ML20004B739
| ML20004B739 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 05/22/1981 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML111960130 | List: |
| References | |
| RTR-NUREG-0588, RTR-NUREG-588, RTR-NUREG-588-C-810522 IEB-79-01, IEB-79-01B, IEB-79-1, IEB-79-1B, IEC-78-08, IEC-78-8, NUDOCS 8105290446 | |
| Download: ML20004B739 (31) | |
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SAFETY EVALUATION REPORT BY THE OFFICE OF NUCLEAR REACTOR REGULATION EQUIPMENT QUALIFICATION BRANCH FOR ARKANSAS POWER AND LIGHT COMPANY ARKANSAS NUCLEAR ONE - UNIT 2 DOCKET NO. 50-368 18105290 N
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CONTENTS Page 1
Introduction...............................................
1 2
Background.................................................
1 2.1 Purpose...............................................
2 2.2 Scope.................................................
2 3
Staff Evaluation...........................................
2 3.1 Completeness of Safety-Related Equipment..............
2
- 3. 2 Service Conditions....................................
3 3.3 Temperature, Pressure, and Humidity Conditions Inside Containment....................................
4 3.4 Temperature, Pressure, and Humidity Conditions Outside Containment.............
4 1
3.5 Submergence...........................................
5 3.6 Chemical Spray........................................
5 3.7 Aging.................................................
5 3.8 Radiation.............................................
6 1
4 Qualification of Equipment.................................
7 4.1 Equipment Requiring Inanediate Corrective Action.......
7 4.2 Equipment Requiring Additional Information and/or Corrective Action....................................
7 4.3 Equipment Considered Acceptable or Conditionall Acceptable....................................y 9
5 Deferred Requirements......................................
9 6
Conclusions................................................
9 APPENDIX A Equipment Requiring Immediate Corrective Action APPENDIX B Equipment Requiring Additional Information and/or Corrective Action APPENDIX C Equipment Considered Acceptable or Conditionally Acceptable APPENDIX 0 Safety-Related Systems List :
Letter from the Foxboro Company dated March 12, 1981, regarding deficiencies in the Model Ell l
and E13 transmitters.
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SAFETY EVALUATION REPORT BY THE OFFICE OF NUCLEAR REACTOR REGULATION EQUIPMENT QUALIFICATION BRANCH FOR ARKANSAS POWER AND LICLT COMPANY ARKANSAS NUCLEAR ONE - UNIT 2 DOCKET NO. 50-368 ENVIRONMENTAL QUALIFICATION OF SAFETY-RELATED ELECTRICAL EQUIPMENT 1 INTRODUC TION General Design Criteria 1 and 4 specify that safety-related electrical equip-ment in nuclear facilities must be capable of performing its safety-related function under environmental conditions associated with all normal, abnormal, and accident plant operation.
In order to ensure compliance with the cri-teria, the NRC staff required all licensees of operating reactors to submit a reevaluation of the qualification of safety-related electrical equipment which may be exposed to a harsh environment.
2 BACKGROUND On February 8,1979, the NRC Office of Inspection and Enforcement (IE) issued to all licensees of operating plants (except those included in the systematic evaluation program (SEP)) IE Bulletin IEB 79-01, " Environmental Qualification of Class IE Equipment." This bulletin, together with IE Circular 78-08 (issued on May 31, 1978), required the licensees to perform reviews to assess the adequacy of their environmental qualification programs.
Subsequently, Commission Memorandum and Order CLI-80-21 fissued on May 23, 1980) states that the D0R guidelines and portions of NUREG-0588 (which were issued on January 14, 1980, as enclosures 4 and 5 to IE8-79-018) form the requirements that licensees must meet regarding environmental qualification of safety-related electrical equipment in order to satisfy those aspects of 10 CFR 50, Appendix A, General Design Criterion (GDC)-4.
This order also requires the staff to complete safety evaluation reports (SERs) for all operating plants by February 1, 1981.
In addition, this order requires that the licensees have qualified safety-related equipment installed in their plants by June 30, 1982.
Supplements to IE8 79-018 were issued for further clarification and definition of the staff's needs.
These supplements were issued on February 29, September 30, l
and October 24, 1980.
I In addition, the staff issued orders dated August 23, 1980 (amended in September 1980) and October 24, 1980 to all licensees.
The August order required that the licensees provide a report, by November 1,1980, documenting the qualifica-tion of safety-related electrical equipment.
The October order required the establishment of a central file location for the maintenance of all equipment-qualification records. The central file was mandated to be established by December 1, 1980.
The order also required tnat all safety-related electrical l
t
b equipment be qualified by June 30, 1982.
In response, the licensee submitted information through letters dated February 22, April 14, Juae 23, and October 4 and 31, 1980.
2.1 Purpose The purpose of this SER is to identify equipment whose qualification program does not provide sufficient assurance that the equipment is capable of performing the design function in hostile environments.
The staff position relating to any identified deficiencies is provided in this report.
2.2 Scope The scope of this report is limited to an evaluation of the equipment which must function in order to mitigate the consequences of a loss-of-coolant accident (LOCA) or a high-energy-line-break (HELB) accident, inside or outside containment, while subjected to the hostile environments associated with these accidents.
3 STAFF EVALUATION The staff evaluation of the licensee's response included an examination of the 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 and documented it in a technical evaluation report (TER) dated December 10, 1980.
An onsite verification inspection of selected safety-related electrical equipment will be conducted in May 1981 during the scheduled plant outage.
The inspection will review the reactor coolant system to verify proper installation of equipment, overall interface integrity, and manufacturers' nameplate data.
The manufacturer's name and model number from the nameplate data will be compared to information given in the Component Evalu-ation Work Sheets (CES) of the licensee's report.
The site inspection will be documented in a copplemental report, and any deficiencies will be identified.
For this review, che TER referenced above has been factored into the overall staff evaluation.
3.1 Completeness of Safety-Related Equipment In accordance with IEB 79-018, the licensee was directed to (1) establish a list of systems and equipment that are required to mitigate a LOCA and an HELO and (2) identify components needed to perform the function of safety-related display information, post-accident sampling and monitoring, and radiation monitoring.
The staff developed a generic master list based upon a review of plant safety analyses and emergency procedures.
The instrumentation selected includes 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 regard to location of equipment relative to hostile environments)..-
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.The list of safety-related systems provided by the licensee was reviewed against 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 Appendix D) 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 procecures 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 which is not considered to be safety related but which is mentioned in the emergency procedure should appear on the list.
For these instruments, (1) justification should be provided for not considering the instrument safety related and (2) assurance ;hould be provided that its subsequent failure will not mislead the operator or adversely affect the mitigation of the consequences of the accident.
The environmental qualifi-cation of post-accident sampling and monitoring and radiation monitoring equipment is closely related to the review of the TMI Lessons-Learned modifications and will be performed in conjunction with that review.
The licensee identified 281 items of equipment which were a::sessed by the staff.
3.2 Service Conditions Commission Memorandum and Order CLI-80-21 requires that the 00R guidelines and the "For Comment" NUREG-0588 are to be used as the criteria for establishing j
the adequacy of the safety related electrical equipment environmental quali-l fication program.
These documents provide the option of establishing a bounding l
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 staff has assumed, unless otherwise noted, that the analysis for developing the environmental envslopes relative to the temperature, pressure, and the containment spray caustics, has been performed in accordance with the requirements stated above. The staff has reviewed the 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 :ontainment spray system which satisfies the single-failure criterion, the main-steam-line-break (MSLB) environmental,
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conditions are enveloped by the large-break-LOCA environmental conditions.
l The staff performed an evaluation of the licensee's automatic containment spray system and verified the licensee's claim that the system is not subjected to a disabling single-component failure and therefore satisfies the requirements of Section 4.2.1 of the DDR guidelines.
Equipment submergence has also been addressed where the possibility exists that flooding of equipment may result from HELBs.
- 3. 3 Temperature, Pressure, and Humidi_ty Conditions Inside Containment The licensee has provided the results of accident analyses as follows:
Max Temp (*F)
Max Press (psig)
Humidity (%)
LOCA 289 48 100 MSLB (not provided)
(not provided) 100 The staff has concluded 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.
U a of the steam saturation temperature currasponding 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 MSLB, whichever is controlling, as to potential adverse environmental effects on equipment.
The licensee's specified temperature (service condition) of 289 F does not satisfy the above requirement. A saturation temperature corresponding to the peak profile (295 F peak temperature at 48 psig) should be used instead.
The licensee should update his equipment summary tables to reflect this change.
If there is any equipment that does not meet the staff position, the licensee must provide either justification that the equipment will perform its intended function under the specified conditions or propose corrective action.
3.4 Temperature, Pressure, and Humiu1ty Conditions Outside Containment The licensee has provided the temperature, pressure, humidity and applicable environment associated with an HELB outside containment.
The following areas outside containment in the auxiliary building have been addressed:
(1) Main steam chase and pipeways areas (2) Main feedwater penetration, chiller equipment, and heater and compressor areas (3) Norht piping area (4) Steam generator penetration areas, cump areas, and access areas (5) Emergency feedwater. pump and access areas (6) South piping penetration area (7) Charging and letdown areas.
The staff has verified that the parameters identified by the licensee for the MSLB are acceptable.
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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 maximum submergence is at elevation 343 ft 6 in.
Equipment below this level has been identified by the licensee, along with the proposed corrective action.
The licensee identified four safety-related electrical components for Arkansas Nuclear One-Unit 2 as having the potential for becoming submerged after a postulated event. Two of the items (Rotork Valves Items I-027 and 028) have been subjected to qualification testing under submerged conditions for 30 days. These tests were previously reviewed by the staff and have been found acceptable.
For the remaining two items (contair. ment sump level sensors by DeLeval - Items I-025 and 026), the information provided by the licensee is not complete enough to ensure that adequate equipment operability is maintained under submerged conditions.
The licensee is required to supplement the information and document the qualification methodology which assures that the equipment will maintain its functional operability or justify the design or, some defined basis.
The licenue's response should provide an assessment of the failure modes associated with the submergence of these level sensors.
The licensee should also provide assurance that the subsequent failure of this component will not adversely affect any other safety functions or mislead an operator.
If the results of the licensee's assessment are acceptable, then the equipment may be exempt from the submergence parameter of qualification.
It is not clear from the information submitted that submergence of safety-related electrical equipment outside of containment was addressed.
The licensee should address this area more specifically in the 90-day response anc upgrade the CES as appropriate.
3.6 Chemical Spray The licensee's FSAR value for the chemical concentration is 15,000 ppm boric acid solution, 0.1% sodium hydroxide (by weight) and 1% sodium thiosulfate by weight at a pH of 10.5.
During the review, staff identified several items of equipment that were tested with caustic spray concentrations significantly less than that used in the plant.
The licensee is therefore required to justify the adequacy of this desigr. on some defined basis or modify the desig7 accordingly.
The staff will review the licensee's response when it is submitted and discuss the resolution in a supplemental report.
l 3.7 Aging Section 7 of the DOR guidelines does not require a qualified life to be estab-lished for all safety-related electrical equipment.
However, the following t
actions are required:
(1) Make a detailed comparison of existing equipment and the aaterials identi-fied in Appendix C of the DOR guidelines.
The first supplement to IEB-79-018 requires licensees to utilize the table in Appendix C and identify any additional materials as the result of their effort.
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(2) Establiqh an ongoing program to review surveillance and maintenance records to identify potential age-related degradations.
(3) Establish component maintenance snd 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 example, 40 years). In its assessment of these submittals, the staff did not review the adequacy of the methodolcgy nor the basis used to i.ive at these values; the staff has assumed 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. 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 D0R guidelines, in NUREG-0588, and in the guidance previded in IEB-79-01B, 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 was qualified enveloped the requirements identified by the licensee.
The value required by the licensee inside containment is an integrated dose of 3.3 x 107 rads.
The radiation service condition provided by the licensee is lower than that provided in the 00R guidelines for gamma and beta radiation.
The licensee is requested to either provide the justification for using the lower service condition, or use the service condition provided in the D0R guidelines for both the gamma and heta radiation.
If the former option is chosen, then the analysis--including the basis, assumptions, and a sample calculation--should be provided.
A required value outside of containment of 1 x 107 rads has been used by the licensee to specify limiting radiation levels within the shutdown heat exchanger room, rmergency feedwater pump rooms, and the high pressure injection pump rooms of the auxiliary building. The licensee stated that the radiation environment outside the containment in these areas consists of the dose due to the recirculating primary coolant and the dose due to airborne activity in the building resulting from leakage of primary coolant.
This value appears to consider the radiation levels influenced by the source term methodology asso-ciated with post-LOCA recirculation fluid lines and is therefore 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 staff's 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 determination as to the stated conditions presented by the licensee. Additionally, the staff has not completed its review of 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 documents are found to be unacceptable, the licensee will be required to take additional corrective actions to either establish 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 which 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 the Commission 'demorandum and Order, that the deficien-cies identified do not necessarily mean that equipment is unqualified. However, they are cause for concern and may require further case-by-case evaluation.
4.1 Equipment Requiring Immediate Corrective Action Appendix A identifies equipment (if any) in this category.
The licensee was i
asked to review the facility's safety-related electrical equipment.
The licensee's review of this equipment has not identified any equipment requiring immediate corrective action; therefore, no licensee event reports (LERs) were submitted.
In addition, in this review, the staff has not identified aay safety-related electrical equipment which is not able to perform its intended safety function during the time in which it must operate.
4.2 Equipment Requiring 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 (identified below), indicating that the information provided is not sufficient for the qualification parameter or condition.
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Legend 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 S
- 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 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-ment, and equipment failure in the harsh environment will not impac.t safety-related functions or mislead an operator.
(2a) Equipment performs its function before its exposure to the harsh environ-ment, and the adequacy for the time margin provided is adequately justified, and (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 3quipment that has been adequate'y qualified and satisfies the single-failure criterion.
i (4) Equipment will not be subjected to a harsh environment as a result of the postulated accident.
The licensee is, therefore, required to supplement the information presented by providing resolutions to the deficiencies identified; these resciutions should include a description of the corrective action, schedules for its comnletion (as applicable), and so forth. The staff will review the licensee's response, when it is submitted, and discus 1 the resolution in a supplemental report. t
It should be noted that in cases where testing is being conducted, 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 Equipment Considered Acceptable 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
- used, (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 eouipment identified in item 1 or equipment that is qualified for less than the life of the plant.
The licensee is, therefore, required to supplement the information presenu d 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-mitted and discuss the resolutio. in a supplemental report.
5 DEFERRED REQUIREMENTS IEB 79-01B, 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 evaluation addressing these concerns.
6 CONCLUSIONS The staff has determined that the licensee's listing of safety related cystems and associated electrical equipment whose ability to function in a harsh environment following an accident is required to mitigate a LOCA or HELB is complete and acceptable, except as noted in Section 3 of this report.
The staff has also determined that the environmental service conditions to be met by the electrical equipment in the harsh accident environment are appropriate, except as noted in Section 3 of this report.
Gutstanding information identified in Section 3 should be provided within 90 days of receipt of this SER. -
The staff has reviewed the qualification of safety-related electrical equip-ment to the extent defined by this SER and has found no outstanding items which would require immediate corrective action to ensure the safety of plant operation.
However, the staff has determined that many items of safety-related electrical equipment identified by the licensee for this review do net have adequate documentation to ensure that they are capable of withstanding the harsh environmental service conditions.
This review was based on a comparison of the qualification values with the specified environmental values required by the design, which were provided in the licensee's summary sheets.
Subsection 4.2 identified deficiencies that must be resolved to establish the qualification of the equipment; the staff requires that the information lack-ing in this category be provided within 90 days of receipt of this SER.
Within this period, the licensee should either provide documentation of the missing qualification information which demonstrates that such equipment meets the D0R guidelines or NUREG-0588 or commit to a corrective action (requalifi-cation, replacement, relocation, and so forth) consistent with the requirements to establish qualification by June 30, 1982.
If the latter op' ion is chosen, the licensee must provide justification for operation until such corrective action is complete.
Subsection 4.3 identified acceptance and conditional acceptance based on noted deficiencies. Where additional information is required, the licensee should respond within 90 days of receipt of this SER by providing assurance that these concerns will be satisfactorily resolved by June 30, 1982.
The staff issued to the licensee Sections 3 and 4 of this report and requested, under the provisions of 10 CFR 50.54(f), that the licensee review the deficiencies enumerated and the ramifications thereof to determine whether safe operation of the facility would be impacted in consideration of the deficiencies. The
. licensee has completed a preliminary review of the identified deficiencies and has determined that, after due consideration of the deficiencies and their ramifications, continued safe operation would not be adversely affected.
Based on these considerations, the staff concludes that conformance with the above requirements and satisfactory completion of the corrective actions by June 30, 1982 will ensure coupliance with the Commission Memorandum and Order of May 23, 1980.
The staff further concludes that there is reasonable assurance of continued safe operation of this facility pending completion of these corrective actions.
This conclusion is based on the following:
(1) that there are no outstanding items which would require immediate correc-tive action to assure safety of plant operation (2) some of the items found deficient have been or are being replaced or relocated, thus improving the facility's capability to function following a LOCA or HELB (3) the harsh environmental conditions for which this equipment must be qualified result from low probability events; events which might reasonably be anticipated during this very limited period would lead to less demanding service conditions for this equipment..
a APPENDIX A Equipment Requiring Immediate Corrective Action (Category 4.1) i Item Equipment Manufacturer Model Deficiency i
None in this category.
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APPENDIX B Equipment Requiring 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 evaiuation, replacement schedule, ongoing equipment surveillance S - Submergence M - Margin I - HELB evaluation outside containment not completed QM - Qualification method RPN - Equipment relecation 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 Item Equipment Manufacturer Model Deficiency 1-001 Motor-Operated Valve EBV Systems Electrip RT,QT-M, Valve CS-E.vN,A I-G04 Motor-Operated Valve EBV Systems Electrip RT,QT-M, CS-EXN,.^
I-007 Motor-Operated Valve E3V Systems Electrip RT,QT-M, CS-EXN,A I-010 Motor-0perated Valva EBV Systems Electrip RT,QT-M, CS-EXN,A I-002 Motor-0perated Valve Limitorque SMB-3 CS,QI,A B-1
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APPENDIX B (Continued)
Item Equipment Manufacturer Model Deficiency I-005 Motor-Operated Valve Limitorque SMB-3 CS,QI,A I-008 Motor-0perated Valve Limiterque SMB-3 CS,QI,A I-011 Motor-0perated Valve Limitorque SMB-3 CS,QI,A I-013 Motor-Operated Valve Limitorque SMB-3 CS,QI,A I-014 Motor-0peraced Valve Limitorque SMB-3-100 CS,QI,A I-015 Motor-Operated Valve Limitorque SMB-000-10 CS,QI,A I-016 Motor-Operated Valve Limitorque SMB-000-5 CS,QI,A I-017 Motor-Operated Valve Limitorque SMB-000-5 CS,QI,A I-018 Motor-0perated Valve Limitorque SMB-000-5 CS,QI,A I-019 Motor-Operated Valve Limitorque SMB-000-5 CS,QI,A I-020 Motor-Operated Valve Limitorque SMB-000-5 CS,QI,A I-031 Motor-Operated Valve Limitorque SMB-000-5 CS,QI,A I-032 Motor-0perated Valve Limitorque SMB-000-7 CS,QI,A I-033 Motor-0perated Valve Limitorque SMB-000-5 CS,QI,A I-050 Motor Operated Valve Limitorque SMB-1-40 CS,QI,A I-051 Motor-Operated Valve Limitorque SMB-1-40 CS,QI,A I-025 Level Sensor EMS DeLeval XM-36496 T-M,P-M,A,5 I-026 Level Sensor EMS DeLeval XM-36496 T-M,P-M,A,5 I-027 Valve Motor Operator Rotork 70NAI(S)
CS,A l
I-034 Valve Operator Target Rock 74F-00-3-2 QT,RT,QI,CS,A I-035 Valve Operator
'Drget Rock 74F-015 QT,RT,QI,CS,A I-048 Valve Operator Target Rock 74F-012 QT,RT,QI,CS,A I-049 Valve Operator Target Rock 74F-011 QT,RT,QI,CS,A I-044 Motor Baldor N3S34TEFC QFM,CS,R,A l
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APPENDIX B (Continued)
Item Equipment Manufacturer Model Deficiency
'I-045 Motor Baldor N3534TEFC QFM,CS,R,A I-046 Motor Baldor N3534TEFC QFM,CS,R,A I-047 Motor Baldor N3S34TEFC-QFM,CS,R,A I-078 Valve Operator Limitorque SMS-0010 QI,A I-079 Valve Operator Limitorque SMB-0015 QI,A I-098 Pump Speed Sensors Bently Nevada T,P,M,R,QT, Corp CS,A I-099 Pump Speed Sensors Bently Nevada T,P,M,R,QT, Corp CS,A I-100 Pump Speed Sensors Bently Nevada T,P,M,R,QT, Corp CS,A I-101 Pump Speed Sensors Bently Nevada T,P,M,R,QT, Corp CS,A I-102 Pump Speed Sensors Bently Nevada T,P,M,R,QT, Corp CS,A I-103 Pump Speed Sensors Bently Nevada T,P,M,R,QT, Corp CS,A I-104 Pump Speed Sensors Bently Nevada T,P,M,R,QT, Corp CS,A I-105 Pump Speed Sen. ors Bently Nevada T,P,M,R,QT, Corp CS,A I-106 Pump Speed Sensors Bently Nevada T,P,M,R,QT, Corp CS,A I-107 Pump Speed Sensors Bently Nevada T,P,M,R,QT, Corp CS,A I-108 Pump Speed Sensors Bently Nevada T,P,M,R,QT, Corp CS,A I-109 Pump Speed Sensors Bently Nevada T,P,M,R,QT, Corp CS,A B-3
e APPENDIX B (Continued)
Item Equipment Manufacturer Model Deficiency I-110 Pump Speed Sensors Bently Nevada T,P,M,R,QT, Corp CS,A I-111 Pump Speed Sensors Bently Nevada T,P,M,R,QT, Corp CS,A I-112 Pump Speed Sensors Bently Nevada T,P,M,R,QT, Corp CS,A I-113 Pump Speed Sensors Bently Nevada T,P,M,R,QT, Corp CS,A I-114 Pump Speed Sensors Bently Nevada T,P,M,R,QT, Corp CS,A I-115 Pump Speed Sensors Bently Nevada T,P,M,R,QT, Corp CS.A I-116 Pump Speed Sensors Bently Nevada T,P,M,R,QT, Corp CS,A I-117 Pump Speed Sensors Bently Nevada T,P,M,R,QT, Corp CS,A I-118 Pump Speed Sensors Bently Nevada T,P,M,R,QT, Corp CS,A I-119 Pump Speed Sensors Bently Nevada T,P,M,R,QT, Corp CS,A I-120 Pump Speed Sensors Bently Nevada T,P,M,R,QT, Corp CS,A I-121 Pump Speed Sensors Bently Nevada
,T,P,M,R,QT, Corp CS,A I-122 Pump Speed Sensors Bently Nevada T,P,M,R,QT, Corp CS,A I-123 Pump Speed Sensors Bently Nevada T,P,M,R,QT, Corp CS,A I-124 Pump Speed Sensors Bently Nevada T,P,M,R,QT, Corp CS,A i
I-125 Pump Speed Sensors Bently Nevada T,P,M,R,QT, Corp CS,A B-4
APPENDIX B (Continued)
Item Equipment Manufacturer Model Deficiency I-126 Pump Speed Sensors Bently Nevada T,P,M,R,QT, Corp CS,A I-127 Pump Speed Sensors Bently Nevada T,P,M,R,QT, Corp CS,A I-128 Pump Speed Sensors Bently Nevada T,P,M,R,QT, Corp CS,A I-129 Pump Speed Sensors Bently Nevada T,P,M,R,QT, Corp CS,A I-130 Radiation Detector Victoreen 877-1 QI,A I-131 Radiation Detector Victoreen 877-1 QI,A I-135 Electrical Penetration Amphenol 3X350MCM(LV)
T,P,A I-136 Raychem Instrument QI,A Cable Outside Containment A-001 Motor Operator Limitorque SMB-00-10 QI,A A-003 Motor Operator Limitorque SMB-5-350 QI,A A-004 Motor Operator Limitorque SMB-000-5 QI,A A-005 Motor Operator Limitorque SMB-000-10 QI,A A-007 Motor Operator Limitorque SMB-5-350 QI,A A-008 Motor Operator Limitorque SMB-000-5 QI,A A-022 Motor Operator Limitorque SMB-000-2 QI,A A.-023 Motor Operator Limitorque SMB-000-2 QI,A A-024 Motor Operator Limitorque SMB-000-2 QI,A A-038 Motor Operator Limitorque SMB-000-2 QI,A A-041 Motor Operator Limitorque SMB-000-2 QI,A A-044 Motor Operator Limitorque SMB-000 R-QI,A B-5
APPENDIX B (Continued)
Item Equipment Manufacturer Model Deficiency A-045 Motor Operator Limitorque SMB-000 R-QI,A A-046 Motor Operator Limitorque SMB-000 R-QI,A A-047 Motor Operator Limitorque SMB-000 R-QI,A A-048 Motor Operator Limitorque SMB-000 R-QI,A A-050 Motor Operator Limitorque SMB-0005 R-QI,A A-051 Motor Operator Limitorque SMB-0005 R-QI,A A-052 Motor Operator Limitorque SMB-0005 R-QI,A A-055 Motor Operator Limitorque SMB-000-2 R-QI,A A-056 Motor Operator Limitorque SMB-000-2 R-QI,A A-057 Motor Operator Limitorque.
SMB-000-2 R-QI,A A-058 Motor Operator Limitorque SMB-000-2 R-QI,A A-059 Motor Operator Limitorque SMB-000-2 R-QI,A A-060 Motor Operator Limitorque SMB-000-2 R-QI,A A-061 Motor Operator Limitorque SMB-000-2 R-QI,A A-078 Motor Operator Limitorque SMB-0010 QI,A A-079 Motor Operator Limitorque SMB-00 QI,A A-080 Motor Operator Limitorque SMB-1-40 QI,A A-082 Motor Operator Limitorque SMB-00 QI,A A-083 Motor Operator Limitorque SMB-00 QI,A A-084 Motor Operator Limitorque SMB-1-40 QI,A A-087 Motor Operator Limitorque SMB-00 QI,A A-088 Motor Operctor Limitorque SMS-00 QI,A A-089 Motor Operator Limitorque SMB-00 QI,A 4'
A-091 Motor Operator Limitorque SMB-00 QI,A l
B-6 e
l
APPENDIX B (Continued)
Item Equipment Manufacturer Model Deficiency A-092 Motor Operator Limitorque SMB-00 QI,A A-093 Motor Operator Limitorque SMB-1-40 QI,A A-096 Motor Operator Limitorque SMB-000-5 QI,A A-097 Motor Operator Limitorque SMB-000 QI,A A-100 Motor Operator Limitorque SMB-0-15 QI,A A-101 Motor Operator Limitorque SMB-0-15 QI,A A-111 Motor Operator Limitorque SMB-000-5 QI,A A-112 Motor Operator Limitorque SMB-00 QI,A A-113 Motor Operator Limitorque SMB-00 QI,A A-130 Motor Operator Limitorque SMB-00-7 QI,A A-134 Motor Operator Limitorque SMB-000-5 QI,A A-140 Motor Operator Limitorqu<a SMB-000 QI,A A-145' Motor Operator Limitorque SMB-00-7h QI,A A-146 Motor Operator Limitorque SMB-00-7 QI,A A-150 Motor Operator Limitorque SMB-00-7 QI,A A-152 Motor Operator Limitorque SMB-00-7 QI,A A-002 Valve Operator Rockwell X
R,T,QM,QI,A A-006 Valve Operator Rockwell X
R,T,QM,QI,A l
A-009 Motor Reliance BHPACYA R,A l
A-010 Motor Reliance BHPACYA R,A A-011 Motor Reliance BHPACYA R,A A-012 Motor Reliance BHPACYA R,A A-013 Motor Reliance BHPACYA R,A i
l A-014 Motor Reliance BHPACYA R,A l
B-7 l
APPENDIX B (Continued)
Item Equipment Manufacturer Model Deficiency A-015 Cooler Motor Am. Air 5 HP R,T,QM, Filter Corp.
QI,A A-016 Cooler Motor Am. Air 10 HP R,T,QM, Filter Corp.
QI,A A-025 Motor Operator Electro / Dyne TN200/MB10 QM,QI,A A-026 Motor Operator Electro / Dyne TN200/MB10 QM,QI,A A-031 Motor Operator Electro / Dyne TN200/MB10 QM,QI,A A-032 Motor Operator Electro / Dyne TN200/MB10 QM,QI,A A-033 Motor Operator Electro / Dyne TN200/MB10 QM,QI,A A-036 Motor Operator Electro / Dyne TN200/MB10 QM,QI,A A-049 Motor Operator Electro / Dyne TN200/MB10 QM,QI,A A-062 Motor Operator Electro / Dyne TN200/M820 R,QI,A A-064 Motor Operator Electro / Dyne TN200/MB20 R,QI,A A-070 Motor Operator Electro / Dyne TN200/M820 R,QI,A A-071 Motor Operator Electro / Dyne TN200/MB20 R,QI,A A-027 Electr/ Hydro. Valve Civ. I. Corp.
QM,QI,A,T,R A-028 Electr/ Hydro. Valve Civ. I. Corp.
2340-390 T,R,QM,QI,A A-029 Electr/ Hydro. Valve Civ. I. Corp.
2340-390 T,R,QM,QI,A A-030 Electr/ Hydro. Valve Civ. I. Corp.
2340-390 T,R,QM,QI,A A-034 Rad Monitor Westinghouse 6S4 T,R,QM,QI,A A-035 Flow Switch ITT Barton 289A T,R,QM,QI,A A-037 Flow Switch ITT Barton 289A T,R,QM,QI,A A-063 Flow Switch ITT Barton 289A T,R,QM,QI,A A-065 Flow Switch ITT Barton 289A T,R,QM,QI,A A-066 Flow Switch ITT Barton 289A T,1,QM,QI,A 1
B-8
)
0 APPENDIX B (Continued)
Ite.n Equipment Manufacturer Model Deficiency A-067 Flow Switch ITT Barton 289A T,R,QM,QI,A A-068 Flow Switch ITT Barton 289A T,R,QM,QI,A A-069 Flow Switch ITT Barton 289A T,R,QM,QI,A A-136 Pressure Switch ITT Barton 288A T,R,QM,QI,A A-141 Pressure Switch ITT Barton 288A T,R,QM,QI,A A-144 Pressure Switch ITT Barton 288A T,R,QM,QI,A A-148 Pressure Switch ITT Barton 288A T,R,QM,QI,A
- A-094 Pressure Transmitter Foxboro E11DM R,QI,A
- A-095 Pressure Transmitter Foxboro E11DM R,QI,A A-072 Pump Motor Allis Chalmers 42 QM,R,A A-073 Pump Motor Allis Chalmers 42 QM,R,A A-074 Pump Motor Allis Chalmers 42 QM,R,A A-075 Pump Motor Allis Chalmers 42 QM,R,A A-076 Pump Motor Allis Chalmers 42 QM,R,A A-077 Flow Transmitter Fischer Porter 7210A-5503A82 QM,QI,A A-081 Flow Transmitter Fischer Porter 7210A-5503A82 QM,QI,A A-Obo Flow Transmitter Fischer Porter 7210A-5503A82 QM,QI,A A-090 Flow Transmitter Fischer Porter 7210A-5503A82 QM,QI,A A-098 Pump Motor Allis Chalmers 042 QM,R,A A-099 Pump Motor Allis Chalmers 042 QM,R,A A-131 Pump Motor Allis Chalmers 123 QM,QI,A A-108 Pump Motor GE SK6404AK233 QM,QI,A
^See Attachme ? 1:
Foxboro letter (3/12/81), " Potential Deficiency Affecti::g Foxboro Transuitters, for corrective action.
B-9
APPENDIX B (Continued)
Item Equipment Manufacturer Model Deficiency A-109 Pump Motor GE SK6404AK233 QM,QI,A A-110 Pump Motor GE SK6404AK233 QM,QI,A A-114 Fan Motor Westinghouse SBDP QM.QI,A A-115 Fan Motor Westinghouse SB QM,QI,A A-116 Fan Motor Westinghouse SB QM,QI,A A-119 Motor Operator Fisher Control QM,QI,A A-120 Motor Operator Fisher Control QM,QI,A A-121 Motor Operator Fisher Control QM,QI,A A-122 Motor Operator Fisher Control QM,QI,A A-125 Radiation Element Westingnouse T,QM,QI,A A-126 Radiation Element Westinghouse T,QM,QI,A A-127 Solenoid Valve Target Rock 74F-010 QM,QI,A A-128 Speed Transr.itter Terry Steam QM,QI,A Turbina Co.
A-129 Speed Transmitter Terry Steam QM,QI,A Turbine Co.
A-149 Valve Operator Copes Vulcan Electro /Hyd.
QM,QI,A,T A-151 Valve Operator Copes Vulcon Electro /Hyd.
QM,QI,T,A A-153 E/H Valve Actuator EBV Systems EFCO-MATIC 4 QM,QI,T,A Inc.
A-154 E/H Valve Actuator EBV Systems EFCO-MATIC 4 QM,QI,T,A Inc.
A-155 E/H Valve Actuator EBV Systeas EFCO-MATIC 4 QM,QI,T,A Inc.
A-156 E/H Valve Actuator EBV Systems EFCO-MATIC 4 QM,QI,T,A Inc.
B-10
4 r
APPENDIX B (Continued)
Item.
Equipment Manufecturer Model Deficiency
- I-052 Pressure Transmitter Foxboro E-11 A,R
- I-053 Pressure Transmitter Foxbora E-11 A,R
- I-054 Pressure Transmitter Foxboro E-11 A,R
- A-053 Pressure Transmitter Foxboro E11GM A,R
- A-054 Pressure Transmitter Foxboro E11GM A,R
- A-117 Pressure Transmitter Foxboro E130M A,R
- A-118 Pressure Transmitter Foxboro E13DM A,R
- A-123 Pressure Transmitter Foxboro E13DM A,R l
- A-124 Pressure Transmitter Foxboro E13DM A,R f
- A-132 Pressure Transmitter Foxboro E13DM A,R
- A-133 Pressure Transmitter Foxboro E11GM A,R
- A-137 Pressure Transmitter Foxboro E11DM A,R
- A-138 Pressure Transmitter Foxborc E11GM A,R
- A-142 Pressure Transmitter Foxboro E13DM A,R
- A-143 Pressure Transmitter Foxboro E13DM A,R l
l
- See Attachment 1:
Foxboro letter (3/12/81), " Potential Deficiency Affecting Foxboro Transmitters, for corrective action.
l l
B i
APPENDIX C Equipment Considered Acceptable or Conditionally Acceptable (Category 4.3)
LEGEND:
Designation for Deficiency 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 S - 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 Item Equipment Manufacturer Model Deficiency I-003 Position Switch NAMCO 180 A
l I-006 Position Switch NAMCO 180 A
I-009 Position Switch NAMCO 180 A
j I-012 Position Switch NAMCO 180 A
l I-021 Pressure Transmitter Rosemount 1153AA6 A
I-022 Pressure Transmitter Rosemount 1153AA6 A
I-023 Pressure Trarsmitter Rosemount 1153AA6 A
t l
C-1 i
l L
APPENDIX C (Continued)
Item Equipment Manufacturer Model Deficiency I-024 Pressure Transmitter Rosemount 1153AA6 A
I-064 Pressure Transmitter Rosemount 1153 A
I-065 Pressure Transmitter Rosemount 1153 A
I-066 Pressure Transmitter Rosemount 1153 A
I-067 Pressure Transmitter Rosemount 1153 A
I-069 Pressure Transmitter Rosemount 1153 A
I-070 Temperature Detector Rosemount 104 A
I-071 Temperature Detector Rosemount 104 A
I-072 Temperature Detector Rosemount 104 A
I-073 Temperature Detector Rosemount 104 A
I-074 Temperature Detector Rosemount 104 A
I-075 Temperature Detector Rosemount 104 A
I-076 Temperature Detector Rosemount 104 A
I-077 Temperature Detector Rosemount 104 A
I-082 Level Transmitter Rosemount 1153 A
I-083 Level Transmitter Rosemount 1153 A
I-084 Level Transmitter Rosemount 1153 A
I-085 Level Transmitter Rosemount 1153 A
I-086 Pressure Transmitter Rosemount 1153 A
i I-087 Pressure Transmitter Rosemount 1153 A
I-088 Pressure Transmitter Rosemount 1153 A
I-089 Pressure Transmitter Rosemount 1153 A
I-090 Level Transmitter Rosemount 1153 A
I-091 Level Transmitter Rosemount 1153 A
C-2
APPENDIX C (Continued)
Item Equipment Manufacturer Model Deficiency I-092 Level Transmitter Rosemount 1153 A
I-093 Pressure Transmitter Rosemount 1153 A
I-094 Pressure Transmitter Rosemount 1153 A
I-095 Pressure Transmitter Rosemount 1153 A
I-096 Pressure Transmitter Rosemount 1153 A
I-097 Pressure Transmitter Rosemount 1153 A
4 I-036 Motors Reliance EA0 A
I-037 Motors Reliance EA0 A
I-038 Motors Reliance EA0 A
I-039 Motors Reliance EA0 A-I-040 Motors Reliance EA0 A
I-041 Motors Reliance EA0 A
I-042 Motors Reliance EA0 A
I-043 Motors Reliance EA0 A
I-056 Temperature Detector Rosemount 104 A
I-057 Temperature Detector Rosemount 104 A
I-058 Temperature Detector Rosemount 104 A
I-059 Temperature Detector Rosemount 104 A
I-060 Temperature Detector Rosemount 104 A
i I-061 Temperature Detector Rosemount 104 A
I-062 Temperature Detector Rosemount 104 A
(
I-063 Temperature Detector Rosemount 104 A
I-080 H Recombiner Westinghouse A
2 l
C-3
APPENDIX C (Continued) bn Equipment Manufacturer Model Deficiency I-081 H Recombiner Westinghouse A
2 I-132 Splice Kit Raychem WCSF--N,ANK-A I-133 Connectors Conax 7590 A
I-134 Cable Anaconda Various A
Outside Containment A-085 Valve Motor Operator Rotark 70NA-2 A
A-102 Valve Motor Operator Rotark 40A A
A-103 Valve Motor Operator Rotark 40A A
A-104 Valve Motor Operator Rotark 40A A
A-105 Valve Motor Operator Rotark 40A A
A-106 Valve Motor Operator Rotark 40A A
A-107 Valve biotor Operator Rotark 40A A
C-4
APPENDIX D Safety-Related Systems Listi Function System Emergency Reactor Shutdown Reactor Coolant Reactor Protection Safeguards Actuation Chemical and Volume Control Containment Isolation Main Steam Emergency Feedwater Liquid Radwa.te Boron Management Gaseous Radwaste Chilled Water Sampling Containment Spray Recirculation Residual Heat Removal i
Chemical and Volume Control Main Feedwater l
IThe NRC staff recognized that there are differences in nomenclature of systems because of plant vintage and engineering design; consequently, some systems performing identical of similar functions may have different names.
In those instances it was necessary to verify the function of the system (s) with the responsible IE vegional reviewer and/or the licensee.
D-1
APPENDIX D (Continued)
Function System Reactor Core Cooling Low Pressure Safety Injection High Pressure Safety Injection Accumulators Containment Heat Removal Containment Spray Containment Sump Recirculation Containment Ventilation Core Residual Heat Removal Residual Heat Removal Pressurizer Spray (2)
'ower Operated Relief Valves Main Feedwater Auxiliary Feedwater Main Steam Steam Dump (2)
Component Cooling Water Service Water i
Prevention of Significant Release Containment Spray (Iodine Removal) of Radioactive Material to Environment Hydrogen Recombiners l
Radiation Monitoring Sampling l-I Supporting Systems Emergency Power l
Area Ventilation l
Control Room Ventilation l
D-2
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