ML20203E364

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Rev 0 to S013-V-8.16, RCS Inconel Nozzle Insp
ML20203E364
Person / Time
Site: San Onofre  Southern California Edison icon.png
Issue date: 06/07/1993
From: Reeser K
SOUTHERN CALIFORNIA EDISON CO.
To:
Shared Package
ML19317C790 List:
References
SO23-V-8.16, NUDOCS 9712170037
Download: ML20203E364 (50)
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NUCLEAR ORGANIZATION ENGINEERING PROCEDURE -5023 V 8.16 i

' ~

UNITS 2 AND 3 REVISION 0. PAGE 1 0F 46~

i EFFECTIVE DATE mRN( o 7 199.5 REACTOR COOLANT SYSTEM INCONEL N02ZLE INSPECTION-IABLEOFCONTENTS Itfil103 RECEIVED CDM PEE 1.0 OBJECTIVE ij(g4 0 71993 2

2.0 REFERENCES

- $11E flLE COPY 2 ,

3.0 PREREQUISITES 2 4.0 PRECAUTIONS 3 5.0 CHECKLIST (S) 3 6.0 PROCEDURE 3 6.1 General Inspection Criteria 3 6.2 General Information 4 6.3 Classification and Documentation of Inconel Nozzle Leaks 5 7.0 RECORDS 6 ATTACHMENTS 1 Reactor Coolant Loop Piping. Nozzles Unit 2 7 2 Steam Generator Nozzles Unit 2 11 1

3 Pressurizer Nozzles Unit 2 13 4 Reactor Head CEDM/ICI Nozzles Unit 2 15 5 Reactor Coolant Loop Piping Nozzlos Unit 3 21 6 Steam Generator Nozzles Unit 3 25 7 Pressurizer Nozzles Unit 3 27 8 Reactor Head CEDM/ICl Nozzles Unit 3 29 9 Inspection Sketches 35 10 Developmental- Resources 46 J

V8 16RO W51 NOT QA PROGRAM AFFECTING s

NUCLEAR ORGAN 17AT10N ENGINEERING PROCEDURE S023-V 8.16

. UNITS 2 AND 3 REVISION O PAGE 2 0F 46 REACTOR COOLANT SYSTEM INC0NEL N0ZZLE INSPECTION 1.0 OBJECTIVIS.

1.1 lo provide for a visual inspection and documentation of the Reactor Coolant System Inconel 600 instrument nozzles to detect possible leaks (and resultant carbon steel degradation) caused by Primary Water Stress Corrosion Cracking (PWSCC).

1.2 The results of this inspection will become the basis for changes made by NEDO to the Inconel susceptibility evaluation and replacement plan, document 90022. This document defines the inspection and replacement program for Inconel at SONGS.

2.0 REFERENCES

2.1 E Correspondenra 2.1.1 Generic Letter 68-05, " Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR Plants",

March 17, 1988 2.1.2 IE Bulletin 82-02, " Degradation of Threaded Fasteners in Reactor Coolant Pressure Boundary of PWR Plants, June 2, 1982 2.1.3 Information Notice 80-27, " Degradation of Reactor Coolant Pump Studs", June 11, 1980 2.1.4 Information Notice 86-108, " Degradation of Reactor Coolant i System Pressure Boundary Resulting from Boric Acid Corrosion", December 29, 1986; Supplement 1, April 20, 1987; Supplement 2, November 19, 1987 2.2 Procedure 2.2.1 S0123-VI-0.9, " Author's Guide for the Preparation of Orders, Procedures and Instructions" 2.2.2 S0123-XV-5, " Nonconforming Material, Parts or Components" 2.2.3 50123-V-8.15, " Mode 3 Boric Acid Leak inspection" 2.3 Mditional Criteria 2.3.1 90022, " Susceptibility of Reactor Coolant System Alloy 600 Nezzles to Primary Water Stress Corrosion Cracking Replacement Program Plan" (when issued) 3.0 PRERE0VISITES 3.1 Prior to use of a user-controlled copy of this document, it is the user's responsibility to verify the revision and any TCNs are current by using one of the following methods:

NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023 V-8.16 UN!TS 2 AND 3 REVISION O PAGE 3 0F 46 l 3.0 pRERE0VISITES (Continued) 3.1.1 Access the San Onofre Document Management System (SDMS)

(San Onofre loca area network (SLAN) or online system]

(preferred methods),

3.1.2 Check it against a Corporate Documentation Management-SONGS (CDM SONGS) controlled copy and any TCNs.

3.1.3 Contact CDM SONGS by telephone or through counter inquiry.

3.1.4 Obtain a user controlled copy of this procedure from CDH-SONGS or SDMS SLAN.

3.2 The inspections shall be performed under the following conditions:

3.2.1 The Unit is being removed from service for planned refueling activities.

3.2.2 An attempt is being made to identify RCS leakage when the areas under inspection are accessible.

3.3 The inspection can be performed while the RCS pressure is maintained at nominal operating pressure or at refueling conditions.

3.4 Containment is open for inspection.

3.5 Inconel nozzles inspections are to be performed as soon in the outage as possible to allow for proper planning for emergent issues.

I 4.0 ERECAUTIONS 4.1 Personnel performing the inspections should review the current radiation and contaminatinn surveys with the Health Physics Department prior to inspection to limit their exposure.

5.0 [HECKLISTfS),

5.1 None 6.0 PROCEDURE 6.1 General Inspectign Criteria 6.1.1 Reference 2.3.1 provides the criteria and guidance for inspecting inconel 600 nozzles in the RCS. Based on this guidance, this inspection will identify the following:

.1 Anticipated leaking nozzla. Based on Reference 2.3.1, the nozzles that are anticipated to be leaking (high susceptibility) will h'.ve plans in place for replacement prior to the start of .he outage.

NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023 V 8.16 l . UNITS 2 AND 3 REVISION O PAGE 4 0F 46 6.0 PROCEDURE (Continued)-

6.1.1.2 Unanticipated leaking nozzles. Contingency plans have been conceptualized to temporarily repair a nozzle that is found to be leaking but not identified as high susceptibility by Reference 2.3.1.

.3 The need to update or modify Reference 2 3.1 as a result of the previous 2 criterion. The replacement plan may need to be accelerated or decelerated based on the inspection results.

b 6.2 General Inferration 6.2.1 It is the responsibility of Station Techni nl to ensure 4 the required inspections are performed. Any deficiencies discovered durtug the inspection are to be reported to NEDO.

NOTE: During normal working hours, the Supervising Engineer, NSSS, or designee from the NSSS Mechanical group, NSSS Nuclear grou), or NEDO Nuc/ Mech group should perform the " Lead Engineer" function designated below. Dortrg off-hours, the Duty Division Technical Supervising Engineer, or designee, should )erform the " Lead Engineer" function designated aelow.

I 6.2.2 The Lead Engineer is ressonsible for coordinating the walkdown inspection of tie inconel nozzles and notifying participating organizations of the scheduled date and time of the walkdown including pre planning meetings, and changes to dates and times.

.1 The inspection party normally will be comprised of Station Technical Engineer (s), !!calth Physics Technician (s), and System Design Engineer (s). Membership nf the inspection

) arty may be modified at the discretion of the Lead Engineer.

.2 All personnel partici)ating in the walkdown of the containment shall be (nowledgeable of NSSS containment piping systems and components.

6.2.3 The inspection will be pre planned so the containment walkdown of the affected unit is performed in a systematic, thorough manner. The lead Engineer acts as the " lead" individual for the walkdown and pre-planning activity, and will assign actions required as a result of the walkdown.

.1 The lead Engineer will identify nozzles identifiec in 90022 which have been determined to be most susceptible to PWSCC Tailure.

NUCLEAR ORGANIZATION ENGINEERING PROCEDURE 5023 V 8.16

> . UNITS 2 AND 3 REVISION O PAGE S OF 46 6.0 f20CEDVRE (Continued)

NOTE: The prerequisites and classification definitions contained within the i in body of this procedure are needed when perforuing the Attachments.

Therefore, each team must maintain a copy of the main body while performing the inspection.

6.2.3.2 Land Engineer shall assign each member of the inspection party to a team which shall walk down a portion of the containment assigned to them. Each tetm is responsible for recording equi 3 ment data, evaluating and documenting i the condition of t1e component or equipment affected Phctographs may be' taken by the individual teims as needed.

6.3 Classification and Docunzatation of inconel Nozzle lenki NOTE: 1) The inspection team will inspect nozzles and identify evidence of leakage. The inspeccion determination wili be classified as defined below.

2) Any correlation between the nozzle identifiers used in this procedure and ISI identifiers is purely coincidental.

6.3.1 Pressurizer Nozziel I

.1 Category 1: No Deficiency. No evidence of boric acid, rust stains or any other indeterminate nbservation.

.2 Category 2: Evidence of Rust Stair.1 which have been seen as indicators of leaking pressurizer nozzles. Note:

Absence of boric acid does not net.essarily indicate no nozzle leakage. Evidence of rust stains on the base material will require further evaluation.

.3 Category 3: Evidence of white crystals which are usually indicative of Boric Acid leakage. If boric acid is found on or around the inconel nozzle, it shall be analyzed by Chemistry to determine whether the leak is active. Active leaks shall be replaced or repaired.

.4 Category 4: Any 01 hat abnormalities or unusual visual indications which require further evaluation. The station (

NSSS supervisor shall be responsible for disposition of any category 4 indications.

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<e NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023.V 8.16 UNITS 2 AND 3 REVISION O PAGE 6 0F 46

6.0' PROCEDURE (Continued) 6.3.2 Reactor Head CEDM/ICl Norries NOTEi The Reactor Head will have boric acid present as -

a result of past refueling outage activities.

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Due to the difficulty of head access below the-

. reflective insulation, any boric acid from these past activities has not been removed.

.1 Category 1: No deficiencv. No evidence of surface irregularities.

.2 Evidence of reactor head surface irregularities in the annular reginn around the CEDM/ICI nozzle.

.2.1 Category 2: Carbon steel wastaae with accompanying boric acid crystals. This may be indicative of a nozzle leak.

The boric acid may be analyzed by Chemistry to determine whether the leak is active.

.2.2 Category 3: 01her surf ace irregularities. This may be the result of previous outage activities. An engineering evaluation shall be performed to determine the impact to the structural integrity of the head.

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6.3.3 Any indication or, discrepant condition shall be documented in Section 4 of the applicable Attachment of this '

i procedure, and photographs taken.

6.3.4 All NCRs issued will be recorded in Section 4.2 of the applicable Attachment of this procedure.

7.0 RECORDS 7.1 The Lead Engineer is responsible for ensuring all appropriate Attachments are completed by team members to record inspection data required by section 6.3.1.-

7.2 Upon completion of the walkdown the Lead Engineer will collect the completed Attachments and photos.from team members. The Lead Engineer will retain the original Attachments.

-7.3 The Lead Engineer shall prepare NCRs if required per Reference-2.2.1.

7.4- The Lead Engineer shall generate M0s to have Chemistry analyze any discrepant condition identified in steps 6.3.1 and 6.3.2.

7.5- Results of Chemistry analysis shall be documented on the applicable Attachment of this procedure.

7.6 All completed Attachments shall be transmitted to CDM-SONGS.

KReeser:V8-16RO.W51

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NUCLEAR ORGANIZAT'ON- ENGINEERING PROCEDURE- 5023 V 8.16 UNITS 2 AND 3 REVISION 0 PAGE 7 0F 46-ATTACHMENT l ,

REACTOR COOLANT LOOP PIPING UNIT 2

. MODE- DATE RCS-Press . psia TIME L

1.0 INSPECTION GUIDELINES 1.1 This inspection should determine the condition of each RCS nozzle-listed. The following category (s) (defined in Section.

' 6.3) should be used:

1 - No deficiency exists 2 - Boric Acid Buildup 3' Rust stains. 4 - Other (to be described)

'2.0 ' PROCEDURE. ,

NOTE: The following nozzles as identified in Attachment 9 are .

accessible. The nozzle insulation removable plug (to be installed during the cycle 7 refueling outage) may need to be removed prior to nozzle inspection.

2.1 RCS PIPING: HOT LEG - STEAM GENERATOR E089 TO REACTOR VESSEL (FIG.

9.1) i PERF. BY HQ111,1 1DENTIFIER [ATEGORY INITIALS l-L 2.1.1 012 2TE-0112 3 2.1.2 .013 2PDT 0978-4 2.1.3 014 2TE-Oll2-4 2.1.4 015 2TE-OlllXI .

2.1.5 016 2PDT-0978-1 2.1.6 017 2TE-Oll2-2

(_ 2.1.7 018 2PDT 0978-2

~2.1.8 019- 2TE-Oll2-1 2.1.9 020 52 1201-ML-023 ,

2.1.10 02) 2PDT-0978-3 2.I'.11 022 2TW-0138A ATTACHMENT 1 PAGE 1 0F 4

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NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023 V-8.16 UNITS 2 AND 3 REVISION O PAGE 8 0F 46 I ATTACHMENT 1 REACTOR (Q0(ANT LOOP PIPING UNIT ?

2.1 RCS PIPING: HOT LEG STEAM GENERATOR E089 TO REACTOR VESSEL (FIG.

9.1) (Continued)

PERF. BY iiQIRI IDENTIFlf,8 CATEGORY INITI Alji 2.1.12 023 2TW 0138B 2.1.13 024 2TW-0138C 2.1.14 025 2TW 0138D 2.1.15 026 2TW-0138E 2.1.16 027 2TW 0138F 2.2 RCS PIPING: HOT LEG - STEAM GENERATOR E088 TO REACTOR VESSEL (FIG.

9.2)

PERF. BY

[10llLI IDENTIFIER CATEGORY INITIALS 2.2.1 010 2TE-0122-2 2.2.2 011 2PD1-0979 2.2.3 012 2TE 0122-1 2.2 4 013 2TE-0121X2 i 2.2.5 014 2PDT-0979-4 2.2.6 015 2PDT-0979-2 2.2.7 016 2TE-0122-3 2.2.8 017 2PDT-0979-1 2.2.9 018 S2-1201-ML-065 2.2.10 019 21E-0122-4 2.2.11 020 2TW-0139A 2.2.12 021 21W 0139B 2.2.13 022 21W-0139C 2.2.14 023 2TW-0139D 2.2.15 024 2TW 0139E 2.2.16 025 2TW-0139F ATTACHMENT I PAGE 2 0F 4

NUCLEAR ORGANIZATION ' ENGINEERING PROCEDURE S023 V 8.16-

- - 1; NITS 2 AND 3 REVISION.0 PAGE 9 0F 46 ATTACHMENT 1 -4 i'

REACTOR COOLANT LOOP PIPING UNIT _2 2.3 .RCS PIPING: COLD LEG - RCP P001JTO REACTOR VESSEL (FIG._9.3)

PERF. BY HQ2211 . IDENTIFIER CATEGORY INITIALS 4

2.3.1 015 2TE 9178 3 2.3.2 016- 2TE-0111Y1 .

2.3.3 017 2TE-9178 1 1

2.4 RCS PIPING: COLD LEG - RCP P003 TO REACTOR VESSEL (FIG 9.4)

PERF, BY N0ZZLE 111ENTIFIER LAIIGQB1 INITIALS 2.4.1 013 2TE-9178-2 2.4.2 014 2TE-0115 2 2.4.3 015 2TE-9178 4 2.5 RCS PIPING: COLD LEG RCP P004 TO REACTOR VESSEL (FIG. 9.5)

PERF. BY i N0ZZLE IDENTIFIER CATEGORY INITIALS .

2.5.1 013 2TE-9179-1 __

2.5.2 014 2TE-0125-1 2.5.3 015 2TE-9179-3 2.6 RCS PIPING: COLD LEG - RCP P002 TO REACTOR VESSEL (FIG. 9.6)

PERF. BY IRITIALS HQllLE IDENTIFIER [ATEGORY 2.6.1 011 2TE-9179 2 4

2.6.2 012 2TE-0121Y2 1!.6.3 013 2TE-9179-4 ATTACHMENT 1 PAGE 3 0F 4

NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023 V 8.16 UNITS 2 AND 3 REVISION 0 'PAGE 10 0F 46 ATTACHMENT 1 l REACTOR C00L' ANT LOOP PIPING UNIT 2 ,

3'. 0 ACCEPTANCE 'CRITERIAL ' PERF. BY *

- INITIALS- i 3.1 Chemistry shall verify any category 2, 3 or 4 inspections results' to -  ;

verify the leakage is from the inspected nozzle.  ;

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RESULTS OF CHEMISTRY ANALYSIS:-  ;

3.2 NCRs have been initiated for all identified deficiencies in this Attachment (list the associated step number-below).

J COMMENTS: i t

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8 NUCLEAR ORGANIZATION  : ENGINEERING PROCEDURE- S023 V-8.16 UNITS 2.AND 3 . REVISION 0- PAGE 11 OF 46 ATTI)'HMENT 2-STEAM GENERATOR UNIT 2 ,

MODE DATE

~ RCS Press psia TIME-1.0, INSPECTION GUIDELINES ,

1.1 This inspection should determine the condition of each RCS nozzle listed. The following category (s) (defined-in Section _

6.3) should be used:

l'- No deficiency exists 2 - Boric Acid Buildup 3'- Rust stains- 4 - Other (to be described) 2.0 PROCEDURE N0'i:' The following nozzles as identified in Attachment 9 are.

accessible. The nozzle insulation removable plug (to be

' . installed during the cycle 7 refueling outage) may need to be retoved prior to nozzle inspection, 9

2.1 STEAM GENERATOR E089 (FIG. 9.7)

PERF. BY i

NQllLE IDENTIFIER [8TEGORY INITIALS ,

2.1.1 023 2PDT-0978-1 2.1.2 024 2PDT-0978-2 2.1.3 025 2PDT-0978-3 _ _ _ ,

2.1.4 026 2 POT-0978-4

-2.2 STEAM GENERATOR E088 (FIG. 9.8)

PERF. BY N0ZZLE IDENTIFIER CATEGORY INITIALS 2.2.1 023 2PDT-0979-1 2.2.2 - 024 2PDT-0979-2

-2.2.3 025= :2PDT-0979-3 2.2.4- 026 2PDT-0979-4 ATTACHMENT 2 PAGE 1 0F 2

- . . . . . . . _ - _ _ . . ~ _ - _ .

. NUCLEAR ORGANIZATION: -ENGIliEERING PROCEDURE S023 V-8.16-UNITS 2 AND.3 REVISION 0- PAGE 12 0F 46

ATTACHMENT =2 STEAM CENERATOR UNIT 2 3.0. ACCEPTANCE CRITERIA PERF. BY INITIALS 3.1 Chemistry shall verify any category 2, 3 or 4-inspections results to 1 verify the leakage is from the inspected nozzle.

RESULTS OF CHEMISTRY ANALYSIS:

3.2 NCRs have been initiated for all . identified deficiencies in this Attachment (list the associated step number below).

COMMENTS: i W 9 J

s

-ATTACHMENT 2 PAGE 2 0F 2

NUCLEAR ORGANIZAll0N ENGINEERING PROCEDURE S023 V 8.16 UNITS 2 AND 3 CEVIS!ON O PAGE 13 0F 46 ATTACHMENT 3 1%LSIMRl2ER UNIT 2 H0DE DATE RCS Press psia TIME _ __

1.0 INSPECi10N GVillLGIES 1.1 This inspection should determine the condition of each RCS nozzle listed. The following category (s) (defined in Section 6.3) should be used:

1 No deficiency exists 2 - Boric Acid Buildup 3 . Rust stains 4 - Other (to be described) 2.0 1100.LDuftl NOTE: The following nozzles as identified in Attachment 9 are accessible. The nozzle insulation removable plug (to be installed during the cycle 7 refueling outage) may need to be removed prior to nozzle inspection.

2.1 PRESSURIZER INS 1RUMENT N0ZZLES (FIG. 9.9) p g HQllLL IDENilFILB . CATEGORY INiilALS 2.1.1 020 52-1201 ML 316 - 1 2.1.2 021 52 1201 ML 315 2.1.3 022 2TE 0101 ~.-

2.1.4 023 52 1201-AL-313 -

2.1.5 024 52-1201 ML-311 -

2.1.6 025 52 1201 ML-314 2.1.7 026 52 1201 ML 312 2.2 PRESSURIZER HEATER SLEEVES 2.2.1 Document below any deficiencies of the heater sleeves using the same characterization guideline: specified in step 1.1.

Identify the affected heater sleev6 'iv locatien relative to the 2 bottom head instrument nozzler ile, hemisphere, row, ano number of heaters from the side the instrument nozzles are located).

A11ACHMENT 3 PAGE 1 0F 2

i NUCLEAR ORGANilA110N ENGlHEERING PROCEDURE 5023 V 8.16 4 W 11$ 2 AND 3 REVISION O PAGE 14 Of 46 l ATTACHMENT 3 ERLMURIZER UNIT 2 3.0 &(SEPTANCE CR11ERla PERF. BY IN111ALS 3.1 Cherolstry shall verify any category 2, 3 or 4 inspections results to verify the leakage is from the inspected nozzle.

RESULTS OF CHEMISTRY ANAL.YSIS:

3.2 NCRs have been initiated for all. identified deficiencies in this Attachment (list the associated step number below).

~

COMMLNTS:

I

_ _ . _ _ _ \

ATTACHMENT 3 PAGE 2 0F 2 s;

i.

5023 V 8.16 't NUCLEAR ORGAW'ZATION ENGINEERING PROCEDURE '

l UN115 2 AND 3 REVISION O PAGE 15 0F 46 ATTACHMENT 4 REACTOR llEAD C[DM/ICI N0ZZLES UNIT 2  ;

MODE DATE _

RCS Press psia TIME . _ , _ .

1.0 INSPECil0N GU10EllNES 1.1 This inspection should determine the condition of each RCS nozzle listed. The following cod 7(s) should be used:

1 No Deficiency 2 + Carbon Steel Wastage 3 Other 2.0 j$QCIDE[

NOTE: The following nozzles (as identified in Fig. 9.10 of Attachment

9) will require insulation removal to provide access for visual inspection. 100% inspection may not be required. For the norries not inspected, write N/A in the code column, and initial step.

PERF. BY N0ZZLE 10ENilflER cal [LQM ' 1RillALS 2.1 9/ ICI I

2.2 93 101 .___,

2.3 94 101 ,

2.4 95 101 2.5 96 101 2.6 97 101 2.7 98 101 2.8 99 1C1 2,9 100 101 2.10 101 101 .

2.11 1 CEDM 2.12 2 CEDH .____

2.13 3 CEDM ___

ATTACHNENT 4 PAGE 1 0F 6 4

_ _ . _ _ _ . _ _ _ . _ _ . . ~ . _ . _ . _ _ _

r j

. i I

NUCLEAR ORGANIZAll0N ENGINEERING PROCEDURE 5023 V 8.16

  • UN115 2 AND 3 REV1510N 0 PAGE 16 Of 46 i ATTACHMENT 4 i EE10R HEAD CEDM/ICl N0ZZLES UNIT 2 1

~PERF. BY  :

N0ZZLE IDENilFIER (AIGQM INITIALS i

2.14 4 CEDM

-2.15 5 -CEDM 2.16 6 CEDM ,

2.17 7 CEDM _

t 2.18 8 -CEDM 2.19 9 CEDM 2.20 10- CEDM 2.21 11 CEDM 2.22 12 CEDM ,

2.23 13 CEDM 2.24 14 CEDM 2.25 15 CEDM 1

, 2.26 16 CEDM ,.

2.27 17 CEDM j 2.28 18 CEDM [

2.29 19 CEDM 2.30 20 CEDM 2.31 21 CEDM -

1 2.32 22 CEDM 2.33 23 CEDM 2,34 24 CEDM t 2.35 25 CEDM.  !

2.36 26 CEDM 2.37 27 CEDM i

'2.38- 28 CEDM ATTACHMENT 4 PAGE 2 0F 6 6

L ,

l i l

_- T -

NUCLEAR ORGAN!ZAll0N ENGINEERING PROCEDURE 5023.V.S.16 -

. LEIT5 2 AND 3 REVISION 0- PAGE 17 0F 46 I ATTACHMENT 4 ,

REACTOR HEAD CEDM/ICI N0ZZlES UNIT 2  ;

t PERF. BY EQZ11I IDLE (Ll[8 (1110.QRY INITIALS 2.39 29 CEDM r

2.40 30 CEDM  :

-2.41 31 CEDM

-f 2.42 32 CEDM l 2.43 33 CEDM _  !

2.44 34 CEDM

2.45 35 CEDM 2.46 36 CEDM 2.47 37 CEDM 2.48 38 CEDM* ,

2.49 39 CEDM 2.50 40 CEDM

.I 2.51 41 CEDM 2.52 42 CEDM 2.53 43 CEDM

! 2.54 44 CEOM 2.55 45 CEDM 2.56 46 CE0M 2.57 47 CEDM 2.58 48 CEDM 2.59 49 CEDM- ,

2.60 50 CEDM .

3 2.61 51- CEDM-

~

2.62 - 52 CEDM ATTACHMENT 4 PAGE 3 0F 6

)

9"-ri'- r* 9 'twc-Tr-y--avwesF -'* *yWe wtewmy'vy-e =(re - wi W-MM ev--w*gr 4 's v w y 'W' r'='-4 TW 4+y (w*4='Jww-'W~3yW+W "vt -*r"-'WWw=-t'*ty v

-*T-"' ' *-M'F^'

7 NUCLEAR ORGANIZA110N ENGINEERING PROCEDURE -S023 V 8.16 UNii5 2 AND 3 REVISION 0 PAGE 18 0F 46- -

j

-ATTACHMENT 4 REACTOR HEAD __GEDN/ICI N0ZZLES UNIT 2  !

PERF. BY N0ZZLE IDENilFIER CATEGORY INITIALS  :

2.63 53 CEDM i 2.64 54 CEDM

{

2.65 55 CEDM  !

2.66 56 CEDM j 2.67 57 CEDM  ;

2.68 58 CEDM ~

2.69 59 CEDM ,

2.70 60 , CEDM 2.71 61 CEDM j t

, 2.72 62 CEDM 2.73 63 CEDM l I

2.74 64 CEDM l

2.75 65 CEDM l 2.76 66 CEDM 2.77 67 CEDM ,

i 2.78 68 CEDM -

2.79 69 CEDM 2.80 70 CEDM -

2.81 -71 CEDM ,

2.82 72 CEDM

-2.83 73 CEDM i

=2.84 74- CEDM- ,

, 2.85- 75 CEDM 2.85 76 CEDM, -

ATTACHMENT 4 PAGE 4 0F 6 l

(

l l

NUCLEAR ORGANllA110N ENGINEERING PROCEDURE 5023 V 8.16  !

UN!15 2 AND 3 REVISION O PAGE 19 0F 46 -  ;

ATTACHMENT 4 R SCTOR HEAD.CEDM/ICI N0Z2LES UNIT 2 PERF. BY- i N0ZZl( 10fNilflER CATECORY INITIALS {

2.87 77 CEDM  :

2.88 78 CEDM t

- 2.89 79 CEDM l

- 2.90 80 CEDM  :

I 2.91: 81 CEDM _ .,

t

~

2.92 82 CEDM 2.93 83 CEDM 2.94 84 CEDM  :

' 2.95 85 CEDM i 2.96 86 CEDM 2.97 87 CEDM l 2.98 88 CEDM I

2.99 89 CEDM 2.100 90 CEDM ,

t 2.101 91 CEDM s

3.0- ACCEPTANCE CRITERM PERf. BY '

INITIALS

' 3.1 Chemistry shall verify any category 2 inspection results to verify the leakage is from the inspected nozzle.

l RESULTS Of CHEMISTRY ANALYSIS: ,,_

i l

l

- ATTACHMENT 4 PAGE 5 Of 6 4

va- - - - -,<

-T-TW=-y--'F *- -

_- _ . . _ _ _ _ . _ m._ _ _ . _ _ . _ . _ _ _ _ . _ . , _ _ _ _ _ _ . -

t t

i NUCLEAR ORGANIZATION ENGINEERING PROCEDURE 5023 V 8.16 '

= UNITS 2 AND 3 REVISION O PAGE 20 0F 46-ATTACHMENT 4 ,

j

'f REACT 0lLHEAD CEDM/ICl N0ZZLES UNIT 2 .

3.0 PERF. BY  !

ACCEPTANCE CRITERIA (Continued) I INITIALS 3.2. NCRs have been initiated for all identified .

. deficiencies in this Attachment (list'the associated i step number below).  ;

I CotNENTS:- i I

f b

i 4

1 4 e

6 I

.I s

Y

  • 1 6

1 1

l l

l~

ATTACHMENT 4 PAGE 6 0F 6-I 4 *h

NUCLf.AR ORGANilATION ENGINEERING PROCEDURE 5023 V 8.16 ,

UNITS 2 AND 3 REVISION O PAGE 21 0F 46  :

ATTACMENT 5 ,

REACTOR 000LANT LOOP PIPING UNIT 3 MODE ._..- DATE RCS Press .__ psia TIME  !

1.0 INSPEC110N GU10ELINES l 1.1 This inspection should determine the condition of tich RCS I nozzlelisted.Thefollowingcategory(s)(definedin Section 6.3) should be used:

3 1 No deficiency exists 2 Boric Acid Butidup 3 Rust stains 4 Other (to be described) 2.0 120C[QUEE NOTE: The following nozzles as identified in Attachment 9 are .

accessible. The nozzle insulation removable plug (to be installed during the cycle 7 refueling outage) may need to i be removed prior to nozzle inspection.

2.1 RCS PIPING: HOT LEG STEAM GENERATOR E089 TO REACTOR VESSEL (flG.

9.1) 1 PERF. BY ,

HQllLE IDENTIFIER CATEGORY INITIALS 2.1.1 012 3TE Oll2-2 i l

2.1.2 013 3PDT 0978-3 2.1.3 014 NONE .._

2.1.4 015 3TE 0111X1 ,

2.1.5 016 3PDT 0978-2 2.1.6 017 3TE 0112-3 .

2.1.7 018 3PDT 0978 1 -

2.1.8 019- 3TE Oll2-4 2.1.9 '020 53 1201 NL 023 2,1,10 021 3PDT 0978 4 2.1.11 022 31W 0138A

-ATTACHMENT 5 PAGE 1 0F 4

, . _ _ . _ _ _ . _l

l NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023 V 8.16 i UNITS 2 AND 3- REVISION 0 PAGE 22 0F 46 .  !

. ATTACMENT 5 REACTOR COOLANT LOOP PIPING UNIT 3 i PERF. BY N0ZZLE 1DENTIFIER CATEGORY INITIALS ,

2.1.12 023 3TW 01388  !

, 2.1.13 024 3TW 0138C l 3 2.1.14 025 3TW 01380 l

. 2.1.15 026 3TW 0138E l 2.1.16 027 3TW 0138F .

l 2.2 RCS PIPING: HOT LEG STEAM GENERATOR E088 TO REACTOR VESSEL (FIG.  !

' .9.2)

PERF. BY  !

N0ZZLE ]DENTIFIER CATEGORY INITIALS  :

2.2.1 010 3TE 0122-3 f 2.2.2 011 3PDT 0979 2

l. 2.2.3 012 3TE 0122 4 [

2.2.4 013 3TE 0121X2 [

t 2.2,5 014 3PDT 0979 1  ;

4 2.2.6 015 3PDT-0979 3 2.2.7 016 3TE 0122 2 .

1 2.2.8 017 3PDT 0979 4 2.2.9 018 S3-1201-NL 065 2.2.10 019 3TE 0122 1 ,

2.2.11 020 3TW 0139A 2.2.12 021 3TW 01398 2.2.13 022 3TW 01390

.2.2.14 023 3TW 01390  ;

2.2.15 024 3TW 0139E 2.2.16 025 3TW 0139F i

.ATTACllMENT 5 PAGE 2 0F 4 j i

. . ~ - -. -.. - - . - - . - . - _ . = . . . ~ . - . . -_ -.--.:. . - - - -

NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023 V 8.16  !

. UN11S 2 AND 3 REVISION O PAGE 23 0F 46 i

-ATTACHMENT 5 REACTOR COOLANT LOOP PIPING UNIT 3 i 2.3 -RCS PIP!NG: COLD LEG RCP P001 TO REACTOR VESSEL (FIG. 9.3) i FERF. BY  !

N0ZZLE _IDEN11FIER CATEGORY INITIALS 2.3.1 015 31E 9178 1  ;

2.3.2 016- 31E OlllYl- ,

2.3.3 017 3TE 9178 3 2.4 RCS PIPING: COLD LEG RCP P003 TO REACTOR VESSEL (FIG. 9.4)  ;

PERF. BY HQ11LE IDENTIFIEB CATEGORY INITIALS 2.4.1 013 3TE-9178 4 a

2.4.2. 014- 3TE-0115 2 ,

2.4.3 015 3TE 9178 2 2.5 RCS PIPING: COLO LFG -RCP P004 TO REACTOR VESSEL (FlG. 9.5)

PERF. BY N0ZZLE IDENTIFIER (ATEGORY INITIALS I

2.5.1 . 013 3TE 9179 3 2.5.2 014 3TE 0125 1 2.5.3 015 31E 9179 1 2.6 RCS PIPING: COLD LEG - RCP P002 TO REACTOR VESSEL (FIG. 9.6)

PERF. BY N0ZZLE IDENTIFIER CATEGORY INITIALS 2.6.1 011 31E 9179 4 2.6.2- 012 3TE 0121Y2 2.6.3 013 31E 9179 2 ,

ATTACHMENT 5 -PAGE 3 0F 4 J

7

,--nwe -

'n -

i NUCLEAR ORGANilATION ENGINEERING PROCEDURE 5023.V ti.16 UNils ! AND 3 REVISION 0 PAGE 24 0F 46 '

ATTACIMENT 5 RE4CTOR COOLANT LOOP PIPING UNIT 3 3.0 ACCEPTANCE CRiiERIA PERF. BY lh1HALS  !

l 3.! . Chemistry shall verify any category 2, 3 or 4 inspections results to .  ;

verify the leakage is from the inspected nozzle.  ;

i RESUL15 0F CHEMISTRY ANALYSIS: {

i 3

i i

3.2 NCRs have been initiated for all identified deficiencies i in this Attachment (list _the associated step number  ;

below).  ;

! COMMENTS: ,

I >

t 8

7 I

t ATTACHMENT 5 PAGE 4 0F 4 3

m . . , . e. ~.r , - - . -r w'-o . * - - , . - - - - . - - *---- , +--.,-~..-<----m--a.ii -

-w'~

.. . . . - - . ~ . - . . .

NUCLfAR 0RGANIZATION ENGINEERING PROCEDORE 5023 V 8.16  !

UNITS 2 7.M0 3 REVISION O PAGE 25 0F 46 ATTACHMENT 6 .

STEAM GENERATORS UNIT 3 MODE DATE t

RCS Press psia TIME 1.0 INSPECTION GUIDELINES +

1.1 This inspection should determine the condition of eat.h RCS norrie' listed. The following category (s) (defined in Section i 6.3) should be used:

1 + No deficiency exists 2 .

Boric Acid Buildup 3 Rust stains 4-Other(tobedescribed) 2.0 EBQCLQURL NOTE: The following nozzles as identified in Attachment 9 are accessible. The nozzle. insulation removable lug (to be installed during the cycle 7 refueling outage may need to be. i removed prior to nozzlo inspection.

2.1 STEAMGENERATORE089(FIG.9.7)

PERF. 8Y N0ZZLE IDENTIFIEB CATEGOU INITIALS 2.1.1 023 3PDT-0978 1 -

2.1.2 024 3PDT-0978 2 2.1.3 025 3PDT-0978 3 2.1.4 026 3PDT-0978 4 2.2 STEAM GENERATOR E088 (FIG. 9.8)

PERF. BY N0ZZLE EENilFIER CATEGORY INITIALS -

2.2.1 023 -3PDT-0979 1 ,

2.2.2 024 3PDT 0979 2 2.2.3 025 3PDT-0979 3 2.2.4- 026- 3PDT 0979 4 E ATTACHMENT 6 PAGE 1 0F 2

[ p.

' i i

NUCLLAN C?.GANIZAT 0N ENGINEERING PROCEDU.' 5023 V-8.16 i UNITS 2 AND 3 REVISION 0 . PAGE 26 0F 46' ATTACHHENT 6 ,

l STEAM GENERATORS UNIT 3 3.0 &CLEPTANCE CRITERIA . PERF. BY INiilALS  ;

3.1 Chemistry shall verify any category 2, 3 or 4 inspections results to  !

verify the leakage is from the inspected nozzle.  !

RESULTS Of CilEMISTRY ANALYSIS: ,

1

~

3.2 NCRs have been initiated for all identified deficiencies '

in this Attachment (list the. associated step number

below).

COMMENTS: _ _

I i

t i

a

).

n ATTACHMENT 6 PAGE 2 Of 2 a

t

.f '

i

- -.- .--,-v.m..,. ...,m[m, .,e--y,m---- ..w-e,--.. . . , - ., v.-.sa,w,...,.<...#,v1.w.,5---,.>yv

.-- -.-r%---,.--.---.E#, .-.-,.u-.e,- w r,,,,.. -wr-,w,

NUCLEAR ORCANIZATION ENGINEERING PRDCEDURE 5023 Vo8.16 UNITS'2 AND 3 REVISION O PAGE 27 0F 46  !

ATTACHMENT 7  :

PRESSURIZER UNIT 3

= MODE .. _ _- DATE j RCS Press psia TIME _  !

1.0 INSPEC110N Gul0ELINES 1.1 This inspection should determine the condition of each RCS nozzlelisted.Thefollowingcategory(s)(definedinSection 6.3) should ta ased:

1 - No deficiency exists 2 Boric Acid Buildup 3 - Rust stains 4-Other(tobedescribed) i 2.0 PROCEDURE

' NOTE: The following nozzles as identified in Attachment 9 are  ;

- accessible. -The nozzle insulation-removable plug (to be installedduringthecycle7refuelingoutage)mayneedtobe removed prior to nozzle inspection.

2.1 PRESSURilfRINSTRUMENTN0ZZLES(FIG.9.9)

PERF. BY I

EQIZLI IDENTIFILB CATEGORY INITIALS .

2.1.1 020 53 1201 ML 316 2.1.2 021 53 1201-ML-315 i

2.1.3 022 3TE-0101 2.1.4 023 53 1201-ML-313 2.1.5 024 S3 1201-ML 311 ,

2.1.6- 025 53 1201-ML 314 2,1.7 026 S3 1201-ML-312 ATTACHMENT 7 PAGE 1 0F 2 P

e h

I. 9 m,.

- . . . ~ . ---

,I  :

NUCLEAR ORGANIZATION ENGINEERING PROCEDURE 5023 V 8.16  ! '

UN115 2 AND 3 REVISION 0 PAGE 28 Of 46 ATTACHMENT 7  !

i PRESSURIZER UNIT 3 2.2 PRESSURIZER HEATER SLEEVES 2.2.1 Document below any deficiencies of the heater sleeves using the same characterization guidelines specified in step 1.1.  ;

, Identify the affected heater sleeve by location relative to  :

the 2 bottom head instrument nozzles (ie. hemisphere row.  !

and number of heaters frne the side the instrument nozzles i arelocated). ,

s 3.0 BCCEPTANCECRITERIA 1 3.1 Chemistry shall verify any category 2, 3 or 4-inspections results to verify the leakage is from the inspected nozzle.

RESULTS Of CHEM!$TRY ANALYSIS' i

l l

i 3.2 NCRs have been initiated for all l'dentified deficiencies in this- I Attachment (listtheassociatedstepnumberbelow).

COMMENTS:  ;

I t

w

. ATTACHMENT 7 PACE 2 0F 2 4

s i

NUCLEAR ORGANilATION ENGINEERING PROCEDURE 5023 V 8.16 UNil5 2 $NO 3 . REVISION 0 PAGE 29 0F 46 ATTAC MENT 8 -

. . j REACTOR HEAD CEDN/III N0Z2LES UNIT 3 MODE DATE f psia -  !

RCS Press. TIME 1.0 INSPECTION GUIDELINES i 1.1 This inspection should determine the condition of each RCS .

nozzle listed. The following code (s) should be used: l 1 No Deficiency 2 Carbon Steel Wastage 3 Other l

2.0 ERQtEDURE NOTE: The following nozzles (as identified in Fig. 9.10 of Attachment .

9) will require insulation removal to provide access for visual  !

inspection. 100% inspection may not be required. For the '

nozzles not inspected, write N/A in the code column, and initial step. ,

PERF. BY N0ZZLE IDENTIFIER CATEGORY JNITIALS I

2.1 92 101 .

2.2 93 101 2.3 94 101 4

2.4 f 95 101 i 2.5 96 101 -!

2.6. 97 101 ,

2.7 98 101 2.8 99 101 2.9 100 101 ,

-2.10 101 101 4 2.11- 1 CEDM 2.12 2 CEDM .,_._ i ATTACHMENT 8 PAGE 1 0F 6 ,

4

NUCLEAR ORGANIZATION ENSINEERING PROCEDURE S023 V 8.16 UNITS 2 AND 3 REVISION O PAGE 30 Of 46 ATTACHMENT 8 ,

REACTOR HEAD CEOM/ICI N0Z2LES UNIT'3 PERF. 8Y hall 11 10ENilflE9 CATEGORY INITIALS 2.13 3 CEDM 2.14 4 CEDM 2.15 5 CEDM 2.16 6 CEDM 2.17 7 CEDM 2.18 8 CEDM __

2.19 9 CEDM 2.20 10 CEDM 2.21 11 CEDM -

2.22 12 CEDM .

2.23 13 CEDM 2.24 14 CEDM i

2.25 15 CEDM _ _ _ _

2.26 16 CEDM 2.27 17 CEDM 2.28 18 CEDM i

2.29 19 CEDM 2.30 20 CEDM -

2.31 21 CEDM __

2.32 22 CEDM ,

2.33 23 CEDM 2.34 24 CEDM 2.35 25 CEDM 2.36 26 CEDM l

ATTACHMENT 8 PAGE 2 Of 6 l

6 l .

1

NUCLEAR ORGAN!ZAll0N ENGINEERlWG PROCEDURE 5023 V 8.16 UN115 2 AND 3 REVISIDN O PAGE 31 0F 46 ATTACHMENT 8 REACTOR HEAD EEDM/lCI N0ZZLES UNIT 3 PERf. 8Y EQ1Z11 IDENilFl[R (ATEGORY INiilAlb 2.37 27 CEDM 2.38 28 CEDM 2.39 29 CEDM 2.40 30 CEDM 2.41 31 CEDM 2.42 32 CEDM . _ . _ _

2.43 33 CEDM 2.44 34 CEDM 2.45 35 CEDM 2.46 36 CEDM 2.47 37 CEDM 2.48 38 CEDM i

2.49 39 CEDM _

2.50 40 CEDM 2.51 41 CEDM 2.52 42 CEDM Z.53 43 CEDM 2.54 44 CEDM 2.55 45 CEDM 2.56 46 CEDM 2.57 47 CEDM 2.58 48 CEDM 2.59 49 CEDM 2.60 50 CEDM 2.61 51 CEDM ATTACHMEi!T 8 PAGE 3 Of 6

,,- w

5023.V.8.16 NUCLEAR ORGANIZATION ENGINEERING PROCEDURE- ,

UNITS 2 AND 3 REVISION O PAGE 32 0F 46-ATTACHMENT 8 l

REACTOR HEAD CEDM/ICI N0ZZLES UNIT 3 .  !

~

I PERF. BY N0ZZLE IQENTIFl[R (.ATEGORY INITIALS' ,

2.62 52 CEDM .

4 2.63 5'l CEDM 2.64 54 CEDM ,

2.65 55 CEDM 2.66 56 CEDM t 2.67 57 CEDM 2.68 58 'CEDM 2.69 59 CEDM 2.70 60 CEDM ,

2.71 61 CEDM 4

2.72 62 CEDM -

2.73 63 CfDM I .

2.74 64 CEDM 2.75 65 CEDM ,

2.76 66 CEDM i 2.77 67 rEDH ,

2.78 68 CEDM

, 2.79 69 CEDM 2.80 70 CEDM 2.81 71 CEDM 2.82 72 CEDM  !

2.83 ~73 CEDM ,

t 2.84 74 CEDM

ATTACllMENE 8 PAGE 4 0F 6 i

- T.d, . , . ,- - , ' . . ~ . . .--,,.~..1 . - _ _ ~ . _ . . . . . , . . _ , . . . . ~

NUCLEAR OkGANIZATION ENGINEERING PROCEDURE 5023.V 8.16 <

. UNITS 2 AND 3 REVISION O PAGE 33 0F 46 ATTACHMENT 8 REACTOR HELD Ef0M/ICI N0ZZLES UNIT 3 PERF, BY N0Z2t( IDENTIFILB CAILE011 INITIALS 2.87 77 CEDM

?.88 78 Ct0M 2.29 79 Cf0M 2.90 80 CEDM 2.91 81 CEDM ___

2.92 82 CEDM 2.93 83 CEDM 2.94 84 CEDM .

2.95 85 CEDM 2.96 86 CEDM 2.97 87 CEOM 2.98 88 LEDM i

2.99 89 CEDM 2.100 90 CEDM 2.101 91 CEDM 3.0 6(CEPTANCE CRITERIA 3.1 Chemistry may verify any categery 2 inspection results to verify the leakage is from the inspectod nozzle.

RESULTS OF CHEMISTRY ANALYSIS: . .

m e um mmp i

m ATTACHMENT 8 PAGE 5 0F 6

-M

l ENGINEERING PROCEDURE $023 V.8.16  :

NUCL?AR ORGANIZATION '

UN!15 2 AND 3 REVISION 0 PAGE 34 0F 46 ATTACHNENT 8 i REACTOR HEAD CEON/lCI N0Z2LES UNIT A.

j-PERF BY l INITIALS  !

t 3.2 NCRs have been initiated for all identified deficiencies in this Attachment (list the associated -l stepnumberbelow). v i

CONMENTS:  ;

t h

i l

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l I

4 k

f l

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5 4 Y i

ATTACHMENT 8 PAGE 6 Of 6 l

i 6

.L. ,..--_.--..__u.-._-__.,a_.-_.-.a.u...__..--.-.._.._......~.. _ _ ~ _ , _ . . . - _ ~ . .. . - - . . , _ . ~ . . . - . - - . _ . _ , -

~ . _ - . . _ . . _ _ . _ _ _ . _ _ _ _ _ _ . _ _ . _ . _ . _ _ . _ - . . _ _ - . _ . - . _

NUCL EAR ORGANIZA110N - ENGINEERING PROCEDURE S023 V 8.16 i UNITS 2 AND 3 REVISION 0 PAGE 35 0F 46  ;

ATTACHMENT 9 j i

INSPECil0N SKETCHES  !

NOTE: lhe Figures are generic for both Units 2 and 3. The applicable Attachments are listed in parentheses for each Figure.

A. List of Figures  ;

9.1 HotLegfromSGE089toReactorVessel(Attachments 1and5) ,

9.2 Hot leg from SG E080 to Reactor Vessel (Attachments 1 and 5) ,

9.3 Cold Leg from RCP P001 to Reactor Vessel (Attachments 1 and 5) (

9.4 Cold Leg from RCP P003 to Reactor Vessel (Attachments 1 and 5) l 9.5 Cold Leg from RCP P004 to Reactor Vessel (Attachments 1 and b) l 9.6 ColdlegfromRCPP002toReactorVessel(Attachments 1and5) 9.7 Steam Generator E089 (Attac'nents 2 and 6) .

9.8 SteamGeneratorE088(Attachments 2and6) 9.9 Pressurizer (Attachments 3 and 7) 9.10 ReactorHead(Attachments 4,and8) ,

I t

i ATTACHMENT 9 PAGE 1 Of 11 1

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. , , . , ,-- ~ ~

d NUCLEAR ORGANIZAT!DN ENGINEERING PROCEDURE $023 V 8.16 UNITS 2 AND 3 REVISION O PAGE 36 0F 46 ATTACHMENT 9 ,

e22 612 i 416 i c '

89 p n 9 N i

% n  ? .. - >

I c aa s

[ }. s SECTION B-8 1 ~ '

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$15 _,. '

i 1423 : L .i3

'24 . eis

$17 02.1

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$26

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+

\J L tis T __

VIEW C-C M7 Hot Leg from SG E089 to Rx Vessel Figure 9.1 ATTACllMENT 9 PAGE 2 OF 11

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(S):SN010729.016:(E):

- Facility Change: MMP 1;7011.OOBC, Revision 0

. Title -

Sewage Treatment Plant Modifications -

Description This change mEditied the influent flow paths to allow all influents to be processed by either of the two sewage treatment plant trains. Prior to this modification each train of the -

sewage treatment plant received influent from different sources and could not be cross-connected. The old alignment often over burdened one train while the other train was

  • under utilized. This condition resulted in violations of the National Pollution Discharge Elimination System (NPDES) permit. The new design will equalize influent to each train.

This modification also allows one train to be removed from service for maintenance.

Safely Evaluation The sewage treatment system is a non-safety related system and it has no safety related >

design basis. It has not been included in any accident analysis in the safety analysis report. Therefore, the probability of occurrence of an accident, or malfunction of any equipment irnportant to safety previously evaluated in-the UFSAR will not increase as a result of this change. The possibility of either an accident or malfunction of a different type than previously evaluated in the UFSAR will not be created as a result of this change.

This change has no effect on either the existing Limiting Conditions for Operation or the Surveillance Requirements in the Technical Specifications; thus, the margin of safety as defined in the bases for the Technical, Specifications will not be reduced as a result of this change.

7

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