ML18052A746
| ML18052A746 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 10/20/1986 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Wambach T Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML18052A747 | List: |
| References | |
| TAC-45156, NUDOCS 8610270422 | |
| Download: ML18052A746 (10) | |
Text
Docket No.:
50-255 October 20, 1986 MEMORANDUM FOR:
FROM:
SUBJECT:
Thomas V. Wambach, Senior Project Manager PWR Project Directorate #8 Division of PWR Licensing-B Dennis M. Crutchfield, Assistant Director Division of PWR Licensing-B EVALUATION OF CONSUMERS POWER COMPANY'S PROPOSED INADEQUATE CORE COOLING INSTRUMENTATION SYSTEM FOR PALISADES (TAC# 45156)
The Reactor Systems Branch has reviewed Consumers Power Company's (CPC)
June 11, 1986 submittal on its inadequate core cooling instrumentation system for the Palisades plant and has found that CPC's approach to a reactor vessel level monitoring system based on RADCAL gamma thermometer probes is acceptable.
However, the staff requires that CPC provides the implementation letter report described in Enclosure 3 so that the staff can complete its implementation review of the installed inadequate core cooling instrumentation system.
The enclosed safety evaluation reports (SERs) (Enclosure 1 proprietary version, Enclosure 2 non-proprietary version) presents ffie *results of the staff's review.
The SERs include significant input prepared by the
- staff's consultants at Oak Ridge National Laboratory (ORNL) under Tech-nical assistance contract FIN B-0779.
Please forward the enclosed SERs to CPC and request that they initiate the necessary actions to implement its inadequate core cooling instrumentation system and that a schedule for response to Enclosure 3 be provided.
The staff has prepared information (Enclosure 4) for a SALP review.
Original signed by Dennis M. Crutchfield, Assistant Director Division of PWR Licensing-B
Enclosures:
As stated cc:
A. Thadani R. Karsch DI STR I BUTI ON.w/_o_Jlf.~Jclsure**11 C.Centr:aLJ:iJ e RSB File--or; eno NLauben CThomas DCrutchfield ENCLOSURE(S) CONTAIN(S) 10 CFR 2.790 MATERIAL. DECONTROLLED WHEN SEPARATED FROM ENCLOSURES.
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Docket No.:
50-255 MEMORANDUM FOR:
FROM:
SUBJECT:
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 October 20, 1986 Thomas V. Wambach, Senior Project Manager PWR Project Directorate #8 Division of PWR Licensing-B Dennis M. Crutchfield, Assistant Director Division of PWR Licensing-B EVALUATION OF CONSUMERS POWER. COMPANY'S PROPOSED INADEQUATE CORE COOLING 1NSTRUMENTATION SYSTEM FOR PALISADES* (TAC# 45156)
The Reactor Systems Branch has reviewed Consumers Power Company's (CPC)
June 11, 1986 submittal on its inadequate core cooling instrumentation system ftir the Palisades plant and has found that CPC's approach to a reactor vessel level monitoring system based on RADCAL gamma thermometer probes is acceptable. However, the staff requires that CPC provides the implementation letter report described in Enclosure 3 so that the staff can complete its implementation review of the installed inadequate core coo 1 ing instrumentation system. --
The enclosed safety evaluation reports (SERs) (Enclosure 1 proprietary version, Enclosure 2 non-proprietary version) presents the results of the staff's review.
The SERs include significant input prepared by the staff's consultants at Oak Ridge National Laboratory (ORNL) under Tech-nical assistance contract FIN B-0779.
- Please forward the enclosed SERs to CPC and request that they initiate the necessary actions. to implement its inadequate core cooling instrumentation system and that a schedule for response to Enclosure 3 be provided.
The staff has prepared information (Enclosure 4) for a SALP review.
Enclosures:
As stated cc:
A. Thadani R. Karsch CONTACT:
D. Fieno, RSB/DPLB x27742
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D~rutchfield, A istant Director Division of P~R Licensi -a
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ENCLOSURE(S) CONTAIN(S) 10 CFR 2.790 MATERIAL.
DECONTROLLED WHEN SEPARATED FROM ENCLOSURES.
PROPRIRll!
"\\
NONPROPRIETARY VERSION e
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 Cpmpany (CPC) has.proposed a system for detecting and monitoring inadequate cor~ cooli~g (ICC) conditions for the Palisades plant. The system includes a subcooling marQin 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 (ORNL) under technical assistance contract FIN B-0779.
This review incl~des informat.ion 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'~
evaluation follows.
2.0 EVALUATION 2.1 Reactor Inventory Measurement (RIM) System
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- PDR._.i_J' NONPROPRIETB_RY 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 slgnals from each probe ~re 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 locat~d 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 seismicall~
qualified from sensorto display. The system has two redundant, inde-pendent channels which are physically separated for.their entire length.
Both channels are fed from separate 120 volt ac, class lE power sources.
Indication and recording is continuous on the display panel. Primary display for CET information is the CFMS which provides all the required CET display attributes, including a core map.
Isolation devices at the CFMS computer inputs are easily accessible for maintenance during accident conditions.
,, 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-range 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 iimited 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 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.
- 3. 0 CONCLUSIONS The staff concludes that the Consumers Power Company's ICC! 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 requiremen~s 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 Onofr~ 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).
... 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 from D. 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 Junctioh Thermocouples For Reactor Vessel Level Measurement,"
NUREG/CR-2627, March 1982, (prepared by Oak Ridge National Laboratory}.
- 10.. "Surmnary 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, (Attachment to Reference 8).
- 11.
Letter dated September 25, 1986 from J. L. Kuemin {CPC) to Director, NRR.
- 12.
"Clarification of TMI Action Plan Requirements, 11 NUREG-0737, November 1980.
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4 *.
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- 6.
- 7.
ENCLOSURE 3 MILESTONES FOR IMPLEMENTATION Of INADEQUATE CORE COOLING INSTRUMENTATION Submit final design description-(by licensee) (complete the docu-mentation requirements of NUREG-0737, Item II.F.2, including all p1ent-spec1fic 1nfonnat1on items identified fn applicable NRC evaluation reports for generic approved systems).
Approval of emergency operating procedure (EOP) technical guidelines -
{by NRC).
Note: This EOP technical guideline which incorporates the selected system must be based on the intended uses of that system as described in approved generic EOP technical guidelines relevant to the selected system.
Inventory Tracking Systems (ITS) installation complete (by licensee).-
- ITS functional testing end calibration complete (by licensee}.
Prepare revisions to plant operating procedures end emer~ncy procedures based on approved EOP guidelines (by licensee).
Implementation letter* report to NRC (by licensee).
Perfonn procedure walk-t~rough to complete task analysis portion of I CC *system des 1 gn (by 1i censee}.
- 8.
- Turn on system for operator treining and familiarization.
- 9.
Approval of plant-specific 1nsta1 let ion (by NRC).
- 10.
Implement modified operating procedures end emergency procedures (f>y 1 icensee).
- System Fully Operational -
- Implementation Letter Report Content (1) *Notification that the system 1nsta11ation, functional testing, end calibration fs complete end tett results are available for in-spection.
(2) Sunmery of licensee conclusions based on test results, e.* g.:
{a) the system perfonns in accordance with design expectations and within design error tolerances; or (b) description of deviations from design perfonnance 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)
(5)
(6)
Request for modification of Technical Specifications to include ell ICC 1nstrunen~t1on for accident nt>n1tor1ng.
Request for HRC 1pproval of the plant-specific 1nsta1lation.
Confinn thet the [O~ used for operator tTa1ning w111 confonn to*
the technical content of HRC approved EOP guidelines (generic or plant specific).
ENCLOSURE 4
. 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 Cons_umers Power (CPC) were of high quality and indicate CPC management involvement in assuring high quality technica.l information~
Rating: Category 1
- 2.
Approach to Resolution of Technical lssues 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