IR 05000387/1990006
| ML17157A143 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 04/04/1990 |
| From: | Anderson C, Cheung L, Paolino R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17157A141 | List: |
| References | |
| RTR-REGGD-01.097, RTR-REGGD-1.097 50-387-90-06, 50-387-90-6, 50-388-90-06, 50-388-90-6, NUDOCS 9004250129 | |
| Download: ML17157A143 (13) | |
Text
U.
S.
NUCLEAR REGULATORY COMMISSION
REGION I
50-387/90-06 Report Nos.
50-388/90-06 50"387 Docket Nos.
50-388 NPF-14 License Nos.
NPF-22 Licensee:
Penns lvania Power 5 Li ht Com an 2 North Ninth Street Allentown Penn s 1 vani a 18101 Facility Name:
Sus uehanna Steam Electric Station Units 1&2 Inspection At:
Berwick Penns lvania Inspection Conducted:
March 12-16 1990 Inspector s:
Leonar Cheung, Senior Reac r Engineer date R. J.
aolino, Senior Reactor Engineer date Approved by:
C. J.
A derson, Chief, Plant System Section, EB/DRS date Ins ection Summar:
Ins ection of March 12-16 1990 Combined Ins ection Re ort Nos. 50-387/90-06 and 50-388/90-06 implementation of Regulatory Guide 1.97, Revision 2 which relates to post accident monitoring instrumentation.
Results:
Based on this inspection, the inspectors determined that the licensee had implemented a program to meet the recommendations of 'R.G
~ 1.97.
One unresolved item was identified - R.G.
1.97 instruments in the control room were not specifically marked.
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PC~R ADOCi; 0 Ce0:."7
DETAILS 1.0 Persons Contacted See Attachment
2.0
~Back round The purpose of this inspection was to review instrumentation systems for assessing plant conditions during and following the course of an accident based on the criteria specified in Regulatory Guide (RG) 1.97, Revision 2.
These systems were inspected to determine if they were installed in accordance with Generic Letter number 82-33 "Requirements for Emergency Response Capability" (Supplement 1 to NUREG-0737).
This letter specifies those requirements regarding emergency response capabilities that have been approved by the NRC for.implementation.
This supplement also discusses, in part, the application of RG 1 '7 to the emergency response facilities, including the control room, the technical support center (TSC)
and the emergency response facility.
Regulatory Guide 1.97 identifies the plant variables to be measured and the instrumentation criteria for assuring acceptable emergency response capability during and following the course of an accident.
Regulatory Guide 1.97 divides Post Accident Instrumentation into three categories and five types.
The three design categories are noted as 1,
and 3.
Category 1 has the most stringent design requirements and category 3 has the least stringent.
The five types of instrumentation identified in the Regulatory Guide are types A, B, C,
D, and E.
Type A variables are plant specific and classified by the licensee.
Type B
variables provide information to indicate that plant safety functions are being accomplished, Type C variables provide information regarding the breach of barriers for fission product release.
Type D variables indicate the operation of individual safety systems.
Type E variables are those that indicate and determine the magnitude of the release of radioactive materials.
Each variable type can be any design category.
However, Type A variables must meet Category 1 design requirements.
3.0
~Sco e
The NRC inspection scope included:
equipment qualification (Seismic and Environmental),
redundancy of power supplies, measured variables, display and recording methods used, independence and separation of electrical circuits, range and-overlapping features of multiple instrument indicator s, equipment identification for RG 1.97 instruments, service, test and surveillance frequency, and direct and indirect measurement of parameters of interes The safety related (g) and Eg master equipment lists were reviewed for the instruments selected to ascertain whether they had been evaluated and tested to the appropriate environmental, quality assurance (gA) and seismic qualification requirements.
4.0 Ins ection Details The inspectors held discussions with various members of the licensee's staff, reviewed drawings and procedures, and selected variables for a system walkdown.
Walkdowns were performed for the sensing instruments (transmitters and Oz and Hz analyzers)
at various locations of the reactor building and the display instruments in the control room to assess the implementation of RG 1.97, Rev.
2.
Instrument variables reviewed included reactor coolant level, reactor coolant pressure, drywell pressure, containment hydrogen/oxygen concentration, suppression pool water level, suppression pool water temperature and neutron flux monitors.
Characteristics examined for each variable include identity, location, function, separation (physical/electrical),
isolation, seismic, power source, environmental qualification status and instrument ranges.
The following instrumentation was examined:
4. 1 Neutron Flux Unit
The neutron flux instruments are classified as type B variable, Category 1 instruments in RG 1.97.
The recommended instrument range is 10-'%o 100% full power.
The installed instrumentation covers a
range of from approximately 10-'%o 100% of full power, the lower range is displayed in counts per second.
This exception was identified by the licensee in their submittal to the NRC in 1984 and was discussed in the Susquehanna Safety Evaluation Report (SER).
The SER indicates that the neutron flux instrumentation is acceptable on a permanent basis if the licensee provides a quantitative analysis justifying the range installed.
The record indicates that a letter providing justification with quantitative analysis had been sent to NRC and is currently under review by the NRC office of NRR.
The instruments provided for this parameter are as follows:
~
Sensor NE-1572 5A NE-12725B NE-12726A NE-12726B Power Division IIIIII Indicator NI-15725A NI-15725B NI-15726A NI-15726 B Recorder Rancae 10-'o 10'ps 10-'o 10'ps 10-> to 100%
10-~ to 100%
No recorders were provided for this parameter.
The licensee identified this exception in their submittal to NRC dated May 31, 1984.
Justification for this exception was provided by the licensee on.page 20 of their submittal.
The licensee provided computer inputs for this parameter.
The data from this system can be plotted and displayed on a control room CRT by the operator if the need arises.
This information can also be stored in the computer historical files and be recalled and plotted.
The inspector considered this to be an acceptable alternate for providing recorded data.
All of the above instrument loops were found to be in calibration as evidenced by the calibration records.
The inspector reviewed the associated drawings and procedures and did not identify any deficiencies.
Instrument marking in the control room and isolation devices are discussed in paragraphs 5.0 and 4.8, respectively.
4.2 Reactor Water Level Unit
The licensee determined the reactor water level to be a Type A, Category 1 variable.
The licensee has provided the following instruments for post accident monitoring of this variable:
Sensor LT-14201A Power Division Indicator Recorder
~Ran e
I LI"14201Al LR/PR-14201A-150" to 180" (extended range)
LT-14202A LT-14203A LI-14203A LR-14202-340" to 110" (fuel zone range)
"150" to 0" to 180" (dual range)
LT-14201B LI-14201B1 LR/PR-14201B-150" to 180" (extended range)
LT-14202B LT-14203 B LI-14203 B LR-14202-340" to 110" (fuel zone range)
-150 to 0" to 180" (dual range)
The display instruments (indicators and recorders)
are located on the main control board.
All of the above instrument loops were found to be in calibration as evidenced by the calibration record The inspector reviewed the associated drawings and procedures.
No deficiencies were identified.
See Section 5.0 for the discussion of lack of specific marking in the control room.
4.3 Reactor Coolant Pressure Unit 1 The licensee determined that the Reactor Coolant pressure instrumentation to be a type A, Category 1 variable.
The following instrument channels have been identified as providing monitoring capability following an accident:
Power Transmitter Division Indicator Recorder
~Ran e
PT-14201A I
PI-14202A
. PI-14204A LR/PR-14201A 0-1500 psig PT-142018 PT-142038 P I-142028 PI-142048 P I-142028 P I-142048 LR/PR-142018 0-1500 psig 0-1500 psig Three reactor pressure signals are transmitted from three independent transmitters.
Two signals are recorded on two, two pen recorders.
One pen records pressure, the other pen records level.
All three were found to be in calibration as evidenced by the calibration records.
Mithin the scope of this inspection, no deficiencies were identified.
4.4
~0r well Ha/Oa Concentration Unit 2
\\
The licensee determined that drywell hydrogen and oxygen'oncentra-tion are Type A variables.
Accordingly, the licensee furnished category 1 sampling, process and display instrumentation.
The monitoring of these variables is performed by the following redundant instrument channels:
a.
H dro en Concentration Sensing Elements AE"25745A Power Division Recorder Indicator AR-25746A*
AI-25745A
~Ran e
0-lOX 5 0-30K AE-257458 AR-257468257468 AI-257658 0-10K 5 0-30K
b.
Ox en Concentration Sensing Elements Power Division Recorder Indicator
~Ran e
AE-25745A AE-257468 AR-25746A" AI-25746A AR-257468*
AI-257468
10%
8( 0-25%
0-10%
5 0-25%
- Multipen recorder for both Hz and Oz concentration recording The hydrogen and oxygen concentration instruments are located on the main control board.
All instrument loops were found to be properly calibrated as evidenced by the calibration records.
Within the scope of this review, no deficiencies were identified.
See Section 5.0 for a discussion of lack of specific identification of display instruments in the control room.
4.5 Primar Containment dr well Pressure Unit 2 The licensee has determined that'the drywell pressure instrumentation to be a type A, Category 1 variable.
The following instrument channels were provided to monitor this variable after an accident:
Power Transmitter Division Recorder
~Ran e
PT-25709A PT-257098 PT-25710A PT-257108 III III PR-25710A PR-257108 P R-25710A PR-257108 0-250 psig (red pen)
0-250 psig (red pen)
6.5 - 65.0 psia (blue pen)
6.5 - 65.0 psia (blue pen)
4.6 Two redundant, divisionalized, wide range pressure sensing circuits are provided in the primary containment drywell for accident monitoring.
Two redundant two-pen recorders are used for indication and providing an historical record of post-accident, containment pressure.
The wide range is provided for post-accident monitoring and the narrow range for normal operation monitoring.
Redundant circuits are electrically and physically separated.
The transmitters were identified on the Eg Master List and all instruments in the loop were determined to be seismically qualified and in calibration.
Within the scope of this inspection, no deficiencies were identified.
Su ression Pool Water Level Unit 2 The licensee determined the Suppression Pool Water Level Instrumentation to be a type A, Category 1 variable.
The following instrument channels were provided to monitor this variable:
Transmitter LT-25775A LT-25775B LT-25776A LT-25776B Power Division III III Readout LR-25776A LR"25776B LR-25776A LR-25776B Rancae 0-102 INWC (blue pen)
0-102 INWC (blue pen)
0-534 INWC (red pen)
0-534 INWC (red pen)
2 pen recorder blue: 18-26.5 ft red: 4.5 - 49 ft Four independent level transmitters, two of them calibrated for normal operation (narrow range)
and two of them calibrated for post-accident monitoring (wide range) continuously sense the suppression pool water level.
Each narrow range transmitter provides the signal for the divisionalized level indication meter in the control room.
Both level ranges provide input to the recorder input channels'n addition, suppression pool water level indication is provided in the remote shutdown panel.
Within the scope of this inspection, no deficiencies were identified.
Su ression Pool Water Tem erature Unit
Indicator
~
~Ran e
Regulatory Guide 1.97 classifies suppression pool water temperature as a Category 2 variable.
However, the licensee has specified it to be a Type A variable.
Therefore, the instrumentation is required to conform to the Category 1 criteria.
Monitoring of this variable is performed by the following two channels of instrumentation, each comprising eight (8) temperature sensing elements:
Power Division TE-15753 TE-15755 TE"15757 TE-15759 TE-15763 TE-15765 TE-15767 TE-15769 TE-15752 TE-15754 TE-15758 TE-15760 TE-15762 TE-15766 TE-15768 TE-15770 TIAH-15751 SO-250 F
TIAH-15752 50 "250 F
Regulatory Guide 1.97 recommends instrumentation for this variable with a range from 30 to 230'F.
The licensee has instrumentation for this variable with a range from 50 to 250'F.
Temperatures between
and 50'F are not monitored.
This deviation was discussed in the Susquehanna SER and was determined to be acceptable by the NRC.
The temperature indicators are located on the main control board.
They are digital type and receive their input from electronic units (TX-15751 and TX-15752) which are capable of providing the average temperature of the suppression pool as well as the individual tempera-,
ture of each suppression pool zone monitored.
The licensee provided computer input for this parameter.
The instrument loops were found to be properly calibrated as evidenced by the calibration records.
The inspector reviewed the associated documents and did not identify any deficiencies.
4.8 Isolation Devices Where a Category 1 signal is used as input to a non-Category
system, Regulatory Guide 1.97 specifies the use of isolation devices which are fully qualified for use in Category 1 circuits.
The inspector examined the circuits involved and found that:
1)
The isolators used for the process instrumentation loops (reactor water level, reactor coolant pressure, etc.) are Bailey type 740 mi llvolt convertors.
2)
The isolators used for the containment radiation monitors are Action Instrument Company Model 4010 card-type isolators.
3)
The neutron flux loop isolators are part of the Gammametrics Amplifier Panel.
4)
No isolators are used between the Category 1 instruments and non-1E annunciator inputs.
The isolators used for items 1,
2 and 3 provide signal isolation between the Category 1 instruments and the computer inputs, including plant computer and safety parameter display system (SPDS)
inputs.
The licensee considered the annunciators and computer inputs'to be low energy circuits.
Exceptions for low energy circuit isolations were discussed and justification provided in paragraph 8. 1.6. 1.(}.7 of the Susquehanna Final Safety Analysis Report.
In addition, the licensee generated an engineering evaluation entitled "Isolation Capabilities of BOP Isolators",
dated November 21, 1989 to discuss the functional capabilities of all isolators used at Susquehanna.
The licensee stated that they planned to conduct a functional test of the isolators within this year to further demonstrate the functional capability of the isolators.
The general issue of the isolators and of the instrument loop without the isolator (item 4 above) is being examined by the NRC office of NRR.
The inspector had no further question.0 Ph sical Ins ection The inspector performed a physical inspection of display instruments located in the control room, and local instruments located in various areas of the Reactor Building.
For the display instruments (indicators and recorders)
specified, the inspector verified instrument function, instrument range and identification of RG 1.97 Instruments.
For the local mounted instruments, the inspector verified instrument mounting and supports, separation of cable routing and instrument tubing for redundant instrument channels'he inspector examined the RG 1.97 display instruments in the Unit 1 5 2 control room to determine agreement with Regulatory Guide 1.97 for electrical/physical separation and instrument calibration.
No deficiencies were identified applicable to electrical or physical separation.
Calibration of all RG 1.97 instruments was determined to be in accordance with the technical specifications.
6,0 The inspectors observed that the Category 1 instruments of both Unit
and Unit 2 had not been specifically identified as recommended by paragraph 1.4.b of RG 1.97 regarding equipment identification.
NUREG 0737 Supplement 1 and NRC generic letter 86-33 were issued to the licensee on December 17, 1982, asking the licensee to document any deviation from RG 1.97.
However, this deviation was not documented in the licensee's submittal to the NRC dated May 31, 1984.
The inspector noted that the Susquehanna FSAR, paragraph 3. 13. 1 "compliance with RG 1.97" discussed this deviation.
The FSAR indicates that the instrumentation for accident monitoring is not specifically identified on the control panel, and that the licensee's position on RG 1.97, Revision
was transmitted to the NRC i'n PLA-965, dated November 13, 1981.
No justification was provided in the FSAR as to why specific identification is not required and this deviation was not discussed in the Susquehanna SER.
This item is unresolved pending NRC review of the licensee's RG 1.97 submittal for not complying with the specific identification of RG 1.97 instruments (50-387;388/90-06-01).
Surveillance Testin and Calibration The surveillance tests and calibrations of all RG 1.97 Category 1 instruments are performed by the I&C maintenance department.
The licensee employes a
computerized data base for scheduling and tracking instrument calibration.
The inspectors reviewed the data base for the instruments inspected, the frequency of calibration, and the calibration expiration date.
The inspector conducted a review to determine that procedures are in place for the performance of the calibration.
No deficiencies were identifie.0 Unresolved Items Unresolved items are matters about which more NRC review of the licensee supplied information is required in order to determine if they are acceptable items or violations.
An unresolved item identified during this inspection is discussed in Details, paragraph 5.0 of this report.
The inspectors met with-licensee representatives (denoted in Attachment 1)
at the conclusion of the inspection on March 16, 1990.
The inspectors summarized the scope of the inspection, the inspection findings and confirmed with the licensee that the documents reviewed by the team did not contain any proprietary information.
The licensee agreed that the inspection report may be placed in the public Document Room without prior licensee review for proprietary informatio '
Attachment
1.0 Persons Contacted 1.1 Penns lvania Power 8 Li ht Com an J. Bartos, Senior Project Engineer J. Blakeslee, Assistant Superintendent of Plant T ~ Clymer, Nuclear Quality Assurance Coordinator T. Lorfida, ICC Supervisor H. Lloyds, Jr.,
Power Production Engineer G. Stanley, Superintendent of Plant G. Treven, 18C Engineer W. Williams, Project Licensing Engineer 1.2 United States Nuclear Re ulator Commission S. Barber, Senior Resident Inspector J. Stair, Resident Inspector The above personnel attended the exit meeting of March 16, 1990.