ML20071G926
| ML20071G926 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 05/20/1983 |
| From: | Bayne J POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | Vassallo D Office of Nuclear Reactor Regulation |
| References | |
| JPN-83-45, NUDOCS 8305240442 | |
| Download: ML20071G926 (84) | |
Text
POWER AUTHORITY OF THE STATE OF NEW YORK to COLUMBUS CIRCLE NEW YORK, N.Y. 10o 19 (212) 397-6200 LEROv w sinCLAiR TRUSTEES e n e, oe, se WALTER T. MICINSMi JOHN s. DvsON c- -- ~ ,";'."s'.':::,'.
orscae GEQIGE L INGALLS
''""""** JOSEPH R. SCMMIEDER os=v . cmese KICHARD M. FLYNN JAMIS L LAROCC A STEPHEN L BAUM
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May 20, 1983 .'s*.","cl**.".*
JPN-83 -4 5 Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attention: Mr. Domenic B. Vassallo, Chief '
Operating Reactors Branch No. 2 Division of Licensing
Subject:
James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 Response to 10 CFR 50.49 - Equipment Qualification
References:
- 2. NRC letter, D.B. Vassallo to J.P. Bayne dated April 19, 1983.
Dear Sir:
^
This letter provides the information required to be submitted to the NRC per subsection (g) of 10 CFR 50.49. Attachment I identifies all equipment requiring qualification in accordance with 10 CFR 50.49(b).
The information and qualification status for the components in this submittal are provided according to the best knowledge of the Authority.
However, the Authority reserves the right to amend this submittal if necessary. The Authority will continue its verification of the information provided. If, as a result of this verification, the qualification status of a component is changed, or additional components are identified, the Authority will submit a revision promptly.
Attachment I only includes plant equipment which is currently installed in the FitzPatrick plant and which requires qualification.
If, as a result of the Authority's review of Regulatory Guide 1.97 and other activities, it is determined that additional equipment is required to be installed or upgraded, this will be included in our EQ program.
3305240442 830520 f DR ADOCK 05000333 PDR 0 lk}
The schedules provided in Attachment I are tentative and are subject to change based on equipment availability and outage schedules.
However, the qualification efforts, associated with equipment whose qualification has not been demonstrated to date will be completed by March 31, 1985, or earlier, provided circumstances do not arise that would adversely affect this qualification goal. If such circumstances arise, the Authority will promptly notify the NRC in accordance with paragraph (h) of 10 CFR 50.49.
In Reference 1, the Authority had requested a schedular exemption from the provisions of 10 CFR 50.49 (g) which require a response by May 20, 1983, in order that the response to the FitzPatrick Equipment Qualification Technical Evaluation Report (TER), transmitted in Ref erence 2, could be addressed simultaneously with this submittal.
This request was based on the fact that the Authority was not scheduled to receive the TER until April of 1983. Actually the TER was transmitted April 19, 1983 (Reference 2). Since this request was denied, the Authority's response to the TER will be sent separately.
If you have any further questions, please contact Mr. J. A. Gray, Jr. of my staff.
Very truly yours, o
JP f f 7 Executive Vice President Nuclear Generation cc: Mr. J. Linville Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 136 Lycoming, N.Y. 13093
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NEW YORK POWER AUTHORITY.
JAMES A. FITZPATRICK NUCLEAR POWER PLANT INDEX SECTION CONTENTS 01 INTRODUCTION 02 BASES FOR COMPONENT LISTS 03 METHODOLOGY FOR ESTABLISHING 10CFR50.49 (b)
(2) EQUIPMENT LISTING OF ELECTRICAL EQUIPMENT WITHIN SCOPE OF 10CFR50.49 SECTION SYSTEM NO. SYSTEM NAME 04 01-125 Standby Gas Treatment System (SBGIS) 05 02 Nuclear Boiler and Pressure Relief System (ADS)
() 06 02-2 Reactor Recirculation System 07 02-3 Nuclear Boiler Vessel Instrument System 08 03 Control Rod Drive System (CRD) 09 05 Reactor Protection System (RPS) 10 06 Feedwater Control /Reacto r Instrument System 11 07 Neutron Monitoring System 12 10 Residual Heat Removal System (RHR) 13 11 Standby Liquid Control System (SBLC) 14 12 Reactor Water Cleanup System (RWCU) 15 13 Reactor Core Isolation Cooling System (RCIC)
-16 14 Core Spray System (CS) 17 15 Reactor Building Closed Loop Cooling Water Syst em (RBCLCW)
_ . _ . - - . _ . _ ~ _ . . _ _ . - _ . . . _ .. __ .._ _ .._, . ._ _
i SECTION SYSTEM NO.
({} SYSTEM NAME 18 16 Primary Containment System 19 17 Process Radiation Monitoring System j 20 20 Radioactive Waste Processing System I
21 23 High Pressure Coolant Injection System (HPCI)
- 12 2 27 Primary Containment Atmosphere Control / Monitoring System i
23 29 Main Steam and Leak Collection System
. 24 66 Reactor Building Ventilation System i 25 68 Drywell Cooling System j 26 71 Emergency Electrical Power Systems i
i 27 Misc. Electrical Cables 28 Misc. Terminal Blocks /Spilces 29 Misc. Primary Containment Electrical 1
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- 18. 16 Primary Containment System i
-19 17 Process Radiation Monitoring System 20 20 Radioactive Waste Processing System 21 23. High Pressure Coolant Injection System 4
(HPCI) 22 27 Primary Containment Atmosphere Control / Monitoring System 23 29 Main Steam and Leak Collection System 24 66 Reactor Building Ventila' tion System i
25 68 Drywell Cooling System
- 26 71 Emergency Electrical Power Systems 27 Misc. Electrical Cables I
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- 28 Misc. Terminal Blocks / Splices
! 29 Misc. Primary Containment Electrical l Penetrations i
10CFR50.49 SECTION 01
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Jcm:s A. FitzPatrick Nuclear Power Plant DOCKET NO. 50-333 Page 1 of 4 INTRODUCTION I. The Nuclear Regulatory Commission (NRC) has amended its regulations applicable to nuclear plants regarding criteria for environmental qualification of electrical equipment important to safety. The new amendment (10CF R5 0.4 9 )
codifies the environmental qualification methods and criteria that meets the NRC's requirements in this area.
The purpose of this submittal is to specifically meet the requirements stated in subsection (g) o f 10CF R5 0.49.
II. Summary of Equioment Qualification Rule (10CFR50.49)
The following is a brief summary and Section 50.49 of the amended rule which provides a description of the information provided in each subsection and the formal responses required by the New York Powe r Authority for the James A.
FitzPatrick Nuclear Power Plant.
A. Subsection (a) - This subsection establishes a requirement that each holder of or applicant for a license to operate a nuclear power plant shall 8 establish a program for qualifying electrical equipment important to safety.
B. Subsection (b) - This subsection provides guidance for licensees to define the electrical equipment which requires qualification in accordance with the rule.
The rule applies to " electric equipment important to safety" which is defined as including:
- 1. Safety-related equipment.
- 2. Non-safety related equipment whose failure under postulated environmental conditions could prevent satisfactory accomplishment of safety functions.
- 3. Certain post'-accident nonitoring equipment.
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- 10CFR50.49 SECTION 01~~
4 James A. FitzPatrick Nuclear Power Plant
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~ DOCKET NO. 50-333. Page 2 of 4 1
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Subsection (c) 2 C. -
This subsection specifically excludes from the rules applicability dynamic and seismic. qualification, protection of. electrical equipment from natural phenomena and external events, I and qualification of electrical equipment important to safety located in a mild environment.
J 4 D. Subsection (d) - This subsection requires licensees and_ applicants to prepare a list of electric equipment covered by the scope of the rule and the requirement
- that a qualification file be established and maintained for this equipment. The required contents of this qualification file are also stated.
E. Subsection'(e) - This subsection defines the i
requirenents which qualification programs for new equipment must be based on.
F. Subsection (f) - This subsection lists acceptable qualification methods for qualification programs for new' equipment included within the scope of the rule.
The following testing methods are acceptable for qualification:
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- 1) Testing an identical item of equipment under identical conditions or under similar conditions with a supporting analysis.
4
- 2) Testing a similar i tem of equipment with a supporting analysis.
- 3) Experience with identical or similar equipment under similar conditions with a supporting
- analysis to show that the equipment to be qualified is acceptable.
j G. S ub's e c t io n (g) - This subsection requires each holder of an operating license issued prior to February 22, 1983 to submit by May 20,1983 a response to the rule a listing of electric equipment installed by the rule and equipment already qualified. A schedule of completion
- of qualification or_ replacement of unqualified i equipment must also be provided which establishes a goal of final environmental qualification of electric equipment within the scope of the rule by the end of the second refueling outage after March 31, 1982 or by
, March 31, 1985 whichever is earlier.
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10CFR50.49 SECTION 01 James A. FitzPatrick Nuclear Power Plant DOCKET NO. 50-333 Page 3 of 4 H. Subsection (h) - This subsection requires not.ification within 60 days of its discovery any qualification problems which may require extension of the completion date.
I. Subsection (1) - This subsection applies specifically to license applicants and provides guidance for ensuring safe plant operation pending completion of qualification programs.
J. Subsection (j) - This subsection requires that a record of qualification be maintained in an auditable form for equipment covered by the rule.
K. Subsection (k) - This subsection states for holders of operating licenses, that if the Commission has previously required qualification of equipment to I.
previous standards, that this equipment not be requalified in acenrdance with the provisions of this section.
L. Subsection (1) - This subsection requires replacement equipment to be qualified in accordance with the provisions of this section (50.49) unless there are
() sound reasons to the contrary.
III. Summary of Response to 10CFR50.49 This response is provided to specifically meet the requirements of subsection (g) of the rule. The listing of electrical equipment important to safety within the scope of the rule already qualified is provided in Section 04 through 29 of this submittal. A schedule for final qualification, modification, or replacement of the remaining electrical equipment in the list is also provided in these sections.
By reference IV.B the Nuclear Regulatory Commission requested that the following information also be provided in the May 20, 1983 response to 1-O C F R 5 0 . 4 9.
- 1. The submittal should specifically indicate whether your previous submittals comply with subsections (a) and (b) of 10CFR50.49.
- 2. The submittal should discuss the methods used to
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identify the equipment covered by paragraph 10CFR50.49 (b) (2).
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10CFR50.49 SEPTION 01 --
James A. FitzPatrick Nuclear Power Plant DOCKET NO. 50-333 Page 4 of 4 O
Section 02 and 03 address these requests for information to the best of the Authority's knowledge.
IV. References A. Code of Federal Regulations,.10CFR50.49 - Environmental Qualification of Electric Equipment Important to Safety for Nuclear Power Plants.
B. NRC Letter (D. B. Vassallo) to New York Power Authority (J. P. Bayne) dated April 19, 1983 (Safety Evaluation for Environmental Qualification of, Safety-Related Elbetrical Equipment).
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SECTION 02
(} Page 1 of-1 BASES FOR COMPONENT LISTS The Authority has previously submitted lists of safety-related equipment requiring environmental qualification based on guidance provided in NRC Bulletin 79-018. The Authority also responded to a previous NRC safety evaluation by providing a list of safety-related system which formed the bases for the listing of components requiring qualification. This list of systems and the identified safety functions were based on a review of the JAF Final Safety Analysis Report (FSAR), JAF Operating and Emergency Procedures, system electrical drawings and flow diagrams, system descriptions and plant modifications.
The listing of safety systems and essential safety functions was accepted in the FRC TER.
The initial list of electrical equipment requiring qualification for the JAF plant was submitted in October, 1980 in response to NRC Bulletin 79-01B. This listing of components was
- a correct representation of the systems required to mitigate postulated design basis accidents and located in harsh environments. However, the list also included many electrical 3
components which performed non-safety related functions and thus do not require environmental qualification.
- In response to the NRC SER in September, 1981 the Authority stated that based on a review cf the function of this non-safety equipment, these items were deleted from the list of equipment requiring qualification. The Authority has continued to review this listing to ensure that the list is complete and encompasses all required cafety-related equipment.
The Authority has again reviewed the original equipment list in preparing this response to 10CF R50.49 to ensure the completeness of the listing. This review has considered the requirements contained in 10CFR50.49b (1), (2) and (3), and equipment added by recent plant' modifications. Based on this review additional electrical equipment has been added and deleted to the original listing. The additions are included in the attached sections of this submittal containing the equipment listings. This listing is expected to change as a result of on-going and future modification programs.
Attached to this Section is an updated listing of the safety-related systems and essential system safety functions which form the bases for the system equipment listings included as part of this s ubmittal.
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- O O C1 JAFNPP LIST OF SAFETY-RELATED SYSTEMS REQUIRED TO MITIGATE DESIGN BASIS EVENTS j SYSTEM SAFETY FUNCTIONS CONTAIM4ENT l EMERGENCY AND POST-
- SYS. SYSTEM REACTOR CORE CONTAINMENT CONTAINMENT HELB ACCIDENT NOTES NO. NAME SHUTDOWN COOLING ISOLATION COOLING ISOLATION MONITORING i
01-125 STANDBY GAS TREATMENT X X 02 NUCLEAR BOILER AND X X X X I
PRESSURE RELIEF (ADS) j 02-2 SEACTOR RECIRCULATION X j SYSTEM
! 02-3 NUCLEAR BOILER VESSSEL X X X X X j INSTRUMENT .
03 CONTROL ROD DRIVE (CRD) X i 05 REACTOR PROTECTION (RPS) X t ,
- 06 FEEDWATER CONTROL / X REACTOR INSTRUMENT ~
07 NEUTRON MONITORING NOTE 2 10 RESIDUAL HEAT REMOVAL (RHR) X X X X a) LPCI Mode b) Containment Cooling c) Shutdown Cooling i 11 STANDBY LIQUID CONTROL NOTE 2 (SBLC) 12 REACTOR WATER X X CLEANUP (RWCU) 13 REACTOR CORE X X X ISOLATION COOLING (RCIC) (NOTE 1)'
14 CORE SPRAY X X
CONTAINMENT d
EMERGENCY AND POST j SYS. SYSTEM REACTOR CORE CONTAINMENT CONTAINMENT- HELB ACCIDENT
! NO. NAME SHUTDOWN COOLING ISOLATION COOLING ISOLATION MONITORING NOTES 15 REACTOR BUILDING CLOSED X l LOOP COOLING 16 CONTAINMENT AND CONTAIN- X X MENT INSTRUMENTATION
- 17 PROCESS RADIATION X X X
) MONITORING (NOTE 1) (NOTE 1) 20 RADWASTE SYSTEM X 9
23 HIGH PRESSURE COOLANT X X X INJECTION (HPCI) (NOTE 1)
- 27 PRIMARY CONTAINMENT ' X X ATMOSPHERE CONTROL AND MONITORING i
29 MAIN STEAM AND MAIN X X i
STEAM LEAK COLLECTION (MSLCS) i i
66 REACTOR BUILDING X VENTILATION AND '
ISOLATION CONTROL l 68 DRYWELL COOLING X 71 EMERGENCY ELECTRICAL POWER X X X X X X i a) 125VDC (NOTE 1) i b) 120VAC c) 600VAC
- d) LPCI Independent Power Supply l
MISC. CABLING NOTE 3 MISC. SPLICES / TERMINAL BLOCKS NOTE 3 MISC. CONTAINMENT ELECTRICAL ,, NOTE 3 PENETRATIONS
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NOTES
, 1. This system performs this essential safety function in a mild environment and therefore does not require qualification per 10CFRSO.49 for this function.
- 2. There is no equipment in this system requiring qualification per 10CFRSO.49 based on the system's design bases. ;
- 3. These components perform safety-related functions which
- encompass most of the listed essential safety functions.
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't SECTION 03-Page 1 of 3 METHODOLOGY FOR ESTABLISHING 10CFR50.49 (b) 2 EQUIPMENT I. INTRODUCTION - Based on the original electrical design criteria for safety-related electrical circuits, 10CFR50 (Appendix R) reviews of associated circuits, and previous system and component reviews for NRCB 79-018 submittals, the Authority has a high confidence level that failures of l
L electrical equipment not requiring qualification to harsh environments per 10CFR50.49 will not prevent the accomplishment of safety functions by safety-related equipment. However, the Authority has again reviewed this item in preparation of this response. This includes reviews of systems with multiple safety and non-safety related functions which are performed in both harsh and mild environmental conditions. Examples of these systems include:
- 1. Residual Heat Removal (RHR) - This system performs multiple modes of operation involving mitigation of accidents, normal shutdown cooling, and abnormal operations which are performed under various environmental conditions.
O 2. High Pressure Coolant Injection (HPCI) - This system performs two essential safety functions under different environmental conditions. Core cooling following postulated small break LOCA's and isolation of post ulated HPCI steam line breaks.
- 3. Reactor Water Cleanup System (RWCU) - Essential safety-related equipment requiring environmental quali fic ation for this syst em include only those components required for primary containment isolation l and isolation of RWCU line break.
II. METHODOLOGY - This review encompassed the review of the following categories of electrical circuitry:
- 1. Initiation / Actuation Logic Circuit ry
- 2. Instrumentation i
- 3. Moto r Operated Valves
- 4. Solenoid Operated Valve
- 5. Electrical Cabling O
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SECTION 03 Page 2 of~3 A. Initiation / Isolation Logic Circuitry - Logic circuitry associated with various safety-related systems including: reactor protection, primary containment isolation, steam leak detection, and ECCS were reviewed. The logic design (energized or de-energized) and power source ( AC or DC) were determined and failures at field sensors and components located in potential post-accident harsh environments were pos t ulat e d. Postulated failures inc lud e d grounds, short-circuits, and open circuits. False actuations of non-qualified equipment were also reviewed. If it was determined that the postulated failures could jeopardize the function of the logic circuit (normally due to fuse clearing) and the equipment was not inc l ud e d in the original list of equipment requiring qualification, then the c'quipment was added. The amount of equipment added as a result of this review is minimal.
Initiation and Isolation logic circuitry also includes seal-in features which prevent subsequent failure of sensors from affecting safety-related functions which have been previously initiated.
Reactor Protection System and Primary Containment Isolation System logic are normally energized (fail safe) and incorporate separate fusing for each field
,s senso r. Failure of field sensors not cequiring
(/ qualification per 10CFRSO.49 for harsh environments would not affect the f ail-sa fe pe r fo rmance of these circuits.
Summary - Based on this review, the equipment listing associated with this response includec all equipruent which perform a safety-related function in these i n i t i a t io n/ is o l a t i o n logic circuits or equipment whose failure could potentially jeopardize the operation of these logic circuits.
B. Instrumentation - Instrumentatico incorporating separate power supplies was reviewed to determine if these supplies were shared by equipment requiring qualification per 10 C F R 5'O . 4 9 . It has been confirmed that all instrumentation supplies feed individual instruments. The re fo re, failure of any one field sensor would not impact other instrumentation loops due to powe r supply failure.
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CECTION 03 Page 3 of-3 Inst r ument at ion not incorporatirg separate power supplies but energized from electrical distribution panels also incorporate individual electrical protection devices so that postulated failures in j equipment not requiring qualification would not effect !
quali fied safety-related equipment . !
C. Mo t o r-O p e r at ed Valves -
These valves are required to ,
operate based on actuation signals received from automatic initiation logic (paragraph A above) or manual actuation signals from the Control / Relay Room.
Each motor operated valve includes its own power circuit protective device and control circuit protection. There for e, postulated electrical failures for motor operated valves not requiring qualification could not impact other safety-related electrical ,
circuits.
D. Solenoid-Operated Valves - These valves are required to ope rate based on automatic or manual signals. Each solenoid circuit is equipped with its own coordinated p r o t ec t iv e device wh ich would isolate postulated electrical failures from affecting other electrical
( equipment. These design features are true of both
(_,3/ safety-related and non-safety related electrical solenoid-operated valvesi therefore,equirment not re-quiring qualification could not~ impact other safety-related electrical circuits.
E. Electrical Cablino - Cabling of the same design and '
quali fication have been used for electrical circuits requiring qualification and electrical circuits not requiring qualificat ion per 10CFR50.49. Therefore, failures o f non-sa fet y related cabling do not have to be c onsid e red.
III. CONCLUSIONS - The affects-of non-qualified safety-related equipment have been reviewed.- Based on the review methodolo gy described above, electrical components which could co n c e iv a b ly affect the functioning of safety-related electrical equipment have been identified and are included in the equipment listing.
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NLW YORK POWLR AUIHORIIY O JAMESA.FITyIRICKNUCLEARPOWERPLANT LISilNG AND STATUS OF HARSil ENVIRONMENT Lt jiRICAL EQUIPMENT REQUIRING QUALIFICATION (10CFR ( j9) l SYSTEM NO.01-125 SYSTEN NAME: STANDBY GAS TREATMENT (SBGIS) f EQ FILE QUALIFICATION r COMP. ID NO. NO. COMP. NAME STATUS LEVEL METHOD ACTION PLAN 01-125MOV-14A,B 6/8 Filter Train Suction QUALIFIED DDR Test / Analysis None required Valve Operator ,
l 01-125MOV-15A,B 6/9 Filter Train QUALIFIED DDR Test / Analysis None required ,
Discharge Valve Operator 01-125E-5A,B 6/10 SBGTS Filter Train IN DDR Test / Analysis Complete ongoing qual- l Electric Pre-Ileater PROGRESS ification program (radiation) and Control Unit or replace with fully qualified equipment by the
. Jan. 1985 outage.
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Page 2 of 2 f
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7.s NEW K POWER AUTHORITY ~n 7
(
) JAMES A. FI IRICK NUCLEAR POWER PLANT (j LISTIisE AND STATUS OF HARSH ENVIRCNMENT E TRICAL EQUIPMENT REQUIRING QUALIFICATION (10CFRSO.49)
SYSTEM NO.01-125 SYSTEM NAME STANDBY GAS TREATMENT (SBGTS)
EQ FILE QUALIFICATION COMP. ID NO. NO. COMP. NAME STATUS LEVEL METHOD ACTION PLAN 01-12SFN-1 A,8 6/7 SBGTS Fan Motor IN Test / Analysis DDR An ongoing program PROGRESS is expected to be completed by Aug.
1983. If this asses sment does not confirm qualification motors will be replaced with fully qualified units by the Jan,1985 refueling outage.
01 -12 SMOV-11 6/3 Reactor Bldg. QUALIFIED 00R Test / Analysis . None required Inlet Isolation Valve Operator 01-12SMOV-12 6/4 Reactor Bldg. QUALIFIED DOR Test / Analysis None required Inlet Isolation Valve Operator 01-12SMOV-13A 6/5 HPCI System Exhaust QUALIFIED DDR Test / Analysis None required
, Isolation Valve Operator 01-12SMOV-138 6/6 HPCI System Exhaust QUALIFIED DDR Test / Analysis None required Isolation Valve Operator Page 1 of 2
NLW YORK POWLR AUIHORITY
,' JAMES A. FI TRICK NUCLEAR POWER PLANT f LISTIb0 AND STATUS OF HARSH ENVIRONMENT l IRICAL EQUIPMENT REQUIRING QUALIFICATION (10CFR 9)
SYSTEM NO.01-125 SYSTEM NAME: STANDBY GAS TREATMENT (SBGTS)
EQ FILE QUALIFICATION COMP. ID NO. NO. COMP. NAME STATUS LEVEL METHOD ACTION PLAN U1-125MOV-14A,B 6/8 filter Train Suction QUALIFIED DDR Test / Analysis None required Valve Operator 01-125MOV-15A,B 6/9 Filter Train QUALIFIED DDR Test / Analysis None required Discharge Valve Operator 01-12SE-5A,B 6/10 SBGIS Filter Train IN DDR Test / Analysis Complete ongoing qual-Electric Fre-lienter PROGRESS ification program (radiation) and Control Unit or replace with fully qualified equipment by the
. Jan. 1985 outage.
Page 2 of 2
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NEW RK POWER AUTHORITY <~
/ ; JAMES A. FI ATRICK NUCLEAR POWER PLANT i
\'/ LISTIbG AND STATUS OF HARSH ENVIRONMENT CTRICAL EQUIPMENT REQUIRING QUALIFICATION (10CFRSO.49)
SYSTEM NO. 02 SYSTEM NAME NUCLEAR BOILER EQ FILE QUALIFICATION COMP. ID NO. NO. COMP. NAME STATUS LEVEL METHOD ACTION PLAN 02-DPIS-116 A-D 8/1 Main Steam Line High QUALIFIED 00R ' Test / Analysis None required 02-OPI S-117 A-D Flow Differential 02 DPIS-118A-D Pressure Switch 02 DPIS-119A-D 02MOV-53A,B 23/11 Recire Pump Discharge QUALIFIED DDR Test / Analysis None required Valve Operator 02MOV-54A,B 23/12 Recire Pump Discharge QUALIFIED D0R Test / Analysis None required Bypass Valve Operator 02PS-128 A , B 3/118 Reactor Pressure QUALIFIED 00R Test / Analysis Note 1 Switch (RHR-SDC) 02PS-134 8/2 Main Steam Line Low IN PROGRESS 00R Test / Analysis Qualification program to (A-D) Pressure Switch be completed by Sept.
30, 1983 02SOV-71 5/1 Safety-Relief Valve QUALIFIED DDR Test / Analysis None required (A-L) 5/2 Pilot Solenoid Valve 02T S-121 A-D 8/3 Main Steam Line High QUALIFIED 00R Test / Analysis None required .
0 2T S-122 A-D Temperature Swiwtch 02 T S-123A-D (PCIS) 02T S-124 A-D 02VMY-71 36/2 Safety Relief Valve IN PROGRESS NUREG Test Test program to be completed (A-L) 36/3 Acoustical Mon- 0588 by Oct. 1983. Modification 02VME-71 36/4 itoring System Cat. I to upgrade to tested configur-(A-L) (acceleroneter, charge- ntion to be completed by Jan.
amp, and cable) 1985 outage.
Page 1 of 2
NEW YOR JAMES A. FITZP',K ,CKPOWER AUTHORITY NUCLEAR POWER PLANT
(~_/) LISTING AND STATUS OF HARSH ENVIRONMENT ELEbiulCAL EQUIPMENT REQUIRING QUALIFICATION
. SYSTEM NO. 02 SYSTEM NAME NUCLEAR BOILER 4
i EQ FILE QUALIFICATION j COMP. ID NO. NO. COMP. NAME STATUS LEVEL HETHOD ACTION PLAN 02SOV 8/45 Reactor Head Vent IN PROGRESS DDR Test / Analysis Final qualification pending 02SOV-18 8/46 Valve Pilot completion of containment
- . Solenoid (PCIS) inspections during June, i 1983 outage.
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JAMES A. FI'TZPATRICX NUCLE AR POWER PLAN T kYSTEMNO- 02 SYSTEM NAME: NUCLEAR BOILER l /
0 3 NOTES
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The Authority considers this equipment qualified to the DDR Guidelines based on a previous qualifipation assessment completed in early 1982. However, the Authority is
, presently reviewing this assessment to resolve related concerns outlined in the JAF TER received by the Authority s on April 25, 1983. The Authority is also reviewing TER's provided to other utilities for thee same equipment.
Internal resolution of these concerns will be completed by ,
August 15, 1983, at which t im e a review of these items by the NRC staff may be requested. Based on the outcome of this reviev, it may be necessary for the Authority to supplement this response.
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\hDP JAMES A. FITb [kiRICK NOCLEAR POWER PLANT LISTING AND STATUS OF HARSH ENVIRONMENT ELECTRICAL _EQUTPMLNT REQUIRIhG QUALIFICATION (10CFRSO.49)
SYSIEM NO. 02-2 SYSTEM NAME REACTOR WATER RECIRCULATION _ _ , _ _ _
EQ FILE QUALIFICATION COMP. ID NO. NO. COMP. NAtiE STATUS LEVEL ME THOD ACTION PLAN 02-2SOV-39 8/6 Reactor Water Sample QUP.LI FIED NifREG Test / Analysis None required (replaced)
(02-2A0V-39) Inboard Isolation 0588 Valve (pilot solenoid) Cat I 02-2SOV-40 8/7 Reactor Water Sample QUALIFIED NUREC Test / Analysis None required (replaced)
(02-2A0V-40) Outboard Isolation 0503
-Valve (pilot solenoid) Cat. 1 l
Page 1 of 1 P
s NEW YOR ' WER AUTHORITY ('~1
() JAMES A. FITZPA, K NUCLEAR POWER PLANT LISTIh0 AND STATUS OF HARSH ENVIRONMENT ELECTRICAL EQUIPMENT REQUIRING QUALIFICATION (10CFR50.49)
SYSTD4 NO. 02-3 SYSTEM NAME NUCLEAR BOILER VESSEL INSTRUMENT EQ FILE QUALIFICf. TION COMP. ID NO. NO. COMP. NAME STATUS LEVEL METHOD ACTION PLAN 02-3AU-278 4/8 Rx. High Pressure IN PROGRESS ---- ----
Relocate to mild environment (A-D) Analog Trip Unit (RPS) by the Jan. 1985 outage 02-3L IS-101 8/10 Reactor Water Level QUALIFIED Test / Analysis DOR Note 1 (A-D) 8/11 (RPS) 02-3LIS-57A,B 8/8 Reactor Water Level QUALIFIED DOR lect / Analysis Note 1 Switch (Recirc) 02-3LIS-58A,B 8/9 Reactor Water Level QUALIFIED DGR Test / Analysis ' Note 1 Switch (PCIS) 02-3LIS-72 5/5 Reactor Water Level QUALIFIED DDR Test / Analysis Note 1 (A-D) Switch (ECCS) 02-3LIS-83A,B 5/6 Reactor Water Level QUALIFIED DDR Test /Analycis Note 1 Switch (ADS) e Page 1 of 2
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NEW YOR WER AUTHORITY I
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JAMES A. FITZPA 'K NUCLEAR POWER PLANT -
LISTING AND STATUS OF HARSH ENVIRONMENT ELECTRICAL EQUIPMENT REQUIRING QUALIFICATION (10CFR50.49)
SYSTEM NO. 02-3 SYSTEM NAME NUCLEAR BOILER VESSEL INSTRUMENT EQ FILE QUALIFICATION COMP. ID NO. NO. COMP. NAME STAIUS LEVEL MFTHOD ACTION PLAN 02-3 LITS-59A,8 4/6 Reactor Water Level QUALIFIED DDR Test / Analysis Although qualified, this item will Indicating Switch be replaced with fully and Indication qualified level transmitter by Jan. 1985 outage (Plant Mod. F1-83-01) 02-3LI T S-73 3/119 Reactot Shroud Water IN PROGRESS DDR Test / Analysis Replace with fully qualified Level Indicating Switch level transmitter and analog (RHR) and Indication trip unit by the Jan. 1985 outage.
02-3 LITS-79 3/122 Reactor Shroud Water QUALIFIED DDR Test / Analysis ' Note 1 Level Indicating Switch (RHR) and Indication 02-3PS-52 3/120 Reactor Pressure QUALIFIED DDR Test / Analysis Note 1 (A-D) Switch (ECCS) 02-3PS-102 8/45 Reactor Pressure IN PROGRESS DOP Test / Analysis Qualificaticn in progress (A-D) Switch (Recirc) to be completed by Sept.
1983. If not successful, replace by Jan.1985 outage.
02-3PT-178 4/7 Reactor Pressure IN PROGRESS DDR Test / Analysis Ongoing program evaluating (A-D) Transmitter (RPS) outstanding aging concern.
Program to be completed by Sep t . 1983. If program unsuccessful, replace with a fully qualified transmitter by Jan. 1985 outage.
Page 2 of 2
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s NEW YORK POWER AUTHORITY -
-JAMES A. FITZPATRICK-NUCLEAR POWER PLANT s-i i
SYSTEM NO: 02-3 SYSTEM NAME: NUCLEAR BOILER INSTRUMENT .
I l NOTES
- 1. The Authority considers this equipment qualified to the DDR Guidelines based on a previous qualification assessment completed in early 1982. However, thetAuthority is presently reviewing this assessment to resolve related
- concerns outlined in the JAF TER received by the Authority i on April 25, 1983. The Authority is also reviewing TER's j provided to other utilities fcr the same equipment. Internal t
resolution of these concerns will be completed by August 15, 1983, at which time a review of these items by the NRC staff
. may be requested. Based on the outcome of this review, it !
may be necessary for the Authority to supplenent this j response.. '
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NEW f"'y POWER AUTHORITY JAMES A. FITL-afRICK NUCLEAR POWER PLANT f
LISTING AND STATUS OF HARSH ENVIRONMENT ELECTRICAL EQUIPMENT REQUIRING QUALIFICATION (10CFR50.49)
SYSTEM NO. 03 SYSTEM NAME CONTROL ROD DRIVE (CRD)
EQ FILE QUALIFICATION COMP. ID NO. NO. COMP. NAME STATUS LEVEL METHOD ACTION PLAN 03LS-231 A-D 4/2 Scram Instrument IN PROGRESS ---- ----
These level switches are Volume Level Switch to be replaced during the
' (RPS) June,1983 outage with fully qualified redundant and diverse level switches and transmitters as part of long term CRD system modifications.
(Plant Mod. F1-82-18) 03SOV-31A,8 23/10 Scram Pilot Air IN PROGRESS ---- ----
Solenoid valves to be Solenoid Valves replaced with fully qualified valves as part of long term CRD system modifications (Plant
- Mod. F1-82-18) during June 1983 outage.
03SOV-117 23/9 Scram Pilot Air IN PROGRESS DDR Test / Analysis An ongoing qualification 03SOV-118 23/8 Solenoid Valves evaluation will be completed (137 HCU pairs) by Nov. 1983 (General Electric) 03SOV-140A,B 4/11 Back-ttp Scram Air IN PROGRESS ---- ----
Solenoid valves to be Solenoid Valves replaced by Jan. 1985 outage 03PS-401A-D ----
Low Air Header IN PROGRESS --- ----
Pressure switches to be Pressure Switch deleted in June, 1983 as (RPS) part of long term CRD system modifications (Plant Mod.
F1-82-18)
Page 1 of 1
' () NEW JAMES A. FI K PDFE'.3 AUTHORITY TRICK NUCLEAR POWER PLANT LISTING AND STATUS OF HARSH ENVIRONMENT E CTRICAL EQUIP l1ENT REQUIRING QUALIFICATION (10CFR50.49).
(Sj SYSTEM NO. 05 SYSTEM NAME REACTOR PROTECTION SYSTEM EQ FILE QUALIFICATION
, COMP. ID NO. NO. COMP. NAME STATUS LEVEL METHOD ACTION PLAN
) 05PS-12 8/14 Primary Containment QUALIFIED DDR Test / Analysis Note 1 l (A-D) 8/15 Pressure Switch (RPS) i j
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() NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT SYSTEM NO: 05 SYSTEM NAME: REACTOR PROTECTION SYSTEM NOTES
- 1. The Authority considers this equipment. qualified to the DDR .
Guidelines based on a previous qualification assessment completed in early 1982. However, the Autholity is presently reviewing this assessment to resolve related concerns outlined in the' JAF TER received by the Authority on April 2 5, 1983. The Authority is also reviewing TER's provided to other utilities for thee same equipment.
Internal resciution of these concerns will be completed by August 15, 1983, at which time a review of these itsms by I the NRC staff may be requestud. Based on the outcome of this review, it may be necessary f o r- the Authority to sup,nlement this response. >
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NEW ( X POWER AUTHORITY JAMES A. FITirdiRICK NUCLEAR POWER PLANT
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LISTING AND STATUS OF HARSH ENVIRONMENT ELECTRICAL EQijIPMEN1 REQUIRING QUALIFICATION (10CFRSO.49)
SYSTEM NO. 06 SYSTEM NAME FEEDWATER/ REACTOR INSTRUMENTATION __
EQ FILE QUALIFICATION COMP. ID NO. NO. COMP. NAME STAIUS LEVEL METHOD ACTION PLAN _
06PT-61A,B 27/1 Reactor Pressure QUALIFIED NUREG Test None required Transmitter 0588 (Indication) Cat. I Page 1 of 1
t NEW YOR WER AUTl!ORI!Y JAMES A. FITZPATi. CK NUCLEAR. POWER PLANT LISTING AND STATUS OF HARSH ENVIRONMENT ELECTRICAL EQUIPMENT REQUIRING QUALIFICATION (10CFR50.49)
SYSTEM NO. 07 SYSTEM NAME: NEUTRON MONITORING (NMS) ..
EQ FILE QUALIFICATION
, C0t'P. ID NO. NO. COMP. NAME STATUS LEVEL METHOD ACTION PLAN j NONE ----- -------------- ----- ----- -------- --------------
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NE )RK POWER AUTHORITY (m") JAMES A. FI LISTIbG AND STATUS OF HARSH ENVIRONMENT ATRICK NUCLEAR POWER PLANT lll ECTRICAL EQUIPMENT REQUIRING QUALIFICATION (10CFRSO.49)
SYSTEM NO. 10 SYSTEM NAME RESIDUAL HEAT REMOVAL (RHR)
EQ FILE QUALIFICATION COMP. ID NO. NO. COMP. NAME STATUS LEVEL METHOD ACTION PLAN' 10DPIS-125A, B ----
RHR Low Flow Switch IN PROGRESS DDR Test / Analysis Qualification pronram in Dif ferential Pressure progress to be completed by Sept. 30, 1983 10F T-97 A,8 3/6 RHR Heat Exchanger IN PROGRESS ---- ----
To be replaced with fully 3/7 Service Water Flow qualified flow transmitter Transmitter during June,1983 outage (Indication) (Plant Mod. F1-83-01) 10F T-109A ,B 3/9 RHR System Flow IN PROGRESS ---- ----
To be replaced with fully 3/10 Transmitter qualified flow transmitter (Indication) during June,1983 outage (Plant Mod. F1-83-01) 10MOV-12 A ,B 3/13 RHR Heat Exchanger IN PROGRESS ---- ----
See Note 1 for Action 3/14 Outlet Isolation Plan (Mod. M1-83-04)
Valve Operator 10MOV-13 3/15 RHR Pump Suction From QUALIFIED DDR Test / Analysis None required (A-D) 3/16 Suppression Pool 3/17 Isolation Valve 3/18 Operator 10MOV-15 3/19 RHR Pump Suction From QUALIFIFD DDR Test / Analysis None required *
(A-D) 3/20 Recirculation Loop 3/21 Isolation Valve 3/22 Operator 10MOV-16A,B 3/23 RHR Pump Test Line QUALIFIED DDR Test / Analysis None required 3/24 to Suppression Pool Isolation Valve Operator Page 1 of 6 2
g NEW'
{V JAMES A. FIk.<7,K ATRICKPOWER NUCLEARAUTHORITY POWER PLANT ( ])
LISTING AND STATUS OF HARSH ENVIRONMENT ELECTRICAL EQUIPMENT REQUIRING QUALIFICATION (10CFRSO.49)
SYSTEM NO. 10 SYSTEM NAME: RESIDUAL HEAT REMOVAL (RHR)
EQ FILE QUALIFICATION COMP. ID NO. NO. COMP. NAME STATUS LEVEL METHOD ACTION PLAN 10MOV-17 3/25 Shutdown Cooling QUALIFIED DDR Test / Analysis None required ,
Suction From Recire Loop Outboard Contain-ment Isolation Valve Operator 10MOV-18 3/26 Shutdown Cooling QUALIFIED '
DOR lest/ Analysis None required Suction From Recire Loop Inboard Contain-ment Isolation Valve Operator 10MOV-20 3/27 RHR Loop Crosstie IN PROGRESS DDR Test / Analysis' Qualification Program in Isolation Valve Operator in progress to be completed by Sept. 30, 1983 10MOV-21A,B 3/28 RHR Heat Exchanger QUALIFIED 00R Test / Analysis None required E-2A,8 Bypass to the Suppression Pool Isolation Valve Operator 10MOV-25A,8 3/29 RHR Injection Line QUALIFIED DDR Test / Analysis None required 3/30 to Recirc Loop Inboard Isolation Valve Operator 10MOV-26A,8 3/31 Drywell Spray QUALIFIED DDR Test / Analysis None required 3/32 Outboard Isolation Valve Operator 10MOV-27A,B 3/33 RHR Injectic'l.ine QUALIFIED DDR Test / Analysis None required 3/34 to Recire Loop Outboard Isolation Valve Operator Page 2 of 6
j O NEW ,< POWE!! AUTHORI TY JAMES A. FITZPATRICK NUCLEAR POWER PLANT LISTING AND STATUS OF HARSH ENVIRONMENT ELECTRICAL EQUIPMENT REQUIRING QUALIFICATION (10CFR50.49)
SYSTEM NO. 10 SYSTEM NAME: RESIDUAL HEAT REMOVAL (RHR) 4 1 EQ FILE QUALIFICATION j COMP. ID NO. NO. COMP. NAME STATUS , LEVEL METHOD ACTION PLAN
, 10MOV-31A,B 3/35 Drywell Spray QUALIFIED DDR Test / Analysis None required j 3/36 Outboard Isolation Valve
- Operator i
{ 10MOV-32 3/37 Reactor Head Spray IN PROGRESS ---- ----
See Note 1 for Action i Inboard Isolation Plan (Mod. M1-83-04)
-l Valve Operator .
10MOV-33 3/38 Reactor Head Spray QUALIFIED DDR Test / Analysis None required l
Outboard Isolation j
Valve Operator i
j 10MOV-34A,8 3/39 Suppression Pool QUALIFIED DDR Test / Analysis None required l 3/40 Spray Bypass Isolation ,
j Valve Operator 1
10MUV-36A,8 3/41 RCIC Pump Suction QUALIFIED DDR Test / Analysis None required
] 3/42 From RHR Heat Exchanger i E-2A,B Isolation Valve
- Operator I
l 10MOV-38A,8 3/43 Suppression Pool QUALIFIED DDR Tect/ Analysis None required i 3/44 Spray Inboard Isolation Valve Operator i
- 10MOV-39A,B 3/45 Suppression Pool QUALIFIED 00R Test / Analysis None required
- 3/46 Spray Outboard Isolation i Valve Operator -
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O "<w40eowc"^uriion11V JAMES A. FITZPATRICK NUCLEAR POWER PLANT O
LISTING AND STATUS OF HARSH ENVIRONMENT ELECTRICAL EQUIPMENT llEQUIRING QUALIFICATION (10CFR SYSTEli NO. 10 SYSTEM NAME: RESIDUAL HEAT REMOVAL (RilR)
EQ FILE QUALIFICATION COMP. ID NO. NO. COMP. NAME STATUS LEVEL METHOD ACTION PLAN 10MOV-57 3/47 RHR to Radwaste QUALIFIED DCR Test / Analysis None required Downstream Isolation
, Valve Operator 10MOV-65A,8 3/48 Inlet to RHR Heat QUALIFIED
, 00R Test / Analysis None required 3/49 Exchanger E-2A, B Isolation Valve Operator 10MOV-66A,8 3/50 Heat Exchanger E-2A,B QUALIFIED D0tt Test / Analysis None required 3/51 Bypass Isolation valve Operator 10MOV-67 3/52 RHR to Radwaste QUALIFIED 00R Test / Analysis None required Upstream Isolation Valve Operator 10MOV-89A,B 3/55 Heat Exchanger E-2A,B IN PROGRESS ---- ----
See Note 1 for Action 3/56 Service Water Plan (Mod. M1-83-04)
Discharge Isolation Valve Operator 10MOV-148A 3/57 Service Water Cross- IN PROGRESS ---- ----
See Note 1 for Action Tie to RHR Loop "A" Plan (Mod. M1-83-04)
Upstream Isolation Valve Operator 10MOV-1488 3/58 Service Water Cross- QUALIFII:D ----
Test / Analysis None required Tie to Ri!R Loop "B" Upstream Isolation Valve Operator Page 4 of 6
O O NEW YORK POWER AUTHORITY O
JAMES A. FITZPATRICK NUCLEAR POWER PLANT LISTING AND STATUS OF HARSH ENVIRONMENT ELECTRICAL EQUIPMENT REQUIRING QUALIFICATION (10CFRSO.49)
SYSTEM NO. 10 SYSTEM NAME: RESIDUAL HEAT REMOVAL (RHR)
EQ FILE QUALIFICATION COMP. ID NO. NO. COMP. NAME STATUS LEVEL METHOD ACTION PLAN 10MOV-149A 3/S9 Service Water Cross IN PROGRESS ---- ----
See Note 1 for Action Tie to RHR Loop "A" Plan (Mod. M1-83-04)
Downstream Isolation Valve Operator 10MOV-149B 3/60 Service Water QUALIFIED DDR Test / Analysis None required Cross-Tie to RHR Loop "B" Downstream Isolation Valve Operator -
10P-3 3/65 RHR Pump Drive QUALIFIED DDR Test / Analysis None required (A-D) 3/66 Motor (4KV) 3/67 3/68 "
10PS-100 3/77 Drywell Pressure QUALIFIED DDR Test / Analysis See Note 2 (A-D) 3/78 Switch (ADS) 3/79 3/80 e
10PS-101 3/81 Drywell Pressure QUALIFIED DDR Test / Analysis See Note 2 (A-D) 3/82 Switch (ECCS) 3/83 3/84 Page 5 of 6
' NEW K POWER AllTHORITY I
JAMES A. FITZPATRICK NUCLEAR POWER a'LANT LISTING AND STATUS Of HARSil ENVIRONMENT ELECIRICAL EQUIPMLNT REQUIRING QUALIFICATION (10CFRSO.49)
SYSTEM NO. 10 SYSTEM NAME: RESIDUAL HEAT REMOVAL (RitR)
EQ FILE QUALIFICATIGN COMP. ID NO. NO. COMP. NAME STATUS LEVEL METHOD ACTION PLAN 10PS-119 3/86 Drywell Pressure QUALIFIED DDR Test / Analysis See Note 2' (A-D) 3/87 Switch (RilR) 3/88 3/89 10PS-120 3/90, 'ItHR Pump Discharge QUALIFIED D0rt Test / Analysis See Note 2 (A-H) 3/91 Pressur.' Switch 3/92 (ADS) 3/93 3/94 3/95 '
3/96 3/97 Page 6 of 6
a NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT
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SYSTEM NO: 10 SYSTEM NAME: RESIDUAL HEAT REMOVAL (RHR)-
NOTES
- 1. Limitorque valve actuator motor and other actuator internal components will be replaced to upgradetthis actuator to a fully qualified status. If motor delivery from Limitorque is by June 1, 1983, the upgrade will be performed during the June 1, 1983 refueling outage. If motor delivery is after June 1, 1983, the upgrade will be performed prior to completion of the January, 1985 outage.
- 2. It is the Authority's position that these instruments are qualified based on qualification assessments previously performed. However, due to related concerns presented in JAF's TER and TER's of other utilities, additional reviews of these assessments are required by the Authority. Internal resolution of these concerns will be completed by August 15, 1983, at which time, a review of the resolution of these items by the NRC staff may be requested. Based on the r- outcome of this review, it may be necessary for the
(,j) Authority to modify this response.
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() NEW YORd hWEft AUTHORITY JAMES A. FITZPAIR CK NUCLEAR POWER PLANT
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LISTING AND STATUS OF HARSH ENVIRONMENT ELECTRICAL EQUIPMENT HEQUIRING QUALIFICATION (10CFRSO.49)
SYSTEM NO. 11 SYSTEM NAME: STANDBY LIQUID CONTROL (SBLCS) 4 EQ FILE QUALIFICATION I
COMP. ID NO. NO. COMP. NAME STATUS LEVEL METHOD ACTION PLAN NONE ---- --------- ------ ----- ---------- ----------
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NEW \_..X POWEH AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT LISTING AND STATUS OF llARSil ENVIRONMENT ELECTRICAL EQUIPMENT REQUIRING QUALIFICATION (10CFRSO.49) l SYSTEM NO. 12 SYSTEM NAME: REACTOR WATER CLEANUP (RWCU)- SEE NOTE 1 1
4 EQ FILE QUALIFICATION j COMP. ID NO. NO. COMP. NAME STATUS LEVEL tjETHOD ACTION PLAN j 12MOV-15 8/16 Inboard Containment IN PROGRESS ---- ----
See Note 1 for Action
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- Isolation Valve Plan (Mod. M1-83-04)
Operator (PCIS) l >
t 12MOV-18 8/17 Outboard Containment QUALIFIED DDR Test / Analysis Not required
-Isolation Valve Operator (PCIS)
J i 12MOV-80 8/18 Outboard Containment QUALIFIED DDR Test / Analysis Not required
! Isolation Bypass
- Valve Operator i
(PCIS)
I 12T E-117 8/19 Leak Detection QUALIFIED DDR Test / Analysis Not required 4 (A-F) Thermocouples See Note 2 a
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() NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT SYSTEM NO: 12 SYSTEM NAME: REACTOR WATER CLEANUP (RWCU)
NOTES
- 1. Limitorque valve actuator motor and other actuator internal 4
components will be replaced to upgrade'this valve operator to a fully qualified status. If motor delivery from the
. Limitorque Company is by June 1, 1983, the upgrade will be performed during the Jne, 1983 refueling outage. If motor delivery is after June 1, 1983, the upgrade will be performed by the scheduled January, 1985 outage.
- 2. A qualification test program t o NUREG 0588, Cat. I requirements is presently in prograss. Successful completion of this program will upgrade the level of qualification of this item.
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NE g 0RK POWER AUTHORITY
_- JAMES A. FWPATRICK NUCLEAR POWER PLANT -'
LISTING AND STATUS OF HARSH ENVIRONMENT ELECTRICAL EQUIPMENT REQUIRING QUALIFICATION (10CFRSO.49)
SYSTEM NO. 13 SYSTEM NAME: REACTOR CORE ISOLATION COOLING (RCIC)
EQ FILE QUALIFICATION COMP. ID NO. NO. COMP. NAME STATUS LEVEL METHOD ACTION PLAN 13DPIS-83 14/1 RCIC Steam Line QUALIFIED 00R Test /A,alysis Note 1 Dif ferential Pressure Switch (High Flow) 13DPIS-84 14/2 RCIC Steam Line QUALIFIED DDR Test / Analysis Note 1 Differential Pressure Switch (High Flow) 13FS-57 14/3 Pump Discharge Low IN PROGRESS DOR Test / Analysis, Note 3, 5 Flow Switch 13LS-12 14/5 Barometric Condenser IN PROGRESS DDR Test / Analysis Note 4, 5 Tank level Switch 13MOV-15 14/7 Steem Line Inboard QUALIFIED DOR Test / Analysis None required Isolation Valve Operator 13MOV-16 14/8 Steam Line Outboard IN PROGRESS ---- ----
Valve operator to be Isolation Valve replaced during Jan. ,
Operator 1985 outage 13MOV-39 14/14 Suppression Pool IN PROGRESS DDR Test / Analysis Note 3, 5 Downstream Isolation Valve Operator Page 1 of 3
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NE$1RKPOWERAUTHORITY I)
JAMES A. FIUPATRICK NUCLEAR POWER PLANT LISTIb6 AND STATUS OF HARSH ENVIRONMENT ELECTRICAL EQUIPMENT REQUIRING QUALIFICATION (10CFR50.49)
SYSTEM NO. 13 SYSTEM NAME: REACTOR CORE ISOLATION COOLING (RCIC) -
EQ FILE QUALIFICATION COMP. ID NO. NO. COMP. NAME STATUS LEVEL METHOD '
ACTION PLAN 13MOV-41 14/15 Suppression Pool IN PROGRESS DDR Test / Analysis Note 3, 5 Upstream Isolation Valve Operator 13MOV-131 14/17 Turbine Steam Inlet IN PROGRESS DDR Test / Analysis Note 3, 5 Isolation Valve Operator 13PNS-LS4 ----
Turbine Trip Throttle IN PROGRESS DDR Test / Analysis Note 4, 5 Valve Position Switch 13PS-67A, B 14/30, RCIC Pump Low Suction IN PROGRESS D0R Test / Analysis Note 3, 5 31 Pressure Switch 13PS-72A, B 14/32 Turbine Exhaust High IN PROGRESS DDR Test / Analysis Note 3, 5 Pressure Switch 13PS-78 14/33 Turbine Exhaust IN PROGRESS DDR Test / Analysis Note 3, 5 (A-D) Diaphragm High Pressure Switch 13TE-73A, B 14/46 Steam Line Leak QUALIFIED DDR Test / Analysis None required. Note 2 13TE-88A, B 14/48 Detection Thermocouple Page 2 of 3
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O NEL-<DRK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT LISTING AND STATUS OF HARSH ENVIRONMENT ELECTRICAL EQUIPMEN1 REQUIRING QUALIFICATION (10CFRSO.49)
SYSTEM NO. 13 SYSTEM NAME: REACTOR CORE IE9LATION COOLING (RCIC)
EQ FILE . QUALIFICATION COMP. ID NO. NO. COMP. NAME STATUS LEVEL METHOD ACTION PLAN i
13T E-100 14/49 Steam Line Leak QUALIFIED Test / Analysis DDR None required. Note 2 (A-D) 14/50 Detection 14/51 Thermocouple j 14/52 1
j 13T E-106 14/53 Steam line Leak QUALIFIED Test / Analysis DDR None required. Note 2
! (A-D) 14/54 Detection
, 14/55 Thermocouple 4
14/56 5
- 13PS-87 ----
RC'IC Steam Supply QUALIFIED Test / Analysis, DOR Note 3 1 (A-D) Low Pressure i
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NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT O SYSTEM NO: 13 SYSTEM NAME: REACTOR CORE ISOLATION COOLING (RCIC)
NOTES
- 1. It is the Authority's position that these instruments are qualified based on qualification assessments previously performed. However, due to related concerns presented in JAF's TER and TER's of other utilities, additional reviews of these assessments are required by the Authority.
Internal resolution of these concerns will be completed by August 15, 1983, at which time, a review of the resolution of these items by the NRC staff may be requested. Based on the outcome of this review, it may be necessary for the Authority to modify this response.
- 2. A qualification test program to NUREG-0588, Cat. I requirements ie presently in progress. Successful completion of this program will upgrade the level of qualification of this item.
- 3. An ongoing qualification program is scheduled to be
() completed by September 30, 1983. This program involves extending the applicability of previously completed qualification program to this identical equipment.
- 4. This equipment will be replaced by the January 1985
- refueling outage or a modification to provide separate electrical fusing for this component will be provided.
- 5. This equipment performs its safety-related design function in a mild environment. However, the existing system logic design incorporates common electrical fusing for this item and other harsh environment electrical equipment (HPCI steam line break isolation) requiring qualification. Postulated multiple DC grounds resulting fuse clearing, necessitates the need for qualifying or replacement of this equipment or modifying the circuit electricel protection.
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m NEW N RK POWER AUTHORITY p h JAMES A. FI C ATRICK NUCLEAR POWER PLANT v LISTING AND STATUS OF HARSH ENVIRONMENT ELECTRICAL EQUIPMENT REQUIRING QUALIFICATION (10CFR50.49)
SYSTEM NO. 14 SYSTEM NAME: CORE SPRAY EQ FILE QUALIFICAIION COMP. ID NO. NO. COMP. NAME STATUS LEVEL METHOD ACTION PLAN 14FIS-45A,8 7/3 Pump Min. Flow Switch QUALIFIED D0R Analysis / Test Note 1 7/4 14FT.-40A ,8 7/S Core Spray Loop Flow IN PROGRESS -
Transmitters being replaced witt .
7/6 Transmitter fully qualified units during-(Indication) June,1983 refueling outage (Mod. F1-83-01) 14MOV-5A, B 7/7 Core spray Min. Flow QUALIFIED DDR Analysis / Test None required 7/8 Isolation Valve Operator 14MOV-7A,8 7/9 Core Spray Pump QUALIFIED 00R Analysis / Test None required 7/10 Suction Isolation Valve Operator 14MOV-11A,B 7/11 Core Spray Discharge QUALIFIED DDR Analysis / Test None required 7/12 Dutboard Isolation Valve Operator 14MOV-12A,8 7/13 Core Spray Discharge QUALIFIED D0R Analysis / Test None required 7/14 Inboard Isolation Valve Operator 14MOV-26A,8 7/15 Core Spray Test Return QUALIFIED DDR Analysis / Test None required 7/16 Isolation Valve Operator 14P-1 A,8 7/17 Core Spray Pump QUALIFIED D0R Test / Analysis None required
- Drive Motor (4KV) 14PS-41A,B 7/18 Pump Discharge QUALIFIED 00R Test / Analysis Note 1 Pressure Switch (ADS) 14PS-44A,B 7/19 Pump Discharge QUALIFIED DDR Test / Analysis Note 1 Pressure Switch (ADS) 14PT-38A,B 7/21 Core Spray Loop IN PROGRESS ---- ----
Transmitters being replaced
- Pressure Transmitter with fully qualified units I (Indication) during the June, 1983 refueling '
- outage (Fbd. F1-83-01)
T NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT SYSTEM NO: 11 SYSTEM NAME: CORE SPRAY NOTES
- 1. The Authority considers this equipment to be qualified to the DDR Guidelines based on two previous qualification assessments completed in August, 1982 and March, 1983. The Authority is presently reviewing these assessments based on related concerns identified in the Franklin TER received in late April, 1983. Internal resolution of thase concerns by the Authority will be completed by August 15, 1983, at which time, a review of the qualification by the NRC staff may be requested. Based on the outcome of this review, it may tun necessary for the Authority to supplement this response.
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NEW POWER AUTHORITY
') JAMES A. FIT RICK NUCLEAR POWER PLANT
> LISTING AND STATUS OF HARSH ENVIRONMENT EL RICALEQUIPMENTREQUIRINGQUALIFICATIO f SYSTDi NO. 15 SYSTEM NAME: REACTOR BUILDING CLOSED LOOP COOLING EQ FILE QUALIFICATION COMP. ID NO. NO. COMP. NAME STATUS LEVEL METHOD ACTION PLAN 15MOV-101 11/1 RBCLC to ESW Cross- QUALIFIED DDR Test / Analysis None required Connect Supply Valve Operator 15MOV-102 11/2 Drywell Cooler QUALIFIED DDR Test / Analysis None required Assembly A Supply Valve Operator 15MOV-103 11/3 Drywell Cooler IN PROGRESS ---- ----
See Note 2 for Action Assembly B Supply Plan (Mod. M1-83-04)
Valve Operator 15F0V-175A,B 11/4 RBCLC to ESW QUALIFIED DDR Test /Anaysis None required 11/5 Return Cross-Connect Valve Operator 15PS-122 11/6 RBCLC/ESW QUALIFIED DCR Test / Analysis Note 3 (A-D) Permissive Pressure Switch Page 1 of 1 4
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NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT SYSTEM NO: 15 SYSTEM NAME: REACTOR BLDG. CLOSED LOOP COOLING WATER (RBCLCW)
NOTES
- 1. The components of the RBCLCW system required to* cross-tie of the system with the Emergency Service Water System are included.
- 2. Limitorque valve actuator motor and other actuator internal components will be replaced to upgrade to f ully qualified status (DDR). If motor delivery from Limitorque Corporation is by June 1, 1983, the upgrade will be performed during the June, 1983 refueling outage. If motor delivery is after June 1, 1983, the upgrade will be performed prior to the completion of the January, 1985 outage.
- 3. The Authority considers this equipment to be qualified to the DDR Guidelines based on two previous qualification assessments completed in August, 1982 and March, 1983. The Authority is presently reviewing these assessments based on r- related concerns identified in the Franklin TER received in
(_)N late April, 1983. Internal resolution of these concerns by the Authority will be completed by August 15, 1983, at which time, a review of the qualification by the NRC staff may be requested. Based on the outcome of this review, it may be necessary for the Authority to supplement this response.
Page 1 of 1 O
^*ss,
() ... _ , JAMES A. FITZ NEW Y POWER AUTHORITY ICK NUCLEAR POWER PLANT LISTING AND STATUS _ 0F HARSH ENVIRONMENT ELE RICAL EQUIPMENT REQUIRING QUALIFICATION (10CFR50.49)
()
SYSTEM NO- 16 ' \ $ SYSTEM NAME: CONTAINMENT ^ SYSTEM . .'
EQ FILE . QUALIFICATION.
COMP. ID NO. NO. COMP. NAME STAfuS LEVEL METHOD ACTION PLAN i - .
l 16-1 RID 129- 31/1 Suppression Pool QUALIFIED NUREG Test / Analysis None required
! 146 Temperat ure 0588 -
! Detector'(16) '- e . Cat. I i
16-1 PNS-101 A,8 31/3 Differential Pressure IN PROGRESS ----
To be replaced during'the June, 16-1 PNS-102A,B 31/4 Transmitter Isolation 1983 refueling outage (Mod.
] V.alve Position Switch M1-00/9909) 16-1 SOV-1016, B 31/5 Differential Pre $sure IN PROGRESS ---- ----
To be replaced during the June, 16-150V-102 A,B 31/6 Transmitter Isolation 1983 refueling outage Valve Pilot Solenoid .
16-1 RTD-107 ----
Drywell Area Ambient IN PROGRESS -
To be replaced by the January, 16-1 RID-108 Temperature Detector 1985 refueling outage I
i.
-lI i
1 1
l Page 1 of 1 l
l
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NEW tu.t.( POWER AUTHORITY ,
JAMES A. FITZPAIRICK NUCLEAR POWER PLANT LISTING AND STATUS OF HARSH ENVIRONMENT ELECTRICAL EQUIPMENT REQUIRING QUALIFICATION (10CFRSO.49)
SYSTEM NO. 17 SYSTEM NAME: PROCESS RADIATION MONITORING EQ FILE QUALIFICATION COMP. ID NO. NO. COMP. NAME STATUS LEVEL MEIHOD ACTION PLAN STALK EFFLUENTS 17RE-50A,B ----
Stack Exhaust Effluent 'IN PROGRESS ---- ----
Note 1 Monitor (Low Range) -
10-6 to 10* micro ci/cc 17RE-53A,B 26/1 Stack Exhaust Effluent IN PROGRESS ---- ----
Note 1 17RT-53A,B 26/2 Monitor (High Range) -
10E-2D to 10E6D micro ci/cc i
TURBINE BLDG. EFFLUENTS 17RE-431,-432 ----
Turbine Oldg. Exhaust IN PROGRESS ---- ----
Note 1 Vent Effluent Ibnitor (Low Range) 6 to 10 micro ci/cc 17RE-434A,B 26/3 Turbine Bldg. Exhaust IN PROGRESS ---- ----
Note 1 17R T-434 A,B 26/4 Vent Effluent Ibnitor (High Range) - 10E-2D to
- 10E6D micro ci/cc Page 1 of 2
- f. s NEW POWER AUTHORITY ts
(
~
) JAMES A. FI T IICK NUCLEAR POWER PLANT ( J LISTIBC AND STATUS Of HARSH ENVIRONMENT ELE TRICAL EQUIPMENT REQUIRING QUALIFICATION (10CFRSO.49)
SYSTEM NO. 17 SYSTEN NAME: PROCESS RADIATION MONITORING EQ FILE QUALIFICATION COMP. ID NO. NO. COMP. NAME STATUS LEVEL METHOD ACTION PLAN RADWASTE BLDG. EFFLUENTS 17RE-458A,8 ----
Radwaste Bldg. IN PROGRESS ---- ----
Note 1 Exhaust Vent Effluent Monitor (Low Range) -
10-6 to 10*
m.icro ci/cc 17RE-463A,B 26/5 Radwaste Bldg. IN PROGRESS ---- ----
Note 1 17R T-463A ,B 26/6 Exhaust Vent .
Effluent Monitor (Hi 10ghRange)-
t o 106 micro ci/cc Page 2 of 2
(~'
's -
NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT SYSTEM NJ: 17 SYSTEM NAME: PROCESS RADIATION MONITORING NOTES
- 1. This equipment is located remote from the areas experiencing direct postulated accident environments. However, sample stream radiation levels can result in higher than normal local radiation levels in the area of this instrumentation.
The high range effluent monitor design presently incorporates lead shielding to reduce these effects. The Authority is reviewing the existing shielding design for these monitors to confirm its adequacy. This review will be completed by September 1, 1983. If additional shielding is required, this will be added by the January, 1985 outage.
! ,q V
1 i
Page 1 of 1 f) s_-
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\ -} NEW YOI )WER AUTHORITY JAMES A. FITZPAlmEK NUCLEAR POWER PLANT
()
LISTING AND STATUS OF HARSH ENVIRONMENT ELECTRICAL EQUIPMENT REQUIRING QUALIFICATION (10 SYSTEM NO. 20 SYSTEM NAME: RADWASTE EQ FILE QUALIFICATION COMP. ID NO. NO. COMP. NAME STATUS LEVEL METHOD ACTION PLAN 20MOV-82 8/21 Drywell Floor Drain IN PROGRESS Sump Inboard Isolation Motor and actuator internals Valve Operator to be replaced to upgrade operator to a fully qualified status. If the replacement 20MOV-94 8/22 Drywell Equip. Drain motor is received by June 1, IN PROGRESS ---- -
1983, the upgrade will be Sump Inboard Isolation Valve accomplished during the June, 1983 outage. If received after Operator June 1, 1983, the upgrade will be accomplished by the Jan.
1985 outage.
20SOV-83 8/42 Drywell Floor Drain IN PROGRESS Sump Inboard Pilot solenoid to be replaced with Isolation Valve a fully qualified model by the Jan.
Pilot Solenoid 1985 refueling outage 20SOV-95 8/43 Drywell Equip. Drain IN PROGRESS Sump Outboard Pilot solenoid to be replaced with Isolation Valve a fully qualified model by the Jan.
Pilot Solenoid 1985 refueling outage 20PNS-83 8/44 Drywell Floor Drain IN PROGRESS Sump Inboard To be replaced with fully qualified Isolation Valve switches by the January 1985 outage Position Switch 20PNS-95 8/44 Drywell Equip. Drain IN PROGRESS Sump Outboard To be replaced by fully qualified Isolation Valve switches by the January 1985 outage Pilot Solenoid Page 1 of 1
(s 'T NfgDRKPOWERAUTHORITY JAMES A. Fn/ PATRICK NUCLEAR POWER PLANT
('
LISTING AND STATUS OF HARSH ENVIRONMENT ELECTRICAL EQUIPMENT REQUIRING QUALIFICATION (10CFRSO.49)
SYSTEM NO. 23 SYSTEM NAME: HIGH PRESSURE COOLANT INJECTION (HPCI)
EQ FILE QUALIFICATION COMP. ID NO. NO. COMP. NAME STATUS LEVEL METHOD ACTION PLAN 23DPIS-76 12/2 HPCI Steam Line High QUALIFIED DOR Test / Analysis Note 1 Flow Differential Pressure Switch (Leak Detection) 23DPIS-77 12/3 HPCI Steam Line High QUALIFIED 00R Test / Analysis Note 1 Flow Differential Pressure Switch (Leak Detection) 2 3F S-78 12/4 HPCI Low Flow IN PROGRESS DDR Test / Analysis Notc.3 2, S Pressure Switch 23MOV-14 12/11 HPCI Turbine Steam IN PROGRESS DDR Test / Analysis Notes 2, 5 Inlet Isolation Valve Operator 23MOV-15 12/12 HPCI Steam Line QUALIFIED DDR Test / Analysis None required.
Inboard Isolation Valve Operator 23MOV-16 12/13 HPCI Steam Line QUALIFIED DDR Test / Analysis None required. .
Outboard Isolation Valve Operator 23LS-91 A, B 12/6, 7 Suppresssion Chamber IN PROGRESS DDR Test / Analysis Notes 2, S High Water Level Switch Page 1 of 4
NE YORK POWER AUTHORITY ,-
( ';
JAMES A. I PATRICK NUCLEAR POWER PLANT !
LISTING AND STATUS OF HARSH ENVIRONMENT LECTRICAL EQUIPMENT REQUIRING QUALIFICATION (10CFR50.49)
SYSTEM NO. 23 SYSTEM NAME: HICH PRESSURE COOLANT INJECTION (HPCI)
EQ FILE QUALIFICATION COMP. ID NO. NO. COMP. NAME STATUS LEVEL METHOD ACTION PLAN 23L S-99 ----
Gland Seal Condensate IN PROGRESS ---- ----
Note 4 Hotwell Low Level Switch 23LS-100 ----
Gland Seal Condensate IN PROGRESS ---- ----
Note 4 Hotwell High Level Switch 23L T-202A, B 27/2 Suppression Pool QUALIFIED NUREG Test / Analysis None required.
Wire Range Level 0588 Transmitter Cat. I 23LT-203A1, B1 ?.7/1 Containment Level QUALIFIED NUREG Test / Analysis None required.
23L T-203A2, B2 Transmitter 0588 Cat. I 23MO V-57 12/20 Suppression Pool QUALIFIED DDR Test / Analysis None required.
Downstream Isolation Valve Operator 23MOV-58 12/21 Suppression Pool QUALIFIED 00R Test / Analysis None required.
Upstream Isolation Valve Operator
Vacuum Breaker Isolation Valve Operator Page 2 of 4
N ~'
ORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT LISTIbo AND STATUS OF HAitSH ENVIRONMENT ELECTRICAL EQUIPMENT REQUIRING QUALIFICATION (10CFRSO.49)
SYSTEM NO. 23 SYSTEM NAME: HIGH PRESSURE COOLANT INJECTION (HPCI)
EQ FILE QUALIFICATION COMP. ID NO. NO. COMP. NAME STAIUS LEVEL METHOD ACTION PLAN 23MOV-60 12/23 HPCI Steam Line QUALIFIED DDR Test / Analysis None required.
Outboard Bypass Isolation Valve Operator 23PNS-LS4 12/30 HPCI Turbine Stop IN PROGRESS ---- ----
Replace with a qualified Valve Position Switch position switch by Jan.
1985 outage and also Note 5 23PS-68 12/39 HPCI Steam Supply QUALIFIED DDR Test /Analysia Note 1 (A-D) 12/40 Low Pressure Switch (Isolation) 23PS-84A, B 12/43, HPCI Pump Low Suction IN PROGRESS DDR Test / Analysis Notes 2, 5 44 Pressure Switch 23PS-86 12/46- Turbine Exhaust IN PROGRESS DDR Test / Analysis Note 2, 5 (A-D) 49- Diaphragm High Pressure Switch 23PS-97A, B 12/50, Turbine Exhaust High IN PROGRESS DDR Test / Analysis Notes 2, 5 .
51 Pressure Switch Page 3 of 4 n
(Q s
N O /0RK POWER AUTHORITY JAMES A. TwZPATRICK NUCLEAR POWER PLANT O
LISTING AND STATUS OF HARSil ENVIRONMENT ELECTRICAL EQUIPMENT REQUIRING QUALIFICATION (10CFR50.49)
SYSTEM NO. 23 SYSTEM NAME: HIGH PRESSURE COOLANT INJECTION (HPCI) '
EQ FILE QUALIFICAIION COMP. ID NO. NO. COMP. NAME STAIUS LEVEL MFI!!OD ACTION PLAN 23TE-92A, B 12/65 HPCI Area Ambient QUALIFIED DDR Test / Analysis Note 1 12/66 Temperature Thermo-couple (Leak Detection) 23TE-114A, B 12/68 HPCI Area Ambient QUALIFIED DDR Test / Analysis Note 3 12/69 Temperature Thermo-couple (Leak Detection) i l
Page 4 of 4 l
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NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT l SYSTEM NO: 23 SYSTEM NAME: HIGH PRESSURE COOLANT INJECTION NOTES
- 1. The Authority considers.this equipment to be qualified to the DOR Guidelines based on a previous qualification assessment performed in March, 1982. The Authority is presently reviewing this assessment based on related concerns identified in the Franklin TER received in late April, 1983. Internal resolution of these concerns by the Authority will be completed by August 15, 1983, at which time a review of the resolution of these items by the NRC staff may be requested. Based on the outcome of this review, it may be necessary for the Authority to supplement this response.
- 2. An ongoing qualification program is scheduled to be completed by September 30, 1983. This program involves extending a previously completed qualification program for applicability to this identical equipment.
- 3. A qualification test program to NUREG-0588, Cat. I requirements is presently in progress. Successful completion of this program will upgrade the level of qualification.of this item.
- 4. This equipment will be replaced by the January 1985 outage or a modification to provide separate electrical fueing for this component will be provided.
- 5. This equipment performs its safety-related design function in a mild environment. However, the existing systen logic design incorporates common electrical fusing for this item and other harsh environment components (HPCI steam line break isolation) requiring qualification. Postulated multiple DC grounds and resulting fuse clearing, necessitates the need for qualifying or replacement of this equipment or modifying the circuit electric protection.
Page 1 cf 1
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NEW YURK POWER AUTHORITY x JAMES A. FI TZ ICK NUCLEAR POWER PLANT .r ~'
is , ) LISTIbC AND STATUS OF HARSH ENVIRONMENT EL (ICAL EQUIPMENT REQUIRING QUALIFICATION (10CFRSEL ,
SYSTEM NO. 27 SYSTEM NAME: PRIMARY CONTAINMENT AIM 0 SPHERE CONTROL / MONITORING EQ FILE QUALIFICATION COMP. ID NO. NO. COMP. NAME STATUS LEVEL METHOD ACTION PLAN 27DWA-PA 09/1 Drywell Analyzer IN PROGRESS ---- ----
- 1. Fully qualified H Analyzer 2
PB 09/8 Panel system presently being instal]
includes: 09/9 (oxygen, hydrogen) will be completed by end of 2702-'AZ-101 A,8 June, 1983 refueling Outage 27HAZ-101 A,B (Mod. F1-80-20) 27MAZ-101A,0
- 2. Fully qualified 02 Analyzer will be installed by January 1985 outage.
27E/P-103A,B 09/2 Nitrogen Flow to IN PROGRESS ---- Replace with fully qualified (27FCV-103A,B) Containment Electro- -
convertor or modify valve pneumatic Convertor control method by Jan. 1985 for 27FCV-103A, B outage 27F T-103 A ,B 9/6 Nitrogen Supply to IN PROGRESS ---- ----
Replace with fully qualified Containment Flow flow transmitter during June, Transmitter 1983 Outage (Mod F1-83-01) 27HAZ-102A,B 30/3 Containment Hydrogen QUALIFIED NUREG Test / Analysis This is replacement H2 analyzer Analyzer 0588 for 27HAZ-101 A, B above Cat. I (NUREG-0737) 27MOV-113 9/11 Drywell Air Exhaust QUALIFIED 00R Test / Analysis None required Bypass Valve Operator Page 1 of 9
4
/)
\-s' NEW YOF'~'?WER AUTHORITY
(')'
JAMES A. FITZPATusCK NUCLEAR POWER PLANT -
LISTING AND STATUS OF HARSH ENVIRONMENT LLECTRICAL EQUIPMENT REQUIRING QUALIFICATION (10CFR50.49)
SYSTEM NO. 27 SYSTEM NAME: PRIMARY CONTAINMENT ATMOSPHERE CONTROL / MONITORING
' EQ FILE QUALIFICATION COMP. ID NO. NO. COMP. NAME STATUS LEVEL METHOD ACTION PLAN 27MOV-117 9/12 Suppression Chamber QUALIFIED DOR Test / Analysis None required <
Air Exhaust Bypass i Valve Doerator 27MOV-120 9/71 Vent and Purge QUALIFIED DDR Test / Analysis None required Exhaust to SBGTS Iso'lation Valve Operator 27MOV-121 9/72 Vent & Purge Exhaust QUALIFIED DDR Test / Analysis None required 4
~
to SBGTS Isolation '
} Valve 27MOV-122 9/70 Drywell Exhaust Line QUALIFIED NUREG Test / Analysis None required. (NUREG 0737)
Bypass Valve Operator 0588 Cat. I 1
27MOV-123 9/70 Suppression' Pool QUALIFIED NUREG Test / Analysis None required. (NUREG 0737)
Exhaust Bypass 0588 Valve Operator Cat. I 27PNS-101A,B Suppression Chamber '
{ 9/15 QUALIFIED NUREG Test / Analysis None required. (replaced)
, (27A0V-101 A,B) Vent Line Isolation 0588 l
Position Switch Cat. I i
I Page 2 of 9
NEW YOR OWER AUTHORITY l
JAMES A. FITZP NUCLEAR POWER PLANT LISilb0 AND STATUS OF HARSil ENVIRONMENT ELEC CAL EQUIPMENT REQUIRING QUALIFICATION (10CFR50.49)
SYSTEM NO. 27 SYSTEM NAME: PRIMARY CONTAINMENT ATMOSPHERE CONTROL / MONITORING EQ FILE QUALIFICATION COMP. ID NO. NO. COMP. NAME STATUS LEVEL METHOD ACTION PLAN 27PNS-103A,8 9/16 Nitrogen Flow Control QUALIFIED DOR Test / Analysis None required. (replaced)
(27FCV-103A ,B) Valve Position Switches 27PNS-111 9/17 Drywell Purge Supply QUALIFIED NUREG Test /Anaysis None required. (replaced)
(27A0V-111) Isolation Valve 0588 Position Switches Cat. I 27PNS-112 9/18 Drywell Purge Supply QUALIFIED NUREG Test / Analysis None required. (replaced)
Isolation Valve 0588 Position Switches Cat. I ,
27PNS-132A , B 9/26 Nitrogen to QUALIFIED NUREG Test / Analysis None required. (replaced)
(2 7A0V-132A ,B) Suppression Pool 0588 Isolation Valve Cat. I Position Switch 27PNS-141 thru 9/27- Suppression Chanber QUALIFIED NUREG Test / Analysis None required. (replaced)
-147 9/33 Vacuum Breaker 0588 (27VB-1 thru Position Switches Cat. I
-7) 27PS-110A,8 9/34 Drywell Vacuum IN PROGRESS ---- ----
Replace with fully qualified Breaker Isolation pressure switch or transmitter Signal Pressure by Jan.1985 outage Switch Page 3 of 9
s NEW YO OWER AUTHORITY
~
JAMES A. FITZP NUCLEAR POWER PLANT LISTING AND STATUS OF HARSH ENVIRONMENT ELEC1 ICAL EQUIPMENT REQUIRING QUALIFICATION (10CFR50.49)
SYSTEM NO. 27 SYSTEM NAME: PRIMARY CONTAINEMNT ATMOSPHERE CONTROL / MONITORING EQ FILE QUALIFICATION COMP. ID NO. NO. COMP. NAME STATUS LEVEL METHOD ACTION PLAN 27P T-114 9/37 Nitrogen Train "A" IN PROGRESS ---- ----
To be replaced with fully qualifie Pressure Transmitter pressure transmitter during 1983 (Indication) -
refueling outage (Mod. F1-83-01) 27P T-115 A1, 27/1 Primary Containment QUALIFIED NUREG Test None required. (NUREG 0737)
A2 Pressure - Low Range 0500 (Indication) Cat. I 27PT-11581,B2 27/1 Primary Containment QUALIFIED NUREG Test None required. (NUREG 0737)
Pressure - Low Range 0588 (Indication) Cat. I .
27R E-104A , B 28/1 Primary Containment QUALIFIED NUREG Test None required. (NUREG 0737)
High Range Radiation 0588 Detector (Indication Cat. I and Isolation Signal) 27PNS-113 9/19 Drywell Purge Exhaust QUALIFIED NUREG Test / Analysis None required. (replaced)
(27A0V-113) Isolation Valve 0508 Position Switch Cat. I 27PNS-114 9/20 Drywell Purge Exhaust QUALIFIED NUREG Test / Analysis None required. (replaced) .
(27A0V-114) Isolation Valve 0588 Position Switch Cat. I Page 4 of 9
NEW RK POWER AUTHORITY f'~s') JAMES A. F ATRICK NUCLEAR POWER PLANT
(~}
N>
LISTING AND STATUS OF HARSH ENVIRONMENT ELECTRICAL EQUIPMENT REQUIRING QUALIFICATION (10CFR50.49)
SYSTEM NO. 27 SYSTEM NAME: PRIMARY CONTAINMENT ATMOSPHERE CONTROL / MONITORING EQ FILE QUALIFICATION COMP. ID NO. NO. COMP. NAME STATUS LEVEL METHOD ACTION PLAN 27PNS-115 9/21 Drywell Purge Supply QUALIFIED NUREG Test / Analysis None required. (replaced)
(27ADV-115) Isolation Valve 0588 Position Switch Cat. I 27PNS-116 9/22 Drywell Purge Supply QUALIFIED NUREG Test / Analysis None required. (replaced)
(27A0V-116) Isolation Valve 0588 Position Switch Cat. I 27PNS-117 9/23 Suppression Chanber QUALIFIED NUREG Test / Analysis None required. (replaced)
(27ADV-117) Exhaust Isolation 0588 Valve Position Switch Cat. I 27PNS-118 9/24 Suppression Dianber QUALIFIED NUREG Test / Analysis None required. (replaced)
(27A0V-118) Exhaust Isolation 0588 Valve Position Switch Cat. I 27PNS-131 A,B 9/25 Nitrogen to Drywell QUALIFIED NUREG Test / Analysis None required. (replaced)
(27ADV-131 A,B) Isolation Valve 0588 Position Switch Cat. I 27 RID-101 9/41 Suppression Pool IN PROGRESS ---- -
To be replaced with fully (A-D) Temperature RID qualified RTD by Jan.1985 ,
outage.
27 RID-112 9/42 Temperature Compen- IN PROGRESS ---- ----
To be replaced with a fully (27FT-103A) sation for Nitrogen qualified RTD by the Jan.1985 Page 5 of 9
7, NEW YOR '0WER AUTHORITY 2
' JAMES A. FIIZP CK NUCLEAR POWER PLANT LISTING AND STATUS OF HARSH ENVIRONMENT ELEC CAL EQUIPMENT REQUIRING QUALIFICATION (10CFRSO.49 SYSTEM NO. 27 SYSTEM NAME: PRIMARY CONTAINMENT ATMOSPHERE CONTROL / MONITORING EQ FILE QUALIFICATION CONP. ID NO. NO. COMP. NAME STATUS LEVEL METHOD ACTION PLAN 2750V-101A,8 9/43 Suppression Chanber QUALIFIED NUREG Test None required. (replaced)
(27ADV-101 A,B) Vent Line Isolation 0598 Valve Pilot Solenoid Cat. I 27SOV-111 9/44 Drywell Purge Supply Test QUALIFIED NUREG None required. (replaced)
(27A0V-111) Isolation Valve Pilot 0588 Solenoid Cat, I 2750V-112 9/4S Drywell Purge Supply QUALIFIED NUREG Test None required. (replaced)
(27ADV-112) Isolation Valve Pilot 0588 Solenoid Cat. I .
27SOV-113 9/46 Drywell Purge Ediaust QUALIFIED Test NUREG None required. (replaced)
(27A0V-113) Isolation Valve Pilot 0588 Solenoid Cat. I 23SOV-114 9/47 Drywell Purge Exhaust QUALIFIED Test NUREG None required. (replaced)
(27ADV-114) Isolation Valve Pilot 0588 Solenoid Cat. I 2750V-115 09/e8 Drywell Purge Supply QUALIFIED NUREG Test None required. (replaced)
(27ADV-115) Isolation Valve Pilot 0588 .
Solenoid Cat. I Page 6 of 9
NEW YORK POWER AUTHORITY
()\
L JAMES A. FI TZPl[~';CK NUCLEAR POWER PLANT ()
~
LISTING AND STATUS OF HARSH ENVIRONMENT ELECw. CAL EQUIPMENT REQUIRING QUALIFICATION (10CFR50.4 /
SYSTEM NO. 27 SYSTEM NAME: PRIMARY CONTAINMENT ATMOSPHERE CONTROL / MONITORING l EQ FILE QUALIFICATJON COMP. ID NO. NO. COMP. NAME STATUS LEVEL METHOD ACTION PLAN 27SOV-116 09/49 Drywell Purge Suppy QUALIFIED NUREG Test None seguired. (replaced)
(27A0V-116) Isolation Valve 0588 Pilot Solenoid Cat. I 27SOV-117 09/50 Suppression Chamber QUALIFIED NUREG Test None required. (replaced)
(27A0V-117) Exhaust Isolation 0588 Valve Pilot Solenoid Cat. I 27SOV-118 09/51 Suppression Chamber QUALIFIED NUREG Test None required. (replaced)
(27A0V-118) Exhaust Isolation 0588 -
Valve Pilot Solenoid Cat. I i
27SOV-119A,B 09/52 Suppression Chamber QUALIFIED DDR Test / Analysis Nonc required - Notes 1, 3 Sample Flow to Containment Sampling System Solenoid Isolation Valve 27SOV-120A,8 09/53 Drywell Sample Flow QUALIFIED DOR Test / Analysis None required - Notes 1, 3 to Containment Sampling System Solenoid Isolation Valve 27SOV-121A,0 9/54 Drywell Sample Flow to QUALIFIED DDR Test / Analysis None required - Notes 1, 3 Containment Sampling System Solenoid Isolation Valve i
Page 7 of 9 i
,,_ NEW YOR OWER AUTHORITY ,-
! ) JAMES A. FITZP NUCLEAR POWER PLANT (
'~~'
LISTING AND SIAIUS OF HARSH ENVIRONMENT ELEC CAL EQUIPMENT REQUIRING QUALIFICATION (10CFR50.4k>'
SYSTEM NO. 27 SYSTEM NAME: PRIMARY CONTAINMENT ATMOSPHERE CONTROL / MONITORING EQ FILE QUALIFICATION COMP. ID NO. NO. COMP. NAME STATUS LEVEL METHOD ACYION PLAN 27SOV-122A,B 9/55 Drywell Sample Flow QUALIFIED DDR Test / Analysis None required - Notes 1, 3 Containment Sampling System Solenoid Isolation Valve 27SOV-123A,B 9/56 Drywell Sample Flow to QUALIFIED 00R Test / Analysis None reuqired - Notes 2, 3 Moisture Analyzer Solenoid Isolation Valve 2750V-124A,B 9/57 Containment Sampling QUALIFIED 00R Test / Analysis , None required - Notes 2, 3 System Return Line to Suppression Chanber Solenoid Isolation Valve 2750V-125A,B 9/58 Containment Radiation QUALIFIED DDR Test / Analysis None required - Notes 1, 3 Monitor Return to Drywell Solenoid Isolation Valve 2750V-131A,B 9/S9 Nitrogen to Drywell QUALIFIED NUREG Test None required. (replaced)
(27ADV-131 A,B)
Isolation Valve Pilot 0500 Solenoid Cat. I Page 8 of 9
NEW YORK POWER AUTHORITY JAMES A. FITZPf;K NUCLEAR POWER PLANT ' ')
LISTING AND STATUS OF HARSH ENVIRONMENT ELEdu CAL EQUIPMENT REQUIRING QUALIFICATION (10CFR50.4n/
SYSTEM NO. 27 SYSTEM NAME: PRIMARY CONTAINMENT ATMOSPHERE CONTROL / MONITORING EQ FILE QUALIFICATION COMP. ID NO. NO. COMP. NAME STATUS LEVEL METHOD ACTION PLAN 27SOV-132A,B 9/60 Nitrogen to QUALIFIED NUREG Test None required. (replaced)
(27A0V-132A,0) Suppression Pool 0588
. Isolation Valve Cat. I Pilot Solenoid 27SOV-135A,8 9/61 Containment Sample ' QUALIFIED 00R Test / Analysis None required - Note 2 Flow to Radiation Monitors Solenoid Isolation Valve 270WA-HTA,HTB 9/67 Containment Atmos- IN PROGRESS ---- ----
A fully qualified heat tracing 27RTD-102A1,B1 9/64 phere Monitoring
- system will be installed aa part o'
-102A2,B2 9/65 Heat Tracing System the new H2 Analyzer System (Mod. F1-80-20) and the replacement thru -107A1,81 9/66 02 Analyzer System
-107A2,82 to be installed by the Jan.
1985 outage. The Authority is awaiting the final qualification test report. This equipment is not presently installed and operational.
27SOV-119E,F 30/1 Hydrogen Sampling QUALIFIED NUREG Test None required 27SOV-120E,F System Solenaid 0588 27SOV-122E,F Isolation Valves Cat. I 27SOV-123E,F '
27SOV-124E,F Page 9 of 9
I)/ NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT SYSTEM NO: 27 SYSTEM NAME: PRIMARY CONTAINMENT AIM 0 SPHERE CONTROL /
MONITORING '
NOTES
- 1. These solenoid valves provide isolation from the primary containment or the existing containment atmosphere monitoring system (27DWA-PA, PB). With the completion of the installation of the new hydrogen analyzer (27HAZ-102A, B) and replacement oxygen analyzer these solenoid valves will provide only a primary containment isolation function and will not be required to be re-opened for containment sampling following a postulated accident.
The new containment atmosphere monitoring equipment will be isolated by separate fully qualified containment isolation solenoid valves.
p)
(_ 2. Provides containment isolation function only.
- 3. The Authority considers this equipment to be qualified to
, the DDR Guidelines based on two previous qualification assessments completed in August, 1982 and March, 1983. The Authority is presently reviewing these assessments based on related concerns identified in the Franklin TER received in late April, 1983. Internal resolution of these concerns by the Authority will be completed by August 15, 1983, at which time, a review of the qualification by the NRC staff j is requested. Based on the outcome of this review, it may
, be necessary for the Authority to supplement this response.
l t
~
l Page 1 of 1 4
J
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L
NEW YORK POWER AUTHORITY
) JAMES A. FIT 7[~']ICK NUCLEAR POWER PLANT- ()
(/
\_ LISTING AND STATUS OF HARSH ENVIRONMENT ELL-,ilICAL EQUIPMENT REQUIRING QUALIFICATION (10CFR50h,J)
SYSTEM NO. 29 SYSTEM NAME: MAIN STEAM AND MAIN STEAM LEAK COLLECTION SYSTEM (MSLCS)
EQ FILE QUALIFICATION COMP. ID NO. NO. COMP. NAME STATUS LEVEL METHOD ACTION PLAN 29MOV-74 8/23 Main Steam Line Drain IN PROGRESS ----
Note 1 Inboard Isolation
, Valve Operator 29MOV-77 8/24 Main Steam Line Drain IN PROGRESS DOR Test / Analysis Qualification Program to Outboard Isolation be complete by Sept. 1, 1983.
Valve Operator If not successful, motors will be replaced by Jan.
1985 outage.
29MOV-200A, B 8/45 Leak Collection System IN PROGRESS DDR Test / Analysis Qualification Program to Master Isolation be completed by Sept. 1, 1983.
Valve Operator -
If not successful, motors will be replaced by Jan.
1985 outage.
29MOV-201A, B 8/46 Leak Collection System IN PROGRESS DDR Test / Analysis Qualification Program to to Standby-Gas be completed by Sept. 1, 1983.
j Isolation Valve If not successful, motors Operator will be replaced by Jan.
1985 outage.
29MOV-202A, B 8/47 Leak Collection IN PROGRESS DDR Test / Analysis Qualification Program to System to Standby- be completed by Sept. 1, 1983.
Gas Backup isolation If not successful, motors Valve Operator will be replaced by Jan.
1985 outage. '
29MOV-203A, B 8/48 MSIV Steam Packing IN PROGRESS DDR Test / Analysis Qualification Program to Isolation Valve be completed by Sept. 1, 1983.
Operator If not successful, motors will be replaced by Jan.
1985 outage.
Page 1 of 3
~~ NEW YORK POWER AUTHORITY
(\m JAMES A. FITZI DICK NUCLEAR POWER PLANT I'd LISTIhG AND STATUS OF HARSH ENVIRONMENT ElludtICAL EQUIPMENT REQUIRING QUALIFICATION (10CFR50'.w/)
SYSTEM NO. 29 SYSTEM NAME: MAIN STEAM AND MAIN STEAM LEAK COLLECTION (MSLCS)
EQ FILE QUALIFICATION COMP. ID NO. NO. COMP. NAME STATUS LEVEL METHOD ACTION PLAN 29MOV-204A, B 8/49 Leak Collection IN PR9GRESS DDR Test / Analysis Qualification Program to System Backup be completed by Sept. 1, 1983.
Drain Valve If not successful, motors Operator will be replaced by Jan.
1985 outage.
29PNS-80 A1, 8/25 Main Steam Isolation QUALIFIED NUREG Test / Analysis None required (replaced)
A2, A3 Valve (Inboard) 0588 29PNS-80 B1, 8/26 Position Switches Cat. I B2, 83 29PNS-80 C1, 8/27 C2, C3 29PNS-80 D1, 8/28
- D2, D3 29PNS-86 A1, 8/29 Main Steam Isolation QUALIFIED NUREG Test / Analysis None required (replaced)
A2, A3 8/30 Valve (Outboard) 0588 29PNS-86 B1, Position Switches Cat. I B2, B3 29PNS-86 C1, 8/31 C2, C3 29PNS-86 D1, D2, D3 29SOV-80 A2, 8/34 Main Steam Isolation IN PROGRESS -
To be replaced by Jan. 1985
- A3 Valve (Inboard) refueling outage with fully 29SOV-80 82,B3 8/35 Pilot Solenoid qualified solenoid valves.
29SOV-80 C2,C3 8/36 2950V-80 D2,D3 8/37 l Page 2 of 3 1
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,3 NEW Yf"\ POWER AUTHORITY (j JAMES A. FITZy)ICK NUCLEAR POWER PLANT d LISTING AND STATUS OF HARSH ENVIP.ONMENT ELECTRICAL EQUIPMENT REQUIRING QUALIFICATION (10CFR50.49)
SYSTEM NO. 29 SYSTEM NAME: MAIN STEAM AND MAIN STEAM LEAK COLLECTION (MSCLS)
EQ FILE QUALIFICATION COMP. ID NO. NO. COMP. NAME STATUS LEVEL METHOD ACTION PLAN 29SOV-86 A2, A3 8/38 Main Steam Isolation IN PROGRESS - =
To be replaced by Jan. 1985 2950V-86 B2, 83 8/39 Valve (Outboard) outage with fully qualified 29SOV-86 C2, C3 8/40 Pilot Solenoid solenoid valves.
29SOV-86 D2, D3 8/41 29PS-201 A, B 8/49 Leak Collection System IN PROGRESS DDR Test / Analysis A qualification program for (1,igh Pressure Switch these switches is in progress.
Completion is expected by Sept.
15, 1983.
29PS-202A, B 8/50 Leak Collection System IN PROGRESS DDR Test / Analysis t A qualification program for High Pressure Switch these switches is in progress.
Completion is expected by Sept.
15, 1983.
Page 3 of 3 .
i NEW YORK POWER AUTHORITY
() JAMES A. FITZPATRICK NUCLEAR POWER PLANT SYSTEM NO: 29 SYSTEM NAME: MAIN STEAM AND MAIN STEAM LEAK COLLECTION i NOTES 1
- 1. Limitorque valve actuator motor and other actuator internal i components will be replaced to upgrade this actuator to a fully qualified status. If motor delivery from Limitorqua is by June 1, 1983, the upgrade will be performed during the June, 1983 outage. If motor delivery is after June 1, 1983 the upgrade will be performed by the January 1985 outago.
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() RK POWER AUTHORITY NE s
(~'j JAMES A. F ATRIO < FRELEAR POWER PLANT s_
LISTING AND STATUS OF HARSH ENVIRONMENT ECTRICAL EQUIPMENT REQUIRIhG QUALIFICATION (10CFR50.49)
SYSTEM NO. 66 SYSTEM NAME: REACTOR BUILDING VENTILATION EQ FILE QUALIFICATION COMP. ID NO. NO. COMP. NAME STATUS LEVEL METHOD ACTION PLAN 66HV-3A, B 10/S Crescent Area Unit IN PROGRESS ---- ----
See Note 1 10/6 Cooler Local Control Panel 66PNS-100A1, A2 10/12 Reactor Bldg. Inlet QUALIFIED NUREG Test / Analysis None required (replaced) 66PNS-100B1, B2 Isolation Damper 0588 Switch Cat. I 66PNS-101 A, A2 10/13 Reactor Bldg. Outlet QUALIFIED NUREG Test / Analysis None Required (replaced) 66PNS-1010, B2 Outlet Isolation 0588 Damper Position Switch Cat. I 66SOV-100A, B 10/8 Reactor Bldg. Inlet QUALIFIED NUREG Test / Analysis None required (replaced) 10/9 Isolation Damper 0588 Pilot Solenoid Valve Cat. I 66SOV-101 A, B 10/10 Reactor Bldg. Outlet QUALIFIED NUREG Test / Analysis None required (replaced) 10/11 Isolation Damper 0588 Pilot Solenoid Valve Cat. I 660C-22 ( A-K) 13/2 Crescent Area Unit IN PROGRESS DDR Test / Analysis Successfully complete existing Cooler Motors qualification of program by Sept. 30,1983 of replace with
- fully qualified fan motors by Jan. 1985 refueling outage.
Page 1 of 1
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NEW YORK POWER AUTHORITY
() JAMES A. FITZPATRICK NUCLEAR POWER PLANT i SYSTEM NO: 66 SYSTEM NAME: REACTOR BUILDING VENTILATION NOTES
- 1. A modification will be performed to the wiring in Panels 66HV-3A, 3B to eliminate local control of the Crescent Area
! fan coolers from these panels. This modification will consist of removing existing control switches and splicing the control cables. This modification will eliminate the need for qualifying this ventilation panel and will be completed by the January 1985 refueling outage.
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NEW JAMES A. FIT POWER AUTHORITY ICK NUCLEAR POWER PLANT
,- s
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LISTING AND STATUS OF HARSH ENVIRONMENT EL ICAL EQUIPMENT REQUIRING QUALIFICATION (10CFR50'.4d)
SYSTEM NO. 68 SYSTEM NAME: DRYWELL COOLING SYSTEM EQ FILE QUALIFICATION COMP. ID NO. NO. COMP. NAME STATUS LEVEL METHOD ACTION PLAN 68TE-201 thru ----
Drywell Area Temper- IN PROGRESS ----
Replace all 26 thermocouples 212 (Total = ature Thermocouples with fully qualified units by
- 12) the Jan.1985 refueling outage 68TE-301 thru 310 (Total =
10) 60T E-102, 103 23/4-7 Drywell Cooling Direct 104, 105 Temperature Thermocouples i
Page 1 of 1
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NEW YrNPOWER AUTHORITY JAMES A. FITZIs_. DICK NUCLEAR POWER PLANT f'l N
LISTING AND STATUS OF HARSH ENVIRONMENT ELECTRICAL EQUIPMENT REQUIRING QUALIFICATION (10CFR50.49)
SYSTEM NO. 71 SYSTEM NAME: ELECTRICAL POWER EQ FILE QUALIFICATION COMP. ID NO. NO. COMP. NAME STATUS LEVEL METHOD ACTION PLAN BMCC-1, 2, 3, 17/3-5 Motor Control Centers IN PROGRESS DOR Similarity / Note 1 .
4, 6 (125VDC) Analysis i
MCC-151, 152 17/12-20 Motor Control Centers IN PROGRESS DDR Similarity / Note 1 153, 155, 161, (600VAC) Analysis 162, 163, 164 165 L-15 21/3 Unit Substation - IN PROGRESS D0R Similarity / Note 2 L-16 21/4 4KV/600VAC Incl. Analysis Isolation Switch, Transformer and Breaker Cubicle 71 BAT-3A, B 22/1 LPCkIndependent IN PROGRESS ----
Note 4 711NV-3A, B 22/2 Power Supply Charger /
Inverter Incl. Battery (400KW) 71ACAS 23/17 Reactor Bldg. Emerg. IN PROGRESS ----
Note 3 71ACBS 23/18 Control & Instrument PT-71ACAS 23/19 Bus Distribution PT-71ACBS 23/20 Panel (120VAC) including 600/120VAC Transformer Page 1 of 1
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NEW. YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT p
71 SYSTEM NAME: ELECTRICAL POWER 1'- t, SYSTEM NO:
. F, y g' i; t NOTE J t
- 1
,A i f D.-1. Motor Control Center (MCC) Qualification - The Authority
- - 1 <
uith a group of six (6) other BWR owne.rs are working on a
[4%s J,0 ' ' $k 6? joint two phase program for confirming qualification to the DDR Guidelines-based on analysis and similarity. This
- ( qualification program is based on qualification teet data i
c3 S% 4 from a later version of the General Electric 7700 Series
, motor-control centers. Phase I of this program is scheduled
.y for completion in September, 1983. Phase II will require an 4 '
additio.nal six months to complete. It is not feasible to type-test-the existing models because of lack of spare MCC sections of,the proper vintage. The Authority will inform 4
the Commission of this program's progress in October, 1983.
4
- 1. AKD-5 Switchge'ar Qualification - The Authority has pursued i
with theiGeneral Electric Company a program for verifying qualification of these two substations to the DDR
. - Guidelines., Phase I will be completed by September, 1983.
If Phase I is successful, then final qualification will be performed ~during a Phase II program. No schedule can be l
provided for Phase II at this time. The Authority will '
, advise the Commission of the program's progress in October, 1983. it istnot feasible to type test the existing equipment due to size and the unavailability of a similar
- component of the same vintage.
l t 3.'
71ACAS, 71ACBS,.- In lieu of qualifying these local 120VAC
- distribution panels, and associated distribution transformers the Authority intends to relocate to a
! distribution panel located in a mild environment the load I
preakers for the following safety-related components:
b l
"( b. 27NS-CA, CB'- Nitrogen Instrument Supply Panel a . ) 71INV-3A, 3B -- Control Power for LPCI inverters
! The other loads on these distribution panels have been L reviewed and are not required to be functional during and i following postulated design basis accidents.
- 4. LPCI Indenendent Power Supply - Due to this equipment's design, size, and complexity, it is not feasible to perform
_- p ] a type te,st program. These are also no qualified replacement equipment for this item. The Authority is
-i g precently reviewing this equipment's design bases as a
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[ Page 1 of 2 t -
b method of exempting it.from harsh environment qualification 3 with additional modifications. This is based on the q_j following:
- a. LOCA (large) - This equipment is located remote from the direct harsh environment of this accident and would perform its intended design function of providing power to the LPCI valve bus prior to the local temperature, radiation, or humidity significantly exceeding normal condition. The re, quired operating time is less than 3 min'utes.
- b. LOCA (small) - This equipment is located remote from the direct accident environment.
Although the required operating time is significantly longer for this accident, no significant accident radiation exposure is expected due to its elevation in the Reactor Building and minimal fuel damage can be postulated for this accident. The long term temperature does not significantly increase above normal.
- c. HELB - This equipment would be required to operate
~/ flow to the vessel. For this accident, access
! to the Reactor Building would be possible fo r manual operation of the RHR injection valve or for the transferring of the power ' source for these valves from the LPCI independent power supply to the alternate emergency feeder (maintenance supply).
The Authority is investigating a modification which would
! provide for transfer of the power source of the LPCI valve l bus from the LPCI Independent Power Supply to the alternate source by way of operator action in the Control Room (should the inverter system fall).
l The Authority will complete the investigation of the
' licensing and design bases fo r this item and provide a final plan for resolution of this issue to the Commission by September 30, 1983. It is the Authority's goal to provide resolution of the qualification issues for this item by the January, 198 5 outage.
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NEW K POWER AUTHORITY
'T JAMES A. FIT RICK NUCLEAR POWER PLANT
(J LISTIbG AND STATUS OF HARSH ENVIRONMENT EL RICAL EQUIPMENT REQUIRING QUALIFICATION (10CFR50.49)
SYSTEM NO. MISC. SYSTEM NAME: SPLICES / TERMINAL BLOCKS EQ FILE QUALIFICATION COMP. ID NO. NO. COMP. NAME STATUS LEVEL METHOD ACTION PLAN SPLICE ----
Okonite T-95/35 QUALIFIED DDR Test / Analysis Note 1 Splice SPLICE 35/1 Raychem WCSF Cable QUALIFIED NUREG Test / Analysis None required Sleeve 0588 Cat. I SPL ICE 35/3 Raychem Insulating QUALIFIED NUREG Test / Analysis None required End Cap (with sleeve) 0588 101A011-094-52 Cat. I SPLICE 20/1, 3 GE EB-5,-25 Terminal IN PROGRESS DOR Test / Analysis Final qualification pending 4, 5, 6 Blocks in a Gasketed completion of drilling of 7 Steel Junction Box 1/4" weep holes in various junction boxes in the Reactor Bldg. This will be completed by the Jan.,1985 refueling outage.
EPLICE 20/10 Buchanan NQ Series QUALIFIED NUREG Test / Analysis None required Terminal Blocks in 0588 a NEMA 4 Junction Box Cat. I CONNECTOR 35/2 Thomas & Betts Ring QUALIFIED NUREG Test / Analysis None required Terminal (Terzel) 0588 Cat. I SPL ICE 20/2 Cinch-Jones Terminal IN PROGRESS ---- ----
Replace with fully qualified Blocks in a Gasketed terminal blocks by the Jan.
Steel Junction Box 1985 outage.
Page 1 of 1
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(~S NEW YORK POWER AUTHORITY
'v_) JAMES A. FITZPATRICK NUCLE AR POWER PL ANT SYSTEM NO: MISC. SYSTEM NAME: SPICES / TERMINAL BLOCKS NOTES
- 1. The Authority considers this equipment to be qualified to l the DDR Guidelines based on a previousiqualification l assessment. However, the Authority.is presently re-reviewing this item based on related concerns regarding similarity contained in the Franklin TER received in late
! April, 1983. Internal resolution of these concerns will be i completed by August 15, 1983, at which time, a review of the resolution of these items by the NRC staf f may be requested. Based on the outcome of this review, it may be
( necessary for the Authority to update this response.
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-s NEW YOR OWER AUTHORITY ,
( '
) JAMES A. FITZPi CK NUCLEAR POWER PLANT '
LISTib0 AND STATUS OF HARSH ENVIRONMENT ELECIHICAL EQUIPMENT REQUIRING QUALIFICATION (10CFR50.49)
SYSTEM NO. MISC SYSTEM NAME: ELECTRICAL CABLING EQ FILE QUALIFICATION COMP. ID NO. NO. COMP. NAME STATUS LEVEL METHOD ACTION PLAN MARK NO.
NFE-2,5, 6, 8,9 16/1 Power / Control Cable QUALIFIED DDR Test / Analysis Note 1 11, 13, 20, 21 600VAC - XLPE 22, 23, 24, 25 (Okonite) 26, 34, 36, 52 NFF-15,30 NFE-61, 62, 63 16/2 Power / Control Cable QUALIFIED Test / Analysis 64, 65, 66 DDR Note 1 600/1000 VAC-FR NFF-21, 22, 24 Vulkene (GE) 25, 26, 27 28, 29, 31, 32, 33 NFE-61 thru 66 16/3 Control / Instrument QUALIFIED DDR Test / Analysis Note 1 NFF-21, 24, 26 16/4 Cable 600/1000 VAC -
27, 28, 29, 31 Pyrotrol III (Cerro) 32, 33, 35 NFG-02, 03, 04 11, 13, 15, 16 19, 20, 21, 22, 23, 26, 34-41, 43, 64 NFG-67, 69, 85 16/5 Thermocouple QUALIFIED DDR Test / Analysis Note 1 i Extension Wire -
Pyrotrol III (Cerro)
NFE-1, 4, 7 16/7 Power / Control QUALIFIED DDR Test / Analysis Note 1 35 Cable 600 VAC-EPR Page 1 of 2
,_ NEW K POWER AUTHORITY 1
JAMES A. FIT TRICK NUCLEAR POWER PLANI LISTING AND STATUS OF HA9EH ENVIRONMENT E TRICAL EQUIPMENT REQUIRING QUALIFICATION (10CFRS . 9)
SYSTEM NO. MISC SYSTEM NAME: ELECTRICAL COOLING EQ FILE QUALIFICATION COMP. ID NO. NO. COMP. NAME STATUS LEVEL METHOD ACTION PLAN NFF-4, 44, 46 16/8 Power Cable SKV-XLPE QUALIFIED DDR Test / Analysis Note 1 Armored NFG-5, 7 16/9 Instrumentation Cable QUALIFIED DOR Test / Analysis Note 1 Flametrol (Raychem)
R SS-6-104-1981 16/10 ~ Coaxial Cable QUALIFIED NUREG Test / Analysis Note 1 (Rockbestos) 0588 Cat. I 1952-68310 16/12 Instrument Cable QUALIFIED NUREG Test / Analysis' Note 1 16/13 (Eaton-Deko rad) 0588 Cat. I FR-EP 16/14 Instrument Cable QUALIFIED Test / Analysis NUREG Note 1 (Anaconda) 0588 Cat. I 14538-H-006 16/18 Instrument Cable QUALIFIED NUREG Test / Analysis Note 1 (B/W) 0588 Cat. I i
T7600 16/20 Power / Control QUALIFIED Test / Analysis NUREG None required (Ultrol) ,0588 Cat. I Firewall III 16/17 Power / Control QUALIFIED NUREG Test / Analysis None required Cable (Rockbestos) 0588 Cat. I Page 2 of 2
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() NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT SYSTEM NO: MISC. SYSTEM NAME: ELECTRICAL CABLING 4
4 1
- 1. It is the Authority's position that these cables are qualified based on qualification assessments previously performed. However, due to concerns presented in the Franklin TER (received in late April, 1983) relative to similarity, these assessments require additional reviews.
Internal resolution of these concerns by the Authority will be completed by August 15, 1983, at which time, a review of the resolution of these items by the NRC staff may be requested. Based on the outcome of this review, it may be necessary fo r the Authority to supplement this response.
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'/ NEthRKPOWERAUTHORITY JAMES A. FI RPATRICK NUCLEAR POWER PLANT LISTING AND STATUS OF HARSH ENVIRONMENT ELECTRICAL EQUIPMENT REQUIRING QUALIFICATION (10CFR50.49)
SYSTEM NO. MISC. SYSTEM NAME: CONTAINMENT ELECTRICAL PENETRATIONS EQ FILE QUALIFICATION COMP. ID NO. NO. COMP. NAME STATUS LEVEL ME.THOD ACTION PLAN JB-X-1000 15/13 Containment Electrical QUALIFIED NUREG Test / Analysis None required Penetration (Inst ru- 0588 ment) Cat. I JB-X-1000 15/1 Containment Elec- QUALIFIED DDR Test / Analysis None required JB-X-100F 15/2 trical Penetration JB-X-100G 15/3 (Low Voltage / Control)
JB-X-101B 15/4 JB-X-10 4D 15/9 JB-X-111B 15/12 JB-X-109 15/10 JB-X-110D 15/11 .
JB-X-103A 15/7 Containment Elec- QUALIFIED 00R Test / Analysis Nonc required JB-X-10 3B 15/8 trical Penetration JB-X-110C (Inst rument at ion)
JB-X-101E 15/5 Containment Elec- IN PROGRESS DDR Test / Analysis See System 02 trical Penetration Items 36/2, 3, 4 (Instrumentation)
Page 1 of 1
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