ML20197A942
| ML20197A942 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 10/20/1986 |
| From: | NRC |
| To: | |
| Shared Package | |
| ML18052A747 | List: |
| References | |
| TAC-45156, NUDOCS 8610270427 | |
| Download: ML20197A942 (8) | |
Text
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NONPROPRIETARY VERSION i
ENCLOSURE 2 EVALUATION OF INADEQUATE CORE COOLING INSTRUMENTATION -
SYSTEM FOR PALISADES (TAC # 45156)
DOCKET NO. 50-255
1.0 INTRODUCTION
In response to Generic Letter No. 82-28 (Ref. 1) and NUREG-0737, Item II.F.2 (Ref. 12), Consumers Power Company (CPC) has proposed a system for detecting and monitoring inadequate core cooling (ICC) conditions for the Palisades plant. The system includes a subcooling margin monitor (SMM), a core exit thermocouple (CET) system, and a RADCAL inventory meter (RIM). The staff has reviewed the CPC submittals on its inadequate core cooling instrumen-tation(ICCS) system (Refs.2-8). This staff review incorporates signifi-cant technical input prepared by the staff's consultants at Oak Ridge National Laboratory (0RNL) under technical assistance contract FIN B-0779.
This review includes information provided to the staff and its ORNL con-sultant by CPC and its consultant, Technology for Energy Corporation (TEC),
at a meeting held in Bethesda, Maryland, on August 28,'1986. The staff's evaluation follows.
2.0 EVALUATION 2.1 Reactor Inventory Measurement (RIM) System l
-(FROFRitTARY) 8610270427 861020 gDR ADOCK 05000255 PDR NONPROPRIETARY VERSION
2.2 Core Exit Thermocouple (CET) System The Palisades reactor contains 45 distributed CETs. The CETs are at the upper end of top entry incore probes, also containing self-powered in core flux detectors. The CET and flux signals from each probe are fed through a common cable to the control room. The 45 cables share a common path via two adjacent containment penetration units to the input cabinet of a data logger. Cable connectors for 16 CETs will be replaced with qualified connectors. The 16 signal cables will be disconnected from the present data logger and connected to the signal processing units located in the qualified RIM modules (LTRI), which contain the backup displays for the CETs. Display range is 0 to 2300 degrees F.
The in-containment cable has been replaced with qualified, mineral insulated cable (Ref. 11). The system is environmentally and seismically qualified from sensor to display. The system has two redundant, inde-pendent' channels which are physically separated for their entire length.
J Both channels are fed from separate 120 volt ac, class IE power sources.
Indication and recording is continuous on the display panel. Primary display for CET information is the CFMS which provides all the required l
CET display attributes, including a core map.
Isolation devices at the CFMS computer inputs are easily accessible for maintenance during accident conditions.
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3-2.3 Subcooling Margin Monitoring (SMM) System Palisades has installed two Class IE SMMs that meet the environmental qualifications per IEEE-344-1975 and IEEE-323-1974 standards. They include a Combustion Engineering supplied microprocessor which continuously calculates for display the degrees F of primary coolant subcooling. Temperature inputs from each hot leg are provided to each SMM. Two reactor protection system pressure inputs, with range of 0-2500 psia, are provided to each SMM. A CPC committed upgrade of the SMM will consist of installing wide-rangs temperature trans-mitters to provide the SMM with a temperature span of 50-700*F to replace the existing 515-615*F input span and modifying the SMM units to provide the extended range required by NUREG-0737, II.F.2 and Regulatory Guide 1.97, Rev. 3.
The new transmitters will have dual transmitted ranges to preserve the accuracy of the limited span for the plant protection system and to provide the expanded range needed for the SMM.
2.4 Procedures, Technical Specifications, and Training Revised Emergency Operating Procedures incorporating ICCI have been prepared using Combustion Engineering guidelines. These procedures 4
have not been submitted at the present time. CPC is in the process of revising Technical Specifications to include ICCI. CPC is currently conducting training of operators in the use of ICCI.
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3.0 CONCLUSION
S The staff concludes that the Consumers Power Company's ICCI system composed of (1) a vessel inventory system based on the RADCAL gamma thermometer sensor, (2).subcooling margin monitors (SMM), and (3) a core exit thermo-couple system is acceptable since it meets the requirements of Item II.F.2 of NUREG-0737. The staff's acceptance, however, is contingent on the Consumers Power Company's commitment to upgrade the SMM with wide range temperature transmitters.
With respect to the installation of the RIMS, the Consumers Power Company should provide the implementation letter report described in Enclosure 3 so that the staff can complete its review of the RIMS implementation.
4.0 REFERENCES
1.
" Inadequate Core Cooling Instrumentation System," Generic Letter No. 82-28, December 10, 1982 (Letter from NRC to All Licensees of Operating Westinghouse and CE PWRs [Except Arkansas Nuclear One-Unit 2 and San Onofre Units 2 and 3]).
2.
Letter dated January 30, 1984 from B. D. Johnson (CPC) to D. M. Crutchfield (NRC).
3.
Letter dated May 31, 1984 from B. D. Johnson (CPC) to D.M.Crutchfield(NRC).
r 5-4.
Letter dated June 1, 1984 from B. D. Johnson (CPC) to D.M.Crutchfield(NRC).
5.
Letter dated October 19, 1984 from B. D. Johnson (CPC) to Director, NRR.
6.
Letter dated June 10, 1985 fromD.J.VandeWalle(CPC)to Director, NRR.
7.
Letter dated October 31, 1985 from J. L. Kuemin (CPC) to Director, NRR.
8.
Letter dated June 11, 1986 from J. L. Kuemin (CPC) to Director, NRR.
9.
" Inadequate Core Cooling Instrumentation Using Heated Junction Thermocouples For Reactor Vessel Level Measurement,"
NUREG/CR-2627, March 1982, (prepared by Oak Ridge National Laboratory).
10.
" Summary Report - Reactor Vessel Level Monitoring System and Program Test Series for the Palisades Plant," TEC Report R-86-005, Technology for Energy Corporation, June 1986, (AttachmenttoReference8).
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6-11.
Letter dated September 25, 1986 from J. L. Kuemin (CPC) to Director, NRR.
12.
" Clarification of TMI Action Plan Requirements," NUREG-0737, November 1980.
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ENCLOSURE 3 l
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MILESTONES FOR IMPLEMENTATION OF i
INADEQUATE CORE COOLING INSTRUMENTATION i
l 1.
Submit final design description-(by licensee) (complete the docu-mentation requirements of NUREG-0737. Item II.F.2. including all i
evaluation reports for generic approved systems)pplicable NRC plant-specific infomation items identified in a j
2.
Appeval of emergency operating procedure (E0P) technical guidelines -
(byNRC).
Note: This E0P technical guideline which incorporates the selected i
system must be based on the intended uses of that system as described in approved generic E0P technical guidelines j
relevant to the selected system.
3.
Inventory Tracking Systems (ITS) installation complete (by licensee).
l 4.
IT3 functional testing and calibration complete (by licensee).
5.
Prepare revisions to plant operating procedures and emergency i
procedures based on approved E0P guidelines (by licensee).
6.
Implementation letter
- report to NRC (by licensee).
7.
Perfom procedure walk-through to complete task analysis portion of ICCsystemdesign(bylicensee).
l 8.
Turn on system for operator training and familiarization.
9.
Approval of plant-specific installation (by NRC).
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- 10. Implement modified operating procedures and emergency procedures (bylicensee).
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- System Fully Operational -
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- Implementation Letter Report Content l
(1) Notification that the system installation, functional testing, and l
calibration is complete and test results are available for in-spection.
(2) Sumary of licensee conclusions based on test results, e.g.:
(a) the system perfoms in accordance with design expectations and within design error tolerances; or (b) description of deviations from design performance specifications and basis for concluding that the deviations are acceptable.
(3) Description of any deviations of the as-built system from previous design descriptions with any appropriate explanation.
(4) Request for modification of Technical Specifications to include all ICC instrumentation for accident monitoring.
(5) Request for NRC approval of the plant-specific installation.
(6) Confim that the EDPs used for operator training will confom to*
the technical content of NRC approved E0P guidelines (generic or plantspecific).
r ENCLOSURE 4 s
SALP INPUT FACILITY: Palisades / Docket No. 50-255/ License No. DPR-20 EVALUATION:
Inadequate Core Cooling Instrumentation System (TAC #45156) 1.
Management Involvement and Control in Assuring Quality The submittals and the August 28, 1986 meeting with Consumers Power (CPC) were of high quality and indicate CPC management involvement in assuring high quality technical information.
Rating: Category 1 2.
Approach to Resolution of Technical Issues from a Safety Standpoint The RADCAL gamma thermometer approach to inventory (level) measurement to meet NRC requirements is a novel and well-thought out concept.
Rating: Category 1 3.
Responsive to NRC Initiatives The August 28, 1986 meeting with CPC indicated a high degree of willingness to be responsive to NRC requests for information.
Rating: Category 1 4.
Enforcement History N/A 5.
Reporting and Analysis of Reportable Events N/A 6.
Staffing (Including Management)
N/A 7.
Training and Qualification Effectiveness N/A 8.
Overall Rating Rating: Category 1