ML053070326

Boric Acid Corrosion Control Procedure Rev. 0

ML053070326
Person / Time
Site:	Davis Besse
Issue date:	08/29/1991
From:	- No Known Affiliation
To:	Office of Nuclear Reactor Regulation
References
89-6877, 91-1849 NG-EN-00324 R00
Download: ML053070326 (19)

Text

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Released for Cornto EFFECTIVE RATE D B N P S

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LIST OF EWECTIVE, PAGES I

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1.0 2.0 I.!.1 f principal locat ions where n of the prhu5r;Y pressure bo bDric acid corrosion.

1. 1. 2 Procedures f o r locating smell coolant leaks, 1.1.3 Methods f o r conducting examinations and performing engineering evaluations t o e s t a b l i s h the impact on the reactor coolant pressure boundary when leakage is located.

1.l.L Corrective actions t o prevent recurrences of boric acid leaks.

1. 2 Deleted APPLICABltJfY/SCGPE 2-1 This procedure applies whenever a coolsnt leak is detected aapuhere may be in the farm ~f running or bripging uaker, boric acid Pesirfue.

nr discolpred [e.g,, rust stained) insulaticn.

bin the reactor coalant pressure boundary of the Plant-3he 2.1.1 Routine inspections fer coolant leaks s h a l l be conducted during the performance cf a c t i v i r i e s governed by the following procedures:

a.

DB-PF-03065. ASFIE Section X I Pressure Tests

b.

DB-OP-06901. Plant Startup c.

DE-OP-06903, Plant Shutdown and Cooldown.

2.1.2 coolant leaks OK evidence of coolant leaks-,mrty also be D B N P S

e doeis nQt require implementing procedures.

3,l 10 CFR 50.2, Code of Federal Regulation$, Title IO - Enetgy 3.3 Deleted 3.5 DB-PF-OOZ04, ASMJ3 Section X I Pressure Testing 3. 6 Deleted 3.7 DB-OP-WQOD.

Cpnduft of Operations 3.11 DB-OP-06803. Plant Shutdown and Cooldoid?

3-12 DB-MN-CKKKJl.

Conduct of Maintenance 3.13 DB-Q~-00007.

Control of Work nventary Bslanoe.

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BAOP-QDQM, Operuing bogs and Reading Sheets m%le 5.1 TKe person finditrg the coolant leak shall be rcspons e Shift Supemisor of the locetion and ma pewisor shall be respons4ble for:

s.2.1 Innforming S7~hema Engineering of the location and aagnktude of the leak.

UOlX: When thle leak is found du ASHE Section X I prtusurt ducting the pressure test for the nutification of s 5.2.2 DeternrEnlng Plant Shutdovn tequ rates and safety concerns repor Systems Engineering shall be responsible for:

5.3 m:

5.3.1 5.3.2 lhese actions may be completed.by Pe the Icak or evidence oE leakage fe n Section X I pressure t e a t and VT-2 vi on.

A ing and documenting the neceasa insptctj.on(s) of t h e DBNP S

6. 0 5. 3 - 5 Folvarding the inspection report sign Engineering and providing additional technical tn tion a s required.

5.4 Design Engineering shall be responsible the following:

5. 4. 1 Assessing the i n f o r m regarding the coolant data (e.g., NUREG$ and EPRS pub a.

Determine the extent ~f damage incurred by the affected

b.

Perform any neeesaary stress and corrosion calculations for determining axtent of degradation tc t h e aEfecLed pressure boundary.

c.

Determine immediate andlor long term correctfve actions t o stop the leak and prevent recurrence of boric a c i d corrosion.

PROCEDURE 6. 1 Principal Leak Locations 6.1.1 A l l areas and components within primary system pressure boundaries are capable of developing leaks.

when checking f o r leaks. it is important to know the principal locations where they are most l i k e l y t o cause dcgtsdatloa of the pressure boundary by boric acid corrosion.

The following locations i n primary systems have been identified as the most probable locations of le aka ge :

However, 8.

Steam Generator and Pressurizer manuays and handholes h.

Seal Welds c.

Thermowells d.

Reactor Coolant Pump seals and casing flanger:

e.

Control Rod Drive flanges f.

g.

Valves bhnn h.

The Reactor Vessel head Piping flanges and bolted connections D B N P S

a.

DB-PF-03065, ASHE

b.

DE-OP-06901 P h Z t C.

DB-OP-06903 p Plant D B N P S

Kontinued on page loa) 6.2.5 leak s are detected 2

t i O R Reactor Coolant Ron c a.

Inform the S h i f t Supervisor of the location and magnitude of the leak or residua.

n i n i t i a l inspection of a d areas and stems Engineering of the of the leak or rtsidue.

6.3 Exaapinkt io0 and Ekaluatian 6.3.1 Upon n o t i f i c a t i a n of boric a c i d build up in the Plsnt.

Systcprs Engineering shall perform un initial inspect ion of the affected area. i f not already performed, t o deterurine the "as foynd' conditions and documenting the results using drawings. photqgrapho, or other aids a s pristc.

Steps with a **' should be performed becwae they a s s i s t i n determining i f a boric acid corroetan concern e x i s t s.

The remaining steps help identify the scope of the problem.

a.

The t o t a l amount of boron deposits and the amount of boron os1 each component should be estimated.

This m a y be t o identify the build-up as a light f i l m or an estimate of the weight andlor volume.

Coordinate with BADCON before collecting any boron samples i f t h i s is determined t o be appropriate.*

b.

The area of the identified boron build-,up should be inspected to verify t h a t t h e boron is localized t o the identified area.

This eh@uld include a verificarfon that 8 boron build-up is not located e t an elevation above or below t h e identified area or on other near-by components.

A l l components with a boron build-up should be identified.

The area should also be inspected t o determine i f boric acid could have entered the internals of a cmposlent or the inside of insulation and spread internally to a location that is not v i s i b l e and i s susceptible t o boric ac4d corros D B N P S

6.3-1 i chnt fnuad 1 d.

affected compo tea to dete e.

temperatures near 20 leakage e x i s t s. Und f.

The temperature of the affected components shouId be determined for both,existing conditions and for other conditions that the compon subjected to.

As an @xa identified during 8 hydr during refueling and the component cool but during paver operation subjected to high tempetaCul'es.

Actual temperatures m y be nerLsuted using instrumentation or a contact pyrome Temperatures may be et; readings or vendor ixformtion.

g.

The concentration of the boric acid solution in the system should be determine conditivns and for other c may be subjected. This i s by a review of Chtmfstry L DBNP S

6.3.2 System Engineering shall notify the S h i f t Supervisor ef sny imediata safety concerns raised by the i n i t i a l inspectfon.

6. 3. 3 Based on the magnitude of the leak and extent rf damage d 8x811, Systems Engineering shall document tz by one of the foilowirlg:

a.

Writing a Potential Condition Adverse t o Quality

{PCAQ) Report per NG-QA-00702, Potential Condition Adverse to Quality Reporting

b.

Yrfting a Work Request per DB-PN-QOCW7. Control of Work.

6.5.;

If boric acid residue A S present, Systeims Engineeting s h a l l contact RadioP~gical Controls f e r :leanup of the affected area.

6.3.5 Systems Engineering shall determine whether follw-up or more 8

detailed inspe,ctions o f t h e leak are riecessary ta f u l l y B S S P G ~ I ~ ~

component dame&? and determine possible corrective action.

NOTE :

If the magnitude of the leak or the extent of the companent damage i s extreme. Systems Engineering may confer with Design Engineering before takinp further aetion.

a.

If a detailed inspection is deemed necessary. t h e n Systems Ewineering shall perform the foilowing as required :

1.

Write service requests or work requests per DB-PN-00107, Control of Work. as necessary for the removal of snp insulation, scaffolding.

cables, or any other type of interference which prevents access t o the leak.

2.

Perform subsequent inspections of t h e affected eomponent(s) a s neccssarv and include t h e results with the i n i t i a l inspection.

These inspections should include:

a )

A detailed description of v i s i b l e damage t o the affected area.

description should inc Lud itting or materiel. wa oslon i s present, the D B N P S

b)

Pictures of the c )

Ldcntific e )

DetemLnRtion of the leak rate, i f f f Determining be zoot c a w e of the if a PCAQ W B S generated in step 6. 3. 3, then:

fitems Engineering shall giaeering v i a the PCAq ditlonal system technic a s necessary tQ assess the leak.

2.

Asses6 the extent vf component damage.

3.

Determine the component wall degradation rate.

the Technical Library, contain reference material for determin acid corrosion rates:

Boundary Components in PWRs D B N P S

4.

5.

i f IC-l Determine t repair or c continued s OEt I

a.

Reduce IC-1 locatio corrosi

6.

s documented as a PCAQ, d as an HWO, i t shall t as i n DB-PN-00007, D B N P S

TERMS ID 01J041 D B N P S