ML20126F947

Model Tech Specs 3/4.0 & 3/4.4 Re RCS Operational Leakage

ML20126F947
Person / Time
Site:	La Crosse File:Dairyland Power Cooperative icon.png
Issue date:	03/04/1981
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20126F945	List: ML20126F947
References
NUDOCS 8103240065
Download: ML20126F947 (7)

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MDDEL TECHNICAL SPECIFICATIONS - Applicant '

REACTOR COOLANT SYSTEM 'I OPERATIONAL LEAKAGE LIMITING CONDITION FOR OPERATION

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3.4.3.2 Reactor coolant syst.~a leakage shall be limited t'o:

a. No PRES 5URE BOUNDARY LEAKAGE.

b. 5 gpm UNIDENTIFIID LEAKAGE. i

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

d. 1 gpm leakage from any reactor coolant system pressure isolation valve specified in Table 3.4.3.2-1. -

e. 2 gpm increase in UNIDENTIrIED LEAKAGE within any 24-hour period.

• APPLICABILITY: OPERATIONAL CONDITIONS 1, 2 and 3.  ;

ACTION:

a. With any PRESSURE E00NDARY LEA" AGE, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHU10ChN 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 lim'ts in b

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and/or c, above, reduce the leakace 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 SHUTDCWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and.  ;

To COLD SHUTDOWN within the follcwing 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.  !

c. With any reactor coolant syste , 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 />.

i d. With any reactor coolant system leakage greater than the limit in e

• above, identify the source of leakage 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 .

l 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 />.

SURVEILLANCE REOUIREMENT5' 4.?.3.2.1 The reactor coolant system leakage shall be demonstrated to be within l each of the above limits by:

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

b. Monitoring the primary containment sump flow rate at least once per (4) hours, l

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REACTOR COOLANT SYSTEM 1

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l SURVEILLANCE REQUIREMENTS (Continued)

c. Monitoring the primary containment air coolers c6ndensate flow rate at least once per (4) hours, and l

d. Mer.itoring the reactor vessel head flange leak detection system at l lt st 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 reactor coolant system pressure isolation valve specified in Tacle 3.4.3.2-1 shall be demonstrated OPERABLE pursuant to Specification 4.0.5, except that in lieu of any leakage testing required by Specification 4.0.5, each valve shall be demonstrated OPERABLE by verifying leakage to be within its limit:

a. At.least once per 18 months.

b. Pricr to en-- ing HOT SHUTDCWN 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 test .; has not been 3

perforced in the previous 9 months.

c. Prior to returning the valve to service followi: lintenance, repair or replacement work on the valve.

I d. Within 24 h:urs followir.g valve actuation due to automatic or manual a'ction Or flow through the valve.

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APPLICASILITY ~ '

I SURVEILLANCE REQUIREMENTS 4.0.1 Surveillance Requirements shalf be met during the OPE 3ATIONAL .

CONDITIONS or other conditions specified for individual Limiting Conditions

• for Operation unless otherwise stated in an individual Surveillance Requirements.

4.0.2 Each Surveillance Requirement shall-be performed within the specified tice interval with:

a. A maximum allowable extension not to exceed 25% of the surveillance interval, but l

b. The combined tine interval for any 3 consecutive. surveillance intervals l shall not exceed 3.25 times the specified surveillance interval.

4.0.3 Failure to perform a Surveillance Require =ent within the specified time interval shall constitute a failure to meet the OPERASILITY requirements for a Limiting Condition for Operation. Exceptions to these requirements are stated in tne irdividual Specificatons. Surveillance requirerents do not have to be per-formed en inoperable e::uipment.

4.0.4 Enta into an OPERATIONAL CCNDITION or other specified applicable condi-tion shall not be :ade unless the Surveillance Requirement (s) associated with the Limiting Condition for Operation have been performed witnin the applicable surveillance interval cr as otherwise specified.

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. 4. 0. 5 Surve.illance Requirements fer inservice inspection and testing of ASME Code Class 1, 2, & 3 cc:porants shall be applicable as fo11cus:

a. Inservice ins;ection of A5ME C:de Class 1, 2, and 3 components and inservice testing of A5ME Coce Class 1, 2, and 3 pumps and valves

. shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Section 50.55a(g), except where specific written relief has ,

been granted by the Commission pursuant to 10 CFR 50, Section 50.55a(g) .

(6) (i).

b. Surveillance intervals specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda for the inservice .

, inspection and testing activities required by the ASME Boiler and Pressure Vessel Code and applicable Addenda shall be applicable as follows in these Technical Specifications:

ASME Eciler and Pressure Vessel Required frequencies ,

Code and applicable' Addenda for performing inservice  ;

terminolog.y for inservice inspection and testing ins:ecti:n and testi c activities activities Veekly At least cnce per 7 days Monthly At least once per 31 cays Quarterly er every 3 : nt': At least once per 32 days Semiannualiv or e.erv 6 Oc. ths At least once per 134 days ,

E.ery 's contns " A. least once per 275 cays  !

Yearly c- annually At least once per 256 days

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AP?lICABILITY SU 'w'EILLANCE REOUIREMENTS (Continued) f c.

The provisions of Specification 4.0.2 are applicab.le to the above required frequencies for ;erforming inservice inspection and testing activities.

d.

Performance of the.above inservice ins:e : fen and testing activities shall be in acdition to other specifie:: Surveillance Requirements. I e,

Nothing in the ASME Boiler and Pressure Vessel Code shal'i be construed '

to supersede the requirements of any Technical Specification, r

4. 0. c All ASME Code Class 1, 2, and 3 lines shall conform to the guidelines 4 i stated in the NUREG-0313, Rev.1, " Technical Report on Material  ;

i Selection and Processing Guicelines for 5'4R Coolant Pressure Boundary Piping," July 1980.  ;

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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION TO PROVISIONAL OPERATING LICENSE NO. DPR 45 CAIRYLAND POWER COOPERATIVE LA CROSSE BOILING WATER REACTOR DOCKET NO. 50-409

1.0 BACKGROUND

In January 1975, a Pipe Crack Study Group was formed to investigate the occurrence of cracking in austenitic. stainless steel piping of Boiling Water Reactors (BWR). The Study Group report, NUREG-75/067, indicated that, "although the probability is extremely low that the presence of cracks and leaks could result in a significant safety hazard to the public, the presence of such conditions is not consistent with the Design Criteria in 10 CFR 50." The Study Group recommended, " steps should be taken to minimize (intergranular) stress-corrosion crac. king in SWR piping systems ta eliminate this condition and also improve plant reliability."

Intergranular stress corrosion cracking (IGSCC) in austenitic stainless steel material is caused by a combination of high tensile stresses, sensitized material and a corrosive environment. The SWR reactor coolant which operates with a high oxygen content, is a corrosive environment capable of causing IGSCC in sensitized austenitic stainless steel piping.

The NRC through NUREG-0313 implemented an augmented inservice inspection (ISI) and leak detection program in SWR ASME Code Class I and II pressure boundary austenitic stainless steel piping which could be susceptible to IGSCC. Sus'ceptible materials were identified as "non-conforming". The degree of augmented ISI depends upon whether the non-conforming lines had been identified as " service sensitive." Service sensitive lines are defined as the BWR Class I and II pressure boundary piping which experienced cracking in service or are considered to be particularly susceptible because of high stress and relatively stagnant, intermittent, or low coolant flow conditions". Non-service sensitive lines are all' SWR Class I and II pressure boundary non-conforming lines not classified as service s.nsitive.

NUREG-0313 requires non-confording, non-service sensitive lines be examined to the schedule specified in the ASME Code, Section XI-Subsection IWB, with the exception that the examination be completed within 30 months instead of 120 months. If the examination conducted during the first 80 months period re' veals no instances of IGSCC, the examination thereafter would revert to the 120 month schedule prescribed in ASME Section XI.

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NUREG-0313 requires that non-conforming, service sensitive lines in the by-pass piping, in the main recirculation loop, and in the core spray piping be examined at each reactor refueling outage or other plant shutdown. In the event these examinatiors reveal no IGSCC fcr three successive examinations, the examination schedule would be extended to 36 month periods (plus or minus by a much as 12 nonths coninciding with a refueling outage) and the examination would be limited to one by-pass pipe run and one reactor core spray pipe run.

NUREG-0313 requires all other non-conforming service snesitive lines be examined on a sampling basis with the period of examination required for the core spray piping and by-pass piping in the recirculation loop. In the event three successive exa linations at each reactor refueling outage or other plant shutdown and three successive examinations during 36 month periods reveal no IGSCC the examination schedule could revert to ASME Section XI with the exception that the examination be completed within 80 months.

In a letter dated July 10, 1980, the Dairyland Power Cooperative summarized their operating and inspection experience with non-conforming lines during 10 years of operation from 1969 to 1979. Examination of non-service senstt!ve t

lines had been completed according to the accelerated examination requirements o f NUREG-0313. Non-conforming, service sensitive lines had been examined at least once during 1969-1979 and some had been examined more than once from 1959 to 1979. No unacceptable indications were observed during examinations of the non-conforming service sensitive lines'. In addition, LACBWR completed ten years of operation form 1969-1979 without having any welds in the reactor coolant system (RCS) pressure boundary piping develop a leak.

Based upon the successful operating and inspection exoerienced by LAC 3WR, tr.e Cairyland Power Cooperative stated that the scheduled examinations of non-c:r for-ing non-service sensitive lines would be in accordance wiB ASME Code Section XI as nodified by Technical S;ecifications and the schedules examination of non-cenforming sarvice sensitive lines would be conducted in 20 month periods.

2.0 EVALUATION l

1 I a. Non-conforming, Service Sensitive Lines The LAC 5WR non-conforming, service sensitive lines were not examined during three successive outages as required by N" REG-0313. The intent of examining service sensitive lines daring three successive outages was to determine whether an operating BWR had a generic IGSCC problem similar to those identi fied in NUREG-75/067. Since there nave been no leaks identified in the RCS pressure boundary piping and no unacceptable indications have been found during the inservice inspection subsequent to 10 years of operation, the LAC 5WR non-conforming service sensitive lines do not appear to have a potential for IGSCC that is as severe as those lines identified in NUREG-76/067.

However, non-conforming, service seultive lines in the LACBWR are still considered to have potential for !35C0 because of the likely presence of sufficiently high residual tensiie stresses , sensitized uterial, and high oxygen, low flow coolant in -hese lines during plant opert. tion.

b. Non-conforming, Non-Service Sensitive Lines The inspections performed on the LACBWR non-conforming, non-service sensitive lines satisfy the accelerated examinations required by NUREG-0313.

3.0 CONCLUSION

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1) Although non-conforming, service sensitive lines were not examined during three successive outages, the operation without leaks and non-destructive examinations during 10 years of service indicate these lines do not have ,

an IGSCC problem as extensive as BWR's identified in NUREG-75/067.

2) Augmented ISI of LACBWR Non-conforming service sensitive lines is necessary because these lines operate in an environment and with conditions that have the potential to be susceptible to IGSCC.

3) Accelerated augmented ISI required by NUREG-0313 for non-conforming non-

• service snesitive lines has been completed on the LACBWR.

4.0 RECOMMENDATIONS

1) Non-conforming, non-service sensitive lines may be inspected in accordance with ASME Section XI schedule as modified'by LAC 3WR Technical Specifications.

2) The LACSWR Technical Specifications should require that all non-conforming service sensitive lines be examined per NUREG-0313 at 36 month intervals  :

(plus or minus by as much as 12 months) coinciding with a refueling outage.

In the event these examinations reveal no unacceptableindications iwthin three successive inspections, the schedule nay revert to the ASME Boiler and Pressure Vessel Code,Section XI, Inservice Insection of Nuclear Power Plant Ccmponents with the exception that the required examinations l

, should be completed during each 30 month period (two-thirds the time prescribed in the scheduled in tne ASME Code Section XI).

3) Non-conforming lines should be volumetrically inspected using ultrasonic procedures or other advanced non-destructive examination techniques which have been demonstrated to reliably detect and evaluate IGSCC in austenitic stainless steel piping.

4) The LACBWR Technical Specifications should incorporate the equivalent leak detection requirements of NUREG-0313 Rev.1, July 198C , (Model T. S. attached for information).  ;

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