ML19260E310
| ML19260E310 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 01/28/1980 |
| From: | PUBLIC SERVICE CO. OF COLORADO |
| To: | |
| Shared Package | |
| ML19260E296 | List: |
| References | |
| P-0014, P-14, NUDOCS 8002150453 | |
| Download: ML19260E310 (23) | |
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Enclosure (3) to P-80014 SURVEILLANCE INSPECTION AND TEST CRITERIA FOR THE FORT ST. VRAIN NUCLEAR GENERATING STATION EE-SR-0001 Rev. 1 January 28, 1980 1960 :21 8002150 4'53
EE-SR-0001 Rev. 1 p.1 FORT ST. VRAIN NUCLEAR GENERATING STATION SURVEILLANCE INSPECTION AND TEST CRITERIA
- 1. INTRODUCTION Surveillance criteria have been generally established in Ref. 1 ror the Fort St. Vrain inservice inspection and testing program. However, there has been a need to clarify and refine some of these criteria in order to proceed to the actual review of the current surveillance requirements and to serve as a basis for recommending additional or modified surveillance requirements. The refined surveilla--e criteria replace those outlined in Ref. 1.
Note: The safety classes referred to in this report are those defined in the Fort St. Vrain FSAR.
- 2. PROPOSED SURVEILLANCE CLASSIFICATIONS
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2.1 CLASSIFICATION CRITERIA Surveillance classifications shall be defined for all safety-related (safety class 1) and for other (safety class 2) plant structures, systems, and components to reflect an orderly gradation of safety importance to this equipment. The classi-fications will be defined in accordance with the following criteria:
(a) Equipment items considered of highest safety priority are to be designated surveillance class S1 and are those safety class 1 or 2 items providing ultimate protection for these extreme situations int lving failure of major safety-related equipment which, although having a low probability of occur rence,have the potential for causing abnormal off-site doses due to fission product release, aggravated by the potential for core damage.
(b) Equipment items considered of next highest priority are to be designated surveillance class S2 and are those safety class 1 or 2 items providing ultimate protection for those extreme situations involving failure of major safety-related or other plant equipment which, although having a low probability of occu rrence,have the potential for causing abnormal off-site doses due to fission product release.
(c) 1960 :m2L Equipment items considered of next highest priority are to be designated surveillance class 53 and include all other safety class 1 or 2 equipment items not included in surveillance classes S1 and S2, and which contain or support the core or spent fuel elements.
EE-SR-0001aev, 1 P.2 2.1 (cont.)
(d) Equipment items considered of the next highest priority are to be designated surveillance class 54 and are those safety class 2 items which may provide additional protec-tion, eitner directly or indirectly, and thereby assist in preventing or mitigating the consequences of abnormal situations or assist in protecting the health and safety of the public.
2.2 SURVEILLANCE CLASS DEFINITIONS Using the above classification criteria and the accident scenarios evaluated in the FSAR, the following definitions have been developed which will allow all equipment important to safety to be further classified, for purpose of sur-veillance, according to the importance of their safety functions.
(a) Surveillance class S1 applies to those plant equipment items required to cope with the consequences of Design Basis Accident - DBAl, permanent loss of forced circulation.
This accident is defined as the worst case failure of the reactor forced circulation emergency cooling system and it is the only accident capable of potential core damage which could further increase off-site doses due to fission product release.
(b) Surveillance class S2 applies to those plant equipment items required to cope with the consequences of:
Design Basis Accident - DBA2, rapid depressurization/
blowdown, defined as the worst case failure of the reactor containment system or, the maximum credible reactivity accident, rod pair withdrawal, defined as the worst case failure of the reactor reactivity control system or, the maximum credible steam leak, rupture of a steam generator tube or subheader, defined as the worst case failure of the reactor secondary coolant system or, the maximum credible environmental disturbance, safe shutdown earthquake or maximum tornado, considered to be the worst case failure of non-safety ed (i.e. safety class 2) plant equipment. 23 (c) Surveillance class S3 applies to those plant equipm'ent items which contain the reactor and reactor coolant system, ,
to those plant equipment items which handle and store radioactive spent fuel elements and to those plant equip-ment items which provide structural support to surveillance class S1, S2 or S3 equipment.
EE-SR-0001 Rev. 1 p.3 2.2 (cont.)
(d) Surveillance class S4 applies to those other olant equipment items which provide additional protection, such as those that contain radioactive waste, provide fire protection for safety-related equipment, provide additional indication and control, etc.
2.3 APPLICATION CRITERIA (a) Surveillance classes S1 and S2 apply to those systems and components (or part thereof) which are provided with active _ safety functions to protect the integrity of the core and/or the containment under accident conditions, thus insuring that the plant safety objective is achieved during extreme situations.
(b) Surveillance class S3 applies to those structures, systems and components which are provided with active or passive safety functions to protect against the uncontrolled re-lease of radioactive fission products under normal or abnormal conditions, thus insuring that the plant safety objective is achieved during all other types of situations.
(c) Surveillance class S4 applies to those other systems and components which can perform active or passive safety functions, such as those which control operational re-leases of radioactivity, protect safety related equipment from the effects of fire, and contrci or monitor the operation of systems and equipment.
(d) Structures, systems, components, or parts thereof are assigned only to the highest of any classifications to which they apply.
(e) Auxiliary suppor, systems or parts thereof required to function along with the major equipment classified above shall be included in the same surveillance class as the major equipment. Typical auxiliary support systems in-clude: essential electric power, helium circulator auxiliary system, instrument air supply system, and hydraulic actuator supply system.
2.4 MAJOR EQUIPMENT SURVEILLANCE CLASSIFICATIONS The general surveillance classifications for the major Fort St. Vrain structures and systems is given in ,
Attachment 1 for information.
1960 :24 The detailed classifications of structures, systems, components, or parts thereof will be established on the basis of the individual safety functions and the rela-tive importance of the equipment in performing the safety functions.
EE-SR-0001 Rev. 1 p.4
- 3. SURVEILLANCE INSPECTION AND TEST REQUIREMENTS 3.1 OPERATIONAL READINESS OF SYSTEMS (a) Surveillance class S1 - The operational readiness of systems or parts thereof ussigned to surveillance class S1 shall be demonstrated either by normal operation or by surveillance testing and monitoring at a frequency consistent with the highest active compBnent test fre-quency. The surveillance requirements shall be based on verifying overall system performance, and availability of energy power sources. The surveillance shall be per-formed to the maximum exten't with the reactor operating at power.
(b) Surveillance class 52 - The operational readiness of systems or parts thereof assigned to surveillance class S2 shall be demonstrated by normal cperation or by system testing at a frequency consistent with the highest active component test frequency. The surveillance requirements shall be based on verifying system availability and operability to perform the safety function. The sur-veillance shall be performed with the reactor operating at power or shutdown, pressurized or depressurized.
(c) Surveillance classes S3 and S4 - The operational readiness of cystems or parts thereof assigned to surveillance classes S3 or S4 shall be demonstrated by normal operation or by testing individual active components at their re-spective test frequency.
(d) Normal operation means that characteristic data of the system or components shall be recorded during normal operation to meet the intent of the surveillance require-ments, at the frequency which otherwise would be required for testing.
(e) Testing shall be required when the system or components do not operate, or if no 'oal operation is not characteris-tic of the system operation when performing the safety function.
(f)
If the overall system testing implies the destruction of a component, such as a rupture disc for example, the operational readiness of the system shall be demonstrated by testing the operational readiness of individual parts of the system or active components.
1960 '25
EE-SR-0001 Rev. 1 p.5 3.2 OPERATIONAL READINESS OF ACTIVE COMPONENTS 3.2.1 PUMPS AND COMPRESSORS (a) Surveillance class S1 - The operational readiness of pumps and compressors assigned to surveillance class S1 shall be demonstrated by normal operation or by surveillance testing those pumps and compressors not normally in operation. The frequency, as well as the rules and requirements for surveillance testing of these pumps will be based on the Draft ASME Code,Section XI, Division 2.
(b) Surveillance class S2 - The operational readiness of pumps and compressors assigned to surveillance class S2 shall be demonstrated by normal operation,or by surveillance testing at least once each quarter those pumps and compressors not normally in operation. The rules and requirements for surveillance testing will be based on the Draft ASME Code,Section XI, Division 2.
(c) Surveillance classes 53 and 54 - The operational readiness of pumps and compressors assigned to surveillance class S3 or S4 shall be demonstrated by normal operation,or by surveillance testing once each quarter to exercise those pumps and compressors not normally in operation.
3.2.2 VALVES.
(a) Surveillance class S1 - The operational readiness of valves assigned to surveillance class S1 shall be demon-strated by normal operation or by surveillance testing at a frequency, and according to rules and requirements forsurveillancetestingbasedontheDraftASMECfe J 26 Section XI, Division 2. 19 (b) Surveillance class S2 - The operational readiness of auto-matic isolation valves, safety / relief valves and rupture discs assigned to surveillance class S2 shall be demon-strated by normal operation or by surveillance testing at a frequency, and according to rules and requir'ments for surveillance testing based on the Draft ASME Code,Section XI, Division 2. The operational readiness of check valves and remote manual isolation valves assigned to surveillance class 52 shall be demonstrated by normal operation or by surveillance testing at least once each year to exercise those valves, which do not normally operate, according to rules and requirements for sur-veillance testing based on the Draft ASME Code,Section XI, Division 2.
EE-SR-0001 Rev. 1 p.6 3.2.2 (Cont.)
(c) Surveillance classes S3 and S4 - The operational readiness of safety / relief valves and rupture discs assigned to surveillance classes 53 or S4 shall be demonstrated by testing at a frequency, and according to rules and require-ments for surveillance testing based on the Draft ASME Code,Section XI, Division 2. The operational readiness of auto-matic isolation valves assigned to surveillance classes S3 and S4 shall be demonstrated by normal operation or by surveillance testing at least once each year to exercise those valves which do not normally operate, according to rules and requirements for surveillance testing based on the Draft ASME Code,Section XI, Division 2. The operational readiness of check valves and remote manual isolation valves assigned to surveillance classes S3 and S4 shall be demon-strated by normal operation or by surveillance testing at least once every five years those valves, which do not normally operate, according to rules and requirements for surveillance testing based on the Draft ASME Code,Section XI, Division 2. .
(d) Valves, which do not normally operate, can be tested to the requirements of the next lower surveillance class if, during reactor operation, they are in the position required to perform their safety function. If, i :?dition, they are fail safe in that position, such valvas need not be tested. Also, valves need not be tested if they are exempt from testing by the Draft ASME Code,Section XI, Division 2.
3.2.3 INSTRUMENTATION AND CONTROLS (a) Surveillance class S1 - The operational readinesms of in-strumentation and controls assigned to surveillance class S1 shall be demonstrated by a-functional test at least once each month if they monitor an act.ive functicn, or at least quarterly if they monitor a passive function.
(b) Surveillance class S2 - The operation 7.1 readiness of in-strumentation and controls assigned ta surveillance class S2 shall be demonstrated by a functioaal test at least quarterly if they monitor an active tanction, or at least once each year if they monitor a passive function.
(c) Surveillance classes S3 and S4 - The operational readiness of instrumentation and controls assigned to surveillance classes S3 or S4 shall be demonstrated by a functional test at least once each year if they monitor an active or a passive function.
(d) Instrumentationandcontrolsrelatedtovalveb tio shall be tested at the frequency required for valve testing in accordance with paragraph 3.2.2. However, calibration tests need not be performed more of ten than at least once each year.
EE-SR-0001 Rev. 1 p.7 3.2.3 (cont.)
(e) Calibration - In addition to the above functional tests, instrument accuracy shall be demonstrated generally once each year by a calibration test.
3.3 STRUCTURAL INTEGRITY (for passive equipment only assigned to surveillance class S3 or S4)
Structural integrity of plant equipment will be determined by surveillance testing or surveillance inspection. Surveillance testing will include pressure tests and leakage tests. Sur-veillance inspection will be limited to visual examinations, observations and measurements. Surface and volumetric examina-tions of pressure boundaries (primary and secondary) using non destructive test methods will not be used for structural in-tegrity surveillance. However, where specific concerns are identified, non destructive examination may be used to supplement surveillance inspections and tests.
3.3.1 PRESSURE AND LEAKAGE TESTS (a) Leakage monitoring - Safety-related (safety class 1) passive plant equipment provided with instrumentation which allows direct leakage monitoring (such as flow, pressure, level, radiation indicators and/or alarms) shall have their structural integrity demonstrated by continuous leakage monitoring and/or alarm during plant operation. In addition, PCRV penetration closure leakage shall be measured once each quarter for each penetration group.
(b) Leakage examination - Safety related (safety class 1) passive plant equipment which cannot be monitored for leakage shall have their structural integrity demonstrated by an examination for leakage of their accessible cortions while the equipment is at or near its normal operating
. pressure. Such an examination for leakage shall be per-formed st least once during each refueling cycle, for those equipment assigned to surveillance class S3, and at least once every five years for those equipment assigned to surveillance class S4, unless the equipment can be exempt from leakage examination according to the rules of paragraph (c).
(c) Exemption from leakage examination - 1960 '28 (i) Equipment which operate at conditions not expected to degrade their integrity during normal operation, when compared to design conditions, shall have their structural integrity demonstrated by design.
(ii) The structural integrity need not be demonstrated for equipment the failure of which:
does not prevent the performanc,e of an ,
EE-SR-0001 Rev. 1 p.8 3.3.lc (ii) (cont.)
active safety function, and does not lead to release of radioactivity in excess of the limits of 10CFR20, postulating no additional failure, and does not lead to release of radioactivity in excess of the limits of 10CFR100, postulating an additional
, single active or passive failure.
3.3.2 STRUCTURE INSPECTIONS (a) PCRV - Structural integrity of the PCRV shall be verified by surveillance inspections. These inspections shall consist of visual examinations, monitoring, measurements, and inspection of specimens. The frequency, as well 43 the rules and requirements for these inspections will be based on Subsection IGK of the Draft ASME Code,Section XI, Division 2 and will take into consideration the specific design features of the Fort St. Vrain PCRV.
(b) Reactor internals - Structural integrity of the PCRV thermal barrier and support structures for the reactor core shall be verified, where feasible, by surveillance inspections of material specimens which have been exposed to conditions similar to the support components. The frequency of such inspections will be based on evaluations of the material properties.
(c) Steam generators - Structural integrity of the reactor coolant boundary in the steam generators shall be verified by continuous leakage monitoring (see paragraph 3.3.la).
Structural integrity of the steam generators shall be deemed acceptable as long as primary coolant moisture and reheat steam activity remain below acceptable limits.
The structural integrity of the steam generators will be further assured by controlling feedwater chemistry.
(d) Bolting - Bolting of major safety-related (safety class 1) plant equipment items which are frequently disassembled (at least once during each refueling cycle) shall be 'risually examined for indications of surface damage, which could be detrimental to the required structural integrity, when such equipment items are disassembled or reassembled if they have not already been examined during the refueling cycle.
(e) Equipment support - Criteria for surveillance of equipment supports will be determined later.
- 4. REFERENCES 1960 29 (1) PSC letter P-79176 J.K. Fuller to W.P. Gammill dated August 22, 1979.
EE-SR-0001 Rev. 1 p.9 TABLE 1 CRITERIA FOR SURVEILLANCE CLASS S1 EQUIPMENT OPERATIONAL READINESS OF THE SYSTEM (criteria 3.la, 3.ld, 3.le, 3.lf)
Normal operation or testing at a frequency consistent with the highest active component test frequency (to the maximum extent with reactor at power) to demon-strate system performance and availability of emergency power sources.
OPERATIONAL READINESS OF PUMPS AND COMPRESSORS (criteria 3.2.la)
Normal operation or testing at a frequency and according to rules based on Code requirements.
OPERATIONAL READINESS OF VALVES HAVING AN ACTIVE SAFETY FUNCTION (criteria 3.2.2a, 3.2.2d)
For all the valves, normal operation or testing at a frequency and according to rules based on Code require-ments.
Valves which do not operate can be tested to the re-quirements of surveillance class S2 if, during reactor operation, they are in the position required to perform their safety function. If they are also fail safe in that position, they need not be tested. Valves need not be tested if allowed by the Code.
OPERATIONAL READINESS OF INSTRUMENTATION AND CONTROLS (criteria 3.2.3a, 3.2.3d, 3.2.3e)
- Functional test, at least once each month for monitoring of active functions or at least once each quarter for monitoring of passive functions.
960 ;30 Calibration, once each year.
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- Valve instrumentation and controls, according to valve testing.
EE-SR-0001 Rev. 1 p.10 TABLE 1 (cont.)
STRUCTURAL INTEGRITY Does not apply to surveillance class S1 which deals only with active safety functions.
NOTES: (1) " Code" means the Draft ASME Code,Section XI, Division 2.
(2) Criteria are referenced as numbered in EE-SR-0001.
1960 ;31
EE-SR-0001 Rev. 1 p.ll TABLE 2 CRITERIA FOR SURVEILLANCE CLASS S2 EQUIPMENT OPERATIONAL READINESS OF THE SYSTEM (criteria 3.lb, 3.1d, 3.le, 3.if)
Normal operation or testing at a frequency consistent with the highest active component test frequency (reactor at power or shutdown, pressurized or de-pressurized) to demonstrate availability and opera-bility of the system.
OPERATIONAL READINESS OF PUMPS AND COMPRESSORS (criteria 3.2.lb)
Normal operation or testing at least once each quarter, according to rules barad on Code requirements.
OPERATIONAL READINESS OF VALVES HAVING AN ACTIVE SAFETY FUNCTION (criteria 3.2.2b, 3.2.2d)
Safety / relief valves, rupture discs and automatic iso-lation valves, normal operation or testing at frequency and according to rules based on Code requirements.
Remote manual isolation valves and check valves, normal operation or testing at least once a year, according to rules based on Code requirements.
Valves which do not operate can be tested to the re-quirements of surveillance class S3 if, during reactor operation, they are in the position required to perform their safety function. If they are also fail safe in tha_t position, they need not be tested. Valves need not be tested if allowed by the Code.
1960 '32 OPERATTONAL READINESS OF INSTRUMENTATION AND CONTROLS (criteria 3.2.3b, 3.2.3d, 3.2.3e)
Functional test, at least quarterly for monitoring of active functions or at least once each year for monitoring of passive functions.
Calibration, once each year.
Valve instrumentation and controls, according to valve testing.
EE-SR-0001 Rev. 1 p.12 TABLE 2 (cont.)
STRUCTURAL INTEGRITY Does not apply to surveillance class S2 which deals only with active safety functions.
NOTES: (1) " Code" means the Draft ASME Code,Section XI, Division 2.
(2) Criteria are referenced as numbered in EE-SR-0001.
8 1960 '33
EE-SR-0001 Rev. 1 p.13 TABLE 3 CRITERIA FOR SURVEILLANCE CLASS S3 EQUIPMENT OPERATIONAL READINESS OF THE SYSTEM (criteria 3.lc, 3.1d, 3.le, 3.lf)
Normal operation or testing individual active compo-nents at their respective test frequency.
OPERATIONAL READINESS OF PUMPS AND COMPRESSORS (criteria 3.2.lc)
Normal operation or startup test at least once each quarter.
OPERATIONAL READINESS OF VALVES HAVING AN ACTIVE SAFETY FUNCTION (criteria 3.2.2c, 3.2.2d)
Safety / relief valves and rupture discs, testing at frequency and according to rules based on Code requirements.
Automatic isolation valves, normal operation or testing at least once a year, according to rules based on Code requirements.
Remote manual isolation valves and check valves, normal operation or testing at least once every five years, according to rules based on Code requirements.
Valves need not be tested, if, during reactor operation they are in the position required to perform their safety function and also are fail safe in that position, or as allowed by the Code.
OPERATIONAL READINESS OF INSTRUMENTATION AND CONTROLS (criteria 3.2.3c, 3.2.3d, 3.2.3e)
Functional test, at least once each year. ,
Calibration, once each yea..
1960.234 Valve instrumentation and control, according to valve testing.
EE-SR-0001 Rev. 1 TABLE 3 (cont.) p,14 STRUCTURAL INTEGRITY (criteria 3.3.la, 3.3.lb, 3.3.lc)
- Continuous leakage monitoring and/or alarm during plant operation, or examination for leakage of accessible portions, at least once during each refueling cycle, at or near normal operating pressure unless operating conditions not expected to degrade integrity (compared to design conditions) or unless_ failure does not prevent safety function and satisfies 10CFh20 limits with no additional failure and satisfies 10CFR100 limits with one additional single active or passive failure.
BOLTING (criteria 3.3.2d)
- Visual examination of major safety class 1 equipment items which are frequently disassembled, when such item is disassembled or Laassembled, if such examinatien has not already been cerforr.e 3 d.uring the refuelinn cycle.
NOTES: (1) " Code" means the Draft ASME Code,Section XI, Division 2.
(2) Criteria are referenced as numbered in EE-SR-0001.
1960 :35
EE-SR-0001 Rev. 1 p.15 TABLE 4 CRITERIA FOR SURVEILLANCE CLASS S4 EQUIPMENT OPERATIONAL READINESS OF THE SYSTEM, (criteria 3.lc, 3.1d, 3.le, 3.lf)
Normal operation or testing individual act 6ve compo-nents at their respective test frequency.
, OPERATIONAL READINESS OF PUMPS AND COMPRESSORS (criteria 3.2.lc)
Normal operation or startup test at least once each quarter.
OPERATIONAL READINESS OF VALVES HAVINi AN ACTIVE SAFETY FUNCTION (criteria 3.2.2c, 3.2.2d)
Safety / relief valves and rupture discs, testing at frequency and according to rules based on Code requirements.
Automatic isolation valves, normal operation or testing at least once a year, according to rules based on Code requirements.
Remote manual isolation valves and check valves, normal operation or testing at least once every five years, according to rules based on Code requirements.
Valves need not be tested, if, during reactor operation they are in the position required to perform their safety function and also are fail safe in that position, or as allowed by the Code.
1960 236 OPERATIONAL READINESS OF INSTRUMENTATION AND CONTROLS (criteria 3.2.3c, 3.2.3d, 3.2.3e)
Functional test, at least once each year.
Calibration, once each year.
Valve instrumentation and control, according to valve testing
TA;-LE 4 (cont.) EE-SR-0001 Rev. 1 p.16 STRUCTURAL INTEGRITY (criteria 3.3.la, 3.3.lb, 3.3.lc)
Continuous leakage monitoring and/or alarm during plant operation, or examination for leakage of accessible portions, at least once every five years, at or near normal operating pressure unless operating conditions not expected to degrade integrity (compared to design conditions) or unless failure does not prevent safety function and satisfies 10CFR20 limits with no additional failure and satisfies 10CFR100 limits with one additional single active or passive failure.
BOLTING (criteria 3.3.2d)
Visual examination of major safety class 1 equipment items which are frequently disassembled, when such item is disassembled or reassembled, if such examination has not already been performed during the refueling cycle.
NOTES: (1) " Code" means the Draft ASME Code,Section XI, Division 2.
(2) Criteria are referenced as numbered in EE-SR-0001.
1960 37
EE-SR-0001 Rev.1 ,
Attachment p.1 PROPOSED SURVEILLANCE CLASSIFICATI0t11 MAJOR EQUIPMENT / SYSTEM CLASSIFICATIONS SURVEILLANCE CLASS EQUIPMENT / SYSTEM SAFETY FUNCTION S1 RESERVE SHUTDOWN SYSTEM CORE REACTIVITY CONTROL BACK-UP EMERGENCY COOLING CONTAINMENT TEMPERATURE EQUIPMEllT . CollTROL REACTOR BUILDING ACTIVITY AND RADIATION C0tlTROL HELIUM PURIFICATION C'ONTAltlMENT PRESSURE /
SYSTEM - TEMPERATURE CONTROL S2 CONTROL R0D DRIVES CORE REACTIVITY CONTROL REACTOR SCRAM LOGIC CORE REACTIVITY C0tlTROL SAFE SHUTDOWN EMERGENCY CORE TEMPERATURE C0tlTROL COOLING EQUIPMENT STEAM WATER DUMP SYSTEM CONTAINMENT PRESSURE C0tlTROL PCRV SAFETY VALVES CONTAINMENT PRESSURE CONTROL LOOP TRIP / CIRCULATOR TRIP CORE TEMPERATURE / CONTAINMENT LOGIC PRESSURE CONTROL so CN CD LN 00
EE-SR-0001 Rev.1 -
Attachment p.2 14AJOR EQUIPMENT / SYSTEM CLASSIFICATIONS (CONTINUED)
SURVEILLANCE CLASS EQUIPMENT / SYSTEM SAFETY FUNCTIDE S3 PCRV STRUCTURE ACTIVITY AND RADIATION CONTROL PCRV LINER ACTIVITY AND RADIATION CONTROL PCRV PENETRATIONS AND ACTIVITY AND RADIATION CONTROL CLOSURES
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CORE SUPPORT STRUCTURE REACTIVITY CONTROL CORE TEMPERATURE CONTROL STEAM GENERATORS ACTIVITY CONTROL
, CORE TEMPERATURE CornPal FUEL HANDLING MACHINE ACTIVITY Al,D PfN arION CONTROL FUEL TEMPERATURE CONTROL FUEL STORAGE FACILITY ACTIVITY AND RADIATION CONTROL FUEL TEMPERATURE CONTROL S4 EQUIPMENT CONTROL PLANT CONTROL SYSTEMS EQUIPMENT INSTRUMENTATION PLANT CONTROL SYSTEMS RADIOACTIVE WASTE SYSTEMS ACTIVITY CONTROL bo FIRE PROTECTION EQUIPMENT FIRE PROTECTION as CD
.n u .
NO
EE-SR-0001 Rev. 1 Attachment p.3
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PROPOSED SURVEILLANCE CLASSIFICATIONS DETAILED EQUIPMENT / SYSTEM CLASSIFICATION SURVEILLANCE CLASS S1 REACTIVITY CONTROL EQUIPMENT
- RESERVE SHUTDOWN SYSTEM (12)*
PCRV COOLING EQUIPMEld
- HELIUM PURIFICATION SYSTEM (23)*
(INCLUDING HELIUM STORAGE SYSTEM INTERFACE)'
- NITROGEN SYSTEM (25)*
- CIRCULATING WATER MAKEUP SYSTEM (41)*
- SERVICE WATER. SYSTEM (42)*
- FIREWATER SYSTEM (45)*
- PCRV COOLING WATER SYSTEM (46)*
- PURIFICATION COOLING WATER SYSTEM (47)*
ONLY THOSE PORTIONS ACTIVITY / RADIATION CD.NTROL EQUIPMENT MARKED AS SAFETY-RELATED
- ] - REACTOR BUILDING VENTILATION EXHAUST SYSTEM (73) ON THE SR-6-1 DRAWINGS.
ON - REACTOR BUILDING OVERPRESSURE PROTECTION SYSTEM (73) c3 as CD .
EE-SR-0001 Rev.1 .
Attachment p.4 SURVEILLANCE CLASS SI (CONTINUED)
PNEUMATIC / ELECTRIC POWER EQUIPMENT
- ACM SYSTEM (48)
- AUXILI ARY BOILER FUEL OIL SYSTEM (811)*
- STANDBY GENERATOR, OII. AND AIR SYSTEM (92)*
- STATION BATTERIES (92)
- ESSENTIAL POWER SYSTEM (92)
- 0NLY THOSE PORTIONS MARKED AS SAFETY-RELATED ON TliE SR-6-1 DRAWINGS 0
M wo Ch CD t .
Ah s
e
EE-SR-0001 Rev.1 p Attachment p.5 SURVEILLANCE CLASS S2 REACTIVITY CONTROL EQUIPMENT
- CONTROL ROD DRIVES (12)
- PLANT PROTECTIVE SYSTEM - SCRAM LOGIC (93)*
(INCLUDING INTERFACE WITH R0D CONTROL SYSTEM)
CORE COOLING EQUIPMEf11
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- HELIUM CIRCULATORS AND AUXILIARY SYSTEM (21)*
- SECONDARY COOLANT SYSTEM (22)*
(INCLUDING INTERFACE WITH REACTOR BUILDING VENT AND DRAIN SYSTEM)
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- FEEDWATER SYSTEM (31)*
PCRV PROTECTION EQUIPMENT
- STEAM-WATER DUMP SYSTEM (22)*
- PCRV SAFETY VALVES (11)*
- PLANT PROTECTIVE SYSTEM - LOOP / CIRCULATOR TRIP LOGIC (93)*
- PLANT INSTRUMENTATION SYSTEM - NUCLEAR /IN-RdACTOR/ PIPE RUPTURE INSTRUMENTS (93)*
s e /LUXLLI ARY EQUIPMENT
)
- CONTROL COMPLEX HVAC (75)*
- 0NLY THOSE PORTIONS MARKED
- FIRE PUMP HOUSE HVAC (75)*
AS SAFETY-RELATED ON THE II3 - INSTRUMENT AIR SYSTEM (82)*
SR-6-1 DRAWINGS.
- HYDRAULIC POWER SYSTEM (91)*
- HYDRAULIC SNUBBERS (98)
EE-SR-0001 Rev.1 g Attachment p.6 SURVEILLANCE CLASS _63 ACTIVITY / RADIATION CONTROL EQUIPMEtE
- PCRV STRUCTURE (ll)
- PCRV LIf1ER (ll)
- PCRV PEllETRATI0flS AND CLOSURES (ll)
- PCRV THERMAL BARRIER (11)
- PCRV INTERf1AL STRUCTURE (CORE SUPP0T) (11)
- PCRV AUXILIARY SYSTEM (11)*
- FUEL HAllDLING MACHINE (13) '
- FUEL STORAGE FACILITY (14) -
- STEAM GENERATOR (22)
SPEN' FUEL COOLING EQUIPMEfE
- FUEL STORAGE FACILITY AUXILIARY SYSTEM (14)*
- "g
- ONLY THOSE PORTIONS C] MARKED AS SAFETY-RELATED ON THE SR-6-1 DRAWINGS ca 4
EE-SR-0001 Rev.1 '
Attachment p.7 SURVEILLANCE CLASS SA INSTRUMENTATION AND CONTROL EQUIPMENT
- OVERALL PLANT CONTROL SYSTEM (93)*
- CONTROL ROD AND ORIFICING CEI SYSTEM (93)*
- PCRV INSTRUMENTS AND DATA ACQUISITION SYSTEM (93)*
- FAST GAS AND IODINE SAMPLING SYSTEM (93)*
- SG T/C AND S/G INSTRUMENTATION SYSTEM (93)* ,
- ANALYTICAL INSTRUMENTATION SYSTFM (93)*
- AREA RADIATION MONITORING SYSTEM (93)*'
- COOLANT MEASUREMENT DISPLAY SYSTEM (93)* .
- SEISMIC INSTRUMENTATION SYSTEM (89)
- PCRV SURFACE TEMPERATURE MONITORS (73)
' - PCRV AREA 25P AND TEMPERATURE MONITORS (73) *0NLY THOSE PORTIONS
- CONTROL ROOM TEMPERATURE CONTROLLER (75) WHICH PROVIDE AN ADDI-
- 480V ROOM TEMPERATURE INDICATOR (75) TIONAL SAFETY FUNCTION
- AIR EJECTOR VENT MONITOR (41) .
- HOT REHEAT PIPING MONITORS (22) -
- HOT REHEAT PIPING POWER RELIEFS (52)
NO CN CD ,
4h
EE-SR-0001 Rev. 1 Attachment p.8 e a
SURVEILLANCE CLASS SA (CONTINUED)
RADIOACTIVE WASTE MANAGEMENT EQUIPMENT
- RADI0 ACTIVE LIQUID WASTE STORAGE SYSTEM (62)
- RADI0 ACTIVE GAS SYSTEM (63)
ELRE_ PROTECTION EQUIPMENT
- FIRE WATER SYSTEM - DELUGES / SPRAYS / HOSE REELS (45)
- CONTROL. COMPLEX FIRE DETECTION AND ALARM SYSTEM (XX)
- CONTROL COMPLEX HALON SYSTEM (45)
- CONTROL COMPLEX EMERGENCY BREATHABLE AIR SYSTEM (45)
- CONTROL COMPLEX FIXED WATER SPRAY SYSTEM (45)
- CONTROL COMPLEX CABLE COATING AND SEAL SYSTEM (XX)
- CO2 SYSTEM (51) mM NO CN CD Ln
.