ML18018B472
| ML18018B472 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 11/14/1983 |
| From: | Mcduffie M CAROLINA POWER & LIGHT CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-***, TASK-TM LAP-83-528, NUDOCS 8311170368 | |
| Download: ML18018B472 (24) | |
Text
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REGULATOR Y 'RMATION D ISTRI BUTION SY 1
(R IDS
)
P'CCESSION NBR ~ 831 1 170368 DOC ~ DATE 83/1 1/14'OTARIZED NO DOCKET FACIL:50"400'Shearon Harris Nuclear Power Plant< Unit 1< Carolina 05000400 50 401 Shear on Harris Nuclear Power Planti Unit 2i 'Carolina 05000401 AUTH BYNAME AUTHOR AFFILIATION MCDUFFIE<M>AD Carolina Power L Light Co ~
AECIP,NAME RECIPIKNT AFFILIATION DKNTONrH ~ RE Office of Nuclear Reactor Regulationi Director
SUBJECT:
Forwards addi info re draft SER Open Item 220 on QA program L NUREG 0737 itemsiw/reviesed FSAR pages.
DISTRIBUTION CODE:
B001S COPIES RECEIVED:LTRiENCL +
SIZE:,'
,w4 TITLE: Licensing Submittal:
PSAR/FSAR Amdts 8, Related Correspondence NOTES:
RECIPIENT ID CODE/NAME NRA/DL/ADL NRA LB3 LA INTERNAL: ELD/HDS1 IE/DEPKR/EPB 36 IE/DEQA/QAB 21 NRR/DE/CEB 11 NRR/DE/EQB 13 NRR/DE/MEB 18 NRR/DE/SAB 24 NRR/DHFS/HFEB40 NRR/DHFS/PSRB NRR/OS I/AEB 26 NRR/DSI/CPB 10 NRR/DSI/ICSB 16 NRR/DSI/PSB 19 NRR/DSI/RSB 23 RGN2 EXTERNAL: ACRS 41 DMB/DSS (AMDTS)
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Carolina Power & Light Company NO'II'
- 4. )S83 SERIAL:
LAP-83-528 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT NOS ~
1 AND 2 DOCKET NOS ~ 50-400 AND 50-401 DRAFT SAFETY EVALUATION REPORT RESPONSES TO REQUESTS FOR ADDITIONALINFORMATION
Dear Mr. Denton:
Carolina Power
& Light Company (CP&L) hereby transmits one original and forty copies of a revision to Shearon Harris Nuclear Power Plant Draft
- Safety Evaluation Report Open Item 220, Quality Assurance Branch.
The responses to items a.7, a.8(1), a.8(3), a.9(1), b.2, c.5, c.10, c.l5, and c.l8 were revised as shown in the attached to provide clarification to the NRC staff.
The balance of the response remains the same as originally submitted by letter dated August ll, 1983.
We willbe providing responses to other requests for additional information shortly.
83iii70368 83iii4 PDR ADOCK 05000400 PDR CT/cfr (8471NLU)
Enclosures Yours very truly, Qg 7h~
M. A. McDuffie Senior Vice President Nuclear Generation cct Mr. B. C. Buckley (NRC)
Mr. J.
Spraul (NRC)
Mr. G. F. Maxwell (NRC SHNPP)
Mr. J.
P. O'Reilly (NRC-RII)
Mr. Travis Payne (KUDZU)
Mr. Daniel F.
Read (CHANGE/ELP)
Mr. R. P. Gruber (NCUC)
Chapel Hill Public Library Wake County Public Library Mr. Wells Eddleman Dr. Phyllis Lotchin Mr. John D. Runkle Dr. Richard D. Wilson Mr. G. 0. Bright (ASLB)
Dr. J.
H. Carpenter (ASLB)
Mr. J. L. Kelley (ASLB) 411 Fayetteville Street o P. O. Box 1551 o Ralefgh, N. C. 27602
ll t
4
Shearon Harris Nu r Power Plant D aft SER en Item N 20 The NRC requested the inclusion of the following listed information in the SHNPP FSAR:
260.0
- Quality Assurance Branch 260.67 Section 17.1.2.2 of the standard format (Regulatory Guide 1.70) requires the identification of safety-related structures,
- systems, and components. controlled by the QA program.
You are requested to supplement and clarify the Harris FSAR in accordance with the following'-
a.
The following items do not appear on FSAR Table 3.2.1-1.
Add the appropriate items to the table or justify not doing st 1.
Containment emergency sumps 2.
Equipment hatch and personnel air locks 3.
Guard pipes and leak-tight compartments for contain-ment emergency sump recirculation lines and valves 4.
Engineered safety features actuation system 5.
Charcoal filters in the control room HVAC system 6.
Fuel building radiation monitor 7.
,Roof and site drainage system including drains,
- parapets, grading, culverts, and channels 8.
AC Onsite Power System (Class 1E)
- Diesel generator governor, voltage regulator, and excitation system
- Instrumentation,
- control, and power cable splices, connectors, and terminal blocks
- Conduit and cable trays and their supports which do not contain Class lE cables but whose failure may damage other safety-related items Load sequencer AC control po~er inverters
- AC,vital bus distribution equipment
Shearon Harris Nu wer Plant Draft SER en Item No. 220 Cont'd 9.
DC Power System (Class lE)
Conduit and cable trays and their supports which do not contain Class 1E cables but whose failure may damage other safety-related items Battery racks Protective relays and control panels H
10.
Radioactivity sampling (air, surfaces, liquids) 11.
'Radioactivity contamination measurement and analysis equipment 12.
Personnel monitoring equipment (internal, e.g. whole body counts, and external, e.g.,
TLD system) 13.
Instrument storage, calibration, and maintenance program 14.
Decontamination facilities, personnel, and equipment 15.
Respiratory protection equipment (including testing) 16.
Contamination control
- b. 'larify Table 3.2.1-1 as noted below or justify not doing so.
1.
Provide a commitment that all safety-related instrumentation and controls (I&C) described in FSAR Section 7.1 through 7.6 and other safety-related I&C for safety-related fluid systems will be subject to the pertinent requirements of the FSAR Appendix B QA program.
This can be done by a footnote to FSAR Table 3.2.1-1.
2.
Under "Electrical Systems and Components" on FSAR Amendment 3 page 3.2.1-43 is "Safety-related power control and instrument cables and raceways."
It appears that a
comma should be inserted after "power" and one after "control."
3.
Notes 26 and 27 to FSAR Table 3.2.1-1 state that some required information can be found in Table 11.4.2-1.
Table 11.4.2-1 does not have this information, and clari-fication is needed.
c.
FSAR Amendment 3,
on page 3.2.1-42, includes "Post Accident Monitoring Instrumentation NUREG 0737."
However, Enclosure 2
of NUREG-0737 identified numerous other items that are also safety-related or of such importance to safety that they should have the pertinent requirements of the FSAR Operational QA program applied.
These items are listed below. Provide such a commitment in Table 3.2.1-1 of the FSAR or justify not doing so.
Shearon Harris Nu(
ar Power Plant Draft SER en lth 220 Cont'd NUREG-0737 (Enclosure 2)
Clarification Item 1.
Plant-safety-parameter display console 2.
Reactor coolant system vents 3.
Plant shielding 4.
Post accident sampling capabilities 5.
Valve position indication 6.
Auxiliary Feedwater system 7.
Auxiliary feedwater system initiation and flow 8.
Emergency power for pressurizer heaters 9.
Dedicated hydrogen penetrations 10.
Containment isolation dependability 11.
Instrumentation for detection of inadequate core-cooling I.D.2 II.B.1 II.B.2 II.B.3 II.D.3 II.E.1 ~ 1 II.E.1.2 II.E.3.1 II.E.4 '
II.E.4.2 II.F.2 12.
Power supplies for pressurizer relief valves, block valves, and level indicators II.G.1 13.
Automatic PORV isolation 14.
PID controller 15.
Anticipatory reactor trip on turbine trip 16.
Power on pump seals 17.
Emergency plans 18.
Emergency support facilities 19.
Inplant I2 radiation monitoring 20.
Control room habitability II.K.3.1 II.K.3.9 II.K.3.12 II.K.3.25 III.A1.1/III.A.2 III.A.1.2 III.D.3.3 III.D.3.4
Shearon Harris Nuclear Power Plant Draft SER Open Item 220 (Cont'd)
Revised Res onse
~Res ense The responses to items a.7, a.8(1), a.8(3), a.9(1), b.2, c.5, c.10, c.l5, and c.l8 were revised as shown below to provide clarification to the NRC staff.
The balance of the response remains the same as originally submitted by letter dated August ll, 1983.
a.l The containment emergency sump is included under containment building and containment liner which appears on Page 3.2.1-4 of FSAR Table 3.2 '-1.
See FSAR Section 3.8.1 for a discussion of the concrete containment.
The containment sump screens, which are seismically designed, are listed as part of the Containment Spray System.
Page 3.2.1-19 of FSAR Table 3.2.1-1 will be amended to reflect the seismic design of the CS Sump screens.
ae2 The equipment hatch and personal airlocks appear on Page 3.2.1-5 of FSAR Table 3.2 '-1.
a e3 The guard pipes and leak-tight compartments for containment emergency sump recirculation lines and valves are included as part of the containment building and containment liner which appears on Page 3.2.1-4 of FSAR Table 3.2.1-1 ~
See FSAR Section 3.8.1 for a discussion of the concrete containment.
a.4 The Engineered Safety Features Actuation System appears on Page 3.2.1-44 of Table 3.2.1-1.
a.5 The charcoal filters in the Control Room HVAC System is part of the Control. Room HVAC System Emergency Filtration System which appears on Page 3.2.1-32 of Table 3.2.1-1.
See FSAR Section 9.4.1 for a discussion of the Control Room HVAC System.
a.6 The fuel building emergency safety effluent radiation monitors are included as part of the Radiation Monitoring System Effluent Monitors which appear on Page 3.2.1-42 of Table 3.2.1-4.
See FSAR Section 11.5 '.7.2.3 for a discussion of the Fuel Handling Building Emergency Exhaust monitors.
a ~ 7 In the FSAR site flooding analyses, no credit is given for the roof and site drainage systems (drains, parapets,
- culverts, and channels).
These analyses rely solely upon maintaining site grade such that Probable Maximum Precipitation will not cause flooding of safety-related structures.
Changes to grade elevations surrounding the power block will be reviewed to assure that site flooding analyses remain valid.
Modifications to site grade elevations would be subject to the pertinent provisions of the quality assurance program.
An entry to this effect will be added to Table 3.2.1-1 in a future amendment to the FSAR.
The change will be as indicated in the attached marked-up pages to the FSAR.
~ 220 (Cont'd)
Page 2
a.8 AC On-Site Power Systems (Class lE)
The Diesel Generator Governor, Voltage Regulator and Excitation system are part of the Diesel Generator which appears on Page 3.2.1-36 of the table.
See FSAR Section 8.3 '.1.15, Standby AC Power Supply; for a discussion of the Diesel Generator.
These items will be subject to the pertinent provisions of the quality assurance program.
2 ~
Table 3.2.1-1 will be amended to include the instrumentation, control, and power cable splices, connectors, and terminal blocks, for safety related circuits'
~
Table 3.2.1-1 will be amended in a future amendment to address nonsafety-related cable trays, conduits and their applicable supports where structural integrity is required to assure the integrity of safety-related equipments Table 3.2.1-1 will be amended to indicate that modifications affecting the structural integrity and maintenance required to ensure the structural integrity of these nonsafety-related cable trays, conduits and applicable supports shall be subject to the pertinent provisions of the quality assurance program.
566.
The load sequencer is included as part of the instrumentation for the Standby Diesel Generator System which appears on Page 3.2.1-36 of Table 3.2.1-1.
See FSAR Section 7.3.1.5.1 for a discussion of the Diesel Generator Xnstrumentation.
The AC control power inverters and AC vital bus distribution equipment are included as part of the ESF 120V Uninterruptible AC System which appears on Page 3.2.1-43 of Table 3.2.1-1 ~
See FSAR Section 8'.1.1.1.4 for a discussion of the 120V Uninterruptible AC System.
a.9 DC Power Systems (Class lE)
Table 3.2.1-1 will be amended in a future amendment to address nonsafety-related cable trays, conduits and their applicable supports where structural integrity is required to assur'e the integrity of safety-related equipment.
Table 3-2.1-1 will be amended to indicate that modifications affecting the structural integrity and maintenance required to ensure the structural integrity of these nonsafety-related cable trays, conduits and applicable supports shall be subject to the pertinent provisions of the quality assurance program.
2 ~
Table 3'.1-1 will be amended to include battery racks on Page 3.2.1-43.
3 ~
Protective relays and control panels are considered as part of the instrumentation listed under each system.
a.lO-a.l6 These items are controlled by CPSL Procedures and will not be added to Table 3.2.1-1.
The implementation of procedures is subject to audit by the CPSL Quality Assurance Program.
.220 (Cont'd)
Page 3
b.l Note 15 to Table 3.2.1-1 will be amended by adding the following statement:All IE instrumentation is subject to the pertinent requirements of the Appendix B 0A program.
b.2 Page 3.2.1-43 will be amended as noted on the attached FSAR Page 3.2.1-43.
b.3 Notes 26 and 27 to FSAR Table 3.2.1-1 will be amended to reference FSAR Table 11.4.2-4.
c.l The Plant-safety-parameter display console is non-safety related and will not be added to FSAR Table 3.2.1-1.
Interfaces between the SPDS and safety systems will have isolation that meets all the required class IE requirements.
The isolation will ensure the integrity of the safety systems.
Calibration of safety-related instrument loops comprising the SPDS is included in plant operating procedures which are subject to audit by corporate QA.
co2 Table 3.F 1-1 will be amended to include the Reactor Coolant System Vents.
co3 SHNPP utilizes no portable shielding except for personnel protection during maintenance activities.
Use of portable shielding for maintenance activities is governed by plant operating procedures which are subject to audit by Corporate QA.
c.4 The Post Accident Sampling System is not safety-related, and therefore, is not included in Table 3'.1-1.
The use of such equipment is included in plant operating procedures which are subject to audit by Corporate QA.
See FSAR Section 9.3.2 for a description of this system.
c.5 Safety related position indication switches have been provided on the pressurizer safety relief valves.
Valve position has been indicated in the main control room.
FSAR Section 7.4.1.7 will be amended to reflect-this design modification.
This safety-related indication is included in FSAR Table 3.2.1-1, Page 3.2.1-7, under "Instrumentation."
c.6 The Auxiliary Feedwater System appears on Page 3.2.1-40 of the table.
See FSAR Section 10.4.9 for a description of the Auxiliary Feedwater System.
c ~ 7 The Auxiliary Feedwater System initiation and flow is a part of the Auxiliary Feedwater System instrumentation which appears on Page 3.2.1-41 of the Table.
Compliance with this item is described in FSAR Sections 7.2.2, 7.3.1, 7.3.2 and 7.5.
Compliance with IEEE-279-1971 is detailed in FSAR Section 7.3.2.2.
c.8 Provisions have been provided to manually connect two groups of pressurizer heaters to the ESF power bus.
No change is required to Table 3.2.1-1.
Compliance with this item is discussed in FSAR
220 (Cont'd)
Page 4
c.9 Section 8.3.1.2.35.
This item does not apply to SHNPP since qualified, redundant hydrogen recombiners are provided inside the containment.
See FSAR Section 6.2.5 for a description of the hydrogen recombiners in containment.
c.10 SHNPP as designed complies with containment isolation dependability requirements.
The appropriate equipment and instrumentation is included in FSAR Table 3.2.1-1
~
Compliance with this item is discussed in FSAR Sections 6.2.4, 7.3.1.1 and 7.3.1.3.2.
The specific list of containment isolation valves and the applicable actuation signals is given in FSAR Table 6.2.4-1.
The containment isolation system is a Class lE system.. Quality assurance for piping and valves is specified by the applicable ASME Code class.
c.11 Table 3.2.1-1 will be amended to include the Inadequate Core Cooling (ICC) System.
All components of-the ICC System. inside containment will be class lE seismic Category I.
The inputs from these components are processed by the class lE, seismic Category I Reactor Vessel Level Indicating System microprocessors.
An isolated non-class lE output from the qualified microprocessor will be data linked to the ERFIS Computer System for primary display on the SPDS CRT located on the main control board.
FSAR Section 7.5 will be amended to include a description of the ICC System.
c.l2 On-site sources of power are provided for the pressurizer relief valves, block valves and level indicators'ompliance with this item is discussed in FSAR Section 8.3.1.2.35.
As the on-site power supplies are included in FSAR Table 3.2.1 ~ 1, no additional information need be provided.
c.l3 Based on the results of the Westinghouse
- Report, WCAP-9804, dated February
- 1981, no modifications are necessary.
No change will be made to FSAR Table 3.2.1-1.
c.l4 The proportional Integral Derivative controller has the derivative action setting set to zero, thereby eliminating it from considera-tion.
Controller calibration is covered in Plant Calibration Procedures.
No addition to Table 3.2.1-1 is required.
c.15 Compliance with this item is discussed in FSAR Section 7.2.1.
On FSAR Table 3.2.1-1, it is included as part of the Reactor Coolant System instrumentation which appears on Page 3.2.1-7.
c.16 During normal operation, seal injection flow from the Chemical and Volume Control System is provided to cool the RCP seals and the Component Cooling Water System provides flow to the thermal barrier heat exchanger to limit the heat transfer from the reactor coolant to the RCP internals.
In the event of a loss of offsite power the RCP is deenexgized and both of these cooling supplies are terminated;
- however, the diesel generators are automatically started and either seal in)ection flow or component cooling water
.'220 (Cont'd)
Page 5
to the thermal barrier heat exchanger is automatically restored within seconds.
Either of these cooling supplies is adequate to provide seal cooling and prevent seal failure due to a loss of seal cooling during a loss of offsite power for a least two hours.
c.17, Emergency plans are subject to audit'by QA.
This information will not be included in Table 3.2.1-1.
c.18 Emergency support facilities are not considered safety-related.
This information will not be included in Table 3.2.1-1.
- However, emergency plans are subject to audit by QA.
c.19 Calibration of portable and fixed iodine monitors is covered by plant operating procedures which are subject to audit by QA.
This information will not be included in Table 3.2.1-1.
c.20 The components. required for control room habitability appear on Pages 3.2.1-31 and 32 of Table 3.2.1-1.
See FSAR Section 6.4 as augument'ed by FS'AR Section 9.4.1 for a description of this item.
A marked copy of Table 3.2.1-1 is attached to show revisions that will be made in a future FSAR amendment.
(8470COH)
TABLE-3,2, I-I CLASS IF ICATION OF STRUCTURES SYSTEMS AND COMPONENTS Desi n and Construction eratlons Remarks Structures Saf ety Class (I )
Code.
Code CI ass
. Selsmlc Cate or (2) qua I lty Assurance (3)
Oua I Ity Oua I Ity Group Assurance (23)
(24)
Auxl I lary Dam and Spl I lway Auxl I lary Separating Dike 0
See Note (30) 0 See Note (30)
Main Dam and Spl Illy NA if.-.c,'.,.
Emergency ServIce Water System NA Structures 4 Channels 0
See Note (30) a~~
RLPe
(~~)
0 See Note (30)
Auxlllary Reservoir Channel P
See Note (30)
Containment Bulldlng and Containment Liner 2
ASME I I I Dlvision 2/
ACI 359 See Note (30) and Sec, 3 8 Reactor Auxlllary Bulldlng Fuel Handling fbi ldlng and Unloading Bay NA NA See Note (30)
See Note (30)
Waste Processing Bul ldlng Tank Bul Idlng Diesel Generator Bulldlng Turbtne Bul ldlng NA NA See Note (19)
See Note (30)
P 'ee Note (30) 0 See Note (30)
See Note (30)
TABLE 3.2. I-I (Continued)
CLASSIFICATION OF STRUCTURES SYSTEMS AND CO)4'ONENTS S stems and Com ononts Desi n and Construction Safety Code Solsmlc Class l l l Coda Class
~Cote or l21 0 eratlons Qallty Quality Qual lty Group Assurance Assurance (3)
(23)
(24)
Remarks c)
Normal ly or automal Ical ly Isolated from parts of system covorod by a or b d)
Oporators for Safety-Ae lated Active Valvos NNS ANSI B3 I ~ I IE 0
R IE Soo Note (3I )
Instrumentatlon
( In part)
IE IE See Note (15)
Contalnmont 5 ra S stem Refueling Water Storaqo Tank Spray Additive Tank 2
ASME III 3
ASME III Containment Spray Pumps 2
ASME II I Containment Spray Pump Motors IE IE Eductors Contalnmont Spray Hozz los Containment Sump Screens 2
ASME I I I 2
ASME I II NA Q
C Zmm < km (SP)
ASIDE I I I 3
ASME I I I NNS ANSI B3 I ~ I System Pl p I ng and Va I vos a)
Aequlrod for lnltlal InJoctlon 2
or long term roclrculatlon of sump wa tor b)
Acquired for spray addltlvo c)
Norma I Iy or au tomat Ica I Iy Isolated from parts of system coverod by a K b C
0
1AIILE ).2)l-I Iculltltluddf CLASSIFICATION Ol'TRUt)t8\\hk t P5 kq h)fl'i<4'I~NTS S stems and Components Safety Class (I)
Oosl n and Construction Code Se Isml c Coda Ctass
~Cate or IRI 0 erntlons Quality gunllty (Iunllty Group Assurance Assurance (3)
(23)
(24)
Roar r so IIIgh Range Contalnmont Radlatlon Honltorlng IE IE Q
See Note (15)
Electrical S stems and ononts ESF 6,9 kv Ous ESF 6.9 kv Swltchqoar IE IE IE IE fSF 480V Swltchgear and Transformers IE IE ESF 480V Rotor Control IE
- Centers, Including I20V Transformers and Powor Panels IE 480-208/l20V Transformers (omorgoncy llghtlng)
IE IE fSF l20V Unltorruptlble AC System IE IE ESF Station Batterlesgand Chargers IE (3odLcrq~
Safety related motors IE IE IE Safety related powe>r control>
IE and Instrument cables and raceways at'3 a-"-oct4<rcL Ca6le sPIlcc5, Coda.r cctetd c, a 4 tCrN:A I2Ictks aS a.ppbca)2IC Con ta I nmon t o I ec tr I ca I 2
Pone lra t I ons l20 volt O.C ~ Systotn IE IE HOn- ~<Cfq Ae4(J r~CC WSrS o L suppogs co~~a,ssvg 5a(R4y ca(,IRs u42)c 4 ilier< ~aj ddR~Rte cd:r s~g rcl84 tfe Ca f lc Tr~~s Co 8"'el 5
""PP"~~'
gNS
))r)S S~~
AoZc bo) r)(CP g.r g/ Xc (<o)
TABLE 3.2.l-l (Continued)
CLASSIFICATION OF STRUCTURES SYSTEMS ANO CO)4 ONENTS S stems and Components Primary and backup protectlvo devices associated with class IE contalnmont electrlca I penotrallons and 6.9 kv nonmlass IE system Desi n and Construction Safety Code Selsmlc Class lll Code Class
~Cate ar (2t IE 0 oratlons Qua I Ity qua I Ity gua I Ity Group Assurance Assurance (3)
(23)
(24)
IE Remarks Reactor Protect(on S
stem (In part)
IE IE Outmf-Coro Neutron Honltorln
~as tee ESF Protection S stem (T, P, or S s I gna Is)
IE IE IE IE cfor CCRo4tRt 6'I'-4c'cd+
Ps'(Rag (re ~ Pcdkc4r Ue:c~ f c,( I-o ck4 l l 4: g g'Iow reS~r>c.ter.
P:P..-
l l
s p
I-2.
Idkclkmhsd g sccod'sk ima2ckra~ es'.stc f)sAE II<
gsMc lll Q(( o4'4r t,p y 3.ru c-%die pc
~
S Cc.'o)e (<~)
Y nckicq i(e Core (ocRli ]
Sqcggak (i dk part)
R t C o C )t2L4 e Cf fIft Hg nncf Vn/@PE llsnf III Ct C
Neg(i @
'0
Notes to Table 3.2.1-1 (Continued)
(8)
Classified on basis that flow restriction is provided in the piping.
(9)
The reactor coolant system supports are not stamped.
They are also not
~ part of the reactor coolant pressure
- boundary, and therefore, are not
,. included in any Quality Group.
(10) Failure could cause releases of radioactivity.
Portions of containment boundary.
(12) Protects fuel from damage during transportation.
(13)
(14)
Supports for the gas decay tanks are designed to withstand the Operating Basis Earthquake loads.
There is no specific code which classifies the diesel generator as Safety Class 3.
IEEE-323 is the governing design code.
(15)
(16)
Instrumentation Instrumentation required to actuate, maintain operation of, or detect failure of equipment needed to safe shutdown, isolate, and maintain the reactor in a safe condition, and prevent uncontrolled release of radioactivity from the plant is Class IE/Seismic Category I.
Instrumentation designated as Class IE/Seismic Category I includes as Seismic Category I all sensing.lines, instrument valves and instrument racks.
Instrument racks containing Class IE equipment are also considered Class IE.
Systems noted as Class IE may also contain non-Class IE equipment.
Refer to Chapter 7 for specific identification of Class IE equipment
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This piping is designed to the Class 3 requirements of ASME B5PV Code,'ection III and fabricated in accordance with ANSI Power Piping Code B31.1.
Piping which serves hose stations and standpipes required to protect safe shutdown equipment is designed to ANSI B31.1'equirements and is seismically qualified.
(18) Those portions of this system whose failure may have an adverse effect on a nearby safety related component are seismically supported.
(19) The reinforced concrete mat and walls of the Unit 1 Turbine Building between column line 42 (approx.)
and 43 (approz.)
are designed and constructed to Seismic Category I requirements due to the presence of the diesel generator service water pipe tunnel and Class 1 electrical cable area above the pipe tunnel (see Figure 1.2.2-60).
This area is designed and constructed to withstand the collapse of the Turbine Building concurrent with a SSE.
3.2.1-46 Amendm(nt No.
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SHNPP FSAR Notes to Table 3.2.1-1 (20) Provides mechanical support for Safety Class 1 component.
(21) Will be designed and fabricated to the applicable portions of ASME III, although it is not classified as ANS Safety Class 1,
2, or 3.
(22) Provides support to the Safety Class 1 pressure boundary conduit'23)
Quality Group classification,in accordance with Regulatory Guide 1.26, Rev.
3, as defined in Section 3'.2; Class IE is defined in IEEE 308.
(24) Quality Assurance Requirements (Operations Phase)
Q QA requirements'ill meet 10CFR50 Appendix B criteria.
R QA requirements will meet ETSB ll-l QA requirements as a minimum.
Optionally "Q'equirements may be imposed..
F -
QA requirements will meet Pire Protection QA requirements as a
minimum.
Optionally "Q" requirements may be imposed.
QA requirements of 10CFR50 Appendix B are not mandatory.
(25) The code and code class for individual components in the Liquid Waste Processing System can be found on Table 11'.1-7.
(26)
The code and code class for individual components in the Solid Waste Processing System can be found on Table llew 4.2-X.
(27)
The ETSB ll-l QA applies to components listed in Table 11.4.2-g except those listed as manufacturer's standard.
(28)
ASME III Code applies to oil cooler and trip/throttle valve only.
(29) Not Stamped.
(30) Structure is designed to withstand design wind/tornado loadings and missile impacts.
(31) Valve operators for active valves, as listed in Tables 3.9.3-13 and 3'.3-14, are motor, solenoid, or electrohydraulic and qualified to meet IEEE 344 and 323 standards.
(32) Containment water level and containment pressure indication are redundant and class IE up to the isolation device at the SPDS cabinet.
(33) Radiation Monitor is not redundant.
(34) The fuel oil storage tanks are reinforced concrete tanks with steel liners'lthough these tanks are not classified as Safety Class 3, they are designed and constructed commensurate with their intended safety function.
'I (35)
See Figure 9.5.5-1 for ASME III/non-ASME III boundary.
3.2.1-47 Amendment No.
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SHNPP CESAR (36) This table is an overview of all the structures, components, and systems.
Refer to the Master Equipment List, process and instrument
- diagrams, and control wiring diagrams for further detail.
(37) The reactor internals were fabricated prior to implementation of subsection NG of the ASME Code.
- However, the reactor internals were designed and fabricated consistent with ASME Code requirements
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3.2.1-48 Amendment No.
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