ML19347D180
| ML19347D180 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 02/25/1981 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19347D179 | List: |
| References | |
| NUDOCS 8103110404 | |
| Download: ML19347D180 (25) | |
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4 PARTIAL REVIEW EQ'IPMENT EVALUATION REPORT BY THE J
OFFICE OF NUCLEAR REACTOR REGULATION FOR METROPOLITAN EDISON COMPANY THREE MILE ISLAND UNIT 1 DOCKET NO. 50-289 i
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PARTIAL REVIEW EQUIPMENT EVALUATION REPORT BY THE OFFICE OF NUCLEAR REACTOR REGULATION FOR METROPOLITAN EDISON COMPANY THREE MILE ISLAND UNIT 1 DOCKET NO. 50-289 i
3 STAFF EQUIPMENT EVALUATION The staff evaluation of the licensee's response included an onsite inspection of selected Class IE equipment and an examination of the licensee's report for completeness and acceptability. The criteria described in the DOR 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 (1) a preliminary evaluation of the licensee's response, documented in a technical evaluation report (TER) and (2) an onsite verification inspection (July 28-August 1, 1980) of selected safety-related electrical equipment.
Components of the reactor protection and make-up and purification systems were inspected.
The inspection verified proper installation of equipment, overall interface integrity, location with respect to flood level for equipment inside the containment, and manufacturers' nameplate data. The manufacturer's name and model number from the nameplate data were compared to information given in the Component Evaluation Work Sheets (CES).of the licensee's report. The site inspection is documented in report IE 50-289/80-20. The deficiencies noted are discussed in this ER.
For this review, the documents-referenced above have 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 o) systems and equipment that are required to mitigate a LOCA and an HELB and (2) identify component; 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 wall 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).
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 i
shutdown, (2) containment isolation, (3) reactor core cooling, (4) containment heat removal, (5) core residual heat removal, and (6) prevention of signif t-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 l
this report.
Dis). lay instrumentation which provides information for the reactor operators to aid them in the safe handling of the plant was not specifically identified by the Mcensee.
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 which is not considered to be safety relateo 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 should be providid that its subsequent failure will not mislead the operator or adverself affect the mitigation of the consequences of the accident. The envirorAental qualifi-cation of post-accident sampling and monitoring and radiadon monitoring equipment is closely related to the review of the TMI Le.ssons-Learned modifi-cations and will be performed in conjunction with that review.
The licensee identified 275 items of equipment which were assessed by,the staff.
3.2 Service Conditions Commission Memorandum and Order CLI-80-21 requires that the DOR guidelines and the "For Comment" NUREG-0588 are to be used as the criteria for establishing i
the adequacy of the safety-related electrical equipment 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 staff has assumed, unless otherwise noted, that the analysis for developing the environmental envelopes for Three Mile Island Unit 1, 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 containment spray system which satisfies the single-f ailure cri-l terion, the main-steam-line-break (MSLB) environmental conditions are enveloped by the large-break LOCA environmental conditions. The staff assumed, and requires the licensee to verify, that the containment spray system is not subjected to a disabling single-component failure and therefore satisfies the l
requirements of Section 4.2.1 of the D0R guidelines.
Equipment submergence has also been addressed where'the possibility exists that flooding of equipment may result from HELBs.
l I
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3.3 Temperature, Pressure, and Humidity Conditions Inside Containment The licensee has provided the results of accident analyses as follows:
Max Temp (*F)
Max Press (psig)
Humidity (%)
LOCA 275 50.6 100 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.
L'se 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 MSLB, whichever is controlling, as to potential adverse environmental effects on equipment.
The licensee's specified temperature (service condition) of 275*F does not satisfy the above requirement. A saturation temperature corresponding to the peak profile (298*F peak temperature at 50.6 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 tMt the equipment will perform its intended function under the specified conditions or propose corrective action..
3.4 Temperature, Pressure, and Humidity Conditions Outside Containment The licensee has provided the temperature, pressure, humidity and applicable environment associated with an MSLB within the intermediate building..
The staff has verified that the parameters identified by the licensee for the MSLB are acceptable.
3.5 Submergence The maximum submergence levels have been established and assessed by the licensee.
Unless otherwise r.oted, 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 5.94 ft. The licensee identified only Ra.' chem heat shrink tubing as having the potential for becoming submerged after a postulated event, and the work sheet indicates that this component is qualified for submergence.
However, the onsite inspection report indicates that Limitorque motor operators MU-V'2A and MU-V-2B in the make-up and purifi-cation system are below the calculated flood level.
Therefore, before plant restart, the licensee shoald either verify that these motor operators are in fact not subject to submergence or provide documentation showing that the motor operators and associated cables are qualified for, submergence.
If qualification documentation does not exist, the licensee may provide an accept able basis to exempt.this equipment from qualification by providing the information discussed in Section 4.2 of this ER. __
The onsite inspection of a very limited number of components indicated that the valve operators discussed above are below the calculated flood level.
Because the submittal does not indicate the elevation of eqLipment, before plant restart the licensee should verify that, other than the equipment discussed above, no equipment has the potential for becoming submerged.
3.6 Chemical Spray The licensee's FSAR value for the chemical concentration is 2270 ppm boron and sodium hydroxide (NaOH) to raise the pH to 9.5.
Only the work sheet for Raychem heat shrink tubing provides enough information to show qualification for chemical spray. Therefore, for the purpose of this review, the effects of enemical 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 g_ing 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 identified in Appendix C of the D0R guidelines.
The first supplement to IEB-79-01B requires licensees to utilize the table in Appendix C ind identify any additional materials as the result of their effort.
(2) Establish an ongoing program to review surveillance and maintenance records to identify potential age. elated 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 j
of the mett.odology nor the basis used to arrive at these values; the staff has I
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. For equipment for t:hich a materials evaluation has already I
been performed, items (2) and (3) above should be addressed. The response j
should include all the equipment identified as required to maintain functional l
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 t
it is submitted and discuss its evaluation in a supplemental report.
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i 3.8 Radiation (Inside and Outside Containment)
The licensee has provide:: 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-79-01B, 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 2 x 107 rads.
The radiation service condition provided by the licensee is lower than provided in the 00R guidelines for gamma and beta radiation.
The licensee is requested to either provide justification for using the lower service condition or use the service condition provided in the DOR guidelines for both gamma and beta 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 containment of 3.4 x 108 rads has been used by the licensee to specify limiting radiation levels for the decay heat removal pumps in the auxiliary building.
This value considers the radiation levels influenced by the source term methodology associated with post-LOCA recirculatio'n fluid lines and is therefore acceptable.
For some equipment, the licensee has used a calculated integrated radiation dose at I hour after a LOCA as the required radiation environment. Without additional justification (as discussed in Section 4.2 of this SER),.specifying these lower radiation levels is not acceptable and, therefore, radiation has been listed as a deficiency for these components.
Radiation has also been identified as a deficiency if the licensee used other than the values listed in Appendix C of the DDR guidelines, unless the Appendix C values also enveloped the specified value.
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 Memorandum and Order, that the deficien-cies identified do not necessarily mean that equipment is unqualified. However, they ar'e cause for concern and may require further case-by-case evaluation.
4.1 Equipment Requiring Corrective Action Prior co Restart The licensee Event Reports submitted by the licensee to date identifying equipment in this Category are attached.
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.
Legend R
- radiation l
T
- temperature QT qualification time RT - required time P
pressure H
- humidity CS - chemical spray A
- material-agirq evaluation; replacement cchedule; ongoing equipment i
surveillance S
- submergence 6-w
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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 deficit. ries do not necessarily mean that the equipent is unqualified. However, the deficiencies are cause for concern and require further case-by-case evaluation. The staff has determined that an acceptatle basis to exempt equipment from qualification, in whole or part, can be established provided the following can be established anti 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 impact 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 ha sh environment does r.ot degrade other safety functions or mislead the opt ator.
(3) The safety-related function can be accomplished by some o_ner designated equipment that has been adequately qualified and satisfier, the s. ingle-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 supplement 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 the licensee's response, when it is submitted, and discuss the resolution in a supplemental report.
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 j
the equipment in Appendix C as (1) acceptable on the basis that the qualifi-i cation program adequately enveloped the specific environmental plant parameters, l _
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 th6t 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 onCoing 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.
The licensee is, therefore, required to supplement the information presented 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 resolution 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.
APPENDIX B Equipment Requiring Additional Information and/or Corrective Action (Category 4.2)
MGEND:
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 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 Equipment Description Manufacturer Plant ID No.
Deficiency Pressure Switch Static-0-Ring PS-600 QT,P,H,CS,R,A,EXN Fressure Switch Static-0-Ring PS-601 QT,P,H,CS,R,A,EXN i
Preswre Switch Static-0-Ring PS-602 QT,P,H,CS,R,A,EXN Pressure Switch Static-0-Ring PS-603 QT,P,H,CS,R,A,EXN l
Pressure Switch Static-0-Ring PS-604 QT,P,H,CS,R,A,EXN Pressure Switch Static-0-Ring PS-605 QT,P,H,CS,R,A,EXN Pressure Switch Static-0-Ring PS-606 QT,P,H,CS,R,A,EXN Pressure Switch Static-0-Ring PS-607 QT,P,H,CS,R,A,EXN Pressure Transmitter Foxboro SP6A-PT1 CS,A B-1
APPENDIX B (continued)
Equipment Description Manufacturer Plant ID No.
Deficiency Pressure Transmitter Foxboro SP6A-PT2 CS,A Pressure Transmitter Foxboro SP6B-PT1 CS,A Pressure Transmitter Foxboro SP6B-PT2 CS,A Limit Switch
?
LSA/MSV-6 QT,T,P,H,R A.RPN Limit Switch
?
LSB/MSV-6 QT,T,P,H,R,A,RPN Limit Switch NAMCO LSB/MSV-13A T,P,H,A,EXN Limit Switch NAMCO 33/MSV-13A T,P,H,A,EXN Solenoid Valve ASCO SV/h
-13A T,P,H,A,EXN Solenoid Valve ASCO SV/MSV-13B T,P,H,A,EXN Limit Switch NAMCO LSA/MSV-13B T,P,H,A,EXN Limit Switch NAMCO LSB/MSV-13B T,P,H,A,EXN' Motor Westinghouse EF-P2A QT,T,P,H,A Motor Westinghouse EF-P2B QT,T,P,H,A Motor Operator Limitorque EF-V-1A M,A Motor Operator Limitorque EF-V-1B M,A Motor Operator Limitorque EF-V-2A M,A Motor Operator Limitorque EF-V-2B M,A Solenoids
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EF-V-30A QT,T,P,H,R,A,RPN Cont. Pn1 SV1 & SV3 1
Solenoids
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EF-V-30A QT,T,P,H,R,A,RPN Cont. Pnl.SV2 & SV4 Solenoids
?
EFV-30B QT,T,P,H,R,A,RPN Cont. Pn1 SV1 & SV3 Solenoids
?
EFV-30B QT,T,P,H,R,A,RPN Cont. Pn1 SV2 & SV4 Motor Operator Limitorque FW-V-SA QT,T,P,H,R,A l
Motor Operator Limitorque FW-V-SB QT,T,P,H,R,A B-2 l
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APPENDIX B (continued)
Equipreent Descrip, tion Manufacturer Plant ID No.
Deficiency Motor Operator Limitorque FW-V-92A QT,T,P,H,R A Motor Operator Limitorque FW-V-928 QT,T,P,H,R,A Limit Switch NAMCO LSB/MUV-26 R,A Solenoid Valve ASCO SV/MUV-26 R,A,EXN Pressure Switch Square O PS480A R,A Pressure Switch Square D PS480B R,A Pressure Switch Square D PS480C R,A Motor Operator Limitorque MU-V-2A CS,A,5 Motor Operator Limitorque MU-V-28 CS,A,5 Limit Switch NAMCO LSA/MUV-3 R,A Limit 5' itch NAMCO LSB/MUV-3 R,A w
Solenoid Valve ASCO SV/MUV-3 R,A,EXN Solenoid Valve Ross SV/MUV-18 R,A Limit Switch NAMCO LSA/MUV-18 R,A Lin.it Switch NAMc0 LSB/MUV-18 R,A Limit Switch NAMCO LSA/MUV-20 R,A Limit Switch NAMC0 LSB/HUV-20 R,A Solenoid Valve Ross SV/MUV-20 R,A Motor Operator Limitorque MU-V-25 CS,A Limit Switch NAMCO LSA/MUV-26 R,A Motor Operator Limitorque DH-V-1 CS,A Motor Operator Limitorque DH-V-2 CS,A Limit Switch NAMCO LSA/AHV-1A R,A Limit Switch NAMCO LSB/AHV-1A R,A Solenoid Valve ASCO SV/AHV-1A1 R,A,EXN B-3
APPENDIX B (continued)
Equipment Description Manufacturer Plant ID No.
Deficiency Solenoid Valve
' ASCO SV/AHV-1A2 R,A,EXN Motor Operator Limitorque CA-V-1 CS,A Solenoid Valve ASCO SV/CAV-2 R,A,EXN Limit Switch NAMCO LSA/CAV-2 R,A Limit Switch NAMCO LSB/CAV-2 R,A Motor Operator Limitorque CA-V-3 CS,A Motor Operator Limitorque CA-V-4A CS,A Motor Operator Limitorque CA-V-4C CS,A Motor Operator Limitorque CA-V-13 CS,A Limit Switch Micro Switch LSA/CAV-189 R,A Limit Switch Micro Switch LSB/CAV-189 R,A Solenoid Valve ASCO SV/CAV-189 R,A Motor Operator Limitorque IC-V-2 CS,A Solenoid Valve ASCO 20/ ICV-3 R,A Limit Switch NAMCO 33/ ICV-3 R,A Limit Switch NAMCO LSB/ ICV-3 R,A l
l Limit Switch NAMCO LSA/RBV-7 QT,T,P,H,R,A,2PS i
j Limit Switch NAMCO LSB/RBV-7 QT,T,P,H,R,A,RPS i
Solenoid Valve ASCO SV/RBV-7 QT,T,P,H,R,A,RPS Motor Operator Limitorque WDG-V-3 CS,A l
Solenoid Valve ASCO SV/WDG-V4 R,A Limit Switch Micro Switch LSA/WDG-V4 R,A Limit Switch Micro Switch LSB/WDG-V4 R,A Motor Operator Limitorque WDL-V-303 CS,A B-4 i
I
APPENDIX B (continued)
Equipment Description Manufacturer Plant ID No.
Deficiency Limit Switch NAMC0 LSA/WDLV-304 R,A Limit Switch NAMCO LSB/WDLV-304 R,A Solenoid Valve ASCO SV/WDL-V304 R,A Limit Switch NAMCO LSA/WDL-V534 R,A Limit Switch NAMCO LSB/WDL-V534 R,A Solenoid Valve ASCO SV/WDL-V534 R,A Limit Switch NAMC0 LSA/WDL-V535 R,A Limit Switch NAMCO LSB/WDL-V535 R,A Solenoid Valve ASCO SV/WDL-V535 R,A Pressure Transmitter Rosemount RC3A-PT1 CS,R,A Pressure Transmitter Rosemount RC3A-PT2 CS,R,A Pressure Transmitter Rosemount RC3B-DT1 CS,R,A Pressure Transmitter Rosemount RC3B-PT2 CS,R,A Temp. Transmitter Rosemount RC4A-TE2 CS,A,EXN Temp. Transmitter Rosemount RC4A-TE3 CS,A,EXN Temp. Transmitter Rosemount RC48-TE2 CS,A,EXN Temp. Transmitter Rosemount RC4B-TE3 CS,A,EXN Pressure Switch Static-0-Ring PS-672 R,A Pressure Switch Static-0-Ring PS-673 R,A Pressure Switch Static-0-Ring PS-674 R,A Pressure Switch Static-0-Ring PS-675 R,A Pressure Switch Square D PS-283 R,A Pressure Switch Square D PS-284 R,A Pressure Switch Square D PS-286 R,A I
Pressure Switch Square D PS-287 R,A i
B-5
APPENDIX B (continued)
Equipment Description Manufacturer Plant ID No.
Deficiency Pressure Switch Square D PS-289 R,A Pressure Switch Square D PS-290 R,A Pressure Transmitter Foxboro RC3A-PT3 CS,A Pressure Transmitter Foxboro RC3A-PT4 CS,A Pressure Transmitter Foxboro RC38-PT3 CS,A Fan Motor GE AH-E-1A CS,A Fan Motor GE AH-E-1B CS,A Fan Motor GE AH-E-1C CS,A Motor Operator Limitorque CF-V-1A CS,R,A,EXN Motor Operator Limitorque CF-V-1B CS,R,A,EXN f
Motor Operator Limitorque CF-V-2A' CS,M,A l
Motor Operator Liniitorque CF-V-28 CS,M,A
. Motor Operator Limitorque CF-V-3A CS,A Motor Operator Limitorque CF-V-3B CS,A I
Limit 5,iitch Micro Swtich LSA/CiV-19A R,A Limit Switch Micro Swtich LSB/CFV-19A R,A Limit Switch Micro Swtich LSA/CFV-19B R,A Limit Switch Micro Swtich LSA/CFV-19B R,A Solenoid Valve ASCO 20/CF-V19A R,A Solenoid Valve ASCO 20/CF-V198 R,A Limit Switch Micro Switch LSA/CFV-20A R,A Limit Switch Micro Switch LSB/CFV-20A R,A Limit Switch Micro Switch LSA/CFV-208 R,A l
Limit Swtich Micro Switch LSB/CFV-20B R,A Solenoid Valve ASCO SV/CF-V20A R,A B-6 a
APPENDIX B (continued)
Equipment Description Manufacturer Plant ID No.
Deficiency Solenoid Valve ASCO SV/CF-V208 R,A Motor Operator Limitorque NS-V-35 QT,T,P,H,CS,R A Level Transmitter Bailey Meter SP1A-LT2 CS,A Level Transmitter Bailey Meter SPIB-LT2 sCS,A Level Transmitter Bailey Meter SP1A-LT4 CS,A Level Transmitter Bailey Meter SPIB-LT4 CS,A Level Transmitter Bailey Heter RCl-LTI CS,A Level Transmitter Bailey Meter RCl-LT2 CS,A Level Transmitter Bailey Meter RCl-LT3 CS,A Temp. Transmitter Rosemount RC5A-TE1 CS,A,EXN Temp. Transmitter Rosemount RC5A-TE2 CS,A,EXN Temp. Transmitter Rosemount PCSA-TE3 CS,A,EXN Temp. Transmitter Rosemount RC5A-TE4 CS,A,EXN Temp. Transmitter Rosemount RC5B-TEI CS,A,EXN Temp. Transmitter Rosemount RC5B-TE2 CS,A,EXN Temp. Transmitter Rosemount RC5B-TE3 CS,A,EXN Temp. Transmitter Rosemount RC5B-TE4 CS,A,EXN Terminal Block States Co.
Various CS,R,A Model No. NT Electrical GE Various CS,A,EXN Penetration Assembly Model No. F01 Instrument Cable Anaconda Various CS,A Power & Control Cable Kerite Various CS,A Valve Control Center ITE, Gould 1A-ES-VLV CC QT,T,P,H,R,A Valve Control Center ITE, Gould IB-ES-VLV CC QT,T,P,H,R,A Valve Control Center ITE, Gould IC-ES-VLV CC QT,T,P,H,R,A B-7
i APPENDIX B (continued)
Equipment Description Manufacturer Plant IG No.
Deficiency Conax Connectors Conax Rosemount QT,T,P,H,CS,R,A Connectors PL-14-82 Conax Connectors Conax (sailey Connectors CS,R,A TG-14-2 Conax Connectors Conax Bailey Connectors CS,R,A PL-16-B4 t
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B-B
APPENDIX C Equipment Co'nsidered 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 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 3
QI - Qualification information being developed RPS - Equipment relocation or replacement schedule provided Equipment Description Manufacturer Plant ID No.
Deficiency Pump Motor Westinghouse MU-P1A A
Pump Motor Westinghouse MU-P1B A
Pump Motor Westinghouse MU-PIC A
Pump Motor GE MU-P2A A
Pump Motor GE MU-P2B A
Pump Motor GE MU-P2C A
Pump Motor GE MU-P3A A
Pump Motor GE MU-P3B A
A Pump Motor GE MU-P3C l
C-1 l'
. ~,
APPENDIX C (continued)
Equipment Description Manufacturer Plant ID No.
Deficiency Motor Operator Li.mitorque MU-V-36 A
Motor Operator Limitorque MU-V-37 A
Pump Motor Westinghouse MU-P4A A
Pump Motor Westinghouse MU-P48 A
Pump Motor Westinghouse MU-P4C A
Motor Operator Limitorque MU-V-12 A
Motor Operator Limitorque MU-V-14A A
Motor' Operator Limitorque MU-V-14B A
Motor Operator Limitorque MU-V-16A A
Motor Operator Limitorque MU-V-16B A
Motor Opsrator Limitorque MU-V-16C A
Motor Operator Limitorque MU-V-16D A
Pump Motor Westinghouse DH-P1A A
Pump Motor Westinghouse DH-PIB A
Motor Operator Limitorque DH-V-3 A
Motor Operator Limitorque DH-V-6A A
Motor Operator Limitorque DH-V-6B A
Motor Operator Limitorque DH-V-7A A
Motor Operator Limitorque DH-V-78 A
4 Pump Motor Westinghouse DC-P1A A
Pump Motor Westinghouse DC-P1B A
Solenoid Valve ASCO SV/DCV-19A A
Limit Switch NAMC0 LSA/DCV-19A A
Limit Switch NAMC0 LSB/DCV-19A A
Solenoid Valve ASCO SV/DCV-198 A
C-2
APPENDIX C (continued)
Equipment Description Manufacturer Plant ID No.
Deficiency Limit Swtich NAMCO LSA/DCV-19B A
I Limit Swtich NAMCO LSB/DCV-19B A
Limit Swtich NAMCO LSA/AHV-10 A
Limit Swtich NAMCO LSB/AHV-1D A
Solenoid Valve ASCO SV/AHV-lD1 A
Solenoid Valve ASCO SV/AHV-102 A
Limit Switch NAMC0 LSA/CAV-5A A
Limit Switch NAMC0 LSB/CAV-5A A
Solenoid Valve ASCO SV/CAV-5A A
Limit Switch NAMCO LSA/CAV-5B A
Limit Switch NAMC0 LSB/CAV-58 A
Solenoid Valve ASCO SV/CAV-5B A
o Limit Switch NAMCO LSA/CMV-1 A
Limit Switch NAMCO LSB/CMV-1 A
Solenoid Valve ASCO SV/CMV-1 A
Limit Switch NAMC0 LSA/CMV-2 A
Limit Switch NAMCO LSB/CMV-2 A
Solenoid Valve ASCO SV/CMV-2 A
Limit Switch NAMCO LSA/CMV-3 A
Limit Switch NAMCO LSS/CMV-3 A
So'
- Valve ASCO SV/CMV-3 A
Lim 1, Switch NAMCO LSA/CMV-4 A
Limit Switch NAMCO LSB/CMV-4 A
Solenoid Valve ASCO SV/CMV-4 A
Solenoid Valv?
ASCO 20/ ICV-t A
C-3
APPENDIX C (continued)
Equipment Description Manufacturer Plant ID No.
Deficiency Limit Switch NAMCO 33/ ICV-4 A
Limit Switch NAMCO LSB/ ICV-4 A
Limit Switch NAMCO 33/ ICV-6 A
Limit Switch NAMCO LSB/ ICV-6 A
Solenoid Valve ASCO SV/ ICV-6 A
Motor Operator Limitorque RB-V-2 A
Pump Motor Westinghouse BS-P1A A
Pump Motor Westinghouse BS-PIB A
Mote-Operator Limitorque BS-V-1A A
Motor Operator Limitorque BS-V-1B A
f Motor Operator Limitorque BS-V-2A A
Motor Operator Limitorque BS-V-28 A
Motor Operator Limitorque BS-V-38 A
Neutron Detector Westinghouse NI-5 Exempt Neutron Detector Westinghouse NI-6 Exempt Neutron Detector Westinghouse NI-7 Exempt Neutron Detector Westinghouse NI-8 Exempt Pressure Transmittar Foxboro PT-282 A
Pressure Transmitter Foxboro l'T-285 A
Pressure Transmitter Foxboro PT-288 A
Motor Operator Limitorque RR-V-3A A
Motor Operator Limitorque RR-V-38 A
Motor Operator Limitorque RR-V-3C A
Motor Operator Limitorque RR-V-4A A
Motor Operator Limitorque RR-V-48 A
C-4
APPENDIX C (continued)
Equipment Description Manufacturer Plant ID No.
Deficiency Motor Operator Limitorque RR-V-4C A
Motor Operator Limitorque RR-V-4D A
Pump Motor Westinghouse NS-PlA A
Pump Motor Westinghouse NS-PIB A
Pump Motor Westinghouse NS-PIC A
Motor tperator Limitorque NS-V-4 A
Motor Operator Limitorque NS-V-15 A
Moto'r Operator Limitorque NS-V-32 A
Limit Switch NAMC0 LSA/NSV-52A A
Limit Switch NAMCO LSB/NSV-52A A
Solenoid Valve ASCO SV/NSV-52A A
Limit Switch NAMC0 LSA/NSV-52B A
Limit Switch NAMC0 LSB/NSV-52B A
Solenoid Valve ASCO SV/NSV-52B A
Limit Switch NAMCO LSA/NSV-52C A
Limit Switch NAMCO LSB/NSV-52C A
Solenoid Valve ASCO SV/NSV-52C A
Limit Switch NAMCO LSA/NSV-53A A
Limit Switch NAMCO LSB/NSV-53A A
Solenoid Valve ASCO SV/NSV-53A A
Limit Switch NAMCO LSA/NSV-53B A
Limit Switch NAMCO LSB/NSV-53B A
Solenoid Valve ASCO SV/NSV-53B A
Limit Switch NAMCO LSA/NSV-53C A
Limit Switch NAMCO LSB/NSV-53C A
C-5
d APPENDIX C (csntinued)
Equipment Description Manufacturer Plant ID ;40.
Deficiency Solenoid Valve ASCO SV/NSV-53C A
Heat Shrink Tubing Raychem None; Model A
No. Thermofit O
?.
6 C-6
APPENDIX D Safety-Related Systems List 1 (Category 4.4)
Function System Emergency Reactor Shutdown Reactor Protection Engineered Safeguards Actuation Make-up and Purification Containment Isolation Make-up and Purification Fes water d
Decay.' st Removal Sampling Main Feedwater Main Steam Reactor Building Spray Reactor Building Isolation 2 Reactor Core Cooling Make-up and Purfication (HPI)
Core Flood Tanks Containment Heat Removal Reactor Building Spray Reactor Building Air Recirculation and Cooling Containrent Sump Recirculation Core Residual Heat Removal Decay Heat Removal Decay Heat Closed Loop Cooling Nuclear Services Closed Cooling Water Nuclear Services River Water Main Steam Main Feedwater Emergency Feedwater 8
Power Operated Relief Valves IThe 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 responsible IE regional reviewer and/or the licensee.
1 Includes other isolation valves in systems not listed above.
"To be covered as part of TMI-2 lessons learned.
D-1
q APPENDIX D (Continued).
Function System Prevention of Significant Release Reactor Building Spray of Radioactive Material to (Iodine Removal)
Environment Containment Combustible Gas Contro18 Containment Radiation Monitoring Containment Radiation Sampling
- Supporting Systems Emergency Power
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Safety Equipment Area Ventilatica Control Room Habitability (HVAC) 5 I
l l
l l
I D-2