ML20054M289
| ML20054M289 | |
| Person / Time | |
|---|---|
| Issue date: | 03/23/1982 |
| From: | Felton J NRC OFFICE OF ADMINISTRATION (ADM) |
| To: | Hiatt S AFFILIATION NOT ASSIGNED |
| References | |
| FOIA-81-516 NUDOCS 8207120239 | |
| Download: ML20054M289 (1) | |
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8275 Munson Road IN RESPONSE REFER Mentor, OH 44060 TO FOIA-81-516
Dear Ms. Hiatt:
This is in further response to your letters dated December 22, 1981, and January 13, 1982, in which you requested pursuant to the Freedom of Information Act,13 different categories of documents which you listed in your letter.
The review of an additional document, which is subject to your request, has been completed.
The enclosed document is listed below:
SECY-81-582 "TMI Action Plan II.F.2 (NUREG-0737); Additional Instrumentation for Detection of Inadequate Core Cooling,"
October 7, 1981.
As specified in 10 CFR 9.14(b), the charge for reproducing the enclosed 29 pages at five cents ($0.05) per page is $1.45.
You are being charged in full for this document as it is not relevant to a contention admitted by the Atomic Safety and Licensing Board in the Perry proceedings.
You will be billed for this document by our Division of Accounting.
This completes NRC's action on your request.
Sincerely,
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Division of Rules and Records Office of Administration
Enclosure:
As stated 8207120239 820323 PDR FOIA HI ATT81-516 PDR
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October 7,1981 SECY-81-582 POLICY [SSUE For:
The Comis(i~ohemation Vote)
From:
William J. Dircks, Executive Director for Operations
Subject:
TMI Action Plan II.F.2 (fiUREG-0737); Additional Instrumentation for Detection of Inadequate Core Cooling
Purpose:
To inform the Commission of the staff's current position on the placement of thennocouples to monitor core cooling conditions for BWRs, and to provide a status report and recomendations concerning th'e implementation schedule for reactor vessel level instrumentation for PWRs.
Background:
BWR Core Thermocouples Regulatory Guide 1.97, revised in accord with the TMI Action Plan, states that thermocouples should be installed in BWRs to monitor the cooling conditions in the reactor core.
The ACRS, in August 1981 letters reporting on the review of the Fenni and Susquehanna reactors, recommended that the location of such thermo-couples be reevaluated.
The staff agrees and describes its approach for doing that, below.
PWR Reactor Vessel Water Level System Item II.F.2 of flVREG-0737 and the TMI Action Plan require implementation of reactor vessel level instru-mentation in PWRs.
The ACRS has expressed concern about the schedule required for implementation of this requirement beir.g too tight.
We have assessed the progress of industry in development and installation of these systems and recomend that the existing imple-mentation date of January 1982 be replaced. The earliest practical date by which these systems could be installed, calibrated, and operable at all operating PWRs is the first refueling after January 1,1983, for reasons discussed below.
Discussion:
Status of BWR Core Thermocouples The ACRS supported use of core thermocouples in BWRs in its letter of tiovember 10, 1980 to the tiRC Executive l
Director for Operations, but called attention to the need for further study to determine the appropriate vertical location of such thermocouples.
In the August 11, 1981 ACRS letters (reporting on Fenni 2 and
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. Susquehanna reviews) from ACRS Chairman J. C. Mark to NRC Chairman N. J. Palladino, the ACRS recommended that further study be given to placement of a small number of thermocouples in a more accessible location.
Regu-latory Guide 1.97 Revision 2, provides for inclusion of a minimum of four thermocouples in each BWR core quadrant but does not further specify the location of such thermocouples.
The staff did study the placement of thermocouples in BWRs in the process of formulating the requirements in Regulatory Guide 1.97.
Our study included our own calculations and those of consultants in addition to a review of General Electric Company studies and recom-mendations on the subject. We concluded that inclusion of ccre thermocouples, one in each of several Local Power Range Monitor (LPRM) assemblies, would provide operationally useful data about core cooling when the ECCS core spray is degraded. We also concluded that the vertical location of the thermocouples in the LPRM assemblies was not critical and that the location in LPRM assemblies used by GE in its analyses was the most practical.
Our evaluation is reported in the LaSalle SSER (NUREG-0519) and was called to the attention of ACRS in a memorandum from H. Denton to Chairman Mark (Enclosure 1) and in staff presentations during the ACRS review of Fermi 2.
However, we have no reason to disagree with the ACRS conclusion that placement of the thermocouples at another location may prove to be more practical and just as useful for accident diagnosis.
Therefore, in response to the ACRS recommendation for a reevaluation, we have prepared a letter for BWR appli-cants and licensees (Enclosure 2) requesting that they perform a study to confirm the most suitable location for thermocouples for their facility.
We will en-courage and expect to receive generic responses, perhaps for the various classes of BWRS.
We do not expect this to affect the June 1983 implementation date of Regulatory Guide 1.97.
Al though this approach will be responsive to the stated i'
concern of the ACRS, it will not completely resolve all controversy surrounding these thermocouples.
The BWR owners are expected to again appeal the need for the l
thermocouples to the ACRS in the near future.
3 L
Status of Reactor Vessel Water Level Measurement Systems for PWRs The purpose of a reactor water level measurement system is to provide the reactor operator with instrumentation to directly monitor water level in the reactor vessel and thereby the adequacy of core cooling so that he l
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I may implement actions to correct or avoid conditions of inadequate core cooling.
Instrumentation presently available in PWRs does not provide an unambiguous indication of availability of cooling capacity for the core.
At this time, additional instrumentation proposed by applicants and licensees includes three types of water level measurement (Enclosure 3):
(a) Westinghouse Reactor Vessel Level Instrumentation System (RVLIS),
(b) Combustion Engineering Heated Junction Thermocouple (HJTC) system, and (c) National Nuclear Corporation (NNC)/EPRI Neutron Detector system.
In addition, a modified differential pressure (dp) system which includes hot leg dp measurement to the top of the candy cane is under study by some B&W reactor applicants and licensees.
It is expected that the details of such a system will be submitted for review soon by B&W or one of the B&W reactor owners.
Westinghouse dp System The Westinghouse RVLIS utilizes two sets of three dp cells.
These cells measure the pressure drop from the bottom of the reactor vessel to the top of the vessel, and from the hot legs to the top of the vessel.
This dp measuring system utilizes cells of differing ranges to monitor different flow behaviors with and without pump operation.
The dp signal is processed and converted into the reactor water level.
When the reactor coolant pumps are not operating, the RVLIS reading will be indicated on the narrow range scale ranging from zero to the height of the vessel.
This reading represents the equivalent collapsed liquid level in the vessel.
When the reactor coolant pumps are operating, the RVLIS reading will be indicated on the wide range scale.
With the pumps running the RVLIS reading is an indication of the void fraction of the vessel water and steam mixture.
Upper range RVLIS is used for head venting operations during long term recovery.
The Westinghouse summary report, " Westinghouse RVLIS for Monitoring Inadequate Core Cooling (ICC) (7300 System), (UHI Plant), and (Microprocessor System)" was submitted in December 1980 and is under staff review.
The review includes results from a test program being performed at the Semiscale facility in Idaho.
Our review and the test program are consistent with the original plan (Enclosure 4) but are approximately one month behind at this time.
We expect to complete our generic evaluation, except for the analysis of the final performance test, by the end of 1981.
4 The Westinghouse dp system has been selected by licen-sees for use in eighteen reactors. We are told that twelve of these reactors will have the system installed prior to the current January 1, 1982 deadline in NUREG-0737.
The systems for Zion Units 1 and 2 are already installed.
Most of the operating license applicants who have selected the Westinghouse system expect to complete installation prior to power operation (Summer 1, McGuire 1 and Diablo Canyon).
Licensees have requested that installation be delayed until the first refueling outage for Sequoyah Units 1 and 2, North Anna 1 and 2, and Salem 2.
The staff concludes that those plants which have committed to install the Westinghouse dp system are
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substantially in compliance with the NUREG-0737 pro-vided that major technical problems are not encountered in proof tests of the system that affect its generic approval.
One problem attributed to an atypicality in the Semiscale test model has been encountered and is expected to be resolved by a final performance test to be performed in mid-November.
Evaluation of this additional test will delay the generic SER until January 1982.
In addition, a LOCA survivability test to evaluate the instrument performance after it has been subjected to large break blowdown conditions will be performed in February 1982.
However, this test is confirmatory in nature since the objective is to assure a correct interpretation of the instrument readout after such an event, and not necessarily to require l
continued operability as a design basis.
The results of the large break LOCA survivability tests and con-clusions on the post-LOCA interpretation of level instrumentation will be reported in conjunction with our review of calibration test data obtained from plant specific reviews.
In summary, installation of Westinghouse dp systems are expected to be completed on schedules ranging from the present to the first refueling after January 1,1982.
We believe that our generic review of the system will be substantially complete by the end of 1981 and that approval of plant specific installations for incorpo-(
ration into plant operating procedures can be completed I
on schedules ranging from mid-1982 to mid-1983, depending l
on the submittal schedules for final system descriptions l
and calibration data from individual plants.
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Combustion Engineering HJTC System The HJTC system measures reactor coolant liquid inven-tory with discrete HJTC sensors located at different levels within a separator tube ranging from the top of the core to the reactor vessel head.
The basic princi-ple of system operation is the detection of a temperature difference between adjacent heated and unheated thermo-couples.
In a fluid with relatively good heat transfer properties (e.g., water), the temperature difference between the adjacent thermocouples is very small.
In a fluid with relatively poor heat transfer properties (e.g., steam), the temperature difference between the thermocouples is large.
The separator tube provides for a steam-water interface at the collapsed liquid level and thermocouples at discrete axial levels within the tube indicate the presence of water at the measure-ment level.
The description of the Combustion Engineering (CE) HJTC system has been documented by individual users and is currently under staff review.
We have been in communica-tion with CE and with the CE Owners' Group in an effort to conduct the review generically.
The review i
of the initial submittal on the docket for San Onofre Units 2 and 3 (Amendment 23, February 1981, Docket flumbers 50-361/362) is one to two months behind the review schedule originally projected (Enclosure 4).
However, functional performance test data on the system have not yet been submitted even though the tests have been run and the vendor claims good results.
Performance tests on the production probe should be complete by the end of the year.
On this basis, we estimate that generic approval of the system can be completed near the end of the first quarter of 1982.
The installation of a HJTC system requires modification of incore instrument flange assemblies, containment penetration assemblies, and mineral insulated cabling.
For San Onofre, which is the lead plant using the HJTC system, the required plant modifications can not be completed prior to mid-1982, even though the HJTC probe assembly can be delivered during the first quarter, 1982 (Enclosure 5).
Southern California Edison has requested that the installation of the system be delayed until the first quarter,1983, during its first refueling shutdown.
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t Those plants that have selected the HJTC system (there are eight in total and several ordered the system as early as one year ago) cannot physically complete installation before the latter part of 1982, even though the probe assemblies may be available early in the year.
Therefore, plants committed to the CE system are not able to meet the current NUREG-0737 imple-mentation schedule.
We believe that all plants committed to this system will be able to complete installation on a schedule consistent with San Onofre, i.e., first refueling after January 1, 1983.
Staff review of individual installations and calibration data and approval for incorporation into emergency procedures will probably extend to mid-1984, depending on individual submittal schedules.
NNC/EPRI Neutron Detection System The principle used is the detection of photoneutrons from the reactor coolant system.
The ratio of the count rates from two sets of detectors (one set above and the other below the reactor vessel) provides an indication of reactor water level.
This system was proposed by Alabama Power Company for interim use and developmental testing on Farley Units 1 and 2.
Documentation of early experience with the system was provided in July 1981 and is currently under staff review.
We have requested that additional information be provided by October 1.
The system is still in the research and development stage and we are not optimistic that it will gain our approval.
The licensee projects that the system could become operable by mid-1983.
If the prospects for this system are not more favorable by early 1982, we will urge the licensee to select another system.
Vessel Level Systems to be Prooosed A vessel level system based on differential pressure measurements is currently being evaluated by B&W and B&W Owners.
We estimate that 1 to 2 years would be required to complete the design evaluation, procure-ment, and installation of such a system after completion of preliminary design.
Progress by licensees and OL applicants with B&W reactors has been uniformly poor.
The staff will not license a B&W reactor that does not show reasonable progress in this area.
We have taken a consistent position with TMI-1 for approval of restart.
In view of the good progress being made by others, we believe it is justified to require that B&W owners have their-systems installed and operable before restart following the first refueling outage after January 1,1983.
However, somewhat.later dates may be acceptable, as described in the Recommendation, below.
Recommendation:
It is recommended that the Commission allow the staff to delay the implementation schedule for PWR applicants and licensees for installation of the vessel level measurement system.
In the next two weeks, NRR will describe an approach for renegotiating practical implementation schedules for NUREG-0737 requirements for all operating reactors.
If the Commission endorses that approach, then this requirement for vessel level indicators in PWRs would be decided on a case by case basis.
The decision for each plant would be made in conjunction with decisions on the other TMI work remaining to be done on that plant and in full view of the equipment procurement and installation constraints described above.
As a general matter, we would expect the result to be that most of the level measurement systems would be installed before startup following the first refueling after January 1,1983.
I William J. Dircks Executive Director for Operations
Enclosures:
1.
Memo for Chairman Mark fm H. Denton, " Installation of Core Thermocouples in LaSalle."
2.
Draft ltr to BWR Applicants & Licensees.
3.
Information Report for Commissioners from W. J. Dircks, SECY-80-529.
4.
Staff Review Schedule for NUREG-0737 Section II.F.2.
5.
Figure 8-1 Earliest Possible ICC Installation Schedule - Songs 2.
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Commissioners' comments should be provided directly to the Office of the Secretary by c.o.b. Thursday, October 22, 1981.
Commission Staff Office comments, if any, should be submitted to the Commissioners NLT October 15, 1981, with an information copy to.the If the paper is of such a nature that it Office of the Secretary.
requires additional time for analytical review and comment, the Commissioners and the Secretariat should be apprised of when comments may be expected.
DISTRIBUTION Commissioners Commission Staff Offices Exec Dir for Operations Exec Legal Director ACRS ASLBP ASLAP Secretariat
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I ENCLOSURE 1
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MEMOPJuDUM FOP.:
J. Carson Mark, Chairman, ACRS l
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Harold R. Dentor, Director Office of tiuclear Reactor Regulation
SUBJECT:
It:STALLAT10ti 0F CORE THEF"0COU?LES Iti LaSALLE, In yeu-ietter cf April 16 to Chair. E.. Herdrie re;3rding LaSalle County Station Units I and 2, the Com ittee reco.nence: that a study of tr.e feasibility of the use of core outlet or core subassembly thermoccuples be completed prior to reaching a decision on the recuirement for the LaSalle plant.,
This is to call to your attention Section 18, item (3) of the LaSalle SER Supplement No.1, NUREG-0519, where we described the staff's study.
In addition, our report in response to the Cocenittee's recomendation i!,
included in Section 22, Item II.F.2, of the same document.
The staff concluded that the use of incore thermocouples in BWRs to provide diverse indication of water level and to monitor core cooling is feasi-ble.
We are requiring LaSalle and all 6ther BWR's to incorporate thennoccuples into the ICC monitoring system prior to June 1983 in accordance with Regulatory Guide 1.97.
In a related r.atter, your letter of June 9 to Mr. Dircks requested an early heeting of the staff with ACRS to discuss issues relating to Section II.F.2 of NUREG-0737.
We expect to have that meeting in September.
If the Conmittee has questions concerning our LaSalle report or our intent with other BWRs in this area, the staff will be prepared to discuss them at that meeting.
{) Q Harold R. Denton, Director Office of Nuclear Reactor Regulation l
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EllCLOSURE 2 4
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DRAFT ENCLOSURE 2 LETTER TO BWR APPLICANTS AND LICENSEES As you know, the staff has stated its intention to condition operating licenses for BWRs to require inclusion of thermocouples in the core.
Our evaluation of the placement of the core thermocouples is discussed in the LaSalle SSER (NUREG-0519) wnich concluded that location of one thermocouple in each of several LPRM assemblies (four per core quadrant) was a feasible and acceptable approach.
Based on the GE BWR Owners' Group appeal of this requirement in the August 6 ACRS review meeting on Fermi 2, the ACRS recommended that further study be given to placement of a small number of thermocouples in a more accessible location.
We request that you perform such a study and confirm that the LPRM assemblies l
j are the most suitable location or propose an alternate location and/or number of thermocouples to monitor inadequate core cooling.
If an l
alternative is proposed, provide an evaluation of the advantages and disadvantages of the recommended installation in terms of relative effectiveness to monitor the approach and existence of inadequate core cooling and in terms of the installation and maintenance costs in l
l dollars and occupational doses, including how these costs may be a l
l function of the required installation date now specified as June 1983 in Regulatory Guide 1.97.
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- 3. -39, 4 1933 c :. -.f W ASHINOTON, D. C. tc:5Is iNFORMATION REPORT FOR:
The Ccmissioners FRCM:
William J. Dircks, E2ecutive Director for Operatiens
SUBJECT:
TMI ACTION PLAN - II.F.2; ADDITIOML INSTRUMENTATION FOR MEASUREMEN' 0F C00LAhT LEVEL IN REACTOR VESSEL PURT.SE:
To provide the Ccmission with an afomation paper on the status of the technology fer reasuring reactor vessel water level.
BACMGROUND:
During the Octooer 28, 1980 Comission meeting regarding clarification of TMI Ac:. ion Plan requirements, the staff infomed the Cornission that it would prcvide an infomatien paper that would dist.uss the status of the technology for measuring reactor vessel water level and provide a basf s for its rectm. ended implementation schedule.
The attached document is provided in response to that ecmitment.
DISCUSSION:
The status of Instrumentation for Detection of Inadequate Core Cooling (ICC) was discussed at the LOFT / UTILITY Technology Transfer Meeting (LOFT Meeting) on October 16 and 17,1980 at Idaho Falls, Idaho. Presentations were made by NRC (NRR and RES), INEL, ORNL, Westinghouse, CE, EPRI and DAVC0 covering the NRC requirements and research program, the state of the art and current industry programs. A discussion following the session was conducted among the utilities, instrument suppif ers, reactor vendors, and NRC. The main concerns discussed at this meeting were:
Requirements of the TNI Action Plan Task II.F.2 Status of Current Industry Planning NRC research coordination NRC plan and action The enclosure to this paper provides details. The principal cencern expressed is that there has not been sufficient systems-level testing to demonstrate the acceptability of any device proposed to measure vessel level, and that the required imple-n::ntation date of January 1,1982 is thus in some jeopardy.
Centact:
T. Huang, NRR, 49-29420 L. phillips, tRR, 49-27140
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e The staff believes that further delay of the required implemen-tation of level measurement systems beyond January 1,1982 would i
' result in slower progress and may or may not result in better level measurement systems which would further enF.ance plant safety.
We therefore believe that the current schedule requirements (January 1,1981 for selection and documentation of the measure-j ment system and January 1,1982 for installation) should be maint ained.
However, we also believe that scne flexibility should be maintained to permit develcpment of improved systems where the specific documentation submittals include or subscribe
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to a viable deve'.opment and testing plan to prove the concept selected on reasonabie schedule.
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William Dircks Executive Director for Operations
'i Encl osure:
As stated
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TC E,LTLRMINE A LOGICAL __IMPLEMEhTATICh UATE FOR REACTCR VESSEL LEVEL IN5'TRUNEhTATION 1.
NRC Re uirements Before THI, hRC had no requirements for instrumentation for detection of inacequate core cooling.
Following the TMI accident, the Lessons Learned Task Force (NUREG-0578) and the Office of Nuclear Reactor Reg-ulation (the 1979 clarification letters) have established requirements for the instrumentation for detection of inadequate core cooling. As stated in hbREG-057b, Category A items shall be implemented prior to January 1,1980, and Category 5 items prior to January 1,1981.
(Cate-gory A: develop procedures and describe existing instrumentation; new instrument cesign, subcooling meter. installation, and implementation schedule.
Category B: complete new instrument installation.) This implementation schedule was described in the October'.19791ette*r from H. R. Denton (NRC) to All Operating Nuclear Pc er Plants and confirmed in NUREG-0660, "hRC Action Plan." Consistent implementation schedules for NT0Ls are required by NUREG-0694, "Thl-Related Requirements for New Operating Licenses."
However, based upon the staff's review of state-of-the-art, design progress, and the equipment procurement situation, the staff has recently proposed that the implementation schedule for reactor vessel level Category B requirements be rcscheduled to January 1,1982 and the documentation required for Category B should be reported by the licensee by January 1, 1981. This latest implementation schedule was described in a clarification letter dated October 31, 1980 to all Licensees of Operating Plants and Applicants for Operating Licenses and Holders of Construction Pernits. As indicated by the following discussion, even the revised schedule is in jeopardy.
2.
Status of Current Industry Planning Four types of systems for detection of Inadequate Core Cooling (ICC) were described in the LOFT /UnILITY Technology Transfer Meeting.
The instru-mentation described included the Westinghouse Differential Pressure
~ Neasurement of Reactor Yessel Water Level (Figure 1), the CE Heated Junction Thermocouple System (HJTC) (Figure 2), the EPRI sponsored Honinvasive Water Level heasurement Technique (Neutron Detectors) (Figure 3),
and the DAVC0 hicrowave Liquid Level Gauge for A High Radiation Environrent (Figure 4). Among those four systems three (excluding the DAVC0 system which is under developrent) have been ' currently proposed by utilites for use to neet NRC requirements.
The DAYC0 Microwave Liquid Level Gauge was deconstrated in the presentation and aroused considerable interest from the utilities, the research cou= unity and the NRC. However, 1t still needs an extensive research and developcent effort before it could be installed in an operating, reactor.
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i D2sec on the presentation in the r..ecting, it appears that each of the incustry g.roposed syster.s has inhercnt aovantages and disacrantages.
M:t.ever, none of the propesec systerns has been ceconstratec to be reliable uncer various simulated accident concitions which could challenge the valicity of the c.usurements.
It should be noted that some utilities, ruostly B&W owners, are taking the position that no additional ICC instrutnentation is neeced based on their analyses.
They rely primarily on the subcooling cionitor to detect the advent of ICC,anc on core exit thermocouples and hot leg RTDs to cetect the near advent and exist-ence of ICC.
They contend that existing level ueasurenent n.ethods do not meet all of the NRC design requirements. The staff has indicated in corres-pondence to Stk owner utilities (letter fron. D. Eisenhut dated September 29, 1980) that this position is unacceptabic to the staff. The early warning of the subcooling meter is arbiguous (nct necessarily loss of coolant); a reliable level measureuent system would enhance detection of the advent of ICC anc pro-vide prompt indication of the effectiveness of seasures to prevent or reccver from the condition.
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3.
I;RC P.esearch Coordination
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Eoth INEL and ORNL presented the status of developEent of instrumentation for detection of ICC during the LOFT F;eeting.
They have investigated the use of absolute temperature type thermocouples, heated junction type thenno-couples, a torsional ultrasonic level probc, etc. (see Table 1) and have perforced an analysis of the c.ethods censicered achievable for detection of ICC. The data obtained from these RES research programs are promising; however, the instrumentation systems need further development and testing to support design for installation in co=.ercial reactors. hRC/ DOE research facilities which can be made available for such testing include TNTF, SEMISCALE, and LOFT.
LOFT is an especially appropriate test bed for final integral
.I testing since it is a PWR with most of the test relevant characteristics of a concercial PWR, but includes extensive instrumentation systems not available on a corrercial PWR.
The instrumentation relevant to ICC ronitoring imcludes thermocouples at discrete levels above and within the core (including fuel clad thercoccuples), a conductivity probe for level monitoring, and ganna densitometers to indicate coolant quality conditions in the coolant piping.
The objectives of power plant instrurentation research sponsored by RES are (1) to provide proof of principle for selected conceptual designs, (2) to provide confirmatory test data on specific cc:mercial designs (3) to extend the instrumentation technology where appropriate, and (4) to pro-vide a technology transfer from research programs.
The research is to pro-vide developmental data relating to functional capability; the qualifica-tion testing of systems and components cust be perfor:ed by the industry.
In response to the ThI Task Action Plans I.D.5 and II.F.2, RES has been con-ducting work on possible liquid level measuring concepts.
In order to advance iGC licensing requirements, the facilities for reactor safety research such as LOFT, SEMISCALE, THTF and advanced instrucentation test facility, etc. will be used, under NRC research coordination, to test inoustry supplied prototype systems which are being considered for installation in operating reactors.
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The vendt.rs and RES will eeet ene establish tests neeces icr,he industry E
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preposed systems at sarious test facilities.
In scrne insu :es wLere tne. testing schedule at URC/ DOE facilitics does not support troduct develo ment on a sclefule consistent with the January 1,19?? installa-tion requirement, the supplier is planning to cerform essential cevelcr-ment testing at inaustry facilities.
Later testing at NRC/ DOE facilities would then be confirnatory in nature.
The status of propuse: test plans f ollows:
(1) The Westinghouse Reactor Vessel Level Instrumentation System (RVLIS) is being installed in the SEM15CALE facility.
Data will be taken during the upcoming test program planned for the last cuarter of CY 1980, and the testing is expected to be continued until the end of fiscal year 1981.
(2)
The CE Reactor Vessel Level Monitoring System (RVLMS) is in the final design stage; honever, CE's prototype has been tested in THTF at ORNL.
An additional test program at CE facilities is in progress.
Installa-tion of the CE system for testing in either the SEMISCALE or in the LOFT facility is being negotiated between RES and CE.
The first test may occur early in 1981 and the, program possibly concluded by the end of fiscal year 1981.
(3)
The EPRI sponsored NNC Neutron Detector (which is being installed for testing in Tarley 1 & 2) is being installed in the LOFT facility.
Installation is exrected to be completed in time for the L3-6 test in mid-December inSO, which includes partial core uncovery. Testing is expected to be completed by the end of FY 81.
(4) The DAVC0 Microwave Liquid Level Gauge is still in the development stage.
It has to be subjected to proof of principle testing in separate effects facilities, such as autoclaves, prior to an integral test in the LOFT or other facility.
To go through a prerequisite series of tests will take approximately six months to one year.
i DAVC0 has provided window materials to NRC for materials testing which is now in progress.
The prototype could then be installed I
in integral test facilities for tests which may be concluded by the end of the fiscal year 1982.
Potential industry sponsors of this system indicate that an effort will be made to cmplete the development at an ear 1fer date.
(5) The torsional ultrasonic probe (Figure 5) is still in the research and development state and has no comercici sponsors.
However, the probe is available and can be tested and improved.
The test may be performed in the early part of 19S1 and could be concluded by the end of the fiscal l
year 1981.
1 I
4 NRC Plan and Action None of the instrurentation systems proposed by the industry to date have been tested under simulated reactor operating conditions to substantiate functional reliability and accuracy, l
3 l
l 1
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I The utility representatives who attended the LOFT ceeting have requested that the II.F.2 implementation dates be extended to allow completion of instrument developnent programs before a system must be selected for pro-They have expressed the concern that systems procured prior to curement.
the completion of development at.d testing may prove to be unacceptable ~ to NRC, and would result in unnecessary expense.
The staff is of the opinion that existing technology provides reasonable confidence that a DP measurement system, comparable to the Westinghouse system, can enhance the quality of ICC monitoring systems.
Additional analyses and testing of existing systems are required to identify any situations where erroneous measurements may be indicated and to provide for data processing which identifies and negates or alarms such erroneous indications if they should Also, the staff may need to reconsider the advisability of some occ ur.
requirements (e.g., level measurement with pumps running) based on the analyses and test results.
- 'e believe that heated thermocouple systems and absolate temperature type thernoccuple systems monitoring deviation from saturation at discrete axial locations can be provided with only slightly less confidence in their ultimate acceptability. Other systems promise potential advantage in t;mplicity and possibly in reliability but have greater risks with respect to developrent schedule and ultimate acceptability.
The staff believes that further delay of the required implementation of level easurement systems beyond January 1,1982 would result in slower progress and may or may not result in better level measurement systems which would further enhance plant safety.
We therefore believe that the current schedule requirements (January 1, 1931 for selection and documentation of the measurement system and January 1,19E(
for installation) should be maintained.
However, we also believe that some flexibility should be maintained to permit development of improved systems where the specific documentation submittals include or subscribe to a viable development and testing plan to prove the concept selected on reasonable schedule.
The burden to arrange for appropriate test programs and to provide the selected systems for testing will be on the industry.
NRC will cooperate by making NRC/
)DE facilities available for testing and by evaluating the acceptability of same instrumentation concepts by the end of C181.
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LOFT early 1981 l
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& development problems 1
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LOFT late indication
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system design 1981 3
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ENCLOSURE 4 f
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STAFF REVIEW SCHEDULE FOR 11UREG-0737 SECTI0ti II.F. 2 Iten N2./
Tlt1e Appite.
Type byle.cnt Licensee Sulait Staf f SER Cos.,en ts
_HPDis1._
9 II.F.2 Instrumentattori for inade.
All
- Prefwlecentation review fc (NP F 46) quate Core Conting generic design and postfwl rentation review for plant 1 Licensee sutelttal: design 01/01/81 specific Installation, description and supporting analysis.
2 Staff: develop generic Cosplete positions / questions.
3 Staff: transmit positions /
Corplete questions to Ifcensees 4 Licensee sutalttal: rtspon-09/U1/81 se to questions / positions 5 Generic SERs and Model TS -..
12/01/81 (Installation 01/01/82 7 Lf censee sutalttal: qual-03/01/82 Ification of system for opera tion 3 Staf f: Issue plant spec-05/01/82
/
ific approval and TS 1 Staff: 1ssue plant spec-07/01/82 c
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Decomucr LU, 13U1 Director, Orrice of Administration EREEDOM OF INFORMATION U.S. Huclear neculatory Conaission ACT REQUEST
.asnington, D.C.
20555 FO.LA-P/-3 4 de: FREED 0T! 0F INFOR'.% TION ACT REQUEST ac 'd D-W2/
Dear bir/I's.,
Pursuant to tne Freedou of Information Act, 5 U.S.C.
3cction 552, as amended, and the provisions of 10 CPh Part 9, the under-signcd hereby requests the following items:
1.
uny studies or documents concerning the susceptibility of boiling water rcactor pressure vessels to the prcs-surised tnermal shock phenomenon identified in PJ:ts.
C.
Co.. mission de cision of Junc 29 1981, CLI-81-?, 7 ?THC ?,
(exact citation unknown), Duke Power Company (William B. McCulre Nuclear Station, Units 1 and 2).
3.
SLCY-80-107
" Proposed Interim lydrogen Control Require-ments for Small Containments" i
4.
SECY-80-107l'
" Additional Information he : Proposed Interim tiydrogen Control Hequircments" 5.
SLCY-81-245
" Interim Amendment to 10 CFR Part 50 helated to dydrogen Control and Certain Degraded Core Considerations" 6.
,iunEG-0772
" Technical Buses for Estimating Fission Product
. thavior During Light.Vatcr Heactor Accidents"
?Jurch 1981 7.
NUhEG-0465 "A Transportation Security Personnel Training Il.unu al" (latest edition) 8.
SECY-60-409, Sept.
4, 1980, and SECY-80-400C, Nov.
7, 1980.
Proposed rulemaking on ATl/S.
9.
!uc cranen Technical Position CSE6-2, " Control of Com-bustible Las Concentrations in Containment Following a LOCA" 10.
.UhLC/Cn-0313 "Gcncration of.iydroten Durin; tnc First T.u ce.iours of the Tnree Mile Island Accident" Oct. 1979 11.
WJdC/Cli-lSGl "The Benavior of.iydrogen Luring Accidcnts in Light Water Reactors" Oct. 19EO 12.
!rJREC/Cd-1575
":lydrogen ".1xing in a Closed Containment Compartment Eased on a Ont-Dimensional *odel" Sept. 1920 13.
any docu:lents concerning tne usc of in-core t.nrmocouplcs i n E ll.t s, particularly in
.ls/6 rcactors.
A//W 0 206c20G5 f
. 'L a.... c :1u c s ', p.
2 i
This reque ster asks tnat fees for tut scarch and production of the aoove documents be waived, in accordance with 10 C?h 9.14a, for t.lc following reasons:
1.
This infort:.ation will bc disseminated to the central public through newsletters, press relcases, and other media; tne "public" 'ocncriting thereby icelades but is i
not limited to tae population of..ortheast uhio.
2.
By tne availability of tnis information thc public will ue better informed on nuclcar safety issues and this will tacecrorc enhance tne quality of public debate on tnesc issucs.
Puolic acbate on tatso mattces crucial i
to puolic ncalth and safety and tne quality of the environ-ment is impcrutivc.
3.
Tais information will be uscd in c proceedinr currcntly before tne Ato: ale Safety and Licensing Board: In the j
Uatter of Cleveland Electric Illuminatin[; Co., g cl.,
Perry /441.
Huclear Powcr Plant, Jnits 1 and 2, Docket dos.
50-440 Upon this requestcr's review and analysis of tac rcquested documents, they will bc uscd by intcr-venors in this casc; thesc intervencrs villl thereby bc l
cettcr nble to protect tncir nealth, safcty, and cnviron-l mental interests (and those of thc gcncral public) in cnis proceeding.
4.
Tnis requt. ster cxpects no financial bcncrit from t ne use of tjust-documents.
5.
Tnc financial rcsourocr of this requestcr arc limited; tnus, t he payment of fees incurred ncrcin ciould result in an unduc ha r ds hip.
These factors clearly indicate
- nu t furnishing the documents reqausted nercin cill ocnefit the jeneral public, and therefore t he wai ve r o f am,.
and all recs for scarch and production is appropriatc.
Tnunk ycu ft.
o.
.i t a. a.
Lir et ?cly,
/W.
- e. o. r., x. A -. c Susan L.
- ila t t LO76 '
- unscn..u.
- .:c n t or, 0:1 4 /.09?
. __-_.