ML17262B058
| ML17262B058 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 10/14/1992 |
| From: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Andrea Johnson NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, RTR-REGGD-01.097, RTR-REGGD-1.097 NUDOCS 9210220288 | |
| Download: ML17262B058 (40) | |
Text
, ~CCELER~TEO ISTRIaUTION OEMONSTR~TION SVSTEM REGULATO*.
INFORMATION DISTRIBUTION ZSTEM (RIDE)
I ACCESSION NBR:9210220288 DOC.DATE: 92/10/14 NOTARIZED: NO DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G
05000244 AUTH.NAME AUTHOR AFFILIATION MECREDY,R.C.
Rochester Gas 6 Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION JOHNSON,A.R.
Project Directorate I-3
SUBJECT:
Forwards response to RAI re NUREG 0737,suppl 1,
"Emergency
Response
Capability" 6 rev to reg guide 1.97,rev 3, "Post Accident Instrumentation Comparison. Table."
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TITLE: OR/Licensing Submittal:
Suppl 1 to NUREG-0737(Generic Ltr 2-33)
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. NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
05000244 RECIPIENT ID CODE/NAME PD1-3 LA JOHNSON,A
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A NOTE TO ALL "RIDS" RECIPIENTS:
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~/rztzz zznrm ROCHESTER GAS AND ELECTRIC CORPORATION ct 89 EAST AVENUE, ROCHESTER N.Y. 14649-0001 ROBERT C MECREDY Vice President Cinna Nudear Production October 14, 1992 TELEPHONE AREACODE TtB 546 2700 U.S. Nuclear Regulatory Commission Document Control Desk Attn:
Allen R. Johnson Project Directorate I-3 Washington, D.C.
20555
Subject:
Emergency
Response
Capability/NUREG 0737, Supplement 1
R.
E. Ginna Nuclear Power Plant Docket No. 50-244
, Ref.(1):
NRC letter, A. Johnson to R. Mecredy (RGGE),
"Emergency
Response
Capability
Request for Additional Information", dated July 7, 1992.
(2):
RGGE letter, R. Mecredy to M. Hodges (NRC),
"NUREG 0737 Supplement 1/Regulatory Guide 1.97:
Comparison of Ginna Post Accident Instrumentation,"
dated March 13, 1992.
Dear Mr. Johnson:
By letter dated July 7, 1992 (Reference 1), your office requested additional information regarding the post accident instrumentation capabilities at Ginna Station.
Enclosure 1 to that letter listed sixteen items requiring response.
Attachment 1 to this letter provides the requested response.
In addition your request has made evident the need for us to revise our, "Regulatory Guide 1.97, revision 3/Ginna Post Accident Instrumentation Comparison Table",
attachment 3, table 1 of our letter dated March 13, 1992 (Reference 2).
This revision, along with a summary of changes, is provided as Attachment 2 to this letter.
You will notice in this revised table that several Type A variables have been reclassified.
This resulted from a detailed review of the current Ginna Emergency Operating Procedures against the variable classification criteria.
The previous table reflected classifications dating back to our original submittals on the
- subject, over five years ago.
We hope that the information provided herein'adequately addresses your concerns.
We are prepared to support any further discussions required to resolve these questions.
Very t, uly yours,
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BJF/246 9Zg0ZZOZ88 9ZiOf PDR ADOCH, 05000Z~gp
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Robert C. Mecr dy (P~gO" Ob5
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xc'r. Allen R. Johnson (Mail Stop 14D1)
Project Directorate I-3 Washington, D.C.
20555 U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 US NRC Ginna Senior Resident Inspector
Attachment 1
The responses below are numbered to be consistent with the Request for Additional Information (RAI), attached to USNRC letter, A.R.
Johnson to R.C.
Mecredy (RGE),
"Emergency
Response
Capability Request for Additional Information," dated July 7, 1992.
RCS Cold Leg RGGE concurs with the conclusion of the RAI that one channel of environmentally qualified RCS Cold Leg Temperature should be recorded.
RGGE will assess the means of providing this capability (dedicated recorder or plant process computer), the cost of the modification, and
<<any time constraints to establish a
schedule for this upgrade.
At this time, we expect completion of this modification during the 1994 Refueling Outage.
We would like to note that currently a
channel of RCS Cold Leg Temperature (not environmentally qualified) is recorded both via a dedicated recorder and by the plant process computer.
2.
Containment Sump Water Level Narrow Range The Ginna Containment design incorporates two sumps, Sump A
(instrument sump) directly below the reactor vessel, and Sump B which is used for post-accident recirculation.
Sump A
extends from approximately elevation 205'0" up to the Containment basement floor level, elevation 235'8".
Sump A
can hold less than 50,000 gallons.
The instrumentation listed under Item 33 of Table 1 of our March 13, 1992 submittal as narrow range measures liquid level in Sump A up to roughly the Containment basement floor.
This sump would quickly become filled during LOCA conditions, and is therefore only useful during normal operation for detection of small leaks, and as an initial indication of a LOCA.
Liquid in Sump A is not available for post-accident recirculation.
Therefore it is considered Type C, category 3 post accident instrumentation.
The bottom of Sump B (elevation 227'2") is approximately eight feet below the containment basement floor (elevation 235'8").
The suction for sump recirculation operation of the Residual Heat Removal (RHR) system is in Sump B approximately one foot above the bottom.
Item 23 of Table 1 of our March 13, 1992 submittal (i.e. wide range), lists instrumentation to monitor liquid level in Sump B.
Two channels of five level switches
F, l
(
4 ~
each correspond to levels of 8, 78,
- 113, 180, and 214 inches from the bottom of Sump B.
214 inches corresponds to approximately 500,000 gallons in Sump B.
These instruments are used during an accident to verify that water is being delivered to Containment, and to verify adequate level for the operator to initiate sump recirculation ifrequired. Therefore these channels are considered Type A category 1 post-accident instruments.
NRC SER dated 12/4/90 found the instrumentation provided to monitor both sump levels to be acceptable.
Containment Isolation Valve Position Regulatory Guide 1.97, revision 3
recommends containment isolation valve position indication to verify "accomplishment of isolation".
At
- Ginna, containment isolation occurs concurrent with a Safety Injection (SI) signal, i.e.
when pressurizer pressure drops below a nominal 1723 psig, steam line pressure drops below a nominal 514 psig, or containment pressure exceeds a nominal 4.0 psig.
Containment isolation can also be manually initiated from the control room.
Receipt of an SI signal causes the operator to enter emergency operations procedure E-O, "Reactor Trip or Safety Injection".
Step 12, an immediate action step, requires the operator to verify containment isolation.
This step verifies "accomplishment of isolation" well before any containment isolation valves outside containment experience a
harsh environment.
At no other time in the EOP's is the operator directed to monitor this position indication.
Since it is not credible for penetrations once isolated to spuriously open (minimum of two failures required), it is not necessary for the operator to reverify the isolation function during recovery operation when these valves may be exposed to a harsh environment.
At some point following initial containment isolation the operator may be directed to open specific containment penetrations.
In order to open penetrations the operator must first manually reset the Containment Isolation function, and then manually reset interlocks for the individual valve(s).
The operator is directed to open specific valves for specific
- purposes, such as restoring control air,to containment, or restoring RCP seal flow.
The position of such valves is determined by monitoring the process functions for which the valves were opened.
)
l w
I n
Since isolation is verified prior to these valves seeing a
harsh environment, RG&E does not. consider it necessary to environmentally qualify this indication.
Seismic qualification of the indicating lamps is being addressed under the SQUG program, which has been previously approved by the NRC for use at Ginna.
4.,
RHR Heat Exchanger Outlet Temperature Following the injection phase of a design basis accident the Residual Heat Removal (RHR) System can be used to remove decay heat from the reactor core by one of three methods:
1.
Normal cooldown taking suction from the loop A hot leg and discharging to the loop B cold leg; 2.
Sump recirculation taking suction from the Containment Sump B
and discharging into the reactor vessel upper plenum; 3.
High head sump recirculation taking suction from Containment Sump B
and discharging to the safety injection pump(s) suction which in turn discharges into the RCS cold legs.
In order for the RHR heat exchanger outlet temperature RTD to experience a harsh environment significant, fuel failure must occur.
For situations where normal cooldown (1) or high head sump recirculation (3) are used, the RHR heat exchanger outlet temperature RTD is not exposed to a harsh environment and therefore environmental qualification is not required.
Post-accident cooldown utilizing either methods 2 or 3 above is accomplished using procedure ES-1.3 "Transfer to Cold Leg Recirculation."
This procedure requires manual alignment of component cooling water to the RHR heat exchangers, and manual adjustment of RHR flow.
Therefore it is highly unlikely that the heat exchangers do not function.
This procedure directs the operator to verify adequate core cooling using core exit thermocouples and reactor vessel level indication (step 14).
Both indications are environmentally qualified.
Verification of core cooling is considered an acceptable alternate means of verifying RHR system effectiveness.
5.
Refueling Water Storage Tank Level RGGE has confirmed that loss of instrument bus 1A will not cause a loss of main control board indication of RWST level channel LT-920.
The portion of this channel containing the
transmitter and main control board indicator is isolated from the computer indication portion of the channel by a Foxboro model M/66B current repeater, powered from instrument bus 1C.
Primary System Power Operated Relief Valve Position We have reviewed the criteria used to classify post-accident instrumentation at Ginna and have determined that we have misclassified primary system power operated relief valve (PORV) position indication as Type A.
We concur with Regulatory Guide 1.97, revision 3
that the correct classification should be Type D,
with Category 2
qualifications.
The existing configuration meets these criteria.
We would like to note that although not environmentally qualified, discharge temperature indication does provide backup indication of PORV position, and is supplied from a separate safety related power source.
Seismic qualification of the indicating lamps is being addressed under the SQUG program, which has been previously approved by the NRC for use at Ginna.
Main Steam Flow We have reviewed the criteria used to classify post-accident instrumentation at Ginna and have determined that we have misclassified Main Steam Flow indication as a Type A variable.
We concur with Regulatory Guide 1.97, revision 3, that the correct classification should be Type
,D, with Category 2
qualifications.
The existing configuration meets these criteria.
The nomenclature 1A/1C entered in Table 1 of our March 13, 1992 submittal as the power source for two channels of main steam flow, and six channels of main feedwater flow (Xtem 68) represents the Advanced Digital Feedwater Control System (ADFCS) power supply system which auctioneers from instrument buses 1A and 1C.
This design has been shown to maintain the independence of the two buses.
Letdown Outlet Flow Regulatory Guide 1.97, revision 3 defines design flow as "the maximum flow anticipated in normal operation".
The maximum letdown flow anticipated during normal operation (isolation valve for the largest of three flow restricting orifices open) is 60 gpm.
Therefore the range of the instrument listed, 0 100
- gpm, provides indication of 0
167>
design flow as
'I
defined in Regulatory Guide 1.97, revision 3, and therefore exceeds the recommended range.
Our entry in Table 1, Item 76 of our March 13, 1992 submittal will be modified to reflect this.
9.
High-Level Radioactive Liquid Tank Level Waste drain tank level (LT-1001) indication is provided at the Waste Disposal Panel in the Auxiliary building.
In addition high'tank level alarms at the panel, and consequently at the main control board (Waste Disposal Panel annunciator).
Any operator action based on LT-1001 requires manipulation at the Waste Disposal
- Panel, and therefore an operator would be dispatched to the panel where the indication is available.
We consider this alarm to provide adequate control room Waste Drain Tank level indication.
Waste drain tank level indication is also available at a
remote terminal in the Technical Support Center.
10.
Status of Standby Power Bulk Nitrogen header pressure (PT-1066) is displayed at the Waste Disposal Panel.
In addition low header pressure is alarmed at the panel and consequently at the main control board.
Any operator action based on PT-1066 would require local action, and therefore an operator would be dispatched to the panel where the indicator is available.
While the Nitrogen Gas header monitored by PT-1066 does provide nitrogen gas blankets to several radioactive decay tanks, it is not an energy source as described in Regulatory Guide 1.97, revision 3.
Therefore RG6E will remove it from its list of post accident instrumentation (Table 1, Item 83).
11.
Particulates and Halogens The range deviations for containment vent and plant vent particulate and halogen monitors were evaluated and found acceptable in NRC SER dated December 4,
- 1990, same subject (Item 3.3.22).
The associated TER states that the regulatory guide basis assumes one common vent whereas Ginna Station has two vents.
The ranges monitored are adequate to measure all credible releases through the vents.
The ability to obtain post-accident effluent grab samples (i.e. SPING monitor filter changeout) from the plant vent and containment vent, thereby extending the monitored
- range, was evaluated during NRC inspection 50-244/88-20 and found to be acceptable.
12.
Plant and Environs Radiation The provided range deviations for portable sampling were evaluated and found acceptable in NRC SER dated December 4,
- 1990, same subject.
As stated in the accompanying TER "Because of the potential for personnel
- exposure, the licensee would not use portable instrumentation to assess radiation levels greater than the provided ranges."
13.
Redundancy and Separation When modifying safety related electrical circuits, including post-accident category 1 instruments, RG&E attempts to comply with IEEE Standard 384-1981, section 6.1 separation criteria if practicable.
Deviations from this criteria are addressed in the modification specific safety analysis.
RG&E does not consider that separation of individual redundant circuits in the control room would provide any significant benefit, given the existing original design configuration, which does not provide for separation.
RG&E has demonstrated the ability to achieve safe shutdown in the event of a complete loss of the control room in response to Appendix R.
We believe that this adequately addresses credible multiple failures of redundant equipment in the control room.
14.
Equipment Identification As stated in our March 13, 1992 submittal RG&E feels that the appropriate place to address control board instrumentation labeling and demarcation is in our Detailed Control Room Design Review (DCRDR).
This review was performed in accordance with NUREG-0700, and has been reviewed and approved by the NRC.
- Labeling, demarcation, and color coding of control board instruments is in accordance with the Ginna
- DCRDR, and the Ginna Human Factors Manual.
No requirement exists for commonality of identification of post-accident monitoring instrumentation.
While we concur with the RAI that the Type A post-accident instruments do constitute the minimum set of required indications to be monitored following a design basis
- event, they do not necessarily constitute the most appropriate instruments to be monitored for any specific event or at any given time.
For example the initial actions required of the control board operator during emergency operations involve monitoring instruments to verify proper actuation of automatic safety systems (Type D
variables).
Depending on the situation, this could include category' instruments.
We
I 1y 1
V ii
believe that a common designation for specific post-accident instruments does not provide useful information, could lead to confusion, and may actually distract the operator from monitoring other more appropriate instruments.
We have reviewed the list of Ginna post-accident Category 1
Types A,
B and C instruments.
Of the variables monitored, non-qualified indication exists for only three.
Of these three, two are clearly distinguishable from qualified channels due to range (Containment Pressure channel PT-944 has a range of 0 to 5 psig),
and labeling (Pressurizer Level channel LI-433A is labeled "PRZR Cold Calib Level" and is only used for fillingthe pressurizer).
Unqualified channels for RCS Cold Leg Temperature will be evaluated, and means provided to ensure that operators are aware that these channels may not provide correct indication if exposed to a harsh environment.
We anticipate this change can be made within six months of issuance of Ginna Regulatory Guide 1.97 SER.
15.
Interfaces Due to the original design of Ginna Station, some existing RG 1.97 designated Category 1 and 2 instruments are not isolated from other circuits and components which would have less stringent design criteria.
In the original design of the plant all instrument indication was considered non-safety related.
Consequently indicators were normally designed to share the same instrument loop with controllers, annunciators, and plant process computer (PPCS) inputs.
Qualification of these various components including the indicators was comparable, i.e.
control grade.
This portion of the instrument loop is isolated from what was then considered the safety-related portion of the channel if applicable (i.e.
With the replacement of the PPCS at Ginna, qualified isolation panels (MUX panels) were installed for all inputs to the PPCS.
However, separation of redundant input cables to these panels was not upgraded.
Circuit separation is discussed in the response to question 13.
Isolation from control circuits for Category 2 indications would only be a concern if the control functions were subject to a harsh environment, since seismic qualification and redundancy is not required for Category 2.
There is no harsh environment for the equipment at Ginna Station.
The degree of redundancy for Category 1 indications minimizes the potential for complete loss of indication.
Generally only one channel of these variables provides a
controlling function.
- Also, generally these loops are contained within the control
- room, where fault levels are minimized.
Given the demonstrated ability to safely shutdown the plant outside the control room, and the limited benefit which is considered to be available by additional electrical
isolation in the control
- room, given existing separation conditions (see question 13),
RG&E does not feel that a
detailed analysis of each individual loop can be justified.
For the reasons discussed
- above, RG&E does not feel that categorical isolation of all existing category 1
and 2
indication loops, from control functions is warranted.
When it can be accommodated during a major modification, pro-active efforts are made to isolate and upgrade Category 1 indicators in accordance with current standards.
We consider this a good faith effort to meet the intent of the Regulatory Guide.
16.
Commitment to R.G.
1.97 RG&E has provided documentation comparing Ginna Station post-accident instrumentation to the recommendations of Regulatory Guide 1.97, revision 3.
Deviations from the guidance have been explicitly identified, with supporting justification.
RG&E post-accident instrumentation is identified in the Ginna UFSAR.
As such, any modifications to the equipment must have a safety evaluation performed in accordance with 10CFR50.59.
This assures that future modifications to the post-accident instrumentation will not degrade its performance.
As described in our responses to question 13 and 15, RG&E attempts to comply with current standards for separation, redundancy, and isolation.
Design criteria and safety analyses for modifications document acceptability of alternative standards if "current criteria" cannot be met.
BJF/031
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t
ATTACHMENT 2 Table 1, revision 1
Com arison of Ginna Post-Accident Instrumentation to Re ulator Guide 1.97 Revision 3 Criteria Summary of Changes ITEM s
- 1. 2,4,5,10, 17 I 21 2.
27 3.
41 4.
46 5.
51, 52 6.
55 7.
59 8.
67 9.
69 10.
76 11.
80 CHANGE Deleted as Type A variables Added RCS Hot Leg Channels Corrected range cited in note to 10 psia to 3004 design Added Containment hydrogen concentration channels Changed loop designators for channels LT-934, PT-
- 936, and PT-940.
Added High Pressure Injection (SI) Flow Channels Added Pressurizer PORV position indication Added Main Steam Flow channels; corrected category for FT-498, FT-499 Added standby auxiliary feedwater flow channels Corrected channel range Added note regarding location of indication REASON FOR CHANGE Review of variables against current emergency procedures, and classification criteria established that these variables no longer meet the classification criteria for Type A.
Formerly Type A variables The range provided satisfies all recommendations Formerly Type A variable.
New equipment identification number represents change in plant nomenclature Designation change does not affect equipment attributes.
Formerly Type A variable Formerly Type A variable Formerly Type A variable.
Category changed to reflect lack of environmental qualification of these 2
channels Formerly Type A variable See Attachment 1, Item 8.
NRC RAI requested this clarification
ITEM s 12.
83 13.
84 CHANGE Deleted channel PT-1066.
Added containment high radiation channels REASON FOR CHANGE The channel does not monitor a "power source" as described in RG 1.97, revision 3.
See Attachment 1, Item 10.
Formerly Type A variable.
BJF/032
TYPE
- VARIABLE, CAT.
RANGE Attachment 2
Table 1, revision 1
Comparison of Glnna Post Accident Instrumentatlon to Regulatory Guide 1.97, Revision 3 Criteria C.R.
RECORDER EEQ SEISMIC QA P.S.
IND.
CHART COMP COMMENTS Page 1 of 20 1
n.a.
Aux Feedwater Flow 1
Plant Specific y es yes full 1E yes Plant Specific A
Fi'-2001 (MDAFW/SGA) 1 0 - 275 gpm (0-138%)
Fl'-2013 (MDAFW/SGA) 1 0 - 275 gpm (0-138%)
FT-2002 (MDAFW/SGB) 1 0 - 275 gpm (0-138%)
Fl'-2014 (MDAFW/SGB) 1 0- 275 gpm (0-138%)
Fi'-2006 (fDAFW/SGA) 1 0- 500 gpm (0-125%)
FT-2007 (fDAFW/SGB) 1 0 - 500 gpm (0-125%)
mild yes mild yes mild yes mild yes mild yes mild yes SR SR SR SR SR SR 1A FI-2021A 1C FI-2029 1C FI-2022A 1A FI-2030 1C FI-2023A lA FI-2024A no no no no no no F2021 two per redundant function provided F2029 F2022 F2030 F2023 F2024 also satisfies 469 deleted Core Exit 3
n.a.
Thermocouples A
Tl - T39 1
Plant Specific 1
0-2300'F yes yes full 1E yes Plant Specific yes yes SR 1A CETA no yes 39 CEPs are provided. Technical 1C CETB Specifications require a minimum offour operable per quadrant. 19 CET's ate associated with the Atrain and 20 with the B Train.
also satisfies N's 30,37 deleted deleted
TYPE VARIABLE EEQ SEISMIC QA Attachment 2
Table 1, revision 1
Comparison of Ginna Post Accident Instrumentatlon to Regulatory Guide 1.97, Revision 3 Criteria C.R.
RECORDER P.S.
IND.
CHART COMP COMMENTS Page 2 of 20 6
n.a Containment Pressure 1
Plant Specific yes yes full lE y es Plant Specific A
FI'-945 Fi'-946 PT-947 Pl'-948 Ff-949 PT-950 1
0-60 psig 1
10-200 psia 1
0-60 psig 1
10-200 psia 1
0-60 psig 1
10-200 psia jjcs ycs ycs ycs yes yes ycs ycs yes yes ycs yes SR SR SR SR SR SR 1A PI-945 1B PI-946 lc PI-947 1C PI-948 1B PI-949 MQ483PI-950 no P0945
~eserecorders are proposed to be removed yes*
no with inputs to the SAS/PPCS provided no P0947 instead.
yes*
no no P0949 no no also satisfies items ¹35,41 Condensate Storage 7
n.a.
Tank Level 1
Plant Specific yes yes full 1E yes Plant Specific A
LT-2022A (tank A)
LT-2022B (tank B) 1 0-24 ft 1
0-24 ft mild mild ycs ycs-SR SR 1A LI-2022A no L2022A The transmitters are not located in a Seismic 1C LI-2022B no no Category 1 building. The tanks are connected by a locked open 10" line.
8 n.a.
Pressurizer Pressure 1
Plant Specific y e s yes full lE yes plant specific A
PT429 PT430 PI'431 PT449 1
1700-2500 psig 1
1700-2500 psig 1
1700-2500 psig 1
1700-2500 psig yes yes yes yes jjcs ycs ycs ycs SR SR SR SR lA PI429 1B PI430 1C PI431 1D PI449 PR429 P0429 PR429 has the capability ofrecording any PR429 F0430 one of the four channels at a time (switch PR429 F0431 selectable).Although channel FI'449 is not PR-429 P0449 powered from a safety related supply, itis maintained as a catagory 1 variable in all other aspects. Its protection signals are failsafe.
9 n.a.
Pressurizer Level 1
Plant Specific yes yes
-full 1E yes Plant Specific A
LT426 LT427 LT428 1
0-100%
1 0-100%
1 0-100%
ycs jjcs jjcs ycs jjcs ycs SR SR SR 1A LI426 LR428 L0426 Level instrumentation does not cover the 1B LI-427 LR428 L0427 hemispherical top and bottom ofthe 1C LI428 LR428 L0428 pressurizer.
also satisfies item ¹60 10 deleted
¹ TYPE VARIABLE Attachment 2
Table 1, revision 1
Comparison of Ginna Post Accident Instrumentation to Regulatory Guide 1.97, Revision 3 Criteria C.R.
RECORDER CAT.
RANGE EEQ SEISMIC QA P.S.
IND.
CHART COMP COMMENTS Page 3 of20 RCS Cold Leg 11 n.a Temperature 1
Plant Specific y e s y e s full 1E y e s Plant Specific A
TE409B-1 (Loop A)
TE410B-1 (Loop B) 1 0-700 OF 1
0-700 OF yes yes SR lA TI409B-1 no>>
yes yes SR 1C TI410B-1 no*
no*
<<Currently two channels, TE450, TE451 are no*
recorded (chait and PPCS). These channels are not post accident environmentally qualified. A modiTication to provide recording (PPCS or chart) ofone qualified channel is proposed.
also satisfies item ¹28 12 deleted 13 n.a.
RCS Pressure A
PT420 PT420A 1
Plant Specific 1
0-3000 psig 1
0-3000 psig y es yes full 1E yes Plant Specific yes yes SR 1A PI420 PR420 P0420 yes yes SR 1C PI420A PR-420A P0420A RHR Flow (low 14 n.a.
pressure injection) 1 Plant Specific yes yes full 1E yes Plant Specific also satisfies items ¹29,40 A
FT-626 1
0-4000 gpm (FT-xxx)**
(1)
(0 - 4000gpm)
Fl'-931A (Loop A)*
1 0- 2200 gpm FT-931B(LoopB)<<1 0-2200gpm yes yes SR (yes)
(yes)
(SR) yes yes SR yes yes SR 1C F1426 (1A)
(yes) 1C FI-931A 1B FI-931B FR-626 F0626
- Fl'-931A and FI'-931B monitor RHR flow (no)
(yes) toContainmentSprayandSIpumpssuction.
no no
<<<<AredundantflowtransmittertoFT426 no no utilizing the same primary element is proposed.
also satisfies items ¹49, 56 Reactor Vessel Level 15 n.a.
Indication System 1
Plant Specific y e s yes full 1E y e s Plant Specific A
LT490A LT490B 1
0- 100%
1 0- 100%
yes yes SR 1A LI490A yes yes SR 1C LI490B no L0496A RVLISreceives 'correction'nputs from sensor no L0496B line temperature, RCP status, RHR flow, SI flow,CETs, RCS pressure, and Tcold. Where both channels have common inputs the input signals to each channel are isolated.
also satisfies item ¹31
¹ TYPE VARIABLE EEQ SEISMIC QA CAT.
RANGE Attachment 2
Table 1, revision 1
Comparison of Ginna Post Accident Instrumentation to Regulatory Guide 1.97, Revision 3 Criteria C.R.
RECORDER IND.
CHART COMP COMMENTS Page 4 of 20 16 n.a.
Refueling Water Storage Tank Level 1
Plant Specific yes yes full 1E yes Plant Specific LT-920 LT-921 1
0- 100%
1 0- 100%
mild yes mild yes SR SR 1C*
LI-920 no L0920 1A LI-921 no L0921
- Computer indication of this channel also requires power from 1A.
17 deleted also satisfies item ¹57 18 n.a.
Steam Generator Range Level A
LT-504 (SG A)
LT-505 (SG A)
LT-506 (SG B)
LT-507 (SG B)
Wide 1
Plant Specific 1
0-100%
1 0-100%
1 0-100%
1 0-100%
yes yes ycs jjcs yes ycs ycs ycs ycs ycs fu 1 1 SR SR SR SR 1E yes Plant Specific 1A LI-504 LR-504 L0504 1C LI-505 LR-505 L0505 1A LI-506 LR-506 L0506 1C LI-507 LR-507 L0507 Two per Steam Generator required for two loop plants Two per Steam Generator provided.
also satisfies item ¹65 19 n.a.
Steam Generator Narrow Range Level 1
Plant Specific yes yes full 1E y es Plant Specific A
LT461 (SG A)
LT462 (SG A)
LT463 (SG A)
LT471 (SG B)
LT472 (SG B)
LT473 (SG B) 1 0-100%
1 0-100%
1 0-100%
1 0-100%
1 0-100%
1 0-100%
yes yes ycs ycs ycs jjcs ycs ycs ycs jjcs ycs ycs SR SR SR SR SR SR 1A LI461 1C LIW2 1D LIW3 1D LI471 1A LI472 1B LI473 yes*
yes*
yes*
yes~
jjCS*
yes*
L0461 L0462 L0463 L0471 L0472 L0473
- Median of3 channels per generator is recorded.
Although channels LT463 and LT471 are not powered from a safety related supply, they are maintained as catagory 1 variables in all other aspects.
also satisfies item ¹65 20 n.a.
Steam Generator Pressure 1
Plant Specific yes yes full 1E y e s Plant Specific A
PT468 (SG A)
PT469 (SG A)
PTAS (SG B)
PTP79 (SG B)
PT-482 (SG A)
PT-483 (SG B) 1 0-1400 psig 1
0-1400 psig 1
0-1400 psig 1
0-1400 psig 1
0-1400 psig 1
0-1400 psig yes yes ycs yes ycs ycs ycs ycs yes yes ycs ycs SR SR SR SR SR SR 1A PIC68 1B PI469 1C PI478 MQ483PI479 1C PIP 82A 1B PI483A no no no no no no F0468 F0469 F0478 F0479 P0482 F0483 also satisfies item ¹66
TYPE VARIABLE Attachment 2
Table 1, revision 1
Comparison of Ginna Post Accident Iustrumentatlon to Regulatory Guide 1.97, Revision 3 Criteria C.R.
RECORDER CAT.
RANGE EEQ SEISMIC QA P.S.
IND.
CHART COMP COMMENTS Page 5 of20 21 deleted RCS Subcooling 22 n.a.
iMonltor 1
Plant Specific y e s y e s fu ll 1E y e s Plant Specific A
TI409A TIP10A 1
0- 100'F subcooled yes yes SR 1
0- 100 'F subcooled yes yes SR 1A TI-409A 1C TIPIOA no
- TSUBA*GinnaEOPs provide the means for no
- TSUBB determining subcooling based on CET's and RCS pressure. The SAS/PPCS also calculates subcooling using these variables. Both capabilities exceed the range recommended in RG 1.97, rev 3. Also satisfies item ¹32 Containment Sump 23 n.a.
Wide Range Level 1
Plant Specific y es yes full 1E yes Plant Specific A
LC-942 (A-E)
LC-943 (A-E) 1 8, 78, 113, 180,214 in ycs 1
8,78, 113, 180,214 in yes yes SR 1A yes no yes Five discrete level switches per channel, 214 yes SR 1C yes no yes inch indication corresponds to approximately
'500,000 gallons.
also satisfies items ¹34, 43 24 B
Neutron Flux 1
% -100
%popover yes yes full 1E yes Plant Specific B
N-31, N-32 (SR) 3 1E-1 to 1E6cps (SR)
N-35,N-36 (R) 3 lE-11 tolE-3Amps(IR)
NAIA,B;NBA,B; 3
0 to 100%power (PR)
NBA,B;NMA,B(PR) 3 no yes no yes no yes no yes SR**
1A/1B NI-31, 32 SR**
1A/1B NI-35, 36 SR**
lA/1B NI41,42 SR**
1C/1D NI43,44 (B suffixfor MCB ind.)
yes*
yes yes>>
yes yes*
yes yes*
yes Neutron fluxindication is considered a backup type B indication at Ginna and is therefore considered catagory 3.
- Atwo pen recorder is provided with switchable inputs from all channels.
- Protection portions of channels only.
25 B
Control Rod Position 3
full ln or not full in no no comm.
n.p.
no no B
MicroprocimorRod Position Indication System (MRPI) 3 rod position indicated in no twelve step increments, as weH as indication of rods fullin or not full no SS yes no yes
- TheMRPIsystemispoweredfroma dedicated transformer Irom a safety related 480V MCC.
¹ TYPE VARIABLE Attachment 2
Table 1, revision 1
Comparison of Glnna Post Accident Instrumentatlon to Regulatory Guide 1.97, Revision 3 Criteria C.R.
RECORDER CAT.
RANGE EEQ SEISMIC QA P.S.
IND.
CHART COMP COMME'S Page 6 of 20 RCS Boron 26 B
Concentration 3
0 to 6000 ppm n o n o comm.
n.p.
n o no B
AIM53(Post Accident 3
50~+0 - 600M300 ppm no no SS Sampling System (PASS) Boron Analyzer) no no no
NRC SER dated April 14, 1986 deferred the range and accuracy capabilities ofpost accident sampling systems to NUREG-0737, Item II.B.3. The Ginna PASS meets these criteria.
RCS Hot Leg Water 27 B
Temperature 1
50 'F - 700 F
yes yes full 1E yes Plant Specific B
TE409A-I (Loop A)
TEPIOA-I (Loop B).
1 0700oF 1
0-700 oF yes yes SR 1A TI409A-I no T0409A yes yes SR 1C TIPIOA-I no
=
T0410A RCS Cold Leg Water 28 B
Temperature 1
50 'F - 700 'F yes yes full 1E yes Plant Specific
- see item ¹11, RGAE Type A variable.
29 B
RCS Pressure A
1 0 - 3000 pslg y e s y es full 1E yes Plant Specific
- see item ¹13, RGB Type A variable.
30 B
Core Exit Temperature 3
200 'F - 2300 'F no no comm.
n.p.
no no
- see item ¹3, RGB Type A variable.
TYPE VARIABLE Attachment 2
Table 1, revision 1
Comparison of Glnna Post Accident Instrumentation to Regulatory Guide 1.97, RevisIon 3 Criteria C.R.
RECORDER EEQ SEISMIC QA P.S.
IND.
CHART COMP COMMENTS Page 7 of20 31 B
Coolant Inventory 1
Hot Leg bot.- flange yes yes full 1E yes plant specific
- see item ¹15, RG&E Type A variable.
RCS Degrees of 32 B
Subcooiirig 2
200'Fsub-35'Fsuper y es
- n o partial rel.
n o
- see item ¹22, RG&E Type A variable.
Containment Sump 33 B
Level Narrow Range 2
Plant Specific yes: n o partial rel.
no no C
LT-2039 (Sump A)
LT-2044 (Sump A) 3 0-30ft 3
0-30ft no
~ no S S 1A LI-2039 no L2039 NRC SER dated December 4, 1990 found the no
'. no SS 1A LI-2044 no L2044 - instrumentation provided to be acceptable.
Containment Sump 34 B
Level olde Range 1
Plant Specific also satisfies item ¹42 yes yes full 1E yes Plant Specific
- see item ¹23, RG&E Type A variable.
35 B
Containment Pressure 1
-5 pslg to design yes yes full 1E yes Plant Specific
- see item ¹6, RG&E Type Avariable.
note: The Ginna containment pressure indication covers a range of 10 psia to 300 %
design presstire.
¹ TYPE VARIABLE Attachment 2
Table 1, revision 1
Comparison of Ginna Post Accident Instrumentation to Regulatory Guide 1.97, Revision 3 Criteria C.R.
RECORDER CAT.
RANGE EKQ SEISMIC QA P.S.
IND.
CHART COMP COMMENTS Page 8 of20 Contain.
Isolation one per redundant function reqd.
Check 36 B
Valve Position 1
closed / not closed yes yes full 1E yes Plant Specific valve position ind.
is not reqd.
B see UFSAR Table 62.13 3
open/closed forlistofcontainment isolation valves.
no yes S S
- ADC, BDC yes no yes Isolation valves outside containment go closed prior to being exposed to a harsh environment and therefore environmental qualification is not reqd.. RGB has taken exception to the need to qualify indication for valves inside containment. Ref. letter RGB-NRC 5/6/91.
37 C
Core Exit Temperature 1
200'F to 2300'F y e s y e s fu 1 1 1E y e s Plant Specific
- see item ¹3, RGB Type A variable.
38 C
RCS Radiation Level 1
.5 - 100X Tech Spec yes yes full 1E yes Plant Specific n.a.
Post Accident Sampling System (PASS), Manual Radiation Isotopic Spectroscopy after sample taken 3
0.01mR - 1.0E04 R/hr n.a.
n.a.
SS n.a.
no no no NRC SER dated April 14, 1986 found the instrumentation provided to be acceptable.
see note 1.
Gamma Analysis of 39 C
Primary Coolant 3
1.0E-5 10 Ci/ml no n o comm.
n.p.
no no C
Post Accident Sampling 3
1.0E-S - 10 Ci/ml.
n.a.
System (PASS), Manual Range can be extended Radiation Isotopic by dilution techniques.
Spectroscopy after sample taken n.a.
SS n.a.
no no no NRC SER dated April 14, 1986 found the instrumentation provided to be acceptable.
40 C
RCS Pressure A
1 0 - 3000 psig yes yes full 1E yes Plant Specific
- see item ¹13, RG8tE Type A variable.
TYPE VARIABLE Attachment 2
Table 1, revision 1
Comparison of Glnna Post Accident Instrumentatlon to Regulatory Guide 1.97, Revision 3 Criteria C.R.
RECORDER CAT.
RANGE EEQ SEISMIC QA P.S.
IiND.
CHART COMP COMMENTS Page 9 of 20 41 C
Containment Pressure 1
-5 psig to design yes yes full 1E yes Plant Specific
- see item //6, RG&E Type A variable.
note: The Ginna containment pressure indication covers a range of 10psia to 300%
design pressure.
Containment Sump 42 C
Level Narrow Range 2
top to bottom yes n o partial rel.
n o no
- see item //33, RG&E Type C variable.
NRC SER dated December 4, 1990 found the instrumentation provided to be acceptable.
Containment Sump 43 C
Level
~Vide Range 1
Plant Specific y e s y e s full 1E y e s Plant Specific
- see item //23, RG&E Type A variable.
Containment Area 44 C
Radiation 3
1 to 1.0E4 R/hr no no comm.
np.
no no E
R-2 3
0.01 - 1.0E5 Rjhr no yes S S IB yes yes R02 NRC SER dated April 14, 1986 found the
=
instrumentation provided to be acceptable.
Condenser Air Exh.
45 C
Noble Gas Radloact.
2 1E-6 to 1E5 itCI/cc yes n o part.
rel.
n o no E
R-15 R-15A (SPING) 2 1E-6 to 1E-3 pCi/cc mild no 2
1E-6 to 1ES ltCi/cc mild no SS 1D yes yes R15
¹ TYPE VARIABLE Attachment 2
Table 1, revision 1
Comparison of Ginna Post Accident Instrumentation to Regulatory Guide 1.97, Revision 3 Criteria C.R.
RECORDER CAT.
RANGE EEQ SEISMIC QA P.S.
IND.
CHART COMP COMMENTS Page 10 of 20 Containment H2 46 C
Concentration 1
0-10 yes
='yes full 1E yes Plant Specific C
HMSLCPA HMSLCPB 1
0-10%
1 0-10%
yes
'es SR lA no yes yes SR 1C no
~ y yes*
CVHA ~ although the recorders are the only control yes*
CVHB room indication of Containment H2 concentration, they are not considered the primary indicator. The H2 Monitorpanels in the Relay room provide primary indication.
Containment Effluent 47 C
Noble Gas at Release 2
. no partial rel.
no no C
R-12(Cont.Purge Vent) 2 1E-6 to IE-21tCi/cc R-14 (Plant Exh. Vent) 2 lE-6 to lE-1 itCi/cc R-31(SG SteamLineA) 2 1E-1 to 1E3pCi/cc R-32 (SG Steam Line B) 2 1E-1 to 1E3 pCi/cc mild no mild
. no mild
-: no mild; no SR IA SS 1A SS SS ycs yes yes ycs (yes) no (yes) no yes
- SPING Monitors are powered via a dedica yes tranformer from MCC D (Safety Related).
yes SPING monitors R-12A (Cont. Purge Vent) ycs and R-14A (Plant Exhaust Vent) are also available to monitor noble gas releases as well as particulates and iodine.
Containment Effluent 4S C
Noble Gas at Pen.etc.
2 1E-6 to 1E-2 ttCi/cc yes no SS rel.
no no
- see item ¹47. These monitors are considered to provide adequate monitoring ofall credible releases.
49 D
RHR System Flow 2
0 - 110 lo design yes no partial rel.
no A
no
- see item ¹14, RGAE Type Avariable.
RHR Heat Exchanger 50 D
Outlet Temperature 2
40 'F - 350 'F yes n o partial rel.
n o no n.a.
TE627 3
50'F-400'F no 'o SS TSC no no T0627 NRC SER dated 12/4/90 found the range pmvidcd acceptable.
¹ TYPE VARIABLE Attachment 2
Table 1, revision 1
Comparison of Ginna Post Accident Instrumentation to Regulatory Guide 1.97, Revision 3 Criteria C.R.
RECORDER CAT.
RANGE EEQ SEISMIC QA P.S.
IND.
CHART COMP COMMENTS Page 11 of 20 51 D
Accumulator Tank Level 2
10 % - 90 %
yes n o partial n.p.
no no n.a.
LT-934 (Loop A)
LT-935 (Loop A)
LT-938 (Loop B)
LT-939 (Loop B) 3
+7 inches from nominal no 3
+7 inches from nominal no 3
27 inches from nominal no 3
+7 inches from nominal no no SS 1C LI-934 no no no SS 1B LI-935 no no no SS 1C LI-938 no no no SS 1B LI-939 no no NRC SER dated 12/4/90 found the instrumentation provided acceptable. The category 3 designation is consistent with RG&Es category determination philosophy.
52 D
Accumulator Tank Pressure 2
0 - 750 psig yes no partial n p.
no no n.a.
PT-936 (Loop A)
PT-937 (Loop A)
PT-940 (Loop B)
PT-941 (Loop B) 3 0- 800 psig 3
0- 800 psig 3
0- 800 psig 3
0- 800 psig 1C PI-936 1B PI-937 1C PI-940 1B PI-941 no no SS no no no no SS no no no no SS no no no no SS no no NRC SER dated 12/4/90 deferred resolution o these deviations to generic staff review ofthis issue. The category 3 designation is consistent withRG&E's category determination philosophy.
53 D
Accumulator Iso.
Valv,e Position 2
open I closed yes no partial n p.
no no n.a MOV-841 (Loop A)
MOV-865 (Loop B) 3 open/closed 3
open/closed no yes SS ADC yes no no Valves are locked open and d~nergized.
no yes SS BDC yes no no NRC SER dated 12/4/90 found the instrumentation provided acceptable.'oric Acid Charging Flow 2
0 - 110
% design yes no partial rel.
no no n.a.
Fl'-128 2
0-75 gpm mild no SS 1D FI-128B no F0128 NRC SER dated 4/14/86 found the instrumentation provided acceptable 55 D
High Pressure InJectlon (SI) Flow 2
0 - 110
% design yes no partial rel.
no no D
FI'-924 (SIP B)
FT-925 (SIP A) 2 0-1000 gpm 2
0-1000 gpm yes yes SR 1A FI-924 no F0924A yes yes SR 1B, 1C FI-925 no F0925A
¹ TYPE VARIABLE Attachment 2
Table 1, revisIon 1
Comparison of Glnna Post Accident Instrumentatlon to Regulatory Guide 1.97, Revision 3 Criteria C.R.
RECORDER CAT.
RANGE EEQ SEISMIC QA P.S.
IND.
CHART COMP COMMENTS Page12of20
~
Low Pressure 56 D
Injection (RHR) Flow 2
0 - 110 fo design yes no partial rel.
no no
- sce item ¹14, RGB'ype A variable.
57 D
R)VST Level 2
top to bottom y es n o partial rel.
n o no
- see item ¹16, RGAE Type A variable.
58 D
RCP Status 3
motor current D
4.16 kV Bus ammeters 3
0- 1200 A and RCP breaker status lights no no comm.
n.p.
no no no S S n.a.
yes no no yes Pressurizer PORVs 59 D
and Safeties Position 2
closed I not closed yes no partial rel.
no no D
ZS430 (PORV) 2 open/close ZS431C (PORV) 2 open/close TE438(discharge temp.)
3* O'F - 300'F ZT434(SafetyValve) 2 open-close(inches)
ZT435 (Safety Valve) 2 open - close (inches)
TE436;12437(dis temp) 3* 0'F -400'F yes yes ycs ycs no yes yes ycs ycs ycs no yes SR BDC ycs SR
- BDC yes S S lA TI438 SS 1A yes SS 1A yes SS 1A yes, yes no V0430 no V0431 no no no no no no no no
- The RTD's downstream ofthese valves, TE438 (PORVs) and TE436 and TE437 (Safeties), are available in the control room and are considered backup indication ofvalve position.
60 D
Pressurizer Level A
1 top to bottom y e s yes full 1E yes Plant Specific
- see item ¹9, RGB Type A variable.
note: level indication does not cover the hemispherical top and bottom portions of the pressurizer.
TYPE VARIABLE CAT.
RANGE Attachment 2
Table 1, revision 1
Comparison of Ginna Post Accident Instrumentation to Regulatory Guide 1.97, Revision 3 Criteria C.R.
RECORDER EEQ SEISMIC QA P.S.
IND.
CHART COMP COMMENTS Page 13 of 20 Pressurizer Heaters 61 D
Status 2
electric current y es n o partial rel.
n o no D
control bank breaker status lights backup bank breaker status lights 480V Bus voltage and kWdemand 2
closed/auto/on 2
closed/auto/on 2
0- 1500 kW mild no mild no mild no SS n.a.
yes no yes SS ADC yes no no NRC SER dated 12/4/90 found the instrumentation provided acceptable.
SS BDC yes no no Pressurizer Relief 62 D
(Quench)
Tank Level 3
top to bottom no no comm.
n.p.
no no D
LT442 3
0- 100%
no no SS 1B LI442 no L0442 Pressurizer Relief 63 D
(Quench)
Tank Temp.
3 50 'F - 750 'F no no comm.
n p.
no no D
TE439 3
(50 'F - 400 'F) no no SS 1A TI439 no T0439 NRC SER dated 12/4/90 found the instrument range acceptable.
Pressurizer Relief 64 D
(Quench)
Tank Press.
3 0 psig to design no no comm.
n p.
no no D
PT440 3
0 - 150 psig no no SS 1B PI440A no F0440 rupture disk setpoint is 100 psig.
PI440B Steam Generator Wide 65 D
Range Level two per generator required for two loop 1
tube sht - separators yes yes full 1E yes Plant Specific plants
~ see item 818, RGAE Type A variable.
¹ TYPE VARIABLE Attachment 2
Table 1, revision 1
Comparison of Glnna Post Accident Instrumentation to Regulatory Guide 1.97, Revision 3 Criteria C.R.
RECORDER CAT.
RANGE EEQ SEISMIC QA P.S.
IND.
CHART COMP COMMENTS Page 14of20 ~.
Steam Generator Pressure 2
atm. - 20% > safety yes no partial rel.
no no
- see item ¹20, RG&E Type A variable.
67 D
Main Steam Flow (or SG safety valve pos.)
2 0 - 110
% design yes no partial rel.
no no D
Fl'464 (SG A)
FT465,(SG A)..
FT-474 (SG B)
FT475 (SG B)
FT-498 (SG A)
Fl'499 (SG B) 2 0- 3.8E6 pph 2
0- 3.8E6 pph 2
0- 3.8E6 pph 2
0 - 3.8E6 pph 3
0- 3.8E6 pph 3
0- 3.8E6 pph yes yes ycs ycs ycs ycs yes yes no yes no yes SR 1A FI-464 SR 1B FI465 SR lc FI474 SR 1D FI475 SS lA/1C*FI498 S S 1A/1C*FI499 yes+ Q yeso%
yeso&
yes' yes' yes+ Q F0464
- denotes auctioneered power supply from the F0465 Advanced DigitalFeedwater Control System F0474 (ADFCS).
F0475
- Medianof3 channels per SG is recorded.
F0498 F0499 68 D
Main Feedwater Flow 3
0 - 110
% design no no comm.
n.p.
no no D
FT466 (SG A)
Fl'467 (SG A)
FT476 (SG B)
FI'477 (SG B)
FT-500 (SG A)
FI'-503 (SG B) 3 0- 3.8E6 pph 3
0- 3.8E6 pph 3
0- 3.8E6 pph 3
0 - 3.8E6 pph 3
0- 3.8E6 pph 3
0- 3.8E6 pph no no SS no no SS no no SS no no SS no no SS no no SS lA/1C FI466 1A/1C FI467 1A/1C FI476 1A/1C FI477, 1A/1C FI-500 1A/1C FI-503 yes*
F0466
F0467 B) record median flowofthe 3 channels.
yes*
F0476 Main Feedwater Flow transmitters receive yes*
F0477 power Irom the DigitalFeedwater Contml yes*
F0500 System (ADFCS). Power for the system is yes*
F0503 auctioneetcd from buses 1A and 1C.
69 D
Auxiliary Feedwater Flovr 2
0 - 110
% design yes
no partial rel.
no no A
D D
Fi'4084 (Standby *)
2 0-250 gpm (0-125%)
mild yes SR lA FI4084 Fl'4085 (Standby *)
2 0-250 gpm (0-125%)
mild yes SR 1C FI4085
- see item ¹1, RG&E Type A variable.
no
- F4084
- ~ Ginna Station has a manual standby no F4085 auxiliary feedwater, which duplicates the capacity of the motor driven main auxiliary feedwater system.
70 D
Condensate Storage Tank Level 1
Plant Specific yes yes full 1E yes Plant Specific
~ see item ¹7, RG&E Type A variable.
¹ TYPE VARIABLE Attachment 2
Table 1, revision 1
Comparison of Ginna Post Accident Instrumentation to Regulatory Guide 1.97, Revision 3 Criteria C.R.
RECORDER CAT.
RANGE EEQ SEISMIC QA P.S.
IND.
CHART COMP COMMENTS Page 15 of 20 Containment Spray 71 D
Floav n.a.
none 2
0 - 110
'Io design yes no partial rel.
no no
- indirect indication ofContainment Spray flow is available using SI flowand RHR fiow. NRC SER dated 12/4/90 found this acceptable.
Containment Fan 72 D
Heat Removal n.a.
none 2
Plant Specific y es n o partial rel.
n o no
- indirect indication ofContainment Fan heat removal is available using containment air temperature, sump tempemture and-containment pressure. NRC SER dated 12/4/90 found this acceptable.
Containment Alr 73 D
Temperature 40 oF 4PP oF yes no partial rel.
no no D
TE-6031 (elev. 245'0")
TE-6035 (elev. 261'")
TE4036 (elev. 261'")
TE-6037 (elev. 261'")
TE-6038 (elev. 261'")
TE-6045 (elev. 286'4")
2 O'F - 300'F 2
O'F - 300'F 2
0'F - 300'F 2
O'F - 300'F 2
O'F - 300'F 2
0'F - 300'F (yes)
(yes)
(yes)
(yes)
(yes)
(yes)
(ycs)
(yes)
(yes)
(yes)
(yes)
(yes)
SS no yM-SS no yes*
S S no yes*
- ~
no yes*
~*
no yes*
S S
~*
no yes*
yes 6 Environmentally qualified Containment Air yes Temperature RTD's are being installed during yes the 1992 Refueling outage. NRC SER dated yes 12/4/90 found the range deviation to be yes acceptable. *recorded at ILRTpanel yes
- lE supply from MCC 1D (B train)
Containment Sump 74 D
Temperature 5P oF 2SP oF n.a.
TE490 A/B (Sump A) 2 0 oF - 360 oF TE491 A/B(%3'above 2
0 F-360oF basement floor) yes n o partial rel.
n o yes yes SR lA/1C no yes yes SR 1A/1C no no no no yes TE490A/B and TERIA/Bare dual element yes RTD's. The 'A'lements are powered from bus 1A and the 'B'lements are powered from bus 1C. Each element is available on the PPCS as a separate point.
Reactor Mater 75 D
Makeup Flow (CVCS) 2 0 - 110 % design yes no partial rel.
no no n.a.
FT-111 2
5-75 gpm (0'- 100%)
mild no SS 1D no FR-110 no NRC SER dated 12/4/90 found the instrument mnge acceptable.
¹ TYPE VARIABLE Attachment 2
Table 1, revision 1
Comparison of Ginna Post Accident Instrumentatlon to Regulatory Guide 1.91, Revision 3 Criteria C.R.
RECORDER CAT.
RANGE EEQ SEISMIC QA P-S
~
IND.
CHART COMP COMMENTS Page 16 of 20 ~,
76 D
Letdown Flow (CVCS) 2 0 - 110 lo design yes no partial rel.
no no n.a.
FT-134 2
0 - 100gpm (0 - 167 %)
mild no SS 1D FI-134 no F0134 Volume Control Tank 77 D
Level 2
top to bottom y es n o partial rel.
n o no n.a.
LT-112 2
0- 100%
mild no SS 1B LI-112 no L0112 CGA Temperature to 78 D
ESF System 4P oF 2PP oF n.a.
TE421 (Component 2
O'F - 225'F Cooling Water heat exchanger temperature) yes n o partial rel ~
n o mild no SS 1B TI421 no no T0621 NRC SER dated 12/4/90 found the instrumentation provided to be acceptable.
System 2
0 - 110%
design yes no partial rel.
no no n.a.
FT-619 (Component 2
0- 7000 gpm Cooling Water System flow)
Hi Level Radioactive 80 D
Liquid Tank Level 3
top to bottom mild no SS 1C no no no comm.
n.p.
no no F0619 The CCW System is prealigned with flows to various ESF components manually adjusted using local flow indicating switches. RG 1.97 states that the purpose ofthis variable is to monitor operation. The instrumentation provided meets this intent.
no D
LT-1001 (Waste Drain Tank)
LT-1003 (Reactor Coolant Drain Tank) 3
~0-100%
3 0- 100%
no no SS no no no SS no no no Indication ofboth tank levels are available at the radwaste panel, and remotely at a terminal no L1003 in the Technical Support Center.
~ Normally fed fmm 480 Vbus 14 (Train A) with a manual backup to 480 V bus 16 (Train B)
¹ TYPE VARIABLE Attachment 2
Table 1, revision 1
Comparison of Ginna Post Accident Iustrumentatlon to Regulatory Guide 1.97, Revision 3 Criteria C.R.
RECORDER CAT.
RANGE EEQ SEISiMIC QA P.S.
IND.
CHART COMP COMME'S Page 17 of 20;~,
81 D
Radioactive Gas Holdup Tank Pressure 3
0 - 1SO lo design no no comm.
n.p.
no uo n.a.
Ff-1036 (Tank 1)
Ff-1037 (Tank 2)
Fl'-1038 (Tank 3)
PT-1039 (Tank 4) 3 0 - 150psig (0 - 100%)
no no S S 3
0 - 150psig (0 - 100%)
no no S S 3
0- 150psig (0- 100%)
no no SS 3
0- 150psig (0- 100%)
no no SS no no no no no no no no no Design ofeach tank, and its safety valve no setpoint is 150 psig. Normal radgas pump no operating pressure is <100 psig. NRC SER no dated 12/4/90 found this range deviation acceptable. *NormaHy fed from 480 V bus 14 with a manual backup to 480 V bus 16.
82 D
Emerg.Ventilatiou Damper Position 2
open / closed y es n o partial rel.
uo uo D
ZT-7970 (mini-purge) 3 open/closed ZT-7971 (mini-purge) 3 open/closed ZT-7445 (mini-purge) 3 open/closed ZT-7478 (mini-purge) 3 open/closed no yes no
. yes no yes no yes SS SS SS SS ADC yes ADCi yes ADC yes ADC 'es no no no -
no no no no no Mini-purge valves are locked closed and only openned for containment pressure control.
These valves are in their safety related position prior to any adverse conditions and do not change position throughout any accident.
'Iherefore EQ is not deemed necessary.
83 D
Stdby power / Energy Imp. to Safety Status 2
Plant Specific yes
- no partial rel.
uo no D
EDG A, B: V, kW, A 3
0-500V,0-3000A,0-2MW 125VDC A, B: V, A 3
0-150 V,0-50 A PT-2023 (instrument Air) 3 0 - 160 prig FT455 (PORV, SI Acc) 2 0- 1000 psig PT-456 (PORV, SI Acc) 2 0 - 1000 psig mild no mild no mild
- no mild no mild no SS SS NS SS SS n.a.
yes n.a.
yes PI-2023 1B PITS 1A F1456 no yes no yes no no no no no no Contalumeat High Radiation Monitor 1
1
- 1E7 R/hr yes yes full 1E yes Plant Specific R29 R30 1
1 R/hr - 1E7 R/hr 1
1 R/hr - 1E7 R/hr yes yes SR 1A RM-29 yes R29 yes yes SR 1C RM-30 yes R30 85 E
Rad. Exposure Rate-Access rqd. areas based monitors located, and qualified to sahsfy NUREG4654 3
1F 1 - 1FA,R/hr 3
0.1 - 1E7 mR/hr no 'o comm.
n.p.
no no no no SS various yes yes "
yes
TYPE VARIABLE Attachment 2
Table 1, revision 1
Comparison of Ginna Post Accident Instrumentation to Regulatory Guide 1.97, Revision 3 Criteria C.R.
RECORDER CAT.
RANGE EEQ SEISMIC QA P.S.
IND.
CHART COMP COMMENTS Page 18 of 20 ~,
Airborne Rad Release 86 E
Noble Gas and Flow 2
lE 1E5 ttCVcc yes no partial rel.
no no
- see item N47 RG&E Type C variable Airborne Rad Release.
87 E
Part.
and Halogens 3
- 1E2 itCI/cc no no comm.
n.p.
no no E
R-12A (Cont. Vent) 3 1E-5-10)tCi/cc halogens, 1E-6-1)tCi/cc R-14 A (Plant Exh. Vent) 3 particulate 5E-5-50@ Ci/cc
- halogens, 2.5E-5-25)tCi/cc part.
no no no SR no SR yes R12A
- SPING Radiation monitors are powered from a dedicated supply from MCC D (Safety yes R14A Related).
Airborne Radio. and 88 E
Part. (portable samp.)
3 1E-9
- 1E-3 pCi/cc no no comm.
n.p.
no E
Various fixedand portable 3
1E-12-1E-3 itCi/cc no no SS n.a.
no samplers (Aliquotor diluted sample) no no no Plant and Environ.
89 E
Radiation (portable) 3 1E 1E4 R(rad)/hr no no comm.
n.p.
no no beta radiations and photons E
Various portable instrumentation 3
lEA-1E3 R/hr gamma no no SS n.a.
no 1E 1E3 R/hr beta no no Plant and Environ.
90 E
Radioactivity - (port.)
3 isotopic analysis no n o comm.
n.p.
no E
Multichannel Gamma 3
IE4= 10 jiCi no no SS'a.
no Ray Spectrometer no no no
TYPE VARIABLE CAT.
RANGE Attachment 2
Table 1, revision 1
Comparison of Glnna Post Accident Instrumentation to Regulatory Guide 1.97, Revision 3 Criteria C.R.
RECORDER EEQ SEISMIC QA P.S; IND:
CHART COMP COMMENTS Page 19 of20' 91 E
>Vind Direction 3
0 - 360O E
wind direction (met tower) 3 0-360'o no comm.
n.p.
no no no no S S
~
no RK-32 WD033 *the weather tower currently receives power WD150 directly via an offsite supply.
WD250 92 E
YVind Speed 3
0-50 mph n o
~ n o comm.
n.p.
n o no E
wind speed at 33, 150, 3
0- 100 mph 250 ftelevations (met tower) no no SS no RK-32 WS033 *the weather tower currently receives power
, WS150 directly via an offsite supply.
WS250 Estimation of 93 E
Atmospheric Stab.
3 based on vert. AT n o n o comm.
n.p.
n o n o E
RTD's at 33, 150,250 ft 3
4-20'F between each no I no SS elevations (met tower) elevation yes**
no WDT1 *the weather tower currently receives power WDT2 directly via an offsite supply.
- Temperatures at each elevation are displayed in the control room.
Accident Sampling:
94 E
various no no comm.
n.p.
no no gross activity, gamma
E gross activity (grab samp) 3 gamma spectrum 3
boron content 3
chloride content 3
dissolved hydmgen 3
dissolved oxygen, pH 3P 1-1E6ltCi/cc (dilution) mutichannel analyser 50 - 6000 ppm 5ppb-100ppm 10- 2000 cc/Kg 0.1-20ppm, 1-13 pH no no no no no no no no no no nopo nopo SS SS SS SS SS,SS no no no no no no, no no no no no no no, no no no no no no no, no
- The PASS panel is powered from 480 Vbus 13 (non SR) via panel SB14. NRC review of the PASS capability was documented under NUREG-0737 Item KB.3 (SER dated 4/14/84). NRC SER dated 12/4/90 concludes that the minor range deviations are acceptable.
Accident Sampling:
95 E
Containment Air 3
various no no comm.
n.p.
no no Hydrogen
- content, oxygen
- content, gamnla spectrum E
Hydrogen content Oxygen content Gamma Spectnun 3
no no no Hydrogen concentration is also available using 3
no no no the installed Type AHydrogen Monitors, see 3
multichannel analysis no no SS na.
no no no item N5.
Page 20 of 20 Table 1, revision 1 1.97, Revision 3 Criteria Notes Radioactivit Con~tration or Radiation Level in Circulatin Pr'oolant (Isotopic Analysis)
The original design basis for implementation of NUREG-0737 Topic II.B.3, involves sampling requirements to perform a radiological analysis within a three hour time period for "certain radionuclides in the reactor coolant...".
The NUREG-0737 Clarification, dated October 31, 1980, (2)(d),
states uAlternatively, have inline monitoring capabilities to perform all or part of the above analysis".
Ginna's response involved the selection of semi-automated manual dilution techniques involving.sample withdrawl and preparation of the sample aliquot by the Post-Accident Sampling System@ not a inline monitoring capability.
The remote-manual sampling and dilution capabilities of the existing installed equipment are equivalent to Category 3, Type C attributes.
The Ginna Post-Accident Sampling System (PASS) is equipped with remote~ual abilities to acquire a Reactor Coolant System (RCS) sample, then manipulate the sample by diluting it approximately 1000:1.
The dilutant may then be manually delivered to either of two diverse counting facilities at Ginna Station for multichannel spectrometer isotopic analyses.
The PASS panel is utilized by Health Physics technicians at least once per week to produce routine proceduralized analyses when the unit is on-line.
Regulatory Guide 1.97 guidance for radiation concentration determinations states that Category 1, Type C attributes apply to this measurement variable with the purpose stated to be detection of breach (Fuel Cladding Topic).
Fuel cladding breach detection is not within the Ginna licensing basis but is acknowledged to be a concern during Functional Restoration activities.
Functional restoration activity is beyond the Ginna licensing basis.
No EOP activity involved with design basis DBA occurrences requires that the radiation concentration determination in RCS be performed, and there's no consequent operator action requirement.