ML20083N593
| ML20083N593 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 01/24/1983 |
| From: | Vollmer R Office of Nuclear Reactor Regulation |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20079G498 | List:
|
| References | |
| FOIA-83-243, FOIA-83-A-18 NUDOCS 8302020181 | |
| Download: ML20083N593 (13) | |
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MEMORANDUM FOR:
Darrell G. Eisenhut, Director y
r
- f. _
Division of Licensing FROM:
Richard H. Vollmer, Director Division of Engineering N
SUBJECT:
SIGNIFICANT HAZARDS DETERMINATION PERTAINING TO RESTART OF TMI-1 SUBSEQUENT 10 OTSG REPAIRS In response to a request from the Division of Licensing, we have pre-a pared a significant hazards deterisination on the TMI-1 steam generator recovery program.
By letter dated Deceder 10, 1982, we received the licensee's assessment of plant safety for return to service.
Based on this letter and numerous meetings in 1982 we find that:
t 1.
The corrosive species and its source have been identified and measures instituted to prevent the reintroduction of sulfur con-taining impurities,
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2.
There is reasonable assurance based on field investigation that L]
the remainder of the RCS has not been subjected to sulfur induced corrosion and is therefore acceptable for continued operation, y
M 3.
Qualification testing of ECT equipment has demonstrated adequate reliability and sensitivity to detect the defects which were present.
Therefore, reasonable assurances exist that defective times can be identified for repair or removal from service, t
-?
l 4.
The tubesheet reppir method selected establishes a new load carry-l ing joint and primary pressure boundary which has been qualified l
to the plant ifcensing basis. Therefore, reasonable assurances i
exist that the OTSG can be safely returned to service after leak
- testing, j
r i
l 5.
Purification and flushing of all systems and tanks which contained i
sulfur impurities has been conducted.
However, a sulfur residual I
remains which is chemically bound to the oxide layer on all RCS d'
wetted surfaces.
If a determination is made that a significant future corrosion potential exists, the licensee has commited to institute a sulfur removal process.
Therefore, we believe that reasonable measures have been or will be instituted to minimize the potential for f urther corrosion.
6.
A number of measures have been instituted to ensure corrosion i
does not continue or if it does that excessive leakage will not occur.
These measures include; a.
New RCS water chemistry limits which are known to reduce the 3+
-cotantial for sulfur induced attack.
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D. Eisenhut N Extensive leak and operational testing prior to critical operations.
c.
hetdown and ECT ninety days after reaching full power ration.
d.
Adai strative limits for primary to secondary leak which tre plant shutdown prior to reaching the echnical speciff ion limit of 1.0 (pet.
Conclusiens We find that:
the causa ve agent and its potsatta sources have been identified, the remainder the hCS has not been facted, the repair method established a nee-de fue pressure without signifi-cently degradfag ther SI5E per
.er al accident evaluations, the contentasets hous' hose er
'telag' and precedures incer- -
parated to prevent me- _Jc:r_-l Madet strative,,ee: 1.es will he fecerperated to!% plast" or to reaching the tactedcol spectftestfen Teatepitipit t gen per steen generetor.
Therefere,wafflad:
e t 1.c M, 15 31.hsee hees met as they apply to sintelse.ttt litar propagating failure of the W pressure hashdery ash le assurances exist and a significant that the pelle hedth and es -
hazard does estn r.st.? '..
esi
[
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. Richard H. Vo11mm Ofrector 2-Division of Ensi ng
Enclosure:
As's I
cc:
W. Johns J. Eat 1
G. Lai J.
Y.
C.
kan l
J Stela i
. Van Vliet J. Jacobs J. Rajan 3
L. Frank
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S. Kirslis
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D. Eisenhut b.
Extensive leak and operational testing prior to critical operations, c.
Shutdown and ECT ninety days after reaching full power operation, d.
An administrative limit requiring plant shutdown which is significantly less than the current technical specification limit of 1.0 gpa for priury to secondary leakage.
Conclusions In summary, we find that: the causativa agent and its potential sources have been identified; the remainder of the RCS has not been affected; the repcir methat established a non-defective pressure boundary without signifi-cantly degreding the OT54 performance er altering accident evaluations; the contaminants have been or are belag removed and procedures incorporated to prevent re-letroduction; and admin < strative procedures will be incorporated to require plant shutdown well before reaching the current technical speci-fication leakage limit of 1.D. s e per steam generator.
Therefore, we find
(
that GDC 1. M,15 and 31 hoveWest at they apply to minialze the possibility gf a rapidly propegatisg failure of the RCS pressure boundary and that reassemble assurances exist.that the public health and safety is protected and a si pitffcant hazard does not exist.
i
.e..
Richard H. Vollmer, Director Division of Engineering r
Enclosure:
As stated,
cc:
W. Johnston J. Knight G. Laines J. Bosnak V. Beneroya C. McCracken J. Stolz J. Van Vliet J. Jacobs J. Rajan L. Frank
- 0. Sellers P. Wu S. Kirslis i.
- SEE NEXT PAGE FOR PkEVIOUS CONCURRENCES q
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SIGNIFICANT HAZARDS DETERMINATION BY THE OFFICE OF NUCLEAR REACTOR REGULATIOM ETROPOLITAN EDISON COMPANY JERSEY CENTRAL POWER.410 LIGHT COPFANY PENNSYLVANIA Ei.ECTRIC C00@ANY GPU NUCLEAR CORPORATION THREE MILE ISLAW NUCLEAR STATION, UNIT NO.1 000ET W. 50-289 LO Introduction 4
I j
In inte november 1981, with the reacter shutdoun, primary-tesocondary I
l system leakage was detected in both once-through steam generators (OTSG).
j Detailed enminations revealed ttuosands of defective tunes. Metallo-I graphic exasination of'pertiene of removed tubes confirmed that the the tube falleres were initiated from the primary side (ID) of the tubes resulting in the forestion of circumferential. stress assisted inter-gresular cracks. The' active chemical lopurity causing the corrosion was sulfur in reduced. forms which had been inadvertently introduced i
j iets the reactor coolant system. The vast mejority (approximately 95%)
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ef the defects occurred within the top 2-3 inches of the 24 inch thick apper teesheet (UTS). To repair the defective SG tubes within the UTS, l
the licensee is applying an explosive expansion repair technique which 4
will expand and tightly seal the tubes within the tubesheet, thereby l
establishing a new leak limiting / load carrying seal. The licensee has decided to apply the explosive expansion repair technique to all tubes within the UTS to ensure that all potentially degraded tunes are sealed.
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The MitC staff has met with the licensee on numerous occasions since l
the SG problem was first discovered to monitor the various aspects of the licensee's SG recovery program. On October 13, 1982 m issued a safety evaluation for the OTSG axplosive expansion repair technique.
l la the safety sealuetten we found that the repair process did not levolve es unreviewed safety question or a modification to the i
technica epecifiest$eas and hence could-be conducted without MtC T. g M R.} 2(,:..:n ;;Ilussver,'9 _.we' stated that M C j
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The evere11 program to return the STSG to service includes:
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determinutica of the causative agost(s) anasiantions of the remainder of the reactor coolant systems OtCS) 0T38 enemiastions to determine extent of degredation l
OT5G repair l
l ST5G performance evaluation subsequent to repairs clemag of the contaminent.
l procedures to prevent a es-introduction of contaminants 1
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1.1 Description of the Repefr Method e
The as-built GTSE has tuo t trrwinch thick teesheets, one at the l
top and one at the bottaa. The ence t W (stralprt) te es are A
hk neelaally fifty-six feet and one-half inch long, with fifty-tus. feet WH 1,.:
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1 2.1 Determinetion of Causative Agest(s)
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systans have been analyzed and detersined to have high concentrations
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flad that the corror as was emmaed ty a' redeced sulfur species.
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h7 2.2 Examinations of the Remainder of the 10$
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To ensare that the costaufnents had not, caused corresten of other RCS a
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estarials am 1ampact$es and regalfffciMen preyins (Sint 1727, l
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April 25,1982) rumste visum1 [ M.:pr" cure..:d ins M 31metreet refle-6 1
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Sesed on the above.esamlastipos to hous esseemable assureeces that the i
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russindre of the RC$'hos amt bene sad @ected to sulfur ineced escrosten f
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- 2. 3 OTSG Examination to Botereine Extent of Deeradotten k.l j i 3
A one-hundred percent ECT wts conducted in toth OTSG to datomine the extent of degradation. Qualification testing by ECT of the twenty-nine 4'
- 'es wnich were removed along with the use of EDM notches as standards
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has demonstrated a technqiue with a high degree of sensitivity to reliably detect the circumferential defects whien were present.
Therefore, reason-able assurances exist that defective te es will be identified for repair er remeest from service.
2.4 073E Emair
&2 The repair sa..f.e. ty evelesties., dich ens issued as Octeer 13, 1982 covers the deta11s of the emplestwa W,.,,preceihre within the tubesheet.
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v additiek..nr,&:.:.the tses le the free spee (between the W) having
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.r decerts X.41E three $ y ewell (stendere pluglas criteria) will be removed i-..Orn, R3 h~.+.
fres service tg.plugles. Tees w{th defects le high cross flow zones will be stablitant M p) p.G 4'u ~ ~.ijks kiestic expansion repair metho
%;;N.9 a aw.. N establisten 4,aseleed c.; >:.x 2.C- 'ereplog jotst est primary pre
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~. y. J ;. y. s '.;:.4 s :: r-has hees qualfMed throu$ testing pregrains. Therefore, reasonable
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esearsaces emist theti the Sf53 ces be safely returned ta service arter q :..y.
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leak test $iig. D '
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.c-2.5 GTSG 4 4 c ce Evolustica $ 4secuent to sepairs The repair program will result in plugging of approximately 1100 tubes.
Analyses for all accidents and transients in the FSAR indicate that the margins of safety as defined in the technical specifications will not be reduced with up to 1500 tubes removed from service. Tbtre f ore,
no ugnificant change will result in plant performance nor will a technical specification change be required.
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2.6 Cleanuo of the Costaminant l
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Perification and flushing of all systems and tanks which contained l
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Bulk water sulfate concentrations
'su1*er leperit.las has been conducted.
l are less W 0.1 pas in the'RC5.(tie,ssting.has'shown that greater than
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bulk waterls n{e. ded'te initista corrosion).
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WemoveId asf;sighe(fissbinisethods) within the t
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x si mord' corrosive. and active. species.
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i Betarefine "si 1.h!!&lR. T. j.J&pitffcont'potentt l. exists to convert the oxide-L'
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Develop.a process for removal (desulfurize the RCS) of the oxide-trapped sulfur if testing shows a significant potential for conversion to a more active species.
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1 Onc:r. this testing is coupleted the Itcensee will meet with the staff and our consultants to discuss the results and propose a course of
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The above listed measures provide reasonable assurances that sulfur containing contaminants will not be re-introduced to tne RCS.
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The evidence at1181-1 demonstrates that tha,selfur induced corrosion s
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RC5 desulfurization will be conducted if testi.ac demonstrates that g
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it is necessary.
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