ML20238A721
| ML20238A721 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 08/20/1987 |
| From: | ABB IMPELL CORP. (FORMERLY IMPELL CORP.) |
| To: | |
| Shared Package | |
| ML20238A695 | List: |
| References | |
| RTR-REGGD-01.097, RTR-REGGD-1.097 09-0590-82-R00-S01, 09-0590-82-S01, 9-590-82-R-S1, 9-590-82-S1, NUDOCS 8708310184 | |
| Download: ML20238A721 (49) | |
Text
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i SUPPLEMENT.1 TO REPORT NO. 09-0590-82 REV. O RESPONSE TO THE NRC ZION R.G. 1.97 TECHNICAL EVALUATION REPORT i
1 l
Prepared for:
COMMONWEALTH EDIS0N COMPANY
=
l Prepared by:
Impell Corporation 300 Tri State International Suite 400 Lincolnshire, IL ' 60015 Revised August 20, 1987 B708310184 B70824 ADOCK0500g5 DR L:_-_-__-_-_____-__---_____-____
SUPPLEMENT 1 TO l
REPORT NO. 09-0590-82 REV O j
RESPONSE TO THE NRC ZION R.G. 1.97 TECHNICAL EVALUATION REPORT INTRODUCTION On August 1, 1986, Commonwealth Edison Company (CECO) submitted detailed descriptions of conformance to Regulatory Guide 1.97, Revision 2 to the Nuclear ~ Regulatory Commission (NRC).
This submittal was reviewed by the NRC with technical assistance from the Idaho National Engineering Laboratory (INEL). The results of this review were documented in a Technical Evaluation Report (TER) transmitted to CECO May 15, 1987 under Docket Numbers 50-295 and 50-304.
This supplement was prepared'in response to the TER and contains clarifications and additional information for the exception. items contained in the TER. Attached is a revised Parameter Summary Table (Table 1) incorporating the clarifications and additional information requested by the NRC in the TER.
DISCUSSION In order to clarify each response, the TER exception item being addressed is stated in full.
Each TER exception item is followed by CECO's response.
The responses specifically address' each of the NRC concerns stated and where applicable, the response provides additional information to clarify the i
response positions.
Also included is a reference variable number to facilitate cross referencing to the Parameter Summary Table (Table 1).
1
REPORT NO. 09-0590-82, REV. O SUPPLEMENT 1 DATE: August 7, 1987 REVISED: August 20, 1987 TER EXCEPTION ITEM:
3.3.1 Neutron Flux (Variable No. 16)
Regulatory Guide 1.97 recommends Category 1 instrumentation to monitor this variable.
The licensee has provided instrumentation that does not meet Category 1 requirements for environmental and seismic qualification.
The licensee states that they have reclassified this Instrumentation to Category 3 since the primary indication of reactivity and control and reactor shutdown is provided by the control rod position (short term) and the post accident sampling system for boron concentration (long term).
The measurement of neutron flux is the key variable, defined in Regulatory Guide 1.97, for detecting an uncontrolled approach to criticality and for determination that an accident has been successfully mitigated.
Control rod position and RCS soluble boron concentration are the backup variables (Category 3) as defined in Regulatory Guide 1.97.
Because of this, the licensee's justification is not acceptable.
The licensee should therefore provide instrumentation for this variable that is environmentally qualified in accordance with the provisions of 10CFR50.49 and Regulatory Guide 1.97.
Regulatery Guide 1.97 recommends seismic qualification for all l
I Category 1 instrumentation.
The licensee's justification is not acceptable.
The licensee should provide the recommended seismic qualification for this variable in accordance with the plant's seismic design criteria.
CECO RESPONSE:
Measurement of neutron flux is a key variable in a very limited sense since the reactor trip system is designed to activate automatically at the onset of a serious accident or whenever key process variables vary outside a small percentage of nominal operating conditions.
The automatic action is specifically designed to release the reactor I
control rods and reduce neutron flux to essentially zero in less than a j
few hundred seconds.
This reactor trip function occurs at the onset of severe accident symptoms before harsh environmental conditions would be established inside containment.
Consequently, the neutron flux source range monitors (NE-31, NE-32) and the neutron flux intermediate range detectors (NE-35, NE-36) have a high probability of functioning for the short-term following an accident to provide the operator indication of neutron flux.
If neutron source and/or intermediate range detectors were assumed to fail prior to a verification of reactor shutdown conditions, the reactor operator would verify reactor trip by alternate indications.
2 1
1
REPORT NO. 09-0590-82, REV. O SUPPLEMENT 1 DATE: August 7, 1987 REVISED: August 20, 1987 If alternate indications such as the Rod Position Indication System and rod bottom lights on the Main Control Board Panel do not verify control rod insertion, the operator is required to initiate emergency boration of the reactor coolant system.
The reactor trip beakers in the auxiliary relay rack in the Auxiliary Building Electrical Equipment room can also be visually checked to verify reacter trip and could be racked out-of-service at cold shutdown conditions to prevent re-energization of the rod control system motor-generator drives.
Long-term shutdown conditions and detection of a return-to-criticality are monitored using the RCS sampling system to check boron i
concentration in the primary system in the event the source and/or i
intermediate range detectors are unavailable.
This system was recently modified to ensure reliable post-accident sampling capability. With frequent RCS sampling, the operator can ensure that adequate levels of boron remain in~ solution to maintain the reactor in a shutdown condition.
Commonwealth Edison is providing this supplemental information as added justification for reclassifying neutron flux as a Category 3 parameter per Regulatory Guide 1.97, Revision 2' requirements.
This deviation is consistent with the discussion of alternative instrumentation contained g in Generic Letter 86-10 for Appendix R Alternate / Dedicated Shutdown Systems process monitoring., Paragraph I of Generic Letter 86-10 uses boron concentration indication as an example of alternative l
instrumentation which may be proposed to verify shutdown reactivity
/
l conditions.
Therefore, installing Category I neutron flux monitoring instrumentation does not appear warranted or prudent.
TER EXCEPTION ITEM:
3.3.3 Core Exit Temperature (Variable No. 22)
The licensee has identified this variable as Type A which requires Category 1 Instrumentation.
The licensee hn not provided Category 1 I
instrumentation stating that further modification is required since only part of the system is environmentally qualified and safety-related.
The NRC is reviewing the acceptability of this variable as part of their review of NUREG-0737, Item II.F.2.
CECO RESPONSE:
Upgrade modifications to the instrumentation provided for this variable are currently in progress. As stated in the NRC Letter and Safety Evaluation Report (SER) dated August 18, 1986, the design for these modifications was reviewed and accepted as part of NUREG-0737 Item II.F.2.
An Implementation Letter to close out the modifications l
performed per NUREG-0737, Item II.F.2 will be transmitted when installation and testing of the required modifications is complete, i
3
REPORT NO. 09-0590-82, REV. O SUPPLEMENT 1 DATE: August 7, 1987 REVISED: August 20, 1987 1
I TER EXCEPTION ITEM:
3.3.4 Dearees of Subcoolina (Variable No. 24) l Regulatory Guide 1.97 recommends environmentally qualified.
instrumentation for this variable.
The licensee states that further modification is needed for this instrumentation.since only part of the system is environmentally qualified and safety-related.
The NRC is reviewing the acceptability of this variable as part of l
i their review of NUREG-0737, Item II.F.2.
CECO RESPONSE:
Upgrade modifications to the instrumentation provided for this variable are currently in progress. As stated in the NRC Letter and Safety Evaluation Report (SER) dated August 18, 1986, the design for these modifications was reviewed and accepted as part of NUREG-0737 Item l
II.F.2.
An Implementation Letter to close out the modifications performed per NUREG-0737, Item II.F.2 will be transmitted when t
installation and testing of the required modifications is complete.
TER EXCEPTION ITEM:
3.3.5 Containment Isolation Valve Position (Variable No. 29)
Regulatory Guide 1.97 recommends Category 1 valve position indication for the purpose of verifying the accomplishment of isolation.
The l
licensee has provided a list of containment isolation valves and I
justification for exceptions (note 26) from the regulatory guide l
recommendations.
Based on the information provided, we are unable to determine that the recommendations for (a) redundancy, (b) single-failure criterion and (c) environmental qualification have been met.
i The licensee has listed a group of valves that do not have position a.
indication for series pairs.
The licensee states that backup indication is provided by various plant system variables.
The licensee should provide additional information for the valves listed i.e., why is there no indication of individual valves of the series pair? Why is a plant system variable adequate to determine the proper valve position?
b.
The licensee states that all air operated and solenoid operated valves fall in the safe direction (closed) on loss of power, thus, position status for these valves need only meet Category 3 criteria.
i g Mao 4
REPORT NO. 09-0590-82, REV. O SUPPLEMENT 1 DATE: August 7, 1987 REVISED: August 20, 1987 The fact that these valves are supposed to fail shut is not sufficient justification for not meeting the single failure criterion.
In an accident situation, the operator should be able to ascertain that the valves are in fact shut from the position indication.
The licensee should meet this single failure criterion.
He are unable to determine from the licensee's submittal which c.
valve position switches are located in a mild environment and which ones are not.
The licensee should provide information that verifies that all valve position switches requiring environmental qualification do in fact have the proper switch.
CECO RESP 0kSE:
Zion Station Technical Specification Amendment numbers 95 and 105 effective June 23, 1987 revised the list of Containment Isolation Valves. Approximately 84 valves were added to the list.
These additional valves are being evaluated for compliance to Regulatory Guide 1.97 recommendations.
The response to TER Exception Item 3.3.5 will be submitted pending completion of the evaluation of the additional valves.
This response I
will specifically address:
a) Redundancy, b) Single-failure criterion, I
and c) Environmental issues identified in the TER for the new as well as previously evaluated valves.
1 TER EXCEPTION ITEM:
3.3.7 Containment Effluent Radioactivity - Noble Gases (from Identtfl.d i
Release Points. Variable No. 43)
Regulatory Gylde 1.97 recommends Category 2 instrumentation with a l
range of 10-0 to 10-2 pCi/cc for this variable.
The licensee indicates that an instryment is installed to monitor this variable and has a range of 10 to 100 cpm.
The licensee states that this effluent path is not required for post-accident service and therefore, meeting the regulatory guide recommendations for this variable is not applicable.
This is insufficient justification for this deviation.
The licensee should provide an explanation as to why this flow path is not required post-accident and show the correlation between cpm and pCi/cc so a determination can be made that the provided range meets the Regulatory l
Guide 1.97 recommendation.
\\
l l
l 5
REPORT NO. 09-0590-82, REV. O SUPPLEMENT 1 DATE:
August 7, 1987 REVISED: August 20, 1987 CECO RESPONSE:
Regulatory Guide 1.97 does not require effluent monitoring for this flow path if effluent flow discharges through a common plant vent.
Since Zion Station utilizes a common plant vent (main vent stack) for containment and auxiliary building effluents, radioactive noble gas effluent monitoring is not addressed here. All post-accident effluent monitoring instrumentation as well as instrument ranges in pCi/cc are addressed in the response to TER Exception Item 3.3.26.
TER EXCEPTION ITEM:
3.3.8 Effluent Radioactivity-Noble Gases (from buildings-. Variable Nod)
RegulatoryGuide1.g7recommendsCategory2instrumentationwitha range of 10-6 to 10 pCi/cc for this variable. The licensee indicates that an instrument is installed to monitor this variable and has a range of 10 to 106 cpm.
The licensee states that this effluent path is not required for post-accident service and therefore, meeting the regulatory guide recommendations for this variable is not applicable.
This is insufficient justification for this deviation.
The licensee should provide an explanation as to why this ficw path is not required post-accident and show the correlation between cpm and pCi/cc so a determination can be made that the provided range meets the Regulatory Guide 1.97 recommendation.
CEC 0 RESPONSE:
Regulatory Guide 1.97 does not require effluent monitoring for this i
flow path if effluent flow discharges through a common plant vent.
Since Zion Station utilizes a common plant vent (main vent stack) for containment and auxiliary building effluents, radioactive noble gas effluent monitoring is not addressed here. All post-accident effluent monitoring instrumentation as well as instrument ranges in pCi/cc are addressed in the response to TER Exception Item 3.3.26.
TER EXCEPTION ITEM:
3.3.9 Residual Heat Removal (RHR) Flow (Variable No. 46)
Regulatory Guide 1.97 recommends environmentally qualified instrumentation with a range of 0 to 110 percent of design flow for this variable.
The licensee states that the sensors are located in a mild environment and the range is 0 to 59.5 inches of water and 0 to 800 inches of water.
t l
6
REPORT NO. 09-0590-82, REV. O SUPPLEMENT 1 DATE: August 7, 1987-l REVISED: August 20, 1987 Non environmentally qualified instrumentation is acceptable since the i
instrumentation is located in a mild environment. However, we are unable to determine, from the information provided, that the recommended range has been provided. The licensee should provide the i
information that shows that 0 to 110 percent of the design flow is monitored.
CECO RESPONSE:
Calibration and scaling for the RHR flow transmitters and flow indicators is as follows:
FT/FI No.
Transmitter Cal. Ranae Indicator Rance
-970A 0 - 59.5" H O O - 1500 GPM 2
-971A 0 - 59.5" H O O - 1500 GPM 2
-9708 0 - 300" H 0 0 - 3300 GPM 2
-971B 0 - 300" H O O - 3300 GPM 2
Flow instruments FT/FI-970A and -971A are narrow range instruments used i
to more accurately determine RHR flow rates during low flow conditions.
Flow instruments FT/FI-970B and 09718 are wide range instruments capable of indicating a maximum of 3300 GPM. Since the design flow rate through each RHR train is 3000 GPM, the existing instrumentation meets the 0 to 1101. design range specified by Regulatory Guide 1.97, Revision 2.
TER EXCEPTION ITEM:
3.3.11 Accumulator Tank Level and Pressure (Variable No. 48)
Regulatory Guide 1.97 recommends environmentally qualified instrumentation for this variable with a range of 10 to 90 percent volume (for level) and 0 to 750 psig (pressure).
The licensee has supplied instrumentation with no environmental qualification.. The provided ranges are approximately 20 to 95 percent of the tank volume and 0 to 700 psig.
The licensee states that the primary function of both level and pressure instrumentation is to monitor the pre-accident status of the accumulator tanks to assure that this passive safety system is prepared I
to serve its safety function.
The accumulators are passive devices. Their discharge into.the reactor coolant system (RCS) is actuated solely by a decrease.in RCS pressure.
He find that the ranges of the instrumentation supplied for this variable are adequate to determine that the accumulators have discharged.
Therefore, the ranges of this instrumentation are acceptable for this variable.
7
REPORT NO. 09-0590-82. REV. O SUPPLEMENT 1 DATE: August 7, 1987 REVISED: August 20, 1987 The existing non-qualified instrumentation is not acceptable. An environmentally qualified instrument is necessary to monitor the status of.these tanks.
The licensee should designate either level or pressure as the key variable to directly indicate accumulator discharge and provide instrumentation for that variable that meets the requirenients of 10CFR50.49 and Regulatory Guide 1.97.
CECO RESPONSE:
The response to TER Exception Item 3.3.11 will be submitted pending completion of an engineering evaluation of the feasibility and cost'of A
upgrading the existing accumulator tank instrumentation.
If upgrade
/_L\\
modifications are required, either level or pressure will be designated the key variable and modified to meet the applicable Regulatory Guide 1.97 recommendations.
The schedule for implementing any required modifications will be developed pending resolution of all Regulatory Guide 1.97 issues.
TER EXCEPTION ITEM:
3.3.13 Boric Acid Charoina Flow (Variable No. 50)
The licensee has not provided the information required by Section 6.2 of Supplement No. 1 of NUREG-0737.
The information provided pertains to the boric acid transfer pump flow.
The licensee should provide the required information, identify any deviation from Regulatory Guide 1.97 and provide supporting justification or alternatives for those deviations.
CECO RESPONSE:
Boric Acid Charging Flow to the Baron Injection Tank is monitored by FT/FI-934 from 0 to 1000 GPM.
This charging flow is accomplished via the centrifugal charging pumps.
The combined' design flow of both centrifugal charging pumps is 300 GPM (150 GPM per pump). Charging pump flow increases as RCS pressure decreases.
The maximum combined flow rate of both charging pumps is approximately 800 GPM (400 GPM per pump) at 1600 psi when safety injection pump flow is initiated.
Therefore, the existing 0 to 1000 GPM instrument range is adequate to monitor boric acid charging flow.
This flow instrumentation is classified non safety-related since boric acid charging flow is automatically accomplished upon safety injection system actuation.
In addition, this instrumentation does not provide signals for manual or automatic initiation or control of any other safety systems.
Since this instrumentation is designated non safety-related, seismic qualification is not required. Also, the FT/FI-934 instrumentation system is located in a mild environment and therefore environmental qualification is not required.
8
REPORT NO. 09-0590-82, REV. O SUPPLEMENT I DATE: August 7, 1987 REVISED: August 20, 1987 TER EXCEPTION ITEM:
3.3.14 Flow in Hiah Pressure Iniection (HPI) System (Variable No. 51)
Regulatory Guide 1.97 recommends Category 2 instrumentation with a range of 0 to 110 percent'of design flow for this variable.
The licensee has instrumentation that is not environmentally qualified and has a range of 0 - 3200 inches of water and 0 - 25 psi.
The licensee states that environmental qualification is not necessary since the instrumentation is located in a mild environment. The licensee further states that this instrumentation is not safety-related and is adequate for the intended use.
He find the licensee's justification unacceptable.
The licensee should provide information on the following.
i 1.
Hhat basis is used to consider the HPI system to be non-safety-related?
2.
Is the entire flow instrumentation system located in a mild environment?
3.
What is the correlation between design flow, inches of water and.
psi?
i 4.
Is 0 to 110 percent of design flow being monitored with the I
existing range?
CECO RESPONSE:
1 1.
The Safety Injection (HPI) system is considered safety-related; i
however, since the safety function for this system can be accomplished with or without the flow instrumentation, this HPI system flow instrumentation is designat63 non safety-related.
Also, this instrumentation does not provide signals for manual or automatic initiation or control of any other safety systems.
2.
With the possible exception of the cabling all (non-mechanical) instrumentation system components are located in mild environments. The cabling used in the system is fully environmentally qualified and therefore, meets Regulatory Guide 1.97 criteria if portions of the cable are routed through harsh environments.
3.
Safety Injection (HPI) flow is accomplished via the safety injection pumps.
The flow instrumentation provided for monitoring HPI flow is calibrated / scaled as follows:
9 d
REPORT NO. 09-0590-82, REV. 0 SUPPLEMENT 1 DATE: August 7, 1987 REVISED: August 20, 1987
{
FT/FI No.
Transmitter Cal. Ranae Indicator Ranoe I
-922 (A SI Pump) 0 - 600" H O O - 800 GPM 2
-932 (B SI Pump) 0 - 600" H O O - 800 GPM 2
4.
Since the design flow rate for each Safety Injection Pump is 400 GPM and the existing range is 0-800 GPM, this instrumentation exceeds the 0-110% of design flow specified by Regulatory Guide 1.97, Revision 2.
1 TER EXCEPTION ITEM:
3.3.15 Flow in Low Pressure In_iection (LPI) System (Variable No. 52)
I Regulatory Guide 1.97 recommends Category 2 instrumentation with a range of 0 to 110 percent of design flow for this variable. The licensee has instrumentation that is not environmentally qualified and has a range of 0-59.5 inches of water and 0-800 inches of water.
The licensee states that environmental qualification is not necessary since i
the instrumentation is located in a mild environment.
The licensee further states that this instrumentation is not safety-related and is adequate for the intended use, i
He find the licensee's justification unacceptable.
The licensee should provide information on the following.
4 1.
What basis is used to consider the LPI system to be non safety-related?
2, Is the entire flow instrumentation system located in a mild environment?
3.
What is the correlation between design flow and inches of water?
4.
Is 0 to 110 percent of design flow being monitored with the existing range?
i CECO RESPONSE:
1.
The Residual Heat Removal system (LPI) is_ considered safety-related, however since the system's safety function can be accomplished with or without flow instrumentation, the LPI system instrumentation'is designated non safety-related. Alco, this instrumentation does not provide signals for manual or automatic initiation or control of any other safety systems.
2.
Hith the possible exception of the cabling all (non-mechanical) instrumentation system components are located in mild environments.
The cabling used in the system is fully environmentally qualified and therefore, meets Regulatory Guide 1.97 criteria if portions of the cable are routed through harsh environments.
10
REPORT NO. 09-0590-82, REV. O SUPPLEMENT 1 DATE: August 7, 1987 REVISED: August 20, 1987 3.
Low Pressure Injection (RHR) is accomplished via the RHR pumps.
j Calibration and scaling correlations for monitoring LPI flow are as follows:
FT/FI No.
Transmitter Cal. Ranae Indicator Ranae
-970A 0 - 59.5" H O O - 1500 GPM 2
-971A 0 - 59.5" H O O - 1500 GPM 2
-970B 0 - 300" HO 0 - 3300 GPM 2
-9718 0 - 300" HO 0 - 3300 GPM 2
4.
As stated in the response to TER Item 3.3.9 the design flow rate of i
each RHR pump is 3000 GPM and therefore the existing instrument range of 0-3300 GPM neets the 0-110% of design flow specified by Regulatory Guide 1.97.
l TER EXCEPTION ITEM:
i 3.3.16 Refuelina Water Storace Tank Level (Variable No. 53) l Regulatory Guide 1.97 recommends environmentally qualified
)
i instrumentation for this variable. The licensee has instrumentation that is not environmentally qualified and states that a modification is i
required.
1 The licensee should commit to upgrading this instrumentation in l
accordtnce with the Environmental Qualification Rule,10CFR50.49 and Regulatory Guide 1.97.
CECO RESPONSE:
As stated in the Regulatory Guide 1.97 submittal, modification (s) will be performed to upgrade the existing Refueling Hater Storage Tank level instrumentation to provide environmentally qualified instrumentation.
4 These modifications will be scheduled pending final resolution of all Regulatory Guide 1.97 issues and an evaluation of specific i
environmental qualification requirements.
l TER EXCEPTION ITEM:
3.3.17 Primary System Safetv-Relief Valve Position (Variable No. 55) i Regulatory Guide 1.97 recommends Category 2 instrumentation for this variable.
The licensee has provided Category 3 instrumentation for the safety relief valve position indication.
The licensee states that I
existing instrumentation is adequate since the relief valves are l
totally enclosed and self actuated at 2500 psia.
In addition a backup indication of valve position is provided by thermowell temperature indications in each downstream discharge line which includes a nigh temperature alarm, l
)
11
. REPORT NO. 09-0590-82, REV. O SUPPLEMENT 1 DATE: August 7, 1987 REVISED: August 20, 1987 t
He find the licensee's justification unacceptable. Besides the recommendation of Regulatory Guide 1.97 for Category 2 instrumentation, Item II.D.3 of NUREG-0737 also addresses this variable.
Three clar1fications from the position of NUREG-0737 are (a) if the position indication is not safety grade, a reliable single channel of direct indication powered from a vital instrument bus may be provided if backup methods of determining valve position are available and are discussed in the emergency procedures, (b) the valve position indication should be seismically qualified consistent with the component of the system to which.it is attached and (c) the position indication should be qualified for its appropriate environment (any transient or accident which could cause the relief or safety valve to lift).
As a minimum the criteria of Regulatory Guide 1.97 for Category 2 instrumentation should be complied with.
CECO RESPONSE:
The Zion Station Reactor Coolant system is protected by five safety relief valves.
Two of the valves are Power Operated Relief Valves (PORV's) and three are Code Safety Relief Valves.
The PORV's position is directly indicated in the control room using limit r, witches and indicating lights.
These limit switches are safety-related and were b
recently upgraded (Modification No. M22-1/2-82-78) to fully qualified switches and therefore, meet all Regulatory Guide 1.97 Revision 2 recommendations.
Indication that the Code Safety Relief Valves have lifted is provided through temperature elements in each line, downstream of each safety valve.
Each temperature element has control room annunciation to alert the operator to leakage past the valve.
The use of a secondary variable to detect valve position is consistent with the requirements of Regulatory Guide 1.97.
Temperature was selected as the variable because through the use of temperature indication it is possible to measure both large and small flows past the valves.
A second method used to determine if a Safety Relief Valve is lifting is the Babcock & Hilcox Company Valve Monitoring System (VMS).
It is an acoustic-based system which monitors the valve and informs the operator whether the valve is open or closed.
The VMS utilizes accelerometers mounted on the valve to detect the noise caused by flow through the valve.
This noise signal is conditioned and applied to an alarm monitor, indicator, and audio monitor.
The system can distinguish between normal background noise (as when the valve is closed) and the much higher level when the valve is open.
12 l
REPORT NO. 09-0590-82, REV. O SUPPLEMENT 1 DATE: August 7, 1987 REVISED: August 20,'1987 l
'I l
Each instrument used to determine valve position has additional backup
/f\\
instrumentation listed below.
Valve Indication Backun Indication PCV-455C Limit Switch TE-463 PCV-456 Limit Switch TE-463 RC-8010A TE-466 Acoustic Monitor RC-8010B TE-465 Acoustic Monitor RC-8010C TE-464 Acoustic Monitor I
l The existing temperature elements (RTDs) used for safety relief valve A
position indication are not safety-related or environmentally W
qualified.
Since they are not safety-related seismic qualification is not required.
These elements will be upgraded to comply with Regulatory Guide 1.97 environmental qualification recommendations.
This upgrade will be scheduled pending final resolution of all Regulatory Guide 1.97 issues and evaluation of specific environmental qualification requirements.
TER EXCEPTION ITEM:
3.3.18 Ouench Tank (Pressurizer Relief Tank) Temperature (Variable No. 59)
Regulatory Guide 1.97 recommends a temperature range of 50 to 750*F-for this variable.
The licensee has provided a range of 50 to 400*F and states that the instruments are adequate for the intended use.
J The licensee has not provided adequate justification for this deviation. The licensee should show that the temperature ir.dication will remain on scale, including the maximum saturation temperature, during any accident that lifts the pressurizer relief valves.
CECO RESPONSE:
The Pressurizer Relief Tank is equipped with rupture discs' for safety relief.
These rupture discs are set to relieve tank pressure at 100 psig. Since the maximum saturation temperature for steam at 100 psig is 340*F, the existing instrument range of 50-400*F is adequate to determine the Pressurizer Relief Tank temperature during accident and post-accident conditions.
REPORT NO. 09-0590-82, REV. O SUPPLEhENT 1 DATE: August 7, 1987 REVISED: August 20. 1987 a
TER EXCEPTION ITEM:
J 3.3.19 Safetv/ Relief Valve Position or Main Steam Flow (Variable No. 63)
Regulatory Guide 1.97 recommends closed-not closed indication or steam i
flow indication to monitor this variable.
The licensee indicates that the range is 0 to 300 inches of water.
I This is insufficient information to determine that the range recommendation has been met for this variable.
The licensee should provide the correlation between inches of water and flow.
CECO RESPONSE:
1 The transmitter calibration range is -20 to approximately 400" H O 2
for the Main Steam flow instrumentation and corresponds to O to 4.2 x -
106 lbm/hr steam flow. Since only closed /not closed indication is required for this variable, indication of steam flow (in Lbm/hr) meets the range specified by Regulatory Guide 1.97, Revision 2.
TER EXCEPTION ITEM:
3.3.20 Main Feedwater Flow (Variable No. 64)'
Regulatory Guide 1.97 recommends instrumentation with a range of 0 to 110 percent of design flow to monitor this variable. The licensee indicates that the range monitored is 0 to 600 and 0 to 300 inches of water.
This is insufficient information to determine that the range i
recommendation has been met for this variable.
The licensee should provide the correlation between inches of water and flow.
CEC 0 RESPONSE:
The correlation between transmitter calibration and flow indication for the Main Feedwater flow instrumentation is as follows:
ET/FI No.
Transmitter Cal. Range Indicator Ranae
-510 (& FI-510A) 0 - 330" H 0 0 - 4.2x10 Lbm/hr
-511 0 - 330" H 0 0 - 4.2x10 lbm/hr
-520 (& FI-520A) 0 - 330" H 0 0 - 4.2x10 lbm/hr
-521 0 - 330" H 0 0 - 4.2x10 lbm/hr
-530 (& FI-530A) 0 - 330" H 0 0 - 4.2x10 Lbm/hr
-531 0 - 330" H 0 0 - 4.2x10 Lbm/hr
-540 (& FI-540A) 0 - 330" H 0 0 - 4.2x10 Lbm/hr
-541 0 - 330" H 0 0 - 4.2x10 Lbm/hr 14
REPORT NO. 09-0590-82, REV. O SUPPLEMENT 1 DATE: August 7, 1987 REVISED: August 20, 1987 Since the design flow rate for Main Feedwater flow is 3.5x106 Lbm/hr, the existing instrumentation meets the 0-110% of design flow specified by Regulatory Guide 1.97, Revision 2.
TER EXCEPTION ITEM:
3.3.21 Auxiliary Feedwater Flow (Variable No. 11)
Regulatory Guide 1.97 recommends instrumentation for this variable with a range of 0 to 110 percent of design flow. Since the licensee has designated this instrumentation as Type A, this instrumentation should be Category 1.
The licensee indicates the. range is 200 inches of water and there is no redundant channel to meet the single failure criteria.
i The licensee states that the lack of redundancy is resolved by use of redundant instrument power supplies, redundant auxiliary feedwater pumps and the ability to isolate flow through a damaged steam generator line. The licensee further states that steam generator narrow range level is available as backup indication.
This is insufficient information to determine that the range recommendation has been met for this variable.
The licensee should provide the correlation between inches of water and flow.
He find the redundancy deviation unacceptable for Type A variables.
Neither NUREG-0737, nor Regulatory Guide 1.97 require this instrumentation to be Type A.
The licensee has determined that this instrumentation is Type A.
Therefore, the licensee should provide Category 1 instrument channels for this variable.
i CECO RESPONSE:
In order to manually terminate safety injection the Zion Station Emergency Operating Procedures require the operator to verify:
340 GPM total Auxiliary Feedwater Flow (minimum)
Steam Generator level greater than 4% (narrow-range)
Based on these requirements, auxiliary feedwater flow was designated a l
Type A variable.
j In order to dissipate RCS residual heat, auxiliary feedwater flow is b
required to only two of the four steam generators.
Since auxiliary feedwater flow is monitored to each of the four steam generators, two of the four available instrument channels could fail and the operator will still be provided with the required auxiliary feedwater flow information.
Therefore, the existing instrumentation meets Regulatory Guide 1.97 redundancy criteria.
15
- A
I REPORT NO. 09-0590-82, REV. O SUPPLEMENT 1 j
DATE: August 7, 1987 REVISED: August 20, 1987 The correlation between transmitter calibration and flow indication for the auxiliary feedwater flow instrumentation is as follows:
FT/FI No.
Transmitter Cal. Ranca Indicator Rance
-FH02 0 - 200" H 0 0 - 300 GPM
-FH03 0 - 200" H 0 0 - 300 GPM
-FH04 0 - 200" H 0 0 - 300 GPM
-FH25 0 - 200" H 0 0 - 300 GPM l
Since maximum expected flow under design conditions is 900 GPM (total) and the total flow monitoring capability for auxiliary feedwater is I
1200 GPM the existing instruments exceed the 0 to 110% of design flow range specified by Regulatory Guide 1.97 Revision 2.
l l
TER EXCEPTION ITEM:
1 1
3.3.22 Condensate Storaae Tank Water Level (Variable Nos. 15 and 66) l Regulatory Guide 1.97 recommends Category 1 instrumentation for this
{
variable.
The licensee has instrumentation that is not Category I and l
l states that a modification is required.
1 The licensee should commit to upgrading this instrumentation to meet j
the Category I requirements.
CECO RESPONSE:
1 As previously stated, upgrade modification (s) tc the Condensate Storage Tank level instrumentation will be performed to meet Regulatory Guide l.97 Revision 2 recommendations. These modifications will be scheduled pending final resolution of all Regulatory Guide 1.97 issues and evaluation of specific instrumentation requirements.
TER EXCEPTION ITEM:
3.3.23 Containment Atmosohere Temocrature (Variable No. 69)
Regulatory Guide 1.97 recommends Category 2 instrumentation with a range of 40 to 400*F for this variable.
The licensee has supplied i
Category 3 instrumentation with a range of 0 to 150*F.
The licennee l
states that the containment atmosphere temperature is not a key variable for accident monitoring; that the key variable for monitoring I
containment cooling is containment pressure indication, which is monitored by Category 1 instrumentation; and that the containment atmosphere temperature is a backup variable for reactor building accident menitoring.
16 D
REPORT NO. 09-0590-82, REV. O SUPPLEMENT 1 DATE: August 7, 1987 REVISED: August 20, 1987 He find that the licensee's application of Category 3 backup instrumentation is.in accordance with the Regulatory Guide. However, the licensee should justify the range and show that it will remain on scale for post-accident conditions, or provide the recommended range.
CECO RESPONSE:
As stated in the Zion Station Final Safety Analysis Report, the maximum containment temperature, (short-term peak temperature) is 271*F.
The ranges of existing Containment Atmosphere Temperature instrumentation are as follows:
TE/TI No.
Temperature Rangg RV42 0 - 300*F RV43 0 - 150*F RV44 0 - 150'F As indicated above, TE/TI-RV42 provides an adequate range to determine containment temperature post-accident.
TE/TI-RV43 & 44 provide redundant containment temperature information during normal operation.
TER EXCEPTION ITEM:
3.3 25 Emeraency Ventilation Dameer Position (Variable ho. 78)
Regulatory Guide 1.97 recommends Category 2, open-closed status instrumentation for this variable. The licensee states that the instrumentation provided is not environmentally qualified and that radiation monitors provide indication of damper actuation and position verification.
l l
Based on the information provided we are unable to determine if the recommendations of Regulatory Guide 1.97 have br7n met.
The licensee should submit additional information that will clarify what l
instrumentation exists for this variable and that it is environmentally qualified.
I CECO RESPONSE:
l The control room ventilation system contains the following emergency I
ventilation dampers:
OFCV-PV03A OFCV-PV04A 17
I REPORT NO. 09-0590-82, REV. O StJPPLEMENT 1 DATE: August 7, 1987 REVISED: August 20, 1987 OFCV-PV11A
)
OFCV-PV118 OFCV-PVilC OFCV-PV13A OFCV-PV138 OFCV-PV-39 i
i These ventilation dampers actuate on a high radiation signal from ORIA-PR29 or a safety injection signal to isolate the normal outside air supply and provide the control room HVAC system with makeup air from the turbine building.
The makeup air is circulated through a charcoal filter via one of two charcoal booster fans. Direct indication of damper position is not supplied to the operator, however, damper position can be determined by observing a number of related j
variables.
These variables include:
Charcoal booster fan run status (Indicating light)
Charcoal filter differential pressure (OPDT-PV39)
Control room radiation monitors
{
j Per Item 1.5f of Regulatory Guide 1.97 the use of these indirect variables to determine the damper status is acceptable.
The following j
items supply justification for this position.
i The Zion Emergency Procedure uses the charcoal booster fan run status as the indication that this safety function is operating as expected,(powered from a safety-related bus).
Indication of differential pressure across the filter is available l
to the operator.
Differential pressure is an indication of flow, if flow exists it can be assumed the dampers are correctly i
aligned.
1 The dampers fail in the appropriate safeguards position.
Damper position can be verified locally.
System testing is done on a monthly basis to prove system operability by verifying flow through the makeup air filters.
I The equipment associated with control room ventilation is located in a i
mild environment (Environmental Zone A4), for this reason environmental qualification is not necessary.
18
REPORT NO. 09-0590-82, REV. O SUPPLEMENT 1 DATE: August 7, 1987 i
REVISED: August 20, 1987 1
TER EXCEPTION ITEM:
1 4
3.3.26 Noble Gases and Vent Flow Rate (Variable Nos. 82 - 85) i Regulatory Guide 1.97 recommends instrumentation for this variable with -
ranges monitored in pCi/cc and flow monitored from 0 to 110 percent flow. The licensee provides the existing ranges monitored in counts i
per minute (cpm) and mR/hr and states that no ficw instrumentation exists.
4 Based on the information provided we are unable to determine that the instrumentation provided is adequate.
The licensee should show the correlation between pCi/cc and cpm and mR/hr and commit to the installation of flow instrumentation or further justify how releases can be assessed without it.
CECO RESPONSE:
I The available instrumentation provides noble gas concentrations and i
1 i
vent flows in pCi/cc and CFH respectively.
The information provided i
by this instrumentation is indicated at the plant process computer over l
the ranges stated below.
Zion Station utilizes a common plant vont that includes a containment purge.
Effluent discharges through this path is monitored by l
RIA-PR49.
The methodology for calculating noble gas release rates is contained in Zion Station Procedure EPIP-350-2.
Based on the computer
{
point outputs, the range of this instrumentation system is 1x10-7 4
pCi/cc to 10 pC1/cc (Xe-133) which is consistent with the i
requirements of Regulatory Guide 1.97.
The existing flow i
instrumentation, FT-PRS 3, is capable of measuring flow in the range of 0 to 229,500 CFM.
This flow instrumentation exceeds the Regulatory Guide 1.97 requirement of 0-110% design flow since nominal design flow is 150,000 CFM.
The system also utilizes a sampling panel which is capable of maintaining isokinetic sample flow for variations in stack flow of 25% from the nominal design flow rate.
This exceeds the requirement of 120% as specified in NUREG-0737.
The sampling system is located in the non-safety switchgear room (Zone A-2) which has a calculated total integrated dose rate of 104 rads. Because of this mild environment Environmental Qualification is not required.
TER EXCEPTION ITEH:
3.3.27 Particulate and Haloaens (Variable No. 87)
Regulatory Guide 1.97 recommends instrumentation for this variable with ranges monitored in pCi/cc and flow monitored from 0 to 110 percent flow.
The licensee provides the existing ranges monitored in counts per minute (cpm) and states that no flow instrumentation exists.
i ep h 19
REPORT NO. 09-0590-82, REV. O SUPPLEMENT 1 OATE: August 7, 1987 REVISED: August 20, 1987 1
l Based on the information provided we are unable to determine that the i
instrumentation provided is adequate.
The licensee should show the correlation between pCi/cc and cpm and commit to the installation of I
flow instrumentation or further justify how releases can be assessed without it.
i CECO RESPONSE:
At Zion Station, the same system that is used to measure effluent I
discharges is used to measure the release of particulate and halogens.- Based on Zion Station Procedure EPIP 350-g Rev. O the system j
is capable of measuring releases in the range of 10- pCi/cc to l
2 pCi/cc. This range is dependent upon sample flow rates and 10 sample times.
EPIP 350-3 contains the information necessary to calculate the necessary sample times based on sample flow and source term concentration.
As is the case with effluent sampling, isokinetic sampling for particulate is maintained in the range of 1257. of nominal i
design flow. As indicated in the response to TER Item 3.3.26, total j
stack flow is inonitored from 0 to 229,500 CFM.
i TER EXCEPTION ITEM:
3.3.28 Airborne Radiohaloaens and Particulate (Variable _ No. 89)
Regulatory Guide 1.97 recommends that the instrumentation to monitor l
airborne radiohalogens and particulate have a range of 10-9 to 10-3 pC1/cc. The licensee states that this range is N/A.
1 The licensee has not provided the range as required by Section 6.2 of Supplement No. 1 of NUREG-0737.
the licensee should provide the range
{
of their laboratory instrumentation, identify any deviation from l
Regulatory Guide 1.97 and provide supporting justification for those l
deviations.
CECO RESPONSE:
Zion Station utilizes portable sampling equipment with a range of 10-14 pCi/cc to 103 pCi/cc.
This range is based on the methodology contained in EPIP 350-3 and a 5 mr/hr maximum instrument reading.
Samples are analyzed in the laboratory.
The equipment is manufactured by Nuclear Data.
This instrumentation satisfies the l
requirements of Regulatory Guide 1.97.
l l
TER EXCEPTION ITEM:
3.3.30 Estimation of Atmosoberic Stability The licensee has not provided the information required by Section 6.2 of Supplement No.1 of NUREG-0737.
i l
20
REPORT NO.~09-0590-82. REV. O SUPPLEMENT 1 DATE:' August 7. 1987 REVISED: August 20. 1987 The licensee. should provide the required information, ' identify any t
deviation from Regulatory Guide 1.97 and provide supporting 1
justification or alternatives for those deviations.
CECO RESPONSE:
)
Zion Station's. instrumentation used to measure atmospheric stability is -
capable of measuring vertical temperature differences as: follows.
The system uses the 35-ft.Jelevation for the base. At this elevation-temperature indication is available from -80'F to 160'F.. Vertical.
' temperature differences are measured between 35. ft.-and 125 ft. and 35 ft. and 250 ft.
The temperature differences are. measured-in thez range of -20*F-to 40*F.
All meteorological data is supplied to the plant process computer for determination of atmospheric stability.
This instrumentation is consistent with the requirements of Regulatory.
Guide 1.97 for Category 3 instrumentation.
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t t
t t t t
t t
t t t t t
o o o o
o o o o
o o o o o o o
=
N N N N
N N N N
N N N N N N N
=
(
(
(
(
(
(
(
(
(
(
(
(
(
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l
.