ML20086A662
| ML20086A662 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 11/07/1983 |
| From: | Gucwa L GEORGIA POWER CO. |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| References | |
| REF-GTECI-A-09, REF-GTECI-SY, TASK-A-09, TASK-A-9, TASK-OR GL-83-28, NED-83-546, NUDOCS 8311160062 | |
| Download: ML20086A662 (16) | |
Text
Georgia Power Company 333 Piedmont Avenue Adanta, Georg:a 30308 Telephone 404 5266526 Masng Addrest Post Office Box 4545 Atlanta, Georgia 303r?
Georgia Power L T. Gucwa the southem ehrmc system Manager Nuclear Eng:neenng anc Citef Nudear Engmeer NED-83-546 November 7, 1983 Director of Nuclear Reactor Regulation Attention: Mr. John F. Stolz, drief Operating Reactors Branch No. 4 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C.
20555 NRC DOCKETS 50-321, 50-366 OPERATING LICENSES DPR-57, NPF EDWIN I. HATOi NUCLEAR PLANT UNITS 1, 2 STKIUS REPORT ON SALBf GENERIC REQUIRBGNIS Gentlemen:
Pursuant to your letter of October 25,.1983, denying our recent request for extension of response date for Generic Letter 83-28, the attachment to this letter is a status report of our compliance with requirements of that letter.
Preliminary plans and schedules for compliance are provided where these are known.
In most cases, actions to achieve compliance will need careful consideration and coordination among GPC staff, vendors and architect-engineering companies.
Additionally, input from industry initiatives, including the BWR Owners Group Salem Requirements Committee and INPO activities, affect plans and schedules for compliance.
Accordingly, 1
the attachment - contains only the current status of compliance for most requirements.
Plans and Schedules will be provided in a supplemental response prior to February 29, 1984.
Please contact this office if you have any questions or comments.
I Yours very truly, st".*T~ g -
L. T. Gucwa PLS/ab xc:
J. T. Beckham, Jr.
H.C. Nix, Jr.
J. P. O'Reilly (NRC-Region II)
Senior Resident Inspector p/
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8311160062 831107 PDR ADOCK 05000321 P
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1 ATTAO NENT Plant Edwin I. Hatch Units 1 and 2 Salen Generic Requirements Status Report November 7, 1983 4
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Note:.
A stannary of requirements of Generic'.. Letter 83-28 are stated in bold letters..
Plant Hatch status of compliance is provided
- and, if available, plans and schedules for achieving compliance are also included.
1.1 POST-TRIP REVIEW (PROGRAM DESCRIPTION AND PROCEDURE)
POSITION 4
LICENSEES AND APPLICANTS SHALL DESCRIBE 1EEIR PROGRAM FOR ENSURING THAT UNSWEDULED REACIVR SHlTIDOWNS ARE ANALYZED AND 1 HAT A DETERMINATION IS MADE THAT THE PLANT CAN BE RESTARTED SAFELY.
Status:
HNP-426l(Scram / Transient Reporting) and HNP-13 (Authority to Startup and Shutdown Plant) are plant procedures describing requirements for post-trip review and authority to restart the plant.
HNP-426 -is a 25-page procedure providing detailed instructions for collecting, analyzing and documenting infomation related to a scram or transient.
Data collected include conditions prior to the event, performance of the reactor trip system and operation of all other safety-related systems. Setpoints for auto-initiation. logic are checked against maximum and minimum values of plant parameters to. confirm correct response.
Oth-r information collected includes personnel observations, process computer printouts and, if needed, control room recorder traces.
HNP-13 requires that all plant startups be authorized by the Plant General Manager, - the Deputy General. Manager or, in their absence, a
-designated alternate.
The procedure also requires that the cause of a scram or an unexplained power transient will be investigated and determined before the reactor is returned to power.
In the event of an unusual' transient, a post event debriefing is held as soon as involved persons can be relieved from duty.
A decision is made after the debriefing to either recommend to the Plant General Manager a restart of the unit or to initiate further investigation or corrective actions that are to be completed prior to restart.
This may include review by the Plant Review Board (PRB) or the Safety Review Board (SRB) as appropriate.
HNP-426 requires that ' control room personnel participate in the post trip review.
The primary responsibility for the scram / transient report is assigned to the Shift Technical Advisor (STA).
Qualifications of the STA position include,.as a minimum, a four-year technical degree and special training in Plant Hatch systems, plant operation, and transient and accident analysis.
Page 1
. Plans and schedules for compliance:
Current. Plant Hatch procedures and practices meet the requirements of the generic letter.
Improvements based on INPO and BWR Owners Group recommendations will be incorporated where appropriate, but no further
' action is required for the purposes of this response.
1.2 POST-1 RIP REVIBf - DATA AND INFORMATION CAPABILITY 4
POSITION LICENSEES AND APPLICANTS SHALL HAVE 'OR HAVE PLANNED A CAPABILITY 10 RECORD,~ RECALL AND DISPLAY DATA AND INFORMATION 10 PERMIT DIAGNOSING WE
~CAUSES OF UNSWEDULED REAC10R SHUTDOWNS PRIOR TO RESTART AND FOR ASCERTAINING 1HE PROPER FUNCTIONING OF SAFETY-RELATED EQUIPMENT.
ADEQUATE DATA AND INFORMATION SHALL BE PROVIDED 10 CORRECTLY DIAGNOSE THE CAUSE OF UNSGEDULED REAC7OR SHUTDOWNS AND THE PROPER FUNCTIONING OF SAFETY-RELATED EQUIPMENT DURING THESE EVENTS USING SYSTIMATIC SAFETY ASSESSMENT PROCEDURES (ACTION 1.1).
THE DATA AND INFORMATION SHALL BE DISPLAYED IN A-FORM THAT PERMITS EASE OF ASSIMILATION AND ANALYSIS BY PERSONS 1 RAINED IN THE USE OF SYSTEMATIC GAFETY ASSESSMENT PROCEDURES.
Status:
Plant Hatch utilizes a GE-PAC 4020 process computer system to provide on-line monitoring of several -hundred input points (digital, analog and pulse) representing significant plant process parameters.
The process computer's power is supplied from the vital AC bus which is normally supplied by the vital AC batteries and battery chargers through an inverter.
Listings of analog and digital points being monitored can be found in Table 1 at the end of this attachment.
He process. computer provides a sequence of events log to aid in detemining the cause of a plant trip or transient.
He. sequence of events log is printed out on the process computer's alarm printer in the control room with each point appearing in the following format:
Time Cycle Point ID Name Contact Status XX)D00C XX XXXX 24 diaracters XXXX ne time field gives the event time in hours, minutes, and seconds, and the cycle' field further subdivides this time to the nearest 1/60 of a second.
%e point ID and name fields contain the identification and coded description of the monitored input point, and the contact status field. shows the status of the point following the change of state.
He alam printer edits are normally transmitted to the doctanentation department on a monthly basis.
In the event.of a plant trip, the Page 2
Status: (Continued) sequence of events log pertaining to that plant trip is transmitted to the documentation department under HNP-426.
he process computer also provides a post trip log as an analysis tool for use in determining the values of selected analog points immediately prior to and - following a plant trip.
Presently the post trip log monitors thirteen points,. as listed in Table 2 at the end of this attachment.
He post trip log can contain a maximum of twenty analog points.
He thirteen points presently being monitored are considered to be the most important analog points of the analog points -listed in Table 1.
%e points being monitored are continuously stored at 5-second intervals in a special scan table section of the computer memory.
Each stored value. remains in the scan table for a period of 5 minutes and is then discarded.
Hus, at any given time the scan table contains,- for each monitored point, the 60 scanned values stored during the past 5 minutes. Upon an occurrence of a plant trip, the past 5 minutes of data is printed out on the process computer's printer while the scan program continues to collect and save data at 5-second intervals for the next 5 minutes.
%erefore, the post trip log contains monitored data from 5 minutes before the plant trip until 5 minutes after the plant trip. He post trip log format is as follows:
Timei PT IDI PT ID2 Pr ID13 X)0000C XXXX XXXX XXXX
[
VAIDE1 VALUE2 VALUEi3
+ XXXXX
+ XXXXX
+ 20000C VALUE13
' Time 120 VALUE1 VALUE2 X)D000C XXXX XXXX XXXX An example of:this printout is shown in Table 3.
The printer edits are normally transmitted to the documentation department' on a monthly basis.
In tha event of a plant trip, the post trip. log is transmitted to the documentation department under HNP-426.
Other data used to analyze transients include personnel observations
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(recorded on data sheets of }WP-426) and control room recorder traces.
Planned changes to existing data and infonnation capability include addition of the following systems:
I-ne Safety Parameter Display System (SPDS) is currently scheduled for implementation prior to June, 1986.
A description of the system is contained in the GPC response dated April 15, 1983, to Generic letter 82-33.
Page 3
l.
-Status: (Continued)
II. A VAX 11-780 mini-computer system purchased from General Electric Company for reactor core monitoring and prediction is scheduled for
-operation in late 1983.
III 1he Analog Trip Transmitter System (ATIS) will replace existing 4
- sensors and. trip units with state-of-the-art equipment designed to
- improve - ~ accuracy and resolution of plant instrumentation.
The system is scheduled for installation during 1983 and 1984 outages of both Hatch units.
Plans and schedules for compliance:
An evaluation of existing systems will be performed and a report will be provided with our supplemental response.
A schedule for improvement will also be provided if improvements are determined to be necessary.
2.1 EQUIMENT CLASSIFICATION AND VENDOR INTERFACE (REACIOR ' 1 RIP SYSTIN C(NPONENTS)
POSITION LICEhSEES-AND APPLICANTS SHALL CONFIRM 1NAT ALL COMPONENTS WHOSE i
FUNCTIONING IS REQUIRED TO HIP -- WE REAC10R ARE - IDENTIFIED AS SAFETY-RELATED _ ON DOCtNENTS, PROCEDURES,. AND INFORMATION HANDLING SYSTINS USED' IN WE PLANT TO CONTROL SAFETY-RELATED ACTIVITIES,
' INCLUDING MAINTENANCE, WORK ORDERS, AND PARTS REPLACEMENT.
IN ADDITION, FOR 1NESE C(NPONEN13, LICENSEES AND APPLICANTS SHALL ESTABLISH.
IMPLINENT AND MAINTAIN A CONTINUING ' PROGRAM 10 ENSURE THAT VEND INFORMATION IS C(NPIETE, CURRENT AND CONTROLLED EROUWOUT ME LIFE '
EE PLANT, AND APPROPRIATELY REFERENCED OR INCORPORATED IN PIA INSR UCTIONS AND PROCEDURES.
Status:
A review of the equipment list is required to confim that all components are properly classified.
This review has not been initiated, but classification of trip system components is expected to be in conformance with requirements.
Additional information on equipment classification will be provided in a supplemental response.
General-Electric Service Information letters (SILs) are used by GE to communicate technical information and recommendations.
A Plant Hatch administrative guideline requires that all SILs are reviewed for applicability to Plant Hatch.
A system of positive feedback to General Electric is in place.
Page 4 4
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Plans and schedules for compliance:
An evaluation of existing compliance and plans for any needed improvements will be provided in a supplemental response prior to February 29, 1984.
l 2.2 EQUIPMENT CLASSIFICATION AND VENDOR INTERFACE (PROGRAMS FOR ALL SAFETY-RELATED C(NPONENTS).
POSITION LICENSEES AND APPLICANTS SHALL SUINIT, FOR STAFF REVIEW, A DESGIPTION OF WEIR PROGRAMS FOR SAFETY-RELATED BQUIPMENT CLASSIFICATION AND VENDOR INTERFACE AS DESGIBED BEIDW:
1.
FOR EQUIINENT CLASSIFICATION, LICENSEES AND. APPLICANTS SHALL DESGIBE 'INEIR PROGRAM FOR ENSURING WAT ALL COMPONENTS OF SAFETY-RELATED SYSTINS NECESSARY FOR AC(DMPLISHING REQUIRED SAFETY FUNCTIONS ARE IDENTIFIED AS SAFETY-RELATED ON DOCINENTS, PROCEDURES, AND INFORMATION HANDLING SYSTIMS USED IN THE PLANT TO C0h"IROL SAFETY-RELATED ACTIVITIES INCLUDING MAINTENANCE, WORK ORDERS AND REPLACINENT PARTS. THIS DESCRIPTION SHALL INCLUDE:
1.
WE CRITERIA FOR IDENTIFYING COMPONENTS AS SAFETY-RELATED WIEIN SYSTINS CURRENTLY CLASSIFIED AS SAFEIT-RELATED.
WIS SHALL NOT BE INTERPRETED 10 REQUIRE CHANGES IN SAFEIT CLASSIFICATION AT THE SYSTIMS LEVEL.
2.
A DESCRIPTION OF EE INFORMATION HANDLING SYSTEM USED 10 IDENTIFY SAFETY-RELATED C(MPONENTS (E.G.,
COMPUTERIZED BQUIPMENT LIST) AND THE METHODS USED FOR ITS DEVELOPMENT AND VALIDATION.
Status:
A computerized listing of equipment called the Equipment Location Index (ELI) is used to control classification of equipment.
He ELI is controlled by Southern Company Services for Unit 1 and Bechtel for Unit 2.
%e ELI is used by the Plant Hatch Quality Control (QC) department to classify Maintenance Requests (MRs) and Purchase Requisitions.
%ese documents are stamped to designate safety l
classification.
Additional information will be provided in a
supplemental response.
Plans and schedules for compliance:
Improvements to the ELI were under development prior to the Salem event and related generic requirements.
%ese improvements will be evaluated against the Salem requirements.
Plans and schedules will be provided in a supplemental response prior to February 29, 1984.
Page 5
2.
FOR VENDOR INTERFAG, LICENSEES AND APPLICANTS SHALL ESTABLISH, IMPLMENT AND MAINTAIN A CONTINUING PROGRAM E ENSURE EAT VENDOR INFORMATION FOR SAFETY-RELATED COMPONENTS IS-COMPLETE, CURRENT AND CONROLLED 11 ROUGH 0lff THE LIFE OF EEIR PLANTS, AND APPROPRIATELY
~
REFERENQiD OR INCORPORATED IN PLANT INSTRUCT. TONS AND PROCEDURES.
Status:
The - SIL program as described in Section 2.1 is used to implement recommendations from GE, the NSSS: supplier.
For the diesel generators, representatives from Colt Industries are under contract as part of a Diesel Generator Task Force to address operational problems experienced with the diesel generators.
Regular contact is maintained with Bechtel and Southern Company Services for equipment in the AE's scope of supply.
An Operating Experience Assessment program is implemented by procedure IMP-911 (Operating Experience Assessment Report).
Information from the NOTEPAD conferencing system, INP0/NSAC communications, SILs and NRC correspondance is systematically reviewed for applicability to Plant Hatch. Recommendations are implemented and tracked if appropriate.
Plans and schedules for compliance:
GPC _is a participant in a Nuclear Utility Task Action Committee (NtTfAC) supported by 'INPO to develop an industry position on Section 2.2.2 Plans and schedules based on this generic effort will be provided in our supplement in February, 1984.
3.1 POST MAINTENANCE TESTING (REACIOR 'IRIP SYSTM CCNPONENTS)
POSITION THE FOLLOWING ACTIONS ARE APPLICABLE 10 POST-MAINTENANCE TESTING:
1.
LICENSEES AND APPLICANTS SHALL SUBMIT WE RESULTS OF EEIR REVIEN i
0F TEST AND MAINTENANG PROCEDURES AND TECHNICAL SPECIFICATIONS TO ASSURE '1 HAT POST-MAINTENANCE OPERABILITY TESTING OF SAFETY-RELATED C(NPONENTS IN EE REACIOR 1 RIP SYSTM IS REQUIRED 10 BE CONDUCfED AND THAT EE TESTING DMONSIRATES WAT EE EQUIPMENT IS CAPABLE OF PERFORMING ITS SAFEfY FUNCTIONS BEFORE BEING RE1URNED 10 SERVIG.
2.'
LICENSEES AND APPLICANTS SHALL SUBMIT WE RESULTS OF THEIR CHECK OF VENDOR AND ENGINEERING RECOMENDATIONS TO ENSURE THAT ANY APPROPRIATE TEST GUIDANCE IS INCLUDED IN THE TEST AND MAINTENANG PROCEDUREE OR 1HE TECHNICAL SPECIFICATIONS, WHERE REQUIRED.
Page 6 b
3.
LICENSEES AND APPLICANTS SHALL
- IDENTIFY, IF APPLICABLE, ANY POST-MAINTENAN TEST REQUIREMENTS IN EXISTING TECHNICAL SPFCIFICATIONS ~ WHICH CAN BE DIMONS'IRATED TO DEGRADE RAEER WAN ENHAN SAFETY.
APPROPRIATE CHANGES TO EESE TEST REQUIREMEN'IS,
)
WIE SUPPORTING JUSTIFICATION, SHALL BE SUBMITTED FOR STAFF APPROVAL.
Status:
A complete revicw Of maintenance procedures and Technical Specifications has not yet been conducted.
A spot check of a few selected procedures indicates that post maintenance operability testing is included.
GE Sits are tracked on an ongoing basis to ensure that vendor recommendations are incorporated in Hatch procedures and Technical Specifications.
Requirements of Technical Specifications which degrade rather than enhance safety are expected to be addressed generically by the BWR Owners Group.
GPC will participate in this activity, if initiated, and will consider implementation of any recommendations.
Plans and schedules for compliance:
Results of a procedure review and status of owners group activity will be provided in our supplemental response.
Plans and schedules for improvements, if any are needed, will also be provided.
3.2 POST-MAINTENAN TESTING (ALL O WER SAFETY-RELATED COMPONENTS)
POSITION W E FOLLOWING ACTIONS ARE APPLICABLE 'ID POST-MAINTENANCE TESTING:
1.
LICENSEES AND APPLICANTS SHALL' SUBMIT A REPORT DOCUMENTING EE EXTENDING OF TEST ANE MAINTENANCE PROCEDURES AND TECHNICAL SPECIFICATIONS REVIEW TO ASSURE EAT POST-MAINTENANCE OPERABILITY TESTING OF ALL SAFETY-REIATED EQUIPMENT IS REQUIRED TO BE CONDUCTED AND THAT EE TESTING DEMONSTRATES 'IRAT 'IEE EQUIPMENT IS CAPABLE OF PERFORMING ITS SAFETY FUNCTIONS BEFORE BEING REIURNED TO SERVIG.
2.
LICENSEES AND APPLICANTS SHALL SUBMIT E E RESULTS OF THEIR CHECK OF VENDOR AND ENGINEERING REC (MfENDATIONS
'IO ENSURE THAT ANY APPROPRIATE TEST GUIDANCE IS INCLUDED IN EE TEST AND MAINTENANCE PROCEDURES OR W E TECHNICAL SPECIFICATIONS WHERE REQUIRED.
Page 7
4
.3.
LICENSEES AND APPLICANTS SHALL
- IDENTIFY, IF APPLICABLE, ANY POST-MAINTENANCE TEST REQUIRIMENTS IN FXISTING TECHNICAL SPECIFICATIONS WHICH ARE PERCEIVED E DEGRADE RAEER 1 NAN ENHANCE SAFETY.
APPROPRIATE CHANGES 10 1NESE TEST REQUIRIMENTS, WITH SUPPORTING JUSTIFICA1DN, SHALL BE SUEMITTED FOR STAFF APPROVAL.
Status:
Our response is the same as in Section 3.1.
Consistent with the recommendation of the generic letter, a higher priority will be given to work related to reactor trip system components.
4.1 REACIDR 1 RIP SYSIM RELIABILITY (VENDOR RELATED MODIFICATIONS) 4.2 REACIDR 1 RIP SYS11M RELIABILITY (PREVENTIVE MAINTENANCE AND SURVEILLANCE PROGRAM FOR REACTOR 1 RIP BREAKERS) 4.3 REACIDR 1 RIP SYSTIM RELIABILITY (AUlt)MATIC ACTUATION OF SHUNT 1 RIP ATTAONENT FOR WESTINGHOUSE AND B4W PLANTS) 4.4 REACTOR TRIF SYSTIM RELIABILITY (IMPROVIMENTS IN MAINTENANCE AND TEST PROCEDURES F02 B6W PLANTS)
Status:
Positions 4.1 through 4.4 do not apply to a BWR.
Accordingly, no response to these sections is required for Plant Hatch.
4.5 REACTOR 1 RIP SYSTIM RELIABILITY (SYSTIM FUNCTIONAL TESTING)
POSITION ON-LINE ' FUNCTIONAL TESTING OF THE REAClDR 1 RIP SYSTIN, INCLUDING INDEPENDENT TESTING OF THE DIVERSE 1 RIP FEATURES, SHALL BE PERFORMED ON ALL PLANTS.
Status:
Plant Hatch meets this requirement except for on-line testing of back up scram valves.
The BWR Owners Group is expected to develop a generic position for addressing this requirement.
Plans and schedules for compliance:
GPC will implement the owners group position. A report will be provided with our supplemental response.
Page 8
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AGE 3 e 4 150142 DEL A040 LPM 20-21 RI LV A IPE 1150143 PSW A041 LPM 20-21 RI LV I IPW 150144 PSW A042 LPM 20-21 RI LV C IPE -
150145 PSW A043 LPM 20-21 RI LV I IFR
[1501% PSW A044 LPM 28-21 RI LV A IPWR]
150147 PSW A045 LPM 28-21 RI LV I IFR 1
~ 150148 PSW A046 LPM 28 21 RI LV C IPE~
{150149 PSW A047 LPM 28 21 RI LV D IPW[
150150 PSW A048 LPM 36-21 RI LV A IPE 150151 DEL A049 LPM 36-21 RI LV I IPE "~
~
150152 PSUM A050 LPM 36-21 RI LV C IPR ~
1 - 150102 PSE A000 LPM 20-05 RI LV A IPR
~
~~150103 PSUM A001 LFM 20-05 RI LV I IPW
'150153 PSUM A051 LPM 36-21 RI LV I IPR 150104 PSUM A002 LPM 20-05 RI LV C IPE ~'150154 PSW A052 LPM 44-21 RI LV A IPE ~
M - 150105 PSW A003 LPM 20-05 RI LV IIPE 150155 PSW A053 LPM 44-21 RI LV I IPR ~
~~ 501% PSUM A004 LPM 28-05 RI LV A 1PR 150156 PSW A054 LPM 44-21 RI LV C IPE-- ~
~1
~
150107 DEL A005 LP M 28-05 FLI LV I IP E 150157 IEL ' A055 LPM 44-21 RI LV I 2PW 150108 PSUN A0% LPM 28-05 RI LV C 1PR 150150 PSW A0561PM M-29 RI LV A IPE~~~
~150109 PSW A007 LPM 28-05 RI LV I IPs 150159 PSW A057 LPM 04-29 RI LV B IPE~
~150110 PSUN A008 LPM 36-05 RI LV A IPm 150200 PSW A058 LPM M-29 RI LV C 2PR~
150111 PSUN A001 LPM 36-05 RI LV I IPR
~ 150201 PSW A059 LPM M-29 RI LV 3 IPR-
~-~150112 PSW A010 LPM 36-05 RI LV C IPE 150202 PSW A060 LPRR 12 29 RI LV A IPW~
-150113 PSUM A011 LPM 36-05 RI LV I IPS 150203 PSW A061 LPRh 12-29 RI LV I IPE ~
150114 PSW N012 LPM 12-13 RI LV A IPE 1502M PSW ANZ LPM 12-29 RI LV C 2PR-~
~~150115 PSUM A013 LPM 12-13 RI LV E IPR 150205 PSW A063 LPM 12-29 RI LV I IPR ~
~~150116 PSW A014 LPM 12-13 RI LV C 1PR 1502% PSUM A%4 LPM 20-29 RI LV A IPE -
150207 PSW A065 LPM 20-29 RI LV I IPE-
~ 50!!T DEL A015 LPM !! !3 RI LV I IPR
~150208 PSUM A066 LPM 20-29 RI LV C IPE~ ~
1
~
~~150118 PSUN A016 LPM 20-13 RI LV A 2PR 150209 PSW A%7 LPM 20-29 RI LV I ipa J
150119 PSW A017 LPM 20-13 RI LV l'IPW
~~
~150120 PSUM A018 LPM 20-13 RI LV C IPs 150210 PSW A%8 LPM 28-29 RI LV A IPW~
150211 PSW A069 LPM 28-29 RI LV'lIPW-
~~150121 PSUN A019 LPM 20-13 RI LV I IPs150212 PSUM A070 LPM 28-29 RI LV C 2PR
~
i 150122 PSUM A020 LPM Z8-13 RI LV A 2PR 150213 PSW A071 LPM 28-29 RI LV~I IPM ~~
15G123 PSE A021 LPM 13-13 RI LV I IPE 150214 PSW A072 LPM 36-29 RI LV A 1PR-
~
150124 PSUM A022 LPM 28-13 RI LV C IPs
~
~
~~150125 PSUM A023 LPM 28-13 RI LV I IPs 150215 PSE A073 LPM 36-Zi RI LV I IPR-
~
15U216'PSW A074 LPM 36-29 RI LV C 2PW-
'_150126 PSW A024 LPM 36-13 RI LV A 1Pm 150217 PSW A075 LPM 36 29'RIIV l'IPW l
15012f PSUN A025 LPM 36-13 RI LV I 2PE
~
~150128 PSUM A026 LPM 36-13 RI LV C IPS 150218'PSUM A076"LPRM'44 29'RI'LifA 1PR I
150121 PSW A027 LPM 36-13 RI LV I IPE 150219 PSW A077 LPM 44-Zt RI LV I IPR-
~
~ 50130 PSUM A028 LPRM 44-13 RI LV A 2PR
_150220 PSUM M78' LPM'44-19 FLfLYT1Pilt-1
- l 150131 PSW A029 LPM 44-13 RI LV IIPE 150221'PSE A071'LPIM'44-29 RI LVTIPR-I 150132'IEL ' A030 LPM 44;13 RI LV C IPE 150222'PSW A0001PM'M-3fRI'l.V A 1PW
[150133'PSW A031 LPM 44-13 RI LV l IPE __ 150223 PSUM A081 LP
~~
150134 PSUM A032 LPM M-21 RI LV A 1PWR 150224 PSUM A082 LPM M-37 RI LV C IPW
, [150135 PSW A033 LPM M-21 RI LV I IPR __ 150225 IEL 'A083 LPRM'M-3IRI'LV'I'1PW
.150136 PSUM A034 LPM M 21 RI LV C 1PW 150226 PSUM A004 LPM 12-37 RI LV A 1PW 150137 PSUN A035 LPM M-21 RI LV 3 IPR 150227 PSM A085 LPM 12-37 RI LV l'IPE~
l
~
~150138 PSUN A036 LPM !!-21 RI LV A 2Pm
_150228 PSUM A006 LPRM 12-37 RI LV C 1FE -
'"150139 PSUM A037 LPM 12-21 RI LV I IPE ~ 150229 DEL A087 LPM 12-37 RI L
~
l 150140 PK.1 A%3 LU.912-21 RI LV C tra 150230 PSUM AC38 LPRM 20-37 RI'LV A IPE ~
~
' 150231 PSUN A389 LPRM 20-37 RI LV I 1PR ~
150141 Pr " O In 12-21 R1 LV D Fa
~
150232 PSUM A010 LPRR 20-37 RI LV C 2PR -
^
~m 150233 PSUN A091 LPM 20-37 RI LV I IPE l
~150234 PSUM A092 LPM 28-37 RI LV A 1PW~
f 1150235 PSUM A093 LPRM 28-37 RI LV I IPM 150236 PSUM A094 LPM 28-37 RI LV C 2PW 150237 PSUM A0?S LPM 28-37 RI LV I IPtlR ~
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- 150241 PSUM A099 LPEN 36-37 RI LV I FER 150242 PSUM A100 LFEM 44 37 FLI LV A FUR' l 1
150243 PSUN A101 LFEM 44-37 RI LV B UR 1150244 PSUM A102 LPEN 44-37 RI LV C FWR1 !
150245 PSUN A103 LPM 44-37 RI LV I UWR l
~ 150246 PSUM A104 LPRM 12-45 RI LV A IPWR ~l
~150247 PSUN A105 LPM 12-45 RI LV B WWR ~
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150248 PSM A106 LPM 12-45 RI LV C FM-l
~150249 PSUM A107 LPM 12-45 RI LV B FR
, ~150250 PSM A108 LPM 20-45 RI LV A FE " i j
' '1 -~150251 PSW A109 LPM'20-45 RI LV I 2PW l
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'150253 PSUN A111 LPM 20-45 RI LV B FWR ~ l M
~~150254 PSUM A112 LPH 28-45 RI LV A FWR~~ ;
[150255 PSUN A113 LPM 28-45 RI LV I IPWR[
~150256 PSUN A114 LPM 28-45 RI LV C IPWR
~~150257 PSW A115 LPM 28-45 RI LV I UR..
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_150259 PSUM A!!7 LPRM 36-45 RI LV I IPR,, l
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,150300 PSUN A118 LPM 36-45 RI LV C FR _
150301 PSUM Allt LPM 36-45 RI LV B FE w.._.
~150302 PSUN A120 LPM 44 45 RI LV A Fa ' 150334 LEL B030 RIR FW IET A1 TEMP DECF I ~150303 PSM A121 LPM 44-45 RI LV I Fw 150335 DEL ' B031 RTR FW IET~A2'TEF ECF
~150304 PSW A122 LPRM 44-45 RI LV C FWR 150336 BEL ~B032 RTR FW IET~Bi TEFECF s
"150305 PSUN A123 LPRM 44-45 RI LV B 1PWR 150337 BEL ~B033 RTR FU IETBZ' TEMP ECF 1.s,
~150306 PSUM A128 STEM JET AIR EJECTOR MV150338 PSW B034 ECIE Al'TETTEW me d
~~150307 PSUM 9000 APM A RUI LEVEL ~ IPWR~~ 150339 PSW B035 RECIE'A2'llsTTElfECP I
~
150308 PSUN B001' APM B RUI LEVEL FWR-150340 PSUN B036 RECIE Bf'!ETTEW BECF-'--
I
~150309 PSUN B002 APRM C RUI LEVEL ~1PR 150341 PSUM 3037 RECIE'BZ IETTDF~ECF---- L h
? ~I5031FPSUM B002 APRM B RUI LEVEL ~ IPWR 150342 PSW C000TEEBMTER~MC IPullI- -
~
~
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~150312 PSUM 3005 APM F'RUI LEVEL - Um 150344 PSW C500~ CROSS CEIENTW75 m I
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~
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~
3 1503i4 PSUM'8009 TIPTRUITEVEL FR 150346 PSM S00110 W REFEEEE CM 0 W
~
.j ~150315'PSufi3010 TIP'C RUI LEVEL IPs 150347 PSE1002 T/C~REFDt MET!an na i
~
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a ~150316 PSUM Mll'TIP B RUI LEVEL IPR 750348 SUlelART'COWLETED
~
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4 150317 PSW B0lf RTR TOTAL CORE FLOU'M/N
-4
~
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j ~15031J PSM M13 RTR CORE PRESS BIFF PSI
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~150320 PSUM MI5 RTR FW LOOP A RW~ M/H qd.
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~150322 PSW M18 CLEAll-UP STS R0W ~ WIN-
"150323 PSUM B019 REC 1RC PP Fit A P W W i ~150324 PSUM 9020 REC 1E PP'MTR B P R MW
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~150325 PS M B021 REACTOR M TER LEVEL' INCH I
9 ~'150326 PSUM B022 TOTAL STEM R0W M/H ~
~l 150327 PSUM B023 CLNUP STS IET TEMP ECF-
- 4. - =.
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150328 PSUM B024 CLNUP STS OLLT TER KCF '~~
150329 PSUM B025 REACTOR PRESSURE PSI -
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'150330 PSUM B026 RECIRC LP Al M R0 U/H
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150331 PSUM B027 RECIRC LP A2 M FLO M /H
~~
1 150332 FTUM BOIS EECIRC LP Bl DR R0 PJ/H 150333 FG D'9 FECIRC LP E2 [R FLO M/H 1
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e TABLE 2 POST 1 RIP IDG POINTS POINT POINT ID NAME 1
B000 APRM A FLUX LEVEL 2
B002 APRM C FLUX LEVEL 3
B012 RTR TOTAL CORE FIN 4
B013 R1R CORE PRESS DIFF 5
B015 R1R FW IDOP A FLOW 6
B021 REAC10R WA1ER LEVEL 8
B022 1UTAL STEAM FIN 9
B025 REACTOR PRESSURE 10 B030 R1R FW INLT Al TEMP 11 B031 RTR FW INLT A2 TBIP 12 B032 RIR FW INLT B1 TIMP 13 B033 R1R FW INLT B2 TIMP 9
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TABLE 3 "StPIE OF POST 'IRIP ZDG
('
a 14500?
N?s W 33 Tpt: t00 UdIT 7
7!WE E000 E007 EN? P011 E015 R$16 R071 B077 9075 R010 R011 E017 PM1 115351 101.7 99.9 76.4 19.5 5.1 5.7 37.4 10.1 927. 416.4 416.7 416.2 416.7 185?54 101.7 99.9 76.4 19.5 5.1 5.2 37.5 10.1 936. 416.4 416.7 416.1 416.7
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