ML19350B669
| ML19350B669 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 03/16/1981 |
| From: | Novak T Office of Nuclear Reactor Regulation |
| To: | Cavanaugh W ARKANSAS POWER & LIGHT CO. |
| References | |
| NUDOCS 8103230245 | |
| Download: ML19350B669 (29) | |
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,.~,.'o, UNITED STATES
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I 75,. < (i NUCLEAR REGULATORY COMMISSION
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W ASHINGTON, D. C. 20555 9.b4'[j/
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March 16, 1981
"i Docket No. 50- 313 D!
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,N Mr. William Cavanaugh, III p
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b i-Vice President, Generation u
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',,, % ' % ort and Construction B
Arkansas Power & Light Company A
P. O. Box 551 s9 Little Rock, Arkansas 72203 V
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Dear Mr. Cavanaugh:
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SUBJECT:
ENVIRON" ENTAL QUALIFICATION OF SAFETY-RELATED ELECTRICAL EQUIPMENT RE: ARKAtlSAS tiUCLEAR ONE, UtlIT N0.1, FACILITY OPERATItiG LICE ltSE fl0. DPR-51 l
Reference:
Order for Modification of License Concerning the Environmental l
Qualification of Safety-Related Electrical Equipment, October 24, 1980.
1 This letter transmits the preliminary results of our review of environmental qualifications of safety-related electrical equipment at your facility.
This evaluation was based on your submittaia received over the past months.
The facility license was modified by the referenced Order of October 24, 1980, to require that all safety-related electrical equipment be qualified to specified requirements not later than June 30, 1982.
In addition, the Order noted that a licensee is obligated to modify or replace inadequate equipment promptly.
The staff's review of your submittals has resulted in our identifying a number of potential equipment deficiencies involving a lack of proper documentation, inadequate justification of assumed environmental conditions following an accident, and/or inadequate environmental testing of equipment, such that conformance to the 00R guidelines, as required by the Order, s I
cannot be demonstrated. You are requested to review our identified defi-ciencies, and their ramifications, and provide us your overall finding regarding continued safe operation of your facility. Accordingly, in orde'
- to detennine whether your license should be modified or suspended, you are l
required pursuant to 10 CFR 50.54(f), to provide within 10 days of receipt of this letter, a written statement, signed under oath or affirmation sup-porting the safe operation of your facility, that takes into account the NRC staff's preliminary list of deficiencies.
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The purpose of this statement is to provide the NRC with needed assurance, by the licensee, regarding the continued safety of the facility until you can provide an item-by-item reevaluation in a detailed documented manner at a later date. A negative finding on your part concerning the safety of continued operation would result in a unit shutdown, and should be reported as a Licensee Event Report (LER) within twenty-four (24) hours of the deter-mination to the appropriate NRC Regional Office. Include in the LER the actions you have taken for the immediate resolution of the matter. A copy of any such LER should be sent to the Director, Division of Licensing, Office of Nuclear Reactor Regulation.
Please submit a copy of your reply to us via telecopy.
Sincerely, 4^ 7.T Thomas M. Novak, Assistant Director for Operating Reactors Division of Licensing
Enclosure:
l Evaluation Report l
cc w/ enclosure:
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See next page l
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Arkansas Power & Light Comparf cc w/ enclosure (s):
Mr. David f.. Trimble Manager, L':ensing Arkansas Power & Light Company P. O. Box 551 Director, Bureau of Environmental Little Rock, Arkansas 72203 Health Services 4815 West Markham Street Mr. James P. O'Hanlon Little Rock, Arkansas 72201 General Manager Arkansas Nuclear One P. O. Box 608 Russellville, Arkansas 72801 Mr. William Johnson U.S. Nuclear Regulatory Commission P. O. Box 2090 Russellville, Arkansas 72801 Mr. Robert B. Borsum Babcock & Wilcox Nuclear Power Generation Division Suite 420, 7735 Old Georgetow1 Road Bethesda, Maryland '?0014 Mr. Nicholas S. Pcynolds Debevoise & tioerman 120017th Street, NU Washington, DC 20036 Arkansas Tech University Russellville, Arkansas 72801
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Honorable Ermil Grant Acting County Judge of Pope County Pope County Courthouse Russellville, Arkansas 72801 Mr. Paul F. Levy, Director Arkansas Department of Energy l
3000 Kavanaugh Little Rock, Arkansas 72205 Director, Criteria and Standards Division l
Office of Radiation Programs (ANR-460) s U. S. Environmental Protection Agency Washington, D. C.
20460 l
U. S. Environmen+.al Protection Agency Region VI Office ATTN: EIS COORDINATOR 1201 Elm Street First International Building Dallas, Texas 75270 g
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PARTIAL EQUIPMENT EVALUATION REPORT BY THE OFFICE OF NUCLEAR REACTOR REGULATION FOR ARKANSAS POWER A'!O LIGHT CGMPANY ARKANSAS NUCLEAR GNE - UNIT 1 DOCKET NO. 50-313 3 STAFF EQUIPMENT EVALUATION The staff evaluation of the licensee's response Scluded an onsite inspection of selected Class IE equipment and an examination of Oe licensee's report for completeness and acceptability.
The criteria described in the 00R guidelines and in NUREG-0588, in part, were used as a basis for the staff evaluation of the adequacy of the licensee's qualification program.
The NRC Office of Inspection and Enforcement performed a preliminary evaluation of the licensee's response, documented in a technical evaluation report (TER).
An onsite verification inspection of equipment in the reactor building spray and core flood system will be performed during the week of February 15, 1981.
This inspection will be performed to verify proper installation of equipment, overall interface integrity, and manufacturers' nameplate data. The manu-facturer's name and model number from the nameplate data will be compared to information given in the Component Evaluation Work Sheets (CES) of the lice 7-see's report.
Results of the site inspection will be documented in an IE report. For this review, the licensee's October 31, 1980 submittal and the TER referenced above have been factored into the overall staff evaluation.
3.1 Comoleteness of Safety-Related Eouioment In accordance with IES79-01B, the licensee was directed to (1) establish a list of systems and equipment that are required to mitigate a LOCA and an HELB and (2) identify components needed to perform the function of safety-related display information, post-accident sampling and monitoring, and raciation monitoring.
The staff developed a generic master list based upon a review of plant safety l
analyses and emergency procedures. The instrumentation selected includes i
parameters to monitor overall plant performance as well as to monitor the per-formance of the systems on the list. The systems list was established on the basis of the functions that must be performed for accident mitigation (without r
regard to location of equipment relative to hostile environments).
The list of safety-related systems provided by the licensee was reviewed ag. inst the staff-developed master list.
Based upon information in the licensee's submittal, the equipment location references, and in some cases subsequent conversations with the licensee, the staff has verified and determined that the systems included in the licensee's submittal are those required to achieve or support:
(1) emergency reactor shutdown, (2) containment isolation, (3) reactor core cooling, (4) containment heat removal, (5) core residual heat removal, and (6) prevention of signifi-cant release of radioactive material to the environment.
The staff therefore
concludes that the systems identified by the licensee (listed in Apoendix 0) are acceptable, with the exception of those items discussed in Section 5 of this report.
Display instrumentation which provides information for the reactor operators to aid them in the safe handling of the plant was not specifically identified by the licensee. A complete list of all display instrumentation mentioned in the LOCA and HELB emergency procedures must be provided.
Equipment qualifi-cation information in the form of summary sheets should be provided for all components of the display instrumentation exposed to harsh environments.
Instrumentation whie is not considered to be safety related but which is mentioned in the emergency procedure should appear on the list.
For these instr 5ments, (1) justification should be provided for not considering the instrument safety related and (2) assurance should be provided that its subseq'Jent failure will not mislead the operator or adversely affect the mitigation of the consequences of the accident. The environmes.tal qualifi-cation of post-accident sampling and monitoring and radiation monitoring equipment is clcsely related to the review of the TMI Lessons-Learned modifications and will be performed in conjunction with that review.
The licensee identified 322 items of equipment which were assessed by the staff. Many component work sheets, ha ever, do not indicate the manufacturer's name or model number.
Some do not indicate whether the component is above or below the flood level, and many limit switches are not listed separately. The licensee should revise the CES accordingly and bring to the staff's attention any additional equipment subject to submergence which is not included in Appendix B to this ER (with the exception of Rotork valve motor operators CV-1050 and CV-4446).
3.2 Service Conditions Commission Memorandum and Order CLI-80-21 requires tlat the 00R guidelines and 1
the "For Comment" NUREG-0588 are to be used as the criteria for establishing the adequacy of the safety-related electrical equipmen' environmental quali-fication program. These documents provide the option,of establishing a bounding pressure and temperature condition based on plant-specific analysis identified in the licensee's Final Safety Analysis Report (FSAR) or based on generic profiles using the methods identified in these documents.
On this basis, the r.aff has assumed, unless otherwise noted, that the analysis for developing the anvironment:1 envelopes for Arkansas Nuclear One - Unit 1, relative to the f.:mperature, pressure, and the containment spray caustics, has been perform 9 in accordance with the requirements stated above. Tha staff has reviewed tne qualification documentation to ensure that the qualification specifications envelope the conditions established by the licensee. During this review, the staff assumed that for plants designed and equipped with an automatic containment spray system which satisfies the single-failure cri-terion, the main-steam-line-break (MSLB) env1.Nnmental conditions are enveloped l
by the large-break-LOCA environmental conditions. The staff assumed, and l
requires the licensee to verify, that the containment spray system is not subjected to a disabling single-coepenent failure and therefore satisfies the requirements of Section 4.2.1 of the 00R guidelines.
Equipment sucmergence has also been addressed where.he possibility exists that flooding of equipment may result from HEL8s.
3.3 Temaerature. Pressure, and Humidity Conditions Inside Containment The licensee has provided the results of accident analyses as follows:
Max Temo ( F)
Max Press (osic)
Humidity (%)
LOCA 280 53.82 100 The staff nas cor41uded that the minimum temperature profile for equipment qualification purposes should include a margin to account for higher-than-average temperatures in the upper regions of the containment that can exist due to stratification, especially following a postulated MSLB.
Use of the steam saturation temperature corresponding to the total building pressure (partial pressure of steam plus partial pressure of air) versus time will provide an acceptable margin for either a postulated LOCA or MSLS, whichever is controlling, as to potential adverse environmental effects on equipment.
The licensee's specified temperature (service condition) af 280 F does not satisfy the above requirement. A saturation temperature c u responding to the peak profile (30l*F peak temperature at 53.82 psig) should be used instead.
The licensee should update his equipment summary taoles to reflect this change.
If there is any equipment that does not meet the staff position, the licensee must provide either justification tnat the equipment will perform its intended function under the specified conditions or propose corrective action.
3.4 Temoerature. Pressure, and Humidity Conditions Outsice Containment The licensee has provided, on the compenent work sheets, the temoerature, pressure, humidity and applicaole environment associated with HEL3s outside containment. However, the licensee should provide more explicit information relative to (1) the areas in the auxiliary building where the breaks are postulated, (2) in which piping systems the breaks are postulated to occur, and (3) the temperature and pressure as ociated with the postulated breaks.
The staff will verify the adequacy of tne 11censee's specified environment outside containment when the above information has been submitted.
3.5 Submergence The maximum submergence levels have been established and assessed by the licensee.
Unless otherwise noted, the staff assumed for this review that the methodology employed by the licensee is in accordance with the appropriate criteria as established by Commission Memorandum and Order CLI-80-21.
The licensee's value for the maximum Jubmergence level is elevation 345 ft.
Equipment below this level has been identified by the licensee. The licensee identified seven safety-related electrical components--four Limitorque and two Rotork motor operated valves, and Okonite cable--as having the potential for becoming submerged after a postulated event.
The Rotork motor operated valves have been qualified for submergence; the licensee states that the Limitorque motor operated valves perform their function before becoming submerged.
In these cases, the licensee should provide an assessment of the failure modes associated with the submergence of the Limitorque motor operated valves and associated cable.
The licensee should also provide assurance that the subsequent failure of these components will not adversely affect any other safety functions or mislead an operator. Additionally, the licensee should discuss operating time, across the spectrum of events, in relatic, to the time of submergence.
If the results of the licensee's assessment ne acceptable, then the components may be exempt from the submergence parameter of qualification.
3.6 Chemical Soray The licensee's FSAR value for the chemical concentration is 2270 ppm boric acid solution. However, the licensee has not provided the specified pH or the exact chemical concentration and pH of the qualific-ition environment.
Therefore, for the purpose of this review, the effects of chemical spray will be considered unresolved. The staff will review the licensee's response when it is submitted and discuss the resolution in a supplemental report.
3.7 Aging Section 7 of the 00R guidelines does not require a qualified life to be estab-lished for all safety-related electrical equipment.
However, the following actions are required:
(1) Make a detailed comparison of existing equipment and the materials identi-fied in Appendix C of ':ba D0R guidelines. The first supplement to IEB-79-018 requires licsnsees to utilize the table in Appendix C and identify any additional iterials as the result of their effort.
(2) Establish an ongoing progt m to review surveillance and maintenance records to identify potent.1 age-related degradations.
(3) Establish component maintenance and replacement schedules which include considerations of aging characteristics of the installed components.
The licensee identified a number of equipment items for which a specified qualified life was established (for examples, 5 years, 15 years, or 40 years).
In its assessment of these submittals, the staff did not review the adequacy of the methodology nor the basis used to arrive at these values; the staff has assrmed that the established values are based on state-of-the-art technology and are acceptable.
For this review, however, the staff requires that the licensee submit supple-mental information to verify and identify the degree of conformance to the above requirements. Thermal and radiation aging should be addressed in the licensee's response. The response should include all the equipment identified as required to maintain functional operability in harsh environments.
The licensee indicated that this phase of the response is outstanding and that the review is in progress. The staff will review the licensee's response when it is submitted and discuss its evaluation in a supplemental report.._.
3.8 Radiation (Inside and Outside Containment)
The licensee has provided values for the radiation levels postulated to exist following a LOCA.
The application and methodology employed to determine these values were presented to the licensee as part of the NRC staff criteria con-tained in the 00R guidelines, in NUREG-0588, and in the guidance provided in IEB-79-OlB, Supplement 2.
Therefore, for this review, the staff has assumed that, unless otherwise noted, the values provided have been determined in accordance with the prescribed criteria.
The staff review determined that the values to which equipment vis qualified enveloped the requirements identified by the licensee.
The value required by the licensee inside containment is an integrated dose ranging between 8.5 x 108 and 3 x 107 rads gamma and 1.1 x 10s rads beta.
These values envelope the 00R guideline requirements and are therefore acceptable.
A required value outside containment of 6 x 108 rads has been used by the licensee to specify limiting radiation levels within room 10 of the auxiliary building.
This value considers the radiation levels influenced by the source term methodology associated with post-LOCA recirculation fluid lines and is acceptable.
4 QUALIFICATION OF EQUIPMENT The following subsections present the staff's assessment, based on the licensee's submittal, of the qualification status of safety-related electrical equipment.
The staff has separated the safety-related equipment into three categories:
(1) equipment requiring immediate corrective action, (2) equipment requiring additional qualification information and/or corrective action, and (3) equip-ment considered acceptable if the stafi i concern identified in Section 3.7 is satisfactorily resolved.
In its assessment of the licensee's submittal, the NRC staff did not review the methodology employed to determine the values established by the licensee.
However, in reviewing the data sheets, the staff made a determina+. ion as to the stated conditions presented by the licensee. Additionally, the staff has not completed its review cf supporting documentation referenced by the licen-see (for example, test reports).
It is expected that when the review of test reports is complete, the environmental qualification data bank established by the staff will provide the means to cross reference each supporting document to the referencing licensee.
If supporting doc'iments are found to be unacceptable, the licensea will be required to take additional corrective actions to either establisn qualifi-cation or replace the item (s) of concern. This effort will begin in early 1981.
An appendix for each subsection of this report provides a list of equipment for wiiich additional information and/or corrective action is required. Where appropriate, a reference is provided in the appendices to identify deficiencies.
It should be noted, as in t'ae Commission Memorandum and Order, that the deficien-cies identified do not necessarily mean that equipment is unqualified.
- However, they are cause for concern and may require furtaer case-by-case eva;;ation.
T 4.1 Eauioment Reauiring Immediate Corrective Action 4.2 Equioment Reauiring Additional Information and/or Corrective Action Appendix B identifies equipment in this category, including a tabulation of deficiencies.
The deficiencies are noted by a letter relating to the legend (iden1.ified below), indicating that the information provided is not sufficient for tte qualification parameter or condition.
Lpgend R
- radiation T
- temperature QT qualification time RT - required time P
pressure H
- humidity CS chemical spray A
- material-aging evaluation; replacement schedule; ongoing equipment surveillance 5
submergence M
- margin I
- HELB evaluation outside containment not completed QM qualification method RPN equipment relocation or replacement; adequate schedule not provided EXN exempted equipment justification inadequate SEN - separate-effects qualification justification inadequate QI qualification information being developed RPS equipment relocation or replacement schedule provided As noted in Section 4, these deficiencies do not necessarily mean that the equipment is unqualified. However, the deficiencies are cause for concern and l
require further case-by-case evaluation.
The staff has determined that an acceptable basis to exempt equipment from qualification, in whole or part, can be established provided the following can be established and verified by the licensee:
(1) Equipment does not perform essential safety functions in the harsh environ-l ment, and equipment failure in the harsh environment will not impact l
safety-related functions or mislead an operator.
r (2a) Equipment performs its function before its exposure tn the harsh environ-ment, and the adequacy for the time margin provided is adequately justified, l-and i L
(2b) Subsequent failure of the equipment as a result of the harsh environment does not degrade other safety functions or mislead the operator.
(3) The safety-related function can be accomplished by some other designated equipment that has been adequately qualified and satisfies the single-failure criterion.
(4) Equipment will not be subjected to a harsh environment as a result of the postulated accident.
The licensee is, therefore, required to cupplement the information presented by providing resolutions to the deficiencies identified; these resolutions should include a description of the corrective action, schedules for its completion (as applicable), and so forth. The staff will review 'he licensee's response, when it is submitted, and discuss the resolutior ir-
'spplemental report.
It should be noted that in cases where testing is being cunducted, a condition may arise which results in a determination by the licensee that the equipment does not satisfy the qualification test requirements.
For that equipment, the licensee will be required to provide the proposed corrective action, on a timely basis, to ensure that qualification can be established by June 30, 1982.
4.3 Eouioment Considered Acceotable or Conditionally Acceptable Based on the staff review of the licensee's submittal, the staff identified the equipment in Appendix C as (1) acceptable on the basis that the qualifi-cation program adequately enveloped the specific environmental plant parameters, or (2) conditionally acceptable subject to the satisfactory resolution of the staff concern identified in Section 3.7.
For the equipment identified as conditionally acceptable, the staff determined that the licensee did not clearly (1) state that an equipment material evaluation was conducted to ensure that no known materials susceptible to degradation because of aging have been
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(2) establish an ongoing program to review the plant surveillance and main-tenance records in order to identify equipment degradation which may be age related, and/or (3) propose a maintenance program and replacement schedule for equipment identified in item 1 or equipment that is qualified for less than the life of the plant.
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The licensee is,'therefore, required to supplement the information presented l
for equipment in this category before full acceptance of this equipment can be established. The staff will review the licensee's response when it is sub-l mitted and discuss the resolution in a supplemental report.
1 5 DEFERRED REQUIREMENTS f
IEB 79-018, Supplement 3 has relaxed the time constraints for the submission of the information associated with cold shutdown equipment and TMI lessons-learned modifications.
The staff has required that this information be provided by February 1, 1981.
The staff will provide a supplemental safety evaluati.;n addressing these concerns.
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APPENDIX 3 Equip =ent Recuiring Additional Information and/or Corrective Action (Category 4.2)
LEGEND:
Designation for Deficiency R - Radiation T - Temperature QT - Qualification time RT - Required time P - Pressure H - Humidity CS - Chemical spray A - Material aging eva!uation, rep;acement senedule, ongoing ecuipment surveillance 5 - Sut:ergence M - Margin I - HELS evaluation outsice contain=ent not cc cleted QM - Qualification method RPN - Equipment relocation or replacement, adecuate scnecule not provicec EXN - Exe:ptec equipment justification inacecuate SEN - 5ecarate effects qualification justification inadequate QI - Qualification information being developed RPS - Equipment relocation or ren'.; ment scnedule provided Equipment Descriction Manufacturer Plant ID No.
De ficiency Electrical Penetration Conax Type 2325-CS,R,A S205-01 Electrical Penetration Conax Type 2325-T,CS,R,A 8076-01 Electrical Penetration Conax Type 2325-CS,R,A 8077-01 600 V Power and Okonite Generic C5,R,A,5 Control Cacle Triaxial Cable Boston Type RG11/u QT,T,CS,R,A Insulated Wire i
Signal Cable Boston Type 8374-QT,T,CS,R,A Insulated Wire H-002 Cable Seal for PDTs Conax Type PL-15-34 T,P,CS,R,A B-1
APPENDIX B (continued)
Equipment Descriotion Manufacturer Plant ID No.
Deficiency Junction Box Assembly Foxboro Part No. 3 -
CS,R,A With Cable Seal XIB-I/2 Pressure Transmitter Foxboro PT-1020 RT,CS,R,A Pressure Transmitter Rosemount PT-1021 RT,CS,R,A Pressure Transmitter Foxboro PT-1022 RT,CS,R,A Pressure Transmitter Rosemount PT-1023 RT,CS,R,A Pressure Transmitter Rosemount PT-1038 RT,CS,R,A Pressure Transmitter Rosemount PT-1039 RT,CS,R,A Pressure Transmitter Foxboro PT-1040 RT,CS,R,A Pressure Transmitter Foxboro PT-1041 RT,CS,R,A Differential Press.
Bailey Controls PDT-1028 T,P,CS,R,A Transmitter Differential Press.
Bailey Controls PDT-1029 T,P,CS,R,A Transmitter Differential Press.
Bailey Controls POT-1030 T,F,CS,R,A Transmitter Differential Press.
Bailey Controls PDT-1031 T,P,CS,R,A Transmitter Differential Press.
Bailey Controls PDT-1034 T,P,CS,R,A Transmitter l
Differential Press.
Bailey Controls PDT-1035 T,P,CS,R,A l
Transmitter l
Differential Press.
Bailey Controls PDT-1036 T,P,CS,R,A l
Transmitter i
Differential Press.
Bailey Controls PDT-1037 T,P,CS,R,A Transmitter Resistance Temp. Element Rosemount TE-1012 QT,T,P,H,CS,R,A Resistance Temp. Element Rosemount TE-1013 QT,T,P,H,CS,R,A-l B-2 l
I APPENDIX B (continued)
Equipment Descriotion Manufacturer Plant ID No.
Deficiency Resistance Temo. Element Rosemount TE-1040 QT,T,P,H,CS,R,A Resistance Temp. Element Rosemount TE-1041 QT,T,P,H,CS,R,A Motor Operated Valve Rotork CV-1050 RT,QT,T,P,CS,A Motor Operated Valve Limitorque CV-1054 QT,T,P,H,CS,R,A,5 Limit Switch Honeywell ZS-1052 RT,QT,R,A Solenoid Valve ASCO SV-1052 RT,QT,R,A Motor Operated Valve Limitorque CV-1053 QT,T,P,H,CS R,A,5 3
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ZS-1065 RT,QT,R,A Solenoid Valve ASCO SV-1065 RT,QT,R,A Scienoid Valve
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SV-1066 RT,QT,R,A Valve Actuator
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CV-1206 RT,QT,R,A Press. Diff. Transmitter Bailey Controls PDT-1209 RT,QT,A Press. Diff. Transmitter Bailey Controls PDT-1210 RT,QT,A Press. Diff. Transmitter Bailey Controls PDT-1228 RT,QT,A Press. Diff. Transmitter Bailey Controls PDT-1230 RT,QT,A Motor Operated Valve Limitorque CV-1214 RT,T,P,CS,A,5 Motor Operated Valve Limitorque CV-1216 RT,T,P,CS,A,5 i
Motor Operated Valve Limitorque CV-1213
_RT,QT,R,A i
Motor Operated Valve Limitorque CV-1220 RT,QT,R,A Motor Operated Valve Limitorque CV-1221 RT,QT,R,A Motor Operated Valve Limitorque CV-1227 RT,QT,A Motor Operated Valve Limitorque CV-1228 RT,QT,A Motor Operated Valve Limitorque CV-1234 RT,QT,A Motor Operated Valve Limitorque-CV-1270 RT,T,P,CS,A B-3
APPENDIX B (continued)
Equipment Descriotion Manufacturer Plant ID No.
Deficiency Motor Operated Valve Limitorque CV-1271 RT,T,P,CS,A Motor Operated Valve Limitorque CV-1272 RT,T,P,CS,A Motor Operated Valve Limitorque CV-1273 RT,T,P,CS,A Motor Operated Valve Limitorque CV-1274 RT,QT,A Motor Operated Valve Limitorque CV-1300 RT,QT,R,A Motor Operated Valve Limitorque CV-1301 RT,QT,R,A Solenoid Valve ASCO SV-1252 RT,QT,T,P,H,R,A Temp. Switch United Electric TS-1221 RT,QT,T,P,H,R,A Valve Operator Limitorque CV-1400 RT,QT,R,A Valve Operator Limitorque CV-1401 RT,QT,A Valve Operator Limitorque CV-1404 RT,QT,R,A x
Valve Operator Limitorque CV-1405 RT,QT,A Valve Operator Limitorque CV-1406 RT,QT,A Valve Operator Limitorque CV-1407 RT,QT,A Valve Operator Limitorque CV-1408 RT,QT,A Valve Operator
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CV-1429 RT,QT,R,A Press. Diff. Trans.
Bailey Controls PDT-1401 RT,QT,A Press. Dif'. Trans.
Bailey Controls POT-1402 RT,QT,A Signal Converter Bailey E/H-1428 QT,R,A Signal Converter
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E/H-1429 RT,QT,R,A Signal Converter Bailey E/P-1432 RT,QT,R,A Signal Converter Bailey E/P-1433 RT,QT,R,A Motor Operated Valve Limitorque CV-1814 RT,T,P,CS,A Motor Operated Valve Limitorque CV'1816 RT,T,P,CS,A 8-4
APPENDIX $ (c.Jntinued)
Equipment Description Manufacturer Plant ID No.
Deficiency Motor Operated Valve limitorque CV-1820 RT,T,P,CS,A Motor Operated Valve Limitorque CV-1826 RT,T,P,CS,A Valve Operator
?
CV-1818 RT,QT,T,P,H,R,A Valve Operator
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CV-1822 RT,QT,T,P,H,R,A Limit Switch Honeywell 25-1845 RT,QT,R,A Microswitch Solenoid Valve ASCO SV-1845 RT,QT,R,A Limit Switch NAMCO ZS-2100 RT,QT,R,A Limit Switch NAMCO ZS-2101 RT,QT,R,A Limit Switen NAMCO ZS-2102 RT,QT,R,A Limit Switch NAMCO ZS-2103 RT,QT,R,A Limit Switch NAMCO ZS-2104 RT,QT,R,A Limit Switch NAMCO ZS-2105 RT,QT,R,A Limit Switch NAMCC ZS-2106 RT,QT,R,A Limit Switch NAMCO ZS-2107 RT,QT,R,A Limit Switch NAMCO ZS-2108 RT,QT,R,A i
Limit Switch NAMCO ZS-2111 RT,QT,R,A I
Limit Switch NAMCO ZS-2112 RT,QT,R, A l
Limit Switch NAMCO ZS-2113 RT,QT,R,A Limit Switch NAMCO Z5-2114 RT,QT,R,A Limit Switch NAMCO ZS-2115 RT,QT,R,A Limit Switch NAMCO ZS-2116 RT,QT,R,A Limit suitch NAMCO ZS-2123 RT.QT,R,A Limit Switch NAMCO ZS-2126 RT,Q T, R, A B-5 L
APPENDIX B (continued)
Equipment Descriotion Manufacturer Plant IO No.
De ficiency Limit Switch NAMCO ZS-2133 RT,QT,R,A Limit Switch NAMCO ZS-2136 RT,QT,R,A Solenoid Valve ASCO SV-2100 RT,QT,R,A Solenoid Valve ASCO SV-2101 RT,QT,R,A Solenoid Valve ASCO SV-2102 8cT,QT,R,A Solenoid Valve ASCO SV-2103 RT,QT,R,A Solenoid Valve ASCO SV-2104 RT,QT,R,A Solenoid Valve ASCO
'N-2105 RT,QT,R,A Solenoid Valve ASCO SV-2106 RT,QT,R,A Solenoid Valve ASCO SV-2107 RT,QT,R,A Solenoid Valve ASCO SV-2108 RT,QT,R,A Solenoid Valve ASCO SV-2111 RT,QT,R,A Solenoid Valve ASCO SV-2112 RT,QT,R,A Solenoid Valve ASCO SV-2113 RT,QT,R,A Solenoid Valve ASCO SV-2114 RT,QT,R,A Solenoid Valve ASCO SV-2115 RT,QT,R,A Solenoid Valve ASCO SV-2116 RT,QT,R,A Valve Actuator ITT/Fischer CV-2123 RT,QT,R,A Valve Actuator ITT/Fischer CV-2126 RT,QT,R,A Valve Actuator ITT/Fischer CV-2133' RT,QT,R,A Valve Actuator-ITT/Fischer CV-2136 RT,QT,R,A 0/P Transmitter Fischer &
PDT-2119 RT,QT,R,A Porter D/P Transmitter Fischer &
PDT-2120 RT,QT,R,A Porter B-6
APPENDIX B (continued)
Equipment Descriotion Manufacturer Plant ID No.
Deficiency D/P Transmitter Fischer &
PDT-2121 RT,QT,R,A Porter D/P Transmitter Fischer &
PDT-2129 RT,QT,R,A Porter D/P Transmitter Fischer &
PDT-2130 RT,QT,R,A Porter D/P Transmitter Fischer &
PDT-2131 RT,QT,R,A Porter D/P Switch
?
PDS-2125 RT,QT,R,A D/P Switch
?
PDIS-2125 RT,QT,R,A D/P Switch
?
PDS-2126 RT,QT,R,A D/P Switch
?
PDIS-2126 RT,QT,R,A D/P Switch
?
PDS-2127 RT,QT,R,A D/P Switch
?
PDIS-2127.
RT,QT,R,A D/P Switch
?
PDS-2135 RT,QT,R,A D/P Switch
?
PDIS-2135 RT,QT,R,A D/P Switch
?
PDS-2136 RT,QT,R,A D/P Switch
?
PDIS-2136 RT,QT,R,A D/P Switch
?
PDS-2137 RT,QT,R,A D/P Switch
?
PDIS-2137 RT,QT,R,A Flow' Switch
?
FS-2120 RT,QT,R,A Radiation Element
?
RE-2120 RT,QT,R,A Radiation Element
?
RE-2130 RT,QT,R,A Radiation Indicator
?
RI-2120 RT,QT,R,A Radiation Indicator
?
RI-2130 RT,QT,R,A Solenoid Valve ASCD SV-2213 RT,QT,R,A B-7
APPENDIX B (continued)
Equipment Descriotion Manufteturer Plant ID No.
Deficiency Solenoid Valve ASCO SV-2214 RT,QT,R,A Solenoid Valve ASCO SV-2233 RT,QT,R,A Solenoid Valve ASCO SV-2234 RT,QT,R,A 4
Limit Switch Honeywell ZS-2214 RT,QT,R,A Microswitch Limit Switch Honeywell ZS-2233 RT,QT,R,A Microswitch Limit Switch Honeywell ZS-2234 RT,QT,R,A Microswitch Valve Actuator Rotork CV-2220 RT,QT,R,A Valve Actuator Rotork CV-2235 RT,QT,R,A Motor Operated Valve Limitorque CV-2215 QT,T,P,H,CS,R,A Motor Operated Valve Limitorque CV-2221 QT,T,P,H,CS,R,A Valve Actuator Limitorque CV-2400 RT,QT,R,A Valve Actuator Limitorque CV-2401 RT,QT.R A Valve Actuator Limitorque CV-2410 RT,QT,R,A Valve Actuator Limitorque CV-2411 RT,QT,R,A 0/P Transmitter Bailey PDT-2400 RT,QT,R,A D/P Transmitter Bailey POT-2401 RT,QT,R,A Pressure Switch Barion PS-2400 RT,QT,T,P,H,CS,R,A Pressure Switch Barion PS-2401 RT,QT,T,P,H,CS,R,A Pressure Switch Barion PS-2402 RT,QT,T,P,H,CS,R,A Pressure Switch Barion PS-2403 RT,QT,T,P,H,CS,R,A Press. Transmitter Fischer &
PT-2405 QT,T,P,H,CS,R,A Porter Press. Transmitter Fischer &
PT-2406 QT,T,P,H,CS,R,A Porter B-8
APPENDIX B (continued)
Equipment Descriotion Manufacturer Plant ID No.
Deficiency Press. Transmitter Fiscner &
PT-2407 QT,T,P,H,CS,R,A Porter Level Transmitter Foxcoro LT-2410 RT,QT,R,A Motor Operateo Valvr.
Limitorque CV-2416 RT,T,?,CS,A Motor Operatcc Valve Limitorcue CV-2418 RT,T,P,CS,A Valve Operator Limitorque CV-2617 RT,QT,A Valve Operator Limitorque CV-2619 RT,QT,A Valve Operator Limitorque CV-2620 RT,QT,A Valve Ocerator Limitorque CV-2630 RT,QT,A Valve Ocerator Limitorque CV-2667 RT,QT,A Valve Operator Limitorcue CV-2670 RT,QT,A Valve Operator Limitorque CV-2676 RT,QT,A Valve Operator Limitorque CV-2680 RT,QT,A Valve Operator Rotork CV-2626 RT,QT,T,P,H,R,A Valve Operator Rotork CV-2627 RT,QT T,?,H,R,A Pressure Switch G.O.R. Inc.
PS-2617A RT,QT,T,P,H,R,A i
Pressure Switch G.O.R. Inc.
?S-2617B RT,QT,T,P,H,R,A Pressure Switch Barksdale PS-2618A RT,QT,T,P,H,R,A Pressure Switch Barksdale PS-26188 RT,QT,T,P,H,R,A Pressure Switch
?
PS-2667A RT,QT,T,P,H,R,A l
Pressure Switch
?
PS-2667a RT,QT,T,P,H,R,A f
Pressure Switch G.O.R. Inc.
P5-2668A RT,QT,T,P,H,R,A Pressure Switch G.O.R. Inc.
PS-26688 RT,QT,T,P,H,R,A Valve Positioner Honeywell
-CV-2618 RT,QT,T,P,H,R,A Valve Positioner Honeywell CV-2668 RT,QT,T,P,H,R,A B-9
APPENDIX B (continued)
Equipment Descriotion Manufacturer Plant ID No.
Deficiency Valve Positioner
?
CV-2668A RT,QT,T,P,H,R,A Valve Positioner Honeywell CV-26688 RT,QT,T,P,H,R,A Limit Switch Honeywell ZS-2618 RT,QT,T,P,H,R,A Microswitch Limit Switch Honeywell Z5-2668 RT,QT,T,P,H,R,A Microswitch Limit Switch NAMCO Z5-2691-1 RT,QT,T,P,H,R,A Limit Switch NAMCO Z5-2691-2 RT,QT,T,P,H,R,A Limit Switch NAMC0 Z5-2595 RT,QT,T,P,H,R,A Limit Switch NAMCO ZS-2692-1 RT,QT,T,P,H,R,A Limit Switch NAMCO ZS-2692-2 RT.QT,T,P,H,R,A Limit Switch NAMCO ZS-2696 RT,QT,T,P,H,R,A Pneumatic Conv.
Sailey Controls E/P-2618 RT,QT,T,P,H,R,A Pneumatic Conv.
Bailey Controls E/P-2668 RT,QT,T,P,H,R,A
?
?
FY-2618 RT,QT,T,P,H,R,A
?
?
FY-2668 RT,QT,T,P,H,R,A Diff. Press. Trans.
Rosemount PDT-26020A RT,QT,A Diff. Press. Trans.
Rosemount PDT-26208 RT,QT,A Diff. Press. Trans.
Fischer &
PDT-2670 RT,QT,R,A Porter Diff. Press. Trans.
Rosemount PDT-26708 RT,QT,A Pilot Solenoid Norgren SV-2691 RT,QT,T,P,H,R,A Pilot Solenoid Norgren SV-2692 RT,QT,T,P,H,R,A Valve Operator.
Limitorque CV-2800 RT,QT,A Valve Operator Limitorque CV-2802 RT,QT,A Valve Operator.
Limitorque~
CV-2803 RT,QT,A B-10
APPENDIX 8 (continued)
Equipment-Description i4anufacturer Plant ID No.
Deficiency Valve 0pirator Limitorque CV-2806 RT.QT,A Valve Operator Limitorque CV-2813 RT,QT,A Valve Operator Limitorque CV-2814 RT,QT,A Press. Trans & Indicator Fischer &
PIT-2811 RT,QT,R,A Porter Press. Trans. & Indicator Fischer &
PIT-2812 RT,QT,R,A Porter Valve Operator Rotork CV-3800 RT,QT,T,P,H,R,A Valve Operator Rotork CV-3801 RT,QT,T,P,H,R,A Valve Operator Rotork CV-3802 RT,QT,T,P,H,R,A Valve Operator Rotork CV-3803 R1,QT,T,P,H,R,A Valve Operator Rotork CV-3806 RT,QT,T,P,H,R,A Valve Operator Rotork CV-3807 RT,QT,T,P,H,R,A Valve Operator Rotork CV-3808 RT,QT,T,P,H,R,A Valve Operator Rotork CV-3809 RT,QT,T,P,H,R,A Valve Operator Rotork CV-3810 RT,QT.T,P,H,R A Valve Operator Limitorque CV-3811 RT,QT,A Valve Operator Limitorque CV-3820 RT,QT,A Valve Operator Limitorque CV-3821 RT,QT,A Valve Operator Limitorque CV-3822 RT,QT,A Valve Operator Limitorque
.CV-3823 RT,QT,A
.Vaive Operator Limitorque CV-3824 RT,QT,A Valve Operator Limitorque CV-3851 RT,QT,T,P,H,R,A Valve Opera.or
?
CV-3850 RT,QT,T,P,H,R,A Solenoid Valve-
?
SV-3804 RT,QT,R,A 8-11
APPENDIX B (continueo)
Equipment Descriotion Hanufacturer Plant ID No.
Deficiency Solenoid Valve
?
SV-3805 RT,QT,R,A Solenoid Valve ASCO 3V-3812 RT,QT,T,P H,R,A Solenoid Valve ASCO SV-3813 RT,QT,' P,H,R,A Solenoid Valve ASCO SV-3814 RT,QT,T,P,H,R,A Solenoid Valve ASCO SV-3815 RT,QT,T,P,H,R,A Solenoid Valve ASCO SV-3840 RT,QT,T,P,H,R,A Solenoid Valve ASCO SV-3841 RT,QT,T,P,H,R,A Limit Switch
?
ZS-3804 RT,QT,R,A Limit Switch
?
ZS-3805 RT,QT,R,A Limit Switch NAMCO ZS-3812 RT,QT,T,P,H,R,A Limit Switch NAMCO Z5-3813 RT,QT,T,P,H,R,A Limit Switch NAMCO ZS-3814 RT,QT,T,P,H,R,A Limit Switch NAMCO ZS-3815 RT,QT,T,P,H,R,A Limit Swstch Microswitch ZS-3840 RT,QT,T,P,H,R,A Limit Switch Honeywell ZS-3841 RT,QT,T,P,H,R,A Microswitch Limit Switch
?
ZS-4400 RT,QT,R,A Solenoid Valve ASCO SV-4400 RT,QT,R,A Solencio Valve ASCO SV-4804 RT,QT,R,A Solenoid Valve ASCO SV-6201 RT,QT,R,A Solenoid Valve
'ASCO SV-6202 RT,QT,R,A Solenoid Valve ASCO SV-6203 RT,QT,R,A Solenoid Valve ASCO SV-7401 RT,QT,R,A Solenoid Valve ASCO SV-7402 RT,QT,R,A B-12
APPENDIX B (continued)
Equipment Description Manufacturer Plant ID No.
Deficiency Limit Switch Honeywell ZS-4804 RT,QT,R,A Microswitch Limit Switch NAMCO ZS-6202 RT,QT,R,A Limit Switch NAMCO ZS-6203 RT,QT,R,A Limit Switch Betteswitch ZS-7401 RT,QT,R,A Limit Switch Betteswitch Z5-7402 RT,QT,R,A Valve Actuator Limitorque CV-7454 RT,QT,R,A Valve Actuator
?
CV-7459 RT,QT,R,A Valve Actuator
?
CV-7467 RT,QT,R,A Valve Actuator
?
CV-7469 RT,QT,R,A Valve Actuator
?
CV-7457 RT,QT,R,A Valve Motor Operator Rotork CV-4446 RT,QT,T,P,CS,A Motor Operated Valve Limitorque DV-4803 QT,T,P,H,CS,R,A Valve Motor Operator Rotork CV-5612 RT,QT,T,P,CS,A Motor Operated Valve Limitorque CV-6205 QT,T,P,H,CS,R,A Motor Operated Valve Limitorque CV-7403 QT,T,P,H CS,R,A Motor Operated Valve Limitorque CV-7404 OT,T,P,H,CS,R,A Motor General Electric SV-7410 QT,CS,A Motor General Electric SV-7411 QT,CS,A Motor General Electric SV-7412 QT,CS,A Motor General Electric SV-7413 QT,CS,A Limit Switch
?
ZS-7441 RT,QT,R,A Limit Switch
?
ZS-74 Q RT,QT,R,A Solenoid Valve ASCO SV-7441 RT,QT,R,A Solenoid Valve ASCO SV-7442 RT,QT,R,A 8-13
APPENDIX B (continued)
Equipment Descriotion Manufacturer Plant ID No.
Deficiency D/P Transmitter Fischer &
PDT-7441 RT,QT,R,A Porter D/P Transmitter Fischer &
PDT-7442 RT,QT,R,A Porter D/P Transmitter Fischer &
PDT-7451 RT,QT,R,A Porter D/P Transmitter Fischer &
PDT-7452 RT,QT,R,A Porter Temp. Switch Fenwal TS-7441 RT,QT,R,A Temp. Switch Fenwal TS-7442 RT,QT,R,A Radiation
?
RIS-7441 RT,QT,R,A Indicator / Switch Radiation
?
RIS-7442 RT,QT,R,A Indicator / Switch Radiation Element LFE Corp.
RE-7441 RT,QT,R,A Radiation Element LFE Corp.
RE-7442 RT,QT,R,A Radiation Indicator
?
RI-7441 RT,QT,R,A Radiation Indicator
?
RI-7442 RT,QT,R,A l
Valve Actuator
?
CV-7443 RT,QT,R,A Valve Actuator
?
CV-7445 RT,QT,R,A Valve Actuator
?
CV-7447 RT,QT,R,A Valve Actuator
?
CV-7449 RT,QT,R,A Valve Actuator Limitorque CV-7451 RT,QT,R,A Valve Actuator Limitorque CV-7452 RT,QT,R,A D/P Switch Barton DPS-7447 RT,QT,R,A D/P Switch Barton DPS-7448 RT,QT,R,A D/P Switch Barton DPS-7451 RT,QT,R,A B-14 L
APPENDIX B (continued)
Equipment Description Manufacturer Plant ID No.
Oticiency D/P Switch Barton OPS-7452 RT,QT,R,A Fan Motor
?
VEF-37A RT,QT,R,A Fan Motor
?
VEH-378 RT,QT,R,A Fan Motor
?
VSF-30A RT,QT,R,A Fan Motor
?
VSF-308 RT,QT,R,A Vent. Heater
?
VEH-6A RT,QT,R.A Vent. Heater
?
VEH-6B RT,QT,R,A Motor Operated Valve Limitorque CV-7453 QT,T,P,H,CS,R,A Pump
?
P7A RT,QT,R,A Pump
?
P78 RT,QT,R,A Pump
?
P34A RT,QT,R,A Pump
?
P348 RT,QT,R,A Pump Motor
?
P-35A RT,QT,R,A Pump Motor
?
P-358 RT,QT,R,A Pump-
?
P-36A RT,QT,R,A Pump
?
P-368 RT,QT,R,A Pump
?
P-36C RT,QT,R,A Fan Motor
?
VEF-38A RT,QT,R,A Fan Motor
?
VEF-388 RT,QT,R,A Neutron Detector
?
Generic T,CS,R,A Local Connector
- B-15
-e q
m o
i APPENDIX C Equip:nent Considered Acceptable or Conditionally Acceptable (Category 4.3) i Equipment Gescription Manufacturer Plant ID No.
Deficiency No equipment in this category.
i 4
i l
f I
1 f
I s
l~
i i
C-1 i
r 7
c 4++
v y
y rw
-wrn.
- - + - >, - -
APPENDIX D Safety-Related Systems Listi Function System Emergency Reactor Shutdown Reactor Coolant Reactor Protection Engineered Safeguards Actuation Makaup and Purification Containment Isolation Main Steam Feedwater Decay Heat Removal Sampling Guseous Radwaste Intermediate Cooling Service Water Makeup and Purification Chilled Water Firewater Dirty Liquid Radwaste Hydrogen Purge Reactor Building Purge Reactor Building Isolation 2 Reactor Core Cooling High Pressure Injection (Makeup and Purification)
Low Pressure Injection (Decay Heat Removal)
Core Flood Containment Heat Removal Reactor Building Spray Reactor Building Cooling Containment Sump Recirculation (Decay Heat Removal)
Core Residual Heat Removal Decay Heat Removal Power Operated Relief Valves 3 Main Feedwater Emergency Feedwater Steam Dump Intermediate Cocling Water Service Water
'The NRC staff recognized that there are differences in nomenclature of systems because of plant vintage and engineering design; consequently some systems performing identical or similar functions may have different names.
In those instances it was necessary to verify the system (s) function with the msponsible IE regional reviewer and/or the licensee.
2 Includes other isolation valves in systems not given above.
3 Covered as part of TMI-2 Lessons Learned.
D-1
e Appendix 0 (Continued)
Function System Prevention of Significant Reactor Building Spray (Iodine Removal)
Release of Radioactive Hydrogen Purge Material to Environment Sampling Radiation Monitoring Supporting Systems Station Distribution Diesel Generators and Support Systems Co:itrol Room Emergency Air Conditioning i
Emergency Chilled Water t
(
e 4
0-2