ML20114D034

Safety Evaluation Supporting Amend 65 to License NPF-62

ML20114D034
Person / Time
Site:	Clinton
Issue date:	08/21/1992
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20114D032	List: ML20114D029 ML20114D034
References
NUDOCS 9209040102
Download: ML20114D034 (4)

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UNITED STATES n

3, G'2 /i NUCLEAR REGULATORY COMMISSION k

WASHINGTON. D_C. 20566

%,,..... f SAFELY EVAjj)ATION.BY 'HE OFFICE OF NUCLEAR REACTOR REGULA_T_1QL(

IELATED TO AMENDMENT NO.

65 TO FACILITY OPERATING llCFME NO. NPF-62 ILLIN0IS POWER COMPANY. ET AL.

CLINTON POWER STATION. UNIT NO. 1 DOCKET ND. 50-461 1.0 INTRODUCTIDL{

By letter dated July 11, 1990, and supplemented May 7,1991, Illinois Power Company (IP) and Soyland Power Cooperative, Inc. (the licensee) requcsted an amendment to facility Operating License No. NPF-62 for the Clinton Power Station.

The proposed amendment would revise the Technical Specifications (TS) by changing Section 4.0.5, Surveillance Requirements for Inservice Inspection and Testing; Section 3/4.4.3.1, Reacter Coolant System Leakage Detection Systems and Bases; and Section 3/4.4.3.2, Operatio al Leakage and Bases. The amendment would conform to the NRC staff position on Inservice Inspection (ISI) and monitoring of unidentified leakage, as delineated in Generic Letter (GL) 88-01 entitled "NRC Position on Intergranular Stress Carrosion Cracking (Ir: SCC) problems in Boiling Water Reactor (BWR) Austen! tic Stainless Steel Piping."

GL 88-01, which was issued January 25, 1988, provides guidance rWarding IGSCC problems in BWR piping m He of austenitic stainless steel that is 4 inches or larger in nominal diame.er. The GL only addresses problems where the piping contains reactor coolant above 200 degrecs F during reactor power operation, regardless of ASME Code classification.

Information was requested of affected licensees regarding conformance with the NRC positions stated in the GL.

Two specific raquests were:

(1) a TS change to include a statement in the TS section on ISI certifying that tho ISI program for piping covered by G' 88-01 will conform with the NRC positions on schedule, methods and personnel, and sample expansion; and (2) confirmation that the licensee's TSs related to leakage detection will be amended as appropriate to conform with the NRC positions included in the GL.

These two requests are addressed by the proposed amendment.

Two otner revisions reouested by the July 11, 1990 letter, to iS Section 3/4.8.3.1, Onsite Power Distribution Systems - Operating, and Section 3/4.8.1.1, AC Sources - Operating, were issued by Amendment No. 45, dated September 17, 1990. 'nd by Amendment No. 49, dated September 27, 1990, respectively.

2.0 EVALUATION The NRC staff previously completed an evaluation of the licensee's programs to meet the 13 staff positions and other guie nce provided in GL 88-01.

Cy letter dated August 24, 1990, the licensee was informed that its programs were 9209040102 920821 DR ADOCK 0500 1

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acceptable und' satisfied the requirements of GL 88-01, with two exceptions.

~ The first exception concerned the_ categorization of 50 welds.

The staff has-reviewed the licensee's April 12,.1991, response ta this issue, and has found

.that its classification of-welds is acceptable.

The licensee was notified of thi-s finding by letter dated November 15, 1991.

The second exception involved

- t e~ licensee's proposed-TS changes as submitted by letter dat d July 11, 1990.

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- The'licens'ee:eddressed the TS exception.in supplemental correspondence dated May 7,.1991. -The staff's eva'uation of the proposed amendment, as supplemented, follows.

Ths; licensee 1has proposed the following changes to the TSs which conform to the_ guidance-provided in.GL 88-01:

(1)

.Addinew Surveillance Requirement 4.0.5.f to read "The Inservice

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. inspection Program for piping identified in NRC Generic Letter 88-01 shall be performed in accordance with the NRC staff positions on schedule, methods and personnel, and sampla expansion 'ncluded in the

--generic letter."

' (2)-

Modify the - Action St atement.in TS 3.4.3.1 to read "With only two of the aoove required leakage detection syst;:ns OPERABl.E, "a.

l operation may contin.ne for up to~30 days.when the drywell atmosphere particulate radioac'ivity monitoring system is inoperable provided grab-samples of the drywell atmosphere are obtained=and analyzed at:least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />,

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operations may continue:

'"1.

with the drywell equipment drain subp flow monitoring subsystem inoperable provided the drywell equipment drain sump flow rate is monitoredf and determined by alternate means.at_least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

'"2.

for up to 30 days with the drywell floor drain sump flow

- c.anitoring ' subsystem :roperable provided the drywell floor drain sump _ r ow rate is monitored and determined:by alternate means at least once.per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

"c.

operation may continueEfor up to 30 days when the drywell atmosphere gaseous radioactivity monitoring system ~ and the drywell

_ air ccolers condensate flow rate monitoring system are inoperable provided grab sampies of the drywell 4tmosphere are'obtained ~and analyzed-at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

"Otherwise 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 SHOTDOWN within_the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />."

- (3)

Add new limiting: Condition"for Operation 3.4.3.2.2 to read "No greater l

_thanLa 2 gpm increase in UNIDENTIFIED LEAKAGE within a 24-hour period or E

-less during:0PERATIONAL CONDITION-1." In addition, add associated Action L

Statement-3 4.3.2.d to-read "With any reactor coolant system g

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3 UNIDENTIFIED LEAKAGE increase greater than 2 gpm within any 24-hour-periodfor-less'(during OPERATIONAL CONDITION 1), within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> from the time of discovery; isolate the source of increased leakage or verify that the source of increased leakageLis not associated with service sensitive Type 304 or 316,austenitic stainless steel; otherwise be in at least HOT SHUTDOWN within the next 12. hours and in COLD SHUTDOWN within the following 24, hours."

(4)-

Renumber Surveillance Requirement s 4.4.3. ?. l.bi 4.4.3.2.1.c, and

.4.4.

'.l.d to become 4.4.3.2.1.c, 4.4.3.2 1.d. and 4.4.3.

.l.e, re:pectively; and, add Surveillance Requirerent 4.4.3.2.1.0 to read

" Monitoring the drywell floor drain sump flow rate at least once per 8 -

hours." Delete from the renumbered 4.4.3.2,1.c the redundant words -

. floor and...".

The drywell

oor drain sump flow r ate surveillance nis covered oy~the_new 4.4.3.2.1.b.

. (5)

Make1 administrative change to 15 Section 4.4.3.2.2.a removing a footnote that was applicable only untyl startup following tne first refueling cutage.

(6)

Revise Bases Section-3/4.4.3.l on Leakage-Detection System". 10 include the statement'"With certain exceptions as noted in the Clinton Power

Station Updated Safety Analysis Report these detection systems are

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' consistent with_the recommendation of Regulatory Guide 1.45, " Reactor

Coole.1 Pressure Boundary Leakage Detection Systems," May-1973.

Except cfor.th' drywe_ll particulate and gaseous radioactivity monitors, the e

= sys.tems provide 1.he ability to measure leakage from fluid systems in the

'drywell.

Th(Jrywr:ll sump t h munitoring system consists of the drywel-1Lfloor drain ~ sump flow sta_ituring subsystem and the~drywel' equipment drain Dump f 10 monitoring. subsystem.

OPERABILITY of each or C

- these subsystems requires that the applicable portion of the monitoring subtystem associated with the v-notched weir box Le OPERABLE-Other portions of theEsubsystem. inclrding the. sump pump _ control circuit and the associated. timer,-cycle counter.and level switches, may be utilized as appropriate to provide an alternate means of monitoring-and determining.-UNIDENTirlED or=lDENTIFIED leakage _under the provisions of-

-the associated ACTION: statements for the respective subsystem."

-(7):

ReviseLBases;Section ^/4.4.3.2 on Operational-Leakage to include the-

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statements "With.rr ;ect to IGSLC-related cracks in-service sensitive austenitic.st ainless = steel-piping however. an ~ additional limit. on the allowed! increase in UNIDENTiflED iEAKAGE-(within a 24-hour pericd or-less) is imposed in accordance with Generic Letter 88-01, "NRC Position onEIGSCCfin BWR Austenitic= Stainless Steel _ Piping," since an abrupt L

_ increase 'in-the UNIDENTiflED-LEAKAGE could be indicative of leakage.from suct source." and~"The reactor.will also be shut down if an increase-in U;!'ENTiflED LEAKAGE exceeds'the specified-limit and the source of incr.

ed' leakage cannot bc isolated or it cannot be det.rmined within a 4

short period ofetime that 'the source of increased leakage is not associated witF Justenitic stainless steel."

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4 These proposed changes are consistent with the model TSs provided in the GL 88-01 and are adequate for inservice inspection, monitoring, testing and surveillance of system leakage, The staff has, therefore, concluded that the TS changes satisfy the intent and objectives of ul 88-01 and are acceptable.

3.0 STATE CONSULTAT10tl in accordance with the Commission's regulationi, the appropriate Illinois State official was notified of the proposed issuance of the amendment.

The State official had no comments.

4.0 ENVIRONMEt!TAL CONSIDERATI0fl This amendment changes a c~"irement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 or changes a surveillance requirement.

The staff has determined that the amendment involves no significant increase ir, the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative i

occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration and there has been no public comment on such finding (55 FR 36345 and (57 FR 4488). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(t: '9).

Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of tne amendment.

5.0 CONCLUSION

The staff has concluded, based on the considerations discussed above, that:

(1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations.

and (3) the issuance of the amendment will not be inimitil to the common defense and security or to the health and safety of the public.

Principal Contributors:

A. Hansen J. Lombardo Date: August 21, 1992

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