ML20203E340
| ML20203E340 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 10/19/1995 |
| From: | Schmitt C SOUTHERN CALIFORNIA EDISON CO. |
| To: | |
| Shared Package | |
| ML19317C790 | List:
|
| References | |
| SO123-V-8.15, NUDOCS 9712170026 | |
| Download: ML20203E340 (9) | |
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RerEReNCE: 30123 W14,1 Submmel No.' M bI prapprecable) h$hhg y[. EDITORIAL. CORRECTION (S) (EC) rw u- use cuer:
seeuence o ne c 199N ^
f4T 1 . Ec No, peRementosY; -
>[ h oATe 0CL.191995 1, Document No - 50(7_3-V-B.P3 R. vision No,' I cocument Tme Mod 6 A Bo/(c Aod Lenk Irisoccffon i oocument Author / Originator MG( d OMl k DMT Peshiom TYPE reene, PAA
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- 2. Check approprime base d EnWee document ensched L.) Affected page(s) enached Superseded / Incorporated EC(e)/ICN(e) _ A Id ' (Not acclicable forslople use TcNs) en. worn fr None so s'am TECHNICAL CHANGES ARE tigT ALLOWED (e.g., changee to numerical data, setpointe, or neceptance ermeele, implementing 9 NRC nommamente, changing levels of approvel). For technical changes (or a combine 6cn of technical changes and ednorial correctone) use the re f ielen (SO123.W1) or TCN (So123 Vl 1.0.1) procese.
- CAUTION To be use6er EDITORIAL CORRECT.ONs (ECs) cNLY; ensure occument correctone are covered by hamle) listed in 3, below ',sCe 19,.3g1 change the intent of a document and de not require Safety Evaluation consideration (Lo., uee of fe,n PF(123) 1001, Unroviewed safety Overtion (10CFR50.5e) screening Criteria and/or a tud (7 questiorQ 50.50 Safete Evaluation would not be neesenary)
- 3. Allowed types of Editorial Coires'cnw, r are; e - Updating a spectfled tool to an equivalent or better substitute, o Correcting obvious equipment ioentifier or location errors (e g., correcting 2TSH-8960 to 2TSH 8961 when the procedure section was etwiously Written for 2TSH-8961; an approved document modifies annunciator window phrasing, etc.),
e Correcting misnumbered steps / sections (paragraph numbering) or step references (referencing one step to
. another step),
, o Correcting spel!!ng, punctuation, and typographics.) errors. ( Do not change numerical da:a, setpoints, or acceptance crtterta, use the revision [SO123-VI-1) or TCN [SO123-VI 1.0.1) process.)
- Dividmg large multiple action steps into several smaller steps which accomplish the same goal,
@ Updating names, phone numbers, document format, procedure numbers, distribution lists, or referenc ::,
4 e . Updating personnel titles (without changing the level of apprwaf).
-e Clarifying wording in a step to enhance understanding (changing the meaning / result of the step is not allowed).
-e Updating obsolete material codos (verified in an approved document or SOMMS).
o Reordering steps out of sequence, For example:
6,1 Install cover. RECElVED COM 6.2 Use RTV to seal cwer, Obviously the RTV should be app 6ed to the cover before installing the cover, 00T 191995
- 4. PREPARED BY: /&v DATE y b REVIEWED AND ,
APPROVED BY: -
DATe iO \ t') \q( '
sovicom -
- 3. - (Opponal) The entire document was reviewed in conjunction with this EC and found to be seeeptable es wrieen. This constHute, an erinuat! biennial review disposhion of Acceptable As Written Extend (SO123-W1.02),
REVIEWED and APPROVED BY:
cQQNGarn DVe.;TIOPtAL DYSON mar AGER cn des 4NEZ DATR tL - ForNFTs mfd M W Aogged en Gornputer systern.
Pf m*ostME0 3Y: OCF 1 91995-
_ CE Petita it). 8tm o a/Sise asucuA,4 h MsGsouppeg i jj) DATg e
9712170026 971212 PDR ADOCK 05000361 p PDRe
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t, ./ - 4 TNUCLEAR ORGANIZATION-. .
NSSS ENGINEERING' PROCEDURE S0123-V-8.15'-
LUNITS 1,.2 AND 3 REVISION 1 PAGE 1 0F 8 '
_ EFFECTIVE.0 ATE , TCN/EC /-/ -
MODE 3 B0 hic ACID LEAK INSPECTION-
. TABLE OF CONTENTS ~
SECTION~ pyg 1.0 OBJECTIVE 2 2.01. REFERENCES 3.0 . PREREQUISITES- 3 ,
4.0;-PRECAUTION (S) 3
'5.0' CHECKLIST (S) '3-
-6.0 PROCEDURE- 3 6.1 Applicability . '6.2 General Information 4
, 6.3 Classification and Documentation of Boric Acid Leaks 6
=7.0- RECORDS 7 ATTACHMENTS-
- 1. ' Rationale for Not Performing Boric Acid Walkdown 8 t-l.
L i
lV 8-15T1.W51 NOT QA PROGRAM AFFECTING L
A
NUCLEAR ORGANIZATION NSSS ENGINEERING PROCEDURE S0123-V 8.15 R
= UNITS'1.-2 AND 3- REVISION 1 PAGE2.0f8 TCN/EC I ,/ l
, MODE 3 BORIC ACID LEAK'INSPECTIQN :
- 1.0 .: 0BJECTIVE' l.1 Visually ' inspect the' containment for new and previously identified' .,
boric acid leakage-and equipment condition during any Mode 3 Plant condition.
2.0 REFERENCES
2.1: - NRC Commitment 2.1.1 - - Generic Letter 8805, response from'M. O. Medford to the NRC, dated May 31, 1988 2.2 Procedure 2.2.1 S0123-XV 5, Nonconforming Material, Parts or Components ,
2.2.2 S0123-1-1.7, Maintenance Order Preparation and Processing .
2.3. .qther 2.3.1 Form S0(2/3) 1259-15, Radiation and Contamination Survey Plot Plan Unit 2-Containment - Elevation 63' 6" 2.3.2 Form S0(2/3) 1259-16, Radiation and Contamination Survey Plot-Plan Unit 2 Containment - Elevation 45.0' 2.3.3 Form S0(2/3) 1259 17, Radiation and Contamination Survey Plot Plan Unit 2 Containment - Elevation 30' O'-
2.3.4 Form SO(2/3) 1259-18, Radiation and Contamination Survey Plot Plan Unit 2 Containment - Elevation 17' 6" 2.3.5 Form S0(2/3) 1259-33, Radiation and Contamination Survey Plot Plan Unit 3 Containment Elevation 30.0' 2.3.6 Form 50(2/3) 1259-34,- Radiation and Contamination Survey
. Plot Plan Unit 3 Containment - Elevation 45.0' 2.3.7 Form S0(2/3) 1259-35, Radiation and Contamination Survey Plot Plan Unit 3 Containment -' Elevation 63' 6"
> 2.3.8 - Form SO(2/3) 1259-36, Radiation and Contamination Survey Plot Plan Unit 3 Containment - Elevation 17'- 6"
-~2..3 9 fnrm HP(l)--259-1, Radiation and Contamination Survey P1ot Plan, Unit 1 Containment,.10' Elevation
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- 2.3.10 - Form HP(l).259-2, Radiation and Contamination Survey Plot Plan, Unit 1 Containment,14' Elevation +
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NUCLEAR ORGANIZATION! -NSSS ENGINEERING PROCEDURE S0123 V-8.15- "
< UNITS 1,;2.AND REVISION 1 PAGE 3 0F 8 TCN/EC_1-/ .
/ v
2.0 REFERENCES
(Continued). ,
_2.3.11 : Form HP(l) 259 3,-Radiation and Contamination Survey Plot- ,
Plan, Unit 1 Containment, 22f Elevation -i 2.3.12 form HP(l) 259-4,--Radiation and Contamination Survey Plot !
Plan, Unit 1 Containment, 31' Elevation-
~2.3.13- Form'HP(l) 259-5, Radiation and Contamination Survey Plot-Plan, Unit 1 Containment, 42' Elevation 3.0 PRERE0VISITES--
3.1_Before usire, this. document, verify the revision and any issued TCNs '
and/or ECs (Editorial Corrections) are current by using one of the 1 following methods:
3.1.1 Access the San Onofre Document-Management System (SDMS)=
[ San Onofre local area network (SLAN) or online system)
(preferredmethods), l' 3.1.2 Check it against_a Corporate Documentation Management-SONGS (CDH-SONGS) controlled copy and any issued TCNs/ECs. l 3.1.3 Contact CDM-SONGS by telephone or throtgh counter inquiry.
3.1.4 - Obtain a user-controlled copy of this procedure from COM-SONGS or SONS SLAN.
3.2 Reactor Coolant System is at Normal Operating Temperature and Pressure
. (Mode 3). This procedure may be used for leak. inspections in other-L_
modes at the discretion of the NSSS Supervising Engineer.
3.3 Containment is open for inspection.
- 4.0 PRECAUT10NfS) 4.1 None
. 5.0 MECKLISI(S)
! - 5.1 None
-- 6.0 PROCEDURE i
6.1 : Applicability
-6.1.1 ~ Perform the Boric Acid leak inspection if both of the-following criteria are met:
.1 The containment is accessible and the Reactor Coolant -
. System (RCS) is at Normal Operating Temperature _and Pressure _(NOTP).
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- NUCLEAR' ORGANIZATION-: NSSS ENGINEERING PROCEDUREL S0123i V -8.15-
. UNITS 1, 2:AND 3- - REVISION l' PAGE 4 0F
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- TCN/EC/ h 8-6.1.1.2 The planned outage will: result in the Unit being 'in !
Mode 3, 4 or 5 for more than four (4) days,
+
NOTE: TheSupervisingEngineer,NSSS,ordesignee,may-l:
authorize the performance of-an inspection under: i other conditions, if necessary. l 6.1.2 A Boric Acid leak inspection 11.HQI mandatory if one or i more of the following criteria are met: ;
.1 The Unit has operated for '30 days or less~ since the.-last !
outage in which a Boric Acid leak inspection was ,
performed.
.2 The duration of Mode 3, 4'or 5~is expected to be four (4 days or less, and the RCS leak rate trend ~ is normal and ).
there have been ao unaccountable increases since the last containment inspection.
.2.1 For example, leak rates attributable to U2/3 charging pump [
packing leakage would not warrant a containment inspection, given that no other potential RCS leak problems may necessitate-a limited inspection.
.3 The Lead Engineer shall obtain Management concurrence NOT to eerform the Boric Acid leak inspection and document the rationale by completing Attachment 1, and submit to CDN-SONGS.
6.2 General Infnrmation.
NOTE:- During normal working hours, the Supervising Engineer, NSSS or designee from the NSSS l Mechanical or NSSS Nuclear Systems Groups should perform the " Lead l Engineer" function designated below. During off-hours, the Duty Division Technical Supervising Engineer, or designee, l should perform the MLead Engineer" function designated below.
-6.2.1 The Lead Engineer is responsible for coordinating the walkdown of the affected unit containment and notifying participating; organizations of the scheduled date and time of-the walkdown including pre-planning meetings, and ~
changes-to dates and times. -Unit I walkdowns should be
-coordinated with Operations and Reference 2.2.2.
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' NUCLEAR ORGANIZATION- -NSSS ENGINEERING PROCEDURE 50123 V-8.15
- UNITS 1,(2 AND-3 REVISION 1 PAGE 5 0: 6 TCN/EC 1-1
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- 6.2.1.1 The inspection party normally will be comprised of- l l Technical Engineer (s), Health Physics -Technician (s), Plant .
s Equipment Operator (s), Rad Material Control (RMC) '
representative (s), and Maintenance Planner (s). Membership of the inspection party may be modified at the discretion of the lead Engineer.
.2 All personnel participating in the walkdown of the containment shall be experienced with NSSS containment ,
piping systems and components.
.3 If leakage from a system has been identified during the operating cycle-prior to unit shutdown, the assigned Lead Engineer may request that the-System Engineer perform the
, walkdown of his/her system. ;
6.2.2 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 and Maintenance Planner may meet prior to the walkdown to review previous inspection reports l (obtained from CDM-SONGS) and a listing of open Boric Acid 1eak maintenance orders (obtained from Maintenance Planning). Piping plans and Health Physics survey forms (Ref. 2.3.1, et. al.) may be used to help locate components and plan inspections.
NOTE: Previous inspection reports are also filed with the NSSS/ Mechanical, RCS System Engineers in the Boric Acid Walkdown Binder.
The Lead Engineer will identify components which have been
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determined to have chronic, recurrent leaks. Components previously identified as having dry boric acid leaks will be listed with current Maintenance Orders (MOs). These components will be reinspected to verify that the work plan in the M0 remains appropriate and that the condition of the component has not degraded.
.3 The Lead Engineer will assemble the-inspection team, assign walkdown areas to the team members and discuss inspection requirements to ensure specific components are reinspected based on review of data.
6.2.3 The physical walkdown of the containment may be performed in one of two ways at the discretion of the Lead Engineer:
.1 Using the Group approach, all members of the inspection party walkdown the containment as one group.
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' NUCLEAR ORGANIZATION NSSS ENGINEERING PROCEDURE -S0123 V-8.15
- ~ UNITS 1, 2 AND 3: -REVISION.1 PAGE 6 0F 8
, TCN/EC-l-l 6.2.3.1.1 The Maintenance Planner, or designec, is responsible for. >
Jrecording the equipment' data'.
- .l.2- The Lead-Engineer or System Engineer evaluates and. .
documents the condition of the affected components or !
equipment. Photographs may be taken by the' Engineer as needed.- i
.l.3 The Assistant Control Operator will assist in locating system components. .
.l.4- The Rad Material Control representative will be responsible for developing a plan for cleaning affected.
components and surrounding areas to facilitate further i inspection or repair.
.2 Using the Team Member approach, each member of the inspection party is assigned to a team which walks down a portion of the containment assigned to ; hem. Each team is -
responsible for recording equipment data, evaluating and documenting the condition of the com>onent or equipment affected. Photographs may be taken )y tne individual teams as needed. -
'6.3 Classificatinn and Documentatinn nf Rnric Acid leaks NOTE: Documentation and evaluation of the Boric Acid leak inspection, including the required items specified in Ste)s 6.3.1 through 6.3.2.2.6 will be provided via E-Mail with a hardcopy attached to this procedure and submitted to CDM-SONGS.
6.3.1 The inspection team will inspect components and identify evidence of leakage. Boric acid leaks will be classified as follows:
.1 Ec1 leaks which exhibit active water leakage, or
.2 Qry leaks which exhibit dry boric acid deposits with no evidence of active water leakage.
6.3.2 Depending on the leak classification, the inspection team will-inspect the components as follows:
.1- ' Wet-Leak - the primary objective of the wet leak inspection is to quantify the leakage and evaluate component degradation and the effect of the leakage on
-surrounding components.
..l.1 Record the component / equipment I.D. number, 4' .l.2 -Record the-location (i.e., elevation, inside/outside -
bioshield),-
d -i
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NUCLEAR ORGANIZATION NSSS ENGINEERING PROCEDURE S0123 V-8.15- !
UNITS _-1. 2.AND 3 - REVISION 1- PAGE 7 0: 4 l
-TCN/EC -f l r -
6.3.2.1.3i Estimate the amount _of leakage,
. l' 4 Identify the source of the leak (bonnet, packing--and-whether the packing can still be adjusted,--flange, etc.),
1
.l.5 - Evaluate-if the leakage has degraded.the component or if it will adversely affect any other component.
.l.6 Optionally, document the leakage and equipment condition >
by a clearly labeled photograph.
.2 Dry leak - the objective of-the dry leak Inspection is to -
quantify the amount of accumulated dry boric acid crystals and evaluate the effect of the crystals on the components-or surrounding areas.
.2.1 Record the component / equipment I.D. number,
.2.2 Record the location (i.e., elevation, inside/outside bioshield),
.2.3 Estimate the amount of accumulated boric acid crystals and their locaticn, ,
. 2. 4 ~ Identify the apparent source of_ the leak that produced the crystals,
.2.5 Evaluate the effect of the crystals on the component involved or the other affected components in the vicinity.
L .2.6 Optionally, document the leakage and equipment condition by a clearly labeled photograph.
7.0 RECORDS 7.1 The Lead Engineer is responsible for ensuring inspection reports are completed by team members to record inspection data required by section 6.3.2.
7.2 Upon completion of the walkdown, the. Lead Engineer will coilect the inspection reports from team members, The Lead Engineer will prepare
- an E-Mail documenting the inspection results from each team, and j' forward the E-Mail to the Maintenance Planner as well as other
, affected organizations (e.g., OPS, RMC, HP, STEC, I&C, etc.).
7.2.1: A copy of the E-Mail shall be attached to this procedure when completed and forwarded to COM-SONGS.
(. 7.3 The _ Lead Engineer shall prepare NCRs if required per Reference 2.2.1.
L 7.4 The Lead Engineer shall generate Mos to correct identified leaks and L to implement the NCR dispositions, as required.
55 haw:V-8 15T1.W51 l .
NUCLEAR ORGANIZATION NSSS ENGINEERING PROCEDURE 50123 V-8.15 UNITS 1, 2 AND 3 REVISION 1 PAGE 8 0F 8 ATTACHMENT'l TCN/EC 1l RATIONALE FOR NOT PERFORMING BORIC ACJ9 WALKDOWN
[ circle applicable number (s)) UNIT: 1 / 2 / 3 '
DATE:
How was Unit removed from service?
Reason for not~ completing Boric Acid Walkdown:
4 COMPLETED BY:
APPROYED BY:
V-8-15T1.W51 ATTACHMENT 1 PAGE 1 0F 1
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