IR 05000219/1974012
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UNITED ST ATES
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ATOMIC ENERGY COMMISSION oinscTon Avr or necut.arony open ARSONS nEGION l
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E 631 PARK AVENUE
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KING OF PRUSSI A, PENNSYLVANI A 19406 i
JUL 181974
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Jersey Central Power and Light Docket No. 50-219 r
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Company Licens,e No. DPR-16 h'
ATTN Mr. Ivan R. Finfrock, Jr.
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Vice President - Generation Madison Avenue at Punch Bowl Road b
Morristown,-New Jersey 07960
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L Gentlemen:
This refers to the inspection conducted by Mr. Walton of this office on June 6, 7, 17, 22 and July.11, 1974 of activities authorized by AEC License No. DPR-16 and to the discussions of our findings.
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held by Mr. Walton with Mr. Reeves of your staff at the conclusion
of the inspection.
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Areas examined during this inspection are described in the Regulatory Operations Inspection Report which is enclosed with this letter.
Within these areas, the inspection consisted of selective====fnations of procedures and representative records, interviews with personnel, and observations by the inspector.
Within the scope of this inspection, no violations or safety
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items were observed.
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Giffi
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In accordance with Section 2.790 of the AEC's " Rules of Practice",
Part 2, Title 10, Code of Federal Regulations, a copy of this
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letter and the enclosed inspection report will be placed in the AEC's Public Document Room.
If this report contains any information that you (or your contractor) believe to be proprietary, it is
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necessary thst you make a written application within 20 days to this office to withhold such information from public disclosure.
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Any such application smast include a full statement of the
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reasons on the basis of which it is claimed that the information e
is proprietary, and should be prepared so that proprietary
information identified in the application is contained.in a separate part of the document.
If we do not hear from you in
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j this regard within the specified period, the report will be placed in the Public Document Room.
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9604180034 960213 i
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Jersey Central Power and Light-2-
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'No reply to this letter is required; however, should you have any questions concerning this inspecties, we will be plassed te discuss.
than with you.
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Sincerely,
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Robert T. Carlson, Chief Facility Construction and Engineering Support Branch Encloshe 30 Inspection Report No. 50-219/74-12
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ces Mr. J. T. Carroll, Station Superi=*=d-e j
bec (w/encis):
R0 Chief FS&EB RO:HQ (5)
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DR Central Files
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Local PDR D
RO Files NEIC DTIE i
Stae of New Jerwey RO Directors (II, III, IV) (Report Only)
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OGC Mr. A. Z. Roisman, Counsel for Citizens Committee for Protection
.j of the Environment i
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UNITED STATES ATOMIC ENERGY COMMISSION
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WASHINGTON D.C. 20545
JUL 16 1974 J. P. O'Reilly, Director, Region I JERSEY CENTRAL POWER AND LIGHT COMPANY (JCP&L) OYSTER CREEK, LEAK IN
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BOTTOM VESSEL HEAD AT INSTRUMENT PENETRATION PEF: YOUR MEMO TO J. G. DAVIS DATED JUNE 19, 1974, SAME SUBJECT In accordance with your memo, we have contacted Licensing regarding this matter. We are informed. that the licensee has committed in writing to perform a visual inspection of all instrument penetrations at the next scheduled outage.
In addition, leakage tests will be performed during each scheduled outage.
In regard to unidentified leakage surveillance, Licensing believes the existing program to be appropriate for continued surveillance. A copy of Licensing's safety evaluation is attached.
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Karl V. Sey t, Chief
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Technical Assistance Branch Directorate of Regulatory Operations
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Enclosure:
As Stated
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J. G. Davis B. H. Grier H. D. Thornburg J. H. Sniezek e
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uni 1co srtres ATOMIC ENERGY COMMISSION
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WASHl5GTON. D.C. 20$45
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June 24, 1974
~m-Docket No. 50-219
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Jersey Central Power & Light Company ATTN:
Mr. I. R. Finfrock, Jr.
Vice President - Generation Madison Avenue at Punch Bowl Road
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Morristown, New Jersey 07960 Gentlemen:
Your letter dated June 17, 1974, submitted "Special Report of Investigations and Repair of Incore Flux Monitor Penetration" for the Oyster Creek Station.
We have evaluated this report and concur with your resolution of
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this matter.
The basis for our conclusion is presented in our Safety Evaluation, a copy of which is enclosed.
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Sincerely,
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Karl R. Goller, Assistant Director for Operating Reactors Directorate of. Licensing Enclosure:
Safety Evaluation cc w/ encl:
See next page
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Jersey Central Power & Light Co.
-2-June 24','1974
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cc w/ enclosure:
ec w/ enclosure and cy of JCP&L ltr i
G. F. Trowbridge, Esquire dtd 6/17/74:
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Shaw, Pittman, Potts & Trowbridge Mr. Paul Arbesman
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910 - 17th Street, N. W.
Environmental Protection Agen'cy Washington, D. C.
20006 26 Federal Plaza
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GPU Service Corporation ATTN: Mr. Thomas M. Crinsnins George F. Kugler, Jr.
Safety & Licensing Manager Attorney General'
260 Cherry Hill Road State of New Jersey Parsippany, New Jersey 07054 State House Annex
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Anthony Z. Roisman, Esquire Berlin, Roisman and Kessler 1712 N Street, N. W.
Washington, D. C.
20036 Paul Rosenberg, Esquire Daniel Rappoport, Esquire j
i 2323 S. Broad Street Trenton, New Jersey 08610
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Honorable Joseph W. Ferraro, Jr.
. Deputy Attorney General State of New Jersey 101 Commerce Street - Room 208
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Neward, New Jersey 07102
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Ocean County Library 15 Hooper Avenue Toms River, New Jersey 08753
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Burtis W. Horner, Esquire Stryker, Tams and Dill 55 Madison Avenue Morristown, New Jersey 07960 Honorable William W. Mason Mayor, Lacey Township P. O. Box 475 Forked River, New Jersey 08731 i
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UNITED STATES
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I WASHINGTON, D.C. 20545 i
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I SAFETY EVALUATION BY TIIE DIRECTORATE OF LICENSING
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JERSEY CENTRAL POWER & LIGi!T COMPANY OYSTER CREEK NUCLEAR GENERATING STATION
DOCKET NO. 50-219
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Introduction In an. abnormal occurrence report dated May 30, 1974, Jersey Central Pouer a'nd Light Company (JCPL) reported the detection of a small leak of primary coolant from incore flux monitor penetration 05-28 in the Oyster Creek reactor vessel.
On June 13 and 14, 1974, representatives of the Licensing staff reviewed records of weld repairs of the incore flux monit'or housing
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welds performed in 1968 and held discussions regarding the occurrence with JCPL replesentatives at the Oyster Creek site.
The results of the review and discussions are contained in a report of the meeting dated June 21, 1974.
In a Ictter dated June 17, 1974, JCPL submitted "Special Report of
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Investigations and Repair of Incore Flux Monitor Penetration" regarding the repair of the leak from the incore flux monitor penetration 05-28'in
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the Oyster Creek reactor vessel.
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P Evaluation
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Leakage from the incore f1ux monitoring housing penetration of the Oyster Creek reactor vessel at location 05-28 was observed _ during an inspection
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while the reactor was subjected to 850 psig at 164*F.
The leakage was
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l measured to be about 0.02 spm, which is well within the allowable unidentified leakage rate f rom the primary coolant system of 5 gpm during plant operation.
A visual inspection of all penetrations in the bottom head of the reactor vessel was conducted by JCPL after removal of the insulation from the bottom head. One control rod drive penetration (18-47) had traces of calcium carbonate deposit around the penetration, but these trace deposits were proved to be non-radioactive.
The particles removed from the vessel around incore flux monitor housing 05-28, however, were radioactive. All other penetrations
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There were no indications of leakage around s
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control rod drive penetration 18-47 during pressure tests conducted to
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-verify the incore flux monitor penetration leakage.
We concur with JCPL's
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conclusions that any leah that might have occurred in this control rod-
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l drive penetration was apparently sealed prior to operation of the reactor.
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The 304 stainless steel incore flux monitor housing, 05-28, and the inconel
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weld joint of the housing _ to the vessel were' subjected to eddy current 'and ultrasonic tests and no defects detected. Helium sniff and additional
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i pressure tests verified that the leakage was.not through the 1/4" vall of the incore flux monitor housing.
It was then postulated that weld. slag
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inclusions, so small as to be undetectabic by nondestructive test techniques,
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- may have linked together to cause a small leakage path through the inconel weld. JCPL concluded, and we agree, that based on the UT and eddy current tests results, the s'trength of the weld is not significantly impaired. 'JCPL
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proposed, however, to install a mechanical restraint below the lower flange
'of incore flux monitor housing 05-28 to prevent the possibility of ejection i
of the housing'from the reactor vessel in the unlikely event of a complete
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failure of the housing or the weld.
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In the abnormal occurrence report dated May 30, 1974, JCPL referenced an analysis of the consequences of a loss-of-coolant accident (LOCA) resulting
from the postulated failure of an incore flux monitor tube.
The penetration
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inthebojtomheadforanincorefluxmonitortubehasabreakareaof
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0.0218 ft. Assuming the worst conditions (which are considered to be the availability of only a single loop of core spray cooling and operating at
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full power) at the time of the LOCA, the fuel peak clad temperature is calculated to be less than 1000'F (reference FSAR Amendment No. 67), which is well below the acceptable limits (2300*F) of the ECCS Interim Acceptance Criteria. JCPL states, and we agree, that the likelihood of such an
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accident resulting f rom the leakage detected in the incore flux monitor
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l housing 05-28 is highly improbable.
The reasons for this conclusion are 1) the leakage area is calculated to be the equivalent' to a 1 mil
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~3(inch) orifice, (2) periodic checks will be made in the future to inspect l-that (10
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for leakage and (3) only 0.2 inch of weld metal would retain ghe housing
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in the vessel and the nominal weld area is in excess of 6 inch p
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JCPL proposes to seal the leak by rolling the incore flux monitor housing against.the reactor vessel hole. As explained in the June 17, 1974, JCPL
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. report, this process of rolling is not unique for sealing against leakage
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under high differential pressure. The nominal diametral clearance between
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i the housing and the vessel surface is 10 mils.
The operation to seal this cicarance will be performed using procedures and equipment for rolling
tubes in high pressure boilers, feed heaters, and other applications.
The rolled joint will start about 1/4 inch below the weld and extend belou i
the weld for a distance of 6 1/4 inches. This joint will be similar to l
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- s those used in nuclear steam generators. In addition General Electric Company (GE) has reported in an informal memo to 'JCPL (and verified by the staff at the site) that this type of repair has been successfully used to repair leakage from a similar incore flux monitor housing in 'the reactor vessel Furthermore, GE has stated that bottom head at the SENN plant in Italy.
the SENN plant has now operated for about 8 years since the repair was made and no leakage has reoccurred in the repaired penetration.
JCPL has stated that the following tests will be performed on the incore flux monitor penetration prior to reactor operation:
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UT and eddy current tests of the rolled portion of the housing,
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and (2)
Inspection for leakage from the repaired area with the reactor
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vessel pressurized to 850 psig.
JCPL has also stated that leakage tests will be performed af ter each scheduled outage and af ter conduct of any maintenance operation which requires primary
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system leak testing, and that a visual inspection of all penetrations in the bottom head of the Oyster Creek reactor vessel will be made during
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We the next refueling outage to verify all penetrations are leak tight.
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' conclude that these surveillance measures will provide reasonable assurance that future similar defects can be located before they progress to a point of failure.
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Conclusion
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Based on the above evaluation, the staff concludes that there is reasonable the health and safety of the public will not be endang'ered j
assurance that j
by operation in the proposed manne..
Date: June 24, 1974
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