Rev 10 to Procedure HNP-1-3980-M, Seismic Instrumentation Functional Test & CalibrML20108E074 |
Person / Time |
---|
Site: |
Hatch ![Southern Nuclear icon.png](/w/images/1/14/Southern_Nuclear_icon.png) |
---|
Issue date: |
06/13/1984 |
---|
From: |
GEORGIA POWER CO. |
---|
To: |
|
---|
Shared Package |
---|
ML20100P367 |
List: |
---|
References |
---|
HNP-1-3980-M, NUDOCS 8412140183 |
Download: ML20108E074 (11) |
|
Similar Documents at Hatch |
---|
Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20212J2721999-10-0101 October 1999 Proposed Tech Specs,Modifying DG Fuel Oil Storage Requirements ML20210G2971999-07-29029 July 1999 Proposed Tech Specs LCO 3.1.7 Re Standby Liquid Control Sys ML20210A4041999-07-15015 July 1999 Ei Hatch Nuclear Plant Unit 1,Extended Power Uprate Startup Test Rept for Cycle 19 ML20204J6031999-03-19019 March 1999 Ei Hatch Nuclear Plant Unit 2 Extended Power Uprate Startup Test Rept for Cycle 15 ML20203C5931999-02-0505 February 1999 Proposed Tech Specs Pages Revising TS to Implement Previously Approved Generic Changes ML20199J9081999-01-21021 January 1999 Proposed Tech Specs Increasing Allowable Values for Reactor Bldg & Refueling Floor Ventilation Exhaust Radiation Monitors ML20197H5171998-12-0404 December 1998 Proposed Tech Specs Section 2.1.1.2,deleting Footnote Which Specifies That SLMCPRs Are for Cycle 18 Only & TS Section 5.6.5.b.2 ML20236U2551998-07-22022 July 1998 Proposed Tech Specs Increasing Allowable Values for High Radiation Trip for Reactor Bldg & Refueling Floor Ventilation Exhaust Monitors ML20217A0861998-04-30030 April 1998 Ei Hatch Nuclear Plant,Units 1 & 2,Process for Implementing Technical Requirements of 10CFR54,License Renewal Rule HL-5558, Edwin I Hatch Nuclear Plant,Unit 1,Power Uprate Startup Test Rept for Cycle 181998-02-17017 February 1998 Edwin I Hatch Nuclear Plant,Unit 1,Power Uprate Startup Test Rept for Cycle 18 ML20197K1861997-12-18018 December 1997 Marked-up Pages to Licenses DPR-57 & NPF-5,respectively. Proposed Changes Delete or Modify Existing License Conditions,Surveillance Requirements That Have Been Completed & Exemptions That Are No Longer in Effect ML20211J1861997-10-0101 October 1997 Corrected TS Pages Unit 1 & 2 Page 3.4-8,Unit 1 Page 3.5-6 & Unit 2 Page 3.5-5 Provided in Order for Util to Issue Amends 208 & 150 to Manual Holders ML20211A2301997-09-19019 September 1997 Proposed Tech Specs Page 2.0-1 & Corresponding mark-up Page Re SLMCPR ML20210J0491997-08-0808 August 1997 Proposed Tech Specs,Allowing Plant to Operate at Uprated Power Level of 2763 Mwt Which Represents Power Level Increase of 8% HL-5438, Ei Hatch Nuclear Plant - Unit 2 Power Uprate Startup Test Rept for Cycle 141997-07-21021 July 1997 Ei Hatch Nuclear Plant - Unit 2 Power Uprate Startup Test Rept for Cycle 14 ML20141B7591997-05-0909 May 1997 Proposed Tech Specs 2.1.1.2,revising Safety Limit Minimum Critical Power Ratio to Reflect Results of Cycle Specific Calculation Performed for Unit 1 Operating Cycle 18,expected to Commence in Nov 1997 ML20141B8561997-05-0909 May 1997 Proposed Tech Specs,Revising Operability Requirements for Rod Block Monitor Sys HL-5376, Proposed Tech Specs 3.4.9 Re Reactor Coolant Sys Pressure & Temp Limits1997-04-29029 April 1997 Proposed Tech Specs 3.4.9 Re Reactor Coolant Sys Pressure & Temp Limits ML20133F3641997-01-0707 January 1997 Proposed Tech Specs Providing Alternate Method of Testing S/Rvs During Shutdown Conditions Rather than During Unit Startup as Is Currently Done ML20138G6271996-12-19019 December 1996 Rev 11 to ODCM for Ei Hatch Nuclear Plant ML20132G2261996-12-17017 December 1996 Proposed Tech Specs Re pressure-temp Limits ML20132E0161996-12-13013 December 1996 Proposed Tech Specs Re Physical Security & Contigency Plan & Guard Training & Qualification Plan ML20135D4881996-12-0303 December 1996 Proposed Tech Specs Revising SLMCPR Values Based Upon Unique plant-evaluations for Current Cycle 13 & Use of GE-13 Fuel in Next Cycle 14 ML20129H9181996-10-29029 October 1996 Proposed Tech Specs,Associating Changes W/Installation of Digital Power Range Neutron Monitoring Sys & Incorporation of long-term Stability Solution Hardware ML20128M8701996-10-0707 October 1996 Proposed Tech Specs to Licenses DPR-57 & NPF-5,increasing Nominal Mechanical Pressure Relief Setpoints for All SRVs & Allow Operation W/One SRV & Associated Functions Inoperable ML20113F5541996-09-19019 September 1996 Proposed Tech Specs,Clarifying Applicability of Certain Surveillances Addressing Rvp & Temp Limits & Replacing Vessel Pressure & Temp Limit Curves W/New Curves ML20117M2251996-09-11011 September 1996 Proposed Tech Specs,Authorizing Southern Nuclear to Become Licensed Operator & to Have Exclusive Responsibility & Control Over Physical Const,Operation & Maint of Plant HL-5192, Edwin I Hatch Nuclear Plant,Unit 1,Power Uprate Startup Test Rept for Cycle 171996-07-18018 July 1996 Edwin I Hatch Nuclear Plant,Unit 1,Power Uprate Startup Test Rept for Cycle 17 ML20115J4861996-07-16016 July 1996 Proposed Tech Specs,Reflecting Changes Through June 1996, Satisfying Requirements of 10CFR50.71 ML20212C1491996-05-31031 May 1996 Stability Monitor ML20117H1391996-05-21021 May 1996 Proposed Tech Specs 3.5.2,ECCS - Shutdown & 3.5.2.2.b SR for Units 1 & 2 Revise to Change Unit 1 CST Water Level Requirement from 12 Feet to 13 Feet & Change Unit 2 CST Water Level Requirement from 12 Feet to 15 Feet ML20100P1041996-03-0404 March 1996 Ei Hatch Nuclear Plant Unit 2 Power Uprate Startup Test Rept for Cycle 13 ML20100H7431996-02-21021 February 1996 Proposed Tech Specs,Revising Changes of Drywell Air Temp LCO from 350 F to 150 F ML20094K3831995-11-10010 November 1995 Proposed Tech Specs,Reflecting Implementation of 10CFR50,App J,Option B ML20093G9401995-10-0505 October 1995 Inservice Insp Program Third 10-Year Interval for Ei Hatch Nuclear Plant Units 1 & 2 ML20092H6461995-07-24024 July 1995 Ei Hatch Nuclear Plant Units 1 & 2 IST Program ML20085K4011995-06-20020 June 1995 Proposed Tech Specs for Power Uprate ML20086E8471995-06-19019 June 1995 Rev 0 to Field Disposition Instruction (Fdi) HT2-0121-12900. Fdi Documents Design Requirements & Matl Required to Install Stabilizers for Shroud Horizontal Welds ML20086E8311995-06-0909 June 1995 Rev 0 to Fabrication Spec 25A5719, Fabrication of Shroud Stabilizer ML20086E8141995-06-0606 June 1995 Rev 1 to Code Design Spec 25A5717, Shroud Stabilizers ML20085A1661995-06-0606 June 1995 Proposed Tech Specs Re Secondary Containment Draw Down & Vacuum Surveillance Requirement Acceptance Criteria ML20086E8121995-05-17017 May 1995 Rev 0 to Design Spec 25A5718, Shroud Repair Hardware ML20082V3791995-05-0404 May 1995 Proposed Tech Specs,Minimizing Thermal Stratification Events ML20082L3331995-04-14014 April 1995 Proposed Tech Specs Re Elimination of Selected Response Time Testing Requirements from TS ML20081F3471995-03-14014 March 1995 Proposed Improved Ts,Permitting Drywell & Wetwell Purge Valves Isolated by Drywell Radiation Monitor Signal to Be Opened W/Inoperable Drywell Radiation Monitor ML20077S0331995-01-13013 January 1995 Proposed Tech Specs Allowing Plant to Operate at Uprated Power Level of 2558 Mwt ML20077D8921994-12-0202 December 1994 Proposed Deleted ETS ML20078G7161994-11-0101 November 1994 Proposed Tech Specs,Converting Current TSs to Improved TS Consistent w/NUREG-1433 ML20076L6911994-10-19019 October 1994 Proposed Improved Tech Specs,Rev F ML20149G3751994-10-13013 October 1994 Proposed Tech Specs,Lowering ATWS-RPT Setpoint by Approx 2 Ft 2 Inches Allowing Restarting Recirculation Pump Following RPT When Temp Differential Between Coolant at Reactor Bottom Head & Reactor Steam Dome Cannot Be Obtained 1999-07-29
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20217A0861998-04-30030 April 1998 Ei Hatch Nuclear Plant,Units 1 & 2,Process for Implementing Technical Requirements of 10CFR54,License Renewal Rule ML20138G6271996-12-19019 December 1996 Rev 11 to ODCM for Ei Hatch Nuclear Plant ML20093G9401995-10-0505 October 1995 Inservice Insp Program Third 10-Year Interval for Ei Hatch Nuclear Plant Units 1 & 2 ML20092H6461995-07-24024 July 1995 Ei Hatch Nuclear Plant Units 1 & 2 IST Program ML20086E8471995-06-19019 June 1995 Rev 0 to Field Disposition Instruction (Fdi) HT2-0121-12900. Fdi Documents Design Requirements & Matl Required to Install Stabilizers for Shroud Horizontal Welds ML20086E8311995-06-0909 June 1995 Rev 0 to Fabrication Spec 25A5719, Fabrication of Shroud Stabilizer ML20086E8141995-06-0606 June 1995 Rev 1 to Code Design Spec 25A5717, Shroud Stabilizers ML20086E8121995-05-17017 May 1995 Rev 0 to Design Spec 25A5718, Shroud Repair Hardware ML20106A6521992-02-29029 February 1992 Proposed Rev 3 to Ei Hatch Nuclear Plant Solid Radwaste PCP, Per GL 89-01 ML20106A6501992-02-0707 February 1992 Rev 7 to Ei Hatch Nuclear Plant ODCM, Reflecting Proposed Changes,Per GL 89-01 ML20056B3031990-08-0101 August 1990 Ei Hatch Nuclear Plant,Units 1 & 2 Inservice Insp Program Second 10-Yr Interval ML20149N1141988-01-0404 January 1988 Revised Second 10-Yr Interval Inservice Insp Program,1980 Edition of ASME Section XI W/Addenda Through Winter 1981 ML20211H5491987-02-20020 February 1987 IGSCC-Susceptible Primary Pressure Boundary Stainless Steel Piping & Components Insp/Mitigation Program, 1987 Maint/Refueling Outage ML20245B8301986-12-10010 December 1986 Rev 0 to SO-OPS-05-1286, Spent Fuel Pool Transfer Canal Gates ML20245B8171986-12-0505 December 1986 Rev 0 to SO-OPS-02-1286, Processing of Water from Yard Drains ML20245B8201986-12-0505 December 1986 Rev 0 to SO-OPS-01-1286, Radwaste Discharges. Supporting Documentation Encl ML20203L9291986-08-0101 August 1986 Rev 0 to Training Procedure 72TR-TRN-002-0S, License Requalification Training Program ML20137V9031985-12-0505 December 1985 Rev 1 to Emergency Implementing Procedure 62RP-RAD-009-05, Airborne Radioactivity Concentration Determination ML20076J1871985-11-0808 November 1985 Rev 2 to Technical Note 20684-EIH, Thermo-Lag 330 Fire Barrier Sys Installation Procedures Manual Prepared for Bechtel Power Corp for Georgia Power Co ML20076J1911985-11-0404 November 1985 Rev 1 to Technical Note 20684-EIH, Thermo-Lag 330 Fire Barrier Sys Installation Procedures Manual Prepared for Bechtel Power Corp,For Georgia Power Co ML20076J1961985-10-23023 October 1985 Rev 0 to Technical Note 20684-EIH, Thermo-Lag 330 Fire Barrier Sys Installation Procedures Manual Prepared for Bechtel Power Corp,For Georgia Power Co ML20135F3161985-08-26026 August 1985 Rev 1 to Emergency Operating Procedures Implementation Plan for Emergency Response Capability Project ML20132E5471985-08-23023 August 1985 Rev 0 to Engineering Svc Procedure 42EN-ENG-011-OS, Scram/ Transient Reporting ML20209F2391985-07-0101 July 1985 Recirculation,Rhr & Reactor Water Cleanup Sys Piping Weld Joint Insp/Mitigation Program for 1985 Maint/ Refueling Outage ML20128A0561985-06-25025 June 1985 Inservice Insp Program,1980 Edition of ASME Section XI W/Addenda Through Winter 1981 ML20126E8331985-06-11011 June 1985 Emergency Plan Implementing Procedures & Deleted Title Sheets,Including Procedures HNP-8007 Re Decontamination of Clothing & Hats & HNP-8004 Re Dosimetry Issuance & Tracking ML20116D4401985-04-23023 April 1985 Revised Emergency Procedures HNP-8109 Re Continuous Air Monitors Models AM-3D & AM-33-1,HNP-8122 Re Radiation Monitor Model RM-16 & HNP-8146 Re Rascal Portable Rate Meter-Scaler/Model PRS-1 Operation & Calibr ML20245B7911985-04-17017 April 1985 Rev 0 to 10AC-MGR-04-0, Deficiency Control Sys. Supporting Documentation Encl ML20107G1421985-02-15015 February 1985 Revised Emergency Implementing Procedures,Including Rev 3 to HNP-8161 Re Eberline Model PCM-1 Portable Monitor Operation & Calibr & Rev 2 to HNP-8036 Re Waste Classification & Manifest Reporting Resin Shipments ML20215F7371984-12-26026 December 1984 Rev 1 to Administrative Control Procedure 40AC-FPX01-0, Fire Protection Program. Portions of Procedures 34AB-OPS-056-1S & 34AB-OPS-056-2S Encl ML20101B0551984-12-17017 December 1984 Rev 5 to Emergency Plan Implementing Procedure HNP-8134, Whole Body Counter Sys ML20108E0921984-11-29029 November 1984 Rev 10 to Procedure Data Package HNP-1-3980-1, Kinemetrics SMA-3 ML20107H5701984-10-31031 October 1984 Detailed Control Room Design Review Program Plan ML20155C8961984-09-30030 September 1984 Rev 1 to Offsite Dose Calculation Manual ML20155C8841984-09-30030 September 1984 Rev 1 to Solid Radwaste Process Control Program ML20098G3401984-09-30030 September 1984 Offsite Dose Calculation Manual ML20098G3381984-09-30030 September 1984 Solid Radwaste Process Control Program ML20108E0741984-06-13013 June 1984 Rev 10 to Procedure HNP-1-3980-M, Seismic Instrumentation Functional Test & Calibr ML20084H4971984-05-0101 May 1984 Rev 0 to Procedures Generation Package for Emergency Operating Procedures,Including plant-specific Technical Guidelines for Units 1 & 2,plant-specific Writers Guide & Implementation Plan for Emergency Response Project ML20086U4131984-02-29029 February 1984 Vendor Equipment Technical Info Program, Per Generic Ltr 83-28,Section 2.2.2,final Draft ML20087N9101984-01-26026 January 1984 Public Version of Transmittal & Title Page to Deleted Emergency Plan Implementing Procedures,Including Procedure HNP-8031 Re Determination of Specific Activity of Spent Resin & Curie Contents of Liner & 840322 Memo ML20087M7911984-01-25025 January 1984 Public Version of Transmittal & Title Pages of Deleted Emergency Plan Implementing Procedures HNP-8019, Insp of Steel Radwaste Shipping Drums & HNP-8422, Handling & Loading of Chem-Nuclear Cask & 840322 Memo ML20087M9321984-01-20020 January 1984 Public Version of Rev 7 to Emergency Plan Implementing Procedure HNP-8101, Teletector Model 6112B/D Operation & Calibr & Jm Felton 840322 Release Memo ML20081B6731984-01-18018 January 1984 Public Version of Rev 0 to Emergency Plan Implementing Procedure HNP-8161, Eberline Model PCM-1 Portal Monitor & Rev 17 to HNP-8008, Radiation Work Permit & Jm Felton 830307 Release Memo ML20087P0191984-01-13013 January 1984 Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures HNP-8038 Re Waste Classification & Manifest Reporting & HNP-8042 Re Radiological Work Practices & 840326 Memo ML20079H9011983-12-0707 December 1983 Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures HNP-8035 Re Pulmonary Function Screening Program & HNP-8016 Re Shipment of Radioactive Matl ML20093D4881983-10-31031 October 1983 Public Version of Revised Emergency Plan Implementing Procedures,Including HNP-4858, Naturally Occurring Phenomenon & HNP-8108, Pocket Dosimeter Use & Performance Test. W/831031 & 840709 Release Memo ML20108E0491983-10-28028 October 1983 Rev 4 to Procedure HNP-4858, Naturally Occurring Phenomenon ML20080L0651983-10-12012 October 1983 Rev 1 to Procedure HNP-4848, Determination of Extent of Core Damage Under Accident Conditions ML20081L9461983-10-12012 October 1983 Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures HNP-4827 Re Offsite Radiological Environ Monitoring During Emergencies & HNP-4852 Re Offsite Dose Estimation 1998-04-30
[Table view] |
Text
_ .
GEORGIA POWER COMPANY HATCH NUCLEAR PLANT PROCEDURE Seismic Instrumentation F T & C.
PROCEDURE TITLE -
HNP-1-39BO-M PROCEDURE NUMDER Maintenance RESPONSIDLE SECTION SAFETY RELATED ( X ) NON-SAFETY RELATED ( )
a-APPROVED APPROVED REV, DESCRIPTION DEPT, GENERAL DATE 4 MANAGER MANAGER 4
. W._". _ _ _ . . . _
10 Page 9 .___.__/_._. T j 77,fp, y j g gg g. _ _ . .
s 1 _lw
-4_
== . .
JII -
m _
4 g
-mM
-a m
.v.
-e
. .. I' _ . . _ _ . . . _ _ . . _ . _ . _ . _ . _ _ . _ _ . . . _ . _ . _ . _ . _ _ _ . . . .
8412140183 841129 ;
PDR ADOCK 05000321 =
V PDR 0
- - - - - - - - - ------------ -- -------- 2-
_____...__._._.._c _ _ . _ _ . _ _ . - _ . _ . _ . .
M, A
"w" HNP-9 a_. .
m
PHulDUHt NO E. I. HATCH NUCLEAR PLANT HNP-1-3980-M See Title Page mis,uu ~O
~
O See Title Page ceo iaPower A ~ ~ -
i op to SEISMIC INSTRtJMENTATION F.T. &C A. PlJRPOSF
- 1. To provide instrtictions for performing an instrument functiona) test and calibration on the seismic system instrumentation as required by Unit 2 Tech. Specs. Table 3,3,6.2-1 and Table 4.3.6.2-1.
- 2. This procedtire is applicable to instrument listed on Table 1.
NOTE Where required in initial equipment component position verifications, independent verification requires there will be a second person present to accomplish a physical verification and also to initial the steps on the Data Package, For accomplishment of maintenance and starveillance, verification is only required to be completed following accomplishnant of the procedure steps for each indi"idual eqttipment component.
B, FREGIJENCY
- 1. Monthly, as required by the manufacturer
- 2. Once/6 months C. RAFFTY Observe safety procedures outlined in Georgia Power Company, SAFETY, Gection "0".
NOTE Defore removing instrument from service, insure that one of the following instruments are operable:
(1) Free Field Accelerometer (2) Peak Response Spectrum Recorder (3) Peak Accelerograph D. REFERENCES
- 1. H-16319 Seismic Measurement Equipment, Control Panel and Instrumentation
- 2. H-17978 Seismic Measurement Equipment Panel H11-P701 Wiring & External Connection Diagram
- -- ,.o See Title Page E.1. HATCH NUCLEAR PLANT HNP-1-3950-M
~
O d See Title Pace Geo iaPbwerd -
2 of 10
- 3. SX-15198 SMA-3 Acceptance Test
. 4. . SX-15199 Operating Instructions for SMA-3 Strong Motion Accelerograph System
- 5. SX-15201 Operating Instructions for SMP-1 Magnetic' Tape Playback System
- 6. H-27169 Seismic Measurement Equipment System 2L51
- 7. S-40872 Seismic Instrumentation Earthquake Response Manual
- 8. Unit 2 Technical Specifications para. 3.3.6.2, E. FUNCTIONAL. TFST (Kinemetrics SMA-3)
- 1. Inform the Shift Supervisor that the test is to be performed,
- 2. Insert key and turn switch to OFF,
- 3. Put on calibration record using the key switch- Turn the-p key to each position with a positive snap action, U a, Turn the key switch (clockwise) to TEST for 60 - c5 seconds.
- h. Turn ihe key switch (clockwise) to CALIB and hold for 1-2 seconds,
- c. Turn the key switch (clockwise) to NAT FREG and hold for 1-2 seconds.
d Turn the key switch (counter clockwise)-to CALIB and hold for 1-2 seconds,
- e. Turn the key switch (counter clockwise) to TEST and
, hold for 10 - 15 seconds,
- f. Turn the key switch (counter clockwise) to OFF, Wait 15 - 20 seconds for the time delay to reset.
- g. Turn the key switch to OPERATE, Wait 60 - G5 seconds-before proceeding,
- 4. In the 230 KV switchyard remove the upper cover from the T Seismic Trigger and start the SMA-3 by gently blowing or, the vertical starter mass. Allow the system to record
[^;.
V background vibrations until it automatically stops (appnoxiately 10 seconds), Replace the upper cover, Return to.-the control panel H11-P701, The event indicator should be white,
E
~ .,aun -
{
E. I. HATCH NUCLEAR PLANT i+#'-1 -39aO-M -
f See-Title Page e=w ;
wt
- A' 10 i
i See Title Page GeoreiaPower U
~~ -
3 of 10
- 5. Turn key switch to TEST and then back to DFF. This will reset the event indicator to black.- Wait 15-20 seconds for
- the time deJay to reset before proceeding.
NOTE Independent verification of equxpment component position requires there will be two (2) individuals to perform the verifications with both initialling the steps on the Data Package.
G. Replace tape cassette with new cassette. (Independent Verification Required)
- 7. Repeat step E.3 to put calibration record on tape.
- 8. Turn the key switch to OPERATE and remove the key
- 9. Check to see that the event indicator is black.
(Independent Verification Required) p 10. Forward status check tape to I & C supervisor for mailing.
Q (Independent Verification Required)
- 11. Notify the Shift Supervisor that the test is complete.
F. CALIBRATION AND PERIODIC MAINTENANCE
' Refer to l(inemetric SMA-3 OAMP (Guality Assurance Maintenance Program) and to purchase order nimiber PEl+-9803 for the calibration and periodic maintenance to be performed by f(i nemetri c s. The calibration and maintenance will be performed per 1(inemetrics procedures, G. RESTORATION OF BEISMIC INSTRItMFNTATION AND DATA RETRIEVAL
- 1. RESTORATION OF SEISMIC INSTRUMENTATION a,
Wait until tape transports have stopped turning, or yellow ligh-t on Control Panel has gone off. Event indicator should be white.
- b. Perform Calibration Procedure via key switch.
(1) Turn 1(ey switch to OFF, then to TEST. Walt 15 seconds, r
(m) t/
(2) Turn key switch to cal _. For 2 seconds, (3) Turn key switch to NAT. FREG. for a seconds.
~
E AFPHQv4L PROCEDUHE '40 See Title Page E. I. HATCH NUCLEAR PLANT. HNP-1 -M80-M aEamm e can O\- See Title Page GeoreiaPower v
~~
4 of 10 10-(4) Ttirn key switch to CAL. for 2 seconds.
(5) Turn key-switch to TEST for 10 seconds.
(6) Turn key switch to CFF, then to OPERATE.
(7) Wait until tape-transports have stopped turning.
. Event indicator should be black.
- c. Remove and label cassettes one at a time. Information on cassette should include.
-date of removal
-time of removal
-tape transport number (should already be labeled)
-name of individual performing sequance After removing each cassette from its respective tape transport, replace it with another cassette immediately, The new cassette should be labeled with the recorder model and serial number. (Independent
,3, Verification Required)
' ') d. After labeling all cassettes, and each tape transport has a new cassette, repeat Step G.1.b, i.e.,_run a calibration record on the new tapes. SMA-3 system is now ready to record.
- a. Store all cassettes in one location, away from all objects (such as large magnets, etc.) which could affect 1he recorded data, free from excess temperatures and humidity,
- 2. RETRIEVAL OF SEISMIC OATA a, Complete section G.1
- b. Rewind and play back all three channels from each cassette ' rom the beginning to the end of the data (indicated when time marker t. eases) using the SMP Playback System. This~is accomplished as follows:
(1) Insert first cassette in to tape transport. Make sure T-slide is all the way up.
(2) Turn POWER SELECT switch to AC RUN,
-('}
U If AC power has been disconnected or is nnt operational, turn POWER SELECT switch tc GATTERY RUN.
-~ m o- ,.o E. l. HATCH NUCLEAR PLANT HNP-1-3980-M See Title Page *veu o
~
- d~') v See Title Page Geor iaPbwerd ~~ .
5 of 10 (3) Turn-CHANNEL SELECT switch to 1, (4). Turn GAIN FACTOR switch'to 1.
(5) Turn STYLUS switch to ON, (G) Turn CHART DRIVE switch to 25 mm/sec and adjust POSITION and STYLUS HEAT controls, (7) Turn off CHART DRIVE.
(B) Turn TRANSPORT switch to ON, Wait until the " time marker" begins to tick, then turn CHART DRIVE ~to 25 mm/sec.
(9) After time marker ceases to tick, depress the STYLUS DRIVE - CAL switch upward for 2 seconds.
(10) Turn CHART DRIVE TO OFF, (11) Using T-slide on tape-transport, rewind the tape '
q to the beginning.
\j
(12) Rip-off chart paper, Label each record with-exactly the same data written on the cassette from which it was played back plus the channel selected.
(13) Turn CHANNEL SELECT switch to 2 and repeat Steps' (8) through (11),
(14) Turn CHANNEL SELECT switch to 3 and repeat Steps (B) through (11),
(15) Turn TRANSPORT switch to OFF and remove tape,
.D O)
.=. _
APPROVAL PRCCEDURE NO See Title Page E. l. HATCH NUCLEAR PLANT liNP-1-3980-M at ve no Daft
{Q T'r Jd
\ GeoreiaPbwer ~ ~o -
See Title Page v G'of 10 i
-- TARI.F 1 RFISMIC INSTriUMENTATION l.51 -NOO1 Seismic Trigger Switchyard- '
L51-NOO2 Sei smi c Accelecompter- (Rx. Oldg. El. 90') (Unit I)
- L51 LNOO3 Seismic Accelerometer (Rx. Bldg. El. 188') .(UnitLI)
L51 -NOO5 Guismic Accelerometer (Free Field) (Switchyard)
-L51-RGOOA, 8 Seismic Recorder-L53-RGO2 Power Supply L51 -RG01 Sei smi c ' Accel erometer Playl>ack Recorder 2L51 --NO21 Seismic Accelerometer (Unit II Diesel Bldg.)
- p. 2L51-NOO4 Seismic Accelerometer (Unit II Reactor Bldg. El.
() 152' Feedwater Line)-
2L51-NO2O Geismic Accelerometer (Unit II Reactor 01d 9 . El, 87')
)
. v f
, g ,w,--, .,y,y * " - - * -
- 4 WLDURE NO E. l. HATCH NUCLEAR PLANT HNP-1-3980-M See Ts.tle Page % mio,, ,.o om g to 1
( )
See Ts. tie Page GeoreiaPower U al ~ ~o l
7 of 10 1 FIGl3RE 1 SMA9 GTATIJG CHECI( TAPE EXAMPI_E This is an example of steps 4b through 4e sliowing the approximate time intervals in each l<ey switch position, and the characteristic curves proditted by the procedure,
,.c__
_,I
- m. i , Th :
I I , "~ l[' !!;GjW!*
j' llll !i i lj!jl l l jii[~Ijf lph!. iiljl;lli ;jj: ;li l 'i;l;I+
.. .. :.l ll ,1lll l llli ll,illllll 31l l ;4 ;;;,
, - . . Q... . l% ,h.,,j
,a
$.[l, l ;
i;i! l!l. ' !, I[II ;j ; [! ,yi i,ll .- :
i
- i l' !,!? ,1' ; l,p fili 1 i.
i l .[ }
,.. Illi W 1ll ~I it : I. i,i i;
.rF
[I . l;!!
! tjji,1,il ! : :[.;-
r r -
!!ll ir! i ilfl [in.Irj i 1- :l" 1
.: ;i,' !yll :, l 'l ,i llj !,-l~l'; l rj il; prl:
p i;q.;!
l1 lj :lm p;ll !!lI l .i, ;j
. i
- l j
-[ ;j;i -@ li ; # :;';:;4' :o,. ;;I;
- m: S 'l i: ::p.i;yi
-. ... :: n. , : e n: m.!! ;: r, mi Fi r ;qm
[.pli si. Ili !r N;;m q! .; :p: tq. . ;;.
ii. ;;:ry:.
cl' :! p. - ::::,g 1.,
'- .- : : : :li: .o i -
i ... - .- ' l.
! jj :ili: i :3
- = -- - .. :
., ~., . . .
g g:; r.,. ;gl pji ![j; iij l: ;.- :( in: : ,- ;- :- ..
i ;. .:: :;g- : :: :
ql. : w ~. . ' ,;;. .';; i.e-
.ngi:grl:4 3; ::: ;;;: ;;; p- : ;!
l ,l.: ! !! t:il,
.; .!!i , li !,.j:. lit il i!1':;'n.
. .. .. ;:. .: . c8 .:P lei t>:: : li
.i.
.n .. .,
- - . :e :3 ::-- l, np ir -
-i - r- r i N ;' " - m-
- -
- :li !; 0- ::-!; :!!: ,I ::; : ": '!
- - l, . .r .n _'.'s _. lit.. _';l.
- -}
.'.. '3 i!..!:i
' :rl:!i : tl1>:
-ll"l: -:
d,- n.. d.
'te li'.! i .! !!:.
i.h,ll8l; i,l.! Ijji rj.ll
- I .'r T ,
- [I ii. a-l.ji 'Isi ! li ll i P- -- -
.il i!ij j ii iii; ; i;r i-f 8
! ;! llj' qlj' s'[! i 111 lli' !'[;
. i h gp :t,!
i ll 1 ,' i i . i f'- $ .
- P h.l
- l; lil ! i Fii ; i - 4,;; y
.l,t: 'ig ' l'- :
.;g t :::i
- !!.::;- jih ;;j: e;j;jg; il !;i.N 5: '; p
.I n.;: ;: -l:i il1 g,! qr j, I i 18 H; :sf .c ila Og
.: 'i :,.- ,l .: 8 ;: .Il .i
. ll ..
i g "' .i .
r : .I i.S I
_.g .'
. . - . N.j..!!E.4 , E
! I! k.I l0 O!I ! '!l! !! -l!
I!! *r
-'! .O !'
h til i- !l[flh.h. *Ii l h 'iE ! '!!! I 'f *" !!i! d" is,!
!!! !!! l,1lI
- i q r - -
p ') lI -
'" ::: iP i
'Y 4 !E !12 idUd. !! I*l 31! $'
,;!! M !'.i.iiE JS .h} d iUli) 'R 3.!!.!d.liS D'"*idt i i!!!!!"k] i'd'i!'!!i!!ii.
M. . ----- --, .--- . ., , . /." Cl ""'" ?. -C'W5g ."W- "
C""" J.N !?.'e- . .
,----(
Step 4b Step 4c " -
Step 4d Step 4e .
. e= c R '2 sec- >< 2 sec k ,
,2 sec - M 10 sec (s.s)
. - . .- . .m_-- - - - - . . ._
APPROVAL PHOCEDUHE NO See Title Page E. i. HATCH NUCLEAR PLANT HNP-1-39BO-M atm o*~o one 10 T~^
'd Georeia Power m&A ~ ~ " -
Gee Title Page U 8 o f 10 PROCEDLRE DATA PACHAGE DOCIDENT NO: FN M80-1 SERIAL PO: _R10-PPL NO:
RTYPE: .C15.19 XREF:
TOTAL SFEETS: 3 FREGLENCY: _Oncp/6 Mnnths COPPLETED BY:
DATE COPPLETED:
I HAVE REVIEWED THIS DATA PACKAGE FOR COMPLETEPESS AFO AGAINGT ACCEPTANCE CRITERIA IN ACCORDANCE WITH F N -830.
ACCEPTARLE LNACCEPTABLE REVIEWED BY; DATE REVIEWED:
REMARHS:
Page 1 of 3 FNP-1 -M80 R10
\v)
FIGl.lRE @
Page 1 of 3
APmOVAL -
PHOCEDUHE NO E. I. HATCH NUCLEAR PLANT HNP-1-3980-M See T)tle Page ***
out 10 Dd S =. a Title Page Georeia v Pbwer ' * " ~
9 of 10 DATA PACHACF_1 HIPEMETRICS SMA-2 REASUN FOR TEST
< ) SURV., ( ) MR NO. , ( ) OTHER TEST PERFORMANCE
...___ _.___...---_ _ _ .__.._____._...._. ~._....____ .....
STEP NO. COPOITION
- . . _ . . . _ - _ _ ..--_____._- _ =.
COPFLETED BY E.2 Hey Switch to OFF E.3.a Hey Switch to TEST (CW)
E. 3. b Hey Switch to CALIB (CW)
E. 3. c Hey Switch in NAT FREQ (CW)
E.3.d Key Switch to CALIB (CCW)
E.3.e Hey Switch to TEST (CCW)
E. 3. F Hey Switch to DFF (CCW)
E.3 9 Hey Switch to DPERATE es E.4 Event Indicator White (v) . __..___.... __... _......_______________...______ . _...._______..._
SYSTEM RFSTORATION INDEPEtorNT VERIFICATION REGUIRED NOTE In equipment component position verifications, initialling a step on a procedure Data Package shall attest to the accomplish-ment of the procedure step. The step shall be initialed follow-ing step.
completion of each separate step before proceeding to another CONDITION COMPLETED BY VERIFIED BY Check tape cassettes removed.
Event Indicator Black.
Tape cassette replaced.
Event Indicator Black.
Status check tape forwarded to I & C Supervisor.
--_. ________.___..__..__= _ _ _ _ . . . _ . _ _ . . . ...._ ____._.._. .._......_.-
Cover replaced on SMA-3.
...-_..._..-_......_.-_...........__......~ _ . . . _ . _ . . . _ _ _ _ .. . . . . . . . . . . -
Key switch to operate.
(
t HNP-1-3980 R10
'x, A
FIGURE 2 Page a of 3 i
.~ ,
. Apppov g PROCEDUWe NO 9 9 ++ T.itle Page E.' l. HATCH NUCLEAR PLANT- i-INP 3980-M
"* ve "0 DATE -
30
- ;O- ' ceorgiaeowerA -- -
Rau Title Page -
10'of 10 l'
\
- I DATA PACKACF L _1_(CONT,) -
I f'
TEST ' RERATS_ .
( ) A c co:ptabl e ( ; Non-Acceptable, Shif t S'ipervisor Notified
,. -Reason for Non-Ac'ceptance/ Comments b
_CM A E ATBY DATFL_
i I
?
1 Page 7, of 3
' \ HNP-1-M80 R10 FIGt.:RE 2 Page 3 nf 3
- - , , . ._ _ _-._._ _.___ __ _ _ ..._._.___,___._ _ _ _ _ ._..,___._.-._ --_.