IR 05000334/1989025
| ML20011F016 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 02/07/1990 |
| From: | Anderson C, Paolino R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20011F013 | List: |
| References | |
| RTR-REGGD-01.097, RTR-REGGD-1.097 50-334-89-25, 50-412-89-23, GL-82-33, NUDOCS 9002230451 | |
| Download: ML20011F016 (13) | |
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U.S. NUCLEAR REGULATORY COMMISSION
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REGION I
Report Nos. -50-334/89-25 s
F-50-412/89-23 Docket Nos.
50-334 50-412 License Nos. DPR-66 DPR-73 Licensee: Duquesne Light Power Company
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Post Office Box 4 Shippingport, Pennsylvanir 15077
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Facility Name: Deaver Valley Power Station, Units 1 & 2
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Inspection At:
Shippinoport, Pennsylvania L
Inspection Conducted-December 4-8, 1989 Inspectors:
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O R /J. Paolino, Senior Reactor Engineer date PSS/EB a
Other Participants and Contributors to the Report Include:
B. Marcus, Elpetrical Engineer, NRR/HQ-A. Udy, Elec r 1 Engineer, EG&G, Idaho Approved by:
b C. J/ Anderson, Chief, Plant Systems date Section, E8/ ORS Inspection Summary: Combined Inspection Report Nos. 50-334/89-25 and 50-412/89-23 g
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Areas Inspected: Special announced inspection to review the licensee's
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implementation of Regulatory Guide (R.G.) 1.97, Revision 3 for post-accident I
monitoring instrumentation.
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'Results:
The licensee has~ implemented and/or provided justification for meeting the recommendations of R.G. 1.97 for Category 1 post-accident monitoring systems. No violations were identified, however, four deviations from licensee commitments to comply with the Design and Qualification criteria required in Table 1 of_R.G. 1.97, and two unresolved items were identified as follows:-
DEVIATIONS PARAGRAPH OPEN ITEM NO.
b A-1.
The installed instrumentation for the 3.3 50-334/89-25-01 Unit 1 Steam Generator Level wide range does not have an isolation device between instrumeat. loops and the common strip chart three pen recorder for channels FW-477, FW-487 & FW-497.
A-2.
Separate indicators were rion provided for 3.3 50-334/89-25-01 the three post-accident ir::trunant channels monitoring the 'steata Gv nerator
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Level-Wide Range varial er Unit 1.
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Recorders for the Unit e Gsnerator 3 '.' 8 50-412/89-23-03 Level narrow range are tw..tismically qualified.
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Unit 2 Post-accident Monitoring Recorders 3.7 50-412/89-23-02 were not specifically identified with a common designation.
UNRESOLVED ITEMS 1.
-The demineralized storage tank water level 3.6 50-412/89-23-01 range indicated in the Control Room differs from the range documented in FSAR table 7.5-1.
2.
Licensee evaluation and determination of 3.4 50-334/89-25-02 the impact of lack of isolation devices on the electrical / physical separation of redundant instrument channels for R.G.1.97
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Details 1.0 Persons Contacted 1.1 Duquesne Light Power Company
- G. Cacciani, EQ Engineer
- J. Carretta, EQ Engineer
- E. Coholick, Senior Licensing Supervisor
- J. Crockett, General Manager, Corporate Nuclear Services
- K. Grada, Manager, Nuclear Safety
- G. Kammerdeiner, Director, Materials and Standards
- T. Noonan, General Manager, Nuclear Operations
- F. Ober11tner, EQ Supervising Engineer D. Schmitt, Director, Electrical Engineering T. Shau11, Supervisor, Electrical Engineering
- T. Slavic, Supervising Engineer
- D. Suhan, EQ Engineer N. Tonet, Manager, Nuclear Engineering Department 1.2 U.S. Nuclear Regulatory Commission
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P. Tam, Senior Project Manager, NRR/HQ
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P. Wilson, Resident Inspector
- Denotes personnel present at exit meeting of December 8, 1989 2.0 Introduction
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2.1 Background The purpose of this inspection was to review the licensee's
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implementation of R.G. 1.97, Revision 3, regarding instrumentation
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systems for assessing plant conditions following the course of an accident for the Beaver Valley Power Station, Units 1 and 2.
These systems were inspected to determine if they were installed in ac-cordance with Generic letter No. 82-33, " Requirements for Emergency Response Capabilities" (Supplement I to NUREG-0737). This letter, issuedion December 17, 1982, specifies emergency response capabili-ties that have been approved by the NRC.for implementation. This 1etter also discusses, in part, the application of Regulatory Guide
(R.G.) 1.97 to the emergency response facilities, including the control room-(CR), the technical support center (TSC) and the emer-gency response facility (EOF) at power plants.
Regulatory Guide 1.97 identifies the plant variables to be measured and the design criteria for assuring acceptable emergency response capabilities during and following the course of an accident.
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Regulatory Guide 1.97 divides the post-accident instrumentation into three (3) categories and five (5) types. The three categories are noted as 1, 2, and 3.
Category 1 has the most-stringent design requirements and Category 3 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 identified by the licensee; type B variables provided information to indicate
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that plant safety functions are being accomplished; type C variables
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provide information regarding the potential breach of barriers for
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-fission product release; type D variables indicate the operation of a
individual safety systems; and type E are those that indicate the magnitude of the release of radioactive materials.
2.2 Correspondence The licensee's response to Regulatory Guide 1.97 for Unit I was pro-vided.in letters to the NRC dated November 29, 1985; October 13, 1986; March 5,1987 and April 22, 1987.
For Unit 2, the licensee's response to Regulatory Guide 1.97 was provided in letters dated September 12, 1983 and June 28, 1985.
Subsequent to the issuance of the generic letter, the NRC held regional meetings in February and March of 1983, to answer licensee questions and concerns regarding the NRC policy for implementation of R.G. 1.97.
At these meetings, it was noted that the NRC, review would be limited to explicit exceptions to the guidance of Regulatory Guide 1.97.
Where the licensee explicitly states that the instrumentation systems conform to the provisions of the guide,
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it was noted that no further staff review would be necessary.
Tne specific references used to assess the licensee's response to R.G. 1.97 are identified in Attachment I to this report.
3.0 Inspection Scope and Details (TI 2515/87)
The following instrument channels, used to provide information required for operator controlled actions, have been classified by the licensee as type A variables:
Unit 1 Cold Leg Water Temperature
Hot Leg Water Temperature
RCS Pressure
Containment Sump Water Level
Containment Pressure
Hydrogen Concentration
Containment Area Radiation-H1 Range
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Pressurizer Level
Refueling Water Storage Tank-Level
Steam Generator Pressure
Auxiliary Feedwater Flow
In addition, two Type D, Category 1 variables (Steam Generator Level-Wide Range, and the Status of Standby Power) were examined.
The Regulatory Guide 1.97 variables selected for the Unit 2 review included the following licensee identified, Type A instrumentation:
Unit 2 Cold leg Water Temperature
Hot Leg Water Temperature
RCS Pressure
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Core Exit Temperature Containment Sump Water Level
Containment Pressure
Containment Area Radiation-Hi Range
Pressurizer Level
Steam Generator Level-Wide Range
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Steam Generator Level-Narrow Range Steamline Pressure
Auxiliary' Feedwater Flow
Primary. Plant Demineralized Water Storage Tank Level
Secondary System (Main Steamline) Radiation
In addition, one Type D, Category 1 variable (Status of Standby Power)
was examined.
The NRC R.G. 1.97 inspection of the above instrument channels included:
equipment qualification (seismic and environmental), redundancy of power suoplies, independence and separation of electrical circuits, measured variables, display and recording methods used, range and overlapping features of multiple instrument indicators, direct and indirect measurements of parameters of interest, equipment identification for R.G. 1.97 instruments, service, test and surveillance frequency.
The safety related Q and EQ master equipment lists were reviewed for the instruments selected, to determine if they had been evaluated and tested to the appropriate environmental, quality assurance (QA) and ' seismic qualification requirements. The procurement of these instruments and the implementation of applicable QA requirements was also reviewed.
The inspectors held discussions with various members of the licensee's staff, reviewed drawings and procedures, and selected variables for physi-cal inspection. A walkdown was performed for the display instruments in the control room to assess the implementation of R.G. 1.97.
The instru-ment variables reviewed for Beaver Valley Units 1 and 2 are described in
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the following paragraphs. The licensee's implementation of R.G. 1.97 was found to be acceptable except for the items discussed in Section 3.1 through 3.8.
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3.1 RCS Cold Leg Water Temperature and RCS Hot Leo Water Temperature
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(Units 1 and 2)
Regulatory Guide 1.97 specifies that the redundant instrument channels for these variables have separate and independent power sources. The inspectors found that all instrument channels for the cold leg water temperature had the same power source. All instrument channels for the hot leg water temperature had a second, single independent power source.
The licensee provided copies of a letter to the NRC dated December 4, 1989, to the inspectors. This letter describes the power sources for_
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these instrument channels.
It also designates alternate instrumenta-tion used for redundant or diverse information. This alternate instrumentation receives power from separate vital instrument power buses. Based on the capabilities of the alternate instruments, the inspectors find the provided power sources to the cold and hot leg water temperature instrumentation acceptable.
3.2 Status of Standby Power (Units 1 and 2).
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Regulatory Guide 1.97 specifies plant specific instruraentation for this variable.
It also specifies that the instrumentation design minimize conditions that could give potentially confusing anomalous indications to the operator. The instrumentation identified to monitor the voltage on the 4-kV Class 1E buses have scales that read from 0 to.130 Volts. The documentation provided for this instrumen-tation lists the range at 0 to 130 percent.
The actual bus voltage is substantially greater than the range provided.
Plant personnel indicated that operators are trained to recognize where the 4-kV voltage is normally indicated on the zero to 130 Volt scale. The zero to 130 Volt scale is the actual voltage on the secondary winding of the instrument transformer.
Based on this relationship, the zero to 130 Volt scale is acceptable.
However, the licensee will correct the documented range to agree with the actual range.
3.3 Steam Generator Level-Wide Range (Unit 1)
Regulatory Guide 1.97, Design and Qualification Criteria-Table 1, specifies independent and redundant instrument channels for Category 1 variables.
It also specifies that the transmission of signals from these channels be through isolation devices that are part of the instrument loop and that meet Category 1 criteria These specifications are based on single failure criteria. That is, l
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no single failure results in the loss of the capability to properly assess and monitor the operation of the steam generators. The inspectors found no isolation was provided between the instrument loops (for transmitters FW-477, FW-487, and FW-497) at the common 3 pen strip chart recorder. Separate-indicators were not provided
.for these instrument loops. The recorder is the only display for the three channels.
The inspectors determined that isolation was not provided between the instrument loops and the plant computer. Thus a single failure at either the recorder or the computer could result in the loss of information from all three steam generator channels, i
This item is a deviation from the R.G.1.97 Category 1 design and qualification criteria for _ instruments as identified in Table 1 paragraph Nos. 2 (redundancy) and 9 (Interface-Isolation),
(50-334/89-25-01)
Subsequent to the inspection a conference call was held on December 21, 1989 between NRC Region I personnel and Beaver Valley Station personnel.
This conference call was documented in a letter frem the s
licensee to the NRC dated December 22, 1989. The letter confirms
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licensee commitments made by the licensee during the call. The
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Duquesne Light Company plans to send a letter to NRC by Januar3 30, i
1990 addressing their resolution to th,e Steam Generator Wide Range Instrumentation Deviation from Regulatory Guide 1.97 guidance.
Pending resolution of this matter, the licensee instituted compensatory measures consisting of weekly channel checks between the Control Room Indication, computer systems and the Remote Shutdown Panel.
3.4 Physical Separation (Unit 1)
Regulatory Guide 1.97 specifies that redundant channels of instru-
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mentation be electrically independent and physically separated from each other in accordance with Regulatory Guide 1.75, " Physical Independence of Electric Systems," up to and including any isolation
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device. The inspectors determined that Unit 1 does not typically.
have isolation devices before the instrument loops enter the control boards.
This deficiency appears generic to all Category 1 variables; the extent of this deficiency was unknown at the time of the exit meeting. The licensee committed to determine the extent of this deficiency; including, but not limited to the instrumentation for the L
following variables:
auxiliary feedwater flow, containment pressure,
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containment sump water level, and containment hydrogen concentration.
The inspectors noted that the Beaver Valley I design predates Regulatory Guide 1.75. This item is unresolved pending NRC review of the licensee's evaluation and determination of the impact of the lack of isolation devices on electrical / physical separation of redundant R.G.
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1.97 instrument channels.
(50-334/89-25-02)
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3.5 -Containment Pressure (Unit 2)
The range documented in the September 12, 1983, submittal for this variable is -5 to +65 psig. However, the range observed in the
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control room is -5 to +55 psig. The provided range covers the containment design pressure and is acceptable. The range was corrected in Table 7.5-1 of-the FSAR (before amendment 18). This discrepancy is resolved.
3.6 Primary Plant Demineralized Storage Tank Water Level (Unit 2)
The range documented in the September 12, 1983 submittal and Table 7.5-1 of the FSAR for this variable is 0 to 350 inches. However,
the range observed in the control room is 0 to 330 inches.
The licensee plans to document the actual range and revise Table 7.5-1 of-the FSAR to reflect the actual -range in the Cnntrol Room. This item is unresolved pending NRC verification of the licensee's corrective action. (50-412/89-23-01)
3.7 Identification of Recorders as Post-accident Instrumentation (Unit 2)
Regulatory Guide 1.97 specifies that Category 1 and 2 instrumenta-tion used for Types A, B, and C variables be specifically identified with a common designation on control panels so that the operator can easily discern that the instrumentation is intended for use in a post-accident situation.
The inspectors noted "PAM-1" or "PAM-2" labels are in place for indicators.
However, no means of post-accident identification is provided for recorders associated with post-accident instrumentation. This item is a deviation from R.G. 1.97 Category 1 design criteria for instruments as identified in Regulatory Guide 1.97 Paragraph 8 of Table 1.
(50-412/89-23-02)
3.8 Steam Generator Level-Narrow Range (Unit 2)
Regulatory Guide 1.97 specifies seismically qualified recorders for
- Category 1 variables. Qualification applies to the complete instru-mentation channel from sensor to display where the display is a direct indicating meter or recording device. The licensee could not
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provide documentation that the Steam Generator Level-Narrow Range recorders are seismically qualified.
Documents examined, indicated that these recorders (2FWS-FR478, 2FWS-FR-488 and 2FWS-FR498) were not seismically qualified. This item is a deviation from R.G. 1.97
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Category I design and qualification criteria for instrumentation as
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identified in R.G.1.97 Paragraph 1 of Table 1.
(50-412/89-23-03)
4.0 Unresolved Items An unresolved item is a matter where more information is required to ascertain whether it is an acceptable item, an open item, a deviation or a violation.
Unresolved items are discussed in Section 3 abov.
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i 5.0- Exit Meeting The inspectors met with licensee representatives at the conclusion of the inspection on December 8, 1989.
The inspecter summarized the scope of l
the inspection and the inspection findings at that time.
No written information was provided to the licensee during this
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inspection.
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Attachment 1
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Instrument Schematics and Drawings Reviewed
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Unit 1
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RCS Cold Leg Water Temperature
~8700-RM-155A-12 Revision 7
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8700-RE-22BP Revision 4
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_RCS Hot Leo Water Temperature 8700-RM-155A-12 Revision 7 8700-RE-22BN Revision 5 Containment Sump Water Level
'lifD0-RM-35A-13 Revision 6
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8700-RE-22EW Revision 5 Containment Pressure 8700-RM-168A-11 Revision 6 87-RE-22GM Revision 3
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8700-RE-22EP Revision'2 8700-RE-22IE Revision 2
_ Steam Generator level Wide Range 87-00-RM-124A Revision 7 87-00-RE-22AC Revision 2 RCS Pressure 8700-RM-155A-12 Revision 7 8700-RE-E2BM Revision 8 Containment Hydrogen Concentration 8700-RM-1508-8 Revision 6 8700-RE-22GM Revision 3 Containment Area Radiation 11730-RE-57W-10 Revision 6 87-00-RE-21XE Revision 5 Auxiliary ~ Feedwater Flow 87-00-RM-124A Revision 7 8700-RE-220Z Revision 3 i
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r Stear,..enerator level Narrow Royal j
~B7661RM-124A Revision 7
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8700-RE-22W Revision 3 8700-RE-22Z.
Revision 4 8700-RE-22X Revision 3 L
8700-RE-22AA Revision 5 L
8700-RE-22Y Revision 3
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8700-RE-22AB Revision 3
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Pressurizer Level I
~E7D0-RM-155B-11 Revision 7 8700-RE-22BH Revision 4 8700-RE-22BK Revision 4
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Steam Generator Pressure F7D0-RR;120A-12 Revision 7
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8700-RE-22AN Revision 3 8700-RE-22AP Revision 4 8700-RE-22AQ Revision 3 Refueling Water Storage Tank Level 8700-RE-22ET Revision 3
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8700-RE-22EV Revision 4
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Unit 2 RCS Cold Leg Water Temperature 10080-TLD-006-040-01 thru 06 Revision 4 20080-TLD-006-056-01-06 Revision 4 10080-TLD-006-072-01-05 Revision 4
10080-RE-3ABT Revision 6 10080-RE-1AW Revision 11 10080-RE-11X Revision 10 10080-RE-11Y Revision 10 RCS Hot Leg Water Temperature
~'10085;TLD-006-044-01 thru 05 Revision 4 10080-TLD-006-060-01 thru 05 Revision 5
'10080-TLD-006-076-01 thru 05 Revision 4 RCS Pressure 10080-TLD-006-004-01 thru 03 Revision 4 10080-TLD-006-005-01 thru 03 Revision 4 10080-TLD-050-008-01/02 Revision 3 10080-RC-3AB Revision 7 I
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Core Exit Temperature 10080-TLD-050-036-01 thru 04 10080-TLD-050-037 thru 085 10080-TLD-050-038-03 Containment Sump Water Level Wide Reage 10080-TLD-13A-003-01 thru 04 Revision 5 10080-TLD-13A-004-01 thru 04 Revision 6 Containment Sump Water Level Narrow Range 10080-TLD-009-032-01 thru 03 Revision 3 10080-TLD-009-045-01 thru 03 Revision 3 L
Containment Pressure 10080-TLD-128-027-01 thru 05 Revision 2 10080-TLD-12B-028-01 thru 05 Revision 2 10080-TLD-128-025-01 thru 05 Revision 2 10080-TLD-12B-030-01 thru 05 Revision 2 10080-TLD-128-034-01, 06 Revision 3 10080-TLD-128-035-01, 02 Revision 4 Containment Area Radiation Monitor
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10080-TLD-043-104-01 thru 03 Revision 5 10080-TLD-043-013-01 thru 03 Revision 5 Pressure Level 10080-TLD-053-104-01 thru 05 Revision 3 20080-TLD-006-105-01 thru 05 Revision 3 10080-TLD-006-106-01 thru 05 Revision 4 Steam Generator Level-Wide Range 10080-1LD-24A-051-01,02,03 Revision 4 10080-TLD-24A-059-01,02,03 Revision 4 20080-TLD-24A-006-01,02,03 Revision 4 Steam Generator Level-Narrow Range 10080-TLD-24A-047-01 thru 05 Revision 4 10080-TLD-24A-048-01 thru 05 Revision 4 10080-TLD-24A-049-01 thru 05 Revision 4 10080-TLD-24A-054-01 thru 05 Revision 4
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10080-TLD-24A-055-01 thru 05 Revision 4 10080-TLD-24A-056-01 thru 05 Revision 4 10080-TLD-24A-061-01 thru 05 Revision 4 10080-TLD-24A-062-01 thru 05 Revision 4 10080-TLD-24A-063-01 thru 05 Revision 4
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Steamline Pressure 10080-TLD-21A-020-01,02,03 Revision 3
10080-TLD-21A-010-01 thru 06 Revision 3 l
10080-TLD-21A-011-01 thru 06 Revision 3
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20080-TLD-21A-021-01 thru 06 Revision 3 91H-C12 ($&W dwg)-01 thru 06 Revision 3 F
10080-TLD-21A-019-01 thru 06 Revision 3 10080-TLD-21A-022-01 thru 06 Revision 3 i
21A-013 (S&W dwg)-01 thru 06 Revision 3 l
10080-TLD-21A-017-01 thru 06 Revision 3 Auxiliary Feedwater Flow 10080-TLD-24B-001-01,02 Revision 4 10080-TLD-24B-004-01,02 Revision 4 10080-TLD-24B-002-01,02 Revision 4 10080-TLD-248-005-01,02 Revision 4 10080-TLD-248-003-01,02 Revision 4 10080-TLD-248-006-01,02 Revision 4 Primary Plant Demineralizer Water Storage Tank Level 10080-TLD-24B-023-01.07,03 Revision 4 10080-TLD-24B-024-01,02,03 Revision 4 10080-TLD-05D-007,01,02 Revision 4 Secondary Systems Radiation
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10080-TLO-043-012-01 thru 04 Revision 5 10080-TLD-043-071-01,02,03 Revision 3 10080-TLD-043-075-01,02,03 Revision 1 i