ML20247R210
| ML20247R210 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 06/21/1989 |
| From: | PUBLIC SERVICE CO. OF NEW HAMPSHIRE |
| To: | |
| Shared Package | |
| ML20245K651 | List: |
| References | |
| FOIA-89-309 1-ST-22, NUDOCS 8909290208 | |
| Download: ML20247R210 (207) | |
Text
{{#Wiki_filter:- _ - STPD REV 2
.qPENDIx[o r0RM 7 .
SE ABROOK ST AT10N l StartuD Test Procedure Field Change Sheet 1 of 3 Rev.No. 02 Field Change No. of Test No. 1-sT-22 Title. NATI'RAL CIRCULATION TEST Description 0f Change. See s<ces 2 and 3. Reason for. Change: To provide additional instructions renardine references. initial m a<e<nne for cecondarv nlant warnun nnd correct tvnngranMent errorn. Originator /Date 4 '
= ME/O DETERMINATION OF 10CFR50 59 APPLICABILITY
- f. Does this fle!d change. .
^
a Make changes in the f acility as described to the FSAR? Yes _u No D Make changes in procedures as described in the FSAR? Yes 2dNo
- c. Involve tests or experirrents not described in the FSAR? Yes !.dNo
- c. Involve changes to the existing Operating License or require ___ Yes E No additional license requirements?
- 2. IT any of the above questions are answered yll a safety evaluation per NHY Procedure 112!0 is required.
INTENT .U_ NON-INTENT T vpe of Change. Reactor Startup Supervisor Approval- N Date.I~U-b Unit Shif t Supervisor Approval N.E k - Date. h' M SORC Reviea/ N gf 5t31'on Manager Approval V
/h/[d / /
Date Id//d
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8909290208 890926 / PDR FOIA PDR d ) BROCK 89-309
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APPENDIX C.~ STPD REV. 2 FORM 7 SEABROOK STATION Startuo Test Procedure Field Chana_m
-Continuation Sheet ,
Test No. ST-22 Rev. No. 2 Sheet 2 of 3 Fleid Change No. 1
- 1) Section 2.0 - add '2.9 RECAL-89-004 IR Detector Conversion Constants for Core Exposure Tracking During the Low Power Test Programs dated 6/14/89'.
- 2) Step 5.3 - add ' Applicable portions of Starting and Phasing the Turbine Generator per ON1031.02 may be performed *.
- 3) Step 6.2 - change Attachment 9.8 to Attachment 9.7.
- 4) Step 6.3 - change Attachment 9.9 to Attachment 9.8.
- 5) Step 6.6.7 - add "The following conditions support or indicate natural circulation flows 0 RCS subcooling - GREATER TliAN 40 F Steam pressure - STABLE OR DECREASING RCS hot leg temperature - STABLE OF DECREASING Core Exit TC's - STABLE OR DECREASING.
RCS cold leg temperature - NEAR SATURATION TEMPERATURE FOR STEAM GENE 3MOR PRESSURE Loop 7 - INDICATED *
- 6) Step 6.10.1 - replace with " Reduce reactor power by inserting Control Bank D to the point of_ adding nuclear heat then transfer steam demand to the ASDV's.*
- 7) Step 6.10.2 - replace with "Close all MSIV's and verify the MSIV l' bypass valves are closed.'
- 8) Step 6.10.3 - add "A post trip review is not required for this manual trip nor is it desired due to time constraints for reactor coolant pump restart. Operations is to respond by utilizing procedures E0.0, E0.1 and OS1000.11'
- 9) Step 6.10.10 - add ' Bypass around and open MSIV's in accordance with Station operating procedures."
- 10) Step 6.11.5 - change Section 6.7 to Section 6.8.
- 11) Attachment 9.1. page 3 of 3, item 9 - change Attachment 9.8 to Attachment 9.7.
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APPENDIX C' STPD REV. 2 l , FORM 7 SEABROOK STATION j. Startuo Test Procedure Field Channe Continuation Sheet Test No. ST-22 Rev. No. 2 Sheet 3 of 3 Field Change No. 1
'12) Attachment 9.3, page 1 of 1, item B.4 - change Attachment 9.8 to Attachment 9.7: item 7 - add '<5410 F (within 15 minutes restore Tavg>541 0 F or be in Hot Standby within the next 15 minutes)*:
add
- item 10 - Pressurizer pressure < 1975 psig'.
- 13) Attachment 9.7, item 1.- change ST-16 to Reference 2.9:
item 3 - change Attachttent 9.9 to Attachment 9.8.
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^ Appendix B STPD Rev.-2 Form.1' SEABROOK STATION Startup Test _ Procedure 1 -ST- 22 _ Rev. 2 i
Title:
NATURAL CIRCULATION TEST F Prepared by:- R. A. Gwinn Date: J///p/pf DETERMINATION OF 10CFR50.59 APPLICABILITY: m ,
- 1. Does this procedure or revision:
- a. Make changes in the facility as described Yes @ No in the FSAR?
- b. Make changes in procedures as described @ Yes @ No in the FSAR?
- c. Involve' tests or' experiments not described U Yes X No in the FSAR?
- d. Involve changes to the existing Operating -
Yes x No License or require additional license requirements?
- 2. If any of the above questions are answered m ,
a safety evaluation per NHY Procedure 11210 is required. Approval Recommended by: ' de Startup Manager
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3/#//6Y
' D&te Approved: -
t> ' l I9 Statiorr%n@r Date socc.ug N 53
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e;; [e ., 1-ST-22 Rev. 2 ; Page'1 of 12 'l
'SEABROOK STATION
-l i
a STARTUP TEST PROCEDURE
, .. o 1-ST ..
I ?. " , NATURAL CIRCULATION TEST
-Prepared by: R. A. Gwinn 1
SECTION TITLE PAGE. i E* 2 1.0 GBJECTIVE l
' i I
2.0- REFERENCES 2 l 3.0 PREREQUISITES 2- . i 3 4.0 SPECIAL PRECAUTIONS l 1 INITIAL CONDITIONS 4 i 5.0 l 6.0 TEST INSTRUCTIONS 5 7.0 FINAL CONDITIONS 12-12 8.0 ACCEPTANCE CRITERIA 1 I 12 9.0 ATTACHMENTS l l l i l 1 I m:-______-_______________ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
j 4 1-ST-22 Rev. 2 Page 2 of 12
- 1. 'O OBJE.CTIVE This test will determine several natural circulation characteristics and will demonstrate the ability to reaove heat from the reactor coolant The characteristics to be determined system include: using natural circulation. time necessary to stabilize natural circulation; r flow distribution; depressurization rate following loss of pressurizer heaters; depressurization rate using auxiliary spray; effect nf charging flow and steam flow on subcooling margin; subcooling monitor performance.
2.0 REFERENCES
CURRENT TITLE REVISION REVISION NO. 1-ST-1, Startup Program Administration 2-2.1 Seabrook Station Technical Specifications Amend 1 2.2 Precautions, Limitations and Setpoints for the Westinghouse NSSS 2 2.3 Seabrook Station FSAR, RAI Responsa 56 2.4 640.51-4t 6 2.5 ES-0.2, Natural Circulation Cooldown 5th Ed. 2.6 ASME Steam Tables Seabrook Station F5AR, Table 14.2-5, Amend 61 2.7 Item 22 2 2.3 Startup fest Program Description INITIALS /DATE 3-3.0 PREREqu! SITES
/ 3.1 The test director has reviewed the latest revisions of the applicable references to determine if any system changes that have been made will affect the test performance.
/ 3.2 Personnel involved with the performance of this procedure have been briefed on the procedure content and informed of their respective duties.
/ 3.3 The Temporary Modifications Log and Danger Tag Log have been reviewed to identify and correct any items which may restrict the performance of the test.
/ 3.4 Instrument inputs to GETARS is arranged to include those identified by Attachment 9.4, as a minimum, and at a scan rate of less than or equal to 250 millisecond interval. ,
/ 3.S The reactor coolant system flow measurement test, 1-ST-11 has been completed and the RCS flow instrumentation has been adjusted as required.
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1-ST-22' Rev. 2 Page 3 of 12 INITIALS /DATE 3.6 The following systems are available for use:
/ 3.6.1 Station' Computer.
/ 3.6.2 Service Air.
, /- 3.6.3 Instrument Air. l
/ 3.6.4 Circulating Water System.
/ 3.6.5 Main Condenser.
/ 3.6.6 Chemical and Volume Control System (including auxiliary spray).
/ 3.6.7 Steam Dump (including atmospheric relief valves).
/ 3.7 The station Operations Manager and Training Center Manager have been notified of the estimated start of the test, so that as many Operations personnel as possible may witness the test. (See Reference 2.4.)
/ 3.8 The Unit Shift Supervisor has been notified ' hat the test is about to comence.
4.0 SPECIAL PRECAUTIONS g,, , g y.J Q $. , J. to..s /
/ 4.1 The requirements of Technical Specifications 3.4.1.1 or 3.10.4 and the associated surveillance requirements must be adhered to throughout the perfonnance of this test.
/ 4.2 Do not exceed 5% thermal power at any time during this test.
/ 4.3 The nonnal AT and Tava indications will be unreliable during natural circulation conditions. The wide range hot and cold leg indications should be used to calculate these values.
/ 4.4 Cold leg temperature should be maintained at approximately the initial (pre-RCP trip) temperature.or greater than 550*F unless otherwise directed.
/ 4.5 All personnel participating in the test should be aware that the moderator temperature coefficient is near zero and may change sign during the test. This is to reduce reactivity feedback effects related to the moderator tem-perature coefficient.
/ 4.6 Maintain steam generator and feedwater conditions as stable as possible as natural circulation develops.
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- 5. a _ 1-ST-22 Rev. 2
,p .. g { 2] Page 4 of 12 INITIALS /DATE q L L25 $51 9 2.
/ 4.7 Minimize thermal shock on the pressurizer spray nozzle by initiating spray slowly and maintaining a minimum con-tinuous flow once spray is actuated.
/ 4.8 Do not use auxiliary spray if letdown is isolated.
/ 4.9 If a reactor trip occurs' during natural circulation, close the spray valves (RC-PCV-455A and B) and restart Reactor Coolant Pump RC-P-1C "
prior to closing the reactor trip breakers, p wi
/ 4.10 Refer to the manual trip criteria listed in Attachment !
-9.3. Insure that these criteria are available in the '
control room for operator reference. /
/ 4.11 Maintain CS-V177 (Loop 4 alternate charging path) in the
" CLOSED" position throughout the test.
/ 4.12 Charging flow should be constant and at as low a flow $ ate h as possible during this test. t 5.0 INITIAL CONDITIONS .
N
/ 5.1 Reactor power is approximately 3% with rod control in 'V
" MANUAL".
/ 5.2 All reactor coolant pumps are operating.
I
/ 5.3 Steam dump is operating in the pressure control mode and maintaining cold leg temperature at approximately 557'F in manual control. 3.
/ 5.4 The Station computer is operating.
/ 5.5 Pressurizer pressure control and level control are in manual and maintaining pressurizer pressure at approxima-Terf22:5psigandlevelat25%(range 25to30).
/ 5.6 The sttrtup feedwater pump is maintaining steam generator levels at approximately 50% (40-60%) narrow range, through the bypass valves.
/ 5.7 RCS boron concentration and control bank rod positions are configured to establish an approximately zero moderator temperature coefficient. Control Banks should be arranged so that there is at least 150 pcm of inserted rod worth.
c.u vag cer-
/ 5.8 The steam generator atmospheric relief valves are avail-able for use as necessary.
/ 5.9 Secure steam generator blowdown during primary calort-metric test activities.
1-ST-22 Rev. 2 ! Page 5 of 12 l 1 INITIALS /DATE j l
/ 5.10 Start the GETARS data recording for the paramaters iden- l tified by Attachment 9.4. {
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/ 5.11 Place analog points identified by Attachment 9.5 in a pro- ]
cess computer block trend with a one-minute interval. , i 5.12 Place the following analog points in a process computer block trend with a one-minute trend interval.
/ 5.12.1 A0301, Reactor Coolant Loop 1 Flow.
/ 5.12.2 A0304, Reactor Coolant Loop 2 Flow.
/ 5.12.3 A0307. Reactor Coolant Loop 3 Flow.
/ 5.12.4 A0309. Reactor Coolant Loop 4 Flow.
/ 5.13 Close, or verify closed, CS-V177 (alternate charging path) and open, or verify open, CS-V180 (normal charging path).
/ 5.14 Perform, or verify the performance of, each intermediate and power range channel and P-7 interlock analog channel operational test within 12 hours prior to initiating startup and physics tests. Document this review in chronological log. (This will satisfy Technical Specification Surveillance Requirement 4.10.4.1.)
6.0 TEST INSTRUCTIONS
/ 6.1 Parform Reactor Coolant System heat balance per Attachment Y 9.1. ge., y,x %c 7,
/ 6.2 Obtain Intermediate Range Detector Normalization constants determined by ST-16. Calculate Intermediate Range current limits to limit power to 5% per Attachment 9.8, and record on Attachment 9.3. i. -) .3
/ _
6.3 During the performance of this test, ST-22, the thermal 1 power shall be determined to be less than P-7 interlock setpoint at least once per hour. The logging of power ' { 1evel will be performed on Attachment 9.9. See Special
, Precaution 4.1. (This will satisfy Technical Specification Surveillance Requirement 4.10.4.1.) J
/ 6.4 Obtain a core thermocouple (T/C) map at approximately three (3) minute intervals using the Station computer until the end of the stabilization period and continue as directed by the test director. Insure each map is appropriately labeled with the test number, step number, date, time and initials of the person performing the data collection.
1-ST-22 Rev.-2 Page 6 of 12 INITIALS /DATE
/ 6.5 Perform, at approximately ten (10) minute intervals, sub-cooling moniter performance test as directed in Attachment 9.2. This subcooling monitoring will continue throughout the test unless otherwise directed by the test director, or as specified within the test. Coordinate data collec-tion with T/C map data recording.
6.6 Natural Circulation
/ 6.6.1 Simultaneously trip all reactor coolant pumps.
Annotate GETARS and HPC trends and record the time . NOTE: 1) The steam generator levels may shrink slightly before swelling.
- 2) Expected RCS response 15 listed in Attachment 9.3, along with the manual trip criteria.
/ 6.6.2 Place Spray Valve Controllers RC-PK-455B and P;jb RC-PK-455C in " MANUAL", and open (fully) Spray
. Valves RC-PCV-455A and RC-PCV-455B. (0pening jf 'g these valves will allow auxiliary spray flow to JI go to loops 1 and 3, and closing these valves will direct auxiliary spray flow to the pressurizer.)
/ 6.6.3 Adjust charging flow and letdown flow, as required to maintain constant RCS water mass. Maintain pressurizer level control in 'KANUAL'.
NOTE: Pressurizer level can be expected to increase slightly rver 1 percent per degree Fahrenheit change in RCS average temperature. Do not allow pressurizer level to increase above 60%. NOTE: Steps 6.6.4 and 6.6.5 can be repeated, as required to control pressurizer pressure at the direction of the test director. CAUTION: MINIMIZE SPRAY N0ZZLE THERHAL SHOCK BY INITIATIN SPRAY FLOW SLOWLY AND MAINTAINING SPRAY FLUID AT TO LESS THAN 320'F.
/ 6.6.4 If pressurizer pressure exceeds 2260 psig, open Auxiliary Spray Valve CS-V185. Manipulate CS-V185, RC-PCV-455A and RC-PCV-455B, as necessary, to maintain approximately 2260 psig.
/ 6.6.5 If pressurizer pressure exceeds 2290 psig, close charging line valve, CS-V180, and manually throttle close Spray Valves RC-PCV-455A and RC-PCV-455B, as required to maintain pressurizer pressure at approximately 2260 psig.
_ _ _ _ _ _ - _ - _ = _ _ _ _ _ _ _ U;, x y,2
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1-ST-22 Rev. 2. M" Page 7 of 12 if ' , l
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g4 INITIALS /DATE g E / 6.6.6 Maintain the plant at stable conditions while natural circulation stabilizes.-
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/ 6.6.7 Natural circulation should take from 10 to 50- i b minutes to stabilize. Verify plant conditions L i approximatingtheconditionsbelowareobserved..I !
Note characteristics in the chronolog.- -
- a. Constant.AT between wide range hot and cold- ,
I a leg temperatures.
- b. Constant AT between wide range cold leg tem-- l perature and. core exit T/C temperature. j k' c. Wide range hot leg temperature is approxima - M l tely equal to core exit T/C average tempera-ture.
/ 6.6.8 Annotate GETARS and Station computer trends when j stable natural circulation is achieved. Record j
the time and continue recording data for-a minimum i of thirty minutes.
/ 6.6.9 Collect data for Attachment 9.1, Page 3.
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6.7 Auxiliary Spray Depressurization Rate Demonstration
/ 6.7.1 Verify, or adjust as required, so that pressurizer pressure is between 2225 and 2260 psig, and that pressurizer level is stable. ,
/ 6.7.2 Continue to obtain core thermocouple maps approxi-mately every five minutes ano start data trending equipment, as required.
/ 6.7.3 Place the Pressurizer Backup Heater Groups A, B, C ;
and D control switches to the *0FF" position. j i
/ 6.7.4 Place or verify the pressurizer control heater i group control switch is in 'AUT0" position. !
l NOTE: Maintain an accurate log (chronological log) of ! position of Charging 1.ine Valve CS-V180 and Spray. ' Controllers RC-PK-455B and RC-PK-455C.
/ 6.7.5 Open, or verify open Auxiliary Spray Valve CS-V185. If pressure cannot be maintained below 2260 psig with CS-V180 open. mark N/A for Steps 6.7.6 - 6.7.7 and go to Step 6.7.8.
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) - - L 1-ST-22 Rev. 2 Page 8 of 12 INITIALS /0 ATE l CAUTION: MINIMIZE SPRAY N0ZZLE THERHAL SHOCK BY INITIATING SPRAY FLOW SLOWLY AND MAINTAIN SPRAY FLUID AT TO LESS THAN 320*F.
/ 6.7.6 Open, or verify open, CS-V180, and observe pressure response for at least fifteen minutes.
Five minutes into the observation period, close l Spray Valve RC-PCV-455A. When RC-PCV-455A is shut, close RC-PCV-455B, as possible (see note). Annotate GETARS and NPC trends. NOTE: Do not allow pressurizer pressure to drop below approximately 2000 psig. % ,..
/ 6.7.7 Open Spray Valves RC-PCV-455A and RC-PCV-455B and close CS+V180. Allow pressure to recover to a value greater than 2100 psig and stabilize.
Annotate GETARS and MPC trends.
/ 6.7.8 Close RC-PCV-455A and RC-PCV-455B and observe the
. pressurizer pressure response. Annotate the GETARS and Station computer trends.
/ 6.7.9 Position RC-PCV-455A, RC-PCV-455B, CS-Y180 and the pressurizer heater controls, as required, to sta-biltze pressurizer pressure at approximately 2050 psig. Annotate GETARS and MPC trends.
/ 6.7.10 Perform a subcooling monitor performance check as directed in Attachment 9.2.
6.8 Chargina and Steam Flow Effect on Subcooling
/ 6.8.1 Start data trending if stopped and annotate the trends with date, time and section.
/ 6.8.2 Increase pressure and stabilize at approximately 2200 psig using RC-PCV-455A, RC-PCV-4558, CS-V180 and the pressurizer heaters as required. Reduce pressurizer spray flow to a minimum so that charging flow to the RCS loop is maximized.
/ 6.8.3 Perform a subcooling monitor performance check as directed in Attachment 9.2.
/ 6.6.4 Note current charging flow rate ( gpm) and increase charging flow by approximately 15 gpm.
Stabilize the charging flow, then perform a sub-cooling monitor check (Attachment 9.2). Allow approximately 15 minutes to elapse before continoing. (Record actual charging flow rate in the chronolog.) . _ - - . - - J
1-ST-22 Rev. 2 Page 9 of 12 INITIALS /DATE
/ 6.8.5 Increase charging flow an additional 15 gpm.
Stabilize the charging flow, then perform a sub-cooling monitor check. (Attachment 9.2) Allow approximate 1y'15 minutes to elapse before continuing. (Record actual charging flow rate-in the chronolog.)
/ 6.8.6 Reduce charging flow and lower pressurizer level as required. Balance charging and letdown flow.
rates.
/ 6.8.7 Use the pressurizer heaters to stabilize RCS-pressure at approximately 2235 psig, then perform a subecoling monitor performance' check.
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/ 6.8.8 Carefully increase steam dump flow until the RCS average cold leg temperature has decreased by approx 1.mately 5'F. Avoid an excessive increase in steam flow.
NOTE: The 5'F increase in saturation margin is desired, but.is not required for test a:ceptance. Do not decrease cold leg temperature below 550*F. i
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/ 6.8.9 Perform a final subcocling monitor performance check. Obtain the final T/C maps.
/ 6.8.10 Place all pressurizer heater controls in "AUT0" with a 2235 psig setpoint.
6.9 Loss of Pressurizer Heaters During Natural Circulation
/ 6.9.1 Open, or verify open, the norcel charoing supply valve, CS-V180, and close, or verify closed.
Auxiliary Spray Valve CS-V185.
/ 6.9.2 Start the GETARS arid HPCS data trending groups identified in Steps 5.10 and 5.11, as required.
[ __
/ 6.9.3 After approximately ten (10) minutes, secure all pressurizer neaters. Backup heaters to "0FF",
control group to "0FF". Record time , and annotate GETARS and MPCS data trends, as appropriate.
/ 6.9.4 Mark the pressurizer pressure recorder, RC-PR-455, to denote the start of RCS pressure reduction.
/ 6.9.5 Continue to acquire data until one of the following conditions is reached:
1-ST-22 Rev. 2
. i Page 10 of 12 INITIALS /DATE M [p N
/
a) RCS Tavg below 541*F (any WR Tave), b) Pressurizer pressure below 2050 psig (by lowest sensor), c) Pressurizer heaters must be used for any reaso d) Reactor coolant pumps are started due to unplanned or unexpected equipmt:nt conditions. e) One hour (60 minutes) has elapsed.
/ 6.9.6 Mark the pressurizer pressure recorder, RC-PR-455, to denote the end of data acquisition.
/ 6.9.7 Return the pressurizer heater control switches to the configuration desired by the Unit Shift Supervisor. Record the time .
/ 6.9.8 Stop the GETARS and MPCS data trending groups.
Remove MPC trend from logger and mark with test' number, date, time and step sequence. Additional data collection may be desired, and it is at the } discretion of the test director to continue data collection. 6.10 Plant Restoration s
/ 6.10.1 Shut down the reactor t'y fully inserting the i control banks and log the (tode changa.
/ 6.10.2 FJ11y insert the shutdown rods.
/ 6.10.3 Open the reacter trip breakers. Upon opening the breakers, notify I&C to perform 151680.950, P-4 -
voltage testing. -
/ 6.10.4 Open, or verify open, the normal charging valve, CS-Y180, and close, or verify closed, Auxiliary Spray Valve CS-Y-185.
/ 6.10.5 Place pressurizer spray controllers PK-455B and PK-455C in " MANUAL / CLOSED". Operate pressurizer heaters as required to maintain RCS pressurizer at approximately 2235 psig.
/ 6.10.6 When wide range AT is less than 5'F and pressuri-zer 1cvel is stable at 25 to 30 percent, restart Reactor Coolant Pump RC-P-IC in accordance with Station operating procedures.
l
/ 6.10.7 Af ter pressurizer pressure has stabilized, return i Pressurizer Spray Controllers RC-PK-455B and l
RC-PK-455C to "AUT0". ) )
4* ' 1-ST-22 Rev. 2 Page 11 of 12 INITIALS /DATE
/. 6.10.8 Individually restart the remaining reactor coolant pumps in.accordance with Station operating proce-dures.
/ 6.10.9 Stop GETARS and the main plant computer block trends,'if required.
6.11 Data Analysis
.1
/ 6.11.1 Using the data collected during the auxiliary spray test, detemine the auxiliary spray depressurization rate. psi / min.
/ 6.11.2 Using the data collected during natural cir-culation, determine the RCS flow rate using Attachment 9.1, page 3. _gpm.
/ 6.11.3 Record the time necessary to establish RCS natural circulation conditon. ,
minutes.
/ 6.11.4 Using the data collected, determine the depressur-ization rate following the loss of all pressurizer heaters. psi / min.
/ 6.11.5 Section 6.7 has been successfully completed and effects on subcooling have been demonstrated due to changes in charging flow and steam flow.
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/ ~
6.11.6 Review the T/C map data to verify that a uniform core flow distribution existed during natural cir-culation conditions. 7.0 FINAL CONDITIONS
/ 7.1 All reactor coolant pumps are operating.
/ 7.2 Pressurizer pressure and level control are in the mode desired by the unit shift supervisor.
1
/ 7.3 Steam dump is in the header pressure control moda with a j setpoint of approximately 1100 psig.
/ 7.4 The test equipment inputs have been removed from the pro-l cess circuitry, unless required for the next test.
/ 7.5 The Unit Shift Supervisor has been informed that the test is completed.
/ 7.6 All equipment output and computer output has been appropriately labeled and attached to the completed test procedure.
L- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
1-ST-22' Rev. 2 Page 12 of 12 INITIALS /DATE
/ 7.7 A copy of the completed test package has been sent to; the Training Center manager.
/' 7.8 Any controller or_setpoint changes made as_a result of this procedure have been documented on Attachment 9.2 of 1-ST-15, Reactor Plant Systems Setpoint Verification, and have been forwarded to the Station I&C Department.
! 8.0 ACCEPTANCE CRITERIA
/ 8.1 Natural circulation heat removal capability has been demonstrated by maintaii'ing stable RCS~ temperature.
/ 8.2 Incore T/C maps have been Obtained to demonstrate uniform
. reactor coolant flow distribution during natural-cir-culation.
/ 8.3 The depressurization rate using auxiliary spray has been determined, and is approximately psi / min.
(Section 6.7)
/ '
8.4 The effects of charging flow and steam flow on subcooling margin have been exhibited. (Section 6.8)
~~
/ 8.5 The depressurization rate following loss of pressurizer heaters has been determined and is approximately psi / min. _(Section 6.9)
/ 8.6 The ability of the subcooling monitor to display the margin to saturated conditions has been demonstrated.
9.0 ATTACHMENTS 9.1 Reactor Coolant System Heat Balance - Full flow 9.2 Subcooling Monitor Performance Test 9.3 Expected Plant Response and Manual Trip Criteria 9.4 GETARS Natural Circulation Test Data Point Listing t 9.5 Main Plant Computer Analog Data Point Listing 9.6 Test Equipment Data Sheet 9.7 Intermediate Range Current Offset and Power Limit Deter- , mination 9.8 Thermal Power Log
. . Attachment 9.1 1-ST-22 Rev. 2 Page l'of 3L REACTOR COOLANT SYSTEM HEAT BALANCE - FULL FLOW INITIALS /DATE-
/ 1. Start,.or verify started, MPCS analog group trends identified by Step 5.11.
/ 2. Allow RCS tunperature, pressure and reactor power to stablize untti at least one loop T v is i l'F. pressure is 1 5 psi and reactor power. stable minute time interval.!5 0.a%g over a minimum of a ten (10)
/ 3. Record data identified on Attachment 9.1, Page 2. Primary Heat Balance Calculation.
/ 4. Calculate reactor power as shown on the Page 2.
/ 5. Stop-MPCS analog group trend, or continue group trend data collection as directed by the Test Director.
/' 6. Remove the analog group trend from the logger and include it with this attachment.
REACTOR COOLANT SYSTEM FLOW RATE - NATURAL CIRCULATION f_ . 1. Record data identified on AttacNnent 9.1, Page 3. I
/ 2. Perform calculations outlined in this attachment.
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,,Ai J Sachment'9.2 '1-ST-22 Rev. 2 i . 21 of 2 , SUBC00 LING MONITOR PERFORMANCE TEST i A. Test Method:-
- 1. Obtain the-lowest value of indicated RCS pressure. (Analog points)-
- 2. Obtain the highest incore T/C reading. (Main plant computer)
Coordinate with T/C map data collection with subcooling monitor data collection.
- 3. Obtain the displayed value from the subcooling monitor. !
.4. Convert.the gauge pressure to absolute pressure and use the. steam tables ,
to find the saturation. temperature corresponding to this. pressure.
- 5. The saturation margin is the difference between the saturation. tem- :
perature and the incore T/C reading.
- 6. Enter all of these valees on the attached' data sheet (s). j l
l
'l 4
l l'
t, Attac'hment 9.2 1-ST-22 Rev. 2 Page 2 of 2 SUBC00 LING MONITOR PERFORMANCE DATA Step Pressure Saturation T/C Saturation Subcooling Time # Tave Psig Temp Temp Margin Monitor Inits/Date l I
Attachment 9.3 1-ST-22'Rev. 2 _Page 1 of 1 EXPECTED PLANT RESPONSE
. AND MANUAL TRIP CRITERIA A. Expected Plant Response at 3% Power.
- 1. Estimated time to stabilized natural circulation flow: 35 minutes, range'10 to 50 minutes.
- 2. Expected AT: 35'F.
- 3. Expected THoy 590*F.
- 4. Estimated hottest incore T/C: 595-600'F.
- 5. Estimated depressurization rate, 75 gpm auxiliary spray, charging isola -
ted: 10 psi / min. B. Manual Trip Criteria: The test must be terminated and the reactor tripped if any of the following occur:
- 1. Subcooling Margin: < 15'F.
- 2. Core Power: > 5% RTP.
- 3. Forced circulation AT Pwr A0312, A0317 A0322 A0327 (5% as indicated)
- 4. Natural circulation IR-A 7. 0 9 16#(normalized)(DeterminedbyStep6.2 1 IR-B 2.q,5e ic" (nonnalized) and Attachment 9.8.) l na NOTE: . Use the excore detector for power level.and account.for preliminary . .E .
scaling.
- 5. Pressurizer Water Level: < 17% or unexplained decrease of > 5%.
- 6. A T, any loop: > 65'F.
- 7. Tavg: > 585'F.
- 8. Core Exit Temp: > 620*F.
L
- 9. Pressurizer Pressure > 2340 psig.
1 % - I. e n o*S i
~.'-
t _ _ _ _-_-__ _ -_---- _ ---- ----- -____ -----
e l l
, Attachment 9.4 1-ST-22 R eti. 2 Page 1 of 1 ,
GETARS NATURAL CIRCULATION TEST DATA POINTS Channel Device Number Parameter _ Cabinet Location Card Point' 107 LY-501 SG 1 Wr Level C1-0331 Isolated Output 113 NM-303 N41 Channel flux TB107-4/5 Lower Fntbay 114 NM-303 N42 Channel Flux TB207-4/5 Lower Fntbay 115 NM-303 N43 Channel Flux TB307-4/5 Lower Fntbay 116 NM-303 N44 Channel Flux TB407-4/5 Lower Fntbay 122 FY-510B Output SG 1 Fw Flow C5-0644 Output
-123 FY-512B Output SG 1 Stm Flow C5-0646 Output 124 FY-520B Output SG 2 Fw Flow C5-0544 Output 125 FY-522B Cutput SG 2 Stm Flow C5-0546 Output .
126 Relay X5A Rx Trip Bkr A CP-111-1 RTA Contacts 3/4 207 LY-502 SG 2 Wr Level C2-0331 Isolated Output 208 LY-519 Iso Out SG 1 Nr Lv1 C2-0343 Isolated Output 209 LOY-549 Iso Out SG 4 Nr Lvl C2-0344 Isolated Output 216 LY-504 SG 4 Nr Lvl C4-0331 Isolated Output 217 LQY-527 Iso Out SG 2 Nr Lv1 C4-0345 Isolated Output 218 LY-537 Iso Out SG 3 Nr Lvl C4-0352 Isolated Output 219 PQY-516 Iso Out SG 1 Press C4-0421 Isolated Output 220 PQY-546 Iso Out SG 4 Press C4-0426 Isolated Output 221 PQY-458 Iso Out Pzr Pres Ch. 4 C4-0430 Isolated Output 222 PY-403 RCS Wr Press C4-0443 Isolated Output 223 PY-516T Stm Ln 1 Press L/L C4-0454 Output 224 PY-546T Stm Ln 4 Press L/L C4-0455 Output 225 PY-458T Pzr Press L/L C4-0456 Ou' eut 303 LY-503 SG 3 Wr Level C3-0331 Isolated Output 304 PQY-526 150 Out SG 2 Press C3-0421 Isolated Output 305 PQY-536 SG 3 Press C3-0426 Isolated Output 306 FQY-416 L1 Flow 3 C3-0441 Isolated Output 307 FQY-426 L2 Flow 3 C3-0443 Isolated Output 308 FQY-436 L3 Flow 3 C3-0445 Isolated Output 309 FQY-446 L4 Flow 3 C3-0447 Isolated Output 310 LQY-461 Pzr Lvl Ch. 3 C3-0451 Isolated Output 311 PY-526T Stm Ln 2 Press L/L C3-0454 Output 312 PY-536T Stm Ln 3 Press L/L C3-0455 Output 313 FY-5308 SG 3 Fw Flow C7-0344 Output 314 FY-532B SG 3 Stm Flow C7-0346 Output 316 TY-413K L1 Wr Tc C8-0249 Input A 317 FQY-132 Output Letdown Flow C8-0245 Output 318 TY-4430 L4 Wr Tc C8-0249 Input D 319 TY-423K L2 Wr Tc C8-0249 Input B 320 TY-433K L3 Wr Tc C8-0249 Input C 321 FY-540B SG 4 Fw Flow C8-0547 Output 322 FY-5428 SG 4 StIn Flow C8-0549 Output 101 TY-413C L1 Wr Th C1-0722 Isolated Output 102 TY-423C L2 Wr Th C1-0727 Isolated Output i 103 TY-433C L3 Wr Th C1-0731 Isolated Output I 104 TY-443C L4 Wr Th C1-0734 Isolated Output
~
Attachment 9.5 1-ST-22 Rev. 2 , Page 1 of 2 MAIN PLANT COMPUTER ANALOG OATA POINTS Parameter- _ Source Instrument Loop 1 Tave A0316 TDY-412A Loop 1 NR Tc A0313 TDY-411E Loop 1 WR Tc A0343 TDY-413B Loop 1 WR Th A0339 TDY-413A Loop l'WR Tave C0694
-Loop 2 Tave A0321 TDY-422A Loop 2 NR Tc A0318 TDY-421E Loop 2 WR Th A0344 TDY-4238.
Loop 2 WR Th A0340 TDY-423A l Loop 2 WR Tave C0695 Loop 3 Tave A0326 TDY-432A Loop 3 NR Tc A0323 TDY-431E Loop 3 WR Tc A0345 TDY-4338. Loop 3 WR Th .A0341 TDY-433A Loop 3 WR Tave. C0696 Loop 4 Tave A0331 TDY-442A Loop 4 NR Tc A0328 TDY-441E Loop 4 WR Tc A0346 T0Y-443B Loop 4 WR Th A0342 TDY-443A Loop 4 WR Tave C0697 Charging Flow A0622 FDY-121 CS-E-2 Chg Outlet Temp A0614 TDY-126 Letdown Flow- A0620 FDY-132 Pzr Surge Line Temp A0372 TDY-450 Pzr Level A0332 LDY-459 Pzr Press A0337 P0Y-457 Pzr Liquid Temp A0375 TDY-453 Pzr Vapor Temp A0371 TDY-454 IR Det 1 Log Pwr A1002 Ni-NM-35B IR Det 2 Log Pwr A1003 NI-NM-S6B Trn A Neutron Flux A1019 Trn B N2utrnn Flux A1022 SG 1 Stm Flow A0729 FDY-512 SG 1 Feed Flow A0728 FDY-510 - SG 2 Stm Flow A0742 FDY-523 SG 2 feed Flow A0741 FDY-521 SG 3 Stm Flow A0749 F0Y-532 SG 3 Feed Flow A0748 FDY-530 SG 4 Stm Flow A0719 FDY-542 SG 4 Feed Flow A0718 FDY-540 SG 1 Feed Temp A0784 TE-4264 SG 2 Feed Temp A0807 TE-4265 SG 3 feed Temp A0786 TE-4266 SG 4 Feed Temp A0809 TE-4267 SG 1 Pressure A0730 PDY-514 SG 2 Pressure A0740 P0Y-524 SG 3 Pressure A0750 PDY-534 SG 4 Pressure A0720 PDY-544
l-
^
. Attachment,9.5' 1-ST-22 Rev. 2 Page~2 of 2-MAIN. PLANT COMPUTER ANALOG DATA POINTS' b
Parameter Source- Instrument, l> RCS WR Pressure A2970 PDY-403 l RCS WR Pressure- lA2914 PDY-405 SG 1 NR Level A0734 LDY-519 l SG 2 NR Level A0744 LDY-529 SG 3 NR Level A0754 LDY-539 SG 4'NR Level A0724 LDY-549 5 Min Heatup Rate C0706 Bulk Avg Core Temp A2923 Subcooled Margin A2926 Bulk Avg Core. Temp A2979 Subcooled Margin. A2982
. _ _ . _ . _ . _ _ _ _ _ _ . _ _ _ _ . _ _ .___..__.____._..._..__________________.____._______._____m___.__.___
Attachme'nt 9.6 1-ST-22 Rev. 2 Page 1 cf 1 TEST E0UIPMENT DATA SHEET l IDENTIFICATION CALIBRATION DESCRIPTION LOCATION /USE NUMBER DUE DATE INITIALS /DATE s sM art
1- d 4 Attachment 9.7 1-ST-22 Rev. 2 Page 1 of 1 POWER LIMIT DETERMINATION
- 1) Obtain intermediate range. detector normalization constants from ST-16.
a) .NI-NM-35B 1 b) NI-NM-36B
- 2) Determine intermediate range detector current limits for 5% core power and
- for the P-7 setpoint.
a) NI-NM-35B: ( ) amps x 5% = amps. b).- NI-NM-368: ( ) 8mPS x 5% = amps. c) .NI-NM-358: ( ) amps x( %) P-7 = amps. d) NI-NM-36B: ( ) amps x( %) P-7 = amps.
- 3) Record these values on' Attachment 9.3, Section B.4 and Attachment 9.9
.p #
r 9 L___________________ _
- a : .. '
N, ' ,5-. Attachmbnt 9.8 1-ST-22 Rev. 2
-Page 1 of 1-THERMAL POWER LIMITS AND LOG 5% P-7
' Current Limits N35' amps _
Emps N36 amp 5 amps IR-A (amps) IR-B (amps). Date Time (A1002) (A1003) Inits/ Time _.g. __ l Reviewed By: Date:
n,. . 53# 46958 IMSf D05.99.99 New Hampst*e Yankee DMalon - - INTRMXHAPANY BUSINESS MEMO .' Putse liernoe of New Harrgetto Subject STARTUP TEST DEPARTMENT PERSONNEL QUALIFICATION AND TRAINING MATRIK Date De cembe r 20, 1988 From C. A. Kann 02-08 Olstrict D. E. Moody 49-S5 Refemoce SS# 46171 To As required by TSAR Section 1.6, test personnel that direct test acti-vities during the Startup Test program must be qualified to ANS 3.1. In addition to this requirement, the Startup Test Program Description (STPD) identifies the specific training requirements for both the Shift Test Directors and Test Directors. As required by the STPD, I have determined the qualifications of the Startup Test Department personnel. The qualification and training statrix is attached. Test personnel not qualified as either a Shif t Test Director or Test Director may not direct test activities, however, they say perform other duties; such as collect and evaluate data, etc., under the direction of a qualified Test Director or Shift Test Director. C. A. Kana
$tartup Manager CAK/jw At t sc hr.dut cc: D. Covill 02-07
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I Attachment to SSf46958 NOTES TO STARTUP TEST DEPARTMENT PERSONNEL QUALIFICATION AND TRAINING MATRIX i I
- 1) Although Mr. Burson does not have a BS Degree in Engineering or related science as allowed by TSAR section 1.8 and the STPD, other training and experience does qualify his for the position of Shift Test Director.in addi- ,.
Mr. Burson has over fourteen years nuclear power plant experience, tion to that, he has eleven years nuclear experience in the U.S. Navy. Mr. Burson has also received SR0 licenses from the USNRC. The experience J and training Mr. Burson has received qualify him for this position.
- 2) Although Mr. Carr does not have a ES Degree in Engineering or related science as allowed by TSAR section 1.8 and the STPD, other training experience does qualify him for the position of Test Director.
and Mr. Carr ( does have an Associate Degree in A9 plied Science and he has over nine years nuclest power plant experience. In addition to this, Mr. Carr has two years experience as an 16C technician and four years experience in the U.S. Navy. The experience and training Mr. Carr has received qualify him for this posi-
)
tion. Burson is currently enrolled in License Operator Training at Seabrook
- 3) Mr.
Station. The training curriculum for this program includes both Transient ' - Analysis Training and Plant operations Training. +
- 4) The Test Directors identified here have not received Transient Analysis #
Training. As allowed by the STFD, these Test Directors do not require this training based on the limited nature of the Low Power Test Program.
- 5) Test Progras Administrative Training was held on October 19, 1988.
- 6) Technical Staf f Plant operations Training presented by the Training Center Staf f was completed for all Shif t Test Directors (eacept Surson see Note 3).
This one week training course included 20 hours of simulator time and tran-sient analysis training, Trais training was received froe September 12 to g November 4, 1968. R s I 1 r meM'
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t Ncw Hampshiro h k MEMORANDUM SSPf 890965 BASIS FOR THE HINIMUM PRESSURIZER LEVEL TRIP CRITERIA FOR THE NATURAL Subject CIRCULATION TEST 1-ST-22 , R. A. Gwinn Dole June 29,1989 From To P. V. Curney Reference Westinghouse Precautions, Limitations, and Setpoints (PLS) The following is a response to the question regarding why the Natural Circulation Test, 1-ST-22, required a manual trip at a pressurizer level below 172. The manual reactor trip requirement on pressurizer level of 172 is based upon the ability to operate plant in a condition where reactor coolant system pressure is capable of being maintained, and without violating plant . technical specifications (3.4.9.2 item c). At a pressurizer level of 172 and decreasing, the reactor coolant system flow to the chemical volume control system is^ isolated and the pressurizer heater groups are automatically deenergized. This is a normal system control function as defined in the above Reference. Once reactor coolant system letdown flov is isolated and pressurizer heaters are denergized, the ability to use auxiliary r. pray to reduce pressurizer is greatly minimized since the charging flow to the reactor coolant system is no longer heated though the regenerative best exchanger. Without this charging flow preheating via the regenerative heat exchanger the differential temperature between the pressurizer spray nozzle and the fluid can be exceeded if a.uxiliary spray flow is used. Without the use of auxiliary spray and backup heaters pressurizer pressure is not controllable and further test performance cannot be expected to continue. Since it is not the intent to perform startup tests that" would violate technical specifications or plant design parameters the manual trip criteria of 172 pressurizer s.s well as the other trip criteria vere established to b utilized as anticipatory reactor trip requirements, to stop the trat r9ould specified plant conditient be exceeded. . i l l h ~ R. A. Owinn ) cc D. E. Hoody J. H. Grillo G. J. Kline G. A. Kann L. W. Rau W. J. Temple New Hampshire Yonlee Division of Public Service Company of New Hompshire i P.O. Box 300
- Seabrook, NH 03874
- Telephone (603) 474 9521
. 4 /
l f . QUALITY ASSURANCE S URVE, ILLA NCE CHE CKL IS T /R E PORT l 2 S URVEILLA NCE TITLE 4 QASR NO. 1 RESPONSIBLE INDIVIDUAL or:s i ( M- WM -
'12cd Reossupv', G. KwJ 028-01-022 FREQUENCY 3 INDIVIDUAL (S) ASSIGNED / INVOLVED IN SURVEILLED ACTIVITY f.AAV S'N'*
- 6. HAE3 ~7%##"#-
jdu REVISION g, g g&Cd g R.0AM D
- REFERENCE, ETC.
5 SCOPE OF S UR V E I LLA NC E - QUALITY ATTRIBUTES The scope of this surveillance is to verify 1-ST-22, Natural Circulation Test, i Revision 2- is performed in accordance with References. R /' .I
- 1. NHY Operational QA Program Manual (NYQA) Rev. 22_
- 2. Start Up Test Program Administration (1-St-1) Rev. t-
- 3. Start Up Test Program Description (STPD) Rev. A 6 METHOD OF S UR VE ILLA NCE
.rcr '/ Car $: Conduct a direct surveillance to verify test is performed in accordance with above references.
.scr'/csurs ~ Verify the following items:
6.1 Verify RCS temperature, pressure and reactor power has stabilized so that at least one loop Tavg is i l'F, pressure is 1 SPSI and reactor power is stable 1 0.5% over a minimum of ten ninute time intenal. i.4 Verify Core Tharnoccuple (T/C) s.ap is obtained. 6.5 - Terify Subcooling houitor Test to performed per attachment 9.2 end subcoolisg m.Argin to } than 15'F. 6.6.7 - Verify natural circulation hso stabilized ud expected response por attachoest 9o3 hu beea obtained.
; 6.7.1 - Verify pressurint pressure is between 2225 and 2*60 PSIG, and I that prsieuriser level is stable ) 6.7.10 - Verify itubcooling is 1 15'F. 4 6.6.9 ~~ Verify siubcooling is 2 15'F. ;; a .
6.*.3 ~. Verify data is obtained until one of the , con (itions speelfied in
- - step 6d.$ is obtainede
- V a M4 h - . - --
W&# Document steps udtnessed ir. Rer,uha Section. See Guidelinss CWcklist on Attachment A for shcific attributes which .
~
should be referenced during surveillance performance.
, 8 APPROVED BY DATE 7 REQUESTED BY DATE b*
- h . .
DISTRIBUTION: E. SOVETSKY FILE F 17 ? i n n '* t NYQA FORM 2/10.3A 10 g4.1p,twg,cgr . . ~ R. M. D.{A }~. Revision,b""U
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h' h1 SSP #890897 NQG f89365 New Hampshire . Yankee - Subject QUALITY ASSURANCE AUDIT REPORT NO. 89-A05-01. ' TECHNICAL SPECIFICATIONS
- From 'J.J. Warnock D* """ '
To . D.E. Moody Reference SSPf890557 Attached is a copy of the subject audit report. This audit was conducted from May 8. to May 16. 1989 on Seabrook Station's Program for Technical Specification compliance. The audit resulted in two (2) Observations, both of which do not impact our program for compliance with Technical Specifications. The report indicates comp'iance to the existing program. Also, an indepth review of the residual heat removal system was conducted by the Technical Specialists, with satisfactory results. The results of the audit indicate that the Technical Specification Program is effective. The Repetitive *ask Sheets retrieved from the record files reflect improvement in ' attention to detail". Past audits have noted problems with the completeness of repetitive task sheet documentation. The effort expended to remedy this problem was apparent in the RTS reviewed during this audit. ) improvement was noted in all functional areas reviewed. Response to this report is required to be within 30 days of the report issue date, and as discussed at the entrance intervior, acknowledgement of the observations content will suffice when addressed as follows: Observation a) Results of the review and investigation. b) Disposition (if any) of observation. hi e rey J. Warnock
, N 'eet Quality Manager
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JJW/TLW/psd AttaEhment cc T.C. Feigenbaum L.A. Cauthier C.S. Thomas RMD R.E. Martel File 17.2.18.1.9 .[ . P.B. Upson File (1) R.D. Begor , .,.g
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;ov G.A. Kann J.A. Stanley H.C. Shaffer-YAEC R.K. Tucker-YAEC D.L. Cov111 New Hampshire Yant.ee Division of Public Service Company of New Hompshire P.O. Bo:: 300 Seabrook, NH 03874
- Telephone (603) 474-9521
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QUALITY ASSURANCE AUDIT REPORT Audit Report #89-A05-01 Page 1 of 7 SU3 JECT: Technical Specifications AUDIT DATE: May 8-16, 1989 AUDITORS: T.!>. Wiebold ATL R.K. Tucker ATM J.A. Stanley ATM . H.C. Shaffer Technical Specialist I. SCOPE: To evaluate conformance to the requirements of the Seabrook Station Technical Specifications. II. DESCRIPTION: The methods employed during this audit consisted of a documentation review of Technical Specification Surveillance, and the Residual Heat Removal (RHR) System was reviewed in detail for compliance to the design basis and verification that the surveillance tests performed are demonstrating that the system will meet the design intent. A. The following references were utilized during this audits
- 1. FSAR Section 5.4.7 and 6.3 as applicable l
- 2. OX1413.01 RHR Quarterly Flow and Valve Stroke Test, and 18 Month ;
Valve stroke
- 3. OX1413.02 RHR/RC Suction Valve 18 Month Interlock Verification Surveillance
- 4. OX1456.03
- 5. OX1406.12
- 6. OX1f56.02 i
- 7. CX0901.03
- 8. NUREG 1022 R1 and R2 LER Program
- 9. HA3.2, Rev. 7 Repetitive Task Sheets B. The objective evidence gathered during this audit is as identified herein or on file with the record copy of this report.
C. This audit satisfies the requirement of Section 6.4.2.8a of the Technical Specifications, l III.
SUMMARY
A. Evaluation of Program Effectiveness
- 1. The results of the audit indicate that the Technical Specification Program is effective. The Repetitive Task Sheets retrieved from the record files reflect improvement in
' attention to detail'. Past audits have noted problems with the completeness of repetitive task sheet documentation.
- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ - . _ _ _ _ _ . _ _ _ . . .)
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. Audit Report (89-A05 ;
'Page 2 of 7- ]
The effort expended to remedy this problem was apparent in'the RTS reviewed during this audit, improvement was noted in all' functional areas reviewed. B. Audit Synoosis
- 1. The review of forty-two (42) Repetitive task Sheets retrieved from RMD included multiple functional areas and were found to be satisfactory. ' Improvement was noted in the ' attention to-detail' concerning the completeness of the documentation of said' forms.
- 2. 'The Residual Heat Removal-(RHR) System was reviewed by the
- c. .,. Technical Specialist.
- a. The reviev focused on the system Design Basis to ascertain that survet11ance tests are documenting that the system (RHR)'can' meet design intent.
~
- b. The FSAR and' detailed system manuals were reviewed'for design intent.. Technical Specifications,' Clarifications and-Requirements were reviewed for licensing cossaitments. The applicable procedures, and data sheets were reviewed, personnel were interviewed and hardware was checked in the plant.
- c. FSAR Section 5.4.7. describing normal RER operation.and Section 6.3 (as applicable to RHR) describing emergency operation of the ECCS were reviewed.
- d. The~ Detailed Systems Training Manual, Section RH, describing the RER system was reviewed.
- e. Technical Specifications 3f4.3.2 ECCS Subsystems -
Temperature greater than 350*F 3/4.5.3 ECCA Subsystwas - Temperature less than 350'F. and 3!4.5.8 RER and Coolant Circulation apply. Technical Clarification TS-041. 042, and 046 were reviewed for. applicability to this audit.
- f. Procedures which perform the surveillance required by Tech Specs were obtained by referring to the table in the plants-Modification and Testing Manual. Copies of the following procedures were obtained:
OX1413.01 RER Quarterly Flow and Valve Stroke Test.'and ,18 Honth Valve Stroke observation . , g* N~T*I OX1413.02 RER/RC Suction Valve 18 Month Interlock Verification Surveillance OX1456.03 18 Month-ECCS Auto Valve, Actuation Verification OX1406.12 18 Month Containment and Containment Spray Recirculation Sump Surveillance
I I 'g ^ y, .
&. Q Audit Report #89-A05-01 '
, -Page 3 of 7 1
- 3. The Lead Surveillance Engineer was contacted to discuss scheduling and handling of Repetitive Task Sheets (RTS) [ Data packages from surveillance procedures). The technician provided a listing of the most recently conducted RTS for each procedure.
DCC assisted in reviewing the microfilmed documents, or obtaining copies of RTSs not yet filmed. One RTS was still in the custody of the system engineer, as it was conducted.on 5-4-89. The following were reviewed: OX1406.12 Performed 1-CES-0T003 11/07/88 1-CBS-0T020 Applies to Mode 1-2-3 OX1413.01 ; 1-RH-07004 04/01/89. 03/15/89 ) 1-RE-07005 05/04/89 { 1-RH-0T008 09/26/88 i 1-RH-0T009 10/07/88 1 1 OX1413.02 ! 1-RH-0T003 10/29/88 ) J OX1456.02 l 1-ECCS-0T027 03/17/87 l OX1456.03 1-ECCS-07054 12/20/86 1-ECCS-07055 12/27/86 j These data sheets were properly filled out, initialed and i signed. Reviews were conducted by supervisory personnel as j required. ! Procedure 0X1406.12. Item 1-CBS-Ot003 last performed 11/07/88 had a data sheet that indicated some items of discussion in the i
' Comments
- section. These consnents were reviewed and accepted '
by the System Engineer. This item requires inspection of CBS , sumps in the Containment. j
- 4. As of the date of this inspection, the plant expects to perfoca Low Power Testing shortly. Therefore, the CBS sumps were ;
inspected. When the sumps were visited, the steel plate entrance covers were found unscrewed, as work inside was obviously in progress. There was a drop light and portable sump pump in the South sump. I Both sumps were entered and inspected. Suction piping to the first CBS isolation valve is straight, and the closed valve disc clearly visible. All conditions were excellent. There is no question that these sumps could carry out their design basis function. All entrance grates and screens were in place. The steel access plate to the North sump presents an l unsatisfactory condition as far as worker safety and ALARA radiation exposure is concerned. This plate, about 2'x4'x1/4" ] i i
]
a Audit Report 189-A05-01 Page 4 of 7 thick, may weigh 82f or more. It is unintentionally ' captive", by the nuts holding in the vertical grates, which protrude over the plate, only 1/2 - 3/4' above it. This arrangement makes removal of the plate so awkward that personnel are likely to injure themselves and/or spend an excessive amount of time in a radiation /high radiation area. This sump was ente:rd by squeezing through the space available at the opposite end c the plate from the sump access ladder and swinging the legs uver to the ladder. The plate had been unscrewed and slid about a foot (by Maintenance personnel it is presumed) and could not be moved any further. See Observation 1.
- 5. The RER System Engineer was interviewed about the last RTS performed and about pump testing. The system as configured tests pump flow at about 600 GPM where the design point is 3000 GPM. It is a real question as to whether a test at this condition guarantees that the pump will perform its design intent for the plant. As discussed, this is an active question within the industry and USNRC. One plant now performs a full flow test of their RHR pumps. Seabrook design reflects the
' state of the art' at the time it was designed. As discussed, Seabrook can also perform a full flow test with no hardware changes. Administrative changes are extensive including a revised safety analysis from the reactor vendor, analyzing a loca with two RER cold leg injection lines in use vice four, as designed, i.e., loca happens during a full flow test. See Observation 2.
- 6. Technical Specifications do not require a performance test of the RER heat exchanger's heat removal capability. This was noted and discussed. This is not a safety concern since if a loca happens when RER is shifted to long term core / containment sump coolinF it will only take longer to cool down to atmospheric pressure. However, when RER is used in its non safety mode for post shutdown cooldown, any performance degradation will be readily apparent to operators, i.e., they will be unable to cool down at the maximum allowed rate, and corrective action will be taken.
Conclusions Based on the procedures reviewed, the personnel interviewed and inspections made, it is concluded that:
- 1. Test procedures will demonstrate that the RHR system can perform to it'a design intent. ,, y
- 2. Test procedures are being correctly performed and 'd' documented.
- 3. Personnel involved are knowledgeable, concerned and aware of the intent of procedures and programs. They are carrying out these programs so they meet the intent, as opposed to going through the motions and forms with no focus on the purpose.
h) Audit Report $89-A05-01 Page 5 of 7
- 7. LER's (Tech Spec 6.5)
LER's for 1989 were reviewed during the audit. It was noted . that to date, six (6) LER's have been issued for the year. Issues that b ome LER's typically are initiated as a SIR, b.st this is not required. The following LER's were randomly l selected for review during the audit: e 89-006
. 89-004
. 89-003
. 89-002 The following items were reviewed *
- Initial finding and reporting dates
. . content of description
. root cause e corrective action to preclude recurrence.
In addition, the program was reviewed and LER formats compared to 10CFR50.73 and NUREG 1022 R1 and R2. Of the LER's identified, none were considered to be ' safeguards information' however, Safeguards controls were reviewed and found to be acceptable, i.e., locking files, controlled distribution, etc.
- 8. SIR SIR's are used to document an investigation as a result of an operational event and can be used in conjunction with the LER process. SIR's are handled within the operations department by an SIR Coordinator versus Licensing who handles and controls LER's. It was observed and noted during interviews that there is a good level of cooperation. This was also verified by evaluating an SIR (89-006) and LER (89-002) that dealt with the storage location of a Portable Cooling Tower Water Makeup Pump (TS 3.7.5.c). Documentation of the problem identification root cause analysis and corrective action were found to be consistent. In this particular case, a Design Change Request (DCR 87-097) was initiated to resolve the issue. With the conclusion that the pump is now located within a seismically qualified structure to assure its availability for use after an event.
l Additional SIR's reviewed during the audit are as follows:
- 89-006 thru 89-010 The current SIR status at this time is:
SIR opened in 1989 - 25 Total remaining open - 18
V.. @ O \ ' Audit Report #89-A05-01 f Page 6 of 7 j t
- 9. Licensing Commitments !
{ 1 In addition to the Security audit performed previously under separate title, Licensing Conditions concerning Fire Protection and inadvertent Boron' Dilution were reviewed during the Audit. The Fire Protection Program addressing the HVAC charcoal I detection system was verified to have been submitted to the NRC and implemented by the Station within the time constraints required by the lice *se. i Inadvertent Boron Dilution is prevented thru the implementation of a number of plant procedures such at:
- OS86-1-6
- OS86-1-7 CX0901.03 In addition, one LER concerning valve positioning locked valves was reviewed (89-006).
- 10. SORC During the audit, two SORC meetings were attended and meeting minutes were reviewed for their content.
Meetings attended were 89-68 and 89-71, these meetings consisted of an covered the following areas:
- Licensing update
- Procedure review / approval T.S. clarification a SIR All issues brought before SORC were presented by a Cognizant Engineer who provided a discussion on the document or changes to as well as answering any questions and addressing comments identifying reviewers comments.
SORC Meeting Minutes were reviewed to verify documented review by $0RC. This was accomplished by the review of the following meeting' minutes: - 89-025 Various Procedures 89-030 Various Procedures
- 89-029 LER 88-05 R2. 88-06 R1, 89-02
- 89-040 89-043 SIR 89-006 3
- 11. POD Plan of the day meetingr were attended during tba audit 5/09-
~
11/89 to verify that daily activities are preplanned with consideration, due to impact, given tc all departments with a high priority given to those tasks to support the plants steady state operation and ability to progress to the next Mode.
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e @ Audit Report 189-A05-01 Page,7 of 7-During the meeting, it was observed that a daily check of T.S. surveillance activities is made to insure tests are completed and found acceptable. If tests are unacceptable, then verification of corrective measures are expected as was the case for RTS items 8E-64, 8E-63; Low Specific Gravity on Fire Pump A Batteries. This item was verified by the auditor as being resolved through the implementation of the regular program. The meetings observed typically followed the following format:
. Heads up of special items
. Hot items
. Daily activities including T.S.
- 12. As suggested by the NSARC representative during Audit 89-A01-0'1, special attention was focused on the Technical Specifications with a scheduled frequency of less than seven (7) days.
The Shift Logs for Operations were reviewed for Mode 5, the results were satisfactory. In addition, the Logs for Modes 4 and 3 were also compared to the Technical Specification requirements with satisfactory results. In Chemistry, the daily boron sample results and documentation were reviewed. Boron content was consistently above 2200 ppm, which is satisfactory.
- 13. The Operations Shift Logs reviewed provided an opportunity to verify the use of the ' Action Statement Tracking Log". (OP10.6)
The exceptions noted on thi Shift Logs were present in the Tracking Log. This review should serve as a close out to NQG
#89026, Subjecta NQG SIR Review, SIR No. 88-084, Action Statement Tracking Log.
C. Exit Interview An exit interview was conducted May 16, 1989. The results of the audit were discussed with the attendees as identified on the Audit Roster Form. l ~ l r Audit Team Leader f/F29 Date Y b Vd)A9rt.
' Audit & Evaluafion Supervisor C / Y -8 'l Date j
l 1 i
-_ ~ - :. .- . . . . - . . . . . ~ . . - - - - ---
Go ... ; @e , _ QUALITY ' ASSURANCE A'UDIT ROSTER FORM'- . AUDIT NUMBER -
.-j 89-A05-01.
l PRE-AUDIT POST-AUDIT NAME
- TITLE CONFERENCE AUDI~I cot! TERE lCE W.A. DiProfto- Asst.' Station Manager. X X P.B. Upson: Audit & Eval. Supervison _
X J.M.~ Grillo Operations Manager X. X X-J.L. Peterson Operations X' X ; R.K. Tucker ATM - YAEC X X X- l R.E. Martel- Staff Engineer X "X T.L. Wiebold ATL X X X R. Begor. Lead Surv. Engineer X X H.C. Shaffer Tech Specialist - YAEC X X .X E.J. Sovetsky. Tech Proj. Supervisor X' X J.M._Malone Opns. Admin.'Supv. X X T. Pucko Regulatory Services X ! E. Trump Fire Protection X G. Sessler Project Engineer- X
.S. Barraclough Tech Project Engr. X A. Xodel Engineer X J._Cade Lead Engr. (BOP) X R. Ferraioulo Engr. Analyst X !
J.A. Stanley, ' ATM X. !
.K. Carter Tech. Surv. X <
-C. Wallace Tech. DOC X i R. Couture Reactor Engineer X*
J. Connolly Test Cntl. Eng. X S. Cochoran. BOP Support Eng." X K.. Whitney Lead ISI Engr. X D. Egonis Eng.-ISI X C.:Strickland Eng. ISI X G. Lavigne Eng. Analyst X R. Strickland Shift Superintendent X J.T. Linville Chemistry Dept. Supv. X' J. Gallagher Chemistry Supv. % REMARKS ,
. Messrs. Tucker and Stanley are certified Lead Auditors by the Yankee Atomic Electric Company.
Mr. Shaffer is an Engineer with Yankee Atomic Electric Company. Pre-audit indoctrination / instruction, education and experience qualifies Mr. Shaffer as a Technical Specialist'in accordance with the requirements of ANSI 45.2.23. NYQA FORM 2/18.tC Rev. f.
Obs:rvction N3.: 89-A05-01-01 j Auditor: T.L. Wiebold i R.K. Tucker H. Shaf fer Date opened: June 16, 1989 Page 1 of 1 OBS Sump Cover Plate - North Sump irn: The steel access plate to the North Sump, (weig'at 82 lbs.) is unintentionally " captive" by the nuts holding the vertical grates, which protrude over the plate, only 1/2 - 3/4 f.nch. This arrange-cent makes plate removal awkward to the poie.:. that an excessive cmount of time in a high rad area vill be required for removal, cod personnel injury can not be ruled out. Was discussed with System Engineer. He agrees it is a minor item end can be done during upcoming work periods. N - m
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NO0$.fCSCIAl$ \ p , f() f Ggj~ /fhlddl~ /$0A.$ f0 0 i id nt ir n : That subject plate arrangement be reviewed and programm,thIcally modified to improve accessibility. O Respondent Date Lt c) Results of review / investigation: b) Disposition of Observation:
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Observation No.: 89-A05-01-02
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Auditor: T.L. Wiebold q~ - R.K. Tucker H. Shaffer Date Opened: June 16, 1989 Page 1 of 1 l
Title:
RHR Pump Flow. i v
Description:
RHR pump testing is currently performed at a test flow of approxi-mately 60'JGPM in accordance with plant procedurs and design. Currently there is.an active question within the industry as to the need of a full flow test (3000 GPM for Seabrook) to
. demonstrate system operability. Engineering and test control engineers are conversant with this item.
4- Recommendation: That plant management remain cognizant of developments con-cerning the flow question. Respondent Date
- r. .
Resconse: a) Results of review / investigation:
..q <
b) Disposition of Observation: iiii.iii-,ii
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- SI TESTY.NG NOG SIM4ARY J
- DATA'
SUMMARY
i. Surveillance: 1}0 ' n
), Finding - Nurce'euw)
(s __11 - Pri.1 - 0. Pri. 2 - 11, Pri. 3 - f. 4 Surveillance J_6, 6 Pri. 2 - 10_, Pro. 3 - J. l NUMBER SURVEILLANCE FINDING
SUMMARY
1-89-577 RX Trip not in accordance with STP-22. 89-549 Steps'in ST-20 (rod worth) performed out of sequence. l 89-417 Log entries required to show equivalent instructions used and thus prescribed surveillance not required. 89-480 Mode 2 checklist signed as complete with 2 open items not identified. i 89-399 SI check valve evolutions performed without a written procedure. 89-383 Changes made to two RTS procedures without an approval form, temperature gages installed without a procedures a gage was lef t i installed without the required METE extended use authorization. 89-372 Two Tech. Spec. surveillance beyond required frequency and not listed ] on Mode 5 to 4 checklists waste gas 02 monitor listed as standby when l it was actually inoperable date/ time missing on various activity l completion signoffs. ( l 89-329 RTS forms not completed properly (Operations signoffs/ blocks not filled in). l 89-337 Steplist (OPS) used improperly (to correct a deficient procedure). l 89-365 ~ Temp. setpoint documentation not properly controlled. 89-353 Not all personnel listed on test personnel log. ) l l l l
F C nsE; ofb '
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! QUA LITY ASSURANCE S U R V E I L LA NC E CHECKLIST / REP'CRT
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9 9
~~i RESPONSIBLE IN D IV I DUA L 2 S UR V E I L LA N C E TITLE 4 QASR .N O . e j
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The scope this surveillance is to verify 1-ST-20, Control Rod Worth Measurements ! Revision 'is perforned in accordance with Reference,s. - l
} 1. NHY Operational QA Program ihnual (NYQA) Rev./h i
e 22 Start Up. Test Program Administration (1-St-1) Revs '7*
) 3: Start UP Test Program Description (STPD) Rev. 'J - 8 8
J. . Testin f ouse Nuclear Design, Report for Seabrook Station, Cycle 1. WCAP-10982
.sev a J#.. : 15 . 6 METHOD OF SURVEILLANCE : .1 v
7 Conduct a direct surveillance to verify test is performed in accordance with I 5
-j above references.
I / Verify the following itens:
-I I - Ster 6.1.3.-- Terif. Control Bank D worth is within 115% of :ne ::tal predicted ,
value .per reference #1) or : 0.1% Delta RHO, ' rier is larger. 3: ; : :.h - ~~erify Control Bank C verth is within 215% of tn: ta' predicted value (per reference 6 , or : 0.1% Delta RHC. f"- ner i; ?arget. t I 3:ep 5.:.3.-- 7erify Control Bank B worth is within 115% of tn- :etal predicted I value (per reference #4)*or 2 0.1% Delta RHO, whi:hever is larger. I Step 5.1. 3.--Terify Control Bank A worth is within 215% of the total predicted value (per reference #4) or 1 0.1% Delta RHO, whichever is larger. I Record Boron Concentration in Results Section. l t I (continued) 8 7 REOCESTED BY DATE , 6 A PPROVED BY , ,1 DATE l } jn c . ckg
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- j RES?ONSE
..a: ion ;f coct s
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4 I i i 1 9 4 i-14 i RESPONSIBLE MANAGER { DATE I t NY:A F O P. .'" .: .. A k s ' . i '. O n *
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I; Original Repor:
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h- QAIR f 4/fA QASR i enN. 2. p-P /IMI97 Fage A of & 1
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l f*. i2 Method of Surveillance (continued)
*i I
6.6.3.-Verify the Worth of Shutdown Banks E, D, and C are within 15% of total [ 5 predicted value (per reference f 4) or 10.1% Delta RHO, whichever is larger. , 1
- 3. 6.7.1.-Verify Control Bank "A" is withdrawn to 6 steps.
6 1 4.--Verifey RCS is borated back to final concentration obtained with all control
- banks inserted and all shutdown banks fully withdrawn (Step 6.4.3). Reccrd Boron Concentration in Results Section. . ;f [8.7 -Verify the Werth of Shutdown. Banks B and A (less the stuck rod) are within 5 v 115% of the total predicted value (per reference, f 4) or r 0.1%, whichever -
is larger. f 3 -,--Ver.- - Red 'a'or:h Measurement with Control Banks in overisp is within 215; cf 1 6. . - , i the :::a1 predicted value (per reference #4), or 2 0.l* Delta RHO. whichever i
!! is larger. $ I j 6.10.4-Verify Rod Worth Measurements taken for designated test banks by Red Swap per RN1736 are analyzed (as required). ? ?,
T 6.10.3--Verify Rod Worth analysis are cc plete. ' f / Docu:en: step.y witnessed in Results Section. See Onde11nes Checklist on Attach =ent A for specific - mOutes which should
; V be radarenced during surveillance performance.
9 5:
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.z ATTACHMENT A I:. .
Guidelines / Checklist +
.T NOT .
SAT UNSAT* VERIFIED I.
- 1. Section 2.0, 3.0, 4, O and 5.0 are complete prior to starting Section 6.0 unless otherwise stated in test. I/.
- 2. All test equipment used is recorded on Test Equi pment Data Sheet. ,8
/ 1 9 ; 3. Test personnel are recorded on the
- Test , '
& Personnel" 1.og . /'
j I. '^
+. Tes- instructions are performed in order unless s l otherwise stated in test. 4M / .
, l'
? 5. Chronological log is properly maintained and the following items are documented.
",i!* '" ) ufe alla j
.t 'I A. Test Commencement /
?. .
- 3. Significant Events / l C. Repeti ions of Portions of Test u!c & .'
l; _ , . I ~J Reasons for Test Ter=ination/ Interruption - s. a b
! I. Review of Applicable Prerequisites and Initial Condition prior to Restart of i f Test after Test Termination / Interruption vc M0 <4 1 l
- l. +
l 6. Data sheets indicate the individual actually MN u h; 84
- l. obtaining the data.
' . Field changes are processed as required by STPD.
I
#ls r 'A N^
S. Test exceptions are processed as required by STPD. 6 s t
*
- See Results Section 3
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, j. IMMEDIATE , ACTION REQUIRED X
2 L 9fiS/?A 3 ..q sf NONE REQUIRED 13 l RESPONSE
'(Include corrective action and completion date, determination of root cause and action to prevent recurrence.)
Q.6 14 RESPONSIBLE MANAGER DA TE (l NYQi FORM 2/10/3A Revision 10
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CONTINUATION SREET G . Original Report.
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f_ ,1 2 - l QUALITY ASSURANCE SURVEILLANCE CHECKLIST / REPORT ( SURVEILLANCE TITLE 4 QASR NO. 2 I'1 RESPONSIBLE INDIVIDUAL Tcer/ /30.f[vP/ g 015-01-018 gp gy FREQUENCY 3 INDIVIDUAL (S) ASSICNED/ INVOLVED IN SURVEILLED ACTIVITY 1 ja Veie. KWheele r "" g, /4% fire. J./2tcke @ d . de "
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~$ SCOPE OF SURVEILLANCE - QUALITY ATTRIBUTES - REFERENCE. ETC.
Charging Pump Operability Test
- 1. Operations Management Manual Chapter 3, Rev.
f5
- 2. OX1456.01, Rev. Ed
- 1. MA 4 3,2e/ 9 4, MA 4;3, A'e t l$ .
6 METHOD OF SURVEILLANCE (' Conduct a direct surveillance and/or document review to verify the test meets the requirements of references 1 and 2. DATE DATE _8 A PPROVED BY
~7 REQUESTED FY Uf - Y f ($ f E. SOVETSKY FILE # ~~ 17 3 in a i NYQA FORM 2/10.3A DISTRIBUTION:
R . M . D . { d, j Revision 10 J. WARNOCK
"*S* * ' # ~ "
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e l CONTINUATION SHEET k m- Original Report I
- & "s' 3 Page of I ph @SR p On 1 June 1989, the surveillant observed portions of OX1456.01 performed to demonstrate changing . pump check valves operability required per tech spec 4.0.5. Operability was detemined via l MT7.2 section 4.1.1.2 and referencj.ng ASME section IX, IWV-3414.
Documentation was by a "special RTS" (see attachment "A") and Unit Journal entries (see attachment "B"). These demonstrate that the technical attributes of Tech spec 4.0.5 are met. However, the following administrative deficiencies are noted: f)_ OPMM, Chapter 3, section 2.2.1.2 and .3 state in part "If the procedure governing a work activity on a given system or component... cannot be performed following the procedure as written... the responsible supervision shall... (submit) a written change in procedure. No further procedural steps shall i be performed until the procedure change is authorized by I completion of ... the station operating procedure change form (SM6.2C)." , aContrary to the above requirement changes to two (2) RTS's, OX1456.01C and -01D, were made without processing SM6.2C. The ( handwritten RTS (attachment "A") uses the same activity numbers as OX1456.01C and -01D. Additionally, documentation that prerequisites and initial conditions are met is not included in the handwritten RTS'or the Unit Journal. OX1456.01 states that a 0-3000 psig test gauge be installed at step 8.3.23.1 and removed at step 8.3.28.
# Contrary to these requirements the test gauge (FLS-258) was found installed prior to entry into the main body of the procedure (section 8).
MA4.3 requires that " Temporary modifications are installed and removed per an approved procedure,... controlled by a work request and falls under the scope of procedure MA4.5" or by the instructions of MA4.3. acontrary to these requirements, teemporary pressure gauge FLS-258 was found installed the day _after work under the controlling procedure was terminated. This is a failure to control plant configuration. The Unit Shift Supervisor was informed of this condition and the test gauge was prcmotiv, removed. (
CONTINUATION SHEET Tiginal Report SSR t 'ODT63 reca of gyg , tJ LD _ This is a priority 2 finding. Operation Department please provide root cause analysis and action to prevent reoccurance. gl F2,MA2.3, 4.1.15 states in part "If equipment will be checked out beyond a 24 hour period, an M&TE Extended Use Authorization, MA2.3F, must be completed by the user and approved by the controlling supervisor." Contrary to the above requirement pressure gauge FLS-258 remained installed in the field for greater than this period; no MA2.3F having been completed by the work supervisor. The test gauge was immediately removed, as described in finding
#2. This situation was catiped by the variances form procedure described in finding #2. This Inicident is considered to be an isolated case.
( This is a Priority 3 finding. No response is required. It is recommended that the procedure (OX1456.01) be revised to provide instructions ~or performing the tests when the positive This may help prevent displacement charging pump is unavailable. reoccurance of the events described above. The findings in this rrrport were discussed with the Unit Shift Supervisor, Shift Superintendent and Assistant Operations 4 Manager. Thih Report Remains Open. W D hGE
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4 1y I I I l l ACCEPTANCE CRITERIA: g " ML O t I I I I I I l l l 1 I I I (. l RETEST: l l l M/A I _I SECTION II l APPLICABLE MODES: 1, 3 . ~8) PLANT STATUS REQD: 1 3 9, h l l CORR. START C/A EST MERS: SCEID START: M/N CORR. END: C/A l l LAST PERT: O/A O/A EST ERS. 005: 4.) k PRIORITY: Al/A-l l WORK PREPARATION CHECKLIST: l l y EM (Y/N) INFO l ITEM (Y/N) INTO l l TAGGING ORDER l Afi l lIKC/O INS FORM ATTD lMl l l RWP/SRWP l Al l l EK VEQT FORM ATTD lMl l l IGN SOURCE PERMIT l A/ l l WORK ON ENER. EQUIP I A/ l l l l COMBUS MATL PERMIT l A/ l l SPEC OUALS OF WRKERS) Af l l l TEMP. MOD. RFOUEST l A/ l l MATERIALS PRESTAGED l A/ l l l WELD / SPEC TRAV ATTD I 1/ l l CHEM. REVIEW l A/ l l l cot (F STACE ENTRY REOl A/l l ALARA REVIEW l A/ l l l ADDITIONAL
REFERENCES:
l l l l l l SPECIAL CLEANING REQTS: (Y/N) 1i l l REQUIREMENTS: l-l _ A 1 l l RESP. PLANNER / WORK GROUP
'~
, Qf, Q DATE: l l SUPERVISOR SIGNATURE: u/e ri l I
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.C 381 QASKCRS-q9 (p o REPETITIVE TASK SHEET Sheet of [
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. QUALITY ASSURANCE SURVEILLANCE CHECKLIST / REPORT
. 1' i 1i RESPONSIBLE INDIVIDUAL i2i SURVElblANCE TITLE I4( QASR NO.
89-00399 Tech Projects Manager 028-02-004. (OPS & Startup Mgr.) INDIVIDUAL (S) ASSIGNED / INVOLVED IN SURVEILLED ACTIVITY l FREQUENCY 3i R. McIntire K. Muirhead R. Anderson NA G. St. Pierre J. Dolan J. Connolly K. Seitz J..Rickett R. Paradis REVISION K. Wilson R. Strickland On-shift Activities 6/2/89 - 1200 to 2359 5i SCOPE OF SURVEILLANCE - QUALITY ATTRIBUTES - REFERENCE, ETC. This surveillance shall be performed by direct observation of random control room and in plant activities. Surveillance'shall verify that Operations, Startup Test, and Quality Control personnel are performing their intended function.
References:
Seabrook Station Start up Test Program Manual and Assoc. Procedures NHY Operational Quality Assurance Program Manual Seabrook Station Technical Specifications Operations Manageuent Manual New Hampshire Yankee Reporting Manual
' 1 6l METHOD OF SURVEILLANCE Verify that Start-up (S/U) Test activities are properly performed and documented (as necessary). Use the attached " Surveillance Checklist" as a guideline for i
( the performance of this surveillance, document complete, partial or deferred I action as necessary. I Identify the test (s) or portions of test (s) witnessed, the test status and asso-ciated actions of Operations, S/U Test and Quality Control personnel on Page 2 (Results of Surveillance). Doc ume n t additional actions, reviews and comments on Page 2 (Results of Surveillance).
~
APPROVED BY DATE 7l REQUESTED BY DATE 8'
& h. J..f. WARNOCK'
) )h8f17.2.10.8.1 FILE f/ tqQA FORM 2/10.3A ,
{ DIS [RIBUTION:, C.J. SOVETSKY RMD (, 4 g & } Revision 10 Page 1 of 2 G.A. KANN .
l 9l RESULTS OF SURVEILLANCE 89-00399 l This surveillance of Seabrook Station Unit 1 Startup/ Low Power Test activities was
'(. ' performed on June 2, 1989 between the hours of 1200 and 2400.
A description of the Startup Test activities surveilled is provided on Page 7. l 1 This surveillance resulted in one (1) Finding and one (1) Concern as documented on Pages 3-6. Finding #1 will remain open pending response from Operations. This report remains open. DATE ' 11 l EVALUATOR DATE 10 l SURVEILLANT x4 b.
, .f - ( *f 12 l RESPONSE PRIORITY ICTS # (D A i C ? 3 f PRIORITY FINDING (S) # DUE DATE ,
1 MA ' IMMEDIATE ACTION REQUIRED 2 i ~/ &\v 1, RM 3 lQA NONE 4EQUIRED' i 13 i RESPONSE (Include corrective action and completion date, determination of root cause and action to prevent recurrence.) l i l I 1 DATE l 14 i RESPONSIBLE MANAGER d I ( NYQA FORM 2/10.3A Revision 10 , Page 2 of 2 l
i 4 .. QASR #89-00399 Page 3 of 7 Findine #1: The Operations Management Manual, Chapter 3. Step 2.2.1 states: 2.2.1 NORMAL RESPONSIBILITIES
- 1. An approved written procedure shall be used:
A- When equipment is sufficiently complicated that methods of operation could cause multiple results. B- When the system or component is necessary for station safety, or C- When tests of equipment under the scope of the OQAP are performed. Contrary to the above on June 2,~1989 at approximately 1915, the surveillant entered the Main Control Room and observed that an in-progress attempt was being made to more firmly seat the safety injection check valves (SI-V 2, 20, 35, and 50). Leakage by these check valves was believed to be responsible for the safety injection header being at the main coolant pressure. Leakage by these l check valves had been discovered during the performance of EX1804.047. The Shift Superintendent had directed the SCR0 to perform evolutions with the intent of more firmly seating the. safety injection check valves to stop the back-leakage. An outline of the evolutions performed is contained in Attachment l ( A. The surveillant inquired about the use of a procedure to perform these evolutions and was told that these evolutions had not been proceduralized. A detailed log of evolutions performed was not being maintained. The SCR0 was l I entering the major operations performed in the unit journal. Some time after the evolutions were completed the surveillant asked the SCR0 if j l p an independent verification of the opening of the power supplies for the accumulator isolation valves had been performed and documented. The surveillant i i felt, that as these breaker positions are on a 30 day surveillance and are required to be verified in the open position prior to entering Mode 3, that an l independent verification of their as left position should have been performed i and documented. The SCR0 stated that he performed an independent verification that the power had i been removed from the accumulator outlet valves after the valves had been I reopened by observing that the power on indicating lights for each valve was extinguished when the operator performing that operation reported to the SCRO. The surveillant believes that the SCR0 did perform the independent verification as stated and that the independent verification was valid although not documented. 1 SUMHARY: The evolutions performed were outside the scope of existing station procedures. l l
QASR #89-00399 Page 4 of 7 The evolutions performed were sufficiently complicated that methods of operations could cause multiple results. Upon review of this finding, the Shift Superintendent stated that he felt that the operations performed vere within the skills of the operator. The surveillant, based upon observation of the SCRO's operational expertise, agrees with the shift Superintendent on this question. The evolutions performed were under the scope of the OQAP. There was no briefing of QC/QA prior to the performance of these evolutions. There was no formal SORC pre-test review of these evolutions. There was no documented pre-test 10CFR50.59, safety evaluation, for these evaluations. The Shift Superintendent stated that he and the SCR0 did consider all of the factors involved in determining if a 10CFR50.59 review of the proposed evolutions was required. They both agreed that non was. There is no documentation of this review. Upon review of the activities performed, the surveillant agrees that a detailed 10CFR50.59 review would not have been required if these evolutions were performed under a procedure change. Change 2 to Procedure 0S1005.05 Rev. 7 was processed on June 3, 1989 to incorporate the evolutions performed that resulted in this finding in addition to other necessary testing of a similar nature. ( RECOMMENDATIONS: A. To provide support to the Shift Superintendent in the performance of similar evolutiens, the procedure change process should be administrative 1y changed. This change should allow procedural intent changes to be made and implemented by the Shift Superintendent without the prior approval of SORC for specific activities. Specific guidelines should be developed to insure that all Station groups can understand the intent and scope of what would be allowed by this administrative change. B. The independent verification that the accumulator outlet valves power supplies have been opened should be documented. I This finding report was reviewed by the Shift Superintendent and his comments , I have been considered and are noted. CONCERN NO. 1 - Voluntary entry into an action statement. Tech. Spec. 3.5.1.1 requires that each reactor coolant system accumulator shall be operable with: , 1 l A. The isolation valve open and power removed. l . B. I C. D. t
g_-_-_--______ __ -_
'O v v '
y: [. QASR #89-00399 Page 5 of 7
< (.
On June 2, 1989, each accumulator isolation valve was energized, closed, and
~
after other evolutions were performed, was opened and de-energized.. The
. evolutions performed are listed in Attachment A. These evolutions ~were performed in an attempt.to more-firmly seat safety injection check valves that were . experiencing back-leakage. The Shift Superintendent felt that it was necessary to perform these evolutions to minimize a source of reactor coolant unidentified leakage, and to prevent the possible dilution of the accumulator-boron concentration.
The Shift Superintendent stated that he interpreted his Tech Spec se being able to remain in the action statement for 6 hours before being required to reduce pressure to below 1000 PSIG. Technical Clarification NO TS-005 allows for voluntary entry in action statements.to perform required surveillance testing. The evolutions being performed were not part of an approved written procedure and were not required to protect plant _ personnel or equipment. The action for this Tech. Spec, is: A. B. With on accumulator inoperable due to the isolation valve being closed, either immediately open the isolation valve or be in at least hot standby. within 6 hours... The bases for Tech. Spec. 3.5.1.1 does not indicate that operation with one accumulator isolation valve closed for any length of time is allowable or acceptable. The surveillant requests that Technical Clarification No. TS-005 be reviewed and broadened. If appropriate, to include guidance and direction to be used for entering an action for other than surveillance testing. The NRC's position on voluntary' entry into action statements for operational convenience should be considered.
.This concern was brought to the attention of the Operational Projects Manager on June 3, 1989 in a telephone conversation with the Nuclear Quality Manager. The operational Projects Manager stated that voluntary entry.into an action was not a problem under any circumstances providing the action was exited prior to the expiration of any time limit imposed by the action statement.
i l i
QASR #89-00399 Page 6 of 7 ATTACHMENT A
SUMMARY
OF EVENTS
SUMMARY
OF TESTING: The evolutions performed were to close each accumulator discharge valve (SI-V 4, 18, 33, and 48) one at a time. The section of piping between the isolation valve and the check valve (SI-V 5, 20, 35, and 50) was drained thru the drain valve to SI-V 70 and 62. The pressure was allowed to decay to approximately 0 and when the flow out of the drain valve had stabilized at its lowest level, the drain line-up was closed and the accumulator outlet was opened. The safety injection header was then monitored to determine if the pressure equalized with the main coolant system. This sequence of operations were performed for each accumulator, one at a time. ( ( 1 l l L______--_____-_____. - _ - _ - - _ - _ _ __- _-__-_-_ ________ _- __- _. _ _ _ _ ___-___________-__--___a
a : s
=.
N- . QASR f89-00399. Page 7 of 7 QA LOG 6/2/89 - 1200 hrs to 2359 hrs 1200 hrs Relieved Ralph Miller. 1210 hrs Reviewed S/U log - Satisfactory. 1215 het Reviewed STP-101 for new steps completed and procedure changes - all changes to date (11) have been approved by SORC. 1220' hrs otverved briefing for closing the HSIV's and closing the valves - Satisfactory. '; 1235 hrs ~G. St. Pierre directed personnel not to distract operator performing an evolution - establishing atmospheric blow - good move. 1310 hrs Reviewed STP-101 for completed steps. -Attended S/U briefing for STP-101. .All involved parties were present. Procedure was being changed during the meeting to reflect other group's concerns. Steam valves failed to open on EFW Turbine 1st start test. Test on hold. SI check valve leakage may be a problem as SI header is at 'C H pressure 1700 PSIG. Attempt to bleed down the pressure have not be (. successful. Steam valves failed to open on EFW turbine 2nd start test. Test exited. Operations trainees being utilized correctly - not manipulating controls. Toured turbine building - satisfactory. Observed attempts to seat the SI-V-5 20, 35 and 50 check valves. Upon investigation issued Finding #1. 1120 hrs Steam valves 373 and 374 remain inoperable. SI header pressurized to MC pressure - leaking check valves. 1130 hrs Obs erved shif t directors turnover - satisfactory. I e
v' 89-00399
~
Paga 1 of 2 Standard Surveillance Checklist - 028-02-004 l l ITEM SAT CONCERN
- N/A*
X
- 1. Verify the minimum staffing requirements for Control Room Operations (CRO) and Start-up Testing are appropriate during the period of surveillance.
Reference:
CR0 per SS Tech Specs, Sec-tion - Admin. Centrols, para. 6.0, OPKM Chapter 2, S/U Test staffing - per the S/U Test Program Manual and associated S/U procedures.
- 2. Determine if S/U Test and CR0 personnel x actions appear correct and coordinated, with direction and actions following the proper chain of command.
Re fe rence : OPMM Chapter 1 & 3, S/U Test Program Manual and associated S/U Test procedures.
- 3. Verify proper communication between the X various Operations and Test personnel during command and control sequences.
e.g., Proper communication between per-sonnel involved in flux mapping and Control Room operating staff, i.e., Operators monitoring Tavg reactor power, manual rod stepping etc., while test personnel operate the it. core detection system.
Reference:
OPMM Chapters 1 & 3, S/U Test Program Manual and associated S/U Test procedures. X
- 4. Verify QC is present in the Control Eoom during S/U testing and major plant evolu-tions. Verify proper sign off of QC witness points and initiation of S/U test documentation for each QC shif t reviewed during this surveillance.
Reference:
NYQA, S/U Test Program Manual and associated S/U Test procedures. (
- A checkmark in this column requires an explanation.
- = -
7 e
- 1. -
. 89-0039'i
'- c.; . Pegs 2 of 2
. ,,=
Standard Surveillance Checklist - 028-02-004
~( ITEM SAT CONCERN
- N/A*
X
$.. Randomly select various Technical Specifi-cation Limiting Conditions of Operation *Concera #1 (LCO's) appilcable to the existing plant mode and verify operational compliance.
Should non-compliance with an LCO exist, verify the requirements of the applicable action statement are met. Re ference: Seabrook Station Technical Specifications
- 6. Verify fleid changes to S/U Test procedures X are properly initiated and documented.
(i.e., Reactor S/U Supervisor's approval, 10CFR50.59 applicability, proper review, etc.).
Reference:
S/U Test Program Manual
- 7. Verify test interruptions and/or termina- x tions are properly initiated and documented.
Reference:
S/U Test Program Manual X
- 8. Determine if significant entries made in the control room log, shif t supervisor's log and S/U Test Chronological Log are consistent. Verify initiation of reporting and/or corrective action docu-ments as warranted by plant conditions.
Re ference : OPMM Chapters 3 & S, S/U Test Program Manual and New Hampshire Yankee Reporting Manual
- 9. Review the process of shift turnover for X Operations, Quality Control and Start-up Test personnel. Determine if a proper carry over, briefing and review of neces-sary logs and test procedures occurred.
Reference:
OPKM, Chapter 4 and S/U Test Program Manual Added Determine if an approved written procedure X
- 10. Finding #1 was used in accordance with OPMM Chapter 3 .
para. 2.2.1. {
- 8 - Could not verify this because of test ng actuvities.
*A checkmark in this column requires an explanation.
4 . .
, QUALITY ASSURANCE SURVEILLANCE CHECKLIST /REPQRJ 1 RESPONSIBLE INDIVIDUAL 2 S U R V E I L LA N C E TITLE 4 QASR NO.
" P-OO46n 028-01-016 1 3 INDIVIDUAL (S) ASSIGNED / INVOLVED IN SURVEILLED ACTIVITY FREQUEFCY
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5 SCOPE OF S URV E I L LA NC E - QUALITY ATTRIBUTES REFERENCE. ETC. The scope of this surveillance is to verify 1-ST-16 Initial Criticality Revision M is performed in accordance with References.
- 1. NHY Operational QA Program Manual (NYQA) Rev. _l2L
- 2. Start Up Test Program Administration (1-St-1) Rev. 2
- 3. Start Up Test Program Description (STPD) Rev. *2 6 METHOD OF S URVE I LLA NC E
[ Conduct a direct surveillance to verify test is performed in accordance ( vith above references. Verify the following items: Step 6.1.13 - Verify 1/M plot is performed and it has been determined the reactor core will not become critical by an additional 114 steps of Shutdown Bank Withdrawal. Step 6.1.25 - Verify 1/M plot is performed and it has been determined ' the reactor core will not become critical by an additional 114 steps of Sht:tdown Banh Withdrawal. Step 6.4.11 - Verify 1/M plot is performed and it has been determined the reactor core will not become critical by an additional 60 steps of l Control Bank Withdrawal. Step 6.2.19 - Verify 1/M plot is performed and it has been determined i the reactor core will not become critical by an additional 60 steps of l Control Bank Withdrawal. Step 6.3.5 - Verify dilution rate of approximately 80 gps. Record i actual dilution rate in results section. Step 6.3.21 - Verify the blended makeup setting is set to concentration determined in step 6.3.20. Record actual dilution rate in results section.
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CONTINUATION SHEET Original Report QAIR # N[A QASR # TS9-CD4lTfD Page 1 of 6 i Surveillance was perfprmed on ST-16, " Initial Criticality" on 6-13-89 Midshift. 1 Sections 2.0, 3.0, 4.0, & 5.0 were reviewed prior to starting { cection 6.0 & all was satisfactory except as stated in finding j
#1. !
Steps 6.1.1 through step 6.2.10 were witnessed from the control ) Room. Hold Points for steps 6.1.13 & 6.1.25 were verified, initialed and dated. Witness Point for section 6.1 was signed { and dated. f Test proceeded without incident until step 6.1.12 when DRPI received a non-urgent alarm for rod P-6 in Control Bank B. This had no effect on immediate testing and test continued. Work request 89W002905 was written to correct. At step 6.1.14 shutdown Bank C could not be withdrawn. Work request 89W002904 was initiated to correct. Both problems were corrected and test
, continued until step 6.2.10 when DRPI Non-urgent alarm for Control Bank B Rod P-6. Test was stopped until problem is corrected.
Finding #1 - STPD Appendix A Section E states that "The Procedure ( shall identify those items or activities which must be performed prior to the start of any testing operations. These may be either administrative in nature..." Contrary to this step 3.12 which states "The Operation Department Mode Change Checklist for Mode 2 entry is complete" was signed off with two items open. Surveillance no. 4.1.1.1.C which is to be done within 4 hours prior to achieving Initial Criticality & 4.1.3.5 which is to be done within 15 minutes prior to Control l Bank withdrawn. Test Director made entry into Chrono Log to I clarify signing of step 3.12. l l This finding was discussed with T. Waechter. The items were completed prior to entry into Mode 2. This is a Priority 3 Finding. No Response Required. l This Report is Closed. (
._ t
CONTINUATION SHEET i -, - i
' (KIR f t-4/A Original Report (MSR # M - O 6 4 W 6
() ! . Page g!( of 1 Method of Surveillance (continued)
/ Document steps witnessed in Results Section.
/See Guidelines Checklist on Attachment A for specific attributes which sho be referenced during surveillance performance. .
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- ATTACEMENT A Guidelines / Checklist NOT SAT UNSAT* VERIFIED r
- 1. - Section 2.0, 3.0, 4, 0 and.5.0 are complete prior to starting Sectior. 6.0 unless otherwise stated in test.
- 2. All test equipment used is recorded on Test Equipment Data Sheet. _ p "'
1
- 3. Test personnel are recorded on the " Test {
Personnel" Log . V i 4 Test instructions are performed in order unless otherwise stated in test. L '" ,
- 5. Chronological log is properly maintained and the l following items are documented. v- i
( A. Test Conssencement g _ B. Significant Events L' C. Repetitions of Portions of Test ___ agc I 1 D. Reasons for Test Termination / Interruption Jeff E. Review of Applicable Prerequisites and Initial Condition prior to Restart of Test af ter Test Termination / Interruption L /'
- 6. Data shetta indicate the individual actually obtaining tbs data. v/'
- 7. Field changes are processed as required by STPD. _
g L '#'
- 8. Test exceptions are processed as required by STPD. ___
- See Results Section
('
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SUMMARY
(1/1/89 - PRESENT)- .
,{
!Yf- -Total Number of NQG Reports (against Operations) - 265' d M M **
@ 4' Total Number of NQG Reports (against Operations) -
38 N
} with-Findings Tio63 J 3 Total Number-of Findings Against Operations -
32 -' ops @dk Operational Related -
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. Administrative / Documentation - 28 .
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JROCEDURAL NONCOMPLIANCE CateRorY A (Operational) 89-577 - Reactor not tripped for STP-22. 89-299 - PCCW Valve Position 50% vice 100% open. V4WE %rto A TEcBLEM S 89-304 - SW Valve closed vs. open (Mode 5). - 89-350 - CS BTRS outlet valves not locked yg%Q%s4sra.-h W M.a <<., { Category B (Administrative / Documentation) A. Improper Forms / Outdated Documents 89 RTS for blanket valve packing Rev. O Vice Rev.1. j B. Inadeouate Documents 89 Combustible Material Forms Inadequate 89-119 - Operator Aid Log Missing Copies 89-304 - Drawing showed valves open, procedure required closed. 89-357 - Some THODs not properly labeled and posted. ! 89-372 - Activity outside specified frequency. C. Failure to Complete Forms 89 Fire Protection inspection documentation incomplete. 89-158 - Ignition source permit not signed by Supv. 89-175 - Tagging order not properly restored. i 89-210 - Controlled test records not up to date. j 1 89-329 - RTS with blank blocks. 89-372 - Time /Date activity signoffs not made. D.- Deviation From Procedural Details ! 89-152 - Valves not on locked valves list were locked._ 89-158 - Fire watch certification out of date. 89-171 - Log sheets not properly completed. 89-222 - Independent verification requirement not stamped on tagging order. _ _ _ _ _ _ - _ _ _ _ _ - - - _ - - _ _ _ _ - - - _ _ _ _ _ _ - _ _ _ - _ _ _ - _ - _-__-____________-____-__-_-____________-______-_-__--___m
.r ...
Page 2 89-255 - Copy of installed th0D not sent to control room. 89-323 - Uncovered boric acid drums in Batch Room. 89-366 - Danger tags improperly marked. 89-383 - Test gage unworkable procedure not changed, 89-480 -- W Mode change checklist signed with 2 open items. F d'bbF,p B'V QAIR 89-566 - Did not dispose of open boric acid drum. E. Inadeauste ProRram 89-148 - Some VAS alarms don't have a response procedure. 89-314 - Uncontrolled operator aids. 89-372 - OP10.6 does not provide adequate direction for inoperable equipment. F. Failure to Notify OC 89-251 - QC not notified prior to start of work. G. No Procedure 89-337 - Step list used vice revising inadequate resin sluice procedure. 89-399 - Attempts made to seat check valves without a procedure.
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,. 1.5 ; PROCEDURE ADHERENCE I( 1.5.1 Policy l L 3. Forms are used in the execution of procedures to record pertinent information. Blanks provided on forms should be filled in with either the data requested or."N/A" (Not applicable) as appropriate. Large l~ areas or large numbers of blanks may be filled in with "N/A" and arrows if each item is not applicable to the circumstance.
- 4. Vendor supplied manuals / documents are to be used as reference only and not.in lieu of a step by step procedure. If such use is required, the manual / document must have the same review, approval and control as an equivalent procedure. Excerpts from vendor manuals may be used as defined in SSMA.
1.5.2 Objectives Develop and maintain procedures necessary to operate and maintain the 4 Station consistent with regulatory requirements and sound operating practices. _ Ensure these procedures are clear, concise and free of ambiguities and } conflicts. -l
. Provide a formal process whereby procedures are changed or deviated from without compromising the safety or quality of Station operation.
1.6 WORKING HOURS { 1.6.1 Policy
- 1. Station Staff should include sufficient personnel so that routine
. work can be accomplished without resorting to large amounts of over-time. During unit outages and temporary periods of unanticipated extra workload, inore overtime may be used.
- 2. Excluding shift turnover time, an individual should not be required to work more than: 16 hours continuously within any 24 hour period; 24 hours within any 48 hour period; or 72 hours within any seven day period.
- 3. A break of at least eight hours should be allowed between work periods (including shift turnover time).
- 4. One full day off should be allowed for every six consecutive working days.
- 5. During unit outages or other special periods, overtime requirements msy be authorized on an individual basis.
- 6. The Station Manager may authorize a deviation from the above guide-lines due to special circumstances. This authorization must be docu-mented.
L
- 7. Overtime shall be distributed among eligible employees as equitably as possible consistent with the needs and requirements of the Station.
l 2-1.4 SSMM Rev. 10 1 l
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4 SH 6.1 Page 11
-ug Rev. 5
,N 4.5 PROCEDURE ADHERENCE
' 4. 5.1 ' Policy.
Station administrative procedures have been prepared, reviewed, Land , approved to govern certain processes and work activities. Where a pro-cedure exists, it shall be considered. guidance regarding the method of
- performing.the function. Procedures.shall be followed,-but not without b question. Where the procedure: directs an action contrary to what is considered proper, question that procedure and seek resolution from- l-p . appropriate supervision. A procedureLbeing questioned should not be deviated from on the basis that it is being questioned. Resolution, obtained through appropriate supervision, shall determine the proper
.l
-course of action in accordance with this. procedure.
4.5.2 Corrections Correct mistakes in los entries or data steps by drawing a single line through them, initialing, and dating. Do not use correction tape.or. fluid (" white'-out") for these mistakes. 4.6- PERIODIC REVIEWS AND HISTORICAL RECORDS 4.6.1 Periodie Review. As a minimum, each administrative procedure and its associated forms
-( shall be reviewed every two (2) years + 25%~ based on the " Effective Date".in Section E, Form SM 6.1A. If no revision has taken place l l within two years of the effective date, perform the steps under $4.2.
Document. completion of the two year review by completing a new Form SH 6.1A, Administrative Procedure Cover Form. Advance the current revision number by one and assign a new effective date. Prepare a new-contents and revision status page reflecting the new revision number. 4.6.2 Historical Records
- 1. A historical file of Station administrative procedures, pro-cedure safety evaluations, changes, and subsequent revisions shall be maintained by the Records Management Department per the Records Management Manual (NTRM).
- 2. A listing of effective Station administrative manuals and operating procedures are maintained in the Document Index
. Reference (DIRE).
4.7 PROTECTED PROCEDURE STEPS
- 1. From time to time specific steps must be added to procedures as a result of external regulatory or operating experience documents such as I&E Notices, SOERs, SERs, etc. It is necessary to provide some protec-
?
. tion for these steps to ensure that they are not altered or inadver-tently removed.
REVIEW COFY ifp', su 6.1 Pcg2 22 JUN 2 71989 - i I Rev. 6 l 4.5 PROCEDURE ADHERENCE 4.5.1 Policy i Station administrative procedures have been prepared, reviewed, and approved to govern certain processes and vnek activities. Where a pro-cedure exists, it shall be considere @ tioj regarding the method of l performing the function. Procedures shall be followed, but not without ; question. Where the procedure directs an action contrary to what is considered proper, question that procedure and seek resolution from appropriate supervision. A procedure being questioned should not be deviated from on the basis that it is being questioned. Resolution, obtained through appropriate supervision, shall determine the proper course of action in accordance with this procedure. 4.5.2 Corrections Correct mistakes in log entries or data steps by drawing a single line through them, initialing, and dating. Do not use correction tape or fluid (" white-out") for these mistakes. 4.6 PERIODIC REVIEWS, DISTRIBUTION, AND HISTORICAL RECORDS l 4.6.1 Periodic Review
- 1. At a minimum, each administrative procedure and its associated forms shall be reviewed every two (2) years based on the
" Effective Date" in Section E, Form SM 6.1A.
- 2. If no revision has taken place within two years of the effee-tive date, perform the steps under $4.2. Document completion of the two year review by completing a new Form SM 6.1A, Administrative Procedure Cover Form. Advance the current revision number by one and assign a new effective date. Prepare a new con-tents and revision status page reflecting the new revision number.
4.6.2 Grace Period
- 1. A +25% grace period (6 months) may be applied to the 2 year administrative procedure review cycle.
- 2. Administrative procedure review cycles should be maintained as close to the 2 year anniversary as practical. The grace period is not meant to be an extension of the normal review cycle, but addi-tional time for completing the approval process, when time or man-power restrictions exist.
L ,
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WW copy 1.4' CONFIGURATION CONTROL - 1.4.1 Policy U $9
- 3. These measures shall apply particularly to the following activi-
[ ties l l a. Aligning equipment and its controls and indications in pre- l paration for operation.
- b. Altering the alignment of equipment, its controls or indica-tions from the normal or established status,
- c. Removing from service and restoring to service equipment,.Its controls and indications, j i
- d. The introduction of temporary modifications to equipment (jumpers, bypasses, etc.).
- e. ' Permanently modifying Station equipment (design changes).
- f. Custody, distribution and updating of official documentation (especially engineering drawings) that is relied upon to represent the status of Station equipment.
1.4.2 Objectives i Ensure that the Shift Superintendent and unit operating personnel are aware of, or have reasonable means available, to ascertain the status of equip-rae nt. i Ensure that information regarding pemanent and temporary changes to the ' status of equipment is made available to the Shif t Superintendent and unit operating personnel. Ensure that equipment operation and operational support activities can occur j 1 simultaneously without introducing the potential for an industrial accident or compromising nuclear safety requirements. 1.5 PROCEDURE ADHERENCE 1.5.1 Policy
- 1. Seabrook Station maintains reviewed and approved procedures to govern certain processes and wo , vities. Where a procedure exists, it shall be considered irectic regarding the method of per- l forming the function. "'
- 2. Procedures shall be followed, but not without question. Where the pfEedunTire~ cts kriTiitTGMry to what is considered proper, question that procedure and seek resolution with appropriate super-visory personnel. A procedure being questioned should not be deviated
( from on the basis that it is being questioned. The resolution, through appropriate supervision, shall determine the proper course of action in accordance with the requirements of procedures SM 6.1 and SH 6.2. i 2-1.3 SSMM Rev. 13 l
, , REVIEW COFT
\ '
JUN 2 7 E89 (- 1.5 PROCEDURE ADHERENCE 1.5.1 Policy cumstances where time does not permit following the pol in item 2 above, the procedure shall be followed unless there is a com-elling reason for the deviation.
/
~4. Forms are used in the execution of procedures to record pertinent information. Blanks provided on forms should be filled in with either the data requested or "N/A" (Not applicable) as appropriate. Large.
areas or large numbers of blanks may be filled in with "N/A" and arrows if each item is not applicable to the circumstance.
- 5. Vendor supplied manuals / documents are to be user as reference only and not in lieu of a step by step procedure. If such use is required, the manual / document must have the sa.me review, approval and control as an equivalent procedure. Excerpts from vendor manuals may be used as defined in SSMA.
1.5.2 Objectives Develop and maintain procedures necessary to operate and maintain the Station consistent with regulatory requirements and sound operating prac-tices. { Ensure these procedures are clear, concise and free of ambiguities and conflicts. Provide a formal process whereby procedures are changed or deviated from without compromising the safety or quality of Station operation. 1.6 VORKING HOURS 1.6.1 Policy
- 1. Station Staff should~ include sufficient personnel so that routine work can be accomplished without resorting to large amounts of over-time. During unit outages and temporary periods of unanticipated extra workload, more overtime may be used.
- 2. Excluding shif t turnover time, an individual should not be required .
to work more than: 16 hours continuously within any 24 hour period; 24 l hours within any 48 hour period; or 72 hours within any seven day period.
- 3. A break of at least eight hours should be allowed between work periods (including shif t turnover time).
- 4. One full day off should be allowed for every six consecutive working days.
( 2-1.4 SSHM Rev. 13
"* SSd 472D IMS# D05.99.99 -
g New Harnpshire Yankee Division ! INTRA COMPANY BUSINESS MEMO Pubsc son 4ce of New HompuP*e Subject STARTUP TEST PROGRAM ADMINISTRATION ) From G. A. Kann 02-08 District Date January 16, 1989 !
< To J. M. Peschel 01-48 Reference NRC IR 88-13 ,
I RE 02311A Startup Test procedure 1-ST-1., Startup Test Program Administration, includes two tables; namely, Test Analysis Schedule Exception, Table l A-1,'and Minimum Test Requirement for Power Escalation, Table A-2. These tables define when final review of test results must be obtained prior to exceeding certain power levels. The concept of a preliminary and final test results review program has been used in most Startup Programs and is identified in the Westinghouse Electric Company's startup documents. However, there , appears to be some confusion in the relationship between the startup program and Technical Specification requirements. The surveillance program for Technical Specifications requires operability prior to entering specific modes. Some evaluations done for the Startup program are not final until after entering the mode in which the sub-ject of the evaluation was required. It was always the intention of the Startup program to' satisfy the ) requirements of the Technical Specification. These analysis which , were deferred until later in the Startup program do not affect the l Technical Specification requirements. Again, these evaluation { deferrals were only with regard to final review of the evaluations as i required by the Startup program. Since the Startup program will be fragmented into several time phases, j it appears appropriate to divide the program af ter tha Low Power Testing. The balance of the Startup program will be revised and , reissued under 1-ST-1, Revision 3. This revision of the program will ., l reorganize the test sequence based on the planned completion of Low Power Testing and will eliminate any confusion with regard to the test ; program and the Technical Specifications, i UU G. A. Kann Startup Manager j i GAK/jw i cc: D. Allan 02-08 j L.,,Rau - 01-62 l P.. , Curney [49-5S f D. Perkins 01-48
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u IMS K04.01.07 New Hampshire Yankee Division INTRA-COMPANY BUSINESS MEMO P@te seMee of New Hompehke Subject NON PROCEDURAL MTC & ITC TRANSLATION TO PARAMETRIC CONDIT"1NS From A. G. Herrill District Date January . ,1989 To P. V. G eney Reference il WCAP-10982
Introduction:
Under Reactor Engineering Department protocol, all reactivity values, predictions and parametric corrections to be used in the perfonnance of surveillance evaluations should be approved and controlled as either a Technical Dat'l Book (TDB) figure, RD 0715; calculations from approved computer programs, RN 0717 or values specifically reviewed and approved within calculations documented by the Reactor Engineering Calculation! srocedure, RD 0716. One such parametric calculation cf a surveil 1 N 4: value, HTC, may involve any comb', nation of the following parameters:
.^S Temperature Boron Concentration Power Level Doppler Tempr . dure Coefficient Xenon & Samarium Worth Core Burnup Power Distribution These calculations may be performed to translate a measured or pre-dicted MTC value to another measured or predicted value at different parametric conditions for comparison or to eliminate ine effects of changing parametric conditions during a measurement. The following discussion shall demonstrate the wisdom and necessity to control the parametric calculations, potentially used in MTC surveillance, by the Reactor Engineering Calculations procedure, RC 0716.
Discussion: The type of control placed on any particular reactivity calculation is predominantly determined by the frequency and complexity of calcula-tion. For example, xenon based calculations are complex and performed on a 5 mim>te basis. Therefore a computer program is warranted with its appurtenant documentation and control. In contrast, Rod Worth data is expected to be used in various surveillance every month. At this frequency of use, the rod worth data is appropriately controlled as a Technical Data Book figure. However, calculations involving the manipulation of MTC for various parametric conditions are typically performed only twice per cycle under the expected surveillance program. Likewise the MTC measurement is expected to be made at the reference conditions, thereby eliminating the need for any parametric calculations. Specific Reactor Engineering Calculations, documented under RD 0716, are appropriate at this low occurrence frequency. )
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- INTRA-COMPANY BUSINESS MEMO g .
'~
To P. Y.. Gurney Date January 9,1989 Various formats for this calculation could be selected from Ref. #1, i (NDR) as appropriate for the specific conditions. In this approach, only the parameters which do not conform to the reference conditions need to be addressed in the calculation and review process. If this: process were to be procedura11 red, then at least 6 new TDB figures would be required to' control all the parametric data even if only one or;two of the parameters was required for a specific calculation. A change to these additional TDB figures is also expected over the - cycle.. Therefore, mid. cycle revision and' review of these figures would be required even though the figures might not be used at all during the cycle. Between cycles the data and methods within the NDR (Ref. II) are expected to change. Therefore, revision and review of the subsequent figures and precedure would be required even though the procedure may not be used during the cycle.
Conclusion:
Therefore, parametric calculation used for the translattoa of MTC or ITC should remain as specific Reactor Engineering Calculations under the control of RD 0726. As such these calculation,s, review and revi-sion efforts shall remain relevant to the task, if and when required.
/'AW Herri
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FRONT PANEL CE REACTIVITY COMPUTER n rs 7 s o mx. ENTER 1.234 r, n 4 , , , O O O n F4 1 2 3 RESPONSE g 'd0 0j FA,,,, ,A A F1 n 0 , - ( s' CH I CH 2 _. g , g _ m, OFF ' SLOW SasCT INPUT
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SUMMARY
F1-RESET CALCULATION RE-RESET KEYPAD F2-TBASE INITIALIZATION CL-CLEAR DISPLAY i F3-SELF CHECK SP-SPACE ' I F4-STRIP CHART CALIBRATION DL-DELETE ENTRY F5-CHANGE COEFFICIENT EN-ENTER VALUE l F6-DECREASE RAN6E < -DISPLAY RIGHT D10lTS l F7-DISPLAY NEXT COEFFICIENT > -DISPLAY LEFT DielTS ROL/ROR-NOT USED F8-INCREASE RANGE l
- - CHANGE PCM/$
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i REAR PANEL FUSE PUT A B I h h INPUT h ! ( TCR ) OUTPUT l l FAN TEST h . h h OUTPUT h I 2 9b l I i I f f- l l I y TEMP /5-T l POWER INPUT l
1.
- . THE C-E REACTIVITY COMPUIER USERS GUIDE I. GENERAL L We C-E digital reactivity couputer has been developed to provide real-time, digital computation of the reactivity of a nuclear reactor. We computer is an implementation of reactor kinetics equations, and provides valuable information on the state
- of the reactor. W e instrument is a useful tool for measuring reactor physics data during start-up testing. We computer calculates reactivity changes due to the derivative and source terms of the reactor kinetics equation as well as six delayed neutron fractions.
n dn , Q - @ , ,, , r o
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E,% dt , (___N __ dH p; - p d-A; H; vhere n -Neutron density () : Reactivity H;: 1-th delayed neutron precusor density A;: Decay constant of the i-th delayed neutron precusor jl+: Prompt neutron lifetime S: Neutron source intensity (3;: Fractional yield of the i-th group of delayed neutron p: Fractional yield of total delayed neutron The Reactivity Computer solves a digital formulation of the kinetics equation using a LSI-il/23 microcomputer. We unit takes a 0 to 1 volt signal proportional to neutron flux, and produces a -10 to +10 volt output signal proportional to reactivity. We output is available on a digital panel meter and as an analog signal for input to a strip chart recorder. An additional, buffered analog output is available for input to a data logger. Reactivity coefficients are entered
v.
' 2.
through a numeric keypad. The keypad ~is also used to control the operation of the instrument. ! We reactivity computer can be programmed to output in Percent Milli-Rho. We conversion from reactivity in dollars to reactivity in PCM units is as follas: RPCM = @ * @ .* 10E5 where: RPCM = Reactivity in Percent Milli-Rho o 5 e
v , i , 4.
.f III OPERATIQi-y ,
When the Reactivity Computer is turned on, the' operator keys in.the~ reactivity coefficients and optional temperature data "using the keyboard / display unit. See Figure 1._ 2e keyboar & display is also used in controlling operation of the-instrument:-for resetting, checking or changing coefficients, for. changing output-i ranges, for calibrating the strip chart recorder, and for generating the self-check signals to verify results. Se various control functions are initated by pressing the appropriate keys. mis can be done at any time after the initial set-up. Bere are. six output rangesAnultipliers: $10, $1,z $0.1, and 10,000, 1000, 100
. PCM. AMitional' control is available with the FAST /SIOf switch for 4 selecting the f requency response of the filter boards. Se Stat
. position otocesses the data throuah a 2 hertz filter, while the
~
~ 7K5T Dosition utilizes a 20 hertz filter. % fratnwnew remnanas - ~
selected should consider the rate of change of the ingut sianal, as wen as se amunc of noi~se~ in the =4 cmai - Tuniem11y. th FAST Tesponse should be used for rod droos or =F=a hhHan anlutinna, while the SInf response should be selected for normal low power
~~gah s em F*cting. The rear panel Treir/SELF TEST switch allows one
'T/A port to serve two functions. In the self. test position, self test voltages are internally connected to the Self hst BNC connector. In the. TEMP position,-_ this connection is broken allowing normal ~ operation.
CAUTION: railure to follow display unit prompts to position the TEMP /SELF TEST switch to the appropriate position will cause the haperature compensation output signal to feed-back into the inputs. his will.. _ cause the anplifier to saturate and the unit will not perform normally. F mbt - ST;Ep poJeOG SoLOTIMS Sg - conam w wet. Pystcs -mnn 1 I }: L l-f.
l'. 8. V. DETAILED ITYPAD OPERATION A. START-UP
- 1. obtain a list of the following reactor kinetic equation coefficients:
- a. SOURCE: Neutron Source strength (S) - Normally zero for commercial power plants. In units proportional to the input signal; for an input signal in the one volt range, 5 is 16384 times the relative source strength in volts. For example, if the neutron source component of the 1 volt signal is 1% of the total signal, then S
-16384 X .01 or 163.84 .
- b. YIELD (@): The total dslayed neutron fraction,/
not percent. ** l
- c. LIFE: Prompt neutron lifetime (1*), in seconds./
- d. DECAY (i): Delayed neutron group decay co tants (A1, . . . ,A6) - in inverse seconds. ,
- e. YIELD (i): Delayed neutron yield from groupi. -*
(pl,...,
- 2. Connect the rpowe(36) - fractions and interconnecting cables.not percent. ** /
- 3. Turn on the power. .
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.doesnotcontaintemperaturecompensating[optip6p eed to ste #8,
[ kv 4. elect a temperature signal proportional t erator ef' g rature. ror example:
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- Cold Leg Temperature Te rature Range - 500 to 0 degrees F.
Elect ' cal Range - 1 to volts
- 5. Select the f owing tempe ure related data:
- a. m AX - imum rature expected during testing corr ng to a full scale (10 volt)' input, degre .
- b. TBASE - se rature where zero temperature crection - desired, degrees F.
- c. m - Minimum te rature expected during testing {
corresponding t minimum scale (0 volt) input, degrees F.
- d. ALPHA - Isothermal tempera e coefficient, De1ta-Rho / degrees r . _ , .
_.~ .m- _ _ -- # v
** Delay Neutron coefficients YIELD (@i) and YIELD (@) should have
)
appropriate neutron importance weighting, prior to entry into the Digital Reactivity Computer. - . - - _m_._ .m--___._. _ _ . -____._- . _ _ _ _ _ _
, . r ~-
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9. I ;
- 6. C culate the raw temperature voltage input expected j
during testing: For example:
.' MAX = 550 F I E ASE - 545 r MIN = 540 r ope = r/ V =(650-500)/(5-1) 7.5 degreesr/
Volt off t = (500-37.5)X1 - 46 r i Therefore: r= 37.5
- v+ 2.5; Solving for V yields the rmula:
V-(r - 462.5)/3 Solving for VMAX and VMIN gi - VMAX = (550-462.5) .5 - 2.333 volts VMIN = (540-462, /37. - 2.066 volts To utilize the full ran of the tempe ute input,it is recommended that a hi quality instrumen tion type DC amplifier be use o both maximize the e cted temperature range i.e. voltage) and act as a ffer betw;en the te rature source and Reactivity C ter. .
- 7. Utili ng a voltage source, adjust the gain and ffset of e external instrumentation ampilifier until y7 . 66 volts input yields 0 volts of the amplifier 3 r.
_ ~2.,333 volts input yields +10 volts out--of the amplif _..'._..~ --
~ ~
- 8. Key in the coefficients as requested; follow each entry with the ENTER key. See section (B) for more information on using the keypad.
- 9. After the last coefficient is entered, the Reactivity computer will display "X$1" in the' keypad display and start the calculation. This display is the range of the reactivity output. The OtfrPUT a p ars on the canel meter to the left. Multiply the CUTPUT by the range to oct, reactivity.
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10. V. DETAILED KEYPAD OPERATION (Continued) B. Notes on Using the Keypad
- 1. Fixing Typographical Errors The membrane keypad should be pushed firmly and squarely, each character should be verified on the display as it is entered. If you press the wrong key 234,3 -22 while enterins a coefficient, $ust press DEL to delete it, then re-enter the character. For multiple missing 2 34 0 45
- N- characters press DEL several times to delete characters then re-enter the data.
- 2. Rotating the Display
- F7 is used to display the coefficients. Identification along with the coefficient is displayed. For example:
YIELD (2) = 0.0012340 The above line is too long to be displayed in the ; twelve character display. To view the rest of the line, press >. To rotate back, press <.
- 3. When a Black Function key is pressed, the display .
should show "&" and the number of the function-for example,"&l" for Fl. If the "&" isn't there (e.g. "1"), then press DEL and again press the function key. The black function keys are used to change output ranges, reset the computer, and verify and change coefficients. W e following is a description of the uses of the function keys:
'(See Figure #1)
Fl: RESET; Key in: F1 ENTER , This function displays the output range'and restarts calculations with the present coefficients and the current input signal. F2: TBASE INITIALIZATION; (Optional) Key in: F2 D7tER Wis function causes the cceputer to sample the temperature input port (TEMP) and calculate a 10 second average value and to assign that value to TBASE. Function key F7 (Display the Next Coefficient) can be used to check this value computed by the F2 i function. F3: SELF-TEST; l Key in: F3 ENTER W e display message will advise " FLIP TO S-T". Switch the TEMP /SELF TEST switch to SELF TEST and connect the SELF TEST BNC output connector on the rear panel to the INFLTT A and B connectors. Then press ENTER. l .
11. l V. DETAILED KEYPAD OPEPATIQJ (Continued) This function causes the instrument to reset and then generate one of two self test signals. We first time this key is used, a 0.4 volt signal is generated. After approximately a 50 second settling period, a doubling step from 0.4 to 0.8 volts is generated. h e reactivity computer will display $.50 and then decay to zero after several minutes. We next time the key is used, after a 15 second settling period, a triangle waveform is produced. W e triangle wave ranges from 0.4 to approximately 0.8 volts to 0.4 over period of 200 seconds. The generated signal alternates between these two waveforms, changing each time F3 ENTER is used. To repeat the step doubling test, use F1 direr to reset the computer then r3 DfrER. his function (F3) is used to verify calculations. A strip chart of the output resulting from the doubling step can be compared to an analytical prediction and verified for . accuracy. The triangle wave may be used to verify long-term stability of the device. After a few minutes the output of the triangle wave solution should settle into a periodic pattern. If either of the self-tests fail, the cause is most likely a mistyped coefficient. Use r7 to verify the coefficients.~ To return to normal operation, reconnect the neutron flux signal to the INPlTI A and B BNC INPt1T connectors, switch the selector switch to TEMP, and use il to reset the device. i ) I F4: STRIP CHART CALIBRATIO4: Key int r4 DfITI Each time this function key-is used, a different calibration signal 1rr generated on the reactivity 4 output channels. We sequence is: 0,1/2 full scale (1/2 PS), full scale (rs), 0, -1/2 full scale (-1/2 PS), and - full scale (-rs).rull scale represents + 10.0 volts. After -rs, the sequence repeats. We output is independer.t of the range. These signals allow calibration of the reactivity strip chart pen. As each signal is output, it is also displayed on the keypad / display unit. Note that this function does not reset computer. We calculations go on as usual; however the results are not displayed while strip chart calibration function is being performed. When the calibration is complete, pressing DiTER results in the reactivity output being displayed as calculated. Function F4 does not cause a reset. ,
12. V. DETAILED KEYPAD OPERATION (Continued) PS: CIWGE THE COEFFICIDE PRESDELY DISPLAYED Key in: F5 De First use F7 to display the coefficient to be changed, then key in F5 Dm. 'Ihe value will be requested (e.g. SOURCE?); Key in the value followed by DEER. Note that this function does not cause a reset. After changing a coefficient, F7 may be.used to display it. F6: 'GE 'IO NEXT LOWER OUTPlTT RAtGE Key in: F6 ENTER Ranges are $10, $1, $0.1 and 10,000, 1000, and 100 PCM. F6 will cause a change from one range to a lower range, if one exists. Note F6 does not cause a reset or effect the reactivity calculations. F7: DISPLAY THE NEXT COEFFICIDU; . 7 i Key in: F7 DCER
' Each time the function key is used, a different coefficient is displayed in'the keypad display.
The sequence is the same as that in which the
]
I coefficients were entered at start-up. After the last coefficient, the sequence repeats. it may be necessary to use the > and/or < keys to view the g coefficient and its label (See Section B). g Note that this function does not effect the g calculations. After displaying the coefficients I s press DUER to disp 3 By range. V.
< F8 y CHA!GE 'IO THE NEXT HIGHER OLTTPLTT RAtGE; k ~
Key in: F8 C This has the o site effee F6. F8 will cause a change from one a higher range, if one exist. If the range is at its highest value, there will be no change. Function F8 does not cause a retet or effect the reactivity calculations.
-: CHAtGE 'IO PCM/$
Key in: - DCER _________ Each time this~ key is used, the output re Maty units are changed from $ to PCM and vice versa.) This
~
function is oHIy actWe Tii the eB=nd..po_dg and is not applicable when entering data, i 6
- --_____________D
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14. n VI. SUGGESTED SET-UP PROCEDURE Prior to the start of testing,~ all equipment should have been checked for alignment and verification of proper c,peration. The following set-up example is based on the use of a Linseis strip chart recorder for recording reactivity results. (Other recorders should be set up in a consistent manner.) A. Recorder Set-Up (For SELF TEST) f 1. Green Pen Scaling (Flux Signal)
-, .\y Range - 1 volt full scale
, / Pen offset - position to left side of the chart with rf the VAR / CAL /0 switch in the O position.
# - V,,- Return the switch to the CAL position.
~
.D 2. Red Pen Scaling (Reactivity Signal)
,0
/ '
/ Range - 10 volts full scale Pen offset- position the pen to the center of the
/ k chart with the VAR /CAI/O switch in the 0 position. Return the switch to CAL
/
f gc' position.
\9p 3. Chart Speed Ay 60 enVmin (minimun) will be needed for doubling check f M solution.
7 dl B. Reactivity Computer Set-Up This section uses relative reactivity units ($) for simplicity and a minimum hand calculations. Operations are equally valid with PCM output to check with an analytical solution in PCM.
- 1. Disconnect the flux input cables from INPtTT A and B.
- 2. Place the TEMP /SELF TEST switch to the SELF TEST position.
- 3. Connect the SELF-TEST output to INPtTT A and B and the strip chart GREEN pen input.
- 4. Place the front panel INPtTT SELEC'IOR switch to (A+B/2).
- 5. Place the FAST /SIG switch to the FAST position.
- 6. If not already done, turn on the Reactivity Computer and key in the coefficients as requested. i
- 7. Use the function F7 (DISPIAY NEXT COEFFICIENT) to check the coefficients. IT any are in error, use F5 (CHANGE PRESD7T COEFFICIENT) to correct them.
15. VI. SUGGESTED SET-UP PROCEDURE (Continued)
- 8. Use functions F6 (CIWGE 'IO ETR PRGE) or functions F8 (CHNGE 'IO HIGHER RMGE) to select the $1 range.
- 9. Use function F4 (STRIP CHART CALIBRATION), to check scale of the red pen (reactivity). The scaling selected for the red pen will result in a value of $.50 driving the red pen to either edge of the chart paper, depending of polarity of the signal. This $ 50 value corresponds to 1/2 PS, driving the pen to the right,
-1/2 drives the pen left. Press direr to exit the F4 function.
- 10. Initiate the doubling check by depressing the F3 (SELF-TEST) and direr keys.
- 11. A 0.4 volt signal will be generated and after approximately a 50 second settling period, the range of $1 appears on the keypad display and a doubling step of 0.8 volts will be generated. The reactivity will increase immediately to approximately $.50 and then decay to zero after several minutes.
- 12. As the reactivity decreases below $0.05, use the F6 (CHANGE 'IO n'ER RANGE) key to change the reactivity ,
scale to $0.1 full scale range.
- 13. After the reactivity has decayed to less than $0.009 (or after 100 seconds), stop the strip chart recorder and compare the analytical prediction and the Reactivity Computer output by completing Table #1. If the Reactivity computer solution and the analytical solution differ by more than 5%, re-check the coefficients and verify that the filter RESPONSE switch is in FAST.
- 14. Disconnect the reactivity computer SELF-TEST output.
If TEMPERATURE COMPENSATED equipped, switch the TEMP / SELF TEST switch to TEMP. , ,,
m- . _ _ . , . _ _ 17. VI. SUGC-ESTED SET-UP PROCEDURE (Continued) D. Equignent Setup for Operation
- 1. Disconnect the Reactivity Comput e-TE!.F-TEST output y fromINPtJTAandBandfliptheTEMP//ELFTEST switch to TEMP.
- 2. Connect the output signals on the back of the Keithley piccameters to INPUT A and B.
- 3. Verify the output selector switch on the back of the Keithleys is set to " Voltage".
- 4. peCtinrReactivity Computer input selector switch to v' (A+B/2)
- 5. Connel:t the UIC high voltage cables to the high voltage powe,r supply and the UIC signal cables to the inputs of the Keithley picoameters.
- 6. Set the voltage output on the high voltage power supply to zero and turn the supply on. Slowly increase the output voltage until the operating voltage is
~
reached.
- 7. Turn on the Keithleys and select a range that gives a mid to 80% of a full scale resding. Place the Keithley meter switch to + or - as determined by the polarity of the high voltage supply. (Do not use the center zero position on the nodel 610 Keithley front Panel.)
l 8. Use Function F6 (CHANGE 'IO NEXT IDh'ER RAtGE) or F8 (CHANGE 'IO NEXT HIGHER RANGE) to select a reactivity g ,. range consistent with the expected change of the 43
- 3, reactivity output. 05Unuq 100 Pcm g- Sv ----jZ
W#
- 9. Rescale the strip chart recorder pens to be consistent with the expected change of the flux signal (0 to 1 volt) and the expected change in reactivity
(+/-10 volt e x, on all ranges). For increased resolution, the recorder offset capability and input range selector switch can be used to expand the scale of the reactivity trace. I
Y,h; R 18. VI. SUGGESTED SET-UP PROCEDURE (Continued)
- 10. Rescale the strip chart recorder blue and brown pens to be consistent with the expected change in TEMPERATURE COMPENSATED REACTIVITY (ICR +/-10 volt-max, on all ranges).and the expected change in moderator. temperature (0 to 10 volts). Verify that the strip chart recorder brown pen reading is consistent with plant temperature indications.
- 11. Select a chart speed that is consistent with the expected change in reactivity and meets the data reduction technique. ..
- 12. Select an input filt c(FAST SLOW) that is consistent with the test being efo .
- 13. Use F1 to RESET the calculation. Occasionally, while making reactivity measurements, it is prudent to check the strip chart recorder,for drift using Function F4 (STRIP CHART CALIBRATION), provided the strip. chart range selected is consistent with the F4 function output ranges and to check the coefficients .
using function F7 (DISPLAY NEXT COEFFICIENT)..Using these functions does effect the reactivity calculations. However, it is recomended that these checks be done when test data is not being taken.
V SECTION 2 OPERATION CAUTION 2.1 INSTALLATION A two-second delay in the center off posi. WARNING tion is required when switching polarity. This unit produces hazardous voltage. Do not apply line voltage input unless ade. Voltage Switch:The voltage switch sets the output quate ground is connected to the unit and voltage in increments of 500V from OV to 2000V. the high voltage output has been properly Voltage Dial:The voltage dial is a 10 tum digital dial that connected. supplements the Voltage sw'tch - setting by up to 1000V. Figure 2-1 illustrates mounting and clearance dimensions as WARNING well as the position of the controis and connectors on the front and rear panels. A package containing screws and rub- Before turning the power on to the ber feet is supp!ied with each unit. For benchtop use, instrument. check the dial rotation of the remove the four corner screws holding the bottom cover. Voltage Dial. When the dial is fully and repiace with the supplied hardware. counterclockwise, it is set at 000. When - the dialis fully clockwise,it is set at 1000. 2.2 FRONT PANEL CONTROLS AND TERMINALS Monitor the meter for the output when the power is on. Power Switch:A toggle switch turns the line power on or off to the entire instruments. NOTE Pilot Light:The pilot light ILEDI tums on indicating that the The output voltage is the sum of the Voltage line power is on. Dial and the Voltage Switch. Output Meter:The output meter monitors the output voltage. The rneter operation is indepenesnt of the AC input power; therefore. It reads the output at all times. Polarity Switch:The polarity switch sets the output for Output Connector:The output connector :s a MHV type positive or negative potanty. Also, it switches the output UG331/U connector. It mates with a MHV type UG932/U voltage off. Connector.
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o j 4 l l' 1 . 22 The Controls: , Fig.1 is a front view of the Instrument. All of tha various operating j 1 controls are situated on the front and are easily accessible. They are 1 pointed out in Fig.1. Clips for attaching plexiglass scale Fibre-tip pens Controls for chart drive
..,' Measurement range input modules ,! Pull-out writing table l
l Paper take-up compartment Pen lif t lever
. On/of f switch (L2025 rect panell 1
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l I, Fig. 6 Chart Drive Control hh Pushing Duttonhaises the chart speeds sequentially from .1 (0.12) up to 200 (300) cm/h (min), as indicated by the LED display. Pushing butto lowers the chart speeds through the whole sequence. As long as the button is despressed, the speeds will continue to change automatically. When button is' released, the speed will remain at the displayed setting. S., g h Raised position (button released) means chart drive is shut off.
' Depressed position (Dutton locked) means chart drive is operating.
18 r.4 h Raised position (button released) means chart drive is operating in forward direction.
' Depressed position (button locked) means chart drive is operating in reverse direction, lf this button is released, the chart speed indicated by the LED display and h all other settings (LED display) apply. If it is depressed the chart drive ")
i follows only the remote control. In this case the remote plug has the pin assignments indicated in Fig. 7 (see next page). 1 s
'I h if buttonhis depressed, the selected chart speed indicated by the LED display means cm/ min.
If push buttenhis released, the indicated speed means cm/h. This f eature allows the selection between two different chart speed sequences, if the button is depressed the sequence is 0.12 0.3 0.6 1.2 3 6 12 30 60 120 300 cm/ min or em/hr. (convenient if min, and / or hr. marking are desired.) When this button is pushed down it actuates the f ast advance of cnart, h independent of selected chart speeds. (however, it operates only if button is released--internal mode). t I C AUTION! Avoid running the chart drive without paper being inserted!
m ,. . . . . . .. .. w ... I j . , .. l- . G8405 16 ranges, O'.5 mV to' 50 V
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" lo w" input teeminal ground of fset adjustrnent (see operating procedures) two step cffset selector (100 % or 200 % of telected measuring range) l
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01/01/80 WISHLIST MODULE REASON FOR REMARES RESPON$1BLE REGUESI SECTION esters ::::::::::::::::::::::::::::::::: ::::::::::::::::::::::::: :::::::::: I '72301 PR06 RAM RED'. - INSPECil0N DUE ^ 2514 MANDATORY MODULE - 5/U TEST RESULTS IN EVALUATION 72302 - PROGRAM RED. - INSPECT 10N DDE 2514 MANDATORY MODULE - 5/U TEST WITNESSINS IN
~72400 PROGRAM REO, - INSPECT!DN DUE 2514 MANDATORY MODULE - 5/U TEST PRD6 RAM In 72592 . PROGRAM RED. - INSPECTION DUE 2514 MANDATORY MODULE - INITIAL CRITICALITY PNR WITNESSIN6 72596 ' PROGRAM RED. - INSPECT 10N DUE 2514 MANDATORY MODULE - PRE-CRiilCAL DATA REVIEW PNR 0000A RESTARTREQUIREMENT 2514 MANDATORY 10CFR50.55(E)CLOSE0VT-EFU -PM SYSTEM TESilNS (86-00-05)(RAll)
-64521 PROSRAM RED. - INSPECT 10N DUE 2514 MANDATORY MODULE - S/U RADNASTE M ERS 83521 PROBRAM RED. - INSPECT 10N DUE 2514 MANDATORY MODULE - S/U RAD PR0iECT10N M FR$
83750 CORE RED. - INSPECT]DN DUE 2515 CORE MODULE - RAD PROTECil0N (RAll) FRS B4750 CORE REO. - INSPECT 10N DUE 2515COREMODULE-RADNASTE(RATI) ERS 3??00 CORE RIO. - INSPECTION DDE '2515 CORE MODULE - DESIGN CHANGES,- F/U IR 88-11 STS FORDRSSALP(RATI) 87828 CORE RED. - INSPECT!DN DUE 2515 CORE MODULE - MODS AND MDD. TESilN6 - F/U IR DRP B9-11FORDRSSALP(RATI) hop CURE Rt0. - INSPEtil0N DUE 2515 CORE MDbOLE - SELF ASSESSMENT - F/U IR 88-15 DRP (RATI) 71710 CORE RED. - INSPECTION DDE 2515 CORE MODULE - ESF SYSTEM UALED0n (RATI) 9RP 72701 RESTART REQUIREMENT 2515 APP.B MODULE - MDD. TESTIN6 (RATI) STS
~
%2700 RESTART REQUIREMENT 2515 APP.BMODULE-MAINTENANCEPROGRAM(RATI) OPS
$1700 RESTART REQUIREMEKi 2515 APP.B MODltE - SURVEILLANCE PROCEDURES (RATI) OPS N700 RESTART REQUIREMENT 2515 APP.BMODULE-PROCEDURES (RATI) OPS 71715 RESTART REDUlREMENT 2515 APP.B MODULE - CONTROL RDOM DBSERVAi!DN DRP (RAll) -
0000D Sl6NIFICANT FOLLONUP OF DPEN ITEMS (112500/20) OPS
L. 1-ST-16 Rev. 4 Page 13 of 13 INITIALS /DATE
/ 7.3 The pressurizer level is 25 + 3%.
/ 7.4 Control Bank D is positioned as necessary to maintain a constant flux level in the zero power test range.
/ 7.5 The reactivity computer is ready for physics testing.
/ 7.6 The unit shift supervisor has been informed of the completion of this test.
/ 7.7 Any controller or setpoint changes made as a result of this procedure have been documented on Attachment 9.2 of 1-ST-15, Reactor Plant Systems Setpoint Verification, and have been forwarded to the Station I&C Deparbnent.
8.0 ACCEPTANCE CRITERIA
/ 8.1 The reactor is critical.
/ 8.2 The measured critical boron concentration is within the
#Et4~11.w cr1Lical boron concentiativia l',-'t' of 6 M Ttachment 9.7.
/ 8.3 The average reactivity measurement error shall be less s ,,___ than 4% (Step 6.5). ,
9.0 ATTACHMENTS 9.1 Base Count Rate Determination 9.2 Count Rate - 1/M Log - RCCA Withdrawal 9.3 Count Rate - 1/M Log - RCS Dilution 9.4 Initial Criticality Data 9.S Reactivity Computer Operational Check 9.6 Appendix A - Shutdown Monitor Test 9.7 Estimated Critical Boron Concentration 9.8 RCS Boron Concentration tog 9.9 Source Range Signal to Noise Ratio Determination 9.10 Intermediate Range Channel Constants and Low Power Flux Mapping Range 1 I
K. " 11-ST-19 Rev.-2 Page 4 of:6
-4 INITIALS /DATE.
/ 6.1.4' Using RN 1732, analyze the flux ma data to derive-el factors an ~
ttach copies tion'as-Attachment 9.2.. i' / 6.1. 5 After the initial map at AR0,-evaluate the traces to verify the upper and lower core limit settings. Modify settings per Reactor Engineering instruc , tions to align traces.to the grid depressions. 6.2 Control Bank D at 0 Flux Map
/ 6.2.1 Verify that control bank D is at 0' steps and control bank C is > 200 steps.
/ 6.2.2 Using RN 1733, generate a full core flux map.
Attach copies of all flux map.information as
' Attachment 9.1.
/ 6.2.3 - Using the flux map data collected, verify that the reactor remained stable (delta. Rods < 5 steps, delta power 1 0.5% of the initial vaTue) through-out the map. If the criteria are not met, the test may proceed as long as the effect of Insta-bility on the results is ' determined and applied to
- these results. -If this'cannot be done, the flux map must be repeated per Step 6.2.2. l
/ 6.2.4 Using RN 1732, analyze the flux map data to derive hot channel factors and power distribution infor-mation. Attach copies of all incore analysis information as Attachment 9.2.
6.3 Control Banks at HZP Insertion' Limits Flux Map
/ 6.3.1 Verify that the control banks are at the hot zero power insertion limits +5/-0 steps.
/ 6.3.2 Using RN 1733, generate a full core flux map.
Attach copies of all flux map information as Attachment 9.1.
/ 6.3.3 Using the flux map data collected, verify that the reactor remained stable (delta Rods < 5 steps, delta power < 0.5% of the initial vaTue) through-cut the map.i lf the criteria are not met, the test may proceed as long as the effect of instabi-lity on the results is determined and applied to
- i. these results. If this cannot be done, the flux i map must be repeated per Step 6.3.2. 3
l 21 Review of obsa vations from previous NRC inspection reports (IR) to verify implementation of findings into the program.
- b. Test procedure Revig-The following observat'ons were made while conducting a review of the startup test (ST) procedures. A list of procedures reviewed are !
provided in Attachment No. I to this report. (1) Generic comment for all ST procedures.
..The revision numbers of procedures provided in the reference Any fevWks N fkU1 section of the ST procedures are not the latest revision for i m c(u,Q o pe b w some of the procedures referenced. It should be noted that the 4 first prerequisite step requires the test director to review the MA. revision numbers on references. If . the revision number is incorrect, the test director is to review all changes to the procedures.
(2) ST-1, "Startup Test program Administration" (Revision 2) Tables A-1 and A-2 provide minimum test requirements for power escalation. The tables require power escalation above ten per-cent to be contingent upon completion of the hot zero power (HZp) tests. Ho.<ever, the technical specifications and surveil-lance programs assure that HZP tests will be completed prior to I five percent power. The licensee agreed to review these tables for consistency. o (3) ST-1, "Startup Test Program Administration" (Revision 2) pffluw J s/4 f Step 4.15 requires that the power increase rate shall not' exceed three pe rcent per hour when above twenty percent power. This ICTs $E07.3//640 precaution, however, does.not include the fuel vendor's recom-mendation of three steps per hour for rod control cluster assembly withdrawal. (4) ST-16, " Initial Criticality" (Revision 2) I Step 8.3, " Acceptance Criteria" states, " Measured reactivity, l period and startup rate data (Step 6.5) is in agreement with the 6I/ 6 Y predicted values from reference 2.11 (Westinghouse design l l report)." Other than the above, there is no quantitative ; acceptance criteria for determining the accuracy of the reactiv-ity computer. Such guidance is available in procedure RN1736 j which requires the measured reactivity to be within four percent l of the predicted value. l l
l l 22 (5) ST-19, " Flux Distribution Measurement at low Power" (Revision 1) g_.g The FSAR page 14.2-5 " Flux Distributions at low Power" states that the acceptance criteria is, " Flux map results are in agree-
/5 er/vgucle ment with the predicted distributions contained in the Westing-g house design report for Cycle 1." Procedure ST-19 acceptance criteria provides criteria for the relative power distribution M Ny a but does not include criteria for incore tilt.
g gg ) Rx-1704, " Moderator Temperature Coefficient Surveillance" (Revision 2) Ik SS*4783 This procedure directs extrapolation of the moderator tempera-N AM A ture coefficient value using graphs and tables. Further guid-fx/bp ance is needed on how to make this extrapolation. The above observations were discussed with licensee representatives for their consideration in enhancing various startup test procedures. The licensee acknowledged the inspector's observations and agreed to review each of the observations for incorporation in future revisions of the applicable procedures. No violations were identified.
- c. Qualifications and Training The inspector reviewed the qualifications of the test directors to verify compliance with the requirements described in the FSAR. It was noted that one of the test directors did not meet the formal education requirements. The licensee stated that the qualifications of all the personnel associated with the startup program were being reviewed and waivers will be evaluated in accordance with the FSAR
! for personnel requiring them. l The inspector observed a formal licensee training course on the startup testing program. The course was part of the licensed opera-tors requalification program. It was conducted by the Startup Program Manager and lasted approximately four hours. The lectures and hand-out material provided the licensed operators a detailed description of the startup testing program. The course topics included program administration, organization, test equipment, and applicable proced-ures. The training provided the operators an awareness of the start-up test program structure. The course also provided the operators a chance to provide feedback to the startup testing program management. l d. Low Power Test Program The inspector reviewed the administration and control of the NHY startup program, as detailed within the Startup Test Program Descrip-tion (STPD) manual . Discussions were held with the Reactor Startup Supervisor with respect to the organizational responsibilities. It was also noted that a few changes had recently been made to the STPD manual. These changes, subsequently discussed with the licensee, had
,.v.,.-- - ' - ' " ' ' . _ _ -
y . i I se. en toese e,ee entes.e *ogme sme se +e IM4 w etsee te ;ra 9eus ee t \ esse en % esAs amme em..es s s estas ta, ed see se an e*een Based on the res te= cf test program and t ; in the following section (2 2) sentatives e s t p roc eew r,
. and discussion as cestetce * '
. 2. 2 oropram con,tinues to be ef fectiveensee's .
and startup acceptablethe test inspe i Test Procedure Review The inspector reviewed the 15 test procedure for Section the2.2. attributes identified in inspection rs listed in Attachment A The inspector identified the following items:eport 50-443/86-3 (1) 1-ST-13: The current procedure (Rev.2) provides instructi of verify thecore calculated nuclear instrumentation thermal power. (NI) readings be within with respect to calculated core conditions. vely N gr.Mt.d ther 4 8 (2) 1-ST-26:
, ,W, 26 The current procedure (Rev.1 TS required value.the test personnel to compare the measu) F-M red Mb RC ow against the YP& t.
.(3) 1-ST-29:
i address how to meet test objective 1.3 with regar thermocouple check, and (b) does not provide e incore ry l lines iftest, plateau quadrant power tilt ratio exceeds evaluation 102guideat- th hW e 30% power bg (4) 1-ST-38: 7g v g O T/ cautions to direct test personnel to potential troub for monitoring the test progress and equipment ocations O (,8(5) 1-ST-39: response. i ( The current procedure (Rev.0 [ ( temperature limits and pressurizer safety v devaluat does not include 0 l' ressure/ a ves. The inspector discussed these concerns with the li ative who indicated that these would be revision. censee incorporated represent- it changes have been incorporated.These procedures n o the next will be reviewed e the licensee's sound. test precedures are well prepOther than the items as noted ab Lead Reduction (1-ST-35). Unit-38),and Station Blackout Test (1-ST-39 - Trip as Large from 200% Po into the test procedures.and lessons learned incorporated from these) simulatio L e t
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--_---_____._____--._______._---__._-__________a
1 MRC Et* TWT NOT? FICA 970N WCOK$HEET Notification Time ' Facility or organisaties Unit [3 kh Seabrook Station 01 l Caller's Mame Telephone pueber (f or cent back) j , 1-603-676-8330 or j
- h. O'Fll. F4, / 45 l-603-669-4000 13201 ',
. /
EVENT C1.A5$171CAIlos
- 1 8 EVENT CATEGott Initiation Slanal Ceneren Eme raency V Beactor Trio /$crea -
Site Area Emeraency E5F Ac tuation N . Alert ECCS Actuatios Dousual Event Safety Injection Flow l I hr (6_nr ) 50.72 Mon-Emergency LCO Action Statement i br Mr Security /$afeauards Other Transportation Event Othert system ps4 f9c3T-Components p1_? r 4.opi CAUSE OF FAILURE Event Time , Sone EST
< Mechanicet ./ or EDT Electrical Personnel Error Procedure ina de q ua c y Event Date Other: Month Day bl lb LVENT DESCRIFILOW
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- ItHY ORO Ntc tesident Press telease vall be Mode of operation until Correction: J released, YES NO Estimate Time to Restart:
f ER 2.0D Rev. 06 Fage 1 of 2
_n-( f l MEMORANDUM OF TELEPHONE CONVERSATION I I ( INDIVIDUAL CONTACTED AGEhCY DATE II.ME i i Ray Sud - IlItc. , _ ,n %", CONVERSATION SUBJECT CONVERSATION INITIATED BY l1/(Jrs(.t'
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w ayeis almus3 6 MJ-LcE NHY #890492 Naw. Hampshire MEMORANDUM Subject Procedural compliance From E. A. Brown D* July 10, 1989 To :All Site Employees Reference As you know, we recently experienced a situation in which a low power test-program procedure was not strictly followed. As a result, the credibility that we have all worked so long and so hard to build has been affected. Procedural ~ cornpliance 'is the foundation for the operation of Seabrook Station, and I want to stress that every person working on site is responsible for following the procedures in place. This applies to all of us -- operators, engineers, technicians, managers, contractors, administrative personnel -- each and every person working here at Seabrook Station. Think for a minute about the variety of prc'cedures we have in place -- procedures for Emergency Response Operations, Health and Safety. Human. Resources. Management. Training -- all in addition to the New Hampshire Yankee general procedures manual. While these procedures are living, changing documents over periods of sime, they are the' rules that must govern our conduct at any specific point in time. Failure to follow procedures can lead to a breakdown in any organization, and procedural compliance is especially essential in the operation of a nuclear power plant. My intent in sending out this memorandum is not to single out any individuals or groups. In fact, I don't believe it's fitting for any of us to comment on recent events without giving serious thought to our own knowledge of, and compliance with, the procedures we are all expected to follow each day. If you are unclear about a procedure, ask questions and get answers. If you have a suggestion to improve a procedure, use the system to make the suggestion. But at all times, you must follow the approved procedures. Deviations from procedures or non-compliance with procedures will not be tolerated unless there are issnediate, overriding safety considerations involved. We have a responsibility here at Seabrook Station to license this plant and operate it safely and efficiently for many years. Procedural compliance is a must for us to fulfill our objectives and meet our responsibility. I expect that each of you will review procedures on a regular basis, and adhere to procedures at all times. Such conduct is the responsible and professional standard we must all uphold every single day here at Seabrook Station. N Edward A. Brown EAB:js1 New Hampshire Yonkee Division of Public Service Company of New Hampshire i P.O. Box 300
- Seabrook, NH 03874
- Telephone (603) 474 9521
) 1
H LC H " n TEMPLE- WILLIAM J 49-CE .NHY #890520 Nes Hampshire Yankee - -- Subid Core Values and Work Ethic From E. A. Brown July 19, 1989 To e ence All New Hampshire Yankee Employees We can expect that, in a few short months, New Hampshire Yankee will begin operating Seabrook Station commercially, producing electricity for one million New England homes. I am confident we will meet this challenging responsibility as a first-rate team of professionals dedicated to the safe, efficient operation of our power plant. Central to our success as an organization are certain core values and a work ethic that we must follow to achieve success. In May I began working on a statement on core values and work ethic for New Hampshire Yankee. The document you are receiving today represents review and input from a variety of New Hampshire Yankee employees. I believe it is important that these values form the b6 sis for everything we do as professionals and as New Hampshire Yankee employees. This core values and work ethic document will serve its intended purpose only if it is formally integrated into the New Hampshire Yankee culture. These values must be reinforced, used and reread on an ongoing basis. To that end, I have directed that the Employee Relations Department take steps to include implementation of this policy statement in the formal New Hampshire Yankee personnel evaluation process. For the organization as a whole I have directed that there be prepared for me a semi-annual review of our adherence to this core values and work ethic policy by the Independent Review Team. I see this document as a continual reminder of the significant responsibility placed on each of us to operate Seabrook Station and manage New Hampshire Yankee in the most professional manner possible. Everyday application of these core values and work ethic will ensure that we're always ready to meet the challenge of our responsibility. n .- _ E. A. Brown EAB:js1 Enclosure New Hampshire Yonkee Division of Public Service Company of New Hampshire P.O. Box 300
- Seabrook, NH 03874
- Telephone (603) 474 9521 j)
e. l 7 ,
,. July 19, 1989 NEW HAMPSHIRE YAltKEE'S
_ CORE VALUES AND WORK ETHIC PROFESSIONALISM All of us must be professionals in managing, operating and supporting our power plant. l i
- Our operation and support of the plant reflect a mission characterized by 'I
. excellence and quality. l
- Our conduct at work and in the community affirms the values and ethics of l 'our profession.
)
*. The values and ethics of our professional conduct are reflected in these !
- principles:
-- respect for nuclear technology
-- pursuit of excellence
-- integrity and ethical behavior 'l
-- teamwork j
-- checks and balances
-- respect for the individual
-- accountability
-- open communication
-- cost effectiveness l
RESPECT FOR NUCLEAR TECHNOLOGY ) We understand and respect that.there are risks inherent in all technologies used ! to generate electricity, including nuclear technology. Our every action is taken I with full regard for the health and safety of our fellow employees and the ; general public. We will operate Seabrook Station in a safe, reliable. environmentally sound and cost-effective manner.
- We accept responsibility for nuclear and industrial safety and minimizing radiation by demonstrating a commitment to safety in all our actions.
- We review, comprehend and comply with licensing and governmental requi ements. ;
- We identify issues of safety and quality, and we initiate appropriate action to assure corrective action.
EXCELLENCE New Hampshire Yankee will be the "best among the best', committed to professional and operational excellence. Each of us is important and everything we do is important.
- We create and accept challenging goals.
- Ve always look for improvement in self, work and plant.
2
- We freely discuss mistakes and take effective . action to learn from them.
- We take pride in our work and do it right -- the first time -- on time --
every time.
- We are committed to excellence in housekeeping and will operate and maintain a clean plant 1and-site.
INTEGRITY AND ETHICS L Integrity a'nd.ethica1' behavior are the cornerstones of our'New Hampshire Yankee professionalism. Each of us must firmly adhere to the. highest ethical. principles and practices; further, we must avoid practices which could even have j the appearance of unethical' behavior.
- We refrain from and avoid any conflict of interest in our business transactions.
- Designated NHY representatives communicate freely, openly and honestly with regulatory agencies, owners, auditing groups, vendors, industry groups, fellow utility companies, local, state and federal authorities and with each other.
- Designated NEY media spokesmen are available, truthful, open and complete in responding to inquiries'from the news media.
TEAMWORK We have proven the value of teamwork over and over again and we recognize that the.whole is bigger than the sum of its parts. We will continue to place a high value on teamwork at every level. Team effort will help us achieve our corporate objectives and goals.
- We participate as team members by giving our mutual support and cooperation to produce the best quality in all assigned work.
- We listen carefully and give full attention to each other.
- Ve offer and provide support to other members of the team. We seek and accept support from other team members.
- We work together to solve problems and disagreements at the peer level whenever possible.
- Ve ' coach' others and provide constructive feedback -- and we receive constructive feedback willingly.
CHECKS AND BALANCES We accept independent reviews and self assessments as a means to help us as individuals and as company to initiate improvements and ensure excellence.
. 3
- Each of us recognizes that we collectively achieve excellence by seeking improvement in our own performance.
- We fully recognize the importance of internal and external reviews of NHY's activities and provide candid, honest responses to all questions.
- We participate in self-assessments by providing factual information.
- We provide timely and complete responses to identified deficiencies and take appropriate corrective actions. *
- We investigate problems in depth to ensure that the solution adequately identifies and corrects the cause.
RESPECT FOR THE INDIVIDUAL Ve respect and value our talented, dedicated fellow employees as New Hampshire Yankee's most important asset. Each person is an essential member of our team.
- We recognize and show interest in each other as unique individuals with differing abilities, needs and motivations.
- We recognize that the standard of performance is excellence, not perfection. We give honest, constructive and timely performance reviews.
- We support individual career development and encourage our feller workers to continue their education.
- We practice and encourage individual initiative, creativity and thought in accomplishing job assignments.
- We follow the rule and the spirit of New Hampshire Yankee's policy on equal opportunity for all employees.
ACCOUNTABILITY We believe in accountability as the acceptance of ownership and responsibility for action and results associated with assigned duties and tasks. A person who , is accountable does not play the role of ' victim' -- blaming mistakes or problems l on others. We believe our accountability extends beyond our own job descriptions to include the success of other departments, functions, and the entire company.
- We constantly pursue the goals and objectives of our jobs -- seeking success for the entire company.
- We identify what is required to do our jobs and will not hesitate to %sk for the resources and support needed.
- We support our fellow workers and know that their success depends on our
, actions. L
- We don't " pass the buck".
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COST EFFECTIVENESS Cost effectiveness is the sensible and economical use of resources entrusted to
.us. We are accountable to the public, the Joint Owners and our fellow employees to be cost-effective. This is a professional and moral' obligation.
- We complete work on time and within budget.
- We analyze both cost and expected benefits before deciding to expend funds. j
- We review-programs regularly to be sure that resources are being used effectively.
- We expect and demand full value from all employees, contractors and I suppliers.
- We encourage creativity in seeking ways to eliminate unnecessary expenses in the completion of assigned work.
- We avoid duplier. tion of work tasks.
COMMUNICATION '! Open, frank communications in plain English are absolutely necessary to help us meet our goals. This applies to all communications throughout New Hampshire j Yankee -- up, down and sideways throughout the organization. j i
- We communicate goals and objectives clearly and concisely throughout the ,
organization, and provide feedback regularly on how we are doing. ) 1
- We foster open discussions on problems so as to determine root causes and find solutions, l
- We contribute to the systematic collection of data for the trending of key performance indicators which provides feedback throughout the organization to help improve performance and achieve excellence.
- l. l
- We provide timely information and encourage communications that will fully brief management to enable proactive response to the needs of the l organization.
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