ML20003E116
| ML20003E116 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 03/27/1981 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20003E114 | List: |
| References | |
| NUDOCS 8104020273 | |
| Download: ML20003E116 (25) | |
Text
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PARTIAL REVI W EQUI?!'E!;T EVALUATION REPORT SY THE OFFICE OF !;UCLEAR REACTOR REGULATION FOR ;EERASKA PUBLIC F0WER DISTRICT COOPER I;UCLEAR STATION DOCKET NO. 50-298 8104020 d73
EQUIPMENT EVALUATION REPORT BY THE OFFICE OF NUCLEAR REACTOR REGULATION FOR NEBRASKA FU5LIC POWER DISTRICT COOPER NUCLEAR STATION DOCKET NO. 50-298 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 fer ccepleteness 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 perfereec (1) a preliainary evaluation of the licensee's response, documented in a technical evaluation report (TER) and (2) an onsite verification inspection of selected safety-related electrical equipment.
Cc ponents of the aute:atic depressurization and the high pressure coolant injection systems were inspected.
The inspec-tien verified prcper instaliation of equip: rent, overall interface integrity, 1ccation with respect to f1ced level for equip =ent inside the containment, and canufacturers' nameplate data.
The manufacturer's name anc eccel nut::er frc:
the naceplate data were compared to information given in tne Ccepenent Evalua-tion Work Sheets (CES) of the licensee's report. The site inspection is documented in a May 12, 1980 repert.
No deficiencies were acted.
For this revies, the docu=ents-referenced above have been factored into the overall staff evaluation.
3.1 Cc=cleteness of Safety-Related Ecuic=ent In accordance with IES79-015, the licensee was directed to (1) establish a list of systems and equipment that are required to mitigate a LOCA a'nd an HELE and (2) identify cc ponents needed to perform the function of safety-related display infor=ation, post accident sampling and scnftering, and radiation
=cnitoring.
The staff develcped a generic master list based upon a revies of plant safety analyses and emergency procedures.
The instru=entation selected includes paramstars to ecnitor 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 ce performed for accident mitigation (without regard to location of equipment relative to hostile envirencents).
The list of safety-related systems provided by the licensee was reviewed against the: staff-developed = aster list.
Eased on the licensee's submittal, the staff has concluded that the informatica en safety-related systems included in the submittal is insufficient to verify that those systens are' cil the systems required to achieve or support:
(1) 5:srgency reactor shutdown, (2) contain=ent isolation, (3) reactor core cooling,
(*) contain ent heat removal, (5) core residual heat removal, and (6) preventien.
of significant release of radioactive material to the environment.
The staff acknowledges the licensee's effort to include only those safety related systems located in a potentially harsh environment.
However, this review requires the listing of all safety-related systems, both inside and outside potentially harsh environments.
The list of safety-related systems submitted by the licensee is included in Appendix D.
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 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 should be provided that its subse-quent failure will not mislead the operator or adversely affe:t the mitigation of the consequences of the accident.
The environmental qualification of pcst-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 266 items of equipment which were assessed by the staff.
3.2 Service Conditions o=nission Memorandum and Order CLI-80-21 requires that the DDR guidelines and
~
'.he "For Comment" NUREG-0588 are to be used as the criteria for establishing the adequacy of the safety related electrical equipment environmental quali-fication program.
These documents provide the option of establishing a bounding pressure and temperature cor.dition 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 develeping the environmental envelopes for Cooper Nuclear Station, 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-failure cri-terion, the main-steam-line-break (MSLB) environmental conditions are enveloped by the large-break-LOCA envircnmental 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
-recuirements of ~ Section 4.2.1 of the 00R guidelines.
I 4
]
Equipment submergence has also been addressed where the possibility exists that flooding of equipment may result from HELBs.
l 3.3 Temperature. Pressure, and Humidity Conditions Inside Containment The licensee nas provided the results of accident analyses as follows:
t Max Temp (*F)
Max Press (psic)
Humidity (%)
LOCA 340 56 100 The staff has concluded that the minimum temperature profile for equipment qualification purposes shculd include a margin to account for analytical 2 -
uncertainties in the calculated temperature profiles for postulated accidents.
A margin of 20 F above steam saturation temperature is considered to be appropriate for either a postulated LOCA or MSLB, whichever is controlling as to potential adverse environmental effects on equipment.
The licensee's minimum temperature profile for qualification purposes include a margin at least as large as would result from the staff's recommendation.
Therefore, the staff concludes that the specified temperature profile is acceptable.
3.4 Temperature, Pressure, and Humidity Conditions Outside Containment
- The licensee has provided'the temperature, pressure, humidity, and applicable environment associated with HELBs outside containment.
The following areas outside containment have been addressed:
'(1) Main steam tunnel (2) NW, NE, and SE Quads, elevation 859 ft 9 in, and 881 ft 9 in.
(3) Torus area, elevation 859 ft 9 in. and 881 ft 9 in.
(4) South RHR quad, elevation 859 ft 9 in.
_ (5) HPCI room, elevation 859 ft 9 in.
(6) South RHR quad, elevation 881 ft 9 in.
(7) -Torus area, elevation 903 ft 6 in.
(8) RHR heat exchanger rooms, elevation 903 ft 6 in'. and 931 ft 6 in.
(9) RWCU pump room and torus area, elevation 931 ft 6 in.
(10) GWCU heat exchanger room, elevation 931 ft 6 in.
(11) Reactor-building, elevation 958 ft 5 in. and 976 ft (12) Turbine building heat bay area (13) Turbine building condenser area (14) Turbine _ building operating floor, elevation 932 ft 6 in.
(15) Turbine building, elevation 882 ft 6 in.
(16) Injection valve room, elevation 903 ft 6 in.
(17) RCIC quad,1 elevation 859 ft 9 in. and 881 ft 9 in.
- (18) RWCU pump room, elevation 931 ft 6 in.
.(19) RHR quads,. elevation 859 ft 9 in.
(20) RHR quads, elevation 881 ft 9 in.
(21)~ Injection valve room, elevation 903 ft 6~in.
(22) Torus area, elevation 903 ft 6 in.
(23) Reactor buiicing, elevation 958 ft 5 in. and 976-ft-4,
.,em
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v.
<,~ +, -
w,
,w 4+<1 w-
- +*
- +-e
--w r-cr
The staff has verified that the parameters identified by the licensee for the MSLB are acceptable.
3.5 Submeroence 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 level inside containment is 16 in.
The licensee has not identificd any equipment inside containment below this level.
In the event of a feedwater line break in the steam tunnel, the NE corner compartment at elevation 859 f t 9 in, would experience a flood level of approximately 19 ft.
The licensee has identified two Static-0-Ring pressure switches as having the potential for becoming submerged in this area.
The licensee has stated that the B side of the core spray system would be unaffected by this break and could be used should these pressure switches fail.
In this regard, the licensee should provide an assessment of the failure modes associated with the submergence of the pressure switches.
The 1icensee 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 spectrur of events, in relation to the time of submergence.
If the results of the licensee's assess-ment are acceptable, then the components may be exempt from, the suenergence parameter of qualification, 3.6 Chemical Sora_v
' Chemical sprays are not utilized at Cooper Nuclear Station.
Camineralized water sprays in the containment and suppression chamber may be manually actuated by the operator, but they are not an engineered safety feature.
The staff has found this acceptable.
However, if the sprays beccee an engineered safety feature, their effects should be addressed.
3.7 Jaino Section 7 of the DDR guidelines does not require a qualified life to be estat-lished for all safety-related electrical equipment.
However, the follcwing actions are required:
(1) Make a detailed comparison of existing equipment and the materials icentified in Appendix C of the 00R guidelines.
The first supplement to IEE-79-01B requires licensees to utilize the table in Appendix C and 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-related degracations.
(3) Establish c0tponent maintenance and replacement scnecules wnich irciace censideratior.s of aging characteristics of the installed cor:crects.
The licensee icentified a number of equip:ent items for which a specified cualified life was established (for exa:ples, 5 years, 15 years, or 40 years).
In its assess:ent of these sub=ittals, the staff did not review the adequacy of the cethecology nor the basis used to arrive at these values; the staff nas assured that the established values are based on state-of-the-art technoicgy and are acceptable.
For this review, however, the staff requires that the licensee submit sucple-cental inferr.atica to verify and identify tne cegree of confor:ance to the above requirements.
The responu should incluce all the ecuipment identified as required to maintain functicnal operability in harsh enviren ents.
The licensee indicated that this phase of the response is cu* standing and tnat the review is in progress.
The staff will review the licensee's respcnse wten it is submitted and discuss its evcluaticn in a supplemental report.
3.5 Raciatien (Inside and Outside Centair ent) ine licensee nas provided values for the raciatien levels pcstulated to exist folle ing a LOCA.
The applicatien anc =etnccology e: ployed te cetermine these values were presented to the licensee as part of the NRC staff criteria con-tained in the DDR guidelines, in NUREG-0555, and in tne guidance provided in IEE-79-013, Supple:ent 2.
Therefore, for this review, the staff nas assured tnat, unless otnerwise noted, the values proviced nave been deter ined in accordance with the prescribed criteria.
The staff review deter ined that the values to which equipment was cualified enveleped the require ents identified by the licensee.
The value required by the licensee insice contain ent is an integrated dose of
%.4 x 107 racs.
This value envelcpes the COR guideline require:ents and is therefore acce:: table.
A required value cutside centainment of 1.5" x 108 rads has teen used by the licensee to specify limiting radiation levels within the steam tunnel.
Inis value acpears to censider the radiatien levels influenced by the scurce ter rathedclegy asscciated with ; cst-LOCA recirculatien fluid lines and is inere-fcre acceptable.
4 QL'ALIFICATION OF EQUIPMENT The 'ollcwing subsections present the staff's assesscent, based en the licensee's st.bnittal, of the qualification status of safety related electrical equi; tent.
The staff has. separated the' safety-related ecuipeent into three categcries:
(1) e;uipment requiring icceciate corrective action, (2) equipment recuiring additicnal qualification infer:ation and/or corrective action, and (3) equip-r.ent considered acceptable if the staff's concern identified in Section 3.7 is satisfactorily resolved.
In i s assessment of the licensee's sub=ittal, the NRC staff dic not review the ethecciogy en::loyed to cetermine the values establisned by the licensee.
-: wever, in reviewing the data sheets, the staff = ace a ceterminatica as to -
3
i the stated conditions preschted by the lictnies IA ilionitif, t he i t t f f hr.1 1
not cc ;,1cted its review / of supporting document: tion iefe.enud by t!.e liccn-see (for example, test reports).
It is expected thct sehen the revice of test reports is cor.plete, the environmental qualificttion data bcnk established by 2
the staff will prov.ide the reans to cross referen:e each supporting docu..;ent to the referencing licensee.
If supporting docu:,ents are found to be unacceptable, the licensce 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 apoendix 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 apper. dices to identify deficiencies.
It should be noted, as in the Cc mission tiemera:dum and Order, that the deficien-cies identified do not necessarily mean that equiptant is unqualified.
- However, they 'are cause' for concern and may require further case-by-case evaluation.
4.1 Ecuiccent Recuiring Ir ediate Corrective Action I
f 4.2 Ecuionent Recuiring Additional I.'ormation and/or Corrective Action Aipendix 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 informatien provided is not sufficient for the qualification parameter or condition.
Lecend R
- radiation T
- temperature QT --. qualification tire RT' - required time P
pressure H=
humidity CS - chemical spray.
A'
- caterial-aging evaluation; replacement schedule; engoing equip =ent.
surveillance.
5
- submergence
'M'
- cargin.
I'
- HELB evaluation cutside containment ~ not cc:pleted Q't - qualification cethed R?R -equipment relocation or replacement;l 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 qualiffcation, in whole er 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 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 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 supplement the information presented by provicing resolutions to the deficiencies identified; these resolutions should include a description of the corrective action, schedules for its completion (as applicable), and so farth. 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 beirg conducted, a condition may arise wnich res::lts in a determination by the licensee that the equiptent does not satisfy the qualific&tien test requirements.
For that equipment, tne licensee will be required to provw the proposed corrective action, on a ticely basis, to ensure that qualiffcation can be established by Jum 30, 1982.
4.3 Eouictent-Considered Acceptable or Conditior. ally Acceotable
- 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 cualifi-cation program adequately enveloped the specific environmental plant parameters, or (2) conditionally acceptable subject to the satisfactory resolution of the staff ccncern 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 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
- EE 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 reqLired that this information be pro-eided by February 1,1981.
The staff will provide a supplemental safety evaluation addressing these concerns.
4 e
-E-
APPENDIX B Equipment Requiring Additional Information and/or Corrective Action (Category 4.2)
LEGEND:
Desicnation for Deficiency R --Radiation T - Temperature QT - Qualification time RT - Required time P - Pressure H - Humidity C5 - Chemical spray A - Material aging evaluation, replacement schecule, ongoing equipment surveillance-5 - Submergence M - Margin I - HELS evaluation outside containment not cc.mpletea 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 scheduie provided Equipment Descriction Manufacturer Concenent No.
Deficiencv Temperature Switch Fenwal Inc.
TS-101A P,M,QM,A Temperature Switch.
Fenwal Inc.
TS-1015 P,M,QM,A Temperature Switch Fenwal Inc.
TS-102A P,M, Q!, A Temperature Switch Fenwal Inc.
TS-1C2B P,M,QM,A Tet;erature Switch Fenwei Inc.
_TS-1 3A P,M,QM,A Temperature Seiten Fenwal Inc.
TS-1C35 P,M,QM,A Temperature Switch Ferwal Inc.
TS-10*A P,M,QM,A Tem:erature Switch Fenwal Inc.
TS-IC43 P,M,CM,A
' Jab.e Tc cr.C:ntreis General Electric-
"0-15-57R QT,R,A,QM
.E'.e "c ce Ccn r-is General Electric M;-17-sir QT,R,A,QM sai.e Motor Cen *cis
. General Electric MO-EE-STR QT,R, A,CM E-1
APPENDIX B (Continued)
Equipment
~Descriotion Manufacturer Comconent No.
Deficiency Pressure Switch Static-0-Ring HPCI-PS-54-1 P,A,QM,M,R Pressure Switch Static-0-Ring HPCI-PS-85 P,A,QM,M,R Pressure Switch Static-0-Ring HPCI-PS-97A P,A,QM,M,R Pressure Switch Static-0-Ring HPCI-PS-973 P,A,QM,M,R Pressure Switch Static-0-Ring HPCI-PS-5EA QT,T,P,H,R,A,QM,M Pressure Switch Static-0-Ring HFCI-PS-655 QT,T,P,H,R,A,CM,M Pressure Switch Static-0-Ring HPCI-PS-65C QT,T,P,H,R,A,QM,M Pressure Switch Static-0-Ring HPCI-PS-6ED QT,T,P,H,R,A,QM,M Differential Pressure Barton HPCI-CPIS-75 QT,T,P,H,R,A,QM,M Indicating Switch.
Differential Pressure Barton HPCI-CPIS-77 QT, T, P, H, R, A, Q!i, M Indicating Switch Turbine Control'Ecx Woodsard Governor HPCI-CBX-2792 QT,R,A Hydraul_ic Actuator Woodward Governor HPCI-CHA-2792 QT,R,A Pemote Servo Motor Woodward Governor HPCI-CRSM-2792 QT,R,A Turbine Signal Woodward Governor-HPCI-SC-279; QT,R,A Converter Magnetic Speed Pick-Up Woodward Governor HPCI-SE'2792 QT,R,A Solenoid Vaive ASCO HPCI-AVSPV-275 QT,T,P,H,R,A,QM,M
-Scienoid Valve ASCO HPCI-AVSPV-550 QT,7,P,H,R,A,QM,M Solenoid Valve ASCO HPCI-AV5PV-565
-QT,A Solenoid. Valve ~
ASCO HPCI-AVSPV-566 QT,A Solenoid Valve-ASCO HPCI-AVSPV-782 QT,A Sciencid Vaive ASCO HPCI-AV5PV-783 QT,A Limit Switch NAMCO HPCI-275AV-LS QT.T,P,H,R,A,'M,M Q
B APPENDIX B (Continued)
Equipment Description Manufacturer Comoonent No.
Deficiency Limit Switch NAMCO HPCI-782AV QT,A Limit Switch NAMCO HPCI-783AV QT,A Limit Switch Microswitch 565AV QT,A Limit Switch Microswitch 566AV QT,A Flow Transmitter General Electric HPCI-FT-82 QT,T,P H,R,A,QM,M g
Flow Indicator /
General Electric HPCI-FIC-108 QT,T,P,H,R,A,QM,M Controller Motor Operator Limitorque HPCI-MO-14 QT,T,P,H,R,A,QM,M Motor Operator Limitorque HPCI-MO-15 T,H,R,QM,M,A Motar Operator Limitorque HPCI-MO-17 QT,R,A,QM Motor Operator Limitorque HPCI-M0-19 QT,T,P,H,R,A,QM,M Motor Operator Limitorque HPCI-MO-20 QT,R,A Motor Operator Limitorque HPCI-MO-21 QT,R,A Motor Operator Limitorque HPCI-MO-24 QT,R,A Motor Operator Limitorque HPCI-MO-25 QT,R,A Motor Operator Limitorque HPCI-MO-57 QT,T,P,H,R,A,QM,M Motor Operator Limitorque HPCI-MO-58 QT,R,A Pressure Transmitter General Electric HPCI-PT-83 QT,T,P,H,R,A,QM,M Pressure Transmitter General Electric HPCI-PT-95 QT,T,P,H,R,A,QM,M Pressure Transmitter-General Electric HPCI-PT-100 QT,T,P,H,R,A,QM,M Aux. Oil Pump Motor General llectric Unknown QT,R,A Aux. Oil Pump Motor General Electric Unknown QT,R,A Motor Starter Motor 0:erator Control General Electric MO-14-STR QT,T,P,H,R,A,QM,M Motor' Operator Control General Electric HPCI-MO-19-STR QT,R,A B-3
1 APPENDIX B (Continued)
Equipment Descriotion Manufacturer Comconent No.
Deficiency Motor Operator Control General Electric HPCI-MO-20-STR QT,R,A Motor Operator Control General Electric HPCI-MO-21-STR QT,R,A Motor Operator Control General Electric HPCI-MO-24-STR QT,R,A Motor Operator Control General Electric HPCI-MO-25-STR QT,R,A Pressure Switch Barksdale RCIC-PS-87A QT,T,P,H,R,A,QM,M Pressure Switch Barksdale RCIC-PS-878 QT,T,P,H,R,A,QM,M Pressure f. witch Barksdale RCIC-PS-87C QT,T,P,H,R,A,QM,M Pressure Switch Barksdale RCIC-PS-870 QT,T,P,H,R,A,QM,M Pressure Switch Static-0-Ring RCIC-PS-83 P,A,QM,M,R Pressure Switch Barksdale RCIC-PS-72A P,A,QM,M,R Pressure Switch Barksdale RCIC-PS-72S P,A,QM,M,R Pressure Switch Barksdale RCIC-PS-67 P,A,QM,M,R
!btor Operator Control General Electric RCIC-MO-18-STR QT,T,P,H,R,A,QM,M Matcr Operator Control General Electric RCIC-MO-30-STR QT,T,P,H,R,A,QM,M Motor Operator Control General Electric RCIC-MO-33-STR QT,T,P,H,R,A,QM,M Mctor Operator Control General Electric MO-20-STR QT,T,P,H,R,A,QM,M Motor Operator Control-General Electric MO-21-STR QT,T,P,H,R,A,QM,M Motor Operator Control
. General Electric MO-27-STR QT,T,P,H,R,A,QM,M Motor Operator Control General Electric MO-16-STR QT,T,P,H,R,A,QM,M Motor Operator Control General Electric MO-131-STR QT,T,P,H,R,A,QM,M Flow Indicating Switch Barton.
'RCIC-FIS-57 QT,T,P,H,R,A,QM,M
~ Differential Pressure Barton RCIC-DPIS-83 QT,T,P,H,R,A,QM,M Indicating Switch Differential Pressure Bar en RCIC-CPIS-54 QT,T,P,H,R,A,QM,M Incicating~ Switch B-a w
y--
r
--?
i APPENDIX B (Continued)
Equipment Descriotion Manufacturer Comconent No.
Deficiency Pressure Switch Barksdale RCIC-PS-78 P,A,QM,M,R EGM Control Box Woodward Governor RCIC-CSX-3067 QT,T,P,H,R,A,QM,M Turbine Control-Woodward Governor RCIC-CHA-3067 QT,T,P,H,R,A,QM,M Hydraulic Actuator Turbine Control Woodward Governor RCIC-CRSM-3067 QT,T,P,H,R,A,QM,M Remote Servo Motor Signal Converter Woodward Governor.
RCIC-SC-3067 QT,T,P,H,R,A,QM,ft Speed Mag Pickup Woodward Governor RCIC-SE-3067 QT,T,P,H,R,A,QM,M Electrical Overspeed Ruggles-Klingeman RCIC-ST-3068 QT,T,P,H,R,A,QM,M Trip Motor Operator Limitorque RCIC-MO-15 T,H,R,M,A Motor Operator Limitorque RCIC-M3-16 T,M,A Flow Transmitter General Electric RCIC-FT-58 iTT,T,P,H,R,A,QM,M Kotor Operator Limitorque RCIC-M3-21 T,M,A Motor Operator Limitorque RCIC-MJ-41 R,QM,A Motor Operator Limitorque RCIC-MJ-18 R,QM,A Solenoid Valve ASCO RCIC-AVSPV-780 QT,T,P,H,R,A,QM,M Solenoid Valve ASCO RCIC-AVSPV-781 QT,T,P,H,R,A,QM,M Limit Switch NAMC0 RCIC-780-AV-LS QT,T,P,H,R,A,QM,M Limit Switch NAMCO-RCIC-781-AV-LS QT,T,P,H,R,A,QM,M Motor-0perator Linitorque
-RCIC-M3-33 R,QM,A
- Pressure Transmitter General Electric RCIC-PT-60 QT,T,P,H,R,A,QM,M Pressore Transmitter General Electric RCIC-PT-65 QT,T,P,H,R,A,QM,M Pressure Transmitter General Electric RCIC-FT-70 QT,T,P,H,R,A,QM,M Differential Pressure Barton RHR-DPIS-125A QT,T,P,H,R,A,QM,fi Indicating Switch c
B-5
. ~...
APPENDIX B (Continued)
Equipment Description Manufacturer Comoonent No.
Deficiency Differential Pressure Barton RHR-OPIS-125B QT,T,P,H,R,A,QM,M Indicating Switch Flow Transmitter General Electric FT-109A QT,T,P,H,R,A,QM,M Flow Transmitter General Electric FT-1098 QT,T,P,H,R,A,QM,M Pressure Switch Static-0-Ring RHR-PS-270 P,A,QM,M,R Motor Operator Limitorque RHR-MO-15A H,QM,A Motor Operator Limitorque RHR-MO-15C H,QM,A Motor Operator-Limitorque RHR-MO-15B T,QM,M,A Motor Operator Limitorque RHR-MO-150 T,QM,M,A Motor Operator Limitorque RHR-MO-13A H,R,QM,A Motor Operator Limitorque RHP,-MO-13B T,QM,M,A Motor Operator Limitorque RHR-M0-13D T,QM,M,A Solenoid Valve' ASCO RHR-AVSPV-312 QT,T,P,H,R,A,QM,M Solenoid Valve ASCO RHR-AVSPV-332 QT,T,P,H,R,A,QM,M Limit Switen-NAMCO RHR-AO-68A QT, T, P, H, R, A, QM,11
~
Limit Switch NAMCO RHR-A0-68B QT,T,P,H,R,A,QM,M Motor Operator Limitorque RHR-M0-17 T,R,QM,M,A Motor' Operator Limitorque RHR-MO-18 QT,T,P,H,R,QM,M,A Motor Operator Limitorque.
RHR-MO-25A-P,QM,M,A Motor Operator.
Limitorque RHR-M0-258 P,QM,M,A Motor Starter ITE RHR-MO-25A QT,T,P,H,A,QM,M Motor Starter ITE RHR-M0-25B QT,T,P,H,A,QM,M tjotor Operator Limitorque RHR-MO-65A T,QM,M,A Motor Operator Limitorque RHR-MO-65E T,QM,M,A B-6
APPENDIX B (Continued)
Equipment Descriotion Manufacturer Component No.
Deficiency Motor Operator Limitorque RHR-MO-66A T,QM,M,A Motor Operator Limitorque RHR-MO-66B T,QM,M,A Motor Operator Limitorque RHR-MO-274A QT,T,P,H,QM,M,A Motcr Operator Limitorque RHR-MO-274B QT,T,P,H,QM,M,A Motor Operator Limitorque RHR-MO-12A T,QM,M,A Mottr Operator Limitorque RHR-MO-12B T,QM,M,A Motor Operator Limitorque MD-16B T,QM,M,A Motor Operator Limitorque MO-348 T,QM,M,A Motor Operator Limitorque MO-38 T,QM,M,A Motor Operator Limitorque MO-39B T,QM,M,A Pu p Motor
-General Electric RHR-P-1A QT,T,P,H,R,A,QM,M Pc:p "otor General Electric RHR-P-1C QT,T,P,H,R,A,QM,M Pump General Electric RHR-P-1B QT,T,P,H,R,A,QM,M Pump General Electric RHR-P-10 QT,T,P,H,R,A,QM,M Motcr Operator Limitorque MO-31A QT,P,QM,M,A Motor l Operator Limitorque MO-318 QT,P,QM,M,A Meter Operator Limitorque M3-26A QT,T,P,R,QM,M,A Motcr. Operator
-Limitorque MO-263 QT,T,P,R,QM,M,A Motor Operator Limitorque MO-32 QT, T, P, R,Q!j, M, A Motor. Ope rator' Limitorque MO-21A T,QM,M,A
_ Motor Operator Limitorque MO-218 T,QM,M,A Pressure Switch Static-0-Ring.
CS-PS-37A P,A,QM,M,5,R
?sessere Switch.
Static-0-Ring _
CS-PS-373 P,R,A,QM,M Pressure Switch-Static-0-Ring PS-43A-P,R,A,5,QM,M
~B-7 L,
APPEh0IX B (Continued)
Equipment Descriotion Manufacturer Comconent No.
Deficiency Pressure Switch Static-0-Ring PS-448 P,R,A,QM,M Solenoid Valve ASCO CS-AVSPV-684 QT,T,P,H,R,A,QM,M Limit Switch NAMCO CS-AO-13A-LS QT,T,P,H,R,A,QM,M 4
Limit Switch NAMCO CS-AO-135-LS QT,T,P H,R,A,QM,M Pump "eter General Electric CS-P-1A QT,T,P,H,R,A,QM,M
? ump Meter General Electric CS-P-1B QT,T,P,H,R,A,QM,M Motor Operater Limitorque CS-MO-5A P,QM,M,A Motor Operator Limitorque CS-MO-5B P,QM,M,A Motor Operatcr Limitorque CS-MO-7A QT,P,QM,M,A Motor Operater Limitorque CS-MO-7B QT,P,QM,M A F
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ADPENDIX C Equipment Considered Acceptable or Conditionally Acceptable (Category 4.3)
LEGEND:
Desicnation for Ceficiency R - Radiation T - Temperature QT - Qualification tire RT - Required tice P - Pressure H - Humidity CS - Chemical spray A - Material acing evaluation, replacement schedule, ongoing equipment surveillance 5 - Submergence M - Margin I - HELS evaluation cutside containment not ccepleted
. QM - Qualifica icn'rethod RPN - Equipment relocation or replacement, adequate schedule not provided EXN - Exempted equipment justification inadequate SEN - Separate effects qualificatier. justification inadequate QI - Qualification information being developed RPS - Equipment relocatica er replacecer.t schedule prcvided Equipment Descriction Manufacturer Cc:conent No.
Ceficiency
~ Temperature Switch Fenwal Inc.
TS-101C A
Tecperature Switen Fenwal :nc.
TS-1010 A
Terperature Switen Fenwai Inc.
TS-102 A
~
Temperature Switen Fenwal Inc.
TS-1020 A
Temperature Switen Fenwal Inc.
TS-105C A
Temperature Switen Fenwal Inc.
TS-10SD A
. Temperature Switch Fenwal Inc.
-TS-10'C A
Tar era ure.Swi ch Fenwal :nc.
TS-IC ":-
A Temperature Switch' Feneal Inc.
TS-125A Tenperature Switc.4
- enwal Inc.
T5-1253 A
n.,
'b e
APPENDIX C (Continued)
Equipment Descriotion Manufacturer Comconent No.
Deficiency Temperature Switch Fenwal Inc.
TS-125C A
Temperature Switch Fenwal Inc.
TS-125D A
Temperature Switen Fenwal Inc.
TS-126A A
Temperature Switch Fenwal Inc.
TS-1263 A
Temperature Switch Fenwal Inc.
TS-126C A
Temperature Switch Fenwal Inc.
TS-1260 A
Temperature Switch Fenwal Inc.
TS-127A A
Temperature Switch Fenwal Inc.
TS-127B A
Temperature Switen Fenwal Inc.
TS-127C A
Temperature Switch Fenwal Inc.
TS-127D A
Temperature Switch-Fenwal Inc.
TS-128A A
' Temperature Switch Fenwal Inc.
TS-12EE A
Temperature Switch Fenwal Inc.
TS-12SC A
Temperature Switch Fenwal Inc.
TS-1280 A
Motor Operator Limitorque HPCI-MO-16 A
Temperature Switch' Fenwal Inc.
RCIC-TS-79A A
Temperature Switch Fenwal Inc.
RCIC-TS-75B A
Temperature Switch Fenwal Inc.
RCIC-TS-790 A
Temperature Switch Fenwal Inc.
RCIC-TS-79D A
' Temperature Switch Fenwal Inc.
RCIC-TS-80A A
Temperature Switch Fenwal Inc.
RCIC-TS-803 A
Temperature Switch Fenwal Inc.
RCIC-TS-SCC A
Temperature Switch Fenwal Inc.
RCIC-TS-500 A
Temperature Switch Fenwal Inc.
RCIC-TS-SIA A
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APPENDIX C (Continued)
Squipment Descriotion Manufacturer Cc cenent No.
Deficiency Te:perature Switch Fenwal Inc.
RCIC-TS-SIS A
Terperature Switch Fenwal Inc.
RCIC-TS-SIC A
Te:perature Switch Fenwal Inc.
RCIC-TS-8ID A
Terperature Switen Fenwal Inc.
RCIC-TS-82A A
Tetperature Switen Fenwal Inc.
RCIC-TS-82B A
Temperature Switen Fenwal Inc.
RCIC-TS-E2C A
Temperature Switch Fenwal Inc.
RCIC-TS-820 A
Mctor Operator Limitorque RCIC-MO-30 A
Meter Operator Limitorcue RCIC-MC-131 A
Motcr Operator Limiterque RCIC-MO-20 A
Meter Operater Limitercue RCIC-MO-27 A
, Mater Operator-Limiterque RCIC-MO-35A A
Meter Cperater Limitorque RCIC-MO-35B A
Terperature Switch Fenwal Inc.
RHR-TS-150A A
Temperature Switch-Fenwal Inc.
RHR-TS-1503 A
Te ;erature Seitch
'Fenwal Ir.c.
RHR-TS-1500 A
.Te:perature Switch Fenwal Inc.
RHR-TS-1503 A
Temperature Switch Fenwal Inc.
RHR-TS-152A A
Temperature Switch Fenwal Inc.
RHR-TS-1523 A
Temperature Switch Fenwal Inc.
RHR-TS-152C-A Temperature Switch Fenwal Inc.
RHR-TS-IS2D A
Te perature-Ssitch Fenwal~Inc.
RHR-TS-152A A
=Tercerature Switen -
Fenwal Inc.
RHR-TS-1532 A
Te perature Switch ~
Fenwal Inc.
RHR-TS-153C-A C-3
APPENDIX C (Continued) 5quipment i
Descriotion Manufacturer Co:conent No.
Deficiency Te :erature Switch Fenwal Inc.
RHR-TS-1530 A
Temperature Switch Fenwal Inc.
RHR-TS-154A A
Temperature Switch Fenwal Inc.
RHR-TS-154C A
r Temperature Switch Fenwal Inc.
RHR-TS-155A A
Te :erature Switch Fenwal Inc.
RHR-TS-155C A
Te perature Swit;h Fenwal Inc.
RHR-TS-156A A
Te:;erature Switch Fenwal Inc.
RHR-TS-156C A
Temperature Switch Fenwal Inc.
RHR-TS-157A A
e :erature Switch Fenwal Inc.
RHR-TS-157C A
Temperature Switch Fenwal Inc.
RHR-TS-154B A
Temperature Switch Fenwal Inc.
RHR-TS-154D A
T,e ;erature Switch Fenwal Inc.
RHR-TS-1553 A
i s :erature Switch Fenwal Inc.
RHR-TS-155D A~
e ;erature Switch Fenwal Inc.
RHR-TS-1563 A
Temperature Switch Fenwal Inc.
RHR-TS-1550 A
Temperature Switch-Fenwal Inc.
RHR-TS-1575 A
'- e ;erature Switch Fenwal Inc.
RHR-TS-1570 A-Temperature Switch Fcqwal Inc.
RHR-TS-ISSA A
Temperature Switch
~Fenwal Inc.
RHR-TS-15SC A
Temperature Switch Fenwal Inc.
RHR-TS-159A A
Temperature Switch Fenwal Inc.
RHR-TS-159C A
-emperature Switch.
Fenwal Inc RHR-TS-160A A
-e :erature Swi ch Fenwal Inc.
RHR-TS-160C A
6 C-4
4 APPENDIX C (Continued)
Equipment Descriotion Manufacturer Comoonent No.
Deficiency
- Temperature Switch Fenwal Inc.
RHR-TS-161A A
Temperature Switch Fenwal Inc.
RHR-TS-161C A
Temperature Switch Fenwal Inc.
RHR-TS-1583 A
Temperature Switch Fenwal Inc.
RHR-TS-1553 A
Temperature Switch.
Fenwal Inc.
RHR-TS-1595 A
Tecperature Seiten Fenwal Inc.
RHR-TS-1593 A
Temperature Switch Fenwal Inc.
RHR-TS-1603 A
Temperature Switen Fenwal Inc.
RHR-TS-16CD.
A Temperature Switch Fenwal Inc.
RHR-TS-1615 A
1 Temperature Switch Fenwal Inc.
RHR-TS-161D A
Motor Operater Lir.iterque RHR-MO-13C Solenoid Valve ASCO RHR-AYSPV-59A A
Solencic Valve ASCO RHR-AVSFV-555 A
Solenoid Valve ASCO RHR-AVSPV-70A A
Solencia Valve ASCO RHR-AVSPV-703 A
Linit Switen' Micreswitch RHR-LCV-69A A
Limit Switch-Micreswitch RHR-LCV-7CA A
i limit Switch Micreswitch RHR-LCV-595 A
1 Limit Switen Micreswitcn EHR-LCV-7CE A
Motor Cperater Linitorece-RHR-MO-27A A
Motor C;erater.
Limitercte RHR-M0-273 A
- Mcter Ccerater Limit:rcue RH O.-MC-27 A-A "cter C eratcr Li-iter:Le
- HR-"C-27E
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APPENDIX C (Continued) i i
Equipe:ent i
Description Manufacturer Com enent No.
Deficiency
?
)
Motor Operator Limitorque RHR-MO-16A A
J Motor 0perator Limitorque RHR-MO-34A A
Motor Operator Limitorque RHR-MO-36 A
i-tioter Operatcr Limitorque RHR-MC-39A A
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J APPENDIX D SAFETY-RELATED SYSTEMS LIST 1 Function System Emergency Reactor Shutdown 2 Reactor Protection 3 Engineered Safeguards 3 Centrol Rod Drive Containment Isclation2 High Pressure Coolant Injection Reactor Core Isolation Cooling Residual Heat Removal Core Spray Reactor Core Ccoling High Pressure Coolant Injection Residual Heat Removal (LPCI)
- Core Spray Automatic Depressurization Centainment Feat Removal
- Residual Heat Removal (Torus Cooling and Containment Spray)
Service Water Core Residuai Esat Removal
- Residual Heat Removal-Service Water Reactor Core. Isolation Cooling Prevention of Significant Release Containment Atmosphere Dilution ef -Radioactive "aterial. to Process Radiation Monitoring Environment Area Radiation Monitoring Drywell Purge and Vent Standby Gas Treatment JSupporting Systems 2 Heating and Ventilating.
General Equipment E
1The NRC staff ' recognized that there~are differences-in' nomenclature of
. systems'because cf plant vintage and engineering design; consequently,.
scoe syste s-;sr'orming identical or.similar functions may have different names..In tacse instances, it was necessary to verify the system (s) function with=the res: nsicle IE regicnal. reviewer and/cr the licenses.
0 Additional inf:rration necessary for completeness review.
~ 3 Components' c:r; rising system contained in several.systens.
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