IR 05000445/1990015
| ML20043B947 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 05/17/1990 |
| From: | Paulk C, Stetka T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20043B946 | List: |
| References | |
| RTR-REGGD-01.097, RTR-REGGD-1.097 50-445-90-15, 50-446-90-15, NUDOCS 9006010086 | |
| Download: ML20043B947 (11) | |
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APPENDIX j
l U.S. NUCLEAR REGULATORY COMMISSION j
REGION IV
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NRC Inspection Report:
50-445/90-15 Operating License: NPF-28
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50 446/90-15 Construction Permit: CPPR-127 l
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Dockets: 50-445
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l 50-446 Licensee:
TU Electric l
400 North Olive L.B. 81 Dallas, Texas 75201 Facility Name: Comanche Peak Steam Electric Station (CPSES), Units 1 and 2-j Inspection At: Glen Rose, Somervell County, Texas
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Inspection Conducted: May 7-11, 1990 l
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Inspector:
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l. f.% Phulk, Reactor Inspector, Plant Systems Date Se'ttion Division of Reactor Safety
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Approved:
M M11M i /7 96 T. F.7tetka, Chief, Plant Systems Section Data
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Division of Reactor Safety inspection Sumary Inspection Conducted May 7-11, 1990 (Report 50-445/90-15;50-446/90-151 Areas Inspected: Routine, announced inspection of the implementatien of the connitments to the provisions of Re9ulstory Guide (RG) 1.97, "Postaccident Monitoring Instrumentation."
Results: The licensee has fulfilled the connitments to comply with the requirements of.RG 1.97 for Unit 1.
Due to the stage of construction on
Unit 2, verification could-not be made with regard to the installed
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instrumentation and compliance with the environmental and seismic qualification
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1.icensee management was supportive of the inspection effort. The appropriate personnel were available to answer questions and to provide needed information in,o timely manner. The effort put forth by the licensee to comply with RG 1.97 was' evident as exhibited by the completeness of the documentation and i
very minor discrepancies that were identified.
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No violations or deviations were identified, i
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i DETAILS l
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Persons Contacted TU Electric
- R. Adams, Supervisor, Instrument and Controls (I&C) Engineering
- I. Ahmad, Supervisor, Electrical Engineering
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- T. Bruffett, Technical Assistant, Project Engineering
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- R. Burns, Senior Engineer, Operations Support Engineering)(OSE)
- G.Butera,SeniorEngineer,DesignBasisEngineering-(DBE i
- V. Cornell, Licensing Engineering, Dallas Licensing
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- C. Creamer, Manager, Project Electrical /I&C-Engineering
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- K. Gangadhar, Engineer. 0SE i
- C, Hogg, Chief. Engineer
- T. Hope, Site Licensing
- J. LaMarca, Manager Electrical and I&C Engineering
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- J. Muffett, Manager of Project Engineering
- T. Narang, Senior Engineer, DBE
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- E. Ottney, Project Manager, Citizens' Association for Sound Energy (CASE)
- P. Passaludo. Supervisor, DBE
- D. Woodlan, Manager, Unit 2 Licensing NRC
- D. Chamberlain, Chief, Reactor Projects Section B
- W. Johnson, Senior Resident Inspector, CPSES
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R. Latta, Resident Inspector, Unit 2 CPSES The inspector also contacted and interviewed other licensee personnel during the course of the inspection.
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POSTACCIDENT MONITORING INSTRUMENTATION (25587)
2.1 Background
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By letter dated December 17,1982(GenericLetter82-33),theNRCprovidedall reactor licensees and applicants with the " Requirements for Emergency Response Capability."
Included in these requirements was the application of Regulatory Guide (RG) 1.97, " Instrumentation for Light Water Cooled Nuclear. Power Plants :
to Assess Plant and Environs Conditions During.and Following an Accident." The provisions for the instrumentation described in RG 1.97 were endorsed by the NRC to ensure that nuclear power plant operators would have sufficient and reliable information available for preventing and/or mitigating the
. consequences-of a reactor accident. During this inspection, the inspector evaluated the acceptability of the installed instrumentation at the CPSES. The inspection was conducted in accordance with the NRC Inspection and Enforcement Manual's Temporary Instruction 2515/87.
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-4-The inspector reviewed the licensee submittals and the NRC staff evaluation of those submittals
" Safety Evaluation Report Related to The Operation of
Comanche Peak Steam Electric Station (CPSES) Units 1 and.2 Supplement No. 23,"
transmitted to the licensee by letter dated February 28, 1990. The inspector also reviewed the CPSES Final Safety Analysis Report (FSAR),Section VII
" Control and Instrumentation," and the CPSES Technical Specifications (TS)
related to instrumentation systems.
The inspector selected for detailed review the instruments utilized for all 13
of the Type A variables for each unit; these were all designated as Category 1
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instruments. An additional sample of two Category 1 and nine Category 2 instruments were also selected. The sampled instruments are listed in Table 1.
The design and qualification criteria for Categories 1, 2, and 3 instrumentation is provided in Regulatory Position 1.3 of RG 1.97, Revision 2, i
dated December 1980. A brief comparison of these criteria is included in i
Table 2.
Category 3 instruments provide backup-type information and were not
included in this inspection effort. The inspector compared the attributes of i
the selected instruments to the provisions contained in Revision 2 of RG 1.97 l
to verify conformance with the recommendations for range, power supply,
environmental qualification, seismic qualification, and redundancy. During this comparison, the inspector also determined whetherothere were any open questions that required a more detailed review (e.g., verify proper instrument range when the readout was specified as only 0-100 percent span) to detennine l
acceptability.
During this onsite inspection, the inspector reviewed piping and instrumentation diagrams to verify that all of the selected parameters were being detected by dit:ct sensing. The inspector reviewed the listing of equipment required to be environmentally qualified to verify that the
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I appropriate RG 1.97 instruments were included. The inspector also verified that all of the selected instruments were included in the licensee's quality assurance program by reviewing the "Q" list.
The inspector had noted that some of the instruments listed in the licensee's I
RG 1.97 submittals were not specifically listed in the TS. During the onsite inspection effort, the subject of operability and surveillance requirements for these instruments were discussed with licensee personnel.
The inspector reviewed the various schematic, loop, and connection wiring diagrams to identify the power supply, electrical separation, and isolation devices utilized for each of the selected instruments. The diagrams were reviewed to ensure that redundant instruments were energized from separate sources, that system interconnections were properly isolated from each other, and that the systems contained the necessary components.
The inspector verified that the required indications and monitors were
available in the Unit I control room and at the training simulator. The l
inspector also verified the installation of the required strip chart recorders
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in the Unit I control room for the Category 1 parameters.
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The documentation for the Unit 2 instruments for verification of power supply, electrical separation, and isolation devices was also reviewed. There was no dccumentation available, however, for verification _of environmental and seismic-qualification, nor for the maintenance activities _ necessary to meet operability and surveillance requirements. Additionally, many of the Unit 2 instruments had not been installed.-
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2.2 Inspection Findings 2.2.1 Review of Design Documentation
.The-inspector reviewed various design documents and drawings for the selected
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instruments to ensure that the RG 1.97 guidance,.as committed to by TV Electric, had been implemented. A listing of_the pertinent drawings that were; reviewed are contained in thn Attachment to this report. The inspector'had the following observations during the review of the design documents.
During the review of the licensee's submittal for instrumentation to be used te verify standby) power was available, the inspector noted that two power panels
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(IEC5 and 1EC6 did not appear to have any instrumentation associated with
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them. A visual inspection confirmed that there were no voltage or amperage
meters on these panels. The licensee acknowledged this discrepancy by steting l
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The inspector verified that the instruments necessary to verify power available were located on panels 1EC3 and IEC4. -The licensee initiated'a change. request
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to remove IECS and-iEC6 from the RG 1.97 list since;they did not provide any
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useful information.
2.2.2 Review of Installed ~ Instrument Displays
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The irnector performed a walkdown of all Type A,.Bi and C, Category 1 or ~2 l
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instruments in order to verify that the installed meters and recorders had the same range as described in the submittal. During this walkdown, the~ inspector noted that the recorders for pressurizer level and steam generator wide range-level were not uniquely identified as required by the'RG. The licensee stated.
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L that these recorders were not Class.1E qualified recorders, and, as such, did not require the labeling. This position was based on previous verbal communications with the NRC; however, the licensee had-failed'to obtain contirmation-in writing. The SER was issued by the NRC based on'the understanding i
that the licensee would provide unique labels on the instruments in.accordance j
with the guidelines of the RG.
Following these discussions regarding the
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requirements of labeling the instruments, the licensee. installed the labels y
prior to the end of this inspection.
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Out of approximately 80 instruments, the only ones that.were not labeled in accordance to the RG were the three recorders identified above. The licensee justified their position based on prior discussions with the NRC; however, there was an apparent misunderstanding during these discussions resulting in
L the unlabeled instruments. Nonetheless, the licensee acu ' q udently to resolve the issue proinptly and satisf actorily.
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.i 2.3 Conclusions-
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The licensee had developed a very detailed' program'to: address-compliance with
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the commitment to RG 1.?7 for Unit 1.
Managenent support was exhibited byl the
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resources supplied to develop and implement the program. The licensee's.
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effort showed a high degree'of compliance'and an excellent understar. ding of the importance,of,the RG 1.97 instruments as an operator aid.
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Exit Interview (30703)
An exit interview was ' conducted on iltur '11,1990, with:the licensee; L
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representatives identified in paragraph 1,1 During.thistinterview, the-
inspector reviewed the scope and. findings of thetinspection as > esiled:in this-report. - Although some proprietary documents were reviewed byathe inspector, no~
i proprietary documents were removed from the facility,-and no proprietar,y l
information is' contained in this report.-
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' TABLE 1:
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POSTACCIDENT. MONITORING INSTRUMENTATION INSPECTED E-
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CATEGORY-1 INSTRUMENTS
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Reactor Coolant Systen guCS) Cold Leg Water Temperature (Wide Range)
RCS Hot leg Water Temperature (Wide Range)'
c RCSPressure(WideRange);
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- Core Exit Temperature.
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Degrees of Subcooling
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ContainmentSumpWaterLevel(WideRange)
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Refueling Water Storage. Tank Level Pressurizer Level Steam Generator Level (Harrow Range)
SteamGeneratorLevel.(WideRange)
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' i Steam Generator Pressure Auxiliary Feedwater Flow ~
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Condensate Storage Tank' Level Containment Pressure Neutron' Flux.
Q CATEGORY 2 iHSTRUMENTS
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High Range Radiation Monitor i
Residual.HeatRemoval(RHR).HeatExchanger0.utletTemperature j
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RHR Flow
Component Cooling Water Header Temperature
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Safety Injection Flow
.1 Charging Pump Flow
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Containmant Spray Flow Pressurizer Heater Current
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Status of Standby Power i
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.j TABLE 2 l
COMPARISON OF REQUIREMENTS:
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CATEGORY 1-
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CATFSORY 2
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Environmental Qualification
- Yes Yes-
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Seismic Qilalification.
Yes:
iAs Appropriate
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Single Failure Yes-
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Power. Supply Emergency Standby Reliable-Indication Immediate;-
- Demand
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I Recording-
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- 3 QA Requirements
.-10 CFR 50,' App. B
'As Appropriate ili Testability Yes.
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ATTACHMENT LIST.0F DRAWINGS REVIEWED '
Drawing 8810D31 Sheet Number Revision Title l
7-Containment Pressure
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6 Refueling Water Storage Tank Level
~13 5'
Stm Gen Level Loop.1 (Wide Range)
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'Stm Gen Level' Loop 2
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8 Stm Gen Level Loop 3
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Stm Pressure Loop 1
14 Stm Pressure Lot.~ ?
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5-Pressurizer Level
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Stm Pressure Loop 3-
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'34 11-Stm Pressure Loop.4
6 Stm Gen Level Control ~
11 Stm Gen Level: Control
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14 Reactor' Coolant: Temp. (Wide an+1 -
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HotLegs)
14 Reactor. Coolant Temp. (Wide Range -
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Cold' Legs)-
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Drawing 8810032
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6-Containment Pressure'
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7 Refueling' Water Storago Tank Level
5 Stm Gen Level Loop-2 (Wide. Range)-
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~14 Stm Gen Level-Loop 1-
7-Stm Gen Level Loop 4
7 Stm Pressure' Loop 1
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7 Stm' Pressure Loop 2-i
6 Pressurizer Level.
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7 Stm Pressure Loop 3-
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13 Stm Pressure Loop 4-37
Stm Gen Level ~ Loop.2 i'
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Stm Gen Level Loop 3 l.
15 Reactor Coolant Temp. (Wide Range -
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Cold Legs) _.
15 Reactor Coolant Temp. (Wide Range -
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.HotLegs).
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Drawing 0810D33 Sheet Number-Revision Title.1
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8 Containment Pressure
8 Refueling Water Storage. Tank Level
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6 Stm Gen Level Loop ~ 3:(Wide Range)
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7 Stm Gen Level-Loop 1.
7 Stm Gen Level Loop 2'
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?tm Gen Level; Loop 3-
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Stm Gen Level Loop 4
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Stm Pressure Loop 2
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6 Stm Pressure Loop:3
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6 Pressurizer Level-l Drawing 8810D34 Sheet--Number Revision Title
8 Containment Pressure
8 Refueling Water Storage Tank Level
7 Stm-Gen Level-Loop 4 (Wide Range)
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Stm Gen Level Loop 1
7 Stm Gen. Level Loop 2
7 Stm Gen Level Loop 3
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14 Stm Gen' level Loop 4 l
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6 Stm pressure Loop 4
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16 RCS-Wide Range Pressure Loop 4
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Drawing 8815D35
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Sheet Number Revision Title
12 Chg. Pump Discharge Flow
6 RHR #1 Return ~ Temp.
8 RHR #1 Bypass Flow Control-l-
L Drawing 8810D36 Sh.18 Rev. 9 Safety Injection Pump #2 Discharge Flow Drawing 8810D37 Sh. 18 Rev. 7-Safety Injection Pump #1 Discharge-
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Flow
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Drawing 8810D38 Sh. 19 Rev. 6 RHR #2 Return Temp.
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Drawing 8810D32 Sheet Number Revison Title
CP-1 Aux. FW Flow To Stm Gen 01, 02, l
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CP-1 Containment Spray Pumps 02 & 04, Disch to Recirc Hdr Flow
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CP-1 Containment Spray. Pumps.02 &-04,-
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=Disch-to Recirc Hdr Flow i
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Drawing VI-8815D31 i
Sheet Number Revison Title
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' Aux FW Flow to Stm Gen 01, 02,.
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'CP-1 Containment Spray' Pump 01 &-03 1,
Disch to Recirc Hdr.-Flow
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4-Containment Spray Pump 01.& 03,
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Disch to Recirc'Hdr Flow
31-CP-1 CCW HX-01 Outlet: Temp"
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i Drawing El-0018 j
Sheet Number Revison Title-a CP-11 118 VAC-Instrument Bus Distribution j
One Line Diagram;.
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CP-9 118 VAC Instrument Bus Distribution
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One' Line-Diagram
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CP-5 118.VAC' Instrument Bus Distribut on
One Line Diagram-i C
CP-5 118 VAC Instrument Bus Distribution
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One Line Diagram'.
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E CP-6 118:VAC Instrument Bus Distribution.
i One Line Diagram a
G CP-8 118;VAC ~ Instrument Bus Distribution
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One Line Diagram
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01F CP-4 208/120 VAC One Line Diagram 01G CP-6 208/120.VAC One Line Diagram 02C CP-5 118'VAC-One Line Diagram 02D CP-5 118 VAC One Line Diagram-Drawing Number Revision Title El-0024 Sh. 3 CP-10 118 VAC Comon and Unit 1 IDPi
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-El-0024 Sh. 4-CP-4
'e Exit Thermocouple Rack El-0137 CP--
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! Exit Thermocouple Rack
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El-0141 CP '
-' Analog Rack' CPI-EIPRCI-01L
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El-0142 CP -
WP Analog Rack CP1-EIPRCI-02
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M1-0260 CP-19 Flow Diagram Residual l Heat Removal -
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