rev.0 6.8 ER-GG-1999-0217-000 6.9 SC-1E51-LT-N035,Rev.I J:\ADMSRVS\TECHSRVS\I\IE51R02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE 06-IC-1E51-R-0002 Revision: 103 Attachment I Page 1 of 15 Page RTYPE B6.61 XRef SURVEILLANCE PROCEDURE DATA PACKAGE COVER SHEET SAFETY RELATED Title: Condensate Storage Tank (RCIC) Low Level Calibration Channel A Technical Specifications: SR 3.3.5.2.4 and SR 3.3.5.2.5, Function 3.3.5.2-1.3; SR 3.5.3.5 1.0 IMPACT STATEMENT 1.1 Performance of this procedure opens Suppression Pool Suction Valve (F031), closes CST Suction Valve (F010) and sends Close signal to RCIC Test Return to CST Valves (F022 and F059). In Mode 1, or in Modes 2 and 3 with reactor steam dome pressure > 150 psig, a channel may be placed in an inoperable status solely for performance of required Surveillances without entering into appropriate Condition for up to 6 hours provided associated Function maintains RCIC initiation capability.

1.2 Thermal

overload protection 8 hour time limit LCO 6.8.2 is applicable.

2.0 PROCEDURE

2.1 Plant Mode is (circle one): 1 2 3 4 5 2.2 Permission to begin test /Shift Supervisor / Date 2.3 Test Start Time: /Performer's signature Date Time 3.0 TEST RESULTS 3.1 Test Completion: (Check one in each category.) Entire procedure completed C ] Partial procedure completed As Found Data Acceptable [ ] Unacceptable As Left Data Acceptable [ ] Unacceptable Tech Spec Acceptance Criteria Acceptable [ ] Unacceptable [All other steps/data Acceptable [ ] Unacceptable 3.2 TCNs in effect during performance (list): 3.3 Comments: Rev Verified by: 3.4 Test performed by Date/Time 4.0 DEFICIENCIES CR Issued # LCO Entered # WR Issued #5.0 APPROVAL Tech Spec Operability Requirements Acceptable ( ] Unacceptable [ ]Shift Supv./Manager Date Comments: CONCURRENCE I&C Superintendent Date J:\ADMSRVS\TECHSRVS\I\IE51R02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Page RTYPE B6.61 XRe f DATA SHEET I CONDENSATE STORAGE TANK (RC!C)LOW LEVEL CALIBRATION CHANNEL A SAFETY RELATED STEP REQUIRED ACTION 5.1 Obtain permission from Shift Supervisor to begin test. Shift Supervisor's signature is required on Data Package Cover Sheet.5.2 Establish communications between Control Room and technician performing test.5,3 On Calibration Unit containing Master Trip Unit 1E51-N635A on 1H13-P629, ensure Transient Current switch knob and center knob of Calibration Select/Command switch are pulled out.5,4 Ensure Calibration Unit POWER switch and both center and outer Calibration Select/Command switches are in OFF position.5,5 Install Readout Assembly into Calibration Unit.5.6 Place Calibration Unit POWER switch to ON.5.7 Verify devices listed are in state indicated. DEVICE DESIRED STATUS DESCRIPTION LOCATION VERIFICATION IE51-F031 Closed Suction From Suppr Pool 1H13-P601-21C Suction From Condensate 1E51-F010 Open Storage Tank 1H13-P601-21C IE51-F031 IE51-HS-M600 Auto Suction From Suppr Pool 1H13-P601-21C IE51-FO10 Suction From Condensate 1E51-HS-M604 Auto Storage Tank 1H13-P601-21C IE51-F031 1C61-HS-M100 Auto Suction From Suppr Pool 1H22-P150 IE51-FO1o Suction From Condensate 1C61-HS-M104 Auto Storage Tank 1H22-P150 5.8 Position center and outer knobs of Calibration Select/Command switch to Position 6, selecting Master Trip Unit 1E51-N635A.

5.9 Adjust

STABLE CURRENT knob to approximately 20 mA as observed on lower display of Readout Assembly.5.9.1 Complete Test Start Time on Data Package Cover Sheet.J:\ADM_SRVS\TECHSRVS\I\IE51R02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Page RTYPE B6.61 XRef DATA SHEUT I (Continued) CONDENSATE STORAGE TANK (RCIC)LOW LEVEL CALIBRATION CHANNEL A SAFETY RELATED STEP REQUIRED ACTION INITIALS$$5.10 Push center knob of Calibration Select/Command switch to activate Calibration Unit.5.11 Ensure CAL LED on Calibration Unit is On.5.12 Verify GROSS FAIL LED on Master Trip Unit is On.5.13 Verify: 5.13.1 Computer Point E51L617 displays OUT SVCE.5.13.2 Status Light TRIP UNIT 1 IN CAL/GR FAIL IH13-P601-21B (DS-12) comes On.5.14 In Plant Mode 3, 4, and 5, check Annunciator "RCIC DIV 1 STM SPLY PRESS LO" 1H13-P601-21A (A-l). If annunciator is in Alarm, continue with Step 5.14.1. If annunciator is Clear, proceed to Step 5.15.5.14.1 On Calibration Unit containing Master Trip Unit 1E31-N685A on 1H13-P629 position center knob to Position 3, place POWER switch to ON, push in center knob and increase Stable Current until Trip Unit Resets (TRIP LED goes Off).5.14.2 Reset RCIC DIV 1 ISOLATION SIGNAL using handswitch 1E51-HS-M628A on 1H13-P601-21B. 5.14.3 Ensure Status Light RCIC D1 ISOL INIT, 1H13-P601-21B (DS6), is Off.5.15 Perform following: 5.15.1 Have Operations place RCIC DIV 1 MOV TEST handswitch, 1E51-HS-M641, in TEST position. Opera'5.15.2 Verify Status Light RCIC DI MOV IN TEST STATUS 1H13-P601-21B (DS8) comes On.5.16 Master Trip Unit Calibration (1E51-N635A on 1H13-P629) 5.16.1 Adjust Stable Current 20.00 + 0.01 mA.tions: J:\ADMSRVS\TECHSRVS\I\IES1R02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Page , RTYPE B6.61 XRef DATA SHENT I (Continued) CONDENSATE STORAGE TANK (RCIC)LOW LEVEL CALIBRATION CHANNEL A SAFETY RELATED STEP REQUIRED ACTION 5.16.2 Record As Found 100% Master Trip Unit meter indication. INITIALS 5.16.3 5.16.4 MASTER TRIP UNIT ANALOG METER 1E51-N635A DESIRED MIN ASFOUND MAX FINAL Ft. Ft. Ft. Ft. Ft.40 39 NOP NOP -Not on Peg Adjust Stable Current to 12.00 + 0.01 mA and record As Found 50% Master Trip Unit meter indication. MASTER TRIP UNIT ANALOG METER 1E51-N635A DESIRED MIN AS FOUND MAX FINAL Ft. Ft. Ft. Ft. Ft.20 19 21 Decrease Stable Current until Master Trip Unit Trips (TRIP LED On). Record "As Found" trip value from upper display of Readout Assembly.LOW LEVEL TRIP CALIBRATION DATA (TRIP) 1E51-N635A DESIRED MIN AS FOUND MAX FINAL mA mA mA mA mA 5.60 5.56 5.64 (62.0" H 2 0) (59.6" H 2 0) (2) (64.4" H 2 0)(2) Transfer value to corresponding location in Step 5.24.5.16.5 Verify:$ a. Annunciator, "CST LVL LO", on 1H13-P601-21A (B-5), Alarmed.b. Computer Point E51NI00 displays OPEN.c. Computer Point E51N104 displays NOT OPEN.$ d. Valve 1E51-F031 Opened.J _e. Valve IE51-FO10 Closed.J:\ADMSRVS\TECHSRVS\I\IE5lRO2.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE 06-IC-IE51-R-0002 Revision: 103 Attachment I Page 5 of 15 Page RTYPE B6.61 XRef DATA SHEET I (Continued) CONDENSATE STORAGE TANK (RCIC)LOW LEVEL CALIBRATION CHANNEL A SAFETY RELATED STEP REQUIRED ACTION 5.16.6 Decrease Stable Current to 4.00 + 0.01 mA and record As Found 0% Master Trip Unit meter indication. MASTER TRIP UNIT ANALOG METER 1E51-N635A DESIRED MIN AS FOUND MAX FINAL Ft. Ft. Ft. Ft. Ft.0 NOP I NOP -Not on Peg 5.16.7 Press RESET pushbutton on Readout Assembly.5.16.8 Increase Stable Current until Master Trip Unit Resets (TRIP LED OFF), then record "As Found" reset value from upper display of Readout Assembly.LOW LEVEL TRIP CALIBRATION DATA (RESET) IE51-N635A DESIRED MIN AS FOUND MAX FINAL mA mA mA mA mA 5.68 5.64 5.72 5.16.9 Pull out center knob of Select/Command switch.5.16.10 Connect Current Calibrator (mA OUT adjust for 0 mA) and DVM positive leads (+) to J1 on Meter Trip Unit and negative leads (-) to J2 on Calibration Unit.J:\ADMSRVS\TECHSRVS\I\IE51R02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Page RTYPE B6.61 XRe f DATA SHEET I (Continued) CONDENSATE STORAGE TANK (RCIC)LOW LEVEL CALIBRATION CHANNEL A SAFETY RELATED STEP REQUIRED ACTION INITIALS NOTE If on, Reset GROSS FAIL LED. If LED does not go Off, adjust Current Calibrator until GROSS FAIL LED can be Reset.5.16.11 Slowly increase milliamp output of Current Calibrator until GROSS FAIL LED on Master Trip Unit comes On. Record As Found High Gross Fail trip voltage from DVM.MASTER TRIP UNIT GROSS FAIL CALIBRATION DATA 1E51-N635A DESIRED MIN AS FOUND MAX FINAL Vdc Vdc Vdc Vdc Vdc 7.50 6.00 9.00$ a. Verify GROSS FAIL LED on Master Trip Unit comes On.5.16.12 Reconnect Current Calibrator negative lead (-) to J1 on Master Trip Unit and positive lead (+) to J2 on Calibration Unit (mA OUT adjusted for 0 mA). (Do not disconnect DVM.)$ 5.16.13 Reset GROSS FAIL LED on Master Trip Unit.5.16.14 Slowly increase milliamp output of Current Calibrator until GROSS FAIL LED on Master Trip Unit comes On. Record As Found Low Gross Fail trip voltage from DVM.MASTER TRIP UNIT GROSS FAIL CALIBRATION DATA 1E51-N635A DESIRED MIN AS FOUND MAX FINAL Vdc Vdc Vdc Vdc Vdc 0.694 0.500 0.887$a. Verify GROSS FAIL LED on Master Trip Unit comes On.Disconnect Current Calibrator and DVM from Master Trip Unit and Cal Unit. Reset GROSS FAIL LED on Master Trip Unit.$ 5.16.15 J:\ADMSRVS\TECHSRVS\I\IE51R02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Page RTYPE B6.61 XRef DATA SHEXT I (Continued) CONDENSATE STORAGE TANK (RCIC)LOW LEVEL CALIBRATION CHANNEL A SAFETY RELATED STEP REQUIRED ACTION INITIALS 5.16.16 If Gross Failure adjustment is required, continue with Step 5.16.16.a. If not, record them as "Final" values and proceed to Step 5.16.17.a. Install card extender between Trip Unit to be adjusted and Card File.b. Connect DVM, negative lead (-) to J2 on Calibration Unit and positive lead (+) to J1 on Master Trip Unit.c. For Low Gross Fail adjustment, connect Current Calibrator positive (+) to J2 on Calibration Unit and negative (-) to J1 on Master Trip Unit. For High Gross Fail adjustment, connect Current Calibrator positive (+) to J1 on Master Trip Unit and negative (-) to J2 on Calibration Unit.d. Increase milliamp output of Current Calibrator until DVM, reads Desired value for Gross Failure Trip being adjusted.e. If necessary, adjust applicable CURRENT TRIP pot on circuit board CCW until GROSS FAIL LED can be reset with RESET pushbutton.

f. Very slowly turn pot CW until GROSS FAIL LED just comes On.g. Lower Current Calibrator output until GROSS FAIL LED can be reset with RESET pushbutton, then very slowly increase output until LED just comes On.h. If value obtained requires no further adjustment, record reading as "Final" and proceed to Step 5.16.16i; otherwise, repeat Step 5.16.16c through 5.16.16h until unit requires no further adjustment.
i. Repeat Steps 5.16.16c through 5.16.16h for other Gross Fail if adjustment is required.j. Disconnect Current Calibrator and DVM from Master Trip Unit and Cal Unit.5.16.17 Push in center knob of Select/command switch.J:\ADMSRVS\TECHSRVS\I\IESIR02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Page RTYPE B6.61 XRef DATA I (Continued)

CONDENSATE STORAGE TANK (RCIC)LOW LEVEL CALIBRATION CHANNEL A SAFETY RELATED STEP REQUIRED ACTION INITIALS 5.16.18 If Trip point adjustment is required, continue with Step 5.16.18a. If not, record as "Final" and proceed to Step 5.16.19.a. Adjust Stable Current to Desired value and adjust Trip Point adjustment as required.b. Recheck Reset Value. If Reset requires no adjustment, proceed to Step 5.16.18e. If Reset required adjustment, proceed to Step 5.16.18c.c. Install card extender between Trip Unit and Card File, if required.d. Adjust Stable Current to Desired Reset value and adjust RESET DIFFERENTIAL pot on circuit board as required.e. Recheck Trip and Reset values. If both Trip and Reset require no further adjustment, record them as "Final" values and proceed to Step 5.16.19. If not, repeat Step 5.16.18a through 5.16.18e until unit requires no further adjustment. 5.16.19 If Master Trip Unit meter adjustment is required, continue with Step 5.16.19a. If not, record them as "Final" values and proceed to Step 5.16.20.a. Install card extender between Master Trip Unit and Card File, if required.b. Adjust meter ZERO at back of meter, then recheck 0,50, and 100 percent indications. Repeat as required until unit requires no further adjustment.

c. Record "Final" indications.

5.16.20 Remove Card extender from Master Trip Unit 1E51-N635A and reinstall Trip Unit in Card File, if required.5.16.21 Adjust Stable Current to approximately 20.00 + 0.01 mA.$ 5.16.22 Verify Annunciator, "CST LVL LO", 1H13-P601-21A (B-5), Clears.J:\ADMSRVS\TECHSRVS\I\IE51R02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Page RTYPE B6.61 XRef DATA SHET I (Continued) CONDENSATE STORAGE TANK (RCIC)LOW LEVEL CALIBRATION CHANNEL A SAFETY RELATED REQUIRED ACTION STEP INITIALS 5.16.23 Complete applicable Hardware Restoration Section for 1E31-N685A.(N/A Hardware Restoration Section if Step 5.14 was not completed.) HARDWARE RESTORATION 5.17 DESCRIPTION TEST NORMAL FINAL PERFORMER VERIFIER Cal Select Command switch center knob POS 3 OFF Cal Select Command switch outer knob POS 3 OFF Cal Unit POWER switch ON OFF Transmitter Calibration 1E51-LT-N035A (119'Aux, Area 7)NOTE Refer to Return to Service Verification Record for instrument valve identification. WARNING Any water drained from the transmitter and/or associated tubing may be contaminated. Exercise caution and radiological safety precautions. 5.17.1 Perform following:

a. Remove valve seals as required.b. Close instrument Isolation Valve F01 to 1E51-LT-N035A 5.17.2 Slowly loosen HP side vent plug on top of transmitter.

5.17.3 Perform one of the following:

a. Install test fitting in HP vent port on top of transmitter.

OR b. Open Test Valve F02 and ensure transmitter is vented and drained of all water.J:\ADMSRVS\TECHSRVS\I\IE51R02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Page RTYPE B6.61 XRef DATA SHEET I (Continued) CONDENSATE STORAGE TANK (RCIC)LOW LEVEL CALIBRATION CHANNEL A SAFETY RELATED STEP REQUIRED ACTION 5.17.4 Perform following:

a. Connect test gauge and pressure source to either test fitting in HP vent port or HP manifold test connection.
b. Connect DVM (mAdc) to test connections on transmitter.

5.17.5 Apply inputs to Transmitter, as specified, and record "As Found" values.Step 5.17.5, 6, 12 1E51-N035A TRANSMITTER CALIBRATION DATA (119'Aux, Area 7)INPUT OUTPUT DESIRED MIN AS FOUND MAX FINAL"H20 mA mA mA mA mA 15 4.03 3.99 4.07 135 8.05 8.01 8.09 250 11.90 11.86 11.94 370 15.92 15.88 15.96 490 19.94 19.90 19.98 370 15.92 15.88 15.96 250 11.90 11.86 11.94 135 8.05 8.01 8.09 62 5.60 5.56 (1) 5.64 15 4.03 3.99 1 4.07 (1): Transfer value to corresponding location in Step 5.24.5.17.6 If "As Found" values require no adjustment, record them as"Final" values and proceed to Step 5.18; otherwise, continue with Step 5.17.7.5.17.7 Apply 0% pressure, as specified, and adjust ZERO until output is as specified. 5.17.8 Apply 100% pressure, as specified, and adjust SPAN until output is as specified. J:\ADMSRVS\TECHSRVS\I\IE51R02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Page RTYPE B6.61 XRef DATA SHUZT I (Continued) CONDENSATE STORAGE TANK (RCIC)LOW LEVEL CALIBRATION CHANNEL A SAFETY RELATED STEP REQUIRED ACTION 5.17.9 Repeat.Steps 5.17.7 and 5.17.8 until unit requires no further adjustment. 5.17.10 Apply 50% pressure, as specified, and ensure output is within specified tolerance. If output requires adjustment, adjust LINEARITY adjustment until no further adjustment is required.5.17.11 Repeat Steps 5.17.7 through 5.17.11 until Transmitter requires no further adjustment. 5.17.12 Reapply inputs to Transmitter, as specified, and record them as "Final" values.5.18 Pull out center knob of Calibration Select/Command switch and verify CAL LED is Off.$ 5.19 Press Master Trip Unit Gross Fail RESET pushbutton and verify Gross Fail LED is Off.5.20 Place Cal Select/Command switch knobs to OFF position.5.21 Condensate Storage Tank (RCIC) Low Level Cal Functional Test INITIALS NOTE Various trips and/or alarms other than those stated below will occur during performance of this section. (See Section 2.0.)They will not require verification. 5.21.1 Establish communications between Control Room and transmitter. 5.21.2 Increase pressure to high side of Transmitter until it is near Reset Point. Very slowly continue to increase pressure until TRIP LED on Master Trip Unit goes Off.J:\ADMSRVS\TECHSRVS\I\IE51R02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Page RTYPE B6.61 XRef DATA SHEET I (Continued) CONDENSATE STORAGE TANK (RCIC)LOW LEVEL CALIBRATION CHANNEL A SAFETY RELATED STEP REQUIRED ACTION$ 5.21.3 Record reset value as indicated on pressure gauge.$5.21.4$ 5.21.5 TRIP FUNCTIONAL TEST DATA (RESET) IES1-N635A TEST GAUGE READING PRESS TO DESIRED MIN TRIP MAX XMITTER SIDE "H 2 0 "H 2 0 "H 2 0 "H 2 0 High 64.4 N/A NA Bleed pressure down until it is near Trip Point. Very slowly continue to decrease pressure until TRIP LED on Master Unit comes On.Record trip value as indicated on pressure gauge.TRIP FUNCTIONAL TEST DATA (TRIP) 1E51-N635A TEST GAUGE READING PRESS TO DESIRED MIN TRIP MAX XMITTER SIDE OH20 "H20 "H20 DH20 High 62.0 59.6 64.4 5.21.6 If any of above values are out of tolerance, contact your immediate supervisor. 5.22 Restoration 5.22.1 Perform one of the following:

a. Vent pressure from HP section of transmitter and remove test gauge and pressure source. Install vent plug in HP vent port on top of transmitter.

OR b. Close Test Valve F02 and Vent pressure from HP section of transmitter and remove test gauge and pressure source.5.22.2 Very slowly open Instrument HP Isolation Valve F01 to admit process pressure to transmitter. J:\ADMSRVS\TECHSRVS\I\IE51R02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Page RTYPE B6.61 XRef DATA SHEET I (Continued) CONDENSATE STORAGE TANK (RCIC)LOW LEVEL CALIBRATION CHANNEL A SAFETY RELATED REQUIRED ACTION STEP INITIALS 5.22.3 Perform following:

a. Vent transmitter as necessary to ensure sensing leg is filled.b. Torque vent plug on transmitter to 90 in/lbs.c. Remove DVM.5.22.4 Complete Return to Service Verification Record.INSTRUMENT NO.: IE51-LT-N035A LOCATION:

119'Aux.,Area 7 I H I I L I I I Atmosphere F F Process I I F02 TEST RETURN TO SERVICE VERIFICATION RECORD VALVE VALVE POSITION INITIALS DESCRIPTION TEST NORMAL FINAL PERFORMER VERIFIER HP ISOL VALVE F01 CLOSED OPEN HP TEST VALVE F02 OPEN CLOSED 5.22.5 Check all valves and fittings for leaks.5.22.6 Replace valve seals on transmitter valves as required.5.22.7 Have Operations Close IE51-F031 and Open IE51-F010. VALVE RESTORATION INITIALS VALVE TEST NORMAL FINAL PERFORMER VERIFIER IE51-F031 OPEN CLOSED IE51-FO10 CLOSED OPEN J:\ADMSRVS\TECHSRVS\I\IE51R02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Page RTYPE B6.61 XRef DATA SHEET I (Continued) CONDENSATE STORAGE TANK (RCIC)LOW LEVEL CALIBRATION CHANNEL A SAFETY RELATED REQUIRED ACTION STEP INITIALS 5.22.8 Have Operations place RCIC DIV I MOV TEST switch to NORM.Operations: Verifier: 5.22.9 Complete Hardware Restoration for IE51-N635A. HARDWARE RESTORATION DESCRIPTION TEST NORMAL FINAL PERFORMER VERIFIER Cal Select Command switch center knob POS 6 OFF Cal Select Command switch outer knob POS 6 OFF Cal Unit POWER switch ON OFF 5.22.10 5.22.11 Remove Digital Readout Assembly.Verify:$ a. Status Light TRIP UNIT I IN CAL/GR FAIL IHI3-P601-21B (DS-12) is Off.b. Computer Point E51L617 displays NORMAL.$ c. Indicating Light RCIC Dl MOV IN TEST STATUS 1H13-P601-21B (DS8) is Off.5.22.12 Verify reading 1E51-N635A is consistent with existing plant conditions. 5.23 Record test equipment used for this test. This step may be performed out of sequence if desired.TEST EOUIPMENT LOG TEST EQUIPMENT I M&TE NO. E CAL DUE DATE J:\ADMSRVS\TECHSRVS\I\IE51R02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Page RTYPE B6.61 XRef DATA SHENT I (Continued).CONDENSATE STORAGE TANK (RCIC)LOW LEVEL CALIBRATION CHANNEL A SAFETY RELATED STEP REQUIRED ACTION 5.24 Complete As Found Loop Error Calculations. CAUTION: Recheck math, especially negative numbers.LOW LEVEL TRIP: 1E51-N635A XMTR mA TRIP UNIT mA COMBINED Desired: 5.60 (2) As Found: mA (1) As Found: Desired: -5.60 5.60 Desired+ ( = ( ) Total Loop Error (add)As Found Loop Setpoint: mA* (Transfer to Step 5.25)5.25 Complete Tech Spec As Found Compliance Verification. LOW LEVEL TRIP: IE51-N635A TECH SPEC: > 3.7 ft. (5.48 mA)Is following true? * > 5.48 mA (*Insert As Found Loop Setpoint)Initial: YES (Complies w/Tech Spec limit)NO (Does not comply -Notify Shift Supervisor) 5.26 Notify Shift Supervisor test is complete. Shift Supervisor's signature is required on Data Package Cover Sheet.J:\ADM_SRVS\TECHSRVS\I\!E51R02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE 06-IC-IE51-R-0002 Revision: 103 Attachment II Page 1 of 15 Page RTYPE B6.61 XRef SURVEILLANCE PROCEDURE DATA PACKAGE COVER SHEET SAFETY RELATED Title: Condensate Storage Tank (RCIC) Low Level Calibration Channel E Technical Specifications: SR 3.3.5.2.4 and SR 3.3.5.2.5, Function 3.3.5.2-1.3; SR-3.5.3.5

1.0 IMPACT

STATEMENT 1.1 Performance of this procedure opens Suppression Pool Suction Valve (F031), closes CST Suction Valve (FO10) and sends Close signal to RCIC Test Return to CST Valves (F022 and F059). In Mode 1, or in Modes 2 and 3 with reactor steam dome pressure > 150 psig, a channel may be placed in an inoperable status solely for performance of required Surveillances without entering into appropriate Condition for up to 6 hours provided associated Function maintains RCIC initiation capability.

1.2 Thermal

overload protection 8 hour time limit LCO 6.8.2 is applicable.

2.0 PROCEDURE

2.1 Plant Mode is (circle one): 1 2 3 4 5 2.2 Permission to begin test /Shift Supervisor / Date 2.3 Test Start Time: / /Performer's signature Date Time 3.0 TEST RESULTS 3.1 Test Completion: (Check one in each category.) Entire procedure completed [ ] Partial procedure completed E As Found Data Acceptable [ ] Unacceptable As Left Data Acceptable [ ] Unacceptable Tech Spec Acceptance Criteria Acceptable [ I Unacceptable [All other steps/data Acceptable [ ] Unacceptable 3.2 TCNs in effect during performance (list): 3.3 Comments: Rev Verified by: 3.4 Test performed by Date/Time 4.0 DEFICIENCIES CR Issued # LCO Entered # WR Issued #5.0 APPROVAL Tech Spec Operability Requirements Acceptable [ ] Unacceptable Shift Supv./Manager Date Comments: CONCURRENCE I&C Superintendent Date J:\ADMSRVS\TECHSRVS\I\IE51R02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Page RTYPE B6.61 XRef_DATA SHEUT I CONDENSATE STORAGE TANK (RCIC)LOW LEVEL CALIBRATION CHANNEL E SAFETY RELATED STEP REQUIRED ACTION 5.1 Obtain permission from Shift Supervisor to begin test. Shift Supervisor's signature is required on Data Package Cover Sheet.5.2 Establish communications between Control Room and technician performing test.5.3 On Calibration Unit containing Master Trip Unit 1E51-N635E on 1H13-P629, ensure Transient Current switch knob and center knob of Calibration Select/Command switch are pulled out.5.4 Ensure Calibration Unit POWER switch and both center and outer Calibration Select/Command switches are in OFF position.5.5 Install Readout Assembly into Calibration Unit.5.6 Place Calibration Unit POWER switch to ON.5.7 Verify devices listed are in state indicated. DEVICE DESIRED STATUS DESCRIPTION LOCATION VERIFICATION 1E51-F031 Closed Suction From Suppr Pool 1H13-P601-21C Suction From Condensate IE51-FO10 Open Storage Tank 1H13-P601-21C 1E51-F031 1E51-HS-M600 Auto Suction From Suppr Pool 1H13-P601-21C 1E51-F010 Suction From Condensate 1E51-HS-M604 Auto Storage Tank 1H13-P601-21C 1E51-F031 1C61-HS-M100 Auto Suction From Suppr Pool IH22-PI50 1E51-F010 Suction From Condensate 1C61-HS-M104 Auto Storage Tank 1H22-P150 5.8 Position center and outer knobs of Calibration Select/Command switch to Position 7, selecting Master Trip Unit 1E51-N635E.

5.9 Adjust

STABLE CURRENT knob to approximately 20 mA as observed on lower display of Readout Assembly.5.9.1 Complete Test Start Time on Data Package Cover Sheet.J:\ADMSRVS\TECHSRVS\I\IES5R02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Page RTYPE B6.61 XRef DATA SHEET I (Continued) CONDENSATE STORAGE TANK (RCIC)LOW LEVEL CALIBRATION CHANNEL E SAFETY RELATED STEP REQUIRED ACTION INITIALS$$5.10 Push center knob of Calibration Select/Command switch to activate Calibration Unit.5.11 Ensure CAL LED on Calibration Unit is On.5.12 Verify GROSS FAIL LED on Master Trip Unit is On.5.13 Verify: 5.13.1 Computer Point E51L617 displays OUT SVCE.5.13.2 Status Light TRIP UNIT 1 IN CAL/GR FAIL 1H13-P601-21B (DS-12) comes On.5.14 In Plant Mode 3, 4, and 5, check Annunciator "RCIC DIV 1 STM SPLY PRESS LO" 1H13-P601-21A (A-i). If annunciator is in Alarm, continue with Step 5.14.1. If annunciator is Clear, proceed to Step 5.15.5.14.1 On Calibration Unit containing Master Trip Unit 1E31-N685A on 1H13-P629 position center knob to Position 3, place POWER switch to ON, push in center knob and increase Stable Current until Trip Unit Resets (TRIP LED goes Off).5.14.2 Reset RCIC DIV 1 ISOLATION SIGNAL using handswitch 1E51-HS-M628A on IH13-P601-21B. 5.14.3 Ensure Status Light RCIC D1 ISOL INIT, 1H13-P601-21B (DS6), is Off.5.15 Perform following: 5.15.1 Have Operations place RCIC DIV 1 MOV TEST handswitch, 1E51-HS-M641, in TEST position. Opera'5.15.2 Verify Status Light RCIC D1 MOV IN TEST STATUS 1H13-P601-21B (DS8) comes On.5.16 Master Trip Unit Calibration (1E51-N635E on 1H13-P629) 5.16.1 Adjust Stable Current 20.00 + 0.01 mA.tions: J:\ADM_SRVS\TECHSRVS\I\IES5R02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Page RTYPE B6.61 XRef DATA SHEET I (Continued) CONDENSATE STORAGE TANK (RCIC)LOW LEVEL CALIBRATION CHANNEL E SAFETY RELATED STEP REQUIRED ACTION INITIALS 5.16.2 Record As Found 100% Master Trip Unit meter indication. MASTER TRIP UNIT ANALOG METER 1E51-N635E DESIRED MIN AS FOUND MAX FINAL Ft. Ft. Ft. Ft. Ft.40 39 NOP NOP -Not on Peg 5.16.3 Adjust Stable Current to 12.00 + 0.01 mA and record As Found 50% Master Trip Unit meter indication. 5.16.4 Decrease Stable Current until Master Trip Unit Trips (TRIP LED On). Record "As Found" trip value from upper display of Readout Assembly.Transfer value to 5.16.5 Verify:$ a. Annunciator, "CST LVL LO", on 1H13-P601-21A (B-5), Alarmed.b. Computer Point E51NI00 displays OPEN.c. Computer Point E51N104 displays NOT OPEN.$ d. Valve 1E51-F031 Opened.J _ e. Valve 1E51-FR02 Closed.J:\ADMSRVS\TECHSRVS\I\IE51R02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Page RTYPE B6.61 XRef DATA SHEET I (Continued) CONDENSATE STORAGE TANK (RCIC)LOW LEVEL CALIBRATION CHANNEL E SAFETY RELATED STEP REQUIRED ACTION 5.16.6 Decrease Stable Current to 4.00 + 0.01 mA and record As Found 0% Master Trip Unit meter indication. 5.16.7 Press RESET pushbutton on Readout Assembly.5.16.8 Increase Stable Current until Master Trip Unit Resets (TRIP LED OFF), then record "As Found" reset value from upper display of Readout Assembly.LOW LEVEL TRIP CALIBRATION DATA (RESET) IE51-N635E DESIRED MIN AS FOUND MAX FINAL mA mA mA mA mA 5.68 5.64 5.72 5.16.9 Pull out center knob of Select/Command switch.5.16.10 Connect Current Calibrator (mA OUT adjust for 0 mA) and DVM positive leads (+) to J1 on Meter Trip Unit and negative leads (-) to J2 on Calibration Unit.J:\ADMSRVS\TECHSRVS\I\IE51R02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Page RTYPE B6.61 XRef DATA SHEET I (Continued) CONDENSATE STORAGE TANK (RCIC)LOW LEVEL CALIBRATION CHANNEL E SAFETY RELATED REQUIRED ACTION STEP INITIALS NOTE If on, Reset GROSS FAIL LED. If LED does not go Off, adjust Current Calibrator until GROSS FAIL LED can be Reset.5.16.11 Slowly increase milliamp output of Current Calibrator until GROSS FAIL LED on Master Trip Unit comes On. Record As Found High Gross Fail trip voltage from DVM.MASTER TRIP UNIT GROSS FAIL CALIBRATION DATA 1E51-N635E DESIRED MIN AS FOUND MAX FINAL Vdc Vdc Vdc Vdc Vdc 7.50 6.00 9.00$ a. Verify GROSS FAIL LED on Master Trip Unit comes On.5.16.12 Reconnect Current Calibrator negative lead (-) to J1 on Master Trip Unit and positive lead (+) to J2 on Calibration Unit (mA OUT adjusted for 0 mA). (Do not disconnect DVM.)$ 5.16.13 Reset GROSS FAIL LED on Master Trip Unit.5.16.14 Slowly increase milliamp output of Current Calibrator until GROSS FAIL LED on Master Trip Unit comes On. Record As Found Low Gross Fail trip voltage from DVM.MASTER TRIP UNIT GROSS FAIL CALIBRATION DATA lE51-N635E DESIRED MIN AS FOUND MAX FINAL Vdc Vdc Vdc Vdc Vdc 0.694 0.500 0.887$a. Verify GROSS FAIL LED on Master Trip Unit comes On.Disconnect Current Calibrator and DVM from Master Trip Unit and Cal Unit. Reset GROSS FAIL LED on Master Trip Unit.$ 5.16.15 J:\ADMSRVS\TECHSRVS\I\IE51R02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Page RTYPE B6.61 XRef DATA SHEET I (Continued) CONDENSATE STORAGE TANK (RCIC)LOW LEVEL CALIBRATION CHANNEL E SAFETY RELATED STEP REQUIRED ACTION INITIALS 5.16.16 If Gross Failure adjustment is required, continue with Step 5.16.16.a. If not, record them as "Final" values and proceed to Step 5.16.17.a. Install card extender between Trip Unit to be adjusted and Card File.b. Connect DVM, negative lead (-) to J2 on Calibration Unit and positive lead (+) to Jl on Master Trip Unit.c. For Low Gross Fail adjustment, connect Current Calibrator positive (+) to J2 on Calibration Unit and negative (-) to J1 on Master Trip Unit. For High Gross Fail adjustment, connect Current Calibrator positive (+) to J1 on Master Trip Unit and negative (-) to J2 on Calibration Unit.d. Increase milliamp output of Current Calibrator until DVM reads Desired value for Gross Failure Trip being adjusted.e. If necessary, adjust applicable CURRENT TRIP pot on circuit board CCW until GROSS FAIL LED can be reset with RESET pushbutton.

f. Very slowly turn pot CW until GROSS FAIL LED just comes On.g. Lower Current Calibrator output until GROSS FAIL LED can be reset with RESET pushbutton, then very slowly increase output until LED just comes On.h. If value obtained requires no further adjustment, record reading as "Final" and proceed to Step 5.16.16i; otherwise, repeat Step 5.16.16c through 5.16.16h until unit requires no further adjustment.
i. Repeat Steps 5.16.16c through 5.16.16h for other Gross Fail if adjustment is required.J. Disconnect Current Calibrator and DVM from Master Trip Unit and Cal Unit.5.16.17 Push in center knob of Select/command switch.J:\ADMSRVS\TECHSRVS\I\IE51R02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE 06-IC-1E51-R-0002 Revision:

103 Attachment II Page 8 of 15 Page RTYPE B6.61 XRef DATA SHEET I (Continued) CONDENSATE STORAGE TANK (RCIC)LOW LEVEL CALIBRATION CHANNEL E SAFETY RELATED STEP REQUIRED ACTION INITIALS 5.16.18 If Trip point adjustment is required, continue with Step 5.16.18a. If not, record as "Final" and proceed to Step 5.16.19.a. Adjust Stable Current to Desired value and adjust Trip Point adjustment as required.b. Recheck Reset Value. If Reset requires no adjustment, proceed to Step 5.16.18e. If Reset required adjustment, proceed to Step 5.16.18c.c. Install card extender between Trip Unit and Card File, if required.d. Adjust Stable Current to Desired Reset value and adjust RESET DIFFERENTIAL pot on circuit board as required.e. Recheck Trip and Reset values. If both Trip and Reset require no further adjustment, record them as "Final" values and proceed to Step 5.16.19. If not, repeat Step 5.16.18a through 5.16.18e until unit requires no further adjustment. 5.16.19 If Master Trip Unit meter adjustment is required, continue with Step 5.16.19a. If not, record them as "Final" values and proceed to Step 5.16.20.a. Install card extender between Master Trip Unit and Card File, if required.b. Adjust meter ZERO at back of meter, then recheck 0,50, and 100 percent indications. Repeat as required until unit requires no further adjustment.

c. Record "Final" indications.

5.16.20 Remove Card extender from Master Trip Unit 1E51-N635E and reinstall Trip Unit in Card File, if required.5.16.21 Adjust Stable Current to approximately 20.00 + 0.01 mA.$ 5.16.22 Verify Annunciator, "CST LVL LO", 1H13-P601-21A (B-5), Clears.J:\ADMSRVS\TECHSRVS\I\IE51R02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Page RTYPE B6.61 XRef DATA SHEET I (Continued) CONDENSATE STORAGE TANK (RCIC)LOW LEVEL CALIBRATION CHANNEL E SAFETY RELATED STEP REQUIRED ACTION INITIALS 5.16.23 Complete applicable Hardware Restoration Section for 1E31-N685A.(N/A Hardware Restoration Section if Step 5.14 was not completed.) HARDWARE RESTORATION DESCRIPTION TEST NORMAL FINAL PERFORMER VERIFIER Cal Select Command switch center knob POS 3 OFF Cal Select Command switch outer knob POS 3 OFF Cal Unit POWER switch ON OFF 5.17 Transmitter Calibration 1E51-LT-N035E (119'Aux, Area 7)5.17.1 Perform following:

a. Remove valve seals as required.b. Close instrument Isolation Valve F01 to 1E51-LT-N035E 5.17.2 Slowly loosen HP side vent plug on top of transmitter.

5.17.3 Perform one of the following:

a. Install test fitting in HP vent port on top of transmitter.

OR b. Open Test Valve F02 and ensure transmitter is vented and drained of all water.J:\ADMSRVS\TECHSRVS\I\IE51R02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Page RTYPE B6.61 XRef DATA SHEET I (Continued) STEP 5.17.4 5.17.5 5.17.6 5.17.7 5.17.8 CONDENSATE STORAGE TANK (RCIC)LOW LEVEL CALIBRATION CHANNEL E SAFETY RELATED REQUIRED ACTION Perform following:

a. Connect test gauge and pressure source to either test fitting in HP vent port or HP manifold test connection.
b. Connect DVM (mAdc) to test connections on transmitter.

Apply inputs to Transmitter, as specified, and record "As Found" values.1E51-N035E TRANSMITTER CALIBRATION DATA (119'Aux, Area 7)INPUT OUTPUT DESIRED MIN AS FOUND MAX FINAL"H 2 0 mA mA mA mA mA 15 4.02 3.98 4.06 135 8.04 8.00 8.08 250 11.90 11.86 11.94 370 15.92 15.88 15.96 490 19.94 19.90 19.98 370 15.92 15.88 15.96 250 11.90 11.86 11.94 135 8.04 8.00 8.08 62 5.60 5.56 (1) 5.64 15 4.02 3.98 4.06 (1): Transfer value to corresponding location in Step 5.24.If "As Found" values require no adjustment, record them as"Final" values and proceed to Step 5.18; otherwise, continue with Step 5.17.7.Apply 0% pressure, as specified, and adjust ZERO until output is as specified. Apply 100% pressure, as specified, and adjust SPAN until output is as specified. J:\ADMSRVS\TECHSRVS\I\IE51R02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Page RTYPE B6.61 XRef DATA SHEET I (Continued) CONDENSATE STORAGE TANK (RCIC)LOW LEVEL CALIBRATION CHANNEL E SAFETY RELATED STEP REQUIRED ACTION INITIALS 5.17.9 Repeat Steps 5.17.7 and 5.17.8 until unit requires no further adjustment. 5.17.10 Apply 50% pressure, as specified, and ensure output is within specified tolerance. If output requires adjustment, adjust LINEARITY adjustment until no further adjustment is required.5.17.11 Repeat Steps 5.17.7 through 5.17.11 until Transmitter requires no further adjustment. 5.17.12 Reapply inputs to Transmitter, as specified, and record them as "Final" values.5.18 Pull out center knob of Calibration Select/Command switch and verify CAL LED is Off.$ 5.19 Press Master Trip Unit Gross Fail RESET pushbutton and verify Gross Fail LED is Off.5.20 Place Cal Select/Command switch knobs to OFF position.5.21 Condensate Storage Tank (RCIC) Low Level Cal Functional Test NOTE Various trips and/or alarms other than those stated below will occur during performance of this section. (See Section 2.0.)They will not require verification. 5.21.1 Establish communications between Control Room and transmitter. 5.21.2 Increase pressure to high side of Transmitter until it is near Reset Point. Very slowly continue to increase pressure until TRIP LED on Master Trip Unit goes Off.J:\ADMSRVS\TECHSRVS\I\IE51R02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Page RTYPE B6.61 XRef DATA SHEET I (Continued) CONDENSATE STORAGE TANK (RCIC)LOW LEVEL CALIBRATION CHANNEL E SAFETY RELATED STEP REQUIRED ACTION$ 5.21.3 Record reset value as indicated on pressure gauge.5.21.4$ 5.21.5 TRIP FUNCTIONAL TEST DATA 1E51-N635E TEST GAUGE READING PRESS TO DESIRED MIN TRIP MAX XMITTER SIDE "H 2 0 "Hi 2 0 "H 2 0 "H20 High 64.4 N/A N/A Bleed pressure down until it is near Trip Point. Very slowly continue to decrease pressure until TRIP LED on Master Unit comes On.Record trip value as indicated on pressure gauge.TRIP FUNCTIONAL TEST DATA 1E51-N635E TEST GAUGE READING PRESS TO DESIRED MIN TRIP MAX XMITTER SIDE "H 2 0 "H 2 0 "H 2 0 "H20 High 62.0 59.6 64.4 5.21.6 If any of above values are out of tolerance, contact your immediate supervisor. 5.22 Restoration 5.22.1 Perform one of the following:

a. Vent pressure from HP section of transmitter and remove test gauge and pressure source. Install vent plug in HP vent port on top of transmitter.

OR b. Close Test Valve F02 and Vent pressure from HP section of transmitter and remove test gauge and pressure source.5.22.2 Very slowly open Instrument HP Isolation Valve F01 to admit process pressure to transmitter. J:\ADMSRVS\TECHSRVS\I\IE51R02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Page RTYPE B6.61 XRef DATA SHEET I (Continued) CONDENSATE STORAGE TANK (RCIC)LOW LEVEL CALIBRATION CHANNEL E SAFETY RELATED REQUIRED ACTION STEP INITIALS 5.22.3 Perform following:

a. Vent transmitter as necessary to ensure sensing leg is filled.b. Torque vent plug on transmitter to 90 in/lbs.c. Remove DVM.5.22.4 Complete Return to Service Verification Record.INSTRUMENT NO.: 1E51-LT-N035E LOCATION:

119'Aux.,Area 7 I H I i I I L I I i I J I I IA X F 01 ITI F02 1DPrTDN MA QWDUTTP XrVTWTI'4TnM IDWfAnf I tmosphere Process.VALVE VALVE POSITION INITIALS DESCRIPTION TEST NORMAL FINAL PERFORMER VERIFIER HP ISOL VALVE F01 CLOSED OPEN HP TEST VALVE F02 OPEN CLOSED 5.22.5 Check all valves and fittings for leaks.5.22.6 Replace valve seals on transmitter valves as required.5.22.7 Have Operations Close 1E51-F031 and Open 1E51-F010. VALVE RESTORATION INITIALS VALVE TEST NORMAL FINAL PERFORMER VERIFIER 1E51-F031 OPEN CLOSED IE51-FO10 CLOSED OPEN J:\ADMSRVS\TECHSRVS\I\IE51R02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Page RTYPE B6.61 XRef DATA SHENT I (Continued) CONDENSATE STORAGE TANK (RCIC)LOW LEVEL CALIBRATION STEP 5.22.8 CHANNEL E SAFETY RELATED REQUIRED ACTION Have Operations place RCIC DIV I MOV TEST switch to NORM.INITIALS Operations: Verifier: 5.22.9 Complete Hardware Restoration Section for IE51-N635E. HARDWARE RESTORATION DESCRIPTION TEST NORMAL FINAL PERFORMER VERIFIER Cal Select Command switch center knob POS 7 OFF Cal Select Command switch outer knob POS 7 OFF Cal Unit POWER switch ON OFF 5.22.10 5.22.11 Remove Digital Readout Assembly.Verify:$$ a. Status Light TRIP UNIT 1 IN CAL/GR FAIL IH13-P601-21B (DS-12) is Off.b. Computer Point E51L617 displays NORMAL.c. Indicating Light RCIC Dl MOV IN TEST STATUS 1H13-P601-21B (DS8) is Off.5.22.12 Verify reading 1E51-N635E is consistent with existing plant conditions. 5.23 Record test equipment used for this test. This step may be performed out of sequence if desired.TEST EQUIPMENT LOG TEST EQUIPMENT M&TE NO. CAL DUE DATE_______ ____ I ______J:\ADMSRVS\TECHSRVS\I\IE51R02.DOC GRAND GULF NUCLEAR STATION SURVEILLANCE PROCEDURE Page RTYPE B6.61 XRef DATA SHEET I (Continued) CONDENSATE STORAGE TANK (RCIC)LOW LEVEL CALIBRATION CHANNEL E SAFETY RELATED STEP REQUIRED ACTION 5.24 Complete As Found Loop Error Calculations. CAUTION: Recheck math, especially negative numbers.LOW LEVEL TRIP: IE51-N635E XMTR mA TRIP UNIT mA COMBINED Desired: 5.60 (2) As Found: mA (1) As Found: -Desired: -5.60 5.60 Desired+( ) = ( ) Total Loop Error (add)As Found Loop Setpoint: mA* (Transfer to Step 5.25)5.25 Complete Tech Spec As Found Compliance Verification. LOW LEVEL TRIP: 1E51-N635E TECH SPEC: > 3.7 ft. (5.48 mA)Is following true? * > 5.48 mA (*Insert As Found Loop Setpoint)Initial: YES (Complies w/Tech Spec limit)NO (Does not comply -Notify Shift Supervisor) 5.26 Notify Shift Supervisor test is complete. Shift Supervisor's signature is required on Data Package Cover Sheet.J:\ADMSRVS\TECHSRVS\I\IE51R02.DOC Attachment 5 To GNRO-2007100068 GGNS Procedure 01-S-06-12 G070068 PLANT OPERATIONS MANUAL Volume 01 Section 06 01-S-06-12 Revision: 109 Date: 8/10/05 ADMINISTRATIVE PROCEDURE GONS SURVEILLANCE PROGRAM SAFETY RELATED Prepared: Reviewed: Concurred: Approved: List of Effective Pages: Pages 1-37 Attachments I-VI List of TCNs Incorporated: Revision TCN 0 None 1 1 2 2 3 3-5 4 None 5 6 6 7 7 8 8 9,10 9 11,12 10 13 11 14,15 (Canceled) 12 None 13 16 14 17,18 15 19 16 20,21,22 17 None 18 23 19 24,25,26 20 None 21 27,28 Revision 100 101 102 103 104 105 106 107 108 109 TCN None 29,30,31,32 None 33,34 None 35,36 None 37,38 39 None J:\ADMSRVS\TECHPUB\REVISION\I\IS0612.DOC GRAND GULF NUCLEAR STATION ADMINISTRATIVE PROCEDURE Title: G NS Surveillance Program No.: 01-S-06-12 Revision: 109 Page: i RPTS FORM 10C1R50.59 Review Required? (X) Yes If Yes, transmit 50.59 Review Form along with procedure to Document Control as a separate irecord.No Not reauired per LI-101 Cross-Dici line review r ired? W(X) Yes (Note affected Departments Below)Prearer Initials>>> 6 Department Cross-DiuciplIne Reviews Needed / Signoff__ I (signed, electronic, telcon)System Engineering Does this directive contain Tech Spec Triggers? C ) YES (X) NO REQUIREMENTS CROSS-REFERINC LIST lRequirement Implemented by Directive IDirective Paragraph Number Name I Paragraph Number That Implements Requirement Ce-C 1011% IsI 302 S I 303. S3 &..4.4 ANSI N18.7 5.2.8.SI, 5.2.19.SI & S2(3) *TECH SPEC 5.4.1.a *FSAR 13.1.2.2.S6

  • FSAR 18.1.13.Response.Para.2.S2
  • FSAR 13.5.3.1.S2
  • QAPM B.S.a, A.1.d *QAPM A.l.b, B.8.c, A.2.e.2 2.0 FSAR 6.3.2.2.1.S34 2.4.3 TECH SPEC SR 3.0.2, SR 3.0.3.S3 6.4.4 TECH SPEC 5.5.6 6.4.5 TRM 7.6.3.3 6.4.5 FSAR 13.5.3.1.Sl 6.1.2 QAPM B.8.c, B.B.d.3, B.9.d.l, 6.2 B.S.d.4, A.l.d FSAR 18.1.13.Response.Para.3.a.S1

& S2 6.5.5b AECM 85/0415 Att. 1, Pg. 1, IV.S1 6.7.1 ANSI N18.7 5.2.6.SI, S2, S3, S4, S5, 6.2.1e S16, S17, S18 FSAR 6.3.2.2.1.$35.a 6.2.1.e ANSI N18.7 5.2.6.S13 & S14 6.2.1e(3)ARCM 80/0026 Question #6 6.2.le(9)FSAR 18.1.13.Response.Para.3.c.Sl 6.2.le(9)ANSI N18.7 5.2.6.S22 6.2.le(9)FSAR 4.6.1.1.2.4.2.6.S35 6.2.le(9)FSAR 18.1.29.1.Response.Para7, 6.3.2.2.l.S35.a 2.4.3, 6.2.1e(9) (a)IEEE 338 All *ANSI N18.7 5.2.6.S14 & SIS 6.2.2b ANSI N18.7 5.3.S3 6.2.2b(4)QAPM A.3.f, B.14.b 6.3.1 ANSI N18.7 5.2.15.S1, S4, S15 & S20(1) 6.3.1b ANSI N18.7 5.2.15.S8 & S14 6.3.if ANSI N1B.7 5.2.15.S9 6.3.1 TRM 7.6.2 6.3.1 QAPM B.8.a, B.10.a, B.10.b J:\ADM_SRVS\TECH_PUB\REVISION\I\IS0612 .DOC R.- GRAND GULF NUCLEAR STATION ADMINISTRATIVE PROCEDURE Title: GONS Surveillance Program No.: 01-S-06-12 lRevision: 109 -Page: ii REQUIPRZMITS CROSS-REPERENCS LIST (Cont.)SRequirement Implemented by Directive _ Directive Paragraph Number Name IParasraph Number That Implements Requirement QAPM Tablel.C.19 6.4 ANSI N18.7 5.2.8.S5 6.4.2, 6.4.4 QAPM Tablel.B.3 6.1.5 OMa-1988 Part 10 4.2.1.2(g) 6.4.5a & b ANSI N18.7 5.2.8.S2 6.4.5 OMa-1988 Part 6 6.1 6.4.6a FSAR 18.1.29.l.Response.Para8 6.5.5 FSAR 7.2.2.1.2.3.1.13.SI 6.5.5a FSAR 7.2.2.1.2.3.1.14.SI, S2 & Para.3 & 4 6.5.5a OMa-1988 Part 10 4.2.1.8 6.7.2 OMa-1988 Part 10 4.2.1.9 6.7.2 QAPM B.8.e, B.8.f 6.8 FSAR 13.1.2.2.S5 6.8.3 AECM 86/0307 Att. 1, Pg. 4, Item E.S5 6.8.3.a, AECM 87/0229 87-26-03, It. 4.S7 6.8.9, 6.9 AECM 87/0229 87-26-03, It. 4.S6 6.8.11, 6.9.1, 6.9.2 AECM 87/0229 87-26-03, It. 4.S4 6.2.2.b(4) AECM 87/0229 87-26-03, It. 4.S5 6.6.1b FSAR 6.3.2.2.1.S33 6.2.le(9) (a)QDR 0202-93 6.4.9, 6.4.11 GNRO-95/00063 Item E. Para. 2 6.2.2.a(2) (c)AECM-83/0177 Pg. 12 Item #7 *QDR 87/0559 6.5.4a,b GNRO-97/00105 Item E. Para. 3(2) *CR GGCR1996-0551 Attachment IV pp 1 of 2, 2 of 2 CR GGCR1997-0088 Attachment VII pp 1 of 2, 2 of 2 CR GGCR1999-0345 6.9.3 CR GGCR2004-1660 6.8.13, 6.9.2 AECM 83/0177 Pg.16,Item 2 6.4.1 AECM 87/0237 Att. 1, Pg. 3,IT.E.S4 6.4.1 GNRO 91-00183 Att. l.E,Para.2.Sl & S3 6.4.1* Covered by directive as a whole or by various paragraphs of the directive. NOTE The Equipment Database (EDB) Request statement is applicable only to Volume 06 and 07 maintenance directives. EDB Change Request generated and the backup documentation available for setpoint and/or calibration data only 0 Yes J N/A EDBCR #Current Revision Statement Revision 109: " Removed outdated commitment ANSI N18.7, Section 5.2.15, Sentence 12 from cross reference list. This commitment required plant procedure review of no less than every two years to determine if changes were necessary. Required procedure reviews are now determined and controlled in accordance with the QAPM Section 6. Ref: CR-GGN-2005-01383" Deleted Step 6.3.3. New and revised Surveillance procedure review and approval requirement is clarified and included in step 6.3.1. Ref: CR-GGN-2005-01383 J:\ADMSRVS\TECHPUB\REVISION\I\IS0612.DOC GRAND GULF NUCLEAR STATION ADMINISTRATIVE PROCEDURE Title: GGNS Surveillance Progra No.: 01-S-06-12 IRevision: 1o9 7Page: iii Current Revision Statement (cont'd)" Incorporates the use of the Corrective Action Process for documenting and reviewing unsatisfactory conditions discovered during performance of Surveillance activities. This action eliminates redundant Engineering reviews and improves the formality of the review process. Reference step 6.8.2.d and section 6.9.* Added requirement to clarify that Surveillance procedures must be prepared per step 6.2 of this procedure in conjunction with the Authors Guide, 01-S-02-3." Step 6.1.6 -Corrected procedure number from 01-S-02-3 to 01-S-02-2." Deleted step 6.2.2.a (8). Post Engineering reviews will be performed using the Corrective Action process.* Section 6.8.10 -Removed the requirement of work order completion in the Work Management System by Xerox copies.* Step 1.1.4 added to clarify the acronym "WMS".* Deleted Reference 3.17 -Procedure 17-S-05-8 is cancelled.

  • Corrected title on Reference 3.6* Attachment 1 revised to include an outline step (FF) for delineating attachments to a Surveillance procedure." Enhanced step 6.1.3 and 6.4.4 to add SR 3.0.3 LCO requirement.
  • Editorial changes were made such as misspelling, changing reference numbers to actual procedure numbers, correction of step number due to deleted steps in previous revision 108." Table of Contents 6.3 and 6.9 changes made to clarify section requirements." Requirements Cross-Reference List updated to add references from cancelled Scheduling procedure, 17-S-05-8.

J:\ADMSRVS\TECHPUB\REVISION\l\IS0612.DOC GRAND GULF NUCLEAR STATION ADMINISTRATIVE PROCEDURE Title: GGNS Surveillance Program No.: 01-S-06-12 Revision: 109 Page: I TABLE OF CONTENTS Page 1.0 PURPOSE AND DISCUSSION 2 2.0 RESPONSIBILITIES 3

3.0 REFERENCES

6 4.0 ATTACHMENTS 7 5.0 DEFINITIONS 7 6.0 DETAILS 8 6.1 Surveillance Requirements 8 6.2 Surveillance Procedure Author's Guide 10 6.3 Review, Approval, and Issue of New or Revised 16 Surveillance Procedures

6.4 Scheduling

of Surveillances 19 6.5 Assembly, Review and Sign-on of Surveillance Packages 24 6.6 Performance of Surveillance Package 26 6.7 Special Requirements 28 6.8 Completion and Review of Surveillance Package 29 6.9 Conduct of Program and System Engineering Reviews 36 J:\ADMSRVS\TECHPUB\REVISION\l\IS0612.DOC GRAND GULF NUCLEAR STATION ADMINISTRATIVE PROCEDURE I Title: GGNS Surveillance Program No.: 01-S-06-12 Revision: 109 FPage: 2 1 1.0 PURPOSE AND DISCUSSION

1.1 Purpose

1.1.1 To define the responsibilities and requirements for implementing the GGNS Surveillance Program.1.1.2 Changes required for implementation of 1994 TSIP were incorporated in Revision 100. For historical reference this statement should not be deleted.1.1.3 For clarification, any reference to "NRC LATE DATE" in this procedure is to be considered synonymous with "LATE DATE" in WMS.1.1.4 For clarification any reference to "WMS", which is commonly known as the Work Management System, in this procedure is to be considered synonymous with any computer system used to track/schedule work activities.

1.2 Discussion

1.2.1 The Surveillance Program implements the surveillance requirements of the Technical Specifications Updated Final Safety Analysis Report (UFSAR), Technical Requirements Manual (TRM), and the Offsite Dose Calculation Manual (ODCM), and Dry Fuel Storage Current License Basis documents (DFS-CLB).

a. The Plant Surveillance Program ensures: 4 (1) Safety Related and (Important To Safety -Dry Fuel Storage) structures, systems and components are available to perform their intended functions.

(2) Adherence to the chemical and radioactive release limits.b. The Inservice Testing (IST) Program, Ref. 3.25, ensures that surveillance requirements for inspection and testing of ASME Code Class 1, 2 and 3 pumps and valves are met.1.2.2 The Surveillance Program Coordinator is the process owner of the Surveillance Program Process and is responsible for: a. Administration and interpretation of day-to-day activities.

b. Monitoring and adjusting for efficiency and effectiveness.
c. Coordination with other processes and organizations.
d. Accountability and responsibility for changes and improvements.

1.2.3 Throughout

the body of this procedure the word "Technical Specification" (Tech Spec or TS) is synonymous with "Updated Final%, Safety Analysis Report" (UFSAR) "Technical Requirements Manual" (TRM) and "Offsite Dose Calculation Manual" (ODCM) and"Certificate of Compliance for Spent Fuel Storage Casks Number 1014'(DFS COC), and "HISTORM IOCFR72.212' (ENS 212), and "HISTORM 10CFR72.212 Appendix C" (GGNS 212).J:\ADMSRVS\TECHPUB\REVISION\I\IS0612.DOC GRAND GULF NUCLEAR STATION ADMINISTRATIVE PROCEDURE Title: GGNS Surveillance Program No.: 01-S-06-12 Revision: 109 1Page: 3 2.0 RESPONSIBILITIES 2.1 Manager, Planning and Scheduling/Outage Is responsible to the Plant General Manager for management of the GGNS Surveillance Program.2.2 Scheduling Supervisor -Is responsible for: 2.2.1 Assigning responsibility for preparing procedures to satisfy Tech Spec surveillance requirements to applicable plant sections.2.2.2 Coordinating and integrating the Surveillance Scheduling Program.2.3 Manager, System Engineering -Is responsible for: 2.3.1 Assisting Scheduling in identifying Tech Spec surveillance requirements and the responsible section in (2.2.1).2.3.2 Providing the technical interface with the Manager, Plant Licensing for those surveillance matters requiring engineering or technical expertise. 2.4 On-Duty Shift Manager -Is responsible for: 2.4.1 Ensuring all surveillance procedures are current and satisfactory.

2.4.2 Ensuring

that required sections of the Technical Specifications are followed.2.4.3 Maintaining a log of all surveillances, which require releasing plant equipment or facilities that have been authorized to start testing. This log should include the date/time surveillance started and date/time surveillance ended in accordance with 02-S-01-5, Shift Logs and Records.2.5 Discipline Supervision -Is responsible for: 2.5.1 Preparing applicable section surveillance procedures which meet the requirements of the Technical Specifications.

2.5.2 Reviewing

applicable section surveillance procedures to ensure their technical adequacy.2.5.3 Determining plant conditions required for each surveillance they are responsible for.2.5.4 Identifying the need for Tech Spec triggers for directives which are outside the implementing department's responsibility, but are required in order to support performance of the implementing procedures.

2.5.5 Approving

all procedures containing Tech Spec Triggers for which they are responsible. This approval ensures that triggers are correct and stay current/correct when procedures are TCNd/revised.

2.5.6 Designating

a cross-discipline review of procedure changes when the procedure being changed contains triggers to another section's procedures. J:\ADMSRVS\TECHPUB\REVISION\I\IS0612.DOC GRAND GULF NUCLEAR STATION ADMINISTRATIVE PROCEDURE I Title: GGNS Surveillance Program No.: 01-S-06-12 lRevision: 109 1 Page: 4 2.5.7 Approving all surveillance procedures (except automatic revisions) for which they are responsible. This approval ensures that procedures are correct and stay current/correct when they are TCNd/revised.

2.5.8 Ensuring

Surveillance tests are converted to Surveillance-WOs for their disciplines. NOTE Planning and Scheduling has the responsibility for converting Surveillance Tasks to Surveillance-WOs.

2.5.9 Ensuring

completed Surveillance WOs and test results are forwarded to the Surveillance Program Coordinator in a timely manner.2.5.10 Ensuring section Surveillance WOs are completed within the time specified on the most recent "Late Date Report" and other scheduling methods/reports per Section 6.4.2 or by notifying the Surveillance Coordinator per Step 6.4.9.2.5.11 Ensuring the correct Surveillance procedure is attached to the respective work order package and issued to the individual(s) performing the test. The person(s) assembling the work order packages will accomplish this by: a. Verifying the Surveillance procedure number, Surveillance-WO number and any applicable attachments, tables, or component numbers shown on the printed Surveillance-WO matches the attached Surveillance procedure data sheets.b. Writing the work order number and any other information designated in 2.5.11a in the upper right hand corner of the data package cover sheet if this information is not pre-printed on the Surveillance procedure data sheets. This step is optional for Operations Surveillance work order packages who should verify this information correct prior to release of work.c. Initialing the Surveillance procedure data package cover sheet per Step 6.5.4 to document that the requirements of Step 2.5.11a and b are complete.2.5.12 Notifying Surveillance Program Coordinator per Step 6.4.12 when changes to their surveillance procedures affect the WMS Database.2.5.13 Ensuring surveillance procedure results are reviewed by qualified individuals to determine that all requirements have been satisfied. J:\ADMSRVS\TECHPUB\REVISION\I\IS0612.DOC GRAND GULF NUCLEAR STATION ADMINISTRATIVE PROCEDURE I Title: GoNS Surveillance Program No.: 01-S-06 Revision: 109 1Page: 5 2.6 Surveillance Program Coordinator or Designee -Is responsible for: 2.6.1 Notifying the Supervisor, Code Programs of the status and completion of all surveillance procedures that address IST requirements to ensure code-related data is reviewed by the Supervisor, Code Programs.2.6.2 Maintaining surveillance information in the WMS Database current by updating the WMS Database as surveillance tasks change.2.6.3 Maintaining a complete status of surveillances and ensuring surveillances do not exceed their time limit without prior notification to Plant Management per Section 6.4.9.2.6.4 Receiving and reviewing completed Surveillance-WOs and Surveillance Procedure Data Packages.2.6.5 Ensuring Surveillance-WOs and Surveillance Procedure Data Packages are forwarded to Records Management for retention. 2.7 Engineering, Programs and Components Group, Supervisor, Code Programs -Is responsible for: 2.7.1 Verifying compliance with ASME code requirements that are a part of the Surveillance Program.2.7.2 Verifying test results for ASME code compliance and identifying necessary changes in the Surveillance Program.2.7.3 Reviewing all surveillance procedures that have IST Acceptance Criteria.2.8 Releasing Organization Supervisor (ROS) -Is responsible for: 2.8.1 Releasing plant equipment or facilities in accordance with 01-S-07-1, Control of Work on Plant Equipment and Facilities. 2.9 Manager, Plant Licensing -Is responsible for maintaining (with input from the technical reviewer on procedure changes) the Requirements Procedure Tracking System (RPTS).2.10 Engineering, Logic System Functional Testing (LSFT)Coordinator -Is responsible to ensure that changes to GGNS procedures which could change the LSFT testing scope of a procedure are reviewed against the LSFT test scope depicted on applicable marked drawings. This review is required to ensure the LSFT testing requirements specified in Technical Specifications are maintained. This review can be performed by the responsible System Engineer and discussed later with the coordinator, if required.2.11 Manager, Programs and Components -Is responsible for assigning responsibility for preparing procedures to satisfy Tech Spec Surveillance requirements for applicable plant programs.J:\ADMSRVS\TECHPUB\REVISION\I\IS0612.DOC GRAND GULF NUCLEAR STATION ADMINISTRATIVE PROCEDURE Title: GGNS Surveillance Program No.: 01-S-06-12 Revision: 109 1 Page: 6

3.0 REFERENCES

3.1 EOI Quality Assurance Program Manual 3.2 USNRC Regulatory Guide 1.33 (Rev 2, 2-78)/ANSI N18.7-1976

3.3 Administrative

Procedure 01-S-17-11, Preventive Maintenance Program 3.4 FSAR Section 13.5.3.1 3.5 Administrative Procedure 01-S-02-3, Author's Guide 3.6 Administrative Procedure 01-S-02-2, Control of the GGNS Operations Manual 3.7 USNRC Regulatory Guide 1.118 (Rev 2, 6-78)/IEEE 338-1977 3.8 IOCFR50.59 3.9 10CFR50.55a (g)3.10 GGNS Technical Specifications (Appendix A to License No. NPF-29)3.11 GGNS Environmental Protection Plan (Appendix B to License No. NPF-29)3.12 ENS Nuclear Management Manual AD-103, Document Control and Records Management Activities 3.13 CEP-IST-4, ENS Standard on In-service Testing 3.14 Administrative Procedure 01-S-06-5, Reportable Events and Conditions 3.15 Administrative Procedure 01-S-06-3, Control of Temporary Alterations 3.16 Administrative Procedure 01-S-07-1, Control of Work on Plant Equipment and Facilities 3.17 Deleted (17-S-05-8 cancelled) 3.18 Administrative Procedure 01-S-15-5, Directive Submittal Requirements for RPTS 3.19 LI-101, IOCFR50.59 Review Program 3.20 Section Procedure 07-S-01-227, Equipment Qualification Program 3.21 Title 10, Code of Federal Regulations, Part 50, Appendix J 3.22 Surveillance Procedure 06-ME-IM61-V-0001, Local Leak Rate Test 3.23 Section Procedure 02-S-01-5, Shift Logs and Records 3.24 Administrative Procedure 01-S-08-2, Exposure and Contamination Control 3.25 Program Section CEP-IST-002, GGNS Pump and Valve Inservice Testing Plan 3.26 LI-113, License Basis Document (LBD) Control Program 3.27 Nuclear Management Manual RP-105, Radiation Work Permits 3.28 Technical Requirements Manual, Section 7.0, Administrative Controls J:\ADMSRVS\TECHPUB\REVISION\I\IS0612.DOC GRAND GULF NUCLEAR STATION ADMINISTRATIVE PROCEDURE Title: GGNS Surveillance Program No.: 01-S-06-12 Revision: 109 Page: 7 3.29 Corporate Procedure, LI-102, Corrective Action Process 3.30 ASME Operation and Maintenance Standard, 1987 Edition, including ASME/ANSI OMa-1988 Addenda.3.30.1 Part 6 -Inservice Testing of Pumps in Light-Water Reactor Power Plants 3.30.2 Part 10 -Inservice Testing of Valves in Light-Water Reactor Power Plants 3.31 Certificate of Compliance for Spent Fuel Storage Casks #1014 3.32 HISTORM 10CFR72.212 3.33 HISTROM lOCFR72.212 Appendix C 4.0 ATTACHMENTS

4.1 Attachment

I- Surveillance Procedure Numbering System 4.2 Attachment II -Surveillance Procedure Cover Sheet (Example)4.3 Attachment III- Surveillance Procedure Data Package Cover Sheet (Example)4.4 Attachment IV -Surveillance Credit Verification Form 4.5 Attachment V -Late Surveillance Notification Form 4.6 Attachment VI -Surveillance Procedure Review Checklist 5.0 DEFINITIONS 5.1 Work Management System (WMS) -The computerized system used to track work activities. For clarification, any reference to "WMS" in this procedure is to be considered synonymous with any computer system used to track/schedule work activities.

5.2 Reguirements

Procedure Tracking System (RPTS) -A computerized program that: 5.2.1 References each applicable Technical Specification/TRM/ODCM requirement to a procedure that meets the requirement.

5.2.2 References

each procedure to the Technical Specifications requirements that it meets.5.2.3 Cross-references requirements of the IST Program, Reference 3.26, by the system component number to the procedure that meets the requirement. 5.2.4 Is controlled and maintained by Nuclear Safety Assurance. J:\ADMSRVS\TECHPUB\REVISION\l\IS0612.DOC GRAND GULF NUCLEAR STATION ADMINISTRATIVE PROCEDURE Title: GGNS Surveillance Program No.: 01-S-06-12 Revision: 109 Page: 7A 5.3 Surveillance Requirements -Requirements of GGNS Technical Specifications relating to test, calibration or inspection to ensure the necessary quality of systems and components are maintained, that facility operation will be within the safety limits, and limiting conditions of operation A will be met (IOCFR50.36(c) (3)). For Dry Fuel Storage Activities: Inspection and monitoring of spent fuel, high-level radioactive waste, or reactor-related GTCC waste in storage; Inspection, test and calibration activities to ensure that the necessary integrity of required systems and components is maintained; Confirmation that operation of the ISFSI or MRS is within the required functional and operating limits; and confirmation that the limiting conditions required for safe storage are met (10CFR72.44 (c)(3)).5.4 WMS Surveillance Testing (ST) Proaram -The module in the WMS computerized system used to track/schedule surveillance procedures and document the performance of GGNS Surveillance Requirements. J:\ADMSRVS\TECHPUB\REVISION\l\IS0612.DOC GRAND GULF NUCLEAR STATION ADMINISTRATIVE PROCEDURE I Title: GGNS Surveillance Program No.: 01-S-06-12 Revision: 109 1 Page: 8 5.5 Tech Spec Trigger -A step that initiates a Tech Spec requirement causing performance of another surveillance procedure or action, or initiates increased frequency of testing to ensure compliance with the GGNS Technical Specifications. 5.6 IST Review -A review of the completed Surveillance Data Package to check any data recorded affecting IST Acceptance Criteria to satisfy ASME Code Section XI, and ASME/ANSI OMa-1988 requirements for Inservice Testing of Pumps and Valves (Tech Spec 5.5.6). This review may be performed either before or after the completed Surveillance Data Package is sent to Records Management.

5.7 Technical

Recruirements Manual (TRM) -A controlled document that may contain relocated Technical Specifications. The items in the TRM are used in conjunction with the TS and may be duplicated in other controlled documents.

5.8 Offsite

Dose Calculation Manual (ODCM) -A supporting document of the Grand Gulf Nuclear Station Technical Specifications. It describes the methodology and parameters used in the calculation of offsite doses resulting from radioactive liquid and gaseous effluents, in the calculation of liquid and gaseous effluent monitoring ALARM/TRIP setpoints, and in the conduct of the Radiological Environment Monitoring Program.5.9 Logic System Functional Test -A Logic System Functional Test shall be a test of all required logic components (i.e., all required relays and contacts, trip units, solid state logic elements, etc.) of a logic circuit, from as close to the sensor as practicable up to, but not including, the actuated device, to verify Operability. The Logic System Functional Test may be performed by means of any series of sequential, overlapping, or total system steps so that the entire logic system is tested.5.10 Dry Fuel Storage License Basis Documents (DFS)- a series of documents that promulgate the requirements of operating an Independent Spent Fuel Storage Installation (ISFSI). They include: HISTORM lQCFR72.212; HISTORM 10CFR72.212 Appendix C; Certificate of Compliance for Spent Fuel Storage Casks Number 1014; HISTORM COC; and HISTORM FSAR.6.0 DETAILS 6.1 Surveillance Requirements 6.1.1 Each Discipline Supervision must prepare specific detailed surveillance procedures to be included in Volume 6 of the GGNS Operations Manual per 6.1.1b and 6.1.1c below.a. If surveillance requirements are covered by permanent procedures not in Volume 6, they must be referenced in the RPTS.b. Surveillance procedures must be prepared in accordance with this procedure as directed by the Author's Guide, section 6.2 in conjunction with the Author's Guide, 01-S-02-3. The numbering system for surveillance procedures must be in accordance with this procedure, Attachment I.c. The review, approval, and distribution of surveillance procedures must be performed in accordance with Administrative Procedures 01-S-02-2 and 01-S-02-3. J:\ADMSRVS\TECH PUB\REVISION\l\1S0612.DOC GRAND GULF NUCLEAR STATION ADMINISTRATIVE PROCEDURE ITitle: GGNS Surveillance Program No.: 01-S-06-12 Revision: 109 Page: 9 6.1.2 This procedure shall control the implementation of Tech Spec surveillance requirements. Other required periodic tests due to self-imposed plant requirements, manufacturer's recommendations, or good engineering practices are generally controlled by other plant section programs, but can be controlled under the surveillance program if directed by Scheduling Supervisor. 6.1.3 Each Surveillance shall be satisfactorily performed within the specified time interval with extensions as allowed by SR 3.0.2 or the required actions for the applicable Limiting Condition for Operation (LCO) shall be met in accordance with SR 3.0.3.6.1.4 Deleted (moved to 6.1.1c)6.1.5 Occasionally, Technical Specifications requirements may be satisfied by means other than permanent plant procedures (e.g., temporary directives, special tests and preoperational tests, normal/abnormal plant events or equipment actuations, etc).The Scheduling Supervisor and the responsible Discipline Supervision must approve such tests/events as satisfying the Technical Specifications requirements using the following guidelines: NOTE If surveillance procedure data sheets are used for retests of WOs, the approval as specified in Step 6.1.5a-f, is not required unless credit for the surveillance is taken.a. The test/event must be reviewed by a qualified Technical Reviewer.b. The Technical Reviewer shall ensure the test and/or event satisfies the applicable Technical Specification requirements.

c. The Technical Reviewer must compare the test and/or event to the plant procedure which incorporates the same Technical Specification requirements if a plant procedure has been issued.d. The Technical Reviewer will document the review, activity date and test/event data on Attachment IV or similar form.The documents shall be subject to at least the same record storage requirements as Surveillance Procedure Data Packages.The documents must be cross-referenced to the surveillance requirement for document retrieval purposes.e. The appropriate Discipline Supervision or designee shall approve the review.J:\ADMSRVS\TECH_PUB\REVISION\I\IS0612.DOC GRAND GULF NUCLEAR STATION ADMINISTRATIVE PROCEDURE T itle: GGNS Surveillance Program INo.: 01-S-06-12 Revision:

109 Page: 101 6.1.5 (Cont.)NOTE The Technical Reviewer and Approver will not be the same person.f. The surveillance activity shall be rescheduled based on the test/event performed date.6.1.6 If a surveillance procedure is issued which supersedes an existing procedure, the author of the new procedure is responsible for issuing a cancellation form per the Control of the GGNS Operations Manual, 01-S-02-2.

6.1.7 During

preparation and review of the procedure, the author must ensure that any special requirements listed in the DFS-CLB, UFSAR, TRM and ODCM are included in the surveillance procedure.

6.2 Surveillance

Procedure Author's Guide 6.2.1 Format and Content The following sections must be included in all surveillance procedures to ensure consistency. The sections listed must be included even if "None" is their content.a. 1.0 PURPOSE Provide a concise statement of the procedure intent,.including its scope and applicability. Specifically address procedure frequency, any IST or NUREG 0588 requirements.

b. 2.0 PRECAUTIONS AND LIMITATIONS Identify all precautions and limitations imposed on plant operations or plant conditions during performance of the surveillance procedure.

List the following items as applicable: (1) Precautions to protect personnel and equipment (2) Requirements for maintaining grade "A" cleanliness (3) Applicable operating limits required during performance of the activity. A list of equipment which could change status during performance of the surveillance procedure may need to be included.(4) Statement such as: "Steps denoted by a pound sign (#)within the body of the procedure require initials on Data Sheet I." (5) Statement such as: "Items marked with a dollar sign ($)are those items which are required to be completed for Technical Specifications Acceptance Criteria." J:\ADMSRVS\TECHPUB\REVISION\I\IS0612.DOC GRAND GULF NUCLEAR STATION ADMINISTRATIVE PROCEDURE Title: GGNS Surveillance Program No.: 01-S-06-12 Revision: 109 Page: 11 6.2.1b (Cont.)(6) Steps marked with a star (0) are those items which indicate interprocedure overlap points for Logic System Functional Test acceptance criteria.(7) Statement such as: "Items marked with an (I) are those items required to be completed for IST Acceptance Criteria (Tech Spec 5.5.6)." c. 3.0 REQUIRED MATERIAL AND TEST EQUIPMENT List the items required to perform the surveillance procedure. Common hand tools may be excluded. Note any equipment which requires an appreciable time (24 hours) to obtain.d. 4.0 PREREQUISITES AND PLANT CONDITIONS List requirements which have to be satisfied before performing the "INSTRUCTIONS" section of the surveillance procedure. These requirements may include the following: (1) Plant Mode in which the Surveillance is required or allowed to be performed (2) Equipment or system isolation requirements (3) Radiation Work Permit requirements

e. 5.0 INSTRUCTIONS NOTE At the discretion of the responsible Discipline Supervision, some or all requirements of Step 6.2.1e may be included in procedure attachments instead of in Section 5.0.Include the following detailed information if applicable:

(1) Permission from releasing organization to start NOTE Permission of the Shift Supervisor is required to release plant systems for surveillance testing.(2) Establishment of required communications (3) Detailed steps for placing the system, channel, instrument or component in a specific condition J:\ADM_SRVS\TECHPUB\REVISION\l\1S0612.DOC GRAND GULF NUCLEAR STATION ADMINISTRATIVE PROCEDURE Title: GONS Surveillance Program No.: 01-S-06-12 IRevision: 109 IPage: 12 6.2.le (Cont.)NOTE Equipment hardware modifications (e.g., lifted leads, jumpers) shall include requirements for the performer and an independent verifier to initial the data package in accordance with Reference 3.15.(4) Step-by-step instructions in the degree of detail necessary for performing the surveillance task correctly (5) Witness or Hold Points and other check points (6) Information applicable to specific steps placed and blocked in accordance with 01-S-02-3, Author's Guide: NOTE -Clarifies instructions CAUTION -Describes equipment hazards or adverse operations WARNING -Describes personnel hazards (7) If a step contains a Tech.Spec trigger, the words "TECH SPEC TRIGGER" followed by the appropriate Tech Spec number in parentheses should be placed before the first sentence of the step.(a) For TRM requirements use the phrase "TECH SPEC TRIGGER".(b) For ODCM requirements use the phrase "TECH SPEC TRIGGER".(8) An alternate method for denoting Tech Spec triggers may be used with approval from the Scheduling Supervisor. (9) Restoration of the component(s): (a) Steps shall be included requiring return to normal valve lineup if valve positions changed during test performance.(b) Steps shall be included delineating other restoration requirements (e.g., lead seals, transmitter gasket replacement and torque requirements) and comply with requirements of Reference 3.20.(c) Steps shall be included to provide verification that all instrumentation has been properly returned to service following testing if applicable.(d) Restoration of hardware modifications shall include requirements for the performer and an independent verifier to initial the data package per Reference 3.15.J:\ADMSRVS\TECHPUB\REVISION\l\IS0612.DOC GRAND GULF NUCLEAR STATION ADMINISTRATIVE PROCEDURE I Title: GGNS Surveillance Program No.: 01-S-06-12 Revision: 109 1 Page: 13 6.2.1 (Cont.)(e) If functional testing cannot be performed, independent verification is required to ensure that Safety Related equipment is properly returned to service.f.

6.0 REFERENCES

(1) List references used to develop the procedure. (2) When ANSI standards, Regulatory Guides, Codes, are listed, the revision number and/or date of the reference should be used.(3) When listing plant procedures and instructions, the revision number may be listed.(4) Surveillance procedures do not have to be revised to reflect new reference revision numbers unless the surveillance procedure contents or commitments are affected by the reference change.6.2.2 Attachments (Data Package Cover Sheets and Data Sheets)a. A Surveillance Procedure Data Package Cover Sheet (Attachment III or similar form) must be prepared for each surveillance procedure. Environmental surveillance procedures (06-EN-S000-....) may utilize a data package cover sheet similar to Attachment III.(1) Provide the surveillance procedure title and applicable Tech Specs on the Data Package Cover Sheet. The Tech Spec references should be as specific as possible (e.g., Tech Spec SR 3.3.6.5.3.a is better than SR 3.3.6.5.3, TRM SR 6.3.10.1, function 6.3.10-1.1.a). (2) In Section 1.0 of the cover sheet, provide a brief explanation of what the impact on plant operations will*be when the Surveillance Procedure is performed.(a) The impact statement should aid the Shift Supervisor in determining whether or not to authorize test start based on actual plant and equipment conditions and Tech Spec requirements.(b) The impact statement should also reference the applicable Tech Specs and identify out-of-service time limits associated with performance of the surveillance procedure.(c) Impact statements for procedures that are infrequently performed or complex, will be sent to Operations Department for cross discipline review, as determined by Discipline Supervision. Impact statement may also be placed in Maintenance Action Item rather than in Procedure for impact that are complex or affect more than one component. J:\ADMSRVS\TECHPUB\REVISION\I\IS0612.DOC GRAND GULF NUCLEAR STATION ADMINISTRATIVE PROCEDURE Title: GGNS Surveillance Program No.: 01-S-012 Revision: 109 Page: 14 6.2.2 (Cont.)(3) In Section 2.0 provide: (a) Means to denote Plant Mode at time of surveillance performance.(b) DELETED (c) A blank to record actual test start time and date.1) The primary purpose of this requirement is to keep track of LCO time.2) A signature blank for test performer should be on the cover sheet.3) The Responsible Discipline Supervision may exempt any of these requirements on a case-by-case basis.(4) In Section 3.0 of the cover sheet, specify the applicable "Acceptable/Unacceptable" items for each Surveillance Procedure. (5) In Section 4.0 provide blank spaces for identification of any deficiency documents written as a result of the surveillance test.(6) Section 5.0 should list the concurrent signature(s) necessary to ensure the test results are adequately reviewed by appropriate disciplines. At a minimum, the applicable Discipline Superintendent/Supervisor must be listed.(7) An "IST Review is Required" statement shall be provided at the bottom of the Data Package Cover Sheet if any data is being recorded which satisfies Tech Spec 5.5.6 or TRM 7.6.3.3, unless a review is not required as determined by the IST Engineer. Adding this statement ensures the Surveillance WO Data Package is routed to the IST Engineer electronically in the WMS. The IST review will be performed after it is scanned into the Records Management computer system and approved electronically in the WMS. See attachment III, page 2 of 3.(8) Deleted b. Data sheets document the completion of significant paragraphs, steps or pertinent data.(1) Data Sheets should be referenced in the text of the surveillance procedure. (2) The surveillance procedure step being documented should be identified on the data sheet.J:\ADMSRVS\TECH PUB\REVISION\l\IS0612.DOC GRAND GULF NUCLEAR STATION ADMINISTRATIVE PROCEDURE I Title: GGNS Surveillance Program No.: 01-S-06-12 Revision: 109 1 Page: 15 6.2.2 (Cont.)(3) Equipment hardware modifications shall require the initials of the performer and an independent verifier.(4) If the Acceptance Criteria is required for recorded data, it must be specified on the data sheet.(a) Qualitative or quantitative Acceptance Criteria results shall be within the limits given in the Tech Specs for the system or component.(b) Any limit associated with the data recorded should be shown on the data sheet as Acceptance Criteria, e.g., manufacturer's limits, administrative limits, etc.(5) Conversion equations must be specified in the procedure text or on the data sheet if the parameter units given in the Tech Specs are different from the units of the instrumentation being used.(6) When specified by the surveillance procedure, operating log sheets, computer printouts or other surveillance attachments may be used in place of data sheets.c. If the surveillance procedure contains Tech Spec triggers, the data sheets should have the following, as a minimum: (1) If another discipline is to perform the action required by the trigger, the data sheet should identify the minimum level of authority to be notified.(2) The data sheet should contain blanks to record time, date, name of person notified, and test performer's initials to verify notification. (3) Specific details of the action to be performed should be included. In some cases, the surveillance procedure number will be adequate.(4) An alternate method other than above for denoting Tech Spec triggers may be used with approval from the Scheduling Supervisor. J:\ADMSRVS\TECHPUB\REVISION\I\IS0612.DOC GRAND GULF NUCLEAR STATION ADMINISTRATIVE PROCEDURE Title: GGNS Surveillance Program No.: 01-S-06-12 I Revision: 109 1 Page: 16 a 6.2.3 Typing Format a. The upper-left portion of the Surveillance Procedure Cover Sheet (Attachment II) must include: (1) Volume 06 (2) Section Number b. The lower-left portion of the Surveillance Procedure Cover Sheet (Attachment II) must include a list of TCNs incorporated by the revision number.(1) For future revisions, preparer must update the list of TCNs.(2) If the revision does not incorporate a TCN, "None" is indicated on the cover sheet.NOTE The list of TCNs incorporated shows what TCNs have been included in the current revision. The preparer ensures that outstanding TCNs are incorporated when making a revision.6.2.4 Revisions a. All changes made in the revision must be denoted by a vertical line in the margin. All changes must be marked except for revision number, page number and other exceptions per the Author's Guide, 01-S-02-3.

b. The reason for the revision must be stated in the Current Revision Statement on the RPTS sheet and the Requirements Cross Reference List must be updated.c. The draft of the revision should be included with the review package.6.3 Review, Approval, and Issue of New or Revised Surveillance Procedures

6.3.1 Surveillance

procedures must be prepared, reviewed, approved and issued in accordance with this procedure, the Author's Guide, 01-S-02-3, the Control of the GGNS Operations Manual, 01-S-02-2, and the QAPM.a. Surveillance Procedure Review Checklist (Attachment VI)(1) This checklist may be used during procedure revision preparation. (2) If the checklist is not used and Discipline Supervision determines the procedure is not correct, he may return the revision to the preparer and require completion of the checklist. J:\ADMSRVS\TECHPUB\REVISION\l\1S0612.DOC GRAND GULF NUCLEAR STATION ADMINISTRATIVE PROCEDURE Title: GGNS Surveillance Program No.: 01-S-06-12 Revision: 109 Page: 17 6.3.1 (Cont.)(3) The checklist may be disposed of after the procedure has been signed by the Responsible Discipline Supervision. (4) TCNs do not require the checklist.

b. Technical Review (1) A member of plant staff other than the preparer shall review each surveillance procedure or procedure change.(2) The reviewer may be from the same organization as the preparer.(3) The reviewer shall be a qualified Technical Reviewer.(4) The Technical Review shall determine: (a) Technical accuracy (b) Compliance with Tech Specs, FSAR and other licensing commitments (c) IOCFR50.59 and/or 10CFR72.48 applicability (must be documented in the surveillance procedure or TCN)(d) If an unreviewed safety question has been identified, signature must be withheld and further processing must be done per EN-LI-101 and/or EN-LI-112.(e) If the revision constitutes a change to a procedure as described in the FSAR or DFS-CLB; if so, a 10CFR50.59 and/or 10CFR72.48 Safety Evaluation shall be performed in accordance with EN-LI-101 and/or EN-LI-112.(f) If a cross-disciplinary review is required; if so, it shall be performed by review personnel of the appropriate discipline.(g) If Tech Spec trigger points within the procedure are affected; if so, this change should be noted on the RPTS sheet.(h) If a change to the Requirements Cross-Reference List is required in accordance with 01-S-15-5, changes should be reflected on the Requirements Cross-Reference List.(i) If a change to a procedure affects Logic System Functional Testing requirements specified for that procedure, then the procedure should be routed through Engineering for concurrence.

This can be accomplished by requiring Engineering review on the Cross-Discipline Review List.J:\ADMSRVS\TECHPUB\REVISION\I\IS0612.DOC GRAND GULF NUCLEAR STATION ADMINISTRATIVE PROCEDURE Title: GGNS Surveillance Program No.: 01-S-06-12 Revision: 109 [ Page: 18 6.3.1 (Cont.)(j) Reviews to verify conformance to requirements of the Quality Assurance Program. The review consists of an objective evaluation to assure:* Compliance with applicable codes, standards, regulatory requirements, etc. listed in the procedure Commitment Cross-Reference Sheet.* Directions are commensurate with the nature of activities affecting quality." Quality requirements are present in the directive and qualitative and/or quantitative acceptance criteria are clearly defined.c. Cross-Disciplinary Review (1) If determined necessary by the Technical Reviewer, this review will be for concurrence review associated with changes to a particular disciplines work processes and/or responsibilities. (2) An IST Review is required for all surveillance procedure revisions affecting the IST test or Acceptance Criteria.d. Responsible Discipline Supervision (1) Approval signature required for procedure/TCN issue, except for Auto Revs.(2) This signature ensures that the procedure reviews adequately verify the incorporation and preservation of: (a) GGNS Technical Specifications (b) Other licensing commitments (3) If a revision requires the procedure to be rerun, the Responsible Discipline Supervision shall inform the Scheduling Supervisor or Surveillance Program Coordinator for tracking the rerun using WMS.6.3.2 Section directives may be established to specify additional review requirements for surveillance procedure reviews.6.3.3 Deleted (statement was clarified in step 6.3.1)J:\ADMSRVS\TECHPUB\REVISION\l\1S0612.DOC GRAND GULF NUCLEAR STATION ADMINISTRATIVE PROCEDURE Title: GGNS Surveillance Program No.: 01-S-06-12 Revision: 109 1Page: 19 6.4 Scheduling of Surveillances 6.4.1 WMS is a computerized scheduling and tracking work management system. The following reports are generated on a routine basis: a. List of surveillances that are due in the present or anticipated mode in the two weeks following date of the report b. List of surveillances that are NRC LATE in the present or anticipated mode in the one week following date of the report c. Any other special reports requested 6.4.2 All identified surveillances shall be scheduled, if applicable. The method for scheduling surveillances must be as follows: a. Surveillance frequency interval greater than weekly -scheduled by the WMS System.b. Surveillance frequency interval less than weekly -scheduled by the Discipline Supervision, e.g., plant logs, surveillance tests.c. Surveillance frequency weekly -scheduled by the Discipline Supervision or may be included in the WMS if desired.d. Variable or Condition-Based Surveillances -triggered by procedures or other methods. The Scheduling Supervisor is responsible for identifying any surveillance scheduled by the discipline and not by WMS.e. Some surveillance tasks may have tentative or conservative due dates, late dates, or scheduled dates assigned in the WMS Database. These dates are based conservatively on the following contingency. These surveillances are tracked via a"Work Category" number code in WMS and are tested on an alternating basis to ensure compliance with Technical Specifications. For example, testing on Division I and 2 for the applicable surveillance will be performed on an alternating basis once per 36 months to ensure both divisions are tested at least once every 18 months. Division II surveillance will be scheduled and performed from the completion/performance date of Division I surveillance. The "tentative" due and late dates of these surveillance tasks are manually changed in WMS to override the electronic automatic calculation of WMS. These manual overrides require a secondary verification when these dates are manually changed.Work Category (WC) codes are defined as follows: (1) WC31 -Schedule Attachments 1,2 and 3,4 every 36 months such that Attachments 1,2 and 3,4 are performed 18 months apart.J:\ADMSRVS\TECHPUB\REVISION\l\IS0612.DOC GRAND GULF NUCLEAR STATION ADMINISTRATIVE PROCEDURE Title: GoNS Surveillance Program No.: 01-S-06-12 Revision: 1091 Page: 20 6.4.2 (Cont.)(2) WC32 -Schedule Attachments 1 and 2 every 36 months such that Attachments 1 and 2 are performed 18 months apart.(3) WC34 -Schedule Attachments 1,2,3,4 and 5,6,7,8 every 36 months such that Attachments 1,2,3,4 and 5,6,7,8 are performed 18 months apart.(4) WC35 -Schedule Attachments 1,2,5,6,9,10,13,14 and 3,4,7,8,11,12,15,16 every 36 months such that Attachments 1,2,5,6,9,10,13,14 and 3,4,7,8,11,12,15,16 are performed 18 months apart.(5) WC38 -Schedule Attachments 5,6 and 7,8 every 36 months such that Attachments 5,6 and 7,8 are performed 18 months apart.(6) WC43 -Schedule 18 months apart on an alternating basis.6.4.3 The Surveillance Program Coordinator or designee should update the WMS daily, during the normal work week, to reflect the status of all surveillance tests and inspections. 6.4.4 If required in the current mode, each surveillance shall be performed within the specified Technical Specifications time interval with extensions as allowed by SR 3.0.2 or the required actions for the applicable Limiting Conditions for Operation (LCO)shall be met in accordance with SR 3.0.3.a. A maximum allowable extension not to exceed 25% of the surveillance interval.b. If the surveillance requirement is required to be met during the existing Plant Mode the applicable section superintendent is responsible to ensure the Shift Supervisor/Manager and the Surveillance Program Coordinator are notified before exceeding the NRC LATE date.c. For non-WMS scheduled items, the applicable Discipline Supervision is responsible for this notification.

d. The Shift Supervisor/Manager should notify the on-call Duty Manager if it is determined that the non-performance will affect plant operations or cause a plant shutdown.e. If surveillance requirements cannot be met, a LCO has been entered and the NRC LATE date will be exceeded, the applicable Discipline Supervision is responsible for notifying the Surveillance Program Coordinator per Step 6.4.9.J:\ADMSRVS\TECHPUB\REVISION\I\IS0612.DOC GRAND GULF NUCLEAR STATION ADMINISTRATIVE PROCEDURE Title: GONS Surveillance Program No.: 0lS012 Re-vision:

109 Page: 21 6.4.5 Scheduling of IST activities (Pump and Valve Program) shall be in accordance with ASME/ANSI OMa-1988 (Ref. 3.30), Technical Specification 5.5.6, TRM 7.6.3.3, and the IST Program, Ref. 3.25.a. All IST cold shutdown surveillances shall be performed at least once during any scheduled cold shutdown which is long enough to permit performing them, unless they have been performed during the preceding 90 days.NOTE Step 6.4.5b is an exception to the requirements of Tech Spec SR 3.0.2 in accordance with NRC-approved OMa-1988, Part 10, Ref. 3.30. Detail may be found in the IST Program, Ref. 3.25.b. If a cold shutdown occurs which is either unscheduled or is scheduled to last no longer than 30 days, all IST cold shutdown surveillances are not required to be performed before returning to Plant Modes 1, 2, or 3, provided all of the following conditions have been met: (1) The cold shutdown was entered to correct a single problem or closely related problems which prevented or severely hampered continued operation in Plant Modes 1, 2, or 3, and (2) The cold shutdown was unscheduled or was scheduled to last no longer than 30 days before returning to Plant Modes 1, 2, or 3, and NOTE The effort made to perform the surveillance Requirements should be determined by the responsible discipline Superintendent; e.g., Assistant Operations Manager, Support for Operations surveillances, Mechanical Superintendent for Mechanical Surveillances, etc.(3) A "good faith" effort was made to perform all surveillance requirements associated with IST within the confines of the time, manpower, equipment and systems available during the cold shutdown period, and (4) The IST began not later than 48 hours after Plant Mode 4 was achieved and continued until other conditions required for entry into Plant Modes 1, 2, or 3 had been met, and J:\ADMSRVS\TECHPUB\REVISION\l\IS0612.DOC GRAND GULF NUCLEAR STATION ADMINISTRATIVE PROCEDURE ITitle: GGNS Surveillance Program No.: 01-S-06-12 I evision: 109 1Page: 22 6.4.5 (Cont.)(5) Performance of the surveillance requirements was generally in the chronological order in which they were due and without bypassing any surveillance requirements, unless both of the following apply: (a) The Plant Safety Review Committee has specifically approved bypassing the surveillance requirements, and (b) The surveillance requirements could or should not be performed for one or more of the following reasons: 1) The surveillance requirements could not be performed without rendering essential plant systems and equipment Inoperative, or 2) The plant would be placed in an unsafe condition by the performance of the surveillance requirements, or 3) Performance of the surveillance requirements would have involved "major" expenditures of time, manpower, or money that were not in line with the scope of the cold shutdown.6.4.6 Increased frequency testing associated with IST Alert Range should be manually tracked and are the responsibility of Assistant Operations Manager, Support.a. Increased frequency testing associated with IST Alert Range can be tracked in WMS by the Surveillance Program Coordinator. Increased frequency changes are accomplished by initiating a work request per the Preventive Maintenance Program procedure, 01-S-17-11 and forwarded to the Surveillance Program Coordinator for implementation into the WMS.6.4.7 Increased frequency testing associated with diesel generator start failures should be tracked by the WMS because the increased frequency would be long-term. It is the responsibility of the Assistant Operations Manager, Support to coordinate increased frequency changes with the Surveillance Program Coordinator.

6.4.8 Surveillances

with a performance interval equal to or greater than six months are scheduled in the WMS based on a calculation code of"Completion Date". Surveillances with a performance interval less than six months are scheduled in WMS based on a calculation code of "Due Date".a. Upon performance of a Surveillance, the next due date on the WMS reports will be calculated using the performance date plus the scheduled interval.b. Surveillance tasks must be completed and approved by the Shift Supervisor/Manager before rescheduling in the WMS.J:\ADMSRVS\TECHPUB\REVISION\l\IS0612.DOC GRAND GULF NUCLEAR STATION ADMINISTRATIVE PROCEDURE I Title: GGNS Surveillance Program No.: 0-S-06-12 IRevision: 109 1Page: 23 6.4.8 (Cont.)c. The test performance date determines reschedule dates unless an exception is granted by the Scheduling Supervisor.

d. Surveillance-WOs with a performance interval less than six months are scheduled based on a calculation code of Due Date, however the Late Date Report reflects a due date and a late date based on the past completion dates.6.4.9 The applicable Discipline Supervision (or designee) must notify the Surveillance Program Coordinator or the Scheduling Supervisor of the completion status of surveillances before exceeding the NRC LATE date.a. If a surveillance required in the current mode cannot be performed, a Late Surveillance Notification Form (Attachment V) is required if the NRC LATE date will be exceeded.

It is the responsibility of the Discipline Supervision to ensure the form has been submitted. Exceptions are: (1) Surveillances which will exceed or have exceeded their NRC LATE date but are not required to be performed in the existing Plant Mode (including IST cold shutdown surveillances) (2) Surveillances that are "Non Tech Spec" (3) Weekly surveillances performed before NRC LATE date but not received by the Surveillance Coordinator (4) Operations surveillances that are Tech Spec"Unacceptable" provided Step 6.8.6d is performed.

b. A LCO must be issued for each surveillance requiring a late Surveillance Notification Form. A copy of the LCO report must be attached to the Late Surveillance Notification Form.6.4.10 Expired surveillances (surveillances which have exceeded their NRC LATE date but are not required to be performed in the existing Plant Mode) must not be rescheduled in WMS until after they have been performed acceptably.
a. The WMS NRC LATE Date Report should list the above as NRC LATE and is the responsibility of the Surveillance Coordinator to track.b. The purpose of expired surveillance tracking is to ensure entry into a Plant Mode is not made unless surveillance requirements have been met and there is no reliance on equipment for which surveillance requirements have not been met.c. A report may be generated showing which surveillances required in the next anticipated mode are past their NRC LATE date.J:\ADMSRVS\TECHPUB\REVISION\l\IS0612.DOC GRAND GULF NUCLEAR STATION ADMINISTRATIVE PROCEDURE Title: GGNS Surveillance Program No.: 01-S-06-12 Revision:

109 Page: 24 6.4.11 It is the responsibility of the Discipline Supervision to track their expired surveillances not tracked by the WMS.6.4.12 Addition of new Surveillances or changes to existing Surveillances will be accomplished by the guidelines of 01-S-17-1i, Preventive Maintenance Program.6.5 Assembly, Review and Sign-on of Surveillance Packages 6.5.1 All WMS scheduled surveillance tasks must be performed per a Surveillance-WO or appropriate records attached to a Surveillance-WO. (Surveillance retests are not required to have a Surveillance-WO if the entire procedure is not rescheduled.) 6.5.2 Each Discipline Supervision (or designee) issues Surveillance-WOs to their appropriate sections.a. Surveillance-WOs may be issued for any period of time.6.5.3 Discipline Supervision is responsible for: NOTE The Planning and Scheduling Manager is responsible for ensuring Step 6.5.3a is met for maintenance disciplines.

a. Ensuring the latest revision, with all TCNs, is used in compiling the Surveillance Procedure Work Order Package.b. Coordinating with Radiation Protection any surveillances which involve work in the Radiological Controlled Area or within a radiological boundary to determine if the work requires an RWP or RP coverage.

Ref: 01-S-08-2, Exposure and Contamination Control.6.5.4 Surveillance Procedure Data Packages are verified correct as follows: a. The person assembling the package must signify that the Surveillance-WO is attached to the correct data sheets by initialing the data package cover sheet.b. The discipline supervisor or designee (Shift Supervisor for Operations) must initial the data package cover sheet to verify requirements of Step 6.5.4a and forward the package to the individual performing the test.NOTE All Surveillance data packages will become QA records whether acceptable or unacceptable. J:\ADMSRVS\TECHPUB\REVISION\I\IS0612.DOC GRAND GULF NUCLEAR STATION ADMINISTRATIVE PROCEDURE ITitle: GGNS Surveillance Program INo.: 01-S-06-12 R evision: 1091 Page: 2 6.5.5 The test performer must be given permission to begin the test by the responsible supervisor (normally the Shift Supervisor) from the releasing organization (normally Operations). For surveillance tasks which require release of plant systems or equipment:

a. The Shift Supervisor should review the applicable Tech Spec LCO requirements, the Impact Statement, the current Plant Operational Condition, the Surveillance-WO Due date/NRC LATE date requirements, and the current plant/system/equipment status as necessary to determine whether or not to authorize start of the surveillance.
b. The Shift Manager/Supervisor alone has the authority to release system and equipment for surveillance testing or to return the system and equipment to service.c. The Shift Supervisor reviews the impact that the surveillance procedure performance will have on safe operation of the plant.d. If permission to start is granted, the Shift Supervisor is responsible for ensuring that the surveillance is logged in the surveillance log.NOTE Shift Supervisor signatures are no longer required on the Surveillance Test Data Package Cover sheets. An Operations SRO will have defined the Control Room Communications requirement for the Surveillance Test and this information will be printed on the WO Cover Sheet. This represents the electronic signature that is releasing the Surveillance Test for performance.
e. N/A the "Permission to begin the test" signature blank until it is removed from the procedure during revision.f. Surveillance procedure steps referring to the 'Permission to begin the test" signature blank should be performed (signed off) based on the WO Cover Sheet "CR Comm Reqd" statement and the performer's knowledge that the required communication took place.g. The test performer circles the appropriate Plant Mode the test is being performed in.h. The actual test start time and date must be logged by the performer on the Data Package Cover Sheet, if required.

GRAND GULF NUCLEAR STATION ADMINISTRATIVE PROCEDURE GRAND GULF NUCLEAR STATION ADMINISTRATIVE PROCEDURE I Title: GGNS Surveillance Program No.: o1-S-06-12 Revision: 109 Page: 25A NOTE If a Surveillance test needs to be performed and the computer (WMS) is off-line, the Surveillance may be performed using only the procedure data package until the WO cover sheet can be printed and attached to the procedure. 6.5.6 For surveillance tasks which do not require release of plant systems or equipment:

a. Permission to start is controlled by the releasing organization's responsible supervisor or senior person on shift.b. If the computer (WMS) is off-line or a terminal and printer is not available, the releasing organization may authorize performance of the surveillance by signing the data package cover sheet and by stamping or writing OFFICIAL COPY on the INFO ONLY copy of the Surveillance-WO.

6.5.7 If permission to start cannot be obtained, the surveillance procedure is retained within the section for rescheduling, providing the NRC LATE date is not exceeded.6.5.8 DELETED GRAND GULF NUCLEAR STATION ADMINISTRATIVE PROCEDURE Title: GGNS Surveillance Program No.: 01-S-06-12 IRevision: 109 1Page: 2 6.5.9 If surveillance procedure contains a listing of Control Room alarms to be initiated during performance of surveillance, the performer should provide a copy of list to the Control Room.6.5.10 The surveillance requirements are typically reviewed in the data base before conversion to a WO. The review will be located on the work package cover sheet in the description section or reference document area. The RP review may be indicated by a statement indicating which RWP to use (or similar). RP need not review each work order generated by the Surveillance once this review is performed unless the scope of that Surveillance-WO is changed.Scope changes to Surveillances will typically be reviewed through the WMS using a Work Request.6.6 Performance of Surveillance Package 6.6.1 All sign-off blocks requiring entry of initials, signature, date or data must be individually marked as required.a. The use of ditto marks, lines or other markings to apply a single sign-off or data to a group of blocks is prohibited except for using a line to write one "N/A" for a group of blocks.b. If the step/requirement cannot be met, a comment number should be recorded on that step and a corresponding comment written on the Data Package Cover Sheet explaining why this step/requirement could be met.6.6.2 The test performer should document any deviation or abnormality found during the test in the Comments section of the Data Package Cover Sheet.6.6.3 If a surveillance test cannot be performed as written, the procedure may be changed in accordance with the Author's Guide Procedure, 01-S-02-3 and this procedure, section 6.2.6.6.4 All TCNs or Temporary Directives that are either written or used during the performance of the surveillance must be referenced on the Data Package Cover Sheet.a. Operations personnel are only required to record TCNs or Temporary Directives, which are written during performance of the surveillance, in the Comment section of the Data Package Cover Sheet.6.6.5 If a problem occurs during the test which cannot be resolved by the test performer, the individual immediately notifies their immediate supervisor.

a. If the immediate supervisor cannot resolve the problem, then the supervisor immediately notifies Shift Supervisor; otherwise, upon resolution of problem, test should continue.b. If immediate supervisor is unavailable, the test performer notifies releasing organization supervisor/Shift Supervisor.

J:\ADMSRVS\TECHPUB\REVISION\l\1S0612.DOC GRAND GULF NUCLEAR STATION ADMINISTRATIVE PROCEDURE Sitle: GGNS Surveillance Program I No.: 01-S-06-12 Revision: 109 1 Page: 27 6.6.6 If a problem concerning a Tech Spec limit occurs during test, test performer immediately notifies releasing organization Supervisor/Shift Supervisor. The following actions are required.-

a. The Shift Supervisor must be notified immediately if operability of required equipment is affected or if Tech Spec out-of-service time will be exceeded.b. The releasing organization Supervisor/Shift Supervisor ensures that the appropriate deficiency reports have been initiated and are listed on the Data Package Cover Sheet.c. The responsible releasing organization Supervisor determines whether the test may continue.6.6.7 If the test cannot continue, the Shift Supervisor must determine the method required to place the system under test in a stable condition (if applicable).

6.6.8 The individual performing the test or the supervisor is responsible for initiating the appropriate corrective action.This includes generation of Work Requests and Condition Reports as required. Refer to section 6.8.2d for additional, specific information related to generation of Condition Reports.NOTE Some Surveillance Procedure Data Package contain a blank for a retest WO # (example: check valve leak tests). This blank may be marked N/A if the surveillance procedure contains Instructions and sign-off blocks for the retest and the retest can be performed before closing the Surveillance-WO. 6.6.9 If corrective action can be performed immediately, the releasing organization supervisor determines if the test can be completed. 6.6.10 If the test is completed successfully, the test performer completes the required sections of the Data Package Cover Sheet.6.6.11 If the corrective action taken or other factors prevent the test completion, the Surveillance work order is returned to the Discipline Supervision. 6.6.12 The Discipline Supervision returns the Surveillance-WO with Data Package to the Surveillance Program Coordinator. 6.6.13 Surveillances which are not performed satisfactorily shall be marked "Unsat" on the Surveillance-WO and not credited by the Surveillance Coordinator until re-performance/disposition of the surveillance, except as noted in 6.6.13a.a. Operations surveillances which have been processed in accordance with 6.8.6d will be updated/credited in the WMS.J:\ADMSRVS\TECHPUB\REVISION\I\IS0612.DOC GRAND GULF NUCLEAR STATION ADMINISTRATIVE PROCEDURE Title: GONS Surveillance Program No.: 01-S-061 Reviion: 109 Page: 28 6.7 Special Requirements

6.7.1 Valve

lineups for Local Leak Rate Tests (LLRTs) will be controlled by section level instructions.

a. Occasionally, due to operational conditions or the need to identify leakage to a particular component, deviation from the standard Local Leak Rate Test (LLRT) valve lineups may be necessary.
b. For this purpose, the LLRT coordinator or responsible engineer may make "pen and ink" changes on a copy of the appropriate valve lineup sheets and shall initial the changes, sign and date the sheets.c. All such changes shall be reviewed for the LLRT program by a qualified technical reviewer who shall initial the changes and sign and date the sheets for technical review.d. The marked-up sheets shall be attached to the LLRT data package.NOTE Section 6.8.3g is a special exception to Section 6.7.2 following maintenance that is intended to change the performance of a valve.6.7.2 A valve stroke time that is longer than Maximum Acceptable Stroke Time (but not longer than Limiting Value of Full-Stroke Time) OR shorter than Minimum Acceptable Stroke Time is classified as Evaluation Required (IST Acceptance Criteria).
a. The Shift Supervisor is notified immediately if a valve is classified as Evaluation Required.b. The Shift Supervisor determines if a second test of the valve is to be authorized.

(1) The test performer documents a second test of the valve on a second Data Package.(2) The test performer must perform the second test as soon as practical OR have the valve declared Inoperable and initiate a CR as soon as it is obvious that the second test will not be performed. J:\ADMSRVS\TECHPUB\REVISION\I1\IS0612.DOC GRAND GULF NUCLEAR STATION ADMINISTRATIVE PROCEDURE Title: GGNS Surveillance Program No.: 1-S-012 vision: 109 Page: 29 6.7.2 (Cont.)c. If a second test is performed, the Shift Supervisor initiates a Condition Report (CR) to analyze the valve's performance. NOTE here is no required time limit per OMa-1988 for completion of the analysis requested per step 6.7.2.c if the second test results are Acceptable, however, the analysis should be completed as soon as practical.

d. If the results of the second test are acceptable per the surveillance requirements the cause of the initial test shall be analyzed via the CR initiated per Step 6.7.2.c. The valve may be considered operable pending completion of the analysis.e. If the results of the second test are classified as Evaluation Required per Step 6.7.2, the data shall be analyzed within 96 hours after the second test to determine that the new stroke time represents acceptable valve operation.

(1) The valve may be of the analysis.tracking LCO for considered Operable pending completion The Shift Supervisor must initiate a the 96 hour operability period.(2) If the analysis will not be completed within 96 hours OR if the analysis indicates that the valve's performance is unacceptable, declare the valve inoperable.

f. If the results of the second test are classified as unacceptable per the surveillance requirements, declare the valve inoperable.

6.8 Completion

and Review of Surveillance Package 6.8.1 The test performer records date and time that test was completed on Data Package Cover Sheet.6.8.2 The test performer performs an initial review by completing Section 3.0 of the Data Package Cover Sheet.a. This initial review is not to determine if the system/equipment meets Tech Spec operability requirements.

b. This review categorizes the procedure steps such that other reviewers can determine operability and actions required.c. If there is difficulty in evaluating the results, the responsible discipline supervisor should be contacted.

J:\ADMSRVS\TECHPUB\REVISION\l\IS0612.DOC GRAND GULF NUCLEAR STATION ADMINISTRATIVE PROCEDURE Title: GGNS Surveillance Program No.: 01-S-06-12 Revision: 109 Page: 30 6.8.2 (Cont.)d. The following conditions require generation of a Condition Report in accordance with Corporate Procedure EN-LI-102, Corrective Action Process.* As Found Data Unacceptable" As Left Data Unacceptable" Tech Spec Data Unacceptable" IST Acceptance Criteria Unacceptable, in the Alert Range or in the.Required Action Range" Valve Data Unacceptable or noted as Evaluation Required Other information, such as observations or any unexpected or unusual conditions may be documented in a Condition Report at the discretion of the department performing the Surveillance activity, based on the requirements and guidelines provided in EN-LI-102. 6.8.3 The test performer should use the following guidelines in completing Section 3.0 of the Data Package Cover Sheet: NOTE Each Surveillance Procedure Data Package Cover Sheet is modified during procedure preparation in order to match the specific procedure; thus, some items discussed here are not applicable to some procedure data packages.a. Procedure Completion -Entire vs. Partial (1) If all steps associated with the data package were performed, check "entire procedure completed". (2) If, for any reason, all steps are not completed, check"partial procedure completed". Reason may include: (a) Computer out of service does not allow checking non-essential computer points.(b) Surveillance procedure is used as a retest for one item and all steps do not need to be performed.(c) Equipment is inoperable making completion of test impossible.(d) Plant SCRAM occurs during test.(e) Test performance is administratively stopped.b. As Found Data Acceptability (1) If any of the recorded "As Found" data does not fall within the allowable min/max limits as specified in the procedure, check "Unacceptable." J:\ADMSRVS\TECHPUB\REVISION\l\IS0612.DOC GRAND GULF NUCLEAR STATION ADMINISTRATIVE PROCEDURE Title: GGNS Surveillance Program No.: 01-S-06-12 I Revision: 109 1Page: 31 6.8.3 (cont'd)c. As Left Data Acceptability (1) If any of the recorded "As Left/Final" data does not fall within the allowable min/max limits as specified in the procedure, check "Unacceptable".

d. Tech Spec Acceptance Criteria (1) Tech Spec Acceptance Criteria are identified in the procedure with a dollar sign ($) or clearly identified in the procedure/data package as a Tech Spec item.(2) If any Tech Spec step cannot be performed acceptably, check "UNACCEPTABLE".

(3) If any As Found Tech Spec Data does not meet Tech Spec Limits, check "UNACCEPTABLE". (4) If any Final Tech Spec Data does not meet Tech Spec Limits, check "UNACCEPTABLE".

e. IST Acceptance Criteria (1) IST Acceptance Criteria to satisfy ASME/ANSI OMa-1988, Parts 6 and 10, Ref. 3.30 for Inservice Testing of pumps and Valves are identified in the procedure with an "I".Reference CEP-IST-4, ENS standard on In-service Testing, for additional information.

(2) Pump data is generally classified into the following areas.(a) Acceptable -for values found that are within the surveillance procedure acceptable range with no corrective action required, check "Acceptable" (b) Unacceptable -if any "I" steps cannot be performed acceptably OR if any IST data falls within the surveillance procedure Alert Range or Required Action Range, check "Unacceptable".(c) Alert Range -values found that require frequency of testing to be increased until the cause of the deviation has been determined and the conditions corrected.(d) Required action range -values found that require the pump to be declared Inoperable until the cause of the deviation has been determined and the condition corrected. J:\ADMSRVS\TECHPUB\REVISION\l\IS0612.DOC GRAND GULF NUCLEAR STATION ADMINISTRATIVE PROCEDURE Title: GGNS Surveillance Program No.: 01-S-06-12 Revision: 109 Page: 32 6.8.3 (cont'd)(3) Valve data is generally classified into the following areas: (a) Acceptable -for values found that are within the surveillance procedure acceptable range with no corrective action required, check "Acceptable". NOTE If applicable, check both "Unacceptable" and"Evaluation Required".(b) Unacceptable -if any "I" steps cannot be performed acceptably OR if any IST data does not meet the surveillance procedure acceptable range or is not classified as Evaluation Required, check"Unacceptable".(c) Evaluation Required -if this classification is used per Step 6.7.2, check "Evaluation Required".

f. All Other Steps/Data Acceptability (1) All other steps/data not already evaluated should be reviewed.(2) If any step not previously evaluated was not performed successfully or any data is not acceptable, check"Unacceptable".
g. Pump or Valve Acceptability after Maintenance (1) When a pump or valve is to be inservice tested as a retest/baseline following maintenance, which was deliberately planned and intended to change one or more IST reference values used to calculate performance limits contained in a surveillance procedure, the preprinted acceptance limits in the surveillance data sheets no longer represent the current pump or valve performance and are obsolete and invalid. They may be ignored when evaluating the performance of the pump or valve.(2) The Operations retest in-service test results that meet the acceptance requirements of the maintenance or engineering document under which the work was performed may be accepted and the pump or valve may be declared Operable, without further review, provided the pump or valve performance meets any and all analytical limits identified for it by ($) in the surveillance procedure.

J:\ADMSRVS\TECH_PUB\REVISION\l\1S0612.DOC GRAND GULF NUCLEAR STATION ADMINISTRATIVE PROCEDURE I Title: GGNS Surveillance Program No.: 01-S-06-12 Revision: 109 1 Page: 33 6.8.3.g (Cont.)(3) Operations will initiate a "WT" in PCRS and assign to Code Programs. Code Programs will determine the new acceptance limits for insertion into the surveillance procedure revision prior to the next scheduled performance of the surveillance. (4) Code Programs will initiate a "WT" in PCRS and assign to Operations for inserting the new acceptance limits into the Surveillance Procedure revision prior to the next scheduled Surveillance performance as determined by 6.8.3.g(3). 6.8.4 Any deficiency documents which are written as a result of the Surveillance test must be identified in Section 4.0 by the test performer or Shift Manager/Supervisor.

a. These documents include Work Request/Work Orders, Condition Reports, and LCO's.b. The documents should be listed whether or not they remain open at the conclusion of the test.c. The Shift Manager/Supervisor must identify any LCO entered due to the test results.6.8.5 The test performer notifies the responsible releasing organization supervisor who logs the surveillance out of the log and completes the approval portion of the Data Package Cover Sheet(Section 5.0).6.8.6 The Shift Supervisor/Manager reviews the results of the surveillance and determines whether the results are acceptable based on Tech Spec operability requirements.

The following, as a minimum, must be reviewed: a. If "Partial procedure completed" is checked, steps not completed must be reviewed to determine if they affect surveillance requirements or operability. (1) If computer points (not required for Tech Spec operability) are not tested in a calibration due to computer availability problems, the use of these points for daily channel checks should be restricted.

b. If "Tech Spec Acceptance Criteria," "IST Acceptance Criteria," or "All other steps/data" are marked Unacceptable, the specific steps/data should be reviewed to determine whether Tech Spec surveillance requirements are affected.c. Tech Spec Operability Requirements

-Acceptable/Unacceptable must be marked based on whether the test as performed meets the Technical Specifications surveillance requirements for operability (including IST, Technical Specification 5.5.6).J:\ADM_SRVS\TECHPUB\REVISION\I\IS0612.DOC GRAND GULF NUCLEAR STATION ADMINISTRATIVE PROCEDURE I Title: GGNS Surveillance Program No.: 01-S-06-12 IRevision: 109 1 Page: 34 6.8.6 (Cont.)d. Operations surveillances that are checked Tech Spec"unacceptable" can be rescheduled/updated in WMS provided all of the following are completed: (1) A LCO is written on each system/component that failed.NOTE This failure could be due to the system/component being inoperative prior to the start of the surveillance. In which case the previously existing LCO will satisfy Step 6.8.6d (1).(2) It is indicated on the LCO(s) that the failed surveillance must be reperformed prior to clearing said LCO; and (3) It is indicated on the "unsat" surveillance the LCO# and that the Step(2) above has been performed. 6.8.7 The Shift Supervisor/Manager must review the deficiency section of the Data Package Cover Sheet and ensure that all documents needed to correct the "Unacceptable" items have been initiated and listed.a. Any LCO entered due to the surveillance test performance must be listed in the deficiency section.6.8.8 The Discipline Supervision (or designee) is responsible for reviewing the test results for technical accuracy and adequacy and insuring that the WO completion is posted in WMS.a. Increased frequency testing requirements associated with Tech Specs and ASME/ANSI OMa-1988 (Ref. 3.30) must be identified and scheduled. (1) If increased frequency is warranted, notify the Surveillance Program Coordinator. (2) Submit a Work Request to increase the frequency of the surveillance task or add a new surveillance task for the increased frequency.

b. The Shift Supervisor must be notified immediately of any item found Unacceptable which had previously been called acceptable.

J:\ADMSRVS\TECHPUB\REVISION\I\IS0612.DOC GRAND GULF NUCLEAR STATION ADMINISTRATIVE PROCEDURE Title: GGNS Surveillance Program No. 01-S-06-12 Revision: 1091 Page: 35 6.8.9 If any deviation or abnormality is indicated, the Discipline Supervision (or designee) should review the surveillance data packages for the following:

a. To determine if an error in the surveillance procedure caused the failure or abnormality in the surveillance results, ensure that a TCN or revision is written to correct the error.b. To determine if a defective component caused the failure or abnormality in the surveillance results, ensure that a WO or Condition Report as applicable is written to cover the specific defective component.
c. To determine if defective materials caused the failure or abnormality in the surveillance results, ensure that a CR is written to cover the specific defective component.
d. To determine if the failure or abnormality was caused by personnel not following the procedure, ensure that a CR is written to document the deficiency.
e. If the surveillance marked "partial" and complete credit is taken, ensure performance of all steps required to meet the intent of the surveillance.

NOTE The "Unacceptable/Acceptable/Partial" determinations may not be changed except to correct errors. Additional documentation (e.g. retests) does not change the original unacceptability of data.6.8.10 After review and approval, the Discipline Supervision or designee forwards the original completed work order to the Surveillance Program Coordinator.

a. The original completed Surveillance Work Order package should be forwarded to the Surveillance Coordinator within five working days of the completion date b. Deleted c. On rare occasion, it is not possible to forward a completed work order to the Surveillance Coordinator within the required limit of 5 working days. An example would be if data results were being sent off the site to be analyzed.Discipline Supervision may extend this 5 day time limit by forwarding a GIN memo to the Scheduling Supervisor and Surveillance Coordinator.

The memo shall explain why the Surveillance will exceed the time limit and the date the Surveillance Coordinator can expect to receive the Surveillance work order package. A copy of the Surveillance work order shall be attached to the GIN memo.J:\ADMSRVS\TECHPUB\REVISION\I\IS0612.DOC GRAND GULF NUCLEAR STATION ADMINISTRATIVE PROCEDURE Title: GGNS Surveillance Program No.: 01-S-0 ision: 109 Page: 3 6.8.11 Supervisor, Code Programs or designated Program Engineer must review all surveillance procedures that are affected by IST requirements.

a. The Supervisor, Code Programs or designee must inform the Surveillance Program Coordinator of any increased frequency testing requirements associated with the IST program, Ref.3.26, not already identified.

NOTE The Discipline Supervision of the section which performed the test is responsible for any required corrections. 6.8.12 The Surveillance Program Coordinator notifies the Program Engineer, ANII, or any other departments as deemed necessary of the surveillance test completion via the WMS (computerized system)for the final review, approval, and trending. This review will be accomplished by reviewing the "scanned" work orders in Record Management IDEAS Database and approving in the WMS.6.8.13 The Surveillance Program Coordinator forwards the completed Surveillance-WO packages to Records Management for retention. Processing and handling of surveillance records will be done in accordance with AD-103, Document Control and Records Management Activities.

6.9 Conduct

of Program and System Engineering Reviews I NOTE Post review "hardcopy" signatures on Surveillance Work Orders are not required for System Engineering and Program Engineering. All post review signature lines on hardcopy WOs will be N/A'd until such time each procedure is revised to remove these signature lines.6.9.1 Completed Surveillance work orders are reviewed as followed: a. To ensure that all IST surveillance requirements for in-service testing of ASME Code Class 1, 2 and 3 pumps and valves are met the Surveillance work order is forwarded electronically to the Program Engineer who reviews and approves via the WMS. Any surveillance that satisfies Technical Specification 5.5.6 or TRM 7.6.3.3 should have a Surveillance work order review unless exempted per step 6.2.2a(7). J:\ADMSRVS\TECHPUB\REVISION\l\IS0612.DOC GRAND GULF NUCLEAR STATION ADMINISTRATIVE PROCEDURE Title: GGNS Surveillance Program No.: 01-S-06-12 Revision: 109 Page: 3 6.9.1 (Cont.)b. Documentation and review of unacceptable or unsatisfactory conditions identified by Surveillance work order activities are to be documented via the Corrective Action process in accordance with EN-LI-102. Surveillance work order data packages denoted with unacceptable conditions are required to be documented through a Condition Report by the performing department in accordance with step 6.8.2d of this procedure. Specifically, step 6.8.2d requires generation of a Condition Report per the requirements of EN-LI-102 for any unsatisfactory or unacceptable conditions. Condition Reports are subjected to an Engineering review as required, and as part of the Condition Report screening, review and disposition process per EN-LI-102, therefore, a hardcopy post review signature or electronic WMS approval is not required by System Engineering.

c. Deleted (moved to 6.9.1(a) above.d. Deleted (moved to 6.9.1(a) above.6.9.2 When reviewing Condition Reports generated to document unacceptable conditions or data collected during Surveillance activities, the following guidelines apply: a. If it appears that instrumentation has drifted or exhibited unacceptable behavior, review previous Surveillance activities on the affected instrumentation to determine if License Criteria might be exceeded before the next performance of the Surveillance activity.

Initiate appropriate corrective actions to address the condition and ensure that the corrective actions are scheduled appropriately to prevent exceeding License Criteria.b. Deleted (incorporated in 6.9.2a above)c. Deleted (incorporated in 6.9.2a above)6.9.3 The System Engineer should review surveillance data packages to gather the latest response times to ensure that the total loop time of a system is within Tech Specs. This review may require summing of the individual loop times after part of the loop was individually tested due to component replacement or due to performance of a time response surveillance test on an associated component during its normal surveillance interval.6.9.4 Completed Surveillance Work Order activities which require a Program (IST) Engineer or ANII hard copy signature shall be reviewed and approved electronically in the WMS by the Supervisor, Code Programs or designated Program Engineer by reviewing the"scanned" work order(s) in the Record Management's "IDEAS" database.J:\ADMSRVS\TECHPUB\REVISION\I\1S0612.DOC GRAND GULF NUCLEAR STATION ADMINISTRATIVE PROCEDURE 01-S-06-12 Revision: 109 Attachment I Page 1 of 1 SURVEILLANCE PROCEDURE NUMBERING SYSTEM 06-AA-BCCC-D-EEEE -FF I AA -Responsible Group OP -Operations CH -Chemistry EN -Environmental HP -Health Physics RE -Reactor Engineering IC -Instrument and Control EL -Electrical ME -Mechanical TE -System Engineering FS -Fuel Services B -Unit Number S -Shared 1 -Unit 1 CCC -GGNS System Number (MPL Number)*D.- Surveillance Test Frequency (at least once per time interval specified except as noted in the Surveillance Procedure) S-D -W-M-Q-SA-A-R-V-C-0-12 hours Daily (24 hours)Weekly (7 days)Monthly (30 days)Quarterly (91 days)Semiannually (183 days)Annually (365 days)Refueling (549 days)Variable Cold Shutdown Other (not covered by other designator) EEEE -Surveillance Procedure Number FF -Surveillance Procedure "Attachment" Number*For surveillance procedures which are not GGNS system specific, use "000".J:\ADMSRVS\TECHPUB\REVISION\I\IS0612.DOC GRAND GULF NUCLEAR STATION ADMINISTRATIVE PROCEDURE 01-S-06-12 Revision: 109 Attachment II IPage 1 of 1 SURVEILLANCE PROCEDURE COVER SHEET (Example)Note: Format varies depending on the work discipline. PLANT OPERATIONS MANUAL Volume 06 Section 01 06-OP-XXXX-Q-0001 Revision: 100 Date: SURVEILLANCE PROCEDURE QUARTERLY FLOW RATE TEST SAFETY RELATED Prepared: Reviewed: Approved: Technical Assistant Operations Manager, Support or Shift List of Effective Pages: Pages 1-11 Attachment I List of TCNs Incorporated: Revision TCN 0 None 1 1,2 2 None 3 3 J:\ADMSRVS\TECHPUB\REVISION\l\IS0612.DOC GRAND GULF NUCLEAR STATION ADMINISTRATIVE PROCEDURE 01-S-06-12 Revision: 109 Attachment III Page 1 of 3 SURVEILLANCE PROCEDURE DATA PACKAGE COVER SHEET (Example)SAFETY RELATED Title: Technical Specifications:

1.0 IMPACT

STATEMENT 1.1 Performance of this procedure (1) has no impact on plant operations; (2)results in isolations, half-scrams, etc. The channel may remain out of service for only hours 2.0 PROCEDURE 2.1 Plant Mode is (circle one): 1 2 3 4 5 2.2 Test Start Time: 3.0 TEST RESULTS/!Performer's Signature Date Time 3.1 Test Completion: (Check one in each category.) Entire procedure completed [ ] Partial procedure As Found Data Acceptable [ ] Unacceptable As Left Data Acceptable [ ] Unacceptable Tech Spec Acceptance Criteria Acceptable [ ] Unacceptable IST Acceptance Criteria Acceptable [ Unacceptable

    • IST Acceptance Criteria Evaluation, Yes [ ] No Required All other steps/data Acceptable

[ ] Unacceptable completed[[[[[[]]]]]][ ]* 3.2 TCNs in effect during performance (list): 3.3 Comments: 3.4 Test performed by Date/Time 4.0 DEFICIENCIES CR Issued #________ _____LCO Entered #WO Issued #* This line is not required on Operations Surveillances

    • Applicable to IST valves with stroke time acceptance criteria only.

GRAND GULF NUCLEAR STATION ADMINISTRATIVE PROCEDURE SURVEILLANCE PROCEDURE DATA PACKAGE COVER SHEET (Example) (Continued) SAFETY RELATED 5.0 APPROVAL Tech Spec Operability Requirements Acceptable [ ] Unacceptable Shift Supv/Manager Date Comments: CONCURRENCE Discipline Supervision/Designee Date*EP&C Review is Required*These review statements are required on the data package only if the review is required. These statements are needed to alert the Surveillance Coordinator or designee that these reviews are necessary prior to the WO being sent to Records Management. J:\ADMSRVS\TECHPUB\REVISION\I\IS0612.DOC GRAND GULF NUCLEAR STATION ADMINISTRATIVE PROCEDURE SURVEILLANCE PROCEDURE DATA PACKAGE COVER SHEET SAFETY RELATED Title: Procedure Number: ODCM Specification: IMPACT STATEMENT: Performance of this procedure will have no impact on plant operation. TASK completed satisfactorily by: Signature/Date COMMENTS: REVIEWED: /Chemistry Superintendent or designee Date J:\ADMSRVS\TECHPUB\REVISION\I\1S0612.DOC GRAND GULF NUCLEAR STATION ADMINISTRATIVE PROCEDURE INSTRUCTIONS FOR USING SURVZILLANCE CREDIT VERIFICATION FORM The appropriate responsible discipline reviews the Surveillance Credit Verification Form and verifies Steps 1, 2, 3 and 4 are correct.1. Check appropriate box.2. List all documents (e.g., WO, TSTIs, etc.) used to satisfy applicable Technical Specifications.

3. List Surveillance Procedure/PMID-RQ Number for which credit is to be taken. Use a separate form for each Surveillance Procedure/PMID-RQ Number credited.

If all the requirements for the Surveillance Procedure/PMID-RQ have been met and credit may be taken, check "Full Completion". If all the requirements for the Surveillance Procedure/PMID-RQ Number have not been met and credit cannot be taken for the entire Surveillance Procedure, check "Partial Completion" and list the specific requirement(s) met under the "COMMENTS" section.4. List all Technical Specifications which have been satisfied that are applicable to this credit. If all the Technical Specifications are not entirely met, provide details (attach additional sheet(s)). The Tech Reviewer completes Steps 5, 6, 7 and 8.5. The Tech Reviewer should initial if the test method used complies with appropriate Quality Programs controls and complies with governing documents.

6. Self explanatory; Tech Reviewer should initial.7. List the date that the Technical Specifications surveillance requirements were met (date performed).

Tech Reviewer should initial.8. Tech Reviewer's comments (if any).9. All signatures are required for credit. Section superintendent is the superintendent of the discipline that the requirement(s) is assigned (e.g., for an electrical requirement, the Electrical Superintendent signs). The Scheduling Supervisor or designee should sign last.J:\ADMSRVS\TECHPUB\REVISION\l\1S0612.DOC GRAND GULF NUCLEAR STATION ADMINISTRATIVE PROCEDURE 01-S-06-12 Revision: 109 Attachment IV Page 2 of 2 SURVZILLANCE CREDIT VIRIFICATION FORM TO: Scheduling Supervisor/Surveillance Coordinator

1. FROM: 13 Chemistry and Rad/Con Supts 03 Mechanical Supt o3 Electrical Supt 13 Assistant Operations Manager, Support

SUBJECT:

Surveillance Credit 2. CREDIT DOCUMENT(S): 0l I&C Supt 13 Other 3. SURV PROC/PMID-RQ NUMBER TO BE CREDITED: El Full Completion -(Step #7 Required)E3 Partial Completion (WMS Update Not Required)4. APPLICABLE TECHNICAL SPECIFICATIONS: The Tech Reviewer completes Steps 5, 6, 7 and 8 below.5. The testing method used was consistent with established Surveillance test requirements and methodology.

6. The applicable Technical Specifications and any definitions associated with these Technical Specifications have been satisfied verbatim.7. Surveillance Credit for Full Completion Date 8. COMMENTS: 9. Approval: Prepared By D_Technical Review D_Discipline Supervision/Supt.

D_Scheduling Supervisor D Initials ate ate ate ate J:\ADMSRVS\TECHPUB\REVISION\1\IS0612.DOC GRAND GULF NUCLEAR STATION ADMINISTRATIVE PROCEDURE 01-S-06-12 Revision: 109 Attachment V Page 1 of 2 INSTRUCTIONS FOR USING LATh SURVEILLANCE NOTIFICATION FORM 1. Discipline Supervision or designee fills out all fields involving the late surveillance and signs approval.2. LATE SURVEILLANCE NOTIFICATION FORM is then hand delivered to the Scheduling Supervisor for concurrence.

3. The Scheduling Supervisor hand delivers approved and concurred form to Surveillance Program Coordinator.
4. Explanations of the fields are as follows: PROCEDURE
  1. Procedure number of late surveillance ST/PMID-RQ
    WMS PMID-RQ number of late surveillance SCHEDULED DUE DATE: Current WMS DUE date SCHEDULED NRC LATE DATE: Current WMS NRC LATE date TECHNICAL SPECIFICATIONS
    Tech Spec that surveillance implements LCO #: Required LCO(s) that has been written against late surveillance Ref Step 6.8.6d. A copy of LCO(s) must be attached to the Late Surveillance Notification Form.WO #: Any WOs listed that affect late surveillance JUSTIFICATION:

Brief explanation for surveillance exceeding late date and justification of why it was allowed.SCHEDULING INSTRUCTIONS TO ENSURE TECH SPEC COMPLIANCE: Any scheduling instructions that will be needed to ensure Tech Spec compliance. If individual requirements need to be scheduled in WMS, procedures may be split apart and tracked separately provided that the procedure is still on Late Date report.Special notes or comments may be listed in WMS to document scheduling requirements. These should be coordinated with the Surveillance Program Coordinator. ANTICIPATED RESOLUTION DATE: Date on which surveillance can resume regular surveillance interval.COMPLETED BY: Person filling out form must sign and date.5. This form is not to be routed in company mail; it must be hand delivered.

6. Discipline Supervision/Supt.

or designee must sign approval.J:\ADMSRVS\TECHPUB\REVISION\I\IS0612.DOC GRAND GULF NUCLEAR STATION ADMINISTRATIVE PROCEDURE TO: FROM: LATE SURVUILLANCE NOTIFICATION FORM Scheduling Superintendent/Surveillance Coordinator 03 Chemistry and Rad/Con 0 Mechanical O3 Operations O3 Electrical o Other o3 I&C

SUBJECT:

PROCEDURE SCHEDULED SCHEDULED TECHNICAL Surveillance to exceed NRC LATE "late" date#: ST/PMID-RQ

  1. DUE DATE: NRC LATE "late" DATE: SPECIFICATIONS
    LCO #: (A Copy of LCO(s) must be attached to this form)WO #: JUSTIFICATION:

SCHEDULING INSTRUCTIONS TO ENSURE TECH SPEC COMPLIANCE: ANTICIPATED RESOLUTION DATE: COMPLETED BY: APPROVAL: Discipline Supervision/Supt. CONCURRENCE: Scheduling Supervisor Date Date Date 0 J:\ADMSRVS\TECHPUB\REVISION\I\1S0612.DOC GRAND GULF NUCLEAR STATION ADMINISTRATIVE PROCEDURE SURVEILLANCE PROCEDURR REVIEW CHECKLIST PROCEDURE REVIEWED: CHECKLIST COMPLETED BY: Signature Date NOTE Use this checklist to provide guidance in writing and reviewing surveillances. The list contains a mixture of procedural requirements and common mistakes encountered in the rewriting of surveillance procedures. Do not check N/A unless statement does not apply to procedure. Throughout the body of this procedure the word "Technical Specification" (Tech Spec or TS) is synonymous with "Technical Requirements Manual" and"Offsite Dose Calculation Manual." Cover Sheet and Concurrence Sheet 1. Are the procedure revision and TCN lists correct?2. Are the Tech Specs listed correct and complete?3. Do the Tech Specs referenced on the procedure cover sheet reflect the RPTS requirements that are taken credit for by the procedure? (Only Tech Specs that cover the Purpose of the procedure should be listed on cover sheet.)4. Have reasons for major changes been identified on the RPTS Sheet under Current Revision Statement?

5. Has the Safety Evaluation Applicability Review been done?Procedure Section 1 through 6 1. Are the Tech Specs listed in Section 1 correct and complete?If the procedure does not contain any Tech Spec setpoints or allowable values, then there should be a statement such as: "The Technical Specifications do not specify any setpoints or allowable values for this test. Therefore, satisfactory completion of this procedure fulfills the requirements of Technical Specification

." (This applies to I&C Procedures only.)2. If test equipment has been added or deleted, does Section 3 reflect this? (Also ensure any new test equipment has an accuracy consistent with the enqineerina reauirements YES N/A NO/-//////II////II 1/////I/// //for the application.)

3. If steps have been changed or deleted, are the Precautions and Limitations, Section 2, and the Prerequisites and Plant Conditions, Section 4, still adequate?4. If the procedure satisfies a portion of Logic System Functional Testing (LSFT) requirements and steps have been changed or deleted, are the LSFT requirements still met (Ref 17-S-01-11)?(This determination should be coordinated with System Engineering.)

System Engineering Concurrence I1 1/ I//I/ */ II/Engr Initial/Date J:\ADMSRVS\TECHPUB\REVISION\I\IS0612.DOC GRAND GULF NUCLEAR STATION ADMINISTRATIVE PROCEDURE 01-S-06-12 Revision: 109 Attachment VI Page 2 of 4 5. If MOVs are cycled during the test, are the Thermal Overloads placed in force?6. Is there a $ for the test switch annunciator or status light that shows the Thermal Overloads are bypassed?7. If any Tech Spec Acceptance Criterion, $ or I has been deleted, is there a legitimate reason for the deletion?B. Is there a $ in the Data Package for each $ in the body of the procedure and vice versa?9. Is there an I in the Data Package for each I in the body of the procedure and vice versa?10. Are all bi-stable devices verified Operable by observing that they will change state and also that they will return to their previous state? (If one state is $, then the other state should be $ also.)11. Are all device functions (i.e., trip, alarm, channel failure) verified Operable before the loop is cali-brated? (There should be a $ on both states.)12. Are the "As Found" conditions and/or values recorded before any actual calibration takes place?13. Is there a Data Sheet I sign-off for each # in the body of the procedure and vice versa? (Only critical steps requiring sign-offs on Data Sheet I require a #in body of procedures.)

14. If the procedure references a Data Sheet (e.g.,"See Data Sheet I," "Record on Data Sheet II") does the Data Sheet correctly reflect the step? (These steps do not require a # in the body of the procedure.

For steps requiring data entry on a data sheet, ensure there is a place to record the data.)15. If test equipment is installed, is there a sign-off to verify removal? (A sign-off is not required to install the test equipment if it does not require a hardware modification.)

16. If changes in drawings or other references in Section 6 affect the contents or commitments in the procedure, are the revision numbers for those references updated?17. Are the Tech Spec triggers labeled per Step 6.2.1 of 01-S-06-12?
18. Have the procedure changes affected the requirements of NUREG 0588 (Reference 07-S-01-227)?

Has Section 1.0 been revised to indicate the procedure implements NUREG 0588 requirements? YES N/A NO// /1 ///I/ /I / I/// // /I II /I //// II I/// /I //// // //// /I //// // //// II //// 1/ II/I 1I /1// // /1/I II //J:\ADMSRVS\TECHPUB\REVISION\1\lS0612.DOC GRAND GULF NUCLEAR STATION ADMINISTRATIVE PROCEDURE 01-S-06-12 Revision: 109 Attachment VI Page 3 of 4 Data Package 1. Are the Tech Specs listed correct and complete?If the procedure intends to satisfy a particular Tech Spec, then it should be listed.Only the Tech Spec satisfied by a particular attachment should be listed on that attachment.

2. Does the title on the Data Sheets relate to the title on the Data Package Cover Sheet?3. Does the Impact Statement adequately cover any inop equipment and/or actions or occurrences that will result from performance of the procedure?
4. Is the Data Package Cover Sheet consistent with GGNS Surveillance Program Procedure 01-S-06-12? (If the procedure does not contain any '$t or Tech Spec accept-ance, then an 'N/A' should be placed in the Tech Spec Acceptance Criteria -Acceptable

-Unacceptable blocks.)5. Do all system modifications have double verification when restored to their normal operating configuration per FSAR 18.1.13 and 18.1.29.1?

6. Do all hardware modifications have double verification when installing and removing (Ref 3.16)?7. If any calibration data has been changed, is the new data correct and documentation available to support the data?8. Are the '$' As Found data compiled and compared to Tech Spec allowable values to document Tech Spec compliance?

There should be a place for initials to signify compliance and a place for initials to notify the Shift Supervisor if not in compliance. Only Scheduling Supervisor approved methods may be used as exceptions.

9. Are the Tech Spec allowable values consistent with the latest Tech Spec? (Check for correct values negative and positive.)

YES//////////////////N/A NO// //// ///I II II //// ///I //// 1/// //// //II II 10. If pump or valve reference values (i.e., valve / /stroke time, pump discharge press) are changing, has Supervisor, Code Programs (Design Engineering, Engineering Programs and Components Group) approved the new reference values?11. Are the Tech Spec triggers incorporated per Step 6.2.1e of 01-S-06-12? II II /I J:\ADMSRVS\TECHPUB\REVISION\I\IS0612.DOC GRAND GULF NUCLEAR STATION ADMINISTRATIVE PROCEDURE General 1. Were all step numbers and number values affected by changes checked carefully for typographical errors?2. If changes affect other parts of the procedure or other procedures, have steps been taken to ensure all necessary corrections are made, e.g., step numbers, program changes, device or alarm IDs? Also, generic portions of all procedures and the common portions of the Channel Functional and Calibration procedures should look alike.3. Are the vertical lines (rev bars) by all the changes except page numbers, revision numbers, changes to the cover sheet and RPTS Form, and other exceptions per 01-S-02-3?

4. Was a revision justified, i.e., did it make the procedure better or did it make necessary corrections?

List any changes that are not justified. YES N/A NO II II II II II II I, 5. Does the procedure still adhere to the applicable Tech Spec definition(s) for a test of this type?6. Does the procedure still satisfy the applicable Tech Spec(s) as originally intended?7. If changes have been made that would affect the WMS data base (e.g., scheduling changes, Tech Spec references), has Attachment V been completed and approved to update WMS?8. If the change(s) to this procedure could affect any Operations procedures (e.g., 101, SOI, ARI, EOI), have steps been taken to ensure necessary changes have been made to the applicable procedures? List any changes and/or procedure numbers./I II////// // //// // //9. Does the procedure ensure IST Acceptance Criteria (CEP-IST-4, Ref. 3.13, and IST Program, Ref. 3.25) is met?10. If a change deletes any Technical Specification requirement, have steps been taken to ensure that this requirement is met elsewhere before this revision is issued?NOTE This step is N/A for editorial changes.11. If changes to this procedure have been made that could affect an ASME Section XI (Class 1,2, and 3) pressure retaining item, have the changes been screened for ASME Section XI requirements in accordance with Attachment III of CEP-R&R-001 and the specified requirements included in this procedure. II// I/// // //1/ // 1/J:\ADM_SRVS\TECHPUB\REVISION\1\IS0612.DOC}}

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