ML19210A373

Tech Specs Change Request 43 to Amend DPR-50,App a, Incorporating Steam Generator Inservice Insp Into TMI-1 Tech Specs

ML19210A373
Person / Time
Site:	Three Mile Island
Issue date:	11/12/1976
From:	Arnold R METROPOLITAN EDISON CO.
To:
Shared Package
ML19210A371	List: ML19210A370 ML19210A373
References
NUDOCS 7910290602
Download: ML19210A373 (11)

Text

.METROPOLITAN EDISON COMPANY JERSEY CENTRAL POWER & LIGHT COMPANY AND PENNSYLVANIA ELECTRIC COMPANY TEREE MILE ISLAND NUCLEAR STATION UNIT 1 Operating License No. DPR-50 Docket No. 50-289

.Technical Srecification Change Recuest No. h3 This Technical Specification Change Request is submitted in support of Licensee's request to change Appendix A to Operating License No. DPR-50 for Three Mile Island Nuclear Station Unit 1.

As a part of this request, proposed replacement pages for Appendix A are also included.

METROPOLITAN EDISON COMPANY

)By i Vice Presidst-Generation Sworn and subscribed to me this day of , 1976.Notary Public 1491 004. .. .. ...gelo 290M P

..Three Mile Island Nuclear Station Unit 1 (TMI-1)

Operating License No. DPR-50 Docket No. 5c 289 Technical Scecification Chance Request No. h3 The licensee requests that the attached pages be added to Appendix A of the TMI-l Technical Specifications.

Reason For Fronosed Chance To incorporate steam generatcrs inservice inspection into the TMI-l Technical Specifications as requested by the USURC in their letter of Septester 14, 1976, to Mr. R. C. Arnold.

Safety Analysis Justifying Change

.This proposed Technical Specification Change does not involve any unreviewed safety questions in that it only incorpcrates additional inspection restrictions tc ensure the continued integrity of the tube portion of the TMI-l Once-Through Steam Generators.

Il1491 005 i.I I t

....L.18 OTSG TU3E INSERVICE INSFECTION Aurlicability This Technical Specification applies to the inservice inspection of the OTSG tube portion of the reactor coolant pressure boundary.

I Ob.iective The objective of this inservice inspection progra= is to provide assurance of continued integrity of the tube portion of the Orce-Through Steam Generators, while at the same time minimizing radiation exposure to personnel in the perfor=ance cf the inspection.

• Scecification

'i Each stea= generator shall be de=onstrated OPTRABLE by performance of the g i following augmented inservice inspection program and the requirements of Specification 3 13 L.18.1 Steam Generator Samole Selection and Insrection Each stess generator shall be deter =ined OPERA 3LE during shutdevn by i i selecting and inspecting at least the minimum number of steam generators f specified in Table 4.18.1.

h.18.2 Steam Generattr Tube Samule Selection and Insrection 4-The stes= generator tube mini =us sample size, inspcetion result I classificatien, and the corresponding action required shall be as

lspe:ified in Table k.18.2.

The inservice inspection of stea= generator

1 tubes shall te perforced at the freq =ncies specified in Specification elk.18.3 and the inspected tubes shall be verified acceptable per the i!acceptance criteria of Specification h.18.h.

The tubes celected for 1 1491 006 L-63

.t't.!l..each inservice inspection shall include at leart 1 % of the total number of tubes in all steam generators:

la.The first inservice inspection of each steam generator included 1 a rando= sampin... of greater than 3% of the tubes in each steam generator.

b.The second and subsequent inservice inspection may be from one

!lsteam generator and shall include 1 % of the total installed i!steam generator heat transfer surface. All tubes to be examined i in the second and subsequent intervsis shall te from previously examined tubes. All unplugged tubes with indications greater than 20% of the nominal vall thickness shall be included in

!!those tubes selected for reexamination.

The results of each sample inspection sPall be classified into one i.lof the following two categories:

lCategory Insteetion Results

!C-1 Less than 105 of the total tubes

{inspected in a steam generator J are degraded tubes exhibiting

, i indications in excess of 20%

of the vall thickness.

C-2 10% or more of the total tubes inspected in a stea generator are degraded tubes exhibiting indications in excess of 2CG cf the vall thickness.

NOTE: In all inspections, previcusif degraded tubes must exhibit i significant (> 10%) further vall penetrations to be included 3n the above percentage calculatiens.

I 1491 007lu_6u i..: f k.18.3 Insteetion Frecuencies The required inservice inspections of steam generator tubes shall be performed at the following frequencies:

The first (baseline) inspection was performed after 6 effective a.full power =enths but within 24 caleadar =onths of initial

lcriticality. The second inservice inspection shall be perfor

ed

1. 1 not less than 9 nor more than 2h calendar =enths after the

'previous inspection. The third and sub equent inspections j shall be performed within additional periods of 3-1/3 years.

f b.If, in say inepection, an excess of 10% of the tubes examined v, exhibit indications in excess of 20% of the vall thickness , the

'next two inspections shall be performed at one to two year intervals.

If, in these examinations , .no more than 10% of the ttbes examined exhibit either (a) additional degradation (greater t than 10% of vall thickness) of previously degraded tubes, (b) tubes with new indicatiens in excess of 20% vall thi 'kness , or (c) a ec=binntion of both, the inspection intervals may continue

'at 3-1/3 yecrs.

Additional, unscheduled inservice inspections shall be perfor ed c.!on each stea= enerator in accordance with the first sa=ple i s inspe: tion specified in Table k.13.2 during the shutdown subsequent

'i to a.y of the following conditions:

, 1.Primary-to-secondary leaks which exceed the limits of

.I 5~.cifi:ation 3.13 2.A seismic cecurrence greater than the Operating Basi i Earthquake.

1491 008 4 i L-65

..3 A loss of coolant accident requiring actuation of the engineering safeguards , or k.A major =ain steam line or feedvater line break.

L.18.h Accentance Criteria a.As used in this Specification:

1.Imrerfection means an exception to the dimensions, finish or contour of a tube fro = that required by fabrication drawings or specifications.

Eddy-current testing indications below 20% of the nominal tube vall thickness, if detectable, may be considered as i= perfections.

2.Deeradation means a service-induced cracking, vastage, vear or general corrosior occurring on either inside or outside of a tube.

, 3 Deeraded Tube =eans a tube contt ining i= perfections < 20%

of the nominal vall thickness caused by degradation.

h.% Degradation means the percentage of the tube vall thickness affected or re=oved by degradation.

5 Defect means an i= perfection of such severity that it exceeds the plugging limit. A tube containing a defect is defective.

6.Plugeine Limit means the imperfection depth at or beyond which the tube shall be rs=oved from service because it may become unse.rviceable prior to the next inspection and is equal to h0% of the no=ina) tube vall thickness, unless higher limits are shown to be acceptable by analysis.

7.Tube Inspection means en inspection of that portion of the stea= generator tube from the bottom of the upper tubesheet completely to the top of the lower tubesheet.

1491 009 h-66

.4 b.Tne stes= generator shall be deter =ined OPERABLE after completing the corresponding a ; ions (plugging including all tubes exceeding a the plugging limit and all tubes containing through-wall cracks) required by Table 4.18.2.

h.18.5 Renorts a.Following each inservice inspection of steam generator tubes, the number of tubes plugged in each steam generator shall be I reported to the Commission within 30 daya.

l b.The complete results of the steam generator tube inservice

.}'inspection shall be included in the Annual Operating Report for the period in which this inspection was co=pleted. This report shall include:

p 1.Nu=ber and extent of tubes inspected.

l2.Lccation and percent of wall-thickness penetra+. ion for i 3 each indication of an imperfection.

!'3.Identification of tubes plugged.

c.Results of steam generator tube inspections which require prompt notification of the Ccemission shall be reported pursuant , ' , to Specificatien 6.9 2 prior to resumption of plant operation.

lThe written followup of this report shall provide a description i of investigations cenducted to determine cause of the tube

.degradation and corrective teasures taken to prevent recurrence.

I 1*Bases The Surveillance Require =ents for inspecticn of the stea: generator tubes ensure that the structural integrity of this portica of the RCS will be maintained.

I 1491 010 i k-o7

+i ,..;.The pro 6:am for inservice inspection of steam generator tubes is based on ASME i Code Secticn XI, Winter 1975 Addenda.

Inservice Inspection of steam generator tubing is essential in order to maintain surveillance of the conditions of the tubes in the event that there is evidence of mechanical danage or progressive degradation due to design, manufacturing errors, or inservice conditions that lead to corrosion.

Inservice inspection of steam generator tubing also provides a means of chrrscterizing the nature and cause of any tube degradation so that corrective measures can be taken.

.6 I (:-The unit is expected to be operated in a manner such that the secondary coolant I!vill be maintained within those che=istry limits found to result in negligible i corrosion of the steam generator tubes.

If the secondary coolant chemistry is i not maintained within these chemisti+ limits, localized corrosien may likely result in stress corrosion cracking.

, ilThe extent of stea= generator tube leakage due to cracking would be limited by i'.the secondary coolant activity, Specification 3 13.

Cracks having a primary-

.to-secondary leakage less than this limit during operation vill have an adequate i margin of safety to withstand the loads impt ,ed during normal operation and by f postulated accidents.

(;.I*Operating plants have demonstrated that scnitoring of secondary coolant can llreadily detect activity in the range of the Specification 3.13 limit.

Leakage in excess of this limit vill require plant shutdown and an unscheduled inspection, during which

..e leaking tubes vill be located and plugged.

• t ,'1491 011 e i 1 k-68

.-,.Wastage-type defects are unlikely with proper chemistry treatment of the secondary coolant.

However, even if a defect vould develop in service, it vill be found during scheduled inservice steam generator tube examinations.

Plugging vill be required for 40% of the tube nominal vall thickness, unless I higher limits are shown to '

4cceptable by analysis.

Steam generator tube inspections of operating plants have demonstrated the capability to reliably detect degradation that has penetrated 20% of the original tube vall thickness.

Whenever the results of any stea= generator tubing inservice inspection fall into category C-2 on the 3rd sample inspection, (See Table h.18.2), these results vill be promptly reported to the Com=ission pursuant to Specification

, 6.9.2 prior to resumption of plant operation. Such cases vill be considered lI, by the Commission on a case-by-case basis and =ay result in a requirenent for

!'analysis , laboratory examinations , terts , additional eddy-current inspection, i and revision of the Technical Specifications, if necessary.

I-1491 012'i i: I a I-..I I 1

_-'.TABLE k.18.1 MINIMUM NUMBER OF STEAM GENERATORS TO BE

.INS?ECTED DURING INSERVICE INSPECTION Preservice Inspection None I No. of Steam Generators per unit Two g[First Inservice Inspection Two i 1 Second & Subsequent Inservice Inspections Cne i ,!!TABLE NOTATION:

!t 1.The Inservice Inspection may be limited to one steam generator on a rotating schedule enecmpassing 35 of the tubes in that steam generator

.if the results of the first and subsequent inspections indicate that both steam generaters are perforning in a like manner. Note that under some circu= stances, the operating conditions in one steam generator nay be found to be more se'rere than those in the other steam generator. Under such I g circumstances the sample sequence shall be modified to inspect the most I severe conditiens.

013.Me

.*..,.TABLE h.18.2 STEAM GE:!ERATCR TUEE INSFECTIO:

, 1st SAMPLE II:SPECTION 2nd SAMPLE I:ISPECTION 3rd SAMPLE INSPECTION 4 Sample Size Result Action Required hesult Action equired

{- it Action Required A minimum C-1 None N/A:I/A N/A N/Al;of lh5 of: total SG C-2 Plug defective C-1 None N/A N/A!Tubes (If tubes. Inspect both SG's additional 35 C-2? lug defective C-1 None inspected, of tubes in tubes. Inspect inspect 1 5 each SG sdditional 35 C-2 Plus defective

!'of each of tubes in tubes. Notify I SG's Tubes each SG IiRC pursusnt to

[If only Specification 6.9.S i one SG 4-inspected, i inspect 35 of that.SG's , Tubes)'_i i NCTE: 1st Sa:ple Inspection as used in this table refers to the required 1'inspections at the frequencies listed in Specification h.18.13 I 1491 014 i I.L-71