ML20151A404
| ML20151A404 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 03/29/1988 |
| From: | SOUTHERN CALIFORNIA EDISON CO. |
| To: | |
| Shared Package | |
| ML20151A165 | List: |
| References | |
| SO123-V-4.14, NUDOCS 8807190361 | |
| Download: ML20151A404 (14) | |
Text
i-
-NUCLEAR GENERATION SITE i UNITS 1, 2 AND 3 ENGINEERING PROCEDURE S0123-V-4.14 REVISIpH6 PAGE 1 0F 13 COMPLETE REVISION EFFECTIVE DATE A/O V /4, N80 TCN tr b PROPOSED FACILITY CHINGE (PFC)
TABLE OF CONTENTS SECTION g
1.0 OBJECTIVES 2
2.0 REFERENCES
2 3.0 PREREQUISITES 3
4.0 PRECAUTIONS 4
5.0 CHECKLIST (S) , 4 6.0 PROCEDURE 6.1 General 4 4
6.2 Routing, Review and Approval of PFC 4 6.3 Review of Revisions to the PFC 12 7.0 RECORDS 12
- 4TTACHMENTS 1 Acror.yms 13 i
h! 00hk$$000068>.
P PNU 0330d.aut QA PROGRAM AFFECTING
NUCLEAR GENERATION SITE UNITS 1, 2 AND 3 ENGINEERING PROCEDURE S0123-V-4.14 REVISION Q PAGE 2 0F 13 TCN h -(D PROPOSED FACILITY CHANGE (PFC) 1.0 OBJECTIVES 1.1 Changes (PFCs).To establish the process for review and approval of Pr 1.2 In addition, this Procedure provides direction in the following areas:
1.2.1 Review of the PFC to meet the requirements of 10CFR50.59; 1.2.2 Interdisciplinary review; 1.2.3 Identification of affected Configuration Documents (Configuration Co'ntrol);
1.2.4 Completion and closeout of Configuration Document changes associated with the PFC.
2.0 REFERENCES
2.1 NRC Commitments 2.1.1 TCN Technical Specification Section 6.5, paragraphs 6.5.2.3 and 6.5.2.4 for Units 1, 2 and 3 2.1.2 Title 10, Code of Federal Regulation: Part 50.59 (10CFR50.59) 2.1.3 .
ANSI N45.2.ll-1974, Quality Assurance requirements for the design of nuclear power plant, Section 6 Design Verification 2.1.4 Updated Final Safety Analysis Reports
.1 Unit 1 FSAR Section 3.1.1, Proposed General Design Criteria for Nuclear Power Plants
.2 Unit 2/3 UFSAR Chapter 3, Design cf Structure, Components, Equipment and Systems i 2.1.5 Topical Quality Assurance Manual (TQAM), Chapt. 2-A 2.1.6 Fire Hazards Analysis, San Onofre Nuclear Generating Station, Units 2 and 3 2.1.7 Fire Hazards Unit 1 Analysis, San Onofre Nuclear Generating Station,
e' NUCLEAR GENERATION SITE UNITS 1, 2 AND 3 ENGINEERING PROCEDURE S0123-V-4.14 REVISIpN 6 PAGE 3 0F 13 TCN 0-b
2.0 REFERENCES
(Continued) 2.2 Procedures 2.2.1 S0123-V-4.15, Structure, Equipment and System Turnover 2.2.2 S0123-VII-3.1, A1. ARA Design Review 2.2.3 S0123-XIII-15, Fire Protection Design Review 2.2.4 S0123-XIV-4.2, Site Design Change Administration 2.2.5 S023-XV-1.0, Post-Maintenance Retest Program 2.2.6 S0123-XIX-3.0, S~ite Work Request Process 2.3 Other 2.3.1 E&C 24-10-15, Processing of Proposed Facility Change Packages for SONGS 1, 2 and 3 2.3.2 E&C QA Procedure 37-30-63 2.4 E_o_C.mit 2.4.1 CC(123) 261, Review, Comment and Resolution 2.4.2 CC(123) 262, Documant Transmittal 3.0 ERGfoulSITES 3.1 Prior to use of a user-controlled copy of this Site document, it is the aser's responsibility to verify that the revision and any TCNs are current by utilizing one of the following mettods:
3.1.1 Check it against a controlled copy and any TCNs; 3.1.2 Access an SCE Occument Configuration System (SOCS);
3.1.3 Contact CDM by telephone or through counter intuiry; 3.1.4 Obtain a user-controlled copy of the Site doccment from COM; {$
3.1.5 Reference a current (within one week) Destination Configuration Control Log and associated daily update.
l
NUCLEAR GENERATION SITE UNITS 1, 2 AND 3 ENGINEERING PROCEDURE S0123 V REVISJON6 TCN fo -6) PAGE 4 0F 13 4.0 ERECAUTIONS 4.1 PFCs shall not be used as implementing change documents unl (SCE 26-294) has been approved through Block 7, ase PFC required 4.2 .
Following completion of modifications to any Units em 2 or 3 EC that alters the subsystem flow characteristics, a flow balance est t
shall beSpecification Technical performed which 4.5.2.g . verifies the flow rates delineate 4.3.
The impact of additional loads added to class IE batteries a 1E diesel generators shall be assessed by requesting the Proje organization generator) to recalculate the affected class lE battery (diesel loading.
Upon receipt of the calculations by Station Technical, (diesel an assessment generator survei shall be made of the need ery to modify
, b Maintenance, as ne)cessary.llance procedures and information provided S.0 CHECKLIST (S) !
5.1 None 6.0 PROCEDURE 6.1 General 6.1.1 phase and the full requirements of this Proc met (e.g., Construction Safety Evaluation (CSE)), the FFC !
shall identify the deviation (s).
Form SCE 26-294. case will be "For Design Only" and this A revised PFC which meets all the and approved prior to the implementation o step 6.3).
6.1.2 Department QA Procedure E&CThis Procedure interfaces 24-10-15, 2.3.1). Facility Change Packages for SONGS 1, 2 & 3 (see Ref 6.2 Routino Review and Acoroval of PFC 6.2.1 The Originator shall:
.1 Configuration Control (or his designee). Forward th 6.2.2 For Information Only:
control (or his designee): Supervisor, Configuration
.1 Determine for the PFC and System (s) involved, the name of the Cognizant Station Supervising Engineer (or his designee):
NSSS Engineering, Power Generation, or Computer Engineering in accordance with Reference 2.2.4.
NUCLEAR GENERATION SITE UNITS 1, 2 AND 3 ENGINEERING PROCEDURE S0123-V-4.14 R VIS N PAGE 5 0F 13 l
6.0 PROCEDURE (Continued) 6.2.2.2 Forward the following to the Cognizant Station Supervising Engineer:
.2.1 Form CC(123) 262;
.2.2 Original DCP;
.2.3 Form CC(123) 261.
6.2.3 Cognizant Station Supervising Engineer (or his designee)
.1 Receive and acknowledge receipt of the PFCP from Configuration Control.
.2 Assign a Station Cognizant Engineer who will be responsible for Station.
for technical review and for first level approval of the PFCP Identify the Station Cognizant Engineer on Form CC(123) 262.
.3 Forward the original of the PFCP with Attachments to the Cognizant Station Engineer for review.
6.2.4 Cognizant Station Engineer
.1 On Form 26-294 and Form CC(123) 262, identify the Cognizant Station Engineer and the affected/ interested Station organizations for Station Interdisciplinary 9eview (IOR):
.1.1 A Fire Protection Design Revia.w shall be documented by a completed Fire Protection Design Checklist included in the PFC .nackage.
If the r; view indicates "yes' to any questions, Emergency Preparedness shall be identified as a required Interdisciplinary Review organization.
.l.2 If an ALARA Design Review was performed or is required (i.e.,
an ALARA Design Review Checklist is included in the PFCP),
Health Physics shall be identified as a required Interdisciplinary Review organization.
.2 Interdisciplinary Review of the PFCP may be waived under the following conditions:
.2.1 If an IDR has been completed for either Unit 2 or 3 and an identical PFC for the other Unit is received, Interdisciplinary Review may be waived and copies of the PFC distributed to affected Managers "For Information Only". In such cases, document this determination on Form CC(123) 262.
NUCLEAR GENERATION SITE UNITS 1, 2 AND 3 ENGINEERING I N PROC'.0URE S012 PAGE 6 0F 13 6.0 PROCE0VE (Continued) 6.2.4.2.2 If an IDR Change was made Package (DCP) and of an theearlier Cognizant gnrevision of Engineer that all major coments incorporated or that there are no substr have been
. satisf>~ twily nes the previously reviewed and approved .ial DCPchanges from may be deemed to have been performed. , the IDR of the PFC Form CC(123) 262.In such cases, document this determin
.3 Provide the IDR list (CC Configuration Control (or(123) 262) his designee).to the Supervisor, 6.2.S For Information Only:
(or his designee): Supervisor, Configuration Control
.1 If an IDR is required d to the Station Manager,s (istribute copies of the PFC package the Cognizant Station Engineer onor their designees) as specified by Form CC 123) 262.
Referenc(e 2.2.4.) (Coordinate the review in accordance w 6.2.6 Station Interdisciplinary Reviewers
.1 Review the PFC and accompanying forms (if any) to ens the requirements of the PFC are accuratelyrereflected that particularly within the discipline represented. ,
Review of ~
.2 Training requirements may be identified d s review.
y.
If the PFCP is approved "as is," so indicate CC(123) 262. rm and sign F
.3 indicate and sign Form CCIf resolution of coments are r ,
are too extensive for Form (123)Record 262. coments which
.4 CC(123) 262 on Form CC(123) 261.
Return the signed CC(123 Configuration Control262(or) to the Su his designee)pervisor, 6.2.7 .
For Information Only:
(or his designee) Supervisor, Configuration Control 1
Collect the IDR approvals and coments.
Provide the IDR approvals Engineer. and coments to the designated Cognizant Station i l
l l
i l
NUCLEAR GENERATION SITE UNITS 1, 2 AND 3 ENGINEERING PROCEDURE S0123 V-4.14 REVISIAN Q PAGE 7 0F 13 TCN fn - (D 6.0 PROCEDURE (Continued) 6.2.8 Cognizant Station Engineer
.1 Resolve the Interdisciplinary Reviewer's comments:
.l.1 Review the Interdisciplinary Reviewer's comments and contact the Reviewers and/or Originator, as appropriate, to resolve the Reviewer's comments;
.l.2 If the comments cannot be resolved, the PFCP shall not be approved. Forward the PFCP with the original Form CC(123) 262 and comments to Supervisor, Configuration Control (or his design m) for return to the Originator;
.1.3 If IDR comments are resolved, indicata the resolution on Form CC(123) 262. The Cognir e t Engineer shall sign and date.
NOTE: The following steps may,11 general, be performed (or initiated) concurrent with the IDR.
.2 Review the PFCP to determine that the PFC form and package is properly initiated by the Originator. This includes, but is not limited to, ensuring that the proper selection was made between short and long-form Engineering / Safety, Envirennental and ALARA evaluations.
.3 If operation of the PFC requires NRC approval of a Technical Specification change, ensure that this is so noted in Block 2 of Form 26-294, and that the Technical Specification change request number is identified. Also, ensure that a copy of 7ds; the Technical Specification change request is included in the PFC, and that the ' Tech Specs" Block on the CC(123) 183 form is checked.
.4 Ensure that the Engineering / Safety and Environmental evaluations are adequate and correct. This includes ensuring that the Equipment Environmental Qualification criteria are provided, if appropriate.
.5 Ensure that the Engineering / Safety evaluation is consistent with the letter numbered revisions of the DCP previously reviewed by Station Engineering and that any Station Engineering comments were resolved as previously agreed.
.6 Ensure that the Implementation section, which addresses changes to the Technical Specifications, changes to the FSAR design basis or analysis and whether the alteration involves an Unreviewed Safety Question as defined by 10 CFR 50.59, is provided.
.7 Ensure that the Quality Classification and Seismic Classification are correct.
NUCLEAR GENERATION SITE UNITS 1, 2 AND 3 ENGINEERING PROCEDURE S0123-V-4.14 REVIS}0Np PAGE 8 0F 13 TCN _M ~U 6.0 PROCEDURE (Continued) 6.2.8.8 Ensure that a Notification of an FSAR Change Requirement or an Updated Fire Hazards Analysis change package is included, if appropriate.
.9 Perform a walkdown, if appropriate, to verify that the feasibility of making the change, maintenance access, Plant safety, correctness of the Construction Safety Evaluation, etc.
.10 Resolve comments with the Originator, as appropriate.
.10.1 If comments cannot be resolved, submit the PFCP and comments, on the original Forms CC(123) 261 and CC(123) 262 if applicable, to the Supervisor, Configuration Control (or his designee) for return to the Originator.
.10.2 If comments are resolved and review of the PFC is complete, indicate concurrence by signing the PFC form in Block 5 and forwaro the PFCP to the Cognizant Station Supervising Engineer (or his designee).
6.2.9 Coanizant Station Suoervisina Fnoineer (or his desionee)
.1 Review the PFCP for Plant safety, and to the extent possible, for technical adequacy.
NOTE: If the PFCP requires additional Information/ engineering study, the PFC shall be forwarded to Configaration Control for returri to the Originator.
.2 Check the appropriate disposition in Black 5 of the PFC form.
If the change involves or may involve an Unreviewed Safety Question, an Unroviewed Environmental Question or a change to the Technical Specifications withhold approval and forward to the Supervisor, Configuration Control (or his designee) to transmit to the Nuclear Safety Group for review prior to implementation.
6.2.10 For Information Only: Supervisor, Configuration Control (or his designee)
.1 If required, transmit a copy of the PFCP to the Nuclear Safety Group for review.
.2 When Nuclear Safety Group verification is received (i.e.,
Block 9 of the PFC form is signed), forward the PFCP to Cognizant Station Supervising Engineer for approval.
NUCLEAR GENERATION SITE UNITS 1, 2 AND 3 ENGINEERING PROCEDURE S0123-V-4.1 ISgN PAGE 9 0F 13 6.0 PROCEDURE (Continued) 6.2.11 Cognizant Station Supervising Engineer (or his designee)
.1 When Approved for Processing, sign Block 5 of the PFC form and forward the PFCP to the Station Technical Manager for approval.
6.2.12 Station Technical Manager
.1 Review the PFCP for its impact on Plant safety and the off-site non-radiological environment.
.2 If the change is acceptable, complete Block 6 of the PFC form and return to Supervisor, Configuration Control (or his de.ignee) to forward to the Unit Superintendent.
.3 Configuration Control (or his designee) with a concerns. Forms CC 123 26 may be used to communicate these co(ncer)ns.2 and CC(123) 261 6.2.13 For Information Only:
Supervisor, Configuration Control (or his desionee)
.1 If the PFCP was not approved by the Stattor Technical Manager, review the basis for his rejection (e.g., list of concerns) t.nd forward the PFCP to the Origiaator for resolution, revision or cancellation, as appropriate. ,
.2 If Block 6 of the PFC form is completed by the Station Technical Manager, forward the original PFCP to the Supervisor, Plant Coordination.
6.2.14 Suoervisor. Plant Coordination for his desionee)
.1 Review the PFCP to determine during which Mode (s) of operation the PFC may be implemented and complete Block 7 of the PFC form.
.2 Identify any special restrictions or limitations on construction. Engineering assistance may be requested.
.3 Return the original PFCP to the Supervisor, Configuration Control (or his designee).
NOTE:
Upon completion of Blocks 1 through 7 of the PFC form, and subject to any restrictions noted, implementation of the PFC may proceed. Equipment Control ensures that the restrictions noted are met during implementation through the Work Authorization prncess. or Construction Work Order approval
NUCLEAR GENERATION SITE UNITS 1, 2 AND 3 ENGINEERING PROCEDURE S0123-V-4.14 R VI N PAGE 10 0F 13 6.0 PROCEDURE (Continued) 6.2.15 For Information Only: Supervisor, Configuration Control (or his designee)
.1 Forward a copy of the PFC form to the Originator for implementation of the PFC.
.2 Forward a copy of the PFC form to the Cognizant Station Supervising Engineer for information.
.3 Coordinate distribution of the PFCP completed through block 7.
.4 Forward the original PFCP to Quality Assurance and then the Nuclear Safety Group for review.
.5 Retain copy of the PFCP in the PFC Design file.
.6 Coordinate interdisciplinary determination of Configuration Documents required to be changed in accordance with
-Reference 2.2.4.
6.2.16 For Information Only: Quality Assurance
.1 Review the PFC package for applicable quality assurance requirements. To indicate agreement, complete Block 8 of the PFC form and forward the PFC package to the Configuration Control Engineer; ctherwise, return the FFC package unsigned to the Cenfiguraton Control Engineer with a statement of concerns.
. 6.2.17 For Information Only: Nuclear Safety Group
.1 Review the PFCP. To indicate agreement, complete Block 9 of the PFC form and forward the PFC package to the Configuration Control Engineer; otherwise, return the PFC package unsigned to the Configuraton Control Engineer with a statement of concerns.
6.2.18 For Information Only: Supervisor, Configuration Control (or his designee)
.1 File the original PFCP in the PFC design file.
~
6.2.19 Originator
.1 The Originator shall ensure that the following requirements are met:
.l.1 The work, as detailed in the PFCP, is accomplished in accordance with approved design documents;
NUCLEAR UNITS 1, 2 ANDGENERATION 3 SITE REVISipN9 ENGINEERING PROCE 6.0 TCN fr(s PAGE 11 0F 13 PROCE0jjRE (Continued) 6.2.19.1.2 Changes to the PFCP, including those that have an impact on safety question or Technical processed as a revision to the PFC volveSpecificati a
, shall be (see step 6.6)and undergo full review and appro 6.2.20 ementation Cognizant Station Engineer:
modifications. Follow the status of the design
.1 development file. of materialsn orto be entered e PFC Design
.2 When "Turnover" allofwork a "Z" associated with a PFC package is (per S0123-V-4.15), package has been accepted by Stationcomplete the Cogaizant Station Engineer shall receive the original of the PFC package Control. from Confi guration dating block 10 of the PFC form 26-294 and package t n designee.o the Cognizant Station Supervising ard the PFC Engineer :
(Certification of "Completion" excludes 6.2.21 considarations related to Configurationanges). Document Ch ;
Cognizant Station Supervising Engineer
, or Designee, shall work associated with the PFC. signonblock of all 10 of the g ., ,
6.2.22 the Supervisor, Configuration Control, or his dForward th esignee.
For it; formatio his designee) n Only: Supervisor, Configuration Control (o
.1 Configuration documents ance andwithprocedure e
Reference 2.2.4, sign Block 11 of the PFC form and forward the original PFCP to COM so attesting, Document Con 6.2.23 .
For Information Only:
.1 COM Document Control CDM/QA procedures. Process and file the PFC in accordanc\
pplicable I
NUCLEAR GENERATION SITE UNITS 1, 2 AND 3 ENGINEERING PROCEDURE S0123-V-4.14 ISI N PAGE 12 0F 13 6.0 PROCEDURE (Continued) 6.3 Review of Revisions to the PFC
~
6.3.1 If a PFCP revision is required, process as a new PFC in accordance with Section 6.2 and the following:
NOTES: 1. Revisions to PFCs shall be reviewed and processed in the same manner as original PFCs. Revisions shall be prepared in a way to entirely supersede all the previous PFC issues (revisions, addenda and CSEs).
- 2. Revisions shall be identified by sequential Arabic numerals assigned by the Supervisor, Configuration Control (or his designee). To ensure consistency of format, vertical lines in the right-hand margin, together with the appropriate revision number, indicating revisions to text shall be used.
.3 If a PFCP revision is not required, the originator shall note on Fora E0165 (E&C) or CC(123) 262 (NGS) and in a memorandum to the Supervisor, Configuration Control (or his designee).
7.0 RFIQRDI 7.1 All records identified herein are to be sent to CDM.
0330d.aut
NUCLEAR GENERATION SITE UNITS 1, 2 AND 3 ENGINEERING PROCEDURE S0123-V-4.14 REVISION 6 PAGE 13 0F 13 ACRONYMS ALARA - As low As Reasonable Achievable (related to radiation
-exposure of nuclear facility workers)
DCP - Design Change Package PFC - Proposed Facility Change PFCP - Proposed Facility Change Package b
0330d.aut . ATTACHMENT 1 PAGE 1 0F 1
\
s '
igrtagi,a g T .,! ,Li g _ ., g FCE C;dd W s% f;
/ L D'W
- 3 80. :55ua4CC ; Aft: MAR 2 91988.: Q C 45[ "O CANCILS Cn:
Q:r forwarees to t9e 'twelear Safety Or:wo. PERFCAP(D Bf: k /d 0 Aft: APR lb W
/
TICn9! CAL $7ECIFICATIC4 V!OLAT'!0N IF 40T CCe'PLETIo w!Th!N 14 oar $
Site Occupeat io. O / 7 N
- Y - N /kl tests?on No. (/ 5QE VSE rCN FE5 40 #
$ tte Cec.reat Title - ! ' 0' N b bib I Y b//h,[b
- 1. Pe(PARt3 BY: h/ AN/![I/NdIgtea(Cr 8AX: sob C :aaatzAr:0n: HCN -/ b TSER
- 2. 0Afl/I!PE $4lSliAIl0: N b d I
-). lf reou tred. ?Ci Oeviation Approval: APPROVIO ST:
CFOM (or cesignee) signaturer;f my telecon print nam ano so state seter nM 4 nut acoroortate son: , N ettre Ocewmeat attacPeo G Affected Page(s) Attached fuserseced/!acorporated C1(s): /C-T ~
so sit acae, so s ta te, het anolicanie for SiQt USC '3sl
- 5. fats enaage cannot east satti the aest rettston of the Site OccuMat and is reovfred:
A. To moleaeat f acility cesign cnange (PFC. MCR. iFw. etc.) RECElVED CDM ru i n , eesi,, coa.,e f.e,iiffer /
!aticate PFC TF
,denttfter MAR 291986
- m,ieMeistion f 0. 1Cx canon of t e .e fu,,in t, ,e.f ces,fe a roved.attite u e, ncyeCA.de.." etc.as .ee ,ete 0 Mfred. vci
- s. j:trer (e.g., Cn. =at sv.it.ents> ge enta,e nas nee 1 i-m se u iffc asai..: SITE FILE COPY A DD STEP &.2. S l.3 GEGNo!M & *s (mtrcH EcouzN ,
hfc M fNED TECH S MC MMSG (CAR Co - P- Md use ,everse s t.e. ir reo. ired,
- s. is t*e exo.eet seio, TCr. 0A Affxti.o us TO m vis, co.iaete t*e nous seio..) of =0. see tei .i (This 15 f adicated on the fatle of Contents paFof the7tte CoTmt. If not fndfcated, tres! as CA Affecting.)
i A. Oces this change af f ect F5AA or Tech. 50 ec. C orve t tsien t s ?
t I. TE5 40 -.
Does this CMange affect the acMreafologfesi eartroenent of any of fsite ares pr9tiously undisturoed durtag site DreDarition and plant ConstrwCtton? .
I C. !s the inte91 of IMe ortjinal doCvMet altered? vt$ 90 .
3 0. Yt$ 40 -t
!$ 1ie CoCVMet to be cR4Mged 49 (Megeacy Coerattng Instructfin? tt! No ~ ~-
i t. Oces 19f t change pose #9 unref fered Safet/ Question per Ifs CFR 50.$9. f.e.. dCes it 16 Crease tRe t 1
protantlf ty of occurreece or the conseoverces of an accisents create the pesstattitv of a stfferent i
accteest; or reduce the te.h. S&ac. margin of safety? rt$ to s t !!F f>C M5btR TO A. I. C. O or I !$ Yts. A TCM 15 407 Auf>0t!!!D.)
- 7. !"e entire focuMat was restewed in conjunctfon atta inf t TCM and found to te cceo 41e as artt.te9 ** ** 1 an annual /blerntal rettew of spolltfo4 of Mceptatie Al Written *(Atend 15012 ).
RCT!fb(0 M0 APPROVID IT: i 1
C@
.. S m r m s .cQur,,,, AM 181988 m un;m .
I mir.co ao memo n" !Ar trAsr c.c m s=0 ca n.t mr arcCrco, SITE FILE COPY l
)
n AW P13nt RenageWeet 5taf f . Valt i 4 3/ N/W m rzl $ t M Gate Ifme Flant Management 5taf" . Latts 24J 3/nkt /HR ;
I gate itse I
Cowld tif t IC4 affect or foes it regrese98 a Cpe to a plaat Could this ICM affect or does it Pearese9t a Cheage to i cceratio in y ss? ft1*" 40 % a pla9t coeration in prog ss? vis"* 90 F '
l 3)
Ms
\ \
wolt r u i NLif U INfe il //]dM ' } ~4 h h /O k I sete irse usa snitsClaJ / / g(te 1 ,
Times I
5IW apendAL l REV!!hfp
- APPt0V f:
h S/N/ W 41 w 6w s)% m/ t 9 oW
, 4. eivi ion ..e49er
..ie wam,u.me-vnu .t.... 4/f$.te
~ ; i f a doCvM*t is 90% 04 Af f ettt99. cDtain 19ttf al approval from the Cogettant 5voervisor(si on tae affectes vatt(s)
(stg9s Plant *aaagemeat $taff If at(s)) and flaal approval free tne Cf;M prfor to swbetttal to CM. 90 otPer sigaatisres are retytred.
- [f CA Af feCt tag, at;'9 vel shall be by o^e me8ter of the Plant "aasteme9% $taff a ACuleegeatle 14 (*e areas af f ectes, sad o*e 580 Uceased on tae valt or wafts affected. (for TCm approval. ' nesters of tae *f ant maaagement Staf f are cof f ned as tne suseritsor in caarge of tme snif t. or as ses tgasted ta .rttiag ty t*e CFM.
esercisteg ressoastellf ty in t*e spectf tc area sad waitis) asaressed by tee cmaage.)
"*!f 10,. the $ntf t Sweertateaceat small provise tae reestred 580 sooroval.
Pf(It)) 110 a[v. 1 02138 00617