ML20005F905
| ML20005F905 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 11/19/1989 |
| From: | Buck R DETROIT EDISON CO. |
| To: | |
| References | |
| NUDOCS 9001170375 | |
| Download: ML20005F905 (68) | |
Text
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Effectiveness Review (Attached) KYes fMtNtr p e E i Other Drawings. Design Calculations, Correspondence. etc. 16 . $, P*** ** * ** ** * ** ** * * * * * * * * * *
- P A RT 2: OPERATING LICENSE CHANGES
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9A.4 1.9.1 Description j This zone, shown in Figure 9A-9, consists of two floor areas at Elevation 659 ft 6 in. These floor areas are separated by the i drywell, the dryer / separator storage pool and the fuel. storage ! pool. The western portion of the zone is bounded on the north, south, ! and west by outside walls and on the east by the drywell, dryer / separator storage pool, and the fuel storage pool. The eastern portion of the zone is bounded on the north and south by outside walls; on the east by the auxiliary buildingt and on.the west by 1 the drywell, dryer / separator storage pool, and the fuel storage pool. The western portion of the sone houses motor-generator (M-G) sets-and oil cooler, dress-out facilities, and RWCU equipment. The eastern portion of the zone houses the standby liquid control system (SLCS). . The walls separating this zone f rom the auxiliary building are constructed of reinforced concrete having a fire-resistance rating of 3 hr. Penetrations through rated walls are sealed to provide a 3-hr fire-resistance rating. The-floor is constructed ! of reinforced concrete and contains open stairwells, unprotected hatches, and unsealed penetrations. Floor drains are provided and trapped at the collection sumps. The ceiling is also con-structed of reinforced concrete and ~contains unprotected hatches " and unsealed penetrations. Cable tray penetrations through the floor and ceiling are orovided with fire stons. Ventilation f adsv a edsd % 9eoftake c.Te% $+evass 9 tem p11ec cirectly to tne area nGuna Tns c.-J sets and th tor e areas north and east of the fuel storage pool. Air en ows from these areas to the clean area, the ' RWCU pump om and the RWCU south and north domineraliser rooms. r a so flows from the clean area to the personnel MSt chm;;e area,Attil:t ::: . 2M ctrie:D Supply air to tho' RWCU olding pump room ans domineralizers is controlled by backdraft dampers. With the exception of air exhausted from the area around the M-G sets, exhaust air is ducted to the reactor / auxiliary building ventilation system exhaust. The M-G set area is locally cooled by air ducted directly to the M-G sets from three recirculating fan-coil units. Fire detection equipment located in this zone consists of an' ion-ization detection system and heat detectors. Fire suppression equipment consists of an automatic sprinkler system in the area ( of the M-G sets and oil coolers, manual hose, and portable fire extinguishers as shown in Figure 9A-9. 9A.4-19
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4(,Y 6/u i / ? -22 P9 Revislen d Page l of $ 9o...... un.....* PART 1: UFSAR, PLAN OR PROGRAM REVISION [ MA * "- " "" :: **"*] 1 A) Document ' 11 P SAK 7 B) Section(s). Tablets), C% A t- F6gure(s), t3 = . etc.- eAffectedgch a -ju ~ - prked-up,page,sg SAr4_n w 1.v./.z. C) Reason for Change 8 . o //a _, aeie lu1. *t.2 :n ,m J & n Inbc
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- PART 2 : OPERATIN G LICENSE CHANGES DdNA -_-_ _-_ _-- "----------I
, A) Document
! ) Operating Licensa [ ] Tech Specs [ ] Environmental Protection Plan
( ) Tech Spec Clarification B) Section(s), Table (s), Figure (s), etc. Affected (Attach marked-up pages)
) Reference end Source Documents Attached
[ ] Significant Hazards Consideration [ ] Environmental Evaluation , ( ) Enviromental Impact / Categorical Exclusion ( )Other D) is UFSAR change required? ~ I l Yes [ I No LCR No - E) Priority 1lD 1 ATUtip NRC approval required by (date): aca / lim ; An [ ) Emergency ( ) Exigent condition will occur if not approved by. (State date): DIST. M N REV. Explanation F) Implementation - DER No. , p... . u..."" * * "" * ""* "
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- 11) NSRO Approval (Operating License Amendments) X NA Date l Form FP-RA2-01 Art 1 P1/1030189 DTC:,N TCLCR for UFSAR File: 1735
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- Reporting to the plant Manager - Buclear Production are the sugerintendent - Operations, the Superintendent - maintenance "
One modifications, the Director - Buclear Security, the ) Superintendent - Radiation Protection, the Superintendent - the Supervisor - Plannang and Scheduling, Technical Engineering,he Plant Manager. The Radiation Protection
'2 and the Assistant to t Manager reports directly to the Plant Manager regarding radiological control (see Subsection 13.1.2.3.2.5).
1 In a6dition to Permi 2 respasibilities, the Plant Manager-will provide support for the decommissioned Feral 1 facility, incisding the reactor, the fuel and repair building, and the This facility should 2 oodium storage and treatment building. take no more than 1 p reent of the Plant Manager's tame. The Superintendent - Radiation Protection will perform the surveil-lance requirements of the Porni 1 Technical Specifications. On the average, these will not require more than 100 work-hours of Offort each year. The plant staff is organised into sections under the13.1-3 Figures direction and of the Plant Manager - Buclear Production. each 13.1-4 are the Nuclear Production organisation charts 2 classification in the figures represents a job p sition for one or more individuals. The functions, resp nsibilities, and authorities of plant personnel are described below. superintendent - Doerations O . The 13.1.2.3.2.1 Operations Section is responsible for the operation of plant lh) equipment and systems including radwaste and plant chemistry. The Superintendent - Operations is responsible for the activities of this section. The Superintendent - Operations exercises overall managerial and supervisory responsibility for the startup testing and safe, reliable, and efficient operation of the plant and all associated 2l equipment. It is the Superintendent's responsibility to have a staff of trained and properly licensed personnel to accomplish the various plant responsibilities and to ensure that qualified personnel are available to fill the plant complement positions.
' Prior to operation, the Superintendent - Operations was The respon-2 sible for the Fermi 2 startup and testing activities.
Operations Section is shown in Figure 13.1-4. All operations, testing, or maintenance work must be approved either by the Superintendent or by an assigned delegate, as established in procedures in the Plant Operations Manual. 2l In the absence of the Superintendent, the succession to the Superintendent's responsibilities is specified by procedures in 2 the Plant Operations Manual. . Reporting to the Superintendent are the operations Engineer, the s O_ Operations Support Engineer, the General Supervisor - Radwaste, 13.1-8 REV 2 3/89 a
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the Startup Sagineer - jBest phase, .and the General Supervisor. - - {7 Chemistry. l lJ The Operations Engineer $s responsible for the overall operations of the plant equipment and systems. As designated La procedures in the Plant Operations Manual, the Operations Engineer or a ' delegate approves written work requests for equipment operation, asiatenance, or tests. During the Operations Engineer's absence, the Operations Support Engineer assume the duties and respon-sibillties of that position, e rations Engineer shall have a senior reactor operator's (SRO) 1 conse. Reporting to the Operations Engineer is the clear Shift Supervisor and shift. organisation. 6p , Ace-ured 540) 1 The Nuclear Shift Supervisor (s) is responsible for and exercises. supervisory control over the operating personnel on shift. During the absence of the Superintendent - Operations, the Opera-tions Engineer, and the Operations Support Engineer, the Nuclear r Shitt Supervisor is responsible for the overall optration of[K) theS'tto) , plant. %(
'- Each Nuclear Shift Supervisor shall have an SRO license. Report-inq'to the Nuclear Shilt Supervisor is the Nuclear Assistant Shatt Supervisor.
The Nuclear Assistant Shift Supervisor assists the Nuclear Shift Supervisor in duties as directed. EachReporting Nuclear Assistant Shift to the Nuclear h Supervisor shall have an SRO li' cense. Assistant Shift Supervisor are the Nuclear Supervising Operators. The Nuclear Supervising Operators manipulate the reactor controls and other controls and direct the activities of the Nuclear Power
- Plant Operators and Nuclear Assistant Power Plant Operators.
Normally, two Nuclear Supervising Operators are assigned to each
- operating shift. Each Nuclear Supervising Operator shall have a reactor operator's (RO) license. ,
The Nuclear Power Plant Operators are responsible, under the direction of the Nuclear Shift Supervisor, the-Nuclear Assistant Shift Supervisor, or the Nuclear Supervising Operators, for oper-ating auxiliary systems and for assasting in the refueling of the plant as directed. Among their regular duties are the operation of such plant equipment as pumps, turbine generator auxiliaries, blowers, radweste systems, ocapressors, and auxiliary service 1 equipment. Additional duties include radiation monitoring, recordkeeping, and general housekeeping. The Nuclear Assistant Power Plant Operators assist the Nuclear Power Plant Operators in duties outside the main control room. The Operations Support Engineer is responsible for providing sup-port to the rating organisation, including procedure prepara-tion and revi ion, in-plant training, corrective action support, 13.1-9 REV 2 3/89 l
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g shall have an SR0 Cerf11oense Wses WW ; The General Supervisor - Sadweste,is responsible for the supervi- 1 cion, both teonnical and operational, of plant activities
=he Radweste Supervisorinvolv-ing radioactive waste processing.
2 Operations reports to the General Supervisor - Radweste. The Startup Engineer - Test Phase was functionally responsible for the checkout and initial operation and preoperational testing and the ascension-to-power testing programs. The General Supervisor - Chemistry is responsible for directing the sampling of plant fluid systems, for the chemical laboratory, for prescribing the procedures to be followed for sample preparation and analysis and result reports, and for environ-cental regulatory compliance. The General Supervisor - Chemistry 2 cvaluates results, reports, and laboratory techniques. The Chemical Engineer, the Chemist, and an engineer report to the General Supervisor - Chemistry. [ The chemical Engineer is responsible for the operation, mainte-nance, and calibration of the plant chemical processing and 2 l water treatment equipment. The Chemist is responsible for maintaining the radiological and chemical parameters of the plant within the requirements of the a Technical Specifications and the Radiological Effluent Technical W Specifications. 21 13.1.2.3.2.2 sunerintendent - Maintenance and M ifications
~
2 The Superintendent - Maintenance and Modifications is respon-sible for the maintenance of the plant and all associated equipment and the modification to plant structures, systems, and equipment. Reporting to the Superintendent - Maintenance ervisor - Modifications, and Modifications the General are the Supervisor General Sup/ Instrument and Control,
- Maintenance 2 the Supervisor - Maintenance Support, the General Foreman -
Maintenance, the General Foreman - Shops, and the Preventive Maintenance Coordinator. The Superintendent - Maintenance and Modification is responsible for the maintenance of plant structures, systems, and equipment. In this capacity, compliance with the Technical Specifications related to maintenance, writ *.en procedures, and work practices is ensured; and duties include the lubrication program, the preven-tive maintenance program, instrument spare parts, routine cali-bration, instrument and control troubleshooting, and the standards calibration program. d_ The General Superviser - Modifications providesThe contractors) in support of modifications to the plant. engineeringexpeg 13.1-10 REV 2 3/89
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D) Reference and Source Documents (identify) EDP Tech Spec O h ti ITM A M M in ; PDC Procedure 5_ i F I r.11 G E I lb ABN SE (Attached) U J !l iI- l1LALJLE i DER PE (Attached)
~ - -
Test d) [ Effectiveness Other fsous /VsM'r/F Review (Attachj/xy8}Yes [ JNop.g A R / M O N / b W J$c?@4l Q #-kbk70 0 N' h DraMngs. Design Calculations. Correspondence, etc. V e,_______ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - * **
- P A R T 2 : OPE RATING LICENSE CH ANGES gitJNA -_ _ -_ -_ --
---_ --------_ l A) Document / pdF# % y d 7
[ ] Operating License [ } Tech Specs [ ] Environmental Protection Plan 1 Tech Spec Clarification B) Hection(s). Table (s), Figure (s), etc. Affected (Attach marked-up pages) C) Reference and Source Documents Attached [ ] Significant Harards Ccnsideration [ ) Environmental Evaluation [ } Enviromental Impact /Can~'gerical Exclusion [ }Other
. 3) is UFSAR change requiredi f)Yes [ ] No LCR No. ssp 4fd ART Alcide/# d et r ATUS E) l'rlority *~
NRC approval required by (date): ACR JA An [ ) Emergency [ ) Exigent condition will occur if not approved by: spaq (State date): OlST. g ,- Explanation
- F) Implementation 1 DER No.
j= =___n =n .:nu = = PART 3: A PPR O VA L iiF ""---i" " - - - - "" - " - " - - - - - ~ = "
-l
_ A) Orleinator K(cW##' 7iiL Date #-MW B) Technical Expert s.4/ #44.4 _w n a Date f'>[FO/AQ C) Nuclear Generation Unit Head 45. >3Md4D Date M2T 9 D) General Director Nuclear Engineering ( )NA d'.NCd44Mr7#M Date /d5P' E) Plant Manager J M 6//bg4/ M Date Ir) Other _ Date
@) Director, Nuclear I.lconsing /,J. 6eoOg4F ~
_ e__- - Date AM//N H) OSRD Approval (Tech Spec Amendments) [I] NA Date
- 1) NSRO Approval (Operating License Amendmeats) /) NA Date i Corm FIP-RA2-01 Att 1 P1/1030189 DTC: 15 TCLCR for UFSAR File: 1735 DTC: [ ) TDLCR for other
EFFECTIVENESS REVIEW l' , meterence I.CR 1819 l - I /ld 141 - lu is 15 I
^
Revisiond Paged of MM _ _ _ _ _ _= _ _2 n _ a _ _ _ m =_ m u n PART 1: UFSAR [ INA = "- = " = " = =- = l l l A) Quality Assurance Program [ )Yes [/Q No Does the change (s) cease to satisfy the criteria of 10CFR50, Appendix B l and the UFSAR program commitments previously accepted by the NRC? I Provide the bests for each chanDe on Attachment 2. Page 2. ! B) Fire Protection Program l [ }Yes [f] No Does the change (s) significantly decrease the level of fire protection in the plant? [ lyes [l] No Does the chenpe(s) result in failure to complete Fire Protection Program approved by the NRC prior to license issue? Provide the basis for each change on Attechment 2, Page 2. 1 [***"PART 2: RADIOLOGICAL EMERGENCY IGTPONSE PREPAREDNES PLAN [JQN A = --- = """ l l A) [ ]Yes [ ] No Does the change (s) decrease the effectiveness of the RERP Plan? [ ] Yes [ ] No Does the RERP Plan, as changed, cease to meet the standards of 10CFR50.47(b) and 10CFR60 Appendix E? Provide the basis for each change on Attachment 2, Pags 2. i-- -
"" """"""= P ART 3: SECURITY PLANS [X]NA " "- """=== = = =l A) Document A) [ ] Yes [ ] No Does the change (s) decrease the effectiveness of the Physical Security l
- Plan or Security Personnel Training and Qualification Plan prepared pursuant to 10CFR50.34(c) or 10CFR737
[ ] Yes [ ] No Does the change (s) decrease the effectiveness of the first four categories of Informational Background, Oeneric Planning Base, Licensee Planning Base, and/or responsiblity matrix of the Safeguards Contingency Plan y O prepared pursuant to 10CFP.60.34(d) or 10CFR737 Provide the basis for each chan je on Attachment 2, Pas e 2.
/
F " " " " * ** * *** ** * *** *"* PA R T o : PROCESS CONTROL PROGRAM [r]N#*"*"*"*"""*"""* l A) [ ] Yes [ ]No Does the change (s) reduce the overall con"ormance of the solidified , waste product to existing criteria for solid wastes in accordance with Technical Specification 6.13? Provide the basis for each change on Attachment 2, Paje 2. i- " " " = "" " " " " " "* ********" P A RT 5 : ODCM [K NA""""1"- -- " = - " " ------ --- l A) [ ] Yes [ ] No Does the change (s) reduce the accuracy or reliability of the dose calculations or setpoint determinations in in accordance with Technical Specification 6.147 Provide the basis for each chan n on Attachment 2, Page 2. F = """""""""""* PAP.T0: AP PR O V ALgP """" *"* ")*"" *" *"""""""""*" l A) oriesnator M&WWMr4L- N l/ JARd,r? Date f u!W a9y B) T.chnicai Exoert vV.##4C O2 jf bdf \ Date 94okc> l ' C) Quality Assurance (For Security Plans ohly)y Date ID) OSRO (Not required for UFSAR Changes) Date l crm FIP-RA2-01 Att 21/2 030189 DTC: [ ] TCLCR for UFSAR File: 1735 DTC: [ ] TDLCR for other
1 EFFECTIVENESS REVIEW DOCUMENTATION Reference Len 18 Ifl- l /18 I 41 - IUl#lSi Document g Listed below is each change by section and page; the reason for the change; and the basis for concluding that the revised plan or program continues to satisfy the criteria for that plan or program. Section/Pege Change Basis
/EN //2 ~/E.- Of/47f 24db#LML 4/ gpf-ddW/dU AWh fd4 AWN kdFAFA J/8/d/7/d3Af44 JAntt/~
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//S De4 //: ?. f l $ 4 4 W M 4 M 414 76 s t d 4 N e % b e"Y GNA' Mad 44W,;""tAtu M/M$h/bd'$ & .
O Form FIP-RA2-01 Att 2 P2/2 030189 DTC: [ ] TCLCR for UFSAR File: 1735 DTC: [ } TDLCR for other
A CE #/- /8#-cW penuis ursan (7. 2.3 h es iy codro/ Qgy bases in accordance with NRC licensing requirements. Design activities may include calculations, analysis, materials selec-tion, equipment arrangement and layout, and specification of test and inspection criteria essential to the safety-related functions of structures, systems, and components. Those design activities performed by individuals within Edison organisations are con-trolled by departmental design control procedures. Design control procedures satisfy the applicable QA requirements for design activities as specified in ANSI N45.2.ll-1974 and as modified by Regulatory Guide 1.64 as addressed in Subsec-tion A.l.64. Any organisation performing design work for Edison must have similar requirements in its procedures before its QA programepnje e pted _
~
Nuclear DA w 11 review and concur with the design control proce-dures adopted by organisations performing design work for the 1 nt. To ensure that the design is adequate and tha the above require-ments and procedures are satisfied, designs are internally veri-fled by the originating organisation. This internal verification of adequacy may be accomplished either by a design review, by alternative calculation methods, or by the establishment of a suitable test program. Where a test program is used to verify the adequacy of a specific design feature in lieu of other veri-fication or checking processes, it will include suitable qualifi-O cation testing of a prototype unit under the most adverse design conditions. Those proposed changes in the facility which involve changes to the Technical Specifications or an unreviewed safety question as defined in 10 CFR 50.59(a)(2) shall also be reviewed by NSRG. Minutes of each NSRG meeting are prepared'and approved. All documentary material reviewed is identified. Copies of minutes are distributed to the originating organisation. During the design reviews, particular attention will be given to ensure that
- a. Appropriate quality standards are contained in the docu-ments and clearly delineated
- b. The technical information for the materials, components, equipment, and processes is contained in the documents and is suitable for the intended applications. This information will include, as applicable, the physics, seismic, radiation, hydraulics, thermal, strength, and accident analyses used; the compatibility of design for inservice inspection, maintenance, and repair; and the acceptance criteria for inspections and tests. Perform-ance history and failure data on installed components will be considered when similar components are intended O for installation as part of a system or structure modification i 17.2-12 REV 2 3/89l l . . ..
, . :. . - a . .r . _ . _.. . . _ . - - ..
AR" / e st. # F.S g* ofc.....TCM4',NroRMATioN.. osn sYsttus L gy ic1NEING,CHAN1E REQUEST
.no t. nv....p......ns- , ,, , , ,,,3,, , , , , , ,
Ncy of 1989 h34c amo a .pc Revision M Page 1 of kY Tc
...... . . . . . . . . .. . P ART i : UrSAR. PLAN. oR eROGRAM REVISION [ ]N A """" " * ; * " * * " " * **l
" A) Document UTSAR B) Sect 6en(s). Table (s), Figure (s), etc. Affected (Attach marked-up pages)
Section 17.2.2.4 PG 17.2.10 C) Reason for Change Channen to the O-tint and menroval of the channen have evolved overtime to the colnt that current cractican are more affective then the criminal commitment. Additionally. OA level desienation has been incoroorated into CECO, - D) Reference and Source Documents (Identity) EDP Tech Spec A f%Ng pgA t - y3 (V , PDC Procedure i " it W A 14 C : s 4 L NN ABN SE (Attached) W it % 9 '^ ~ DER PE (Attached) Yes Test Effectiveness Review (Attached)IX]Yes ( ]No Other TSAR Appendix E Item 111.26 Rev 3B & 50: UFSAR Rev 2. Seet 17 . 2 . 2 . t. Drawings, Design Calculations. Correspondence, etc. p w. ...*u . ... o . . .. . .. . . ...
- P A RT 2: OPERATING LICENSE CHANGES IX]N A *""*"""*"";"" l A) Document
( ) Operating License ! ) Tech Spe:s ( ) Environmental Protection Plan ( ) Tech Spec Clarification B) Section(s), Table (s), Figure (s), etc. Affected (Attach marked-up pages) C) Reference and Source Documents Attached [ ] Environmental Evaluation O (( )) Enviromental Significant Hazards D)is UFSAR change required? Consideration Impact / Categorical Exclusion [ ] Other (XIYes [ ] No LCR No Same as above _ E) Priority -
- e. ., . , ,
NRC approval required by (date): * * ' 'J An [ ) Emergency ( ) Exigent condition will occur 6f not approved by: *e'* r/ m L (State date): i ____m . m
. ,, . . u n .,w; 6 yi Explanation 8 emr i
F) implementation e at " ' m'l DER No. . k~ I p n . . . .u . . . . . . . . . . . . . . * * * * *
- P A R T 3 : AP P R O V A LS* * * * *f """ **"*""*""""""""""""*""" l A) Originator F. T. Schwarte i AM Date 10/9/89
- 9) Technical Expert J. J. Wald Oc:L m Date to. i2-Ao C) Nuclear Generation Unit Head . B. Stafford . Date 10-((s,-BG D) General Director, Nuclear Engineering ( )NA G. V. Cransto ##s # ate /0 /7 E) Plant Manager D. R. Gipson Ase " Date /0 - 17 0 Date F) Other
- 0) Dieettor, Nuclear Licensing L. S. Goodman Date //.3tPIr#7 I
H) OSRO Approval (Tech Spec Amendments) IK 1 NA Date ll) NSRO Approval (Operating License Amendments) ' )NA Date l Form FIP-RA2-01 Att 1 P1/1030189 DTC: 15 TCLCR for UFSAR File: 1735 DTC: ( ) TDLCR for other
- ' EFFECffVENESS REVIEW , Reference LCR l8 10 l- l 1 18 l31- l U lF lS l Revisiono pone 2 of V/ .
rmmm..m.*** ****** PART 1: UF5AR [ IN A ** ;"" = """"" * **
- l A) Ouality Assurance Program Does the change (s) tease to satisfy the criteria of 10CFR50, Appendix 8 I )Yes !x) No and the UFSAR program commitments previously accepted by the NRC7 )
Provide the basis for each chance on Attachment 2, Pese 2
- 8) Fire Protection Program i
( )Yes [X) No Does the change (s) s6gnif6cantly decrease the level of fire protection in the plent? [ IYes IX) No Does the change (s) result in failure to complete Fire Protection Program approved by the NRC prior to license issue? Provide the basis for each chenDe on Attachment 2, Pese 2. P** PART 2: RADIOLOGICAL EMERGENCY RESPON5E PREPAREDNE5 PLAN [v]NA " " " " "" **l A)I ] Yes IX] No Does the change (s) decrease the effectiveness of the RERP Plan? , ( ) Yes [ x) No Does the RERP Plan, as changed, cease to meet the standards of
- 10CFR50.47(b) and 10CFR50 Appendix E?
Provide the bests for each change on Attachment 2, Pano 2. p......m.m mm..m ...
- P ARY 3: SECURITY PLAN S [ r]N A **"""""**""*"";":*l A) Document A)I ] Yes [ ] No Does the change (s) decrease the effectiveness of the Physical Security Plan or Security Personnel Training and Quellfication Plan propered pursuant to 10CFR50.34(c) or 10CFR737 I ) Yes [ ] No Does the change (s) decrease the effectiveness of the first four categories of informational Sockground, Generic Planning Rose, Licensee Planning l Base, and/or responsiblity metrix of the Safeguards Contingency Plan prepared pursuant to 10CFR50.34(d) or 10CFR737 l Provide the bests for each change on Attachment 2, Pes e 2 -
p m . . .m..... . .. . . . . . . . . .
- P ART 4 : PROCESS CONTROL PROGRAM Ix1NA********* l A) [ J Yes [ ] No Does the change (s) reduce the overall conformance of the solidified weste product to existing criteria for solid wastes in accordance with Technical Specification 6.13?
Provide the bests for each change on Attachment 2 Pa;e 2. . p ,m . . .. m m . . . . . . . . . . . . . . . . .. . . . . .
- P A RT 5 : ODCM Ix hl A " " * * * * ** * * * ** * *
- l A)I ] Yes [ ]No Does the change (s) reduce the accuracy or reliability of the dose calculations or setpoint determinations in in accordance with Technical Specification 6.147 Provide the basis for each change on Attachment 2, Page 2.
p.m.mm... ...........* PART 6: APP R O V AL S" * *$* ***** * * * * * * * ** * ;"""* l A) Originator F. T. Schwartz / / /A Date 10/10/89
- 8) Technical Expert J. J. Wald / v
_. e 8 s Date to.s2-M C) Ouality Assurance (For Security Plan o y) Date
- 10) OSRO (Not required for UFSAR Changes) Date l P
crm FIP-RA2-01 Att 21/2 030189 DTC: I ] TCLCR for UFSAR File: 1735 DTC: [ ] TDLCR for other t
- , . _ . . , ,.,m-,,,-m,., . . , ,,,,,y_
RFFECTIVENESS REVIEW DOCUMENTADON . Reference LCR l 819 l- 11 l 8131- IU lF lSl Revision 'O Pese 3 of* i V
- DIcument Listed below is each change by section and pege; the reason for the change: end the basis for c ncluding that the revised plan or program continues to satisfy the criteria for that plan or program.
Section/Pese Change Basis 17.2.2.4/17.2-10 IST & Revise 2nd Paragraph 1 - The 0-List has been to read Der the attached. incorporated into CECO and no lonarr'esists as a - separate entity.
- 2. At the time that approval and control of the Q-List- was raised ie FSAR Appendia E, Item 411.26, Reve38 (6/80), no controls were in ple :e. The controls established called for Direci or N.E. approval & concurrence by t ie Director NQA. The controls were implemented by NE 2.5.8. A hardcopy of the Q- ;ist was issued approximately yearly. It docunented the incorporation of all of the change paper for the prior year, hence approval and concurrence by the Directo rs of N.E. and N.Q.A. respectively was an after-the-fact formality. Distribution of the Q-List was made in accordance with approved procedures..
- 3. In March, 1988, :he Q-List was incorporated into CE :0 along with the hit List,
)
MVL List etc. CCCO is an on-line, interactive cont rolled database whose usage is through direct access versus a hard copy printout. Current c.ontrols of CECO per FIP-CMI-02 call for a hardcopy printout yearly with review and concurrence by Director's N.E. -md N.Q. A. respectively. Again, it is an after the fact review.
- 4. Effectiveness of the QA Program will not be dimishe d by this change as NQA reviews procurement documents routinely for QA Level designation and conducts audits and surveillances of EDPs and the configuration management process. Similarily, N.E.
Supervisors revi sw and approve change paper on an " in line" basis review. Design control activities perfo rmed by or for Nuclear Engineering comply with the requirements of UFSAR 17.2.3 - D esign Control, Review of procurement documents by NQA comply with the requirements of JFSAR 17.2.4. (Continued on back) Farm FIP-RA2-01 Att 2 P2/2 030189 DTC: [ ] TCLCR for UFSAR File: 1735 DTC: [ ] TDLCR for other l
ul RG- l 1
$.sv'$esups A opg i
l Procurement Document Control. Audits are conducted by NQA in accordance with the requirements of UFSAR 17.2.18. i As o result of this change, M D-Q!! and FIP-CM1-02 will require revision to delete the requirement for a hard copy of the Q Level designation from CECO cnd its attendent' requirements for the Director's of N.E. and N.Q.A. , f ( ) f 4 1 ? 4 i s o i , r i i
.,_,,..e. -- . . _ , . , s , ., . , , , _ , . , - . . ._ i.__._-_____..__-
, ; LICENSING CHANGE RECUEST ,
1 LCR 18 19 l- l1 17 l9 l- lU IF lS l { Revision 0 Page 1 of 3 l l '
. _ f*************"* ** **
- P A R T 1 : UFSAR, PLAN, OR PROGRAM REVISION [ IN A ";" = """ " = = = = l ;
[ A) Document l UFSAR d?) l 8) Section(s). Table (s), Figure (s), etc. Affected (Attach marked-up pages) gy Figures 12.1-6 and gA-8. 5 A.mL (A 040*J u ? 'r C) Reason for Change
- g j The Fermi 2 Radiation Zones - 3rd Floor Plan (Figure 12-1-6) is being revised to indicate tl's& i placement of shield wall and change in radiation zone category. \-
The 3rd Floor fire protection evaluation Figure 9A-8 is being revised to show the new shielding wall. ,I g e D) Reference and Source Documents (identify) ~ EDP-10446 Tech Spec N/A g (W c4 5 PDC-10446 Procedure N/A 1 ! ABN N/A SF (Attached) 89-0139 L j ;. Q DER N/A PE (Attached) _ 1.Y k cm Test Effectiveness Review (Attached)[ ]Yes [ ]No g q",j]gd e a jk {p% j< Other Design Calculation (DC) 5078 11 R _ d$ ] 2% b'1b bab ~ Drawings. Design Calculations. Correspondence, etc. p.. . . . ... . . . . . . . . . . * *
- P A R T 2 : OPERATING LICENSE CHANGES [X] N A - - - - - - - - - - - - - - - ***te l A) Document gg {
l ) Operating License [ ] Tech Specs [ ] Environmental Protection Plan [ ] Tech Spec Clarification B) Section(s). Table (s), Figure (s), etc. Affected (Attach marked-up pages) O QC ) Reference and Source Documents Attached [ ] Significant Hazards Consideration [ ] Environmental Evaluation [ ] Enviromental Impact / Categorical Exclusion [ } Other D) is UFSAR change required? [ ]Yes [ } No LCR No STATUS E) Priority ASB -
</x u NRC approval required by (date): m. I '
An [ ) Emergency [ ] Exigent condition will occur if not approved by: 0 8 - "S M (State date): ppv Explanation ,, mc n.m, .;A F) Implementation DER No. P** * * * * * * * * * " " * * * * * * * * * * * *
- P A R T 3 : A P P R O V A L S' * * * * * * ** *** * ** ** *** * ** **** ** * ****** ****** ****** * * **
- l A) Originator A Shahkerami k.dh m '-
Date 6 /28/88[
- 8) Technical Expert & r, ,4.4 , . Date 3/s Y 87 C) Nuclear Generation Unit Head Date d h D) General Director, Nuclear Engineering [ )NA Date /
E) Plant Manager h M, Date 9 /1 -. OF) Other Date G) Director. Nuclear Licensing w* ~ Date /6k
,H) OSRO Approval (Tech Spec Amendments) [ } NA Date ,
11 NS.RG Appioeal tOpr a'ing titenw Amt ndments) l }NA , ,
.,__D a t '
/. ,
.. , # ip ray . > ': i 10i. Tr k TCLCR fo UFSAR rh [gg,
, . EFFECTIVENESS REVIEW i l, lS l
. R;f;r;nce LCR 18 19 l- 11 17 19 l- lU lF '
WW5 *l M Rawlsion 0 Page 2 of $ l' "***** * ** * * ** * * * * * * * * * * ** " * * * * * * *" * * * *
- P A R T 1 : UFSAR 4MTN A ** ********** ** * ************ * " * * *
- I
/ A) Quality Assurance Program
[ ]Yes [ ] No Does the change (s) cease to satisfy the criteria of 10CFR50, Appendix B and the UFSAR program commitments previously accepted by the NRC? Provide the basis for each change on Attachment 2, Page 2.
- 8) Fire Protection Program
[ ]Yes [X) No Does the change (s) significantly decrease the level of fire protection in ! the plant? [ ]Yes [X] No Does the change (s) result in failure to complete Fire Protection Program : approved by the NRC prior to license issue? Provide the basis for each change on Attachment 2, Page 2. l~*"PART 2: RADIOLOGICAL EMERGENCY RESPONSE PREPAREONES PLAN [ X ] N A ****"********" l
- A) [ ] Yes [ ]No Does the change (s) decrease the effectiveness of the RERP Plan?
l [ ] Yes [ ] No Does the RERP Plan, as changed, cease to meet the standards of 10CFR50.47(b) and 10CFR50 Appendix E? l i Provide the basis for each change on Attachment 2. Page 2. l~. .. . .... .u u. * * * "* * *" **
- P AR T 3 : SECURITY PLANS [ X ] N A ** *"" * "* * * * * * * *** * ** ***" * * * **"*
- l A) Document A)[ ] Yes [ ] No Does the change (s) decrease the effectiveness of the Physical Security Plan or Security Personnel Training and Qualification Plan prepared pursuant to 10CFR50.34(c) or 10CFR73? '
[ ] Yes [ ] No Does the change (s) decrease the effectiveness of the first four categories l of informational Background, Generic Planning Base, Licensee Planning Base. and/or responsiblity matrix of the Safeguards Contingency Plan prepared pursuant to 10CFR50.34(d) or 10CFR73? p Provide the basis for each change on Attachment 2. Page 2. A P**"**"*"****"***"******PART4: PROCESS CONTROL PROGRAM [ X ] N # **"* *** * *" * * ** * **" " l A) [ ] Yes [ ] No Does the change (s) reduce the overall conformance of the solidified waste product to existing criteria for solid wastes in accordance with Technical Specification 6.13? Provide the basis for each change on Attachment 2 Pete 2.
, P*******"****"***********************PART5: ODCM [X NA*******"*"""********"**""*******"l A) [ ] Yes [ ]No Does the change (s) reduce the accuracy or reliability of the dose calculations or setpoint determinations in in accordance with Technical Specification 6.14?
Provide the basis for each change on Attachment 2. Page 2. P" * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *
- P A R T 6 : A PPR O V A L S """" * """* "" """"" * """ * " * " * " * " l A) Originator A. Shahkaraml k .hk Ak m '"
Date $ / t. 5 / $g
- 8) Technical Expert w Date f- f/-ff C) Quality Assurance (For Security Plans only) Date lD) OSRO (Not required for UFSAR Changes) Date l Form FIP-RA2-01 Att 21/2 030189 DTC- [ ] TCLCR for UFSAR File: 1735 DTC: [ ] TDLCR for other
EFFICTIVENESS REVIEW 00.CUMENTATION f l
'* R;f;r:nce LCR 18 19 l- 11 17 19 l- IU lF lS l
- l. Revision O Page 5 of.5 l
Document [ Listed below is each change by section and page; the reason for the change; and the basis for < ! concluding that the revised plan or program continues to satisfy the criteria for that plan or program. Section/Page Change Basis Section 9A, UFSAR Add shield wall for fuel UFSAR Figure gA-8 is the Figure gA-8 ' pool cooling and cleanup fire harard analysis (FPCCU) System suction line drawing for the 3rd floor reactor building and is ' being revised to show the , shield well for FPCCU i i system suction line. This wall does not adversely impact fire protection / detection since it does not extend to the ceiling (i.e. does not impair detector response) and i does not enclose any fire l protection equipment. l Access to the area behind I the wall is available i ,f] through the new installed _ doors, l V l I I 1 l l l l l 1 I i l 1 1 1 I i l k i i I - Form FIP-RA2-01 Att 2 P2/2 030189 DTC: [ ] TCLCR for UFSAR File: 1735 DTC- [ ] TDLCR for other
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- s. DENOTES EXPOSURE DURING CERTAIN INFREQUENT Fed 2 LIQUID TRANSFER OPERATIONS. UPDATED FINAL SAFETY ANALYSIS REPORT C. DENOTES EXPOSURE DURING NPCI SYSTEM
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D. DENOTES EXPOSURE DURING TIP REMOVAL. E. DENOTES EXPOSURE DURINO RCIC OPERATION. FIGURE 12.1-4 P. DENOTES MAX. EXPOSURE DURING SMUTOOWN. FERMI 2 RADIATION 20NEs-THIRD FLODR PLAN DETRolf EDISON COMPANY DRAWING NO.SA7212233,REV.C
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. s' Reporting to the Plant Manager - Nuclear Production are the Superintendent - Operations, the Superintendent - Maintenance and Modifications, the Director - Nuclear Security, the ;
Superintendent - Radiation Protection, the Superintendent - Technical Engineering, the Supervisor - Planning and Scheduling, l 2 and the Assistant to the Plant Manager. The Radiation Protection : Manager reports directly to the Plant Manager regarding radiological control (see Subsection 13.1.2.3.2.5). l In addition to Fermi 2 responsibilities, the Plant Manager ; will provide support for the decommissioned Fermi 1 facility, including the reactor, the fuel and repair building, and the 2 sodium storage and treatment building. This facility should , take no more than 1 percent of the Plant Manager's time. The Superintendent - Radiation Protection will perform the surveil-lance requirements of the Fermi 1 Technical Specifications. On the average, these will not require more than 100 work-hours of effort each year. ' Thekleefrohc%
;1 =t staff is organized into sections under the direction of the Plant Manager - Nuclear Production. Figures 13.1-3 and 13.1-4 are the Nuclear Production organization charts; each 2 classification in the figures represents a job position for one '
or more individuals. The functions, responsibilities, and authorities of plant personnel are described below. .
.13.1.2.3.2.1 suoerintendent - Coerations The operations Section is responsible for the operation of plant equipment and systems including radwaste and plant chemistry.
The Superintendent - Operations is responsible for the activities of this section. The Superintendent - Operations exercises overall managerial and supervisory responsibility for the startup testing and safe, reliable, and efficient operation of the plant and all' associated 2I equipment. It is the Superintendent's responsibility to have a staff of trained and properly licensed personnel to accomplish the various plant responsibilities and to ensure that qualified personnel are available to fill the plant complement positions. Prior to operation, the Superintendent - Operations was respon-2 sible for the Fermi 2 startup and testing activities. The operations Section is shown in Figure 13.1-4. All operations, testing, or maintenance work must be approved either by the Superintendent or by an assigned delegate, as 2l established in procedures in the Plant operations Manual. In the absence of the Superintendent, the succession to the Superintendent's responsibilities is specified by procedures in 2 the Plant operations Manual. T, Reporting to the Su'perintendent are the operations Engineer, the operations Support Engineer, the General Supervisor - Radwaste, 13.1-8 REV 2 3/89
~~' - ~ - ~ ~ ~ ~ ~
i i UCENSING CHANEE RECUEST LCR 18 i* l - 1/i6101- iuiFisi !
Revision & Page I of 2>
...........o......*PART1: UFSAR, PLAN, OR PROGRAM REVISION [ ]NA "*"*"***"*"l .
A) Document , uF5AR
~B) Section(s) Table (s) Fspute(s), etc. Affected (Attach marked-up pages)
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! ) Operating License ( ) Tech Specs ( ) Environmental Protection Plan 1 Tech Spec Clarification
- 5) bection(s), Table (s), Figure (s), etc. Affected (Attach marked-up pages)
C) Reference and Source Documents Attached Significant Hazards Consideration ( ) Environmental Evaluation O (( }] Enviromental Impact / Categorical Exclusion D) is UFSAR change required? [ IOther l )Yes ( ) No LCR No STATUS E) Priority A% O'j NRC approval required by (date): An ( ) Emergency [ ) Exigent condition will occur if not approved by: [ygy, M E p4gf (State date)- MtV. Explanation <-'re ,. __ 0 F) Implementation DER No. . p ... . . . ... . . n o . . . . . . . . . . . pany 3 : apppovitse oooooomooooom.ooma::ooomo i A) Originator }{t wn $ Wn.um fht 'L )$ &)U Date 7 . f
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- 0) Director, Nuclear L censing Date /
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- 1) NSRO Approval (Operating L'icense Amendments) )NA Date l hrm FIP-RA2-01 Att 1 P1/1030189 DTC:II TCLCR for UFSAR File: 1735 DTC: ( ) TDLCR for other
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l Skvio# plves FooW an./ 8, [ l Core spray piping upstrema o he outboard shutoff M is i designed for the lower pressur and temperature of the core spray , I pump discharge. Se outboard alve and downstrema piping are , designed for RPV pressure and temperature. The pumps, piping, ! and valves are designed to meet requirements described in Chap- l j ter 3. The pumps are also designed and tested in accordance with ! i the standards of the Nydraulic Institute. ghe pump characteris-i tic curve is given in Figure 6.3-12. i The core spray pumps and all automatic valves can be operated i individually by manual switches in the main control room. , i operating information is provided in the main control roca with i j pressure indicators, flowmeters, and indicator lights. Automatic i signals to start the system preempt all other signals while the . l ! system is in auto mode. In the manual override condition, the i i pump or valve .will be under total operator control. The manual ! override condition is indicated to the operator in the main con- i trol room. ,
* }
6.3.2.2.3.1 Core spray Test Mode Durine Plant operation l A test line for the rated core spray system flow rate is provided . to route the suppression pool water from the pump discharge to ; the suppression chamber without entering the reactor pressure I vessel (see Figure 6.3-9). During reactor operation, the core l _ spray injection valves are normally closed. The pumps are ( started by the operator using the remote manual control in the main control room. Valves F015A and 3 in the test lines are , opened partially to achieve' the rated flow through the test : lines. This mode of operation permits testing of pump operation , and ensures that rated flow is achieved. It also permits testing , l of control and operation of components of the low pressure see-t tion of the core spray system. , i 6.3.2.2.3.2 Core Soray Test Durine Plant Shutdown To provide for system testing during a plant shutdown (see Figure 6.3-10), a connection is provided from the condensate ' storage tank to the pump suction. Sie condensate is used for flow testing of the spray nossles inside the pressure vessel. A
- locked-closed manual valve is provided between the condensate storage tank and the pump suction line to minimise the possibil-ity of communication of the condensate to the suppression pool end to avoid extension of the primary containment. l During plant shutdown, the core spray system is tested by manu- i ally opening valves F00ith and S. The pumps are started by remote
. manual control, and valves F004A and B and F005A and B are opened by remote manual switch. System operation including sparger rings is tested in this manner during shutdown conditions. Any system maintenance or repairs may be made on the core spray sys-tem during plant shutdown by manually closing valves F007A and 3, which are normally locked open.
6.3-11
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a see. ' (eenaewate ama pump ewetens a tas 1: l VI!!. Eish-m7 essure enslaat $ateetten 1 /tro 57f , piping, and valves, steen supply , 4 beyond outermeet toeletion ,
, valve, other . 3 1350 575 r Skvte# v Ivs FooN A nael B ,ote ,e,, a 1,oD 40-31:
C 8f 8' btfMW b ter pump , 3 4SO 40-312 l i ff v)alve aid ouN4 t ,1., . v.tv , .n.e. oh. t : 1:0 wo 1 l0700 h VA *J M4 earl 3 lant supply to haremetrie i eendeneer 3 440 140 , r coetant supply to gland seal sendeneer 3 138 170 , pump ouetion tren sendensate a storage tank (taelusing valves) 3 18 120 { Pump ouetion tres sup'reseteo p p**le piping and valvoo 3 135 170 pump disaharge to feedwater. . l piping and valves 3 1:30 170 pump etocharge bypass time to , suppreesten pool, piptag and valvoo 3 135 340 , Test line to seneonoste stor-age tank, piping and valves 2 1330 170 4
- Turbine eshouet voeuum breaker '
line 3 150 we-
. IX. ICIC erstes , ,
pump 3 1500 tit , Piping and valves in steaa 1:no to turbine, oute14e isoletten valve 2 1250 575 { Turbine exhaust to suppression k' peel, piping and valves 2 150' 367 3.9-121
l
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O I;;;;;;;;;;;;;;PART 1: W 5AR. PLAN. Ok rummadN seu153W I A) Doo ment Updated Final Safety Analysis Report 154 -- ;-- l
- 5) 5ection(s). Table (s), Figure (s), etc. Affected (Atteoh marked-up pages)
Flaure 10.4-5 cm oi wJ C) Reason for Otange A new intake flow arid structure is shown on drawina No. 6M721-2007 which is the base drawina for W5AR Flaure 10 4-5. , j m a m rene m s'h D) Reference and 50urce Documents (Identify) B "[ [jM g L l EDP-10498 Test N/A EaE ERB R hNE 1 PDC-10495 Tech 5pec N/A ****~~-" ; ABN N/A Procedure N/A ! DER N/A SE (Attaohed) 59-0107 ) Effectiveness Review (Att. ached) N/A Other N/A Drawings, Design Calculations, Correspondence, etc. l leeeeeeeeeeeeeeeeeeeePART 2: OPERATING LICMSE mme [ ]NA *********l ! A) Document 1 ( ) Operating License ( ) Tech Specs ( ) Environmental Protection Plan , ( ) Tech Spec Clarification l B) Section(s), Table (s) Figure (s), etc. Affected (Attach marked-up panes)
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[ ] Environmental Evaluation DlSI. jj _ ( ? Other nro - l D) la UI'SAR change required? """ - l [ ] Yes ( ) No LCR No. v"**~'~j -
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"**" "'*"'"*""* UPDATED FINAL SAFETY ANALYSIS REPORT O 1 FIGURE 10.4-6 l 1
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esp ion, see m ! l REV 2 3/89
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Revision % Page I of 4 t'
* "- ' ' P ART 1: UFS AR. PLAN. OR PROGRAM REVISION I INA '""""-""*""-""l A) Document
- 8) Section(s). Tablets). Figurels), etc Affected (Attach marked-up pages)
UFSAR Sections 3.8.3.7 and 3.8.4.7 C) Reason for Change Clarification of inservice intnoction renuir-nte far structures. D) Reference and Source Documents (identity) EDP Tech Spec PDC Procedure ABN SE (Attached) #9 ..e 3 DER PE (Attached) yrs Test E ectiveness Review (Attached) [ ]Yes [X}No Drawings Design Calculations Correspondence. etc. f.% . . . . . . . . . . . . . . . . . . . . . . . . P A R T 2 : OPERATING LICENSE CHANGES IX]NA
**"""""*""*"*"l A) Document
[ ] Operating License [ , )Tech Specs [ ] Environmental Protection Plan { l Tech Spec Clarification B) Section(s) Table (s), Figure (s). etc. Aff ected (Attach marked-up pages) C) Reference and Source Documents Attached [ ] Significant Hazards Consideration [ ] Environmental Evaluation [ ] Enviromentat impact / Categorical Exclusion ( )Other D) is UFSAR change required? my Avg se { } Yes ( ) No LCR No - . . . . - __E) Priority NRC approval required by (date) ASB C I
~
An ( ) Emergency [ ]Emigent condition will occur of not approved by. DIST, MT 69 (Sr. ate date) REV. Explanation F) Implementation DER No . p..... o .........--......... PART 3: AP P R O V AL S" " " " " " " " "" """ "" """" """ * * "" "" l Date bhS7 A) Originator b- nG,h
- 8) Technical Expert 8' h Date ff C) Nuclear Generation Unit Hea'd /r E -f~1 '/IV/$PSA Date /4/8f Date
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D) General Director. Nuclear Engineering i ]NA, Date 2,W#7 E) Plant Manager Date F) Othe, G) Director. Nuclear Licensing - 4__ - Date /4 M Date su oSRo Approvat (Tech Spe- Ame9dments' ( )NA
~ ~ ~ ~ ~ ~
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i 38532 Ferrtir Fu; pert Pedestal. Drywell rieer, Gallery Fleer L e '. e . s , Earthcua<e-Stabil;:er Truss Syste , af.d P:pe - Fres<-Suppert Truss Syste-The ::nstru::f on materials and OC precedures for these structures confer :: the standards set forth in Subsection 3.8.4.6. These structu es are net located in a~ region of high-energy neutron flux thus, radi'ation'danage to these structures is not expected. 3.8,3 7 sTest ng and b ser sur eillance Recuirements A OD INEERT A pf,UJ - i (1 The structures speci:lec in suosection 3.8 3.1 are vasw.64y u. , , j L sceeted when the reactor is shut down.I Structural steal members ; are examined for corrosion, excessive deformation, and' warpage; l their bolted or welded connections are examined for tightness and soundness. The structural integrity of reinforced concrete mem- ; bers is evaluated by mapping cracks in critical areas identi- 1 fiable by design and by checking for spalling and excessive ] deformations. Anchor bolts are inspected for tightness. ' Rigorous inspection is carried out during-construction and in con] unction with the quality control (CC) assurance procedures
'i struc-
- - for structural (tura: Integritymaterials ar.c - cr outlined perrormance-tests in Subsection are not3.8.4.6.]d. concucte __.
A D D l*4 E E R T Eb 3.8.4 Other Category : Structures i 3.8.4.1 Description of the Structures - l All structures that contain or support safety-related systems ; and/or equipment are designed to withstand both seismic and tor- 1 nado loads, including tornado-generated missiles. Seismic loads are not considered to act simultaneously with tornado. loads. ! Subsection 3.3.2 identifies the Category I equipment and struc- l tures that are protect <d against tornadoes. So unique materials or new features are used in the design or i construction of the structures described in this section. j So concrete block masonry walls have been used as load-bearing ! walls in Category I structures. Piping or equipment is not ! supported on masonry walls. The walls are basically non-load- ! bearing partitions. However, minor attachments of weight totaling less than about 2 percent of the weight of the wall, e.g., Junction boxes or key card readers, are permitted. In cases where the weight of items attached to the wall is signifi-cant compared to the weight of the wall, the actual weight of the attachment is considered in the design. i
+
3.5-36 F.I'l 1 1 EB-
m .
, ,,,. , 3 ( , 3 ; M O M. W [N . A. saj 4 'O Tr.e material installation ~and inspection of high-strength bo'ts, .
in general, conform to the requirements of the specification for struct.:ral joints using ASTM A325 or A490 dolts. j 3 . 8 . 4 .'6 . 9 - Summarv of Qualitv Assurance for Construction and Construction Materials The Quality ' Assurance Program, implemented with a fuki and cot-plete field quality control system, has provided~ documented assurance that the structural work at the site, including al'1 concrete, reinforcing steel, miscellaneous steel, structural ! steel, and all ingredients and special processes used in pro- I ducing the aforementioned items, is in accordance with the oro- l ject specification requirements-and the applicable ACI, ASTM, and , AISC standards. { The results of the continuous concrete and reinforcing bar test-inq orogram, carried out at the site laboratory, have confirmed the effectiveness of the controls. All reinforcing has met or exceeded the design tensile strength requirements, and the eval-uation program for monitoring the concrete-cylinder compression test results shows a continuous average strength well above the project specification requirements. 3.6.4.7 Testinc and Inservice Surveillance Requirements O- Secondary containment leak-rate testing is discussed in Subsections 6.2.1.4.2, 6.2.3.3.2, and 14.1.3.2.51. ; Some cracking of the reactor building exterior walls may occur ! during an SSE, but large, predominantly-open cracks are not exoected. Therefore, the leakage rate from the reactor' building l will not change significantly subsequent to an SSE. No other oreliminary structural- integrity or- performance tests are conducted on the reactor / auxiliary building or RMR comolex structures. However, rigorous insoection techniques and QC oro-cedures are adopted throughout their construction, as indicated in subsection 3.8.4.6. g old-IRoutineperiodicinsoectionsoftheconcrete'structureswillbe conducted to check for oossible deterioration, excessive crack-ing, or spalling of the concrete. Similar inspection will de the surface coatings and abnormal deformations or waraage. madeonstructuralsteelmembersto.~checkfordeteriorationof] 3.B.5 Foundations and Concrete Succorts 3.8.5.1 Description of Foundations'and succorts The reactor / auxiliary buildin; is supoorted by a reinforced-concrete basemat ( Figure 3.8-39 ), approximately 4 ft thick. A
-ft-diameter by 19-ft-nigh reinforced-concrete pad, integral with the base and centered under the RPV, supports the biological 3.4-34
. * . .{ .. . . . . . .
,i lCA Bf-M1.W5-n.c.p taf j O
i INSERT A 3.8.3.7.1 Testing and Surveillance Requirements During Plant Construction Phase The structures specified in subsection 3.8.3.1 are
~
1 l visually inspected as part of the Quality Control program, t l-l , INSERT B k 3.8.3.7.2 Testing and Inservice Surveillance Requirements No inservice structural integrity and/or performance
- tests are conducted for containment internal structures.
l l l l l 1 1
A%MS.lNFoRMA TE DT9 PAGE M--- ,,pcy,, TioNOsw ,,f h [ h SIN G CHANRE REDUEST >',, pg i o ode > tcR 16191- I/lfl/l- l ulf t S I SEP 281989
, . ' i U$$ ? v0 Revision hPaDe /61 Y7 UFSAR. PLAN, OR PROGRAM Revision [ ] N A * """" " * * * " " * * ""l O, vou.
- t. . . . . . . . . ... . .. .. P ART 1 :
- 4) Document O f 3/9 d B) Section(s). Table (s), F6gure(s), etc. Affected (Attach marked-up pages)
Sn k a/.x2 w np.4?: A pr M. /- 2 o.,J M -/ C) Reason for Change At s, ,e 7 5F 0 g i A ,,, r /m C e,
- 0) Reference and Source Documents (Identify)
EDP Tech Spec PDC Procedure ABN SE (Attached) 9 4 - o/o / DER w PE (Attached) Test
, Effectiveness Review (Attached)pdYes [ )No Other Drawings. Decion Calculations. Correspondence, etc. ,
p ov.. . . . ..... .. .u. .... . * * * *
- P ART 2 : OPERATING LICENSE CHANGES DQNA "*"*"*"*"*"*"*"I A) Document
[ ] Operating License [ ] Tech Specs [ ] Environmental Protection Plan CONTROLLED [ ] Tech Spec Clarification B) Section(s). Table (s), Figure (s), etc. Affected (Attach marked-up pages) C) Reference and Source Documents Attached [ ] Significant Hazards Consideration [ ] Environmental Evaluation [ ] Enviromental Impact / Categorical Exclusion [ ] Other hvD)is UFSAR change required? [ ] Yes [ ] No LCR No STATUS,, a> Priority ASB Clos //< //4/K NRC approval required by (date): _ An [ ] Emergency [ ] Exigent condition will occur if not approved by: UlbL hE'F7 FW (State date): n ,,, , I 1 h. V. Explanation F) Implementation DER No. , r...........................,AR,,.A,,Ro,A<,...................................................., A) Originator -med Date M5M89 B) Technical Expert / r A AB 5' Date [Vd-M C) Nuclear Generation Uni ad b Date 6f23f8Cl D) General Director, Nuclear Engine ring ( )NA w/ Date / 7 #7' E) Plant Manager fM Date 7.3 'N I F) Other Date FB) Director, Nuclear Licensing g Date '//// H) OSRO Approval (Tech Spec Amendments) [ ] NA Date
'l) NSRG Approval (Operating License Amendments) [ ] NA Date {
%rm FIP-RA2-01 Att 1 P1/1030189 DTC:,PtTCLCR for UFSAR File: 1735 DTC: [ ] TDLCR for other
EFFECTIVENESS REVIEW Reference LCR l b19 l- l / l II / l - IUl/l$ l Revision h Page"Zof Y7 p......u.. ...u n..u...... u u n. . ...... . pany 3 : UF S AR [ ]NA""*""*""""*"**""""*"l A) Quality Assurance Program [ )Yes [>() No Does the change (s) cease to satisfy the criteria of 10CFR50, Appendix B and the UFSAR program commitments previously accepted by the NRC? Provide the basis for each change on Attachment 2, Page 2.
- 8) Fire Protection Program
! )Yes [Xj No Does the change (s) significantly decrease the level of fire protection in the plant?
! )Yes !X) No Does the change (s) result in failure to complete Fire Protection Program approved by the NRC prior to license issue?
Provide the basis for each change on Attachment 2. Page 2. P*"* PART 2: RADIOLOGICAL EMERGENCY RESPONSE PREPAREDNES PLAN [)dNA """;;;;;****** j A) [ ] Yes [ ] No Does the change (s) decrease the effectiveness of the RERP Plan? [ ] Yes [ ] No Does the RERP Plari, as changed, cease to meet the standards of 10CFR50.47(b) and 10CFR50 Appendix E? Provide the basis for each change on Attachment 2, Page 2. p.n..u.......u.u.u..."* PART 3: SE CURITY PLAN S b(]N A ""*" ;;;**""*""**""**"*"*"l A) Document A) [ ] Yes [ ] No Does the change (s) decrease the effectiveness of the Physical Security Plan or Security Personnel Training and Qualification Plan prepared pursuant to 10CFR50.34(c) or 10CFR73? [ ] Yes [ ] No Does the change (s) decrease the effectiveness of the first four categories l of informational Background, Generic Planning Base, Licensee Planning Base, and/or responsiblity matrix of the Safeguards Contingency Plan prepared pursuant to 10CFR50.34(d) or 10CFR737 Provide the basis for each change on Attachment 2 Pas e 2. - pu.. . u .. u..u u. . . .. .,* *
- P AR T 4 : PROCESS CONTROL PROGRAM LNN A*"*""**""*"""**** l A) [ ] Yes [ ]No Does the change (s) reduce the overall conformance of the solidified waste product to existing criteria for solid wastes in accordance with Technical Specification 6.13?
Provide the basis for each change on Attachment 2 Pale 2. p.u.n u..u....u u.....* "*"*"* *" PART 5 : ODCM [X NA**"*""*"*"*"***"***"**"""**"*l A) [ ] Yes [ ] No Does the change (s) reduce the accuracy or reliability of the dose calculations or setpoint determinations in in accordance with Technical Specification 6.147 Provide the basis for each chan ge on Attachment 2, Page 2. pon.u.*"""""*"*""* PART 0: AP P R O V AL S"" * """"""""*""""""" *"""""""" l A) Originator d) Date bMy
- 3) Technical Expert b :m MV /85 Date M2 t/d 9 C) Quality Assurance (For Security Plans only) Date ID) OSRO (Not required for UFSAR Changes) Date l form FIP-RA2-01 Att 21/2 030189 DTC: [ ] TCLCR for UFSAR File: 1735 DTC: [ ] TDLCR for other I
4 . l EFFECTIVENESS REVIEW DOCUMENTATION . Reference LCR I 619 l- l/l5'l/I- I dip 15 I
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up sse l Listed below is escn change by section and page; the reason for the change; and the basis for i concluding that the revised plan or program continues to satisfy the criteria for that plan or program. Section/Page Change , Basis t l '7 .7 J. 3 a.,,s f)sa se A oi l o v / W1 r Ao-v rA n s ., / e house /EJ */ bv< e A> sho w /X'e is n a;/ Af% r .fd, 4se wns V / j
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89 - /T/- v/J panesia upsAR 4C4 l ',; ,, 25Y $ PT V4 7
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O ai == and the Supervisor - Correct *ive Action and Technical support.* ==> J 13.1.3.2 vice President - muelear anoineerino and-services The Vice President - Nuclear Engineering and Services is respon-sible for plant engineerine, nuclear technology,-radiological emergency response preparedness,-nuclear fuel, computer services, information systems, nuclear procurement, materials management, administrative services, and licensing in support of Nuclear Generation. Reporting to the Vice President - Nuclear Engi-neering and Services are the Director - Nuclear Licensing, the General Director - Nuclear Engineering, the Director - Nuclear Services, the General Supervisor - Nuclear Fuel, Director - Nuclear Materials Management, and-4h+ Supervisor - Radiological j Emergency Response Preparednessy a,i/ rie SujaWow- TsMNsorsT 5 %. 2 reren7 G< asp l'3.1.2.2.1 Director - Muelear Lieansina The Director - Nuclear Licensing is responsible for interfacing and maintaining communications with the NRC and providing.regula-tory and compliance support. Reporting to the Director - Nuclear Licensing is the Supervisor - Compliance and Special Projects. 13.1.2.2.2 General' Director - Nuclear Encineerina 1 Director - Nu to r =n.ineeri , i s O I 2he Gene
< -engineering of modifications to plant structures, systems, e
Within the context of Section 4.6.1 of ANSI N18.1-ist J and equipment. 1971-(Selection and Training of Nuclear Power Plant Personnel), 2} the
- Engineer General Director - Nuclear Engineering is equivalent to theIn this capacit , the in Charge."
Nuclear Engineering has the responsibi ity and authority to assign Edison personnel or to retain qualified consultants to perform necessary design work, design reviews, incident evalua-tions, or safety analyses. Reporting to the General Director - Nuclear Engineering are the General Supervisor - Engineering j Design and Services, General Supervisor - Plant Engineering, and the General Supervisor - Special Projects. Also re rting to the General Director - Nuclear Engineering are any arch tect/engi-neers providing support services. 13.1.2.2.3 Director - Nuclear services The Director - Nuclear Services is responsible for business and engineering application computer support, computer opSration ser-vices, the management and control of construction and operational records, the development of supporting information delivery I systems for the plant, and administrative services. Reporting to 2 the Director - Nuclear Services are the General Supervisor - Computer Services, General Supervisor - Information Services, and the General Supervisor --Admi istrative Services. 13.1-6 REV 2 3/89
AM 8 9 ' 'D ~ v^f
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P r (11 7 17.2.1.2.1 Plant Manaaer - Nuclear Production The Plant Manager - Nuclear Production (Plant Manager) is ) responsible for the operation, maintenance, modification, outage management, radiological protection, security, and plant 3 administration of Fermi 2 andAfor the implementation detailed description ofthe plant of quality-related procedures. organisation, including responsibilities, authorities, duties, l and qualifications for all key staff positions, is given in The Plant Manager is the chairman of the Subsection 13.1.2. In matters involving - Onsite Review Organisation (OSRO). implementation of the QA program for the operation of the plant, 1l he is supported by the Supervisor - Production Quality Assurance j and his staff. , 17.2.1.2.2 Director - Nuclear Trainine l 1 The Director - Nuclear Training is responsible for developing and implementing training programs in support of the safe and j efficient operation of the plant. The training program is described in Section 13.2. , 17.2.1.3 Vice President - Nuclear Enaineerina and Services The Vice President - Nuclear Engineering and Services is j responsible for plant engineering, nuclear- technology, radiological eme O computer services, information systems, nuclear procurement, administrative services, and licensing in support of the plant g operation. Reporting to the Vice President - Nuclear Engineering and Services are the Director - Nuclear Licensing; General Director - Nuclear Engineering; the Director - Nuclear Services; 2 the General Supervisor - Nuclear Fuel; Director - Nuclear Materials Aanagement; end4he-Supervisor - Radiological Emergency Response Preparednessj ,d #e 5spemsw- Lwrenhd 54rj ye] 6*F 17.2.1.3.1 Director - Nuclear Licensino The Director - Nuclear Licensing reports to the Vice President - 2 Engineering and Services and is responsible for nuclear licensing activities and for ensuring compliance with regulatory require-ments. The Director or the operating authority is responsible for communications with the NRC Regional Office on reportable deficiencies for activities covered by the Nuclear QA program. 17.2.1.3.2 General Director - Nuclear Encineerina 1 The General Director - Nuclear Engineering reports to the Vice President - Engineering and Services and is responsible for design engineering and nuclear engineering including plant engineering, nuclear technology, and qualifications engineering Nuclear Quality Assurance in support of plant operations. 17.2-2 REV 2 3/89
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, LICENSING CHANGE REQUEST LCR 18191 - 1115141 - IUlFISI Revision & Pare 1 of 7 lunumenneuePART 1: UFSAR, PLAN, OR PROGRAM REVISION [ ; NA ***H H # l A) Document ,
UFSAR l B) Section(s)g Table (s), Fjgure(s), etc. Affected (Attach marked-up pages) 10)
# Fig. 5.1-3, 7.3-11, 7 3-12 (U f.o m e g)
C) Reason for" Change The Main Steam Isolation Valve (MSIV) Manifold Q' ; Assembly Schematic Diagram (Fig. 7 3-11) is being revised to be consistent with the MSIV Manifold Assemblies being installed per EDP-5546. p .-- S i d UFSAR Figs. 51-3 and 7.3-12 are revised to update recent drawing change. D) Reference and Source Documents (Identify) o q [E-al EDP 5546 Test N/A rnN rpn1 1 r [-) g , ,l PDC N/A Tech Spec N/A p l ABN N/A Procedure N/A E $ ., (l DER N/A SE (Attached) 89-0079 N/A y Effectiveness Review (Attached) 9 Other N/A m: K ,, Drawings, Design Calculations, Correspondence, etc. Q f l*enue**ennenn**PART 2: OPERATING LICENSE CHANGES [x]NA ######9*#l ' 5 $ .I-l A) Document L-( ) Operating License ( ) Tech Specs ( ) Environmental Protection l Plan ( ) Tech Spec Clarification i B) Section(s), Table (s), Figure (s), etc. Affected (At+-+ ---Erf STA ;tlTf$m; C) Reference and Source Documents Attached 6 /ro n, ci ( ] Significant Hazards Consideration ASB P s-l [ ] Enviromental Impact - Categorical Exclusion ()lST.ocr #4e9 ( ) Environatental Evaluation [ ] other REV. D) Is UFSAR change required? .c::p. ,,g ,,f l [ ] Yes [ ] No LCR No. E) Priority i NRC approval required by (date): An [ ] Emergency ( ) Exigent condition will occur if not approved by: j (State date): i Explanation F) Implementation , ; DER No. lsuuuuuuuue**HPART 3: APPROVALSee*****unenee*******eseewesenewl KTp Butcri Ko4s?7. ?ffet A) Originator M. Majumder M. AtR A w % / a.Se 7 .G ff B) Technical Expert ,h,4 Late 7- #' 7 7
) Nu 1 r Organiza on Unit Head f Date b7 D) Director, Nuclear Engineering ( JNA / h Date 9 //I/f"[
E) Plant Manager _ , , , , , Date i
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' l Ex _ x _x x =-- .- " FART 1: UFSAR, PLAN, OR PROGRAM REVISION [ ]NA "------ -- " "- =l '
i A) Document ! UFSAR ) B) Section(s), Table (s), Figure (s), etc. Affected (Attach marked-up pages) l Section 6.2.1.6 and Table 6.2-8 C) Reason for Change Add additional paint materials for coating the interior of the Torus in a wet or under water condition. l D) Reference and Source Documents (Identify) I Tech Spec EDP ; PDC Procedure l i ABN SE (Ansched) 89-0104 ! DER PE (Attached). Yes l Test Effectiveness Review (Attached) [ JYes [X]No Other: Design Specification 3071-360 CONTROLLED 1 Drawings, Design Calculations, Correspondence, etc i
- ju n x x x _ _ _ _ _ _ n
- ******** PA RT 2 : OPERATING LICENSE CHANGES [X1 N A - - - - = - = - - - - - - --- - l )
l A) Document - ( [ ] Operating License [ ] Tech Specs [ ] Environmental Protection Plan I } Tech Spec Clarificrtion
- 8) Hection(s). Table (s), *igure(s), etc. Affected (Attach marked-up pages)
C) Reference and Source Documents Attached [ } Significant Hazards Consideration [ ] Environmental Evaluation [ ] Enviromental impact / Categorical Exclusion ( )Other D) is UFSAR change required? [ ]Yes [ ] No LCR No. NRC approval required by (date): STATUS An [ ) Emergency [ ) Exigent condition will occur if not approved by: ASB ##a d wh h4 (State date): . . _ , - - aA v.m. ~ r - oi Explanation r?m_ F) Implementation DER No. l ju_ _xx x x :- ""-- ----- PART 3: A PPRO VAL & " - - - - - - - - - - - - - - - - - " " - - - 2 " - - - - - " - - - - - - - l ) A) Originator R. Y. Buck M Date /7.7alF87
- 8) Technical Expert U
- W. Date MM7 C) Nuctear Generation Unit Head 1 Date 7 Shj D) General Director, Nuclear Engineering [ )NA M [ h Date 7.77-/9 E) Plant Manager h Date 3-7 4 8
F) Other Date G) Director, Nuclear Licensing ~ Date G/2.Pt'7 H) OSRO Approval (Tech Spec Amendments) ( ) NA Date ll) NSRG Approval (Operating License Amendments) I ] NA Date l Form FIP-RA2-01 Att 1 P1/1030189 DTC;}(TCLCR for UFSAR File: 173s , DTC: [ ] TDLCR for other
-* UtsfeSNWS OMNett MOUSST -
600t 181T i . I I 1I181- lUt F 181 -! nevwea o enne 2 ee% 3 f I ptsui3 UPsam ' j The interior surface12ofin. thefrom vents thefrom ring the drywell header shell down is coated with to
- c a transition point Carboline carbo tine 11 roating system.
l The immersion shell area of bay 14 at asisuth 290'30' has metal-
' lined aluminum applied to it wlth a F1satte 7155 finish coat over-the aluminum.
l In boys 15 and 16, the Plasite 7155 coating has been removed in l 1-in. a 2-in. spots to f acilitate installation of instrumentation These and strain gages to be used in the scheduled SRV tests. areas are to be repaired during the first fuel outape, when the _ instrumentation is removed. AtAnsta sw?areces. Genp9
. To NtN . JP Russes To rm aner.reasssed l WDER .ss'8 Mrs sto et ttZ JL4ftt~y may costsyrtwr M , nrm e, st.swpCoM/**ff consy ty,'NJ
- Rct4reo l CoM)*47A" fM. $ A5te4iAcur:t 4de 5?>99 4RD5 ~
Mis D aneous Costines i Coatings on miscellaneous equipment and components in the drywell . are discussed below. These coatings were included in the evalu-I ation of the Persi 2 pisary containment coatings, and will not impair plant operation under normal or abnormal conditions.
- a. Galvanised Surfaces The drywell cooling systes ducting and dampers are com- At pletely galvanised without any further oostings.
welded joints, the galvanised surf ace was ground of f to . clean setti, and in some locations these ground areas
- were touched up with Salvanon I or Salvanos V, sine-rich l2
- coatings similar in properties to carboline carbo Eine
- 11. In addition, all electrical conduit, terair al
- ' -- bones, cable trays, and supporting unistruto are galvanised. The only exceptions are some:large flexible '
conduits made of stainless steel
- b. Naneers and Supports Manger and support components, including clamps, rods, spring cans, snubber attachments, pipe-whip restraint components, and secondary support steel, were originally coated with carboline carbo Eine 11. Significant changes in the hanger and support design resulted in addition of secondary support steel, change-out of Coating .
hanger components, and welding of attachments. repair and touch-up of these areas is not safety . related
- c. pioine Most of the piping within the drywell is insulated with reflective metallic insulation panels (Mirror Insula-tion), consisting of removable sections and having an O outer cover of stainless steel. Encapsulated silicon (Min-K) is used where clearance restrictions exist, i.e., drywell penetrations ar.d spaces between pipe whip i
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O en:1.s o.2-s ParMnar ano secomuner cowensmums sonrnce contrwa senenet.: O .~ 4 1 PRrMnRY CoNTn1NMENT Appr*E. Totet sey File Setet ggstet Average 9PTe g,gg.c, ,,g ,,, ,,,,,
' Twee of coettee tecetton tense) tet2) g,,,gg5)
(th/ft (et3) (tb) Carbo Sine 11 Dryssett laterior steet 7 129.000 217 73 19.901 Dq .nt.ri.e .tructure .t hengere and corporte
- Floette 7tSSble Terme Interior 12 67.000 ISO es.9 te,ess i
i Amoren G4 esed .pf support pedestet 1/16 In. 7.390 123 44.4 S.575 ', l Seefacerb Dryesett cesecrete floore prywell cenerete sette pies 10 elle g { Seleaseos 't er Sold jolete ese gelsentsed S 775 202 0.36 73 I E seivenos V ' docteortt es .1It Scote end Weetnoeleted certose steet 3.4 99.000 350 23.22 9.927 g "! 3, 4 Ternleh piping, structetet steet o stlocettonoces egelpeeset 0.7 to 2.5 '972 9. to ISO 9.129 IS U,ngeellflod einto
- c 10 01.,
M iettnese. Stestesse. Appron.- Appros. Emeettee area (ft2) Prteor ien.) ' Top cost tto.)
.r eu .et.rt.r et.et .2 car.eeeeo, iS .. 2 t .. 2 .one - ll .-
. . .I 9eres esterior steet 94.9 0 Certso Etne 11 0.992 - 9.999- messe . - h '
.econsory contaisesent coseerete 199.200 Corbellne 295 9.tnO - 9. cor.oiime .9 N
E [ eeneer , etain.ont .tr.eteret 2,. . ,2 ,e n to. .. to ces. e F .8' Il steel' leed - 0.00153 Amercote # Epeemet 9.992 - N
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LIcaustmo cuas a Enges? KER 18 19 l - 11 15 16 l - IU lF 15 l Revision d- Pare / ofI l----- ;;;;;;;; FART 1: WSAR, PLAB. OR ruuunAM usTI5 ION [ ; EA seeeeeeel A) Document UFSAR B) Section(s), Table (s), Figure (s), etc. Affected (Attaoh marked-up pages) UFSAR Figures 9A ll and 9A-5 C) Reason for Change To correct an oversight from EDP 4944 (Nov.1959) which added fire wrap to cable trays 2C-012 and 2C-030. These UFSAR ; f1tures were updated accordingly. 'c-nr g':3 i D? Reference and Source Documents (Identify) -
~<.u J ' "Ic Id i
EDP Tech Spec ?D PDC Procedure ~,
'-g a _ .,
ABN 10529-1 SE (Attached) 69-0119 ^" DER PE (Attached) YES pmf i Test - Effectiveness Review (Attached) [X ]Yes [ )No T * "'" j ' Other ' Drawings, Design Calculations, Correspondence, etc. I;;;;;;;;;;;;;;;;;;;;PART 2: OPERATING LImira CHAnwea [I ]MA ######88'l A) Document [ ] Operating License [ ] Tech Specs [ ] Environmental Protection [ ] Tech Spec Clarification Plan ' B) Section(s), Table (s), Figure (s), etc. Affected ( Attach marked-up pages) t C) Reference and Source Documents Attached
] Signifiertnt Hazards Consideration d
[ [ ] Environmental k a Evaluation T t: [ ] Enviromental' Impact / Categorical Exclusion [ ] Other d E D) Is UFSAR change required? [ ] Yes [ ] No LCR No. E m E hM$! E) Priority % L ki NRC approval required by (date):_ CONTROLLED *Nz
> en
=
cn An - [ ] Emergency [ ] Exigent condition will occur if not approved bd k (State date): E "N l Explanation E " ; F) Implementation g$at DER No. 8l 4 I;;;;;;;;;;;;;;;;;;;;PART 3: AFFauwAL5;;;:::::::::: ;;;;;-' :::::::" ;;;; ll ! A) Originator D. S. Eason N Date /o F B) Technical Expert D. S. Eason [. m Date /c-s-Ff u oe m C) Nuclear Generation Unit Head h tOL lfI) A
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/ lik D) General Director, Nu MidirN ]!"./,d LiX_ Tate A//1h a n E) Plant Manager Date / / -
F) Other o v Date l G) Director, Nuclear Licensing s_ Date ////fh H) OSRO Approval (Tech Spec Amendments) [ ] NA Date II) NSRG Approval (Operating License Amendments) [ ' NA Date l Fora FIP-RA2-01 Att 1 P1/1 030189 DTC: gui TCLCR for 1FSAR File: 1735 . DTC: [ ] TDLCR for other ,) _ - - __ - . - - _ -- -) /
i
/
EFFECTIVENESS REVIEN ? maference ICR 18 19 l - 11 IS-16 l - IU IF lS I , Revision Page 2 of I g.....;;;;....;;;;;;;;;;;;;;;;; FART 1:- UFSAR [ JNA ------ ;-------- ;;l l l A) Quality Assurance Program I ( )Yes ( ) No Does the change (s) cease to satisfy the criteria of 10CFR50, Appendix B and.the UFSAR program comaltaents l previously accepted by the NRC? I Provide the basis for each change on Attachment 2. Page 2. l l B) Fire Protection Program l l [ )Yes [X ) Wo Does the change (s) significantly decrease the level of fire protection in the plant? ( ]Yes (X ) No Does the change (s) result in failure to complete Fire Protection Program approved by the NRC prior to license issue? Provide the basis for each change on Attachment 2. Page 2. I N PART 2: RADIOLOGICAL DERGENCY RESPONSE PREPAREDNES PLAN LI JNA WHI A) [ ] Yes [ J No Does the change (s) decrease the effectiveness of the RERP Plan? ( ) Yes [ ] No Does the RERP Plan, as changed, cease to meet the , standards of 10CFR50.47(b) and 10CFR50 Appendix E? Provide the basis for each change on' Attachment 2. Page 2. l** N N N N u'PART 3: SECURITY PLANS [I JNA --------------------_l A) Document A) [ ] Yes [ ] No Does the change (s) decrease the effectiveness of the r Physical Security Plan or Security Personnel Training and Qualification Plan prepared pursuant to 10CFR50 34(c) or 10CFR737 [ ] Yes ( ) No Does the change (s) decrease the effectiveness of the first four categories of Informational Background,. Generic Planning Base, Licensee Planning Base, and/or ' responsiblity matrix of the Safegusrds Contingency Plan prepared pursuant to 10CFR50 34(d) or-10CFR737 Provide the basis for each change on Attachment 2. Page 2. Im*Hmmm*MPART 4: PROCESS wnumX, PROGRAN [X JNAM m m m H l A) [ ] Yes [ ] No Does the change (s) reduce the overall conformance of the solidified waste product to. existing criteria for solid wastes in accordance with Technical-Specification 6.137 Provide the basis for each change on Attachment 2. Page 2. l******** N N H' N N PART 5: ODCN LI JNA -----------------'--------l-A) L J Yes [ J No Does the change (s) reduce the accuracy or reliability of the dose calculations or setpoint determinations intin accordance with Technical Specification 6.14? ' Provide the basis for each change on Attachment 2. Page 2. lw " " M H " N N PART 6: APPIK)TALSewemummmmemmm l A) Originator D. S. Eason I e Date /o-H 7 B) Technical Expert D. S. Eason A % Date /*-4-/7 C) Quality Assurance (For Security Plans only) Date ID) OSRO (Not required for UFSAR Changes) Date l '~ Fora FIP-RA2-01 Att 2 1/2 030189 DTC: [ ] TCLCR for UFSAR File: 1735 DTC: ( ) TDLCR for other
a m - f' % !. EFFECTIVEMESS RETIEW D0QBWATION Reference 14R 18 19 l - 11 15 16 l - lU IF 15 l Revision d Page 3 of I Document ABN 10529-1 Listed below is each change by section and page; the reason for the change; and the basis'for concluding that the revised plan or progran continues to satisfy the criteria for that plan or program. , Section/Page I (hange l Basis l I UFSAR Fig. 9A-4 lShow fire wrapped table IPer EDP 4944-& SE 85-668 , I . I ! I ltray 2C-030 on the 583' and 89-0119 tray 2C-030 ! ! I i lelevation plan view, was fire wrapped and the l I text of 9A describes ; I i l Isame, however this draw- } I I i I ling was overlooked to l l l l l lindicate 20-030 is fire ; I I I lwrapped. ,O l l , I i l l UFSAR Fig. 9A-5 Ishow fire wrapped cable- Per EDP 4944 tray 2C-012 -! I j l ltray 20-012 as it is 'was wrapped and the text I 1 actually wrapped to about of the UFSAR described 4 17' south of col. line 15 same. -This drawing how-1 I lever, was not corrected l l l to show the extent of' I wrap on 2C-012 which was I ( l i I i l i an oversight. SE 85-668 1 -i l l lapproved this configura-t i I l tion, as does SE 89-0119. F I l I I l ; o l l : lO j i . I I l
. Fora FIP-RA2-01 Att 2 P2/2 030189 DTC: L ] TCLCR for UFSAR File: 1735 DTC: [ ] TDLCR for other
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