ML17298A831
| ML17298A831 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 02/23/1984 |
| From: | Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | Knighton G Office of Nuclear Reactor Regulation |
| References | |
| TASK-2.F.2, TASK-TM ANPP-28929-WFQ, NUDOCS 8402270340 | |
| Download: ML17298A831 (35) | |
Text
REGULATORY.
ORMATION DISTRIBUTION SY
.M (RIDS)
ACCESSION NBR;8402270340.
DOC CHOATE: 84/02/23 NOTARIZED: YES DOCKET FACIL:STN"50 528 Palo Verde Nuclear Stationi Unit fr Arizona Publi
-05000528 STN 50 529 Palo Verde Nuclear Station~
Unit 2~ Arizona Publi 05000529 STN 50-530 Palo Verde Nuclear Stations Unit 3i Arizona Publi 05000530 AUTH,NAME AUTHOR AFFILIATION VAN BRUNTiK,E, Ar izona Public Service Co, RECIP ~ NAME RECIPIENT AFFILIATION KNIGHTON g G R
.Licensing Branch 3
SUBJECT:
Forwards response to NRC 831220 request for addi info re THI Item II~ F ~ 2i "Instumentation for Detection of Inadequate Core Cooling+,"
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DISTRIBUTION CODE:
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OR Submittal:Inadequate Core Cooling (Item IFFY 2)
GL 82 28 NOTES:Standardized plant ~
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Arizona Public Service Company P.O. SOX 21666
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PHOENIX, ARIZONA 65036 February 23, 1984 ANPP 28929-WFQ/MAJ Director of Nuclear Reactor Regulation Attention:
Mr. George Knighton, Chief Licensing Branch No.
3 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Subject:
Palo Verde Nuclear Generating Station (PVNGS)
Units 1, 2 and 3
Docket Nos. STN-50-528/529/530 File:
84-056-026'.l.01.10
Reference:
l.
2.
Letter from G.
W. Knighton, NRC, to E.
E.
- APS, dated December 20, 1983.
Request Information on TMI Item II.F.2.
Letter to G.
W. Knighton, NRC, from E.
E.
- APS, dated July 29, 1983.
Revised APS Item II.F.2.
Van Brunt, Jr.,
for Additional Van Brunt, Jr.,
response to TMI
Dear Mr. Knighton:
Reference (1) requested Arizona Public Service Company (APS) to submit additional information to the NRC concerning TMI Item II.F.2, "Instrumentation for Detection of Inadequate Core Cooling."
Attachment A
is the APS response to the NRC request in Reference (1).
If you have any further questions, please contact me.
Very truly yours, 8-C-u'a ~
E. E.
Van Brunt, Jr.
APS Vice President, Nuclear ANPP Project Director EEVB/MAJ/sp Attachment cc:
E.
A. Licitra A.
C.
Gehr T. Huang G. Mazetis (v/a) 8402270340 840223
. PDR ADOCK 05000M8 A
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W e
t1
STATE OF ARIZONA
)
) ss.
COUNTY OF MARICOPA)
I, A. Carter
- Rogers, represent that I am Nuclear Engineering Manager of Arizona Public Service
- Company, that the foregoing document has been signed by me for Edwin E.
Van Brunt, Jr.,
Vice President,
- Nuclear, on behalf of Arizona Public Service Company with full authority so to do, that I have read such document and know its contents, and that to the best of my knowledge and belief, the statements made therein are true.
A. Carter Roge Sworn to before me thfe~day of 1984.
Notary Public My Commission Expires:
hly Comm1sslon Exp1res April 6, 1907
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ATTACHMENT A APS
RESPONSE
TO THE NRC REQUEST FOR ADDITIONAL INFORMATION ON TMI-2 TASK ACTION PLAN II.F.2 FOR PALO VERDE NUCLEAR GENERATING STATION UNITS 1, 2,
AND 3 QUESTION: 1.
Provide a functional and design description of the Emergency
Response
Facility Data Acquisition and Display System (ERFDADS) xelative to the function and design of the Critical Function Monitoring System (CFMS) described in the CESSAR-80 submittal.
RESPONSE
The CFMS is described in the CESSAR-80 submittal as the "Heart of the Integrated Accident Monitoring System (AMS)."
It is designed to meet the criteria set forth in NUREG-0696; "Functional Criteria for Emergency
Response
Facilities."
The CFMS is a
dedicated, computer
- based, Non-Class IE plant information and display system.
Specifically, the CFMS:
1.
Provides primary Safety Parameter Display System/Inadequate Core Cooling (SPDS/ICC) display in Control
- Room, Technical Support Center (TSC),
and the Emergency Operation Facility (EOF).
2.
Includes the Historical Data Storage and Retrieval (HDSR)
System.
'3.
Provides the hardware capability fox transmitting data to the NRC Operation Center via the Nuclear Data Link (NDL).
4.
Provides the capability to display Regulatory Guide 1.23 and 1.97 input parameters in the Control Room, TSC and EOF.
ERFDADS is a
Non-Class IE System, very similar to
- CFMS, that provides all the above mentioned information.
Figure (1) shows the block diagram of the ERFDADS System.
The ERFDADS man/machine interface includes one color-graphic CRT per unit in the Control
- Room, three color-graphic CRT's per unit and two line printers, one for demand and one dedicated for
line printer in the EOF.
A simplified configuration diagram for ERFDADS and the QSPDS is shown in Figure (2).
The following is a design description of the CFMS:
A.
The CFMS shall provide the capability to display the status of the following critical functions:
1 g V W
ATTACHMENT A Page 2 of 15 1.
Core Reactivity Control 2.
Core Heat Removal Control 3.
Reactor Coolant System Inventory Control 4.
Reactor Coolant System Pressure Control 5.
Reactor Coolant System Heat Removal Control 6.
Containment Pressure/Temperature Control 7.
Containment Isolation Control 8.
Radiation Emission Control B.
The CFMS shall alarm deviations of the critical functions.
C.
The CFMS shall provide the User vith
- concise, understandable, integrated information to assist in accessing plant status during all modes of plant operation.
D.
The CFMS shall be capable of measuring the value of plant process input signals.
E.
The CFMS shall be capable of storing the values of plant process, signals, for a minimum of 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br />.
The values shall be time'agged.
F.
The CFMS shall be capable of determining the alarm status of each process paramet'er.
G.
The CFMS shall be capable of displaying information to the operator by means of a color cathode ray tube (CRT).
The CFMS shall be capable of utilizing alphanumeric data
- formats, shapes,
- symbols, color
- coding, and blinking for information display in accordance vith established human engineering guidelines.
H.
The CFMS shall be capable of utilizing greater than 20 fixed format displays (pages) for information'resentation.'age selection shall be under control of the operator.
Each display station (CRT and keyboard) shall be capable of independently calling up any fixed format display page in the repertoire.
ATTACHMENT A Page 3 of 15 The ERFDADS has all the design capabilities as the CFMS.
The ERFDADS presents plant data to personnel in the Control Room and in other areas.
This presentation is primarily via a
set of color monitor displays.
To help personnel focus on detailed information the displays are organized in a
hierarchial arrangement.
The highest level in the display hierarchy is deviation bar
- charts, which are designated safety parameter displays (SPD).
The SPDS indicates deviation from normal key safety parameters per operational mode such that an operator can rapidly access system parameters.
Below the SPD hierarchy are piping and instrumentation
- diagrams, displays (P&ID's) and various plots.
The P&ID's present plant data using simplified diagrams of plant systems identifying key process parameters.
- Thus, the operator can focus on a
particular plant function.
The plots available include time-history plots and pressure versus temperature plots.
The time-history plots show parameter value versus time curves.
The pressure versus temperature p1ots allow the operator to quickly access the state of the primary and secondary systems.
Other
- displays, such as demand and summary
- displays, are also available.
While ERFDADS employs a three-level hierarchy of displays, menus also allow the operator to quickly determine the position of a
display in the hierarchy.
Additionally, menus are also hierarchial in nature and can easily be selected from the local keyboard.
The top-level menu, from which all other menus can be displayed, includes the following:
1.
SPD Menu 2.
P&ID Menu 3.
Demand Display Menu 4.
Summary Display Menu, and 5.
System Interface Menu.
Table (1) provides a
comparison of the CFMS and ERFDADS in relation to the NRC regulatory requirements.
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ATTACHMENT A Page 4 of 15 QUESTION 2.
Provide a figure to show the Accident Monitoring System (AMS) including all of the components of the final Inadequate Core Cooling Instrumentation (ICCI)
System which will clearly identify the primary and backup display system for Core Exit Thermocouples (CETs) and the location of the ICCI display system in the control room.
Describe any deviation from the standard CESSAR-80 system design.
RESPONSE
The Accident Monitoring System (AMS) consists of two major subsystems:
1.
Critical Function Monitoring System (CFMS).
2.
Qualified Safety Parameter Display System (QSPDS).
(Including processing and display for Inadequate Core Cooling).
The Emergency Response Facility (ERF) computer system is similar to the AMS and consists of three ma)or subsystems:
l.
ERFDADS (Emergency
Response
Facility Data Acquisition and Display System) which is identical to the CFMS as explained in Item No. l.
2.
QSPDS (Qualified Safety Parameter Display System) including processing and,display for Inadequate Core Cooling.
This item is provided by C-E,and is identical to the System 80 QSPDS.
3.
Chemical 'and Radiological<< Analysis Computer System (CRACS).
Provides post-accident sampling and dose projection.
These major systems communicate with each
- other, and provide information collection, processing, and a display capability to the emergency operation crew.
Figure (1) shows the block diagram of the ERFDADS System.
The QSPDS (Qualified Safety Parameter Display System) provides a
two-channel, seismically qualified Class IE display of safety parameters including the Inadequate Core Cooling processing information.
The QSPDS utilizies a microprocessor based design for the signal processing equipment in conjunction with an alphanumeric display and associated keyboard for each of the two channels.
Each channel will accept and process QSPDS/ICCI input parameter signals such as core exit thermocouples and transmit its output to the alphanumeric display.
In addition, each channel will transmit its output to the ERFDADS.
Lf
ATTACHMENT A Page 5 of 15 Figure (3) shows the block diagram of the QSPDS.
It also identifies the primary and backup display systems.
Figure (4) shows the location of the QSPDS in the Control Room.
Figure (5) provides the sensor locations for the Inadequate Core Cooling instrumentation.
QUESTION 3.
Describe locations of the Heated Junction Thermocouple (HJTC) sensors in the reactor vessel and identify any deviation from the standard CESSAR-80 system design.
RESPONSE
The HJTC design incorporates two separate probe assemblies which enter the reactor vessel through the two Reactor Vessel Level Monitoring System (RVLMS) nozzles located on the top of the reactor vessel head as shown in Figure (6).
There are a total of 8
HJTC sensors on each of the two probe assemblies.
Their respective locations are shown on Figure (7) relative to the fuel alignment plate.
QUESTION 4.
The Palo Verde Nuclear Generating Station (PVNGS)
RVLMS design is identical with the Standard System 80 design.
There are no plant specific deviations.
Therefore, the discussion in CESSAR Appendix B,~ Section II.F.2 is applicable to the PVNGS System.
In the CESSAR SER it is required that the CE Owners Group (GEOG) should provide a modification to the generic GEOG Emergency Procedure Guidelines (EPG),
CEN-152, Revision 1, for use of the RLVMS.
Discuss the status of the GEOG effort with respect to this requirement including the completion schedule and provide the completio'n schedule 'for Arizona Public Service Company (APS) to incorporate this GEOG EPG into the PVNGS ICC procedures.
RESPONSE
In a letter to D.
G. Eisenhut,
- USNRC, from R.
W. Wells,
- GEOG, dated October 28,
- 1983, the NRC was informed that the GEOG authorized the incorporation of the RVLMS information into the EPGs as Revision 2
to CEN-152.
The GEOG is to submit this revision to the EPGs to the NRC by April 1984.
Once Revision 2
to CEN-152 is issued, APS will review the EPG modifications for the RVLMS information and determine what revisions to the PVNGS Procedure Generation Package (PGP) are
- required, or what deviations are necessary.
Any revisions made to the PVNGS PGP will be made in accordance with the description and schedule (shown in Figure 8) identified in the letter to G.
W. Knighton, NRC, from E.
E.
Van Brunt, Jr.,
- APS, (ANPP-23213) dated June 30, 1983.
Even though the above
'J h
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ATTACk&KNTA Page 6 of 15 referenced letter pertains to the TMI Action Plan Item II.K.3.5, the plan and schedule for the plant specific activities of factoring the GEOG program results into the PVNGS EOPs and operator training applies to the subject of incorporation of the RVLMS information.
Therefore, the evaluation and inclusion of the CEN-152; Revision 2
changes into the PVNGS PGP will be completed within 6 months of receipt of the NRC approval of the Revision 2 changes.
QUESTION 5.
Clarify the implementation schedule for declaring that the final ICCI system is fully operational.
RESPONSE
The final ICCI installation and verification will be four (4) weeks after the completion of the fuel load on PVNGS Unit 1.
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Attachment A
Page S
of'=J,5 TABLE 1 COMPARISON BETWEEN CFMS AND ERFDADS Regulation Re uirement Re ulation CFMS Non-Class IE ERFDADS Non-Class IE NUREG 0696 Emergency
Response
Facility Criteria o
Human Engineered Safety Parameter Display System o
Nuclear Data Link (Hardware'Portion) o Human Engineered Safety Parameter Display System o
Nuclear Data Link (Hardware Portion) o Technical Support Center Data System o
Technical Support Center Data System o
Emergency Operation Facility Data System o
Emergency Operation Facility Data System NUREG 0737 o
Human Engineered Primary Display o
Human Engineered Primary Display Regulatory Guide 1-97 Accident Monitoring Instrument and Display Regulatory Guide 1.23 Meterological Data Acquisition, Recording and Retention o
Categories 2 and 3 Signal processing and display (Category 1 signal processing met by Class IE QSPDS data link to CFMS)
'o Category 3 Signal processing and display o
Categories 2 and 3 Signal processing and display (Category 1 signal processing met by Class IE QSPDS data link to ERFDADS.
Additionally, Category 1
signals are available for display on ERFDADS.)
o Category 3 Signal processing and display
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Page
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Page 13 of 15 FIGURF.. 6 RVLMS Locations
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POWER COMBUSllON ENGINEERING. INC.
t Attachment A
Page 14 of i5
,~FIGURE HOTC Sensor Locations HVTC, SE~P
+ NUMBER.
UGS SuPPoPT 7mTE OuT t 81 goz.z~a P VCI-ALIGQ. PLATE.
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m Attachment A
Page 15 of 15 PIGURE 8 TASK TIifE/tifONTN REVIEW REVISE PSTG REVISE EP 6 RO' VERIPY PROCEDURES VALIDATE PROCEDURES INC. INTO STATION >MiiUAL INC INTO TRAINING PROGRAM(
6 10 months for resulcs from CE 6
mone.hs for incorporation into pvÃCS 12 16 months from stare to comploeion
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