ML20059N029

Forwards Safety Evaluation Accepting Util Responses to Generic Ltr 88-01, NRC Position on IGSCC in BWR Austentic Stainless Steel Piping

ML20059N029
Person / Time
Site:	LaSalle
Issue date:	08/22/1990
From:	Pulsifer R Office of Nuclear Reactor Regulation
To:	Kovach T COMMONWEALTH EDISON CO.
Shared Package
ML20058K090	List: ML20058K086 ML20058K092 ML20058K136 ML20059N029 ML20059N030
References
GL-88-01, GL-88-1, TAC-69141, TAC-69142, NUDOCS 9010090045
Download: ML20059N029 (7)

Text

__ _ ,__

.c-August 22,'1990 Docket Nos. 50-373 N:-

and 50-374 . [j . _ a. 23 NRC & Local PDRs PDIII-2 r/f DCrutchfield JZwolinski RBarrett BPulsifer CMoore OGC-WF1 EJordan Mr. Thomas lJ. Kovach ACRS(10) PDIII-2 Gray Files Nuclear Licensing Manager CYCheng Comonwealth Edison Company-Suite 300 OPUS West III 1400 OPUS Place Downers Grove Illinois 60515

SUBJECT:

REVIEW OF RESPONSE TO GENERIC LETTER 88-01, "NRC POSITION ON IGSCC IN BWR AUSTENTIC STAINLESS STEEL PIPING," LASALLE COUNTY STATION, UNITS 1 AND 2 (TAC NOS. 69141 AND F3142)

The NRC staff has completed its review of LaSalle County Station Units I l and 2 in response to Generic Letter (GL) 88-01 A copy of the staff's Safety Evaluation (SE) and a copy of the Technical Evaluation Report prepared by the staff's contractor, Viking Systems International, are enclosed.

Based on' the Safety Evaluation, the staff finds your responses to GL 88-01 are acceptable'with some exceptions. You are requested to review these-exceptions and notify the staff of actions taken to address them. When tne Committee to Review Generic Requirements (CRGR) niet on this topic, they approved-TS to be incorporated by licensees. Thus, you are requested to

- propose amendments to your Technical Specifications (TS) to:

(1) Include a statement-in the surveillance or administrative controls section that includes the following: "The inservice inspection program for piping identified in NRC Generic Letter 88-01 shall be -)

performed in accordance with the NRC staff positions on schedule, .]

L methods, personnel, and sample expansion included in Generic .

1 L Letter 88-01 or in accordance with alternate measures approved by :I L

the NRC staff." ,

L -(2)' Include an additional Limiting Condition for Operation (LCO)Lthat specifies reactor coolant system leakage shall be limited to a 2 gpm l increase in unidentified leakage within any 24-hour period. j q

(3)' Include a surveillance requirement that primary containment sump 1 flow rate will be monitored at-least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. It should  ;

be noted that the position in GL 88-01_on leak rate monitoring was modified to permit leakage measurements based on sump flow instruments 1 to be-taken every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> instead of every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. 1 L (4) For LaSalle County-Station Unit 1, include an LCO on operability L of-sump' monitoring instruments. Since your plant has IGSCC weld-category E weldments, Generic Letter 88-01 provides an allowed-outage time of 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s-for repairing the drywell floor drain sump

() ? 2 3.7 \f f

' y ,g 9010090045 900322 DR ADOCK0500g3 0 y

c Le li i Mr. . Thomas J. Kovach .

~

monitoring-system,: or an orderly shutdown should be initiated. As ran alternative, the staff recommends that when the drywe'l sump moni- ,

toring system is inoperable, the operator should use a demonstrated manual method for. determining leak rate, such as measuring the time ,

to manually pump the-sump at a fixed interval (4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />). The staff l considers manual measurement a viable sump monitoring method without hardship to the operator; therefore, this method could be added to the  ;

-appropriate LCO section. With the manual method operable, the outage-time for the drywell- sump monitoring' system could be extended to 30 -

days. However, if the sump pump and drywell sum) monitoring systems t are inoperable concurrently, then either system 1as to be repaired within'24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or an orderly shutdown should be initiated.

Pertinent sections of the model BWR Technical Specifications are enclosed as ,

. examples of acceptable positions for items 2 and 3 above. Accordingly, please -

submit the requis_ite TS change requests or notify the staff of actions taken I' within 60 days.

Commonwealth Edison needs to address the RWCU piph.B ostboard of the isolation valves in the ISI. program. If the piping is withit & scope of GL 88-01,. l you will need to modify the program to include 99 identity of the welds as .

well as plans for' mitigation and inspection . A staimum of 10% of the RWCU l system piping outboard of the isolation valves shouM be inspected at each y refueling. outage. If cracks are found, the-lice n e should discuss sample i expansion and mitigation methods with the NRC staff.

i For.SE deficiencies'related to welds, categorization of welds, and qualifica-  ;

tion of personnel, these deficiencies shall be corrected in the :SI program. '

Since you previously submitted integrated IGSCC inspection plans, our safety evaluation precludes the necessity'for you to submit IGSCC.inspectien plans for each future outage. However, if flaws are found.that do not meet the j

criteria'of Section;XI of the ASME Code for continued operation withott evalua-

-ti a i NRC-a? proval'of flaw evaluations or repairs in accordance with I(B 3640 u;d WFT13) is required before resumption of o)eration. Note that we'd overlay 1 l

-repoir'is consTdered as a non-Code repair Mici requires NRC approval.

Sincerely, - l

?kTJsjRiofElb 1

Robert M. Pulsifer, Project Manager -I '

Project Directorate III-2 1

Division of Reactor-Projects - III, IV, V and Special Projects 1 Office of Nuclear. Reactor Regulation l

. l

Enclosures:

_ l 1.

. Examples of Accep(table Specifications optional) Technical

2. Safety Evaluation i

3. Technical Evaluation Report cc w/ enclosures:-

See next page '

Office: .LA/PDI ,1- g PM/PDIII-M EMC (A)PD/

Surname: CMo$& BPulsifer?tg CCh JWechs erger

. Date:J K / 9 /90 //Qy/90 T/(Q/0 8 @ 90 x

., - . , . _ . _ . _ - _ _ _______s -

.[ *% -

, , - 4* kJ Ufe:TED STATE 8 NUCLEAR REQUL ATORY COMMISSION g- 1 reasumaton, c. c. 20s** j August 22, 1990 Docket Nos. 50-373 and 50-374 1 Mr. Thomas J.: Kovach I L Nuclear Licensing Manager L Commonwealth Edison Company-Suite 300 -

-OPUS West 111  ;

~

1400 OPUS Place Downers Grove, Illinois' 60515

SUBJECT:

REVIEW OF RESPONSE TO GENERIC LETTER 88-01, "NRC POSITION ON IGSCC IN BWR AUSTENTIC STAINLESS STEEL PIPING," LASALLE COUNTY STATION, UNITS 1 AND 2 (TAC NOS. 69141 AND 69142)

The NRC staff has completed its review of LaSalle County Station Units 1 and 2 in response to Generic Letter (GL) 88-01. A' copy of the staff's Safety Evaluation (SE) ard a copy of the Technical Evaluation Report prepared by .

the staff's. contractor, Viking Systems International, are enclosed.  :

Based on the Safety Evaluation, the staff finds your responses to GL 88-01 are acceptable with some exceptions. You are requested to review these ,

' exceptions and notify the staff of actions taken to address them. When the Committee to Review Generic Requirements (CRGR) met on this topic, they approved TS to be-incorporated by licensees. Thus, you are requested to propose amendments t, your Technical Specifications (TS) to:

(1) Include a statement in the surveillance or administrative controis-section that includes the following: "The inservice inspection program for piping identified in NRC Generic Letter 88-01 shall.br ,

performed in accordance with the NRC staff positions on schedule, methods,' personnel, and sample expansion included ~in Generic .

Letter 88-01 or in accordance with alternate measures approved by t the NRC staff."

(2) Include an additional Limiting Condition for Operation (LCO) that specifies reactor coolant system leakage shall be limited to a 2 gpm increase in unidentified leakage within any'24-hour period.

(3) Include a surveillance requirement that primary containment sump flow rate will be monitored at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. it should-be noted that the position in GL 88-01 on leak rate monitoring was  :

modified to permit leakage measurements based on sump flow instruments to be.taken every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> instead of every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

(4) For LaSalle Lounty Station Unit 1, include an LCO on operability of sump monitoring instruments. Since your plant has IGSCC weld category E weldments, Generic Letter 88-01 provides an allowed outaga time of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for repairing the drywell floor drain sump

. Mr. Thomas J. Kovach i u,

monitoring- system, or.an orderly shutdown should be initiated.. As an alternative, the staff reconnends that when the drywell sump moni-  !

'toring system is. inoperable, the. operator should use a demonstrated manual method for determining leak rate,-st e as measuring the time to manually pump the sump at a fixed inte m . ?,4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />). The staff considers manual measurement a viable sump monitoring method-without '

hardship to the operator; therefore, this method could be added to the appropriate LCO section. With the manual method operable, the outage -

time for the' drywell sump monitoring system could be extended to 30-days. However, if the sump pump and drywell sump monitoring systems are inoperable concurrently, then either system has to be repaired within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or an orderly shutdown should be initiated.

Pertinent sections of the model BWR Technical Specifications are enclosed as "

examples of acceptable positions for items 2 and 3 above. Accordingly, please submit the requisite TS change requests or notify the staff of actions taken f

within 60 days, Connonwealth Edison needs to address the RWCU piping outboard of the isolation valves in the 151 program. If the piping is within-the scope of GL 88-01, -

you will need to modify the program to include the identity of the welds as-well as plans for mitigation and inspections. A minimum of 10% of the RWCU system piping outboard of the isolation valves should be :nspected at each refueling outage. If cracks are found, the licensee should discuss sample expansion and mitigation methods with the NRC staff.

For SE deficiencies related to welds, categorization of welds, and qualifica-tion of personnel, these deficiencies shall be corrected in the ISI program.

Since-you previously submitted integrated IGSCC inspection plans, our safety evaluation precludes the necessity for you to submit IGSCC inspection plans for each future outage. However, if flaws are found that do not meet the criteria of Section XI of the ASME Code for continued operation without evalua-tion,.NRC a> proval of flaw evaluations or repairs in accordance with IWB 3640 and IWi"113; 15 required before resumption of o>eration. Note that weld overlay repair is considered as a-non-Code repair, wfiici requires NRC approval. ,

Sincerely, RobertM.Pulsidr,ProjectManager project Directorate 111 Division of Reactor Projects - III, IV, Y and Special Projects Office of Nuclear Reactor Regulation-

Enclosures:

1. Examples of Acceptable Technical Specifications (optional)

2. Safety Evaluation

3. Technical Evaluation Report cc w/ enclosures:

'See next page

)

Mr. Thomas J. Kovach LaSalle County Nuclear Power Station- l Connonwealth Edison Company Unit Nos. 1 & 2 -1

• 1 cc:

Phillip P. Steptoe, Esquire Robert Cushing )

Sidley;and Austin Chief, Public Utilities Division- 1 One first National Plaza Illinois Attorney. General's Office Chicago, Illinois 60603 100 West Randolph Street.

Chicago, Illinois 60601 Assistant Attorney General i 100 West Gandolph Street Michael I. Miller, Esq. 1 Suite 12 Sidley and Austin Chicago, Illinois 60601 . One First National Plaza Chicago, Illinois 60690  ;

Resident Inspector /LaSalle, NPS 1 U.S. Nuclear Regulatory Connission l Rural Route No. 1 P. O. Box 224 Marseilles, Illinois 61341 Chairman LaSalle County Board of Supervisors LaSalle County Courthouse  :

Ottawa, Illinois 61350 .

t Attorney General )

500 South 2nd Street Springfield, Illinois 62701 Chairman Illinois Commerce Connission Leland Building 527 East Capitol Avenue Springfield,' Illinois 62706

- Illinois Department of Nuclear Safety

. 0ffice of Nuclear Facility Safety 1035 Outer Park Drive Springfield, Illinois 62704.

Regional Administrator, Region III U. S. Nuclear Regulatory Connission 799-Roosevelt Road, Bldg. f4 Glen Ellyn, 1111nois.60137 Robert Neumann Office of Public Counsel State of. Illinois Center

. 100 W. Randolph i Suite 11-300 Chicago, Illinois 60601

c ENCLOSURE'1

)

MODEL BWR TECHNICAL !;PECIFICATIONS '

, REACTOR-COOLANT SYSTEM OPERATIONAL LEAKAGE ,

LIMITING CONDITION FOR OPERATION 3.4.3.2 Reactor coolant system leakage shall be limited to:

a. No PRESSURE BOUNDARY LEAKAGE.

b. 5 gpm UNIDENTIFIED LEAKAGE.

c. 25 gpm total leakage averaged over any 24-hour period.

I

d. ,1 gpm leakage from any coactor coolant system pressure isolation j valve speci<ied in Table 3.4.3.2-1.

(e 2 gpm increase in UNIDENTIFIED LEAKAGE within any 24-hour period.)

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2 and 3.

ACTION:

a. W

. ith any PRESSURE BOUNDARY LEAKAGE, be in at least HOT SHUTD0WN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, b.

With any reactor coolant system leakage greater than the limits in b and/or c, above reduce the leakage rate to within the limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or,be in at least HOT SHUTDOWN WITHIN THE NEXT 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

4 c.-

With any reactor coolant system pressure isolation valve leakage greater than the above limit, isolate the high pressure portion of the'affected system from the low pressure portion within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least two closed manual or deactivated automatic valves, or be in at least HOT SHUTDOWN within the next- .,

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. '

d. With any reactor coolant system leakage greater than the limit in e above, identity the source of leakage within 4' hours or be in at least HOT SHUTDOWN withinthefollowing24 hours.)within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD-SHUTDOWN -

SURVEILLANCE REQUIREMENTS 4.4.3.2.1 The reactor coolant system leakage shall be demonstrated to be within each of the above limits by:

a. Monitoring the primary containment atmospheric particulate (and/or gaseous) radioactivity at least once per (4 or 12 as applicabletoplant). hours,

b. Monitoring the primary containment sump flow rate at least once

-pereight(8) hours,

,, 1/ A d.9

l

.. I 1 REACTOR COOLANT SYSTEM I

, $URVEILLANCEREQUIREMENTS(continued)

c. Monitoring the primary containment air coolers condensate flow-rate at least once per (4 or 12 as applicable to plant) hours, and

)

.di Monitoring the reactor vessel head flanpa '

' - x detection system at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

- 4.4.3.2.2 Each retetor coolant system pressure isolation valve specified in-Table 3.4.3.2-4 shall be demonstrated OPERABLE pursuant-to Specification 4.0.5, except.the c -in lieu of any leakage testing required by Specification 4.0.5, each valvti shall.be demonstrated OPERABLE by verifying leakage to be within its limit,  ;

a. At least once per 18 months. I b.- Prior tc entering H0T $HUTD0WN_whenever the plant has been in COLD SHUTDOWN for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or more and if leakage testing has not been' performed in the previous g months. i

c. Prior to returning the valve to service following maintenance, repair or replacement work on the valve.

d. Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following valve actuation due to automatic or manual action ~or flow through the valve.

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