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U. S. ATOMIC ENERGY COMMISSION Region I DIVISION OF COMPLIANCE Report of Inspection CO Report No. 219/69 d 7
Licensee:
JERSEY CENTRAL POWER & LIGHT COMPANY (Oyster Creek 1)
License No. DPR-16 Category B D3tes of Inspections:
July 23, 1969 August 1, 1969 Dates of Previous Inspection:
July 17-19, and 28-29, 1969 Inspected by:
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w R. T. Carlson, Senior Reactor Inspector Date (Responsible Inspector)
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s F. J. Nolan, Senior Reactor Inspection Specialist Date Rcviewed by:
O M ko M 9f20!69 f/. G. Ke@Fler, Senior Reactor Inspection Date Specialist Proprietary Information:
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SUMMARY
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Sprcial inspection visits were made to the site on July 23, 1969 and August 1, 1969 for the purpose of reviewing the status of certain of the issues remaining to be resolved before CO could recommend the issuance of the Provisional Operating License for full power operation.*
A brief j
summary of the issues and their status follow:
1.
Leak Rate Testing of Main Steam Isolation Valves The four valves have been successfully tested with measured leakage
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rates less than the maximum allowable.
- Status of all the outstanding issues discu3 sed in memorandum, Engelken to Morris " Jersey Central Power and Light Company (Oyster Creek)
Docket No. 50-219", dated August 1, 1969.
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Leak Rate Testing of Reactor Building
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Testing following completion of modifications to the railroad air-4 lock doors showed the. leakage rate to marginally meet the require-ments of the Technical Specifications.
The licensee is attempting to locate and correct.the source of the existing leakage.
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additional tests will be conducted at various wind conditions.
3.
Reactor Safety Valves Sixteen Dresser safety valves have been properly tested and in-stalled.
DETAILS I.
Scope of Visits L
A special inspection visit was made to Jersey Central Pr.:.: & Light Company's Oystar Creek 1 reactor facility on July 23, 1969 by Mr. F.
J. Nolan, Senior Reactor Inspection Specialist, CO:HQ, Mr.
D. L. Caphton, Reactor Inspector, CO:I, and Mr.
R. T. Carlson, Senior Reactor Inspector, CO:I.
The purpose of the visit was to review the results of recent leak rate tests performed on the main stream isolation valves and on the reactor building.
A special visit was also made to the facility by Mr. Carlson on August 1, 1969 for the purpose of verifying the proper testing and in-stallation of the sixteen safety valves.
The results of additional reactor building leak rate tests were also reviewed at this time.
Because of the nature of the subject matter reviewed during these inspections, the construction phase inspection format is being used to document the results.
j The principal persons contacted during the visits were as follows:
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A.
July 23, 1969 visit Jersey Central Power & Light Company (JC)
T. J. McCluskey, Plant Superintendent I. R. Finfrock, Technical Supervisor v
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3 Jersey Central Power & Light Company (JC) (Cont ' d)
D. A. Ross, Technical Supervisor (In-Training) h R. W. Sullivan, Assistant Technical Engineer General Electric Company (GE)
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K. W. Hess, Site Operations Manager B.
August 1, 1969 Visit Jersey Central Power & Light Company T. J. McCluskey, Plant Superintendent f
I. R. Finfrock, Technical Supervisor D. A. Ross, Technical Supervisor (In-Training)
General Electric Company K. W. Hess, Site Operations Manager R. C. Haynes, Lead Mechanical Engineer II.
Results of Visits A.
Results of July 23, 1969 Visit 1.
The results of the subject special visit were documented in a memorandum from Mr. F. J. Nolan to Dr. M. M. Mann,_" Jersey Central Power and Light Company - Oyster Creek Docket No.
50-219", dated July 25, 1969.
For purposes of continuity in reporting, a copy of the referenced memorandum is attached hereto.
B.
Results of August 1, 1969 Visit 1.
The inspector visually confirmed that 16 six-inch Dresser safety valves were installed in the design location on the j
main steam headers, upstream of the inboard main steam
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isolation valves.
At the time of the inspection, final i
torquing of the valves was underway.
Installation of the j
valve blowdown pipes and related leak detection thermocouples i
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- was also underway and scheduled to be completed on August 2, 1969.
Pertinent valve name plate data, obtained from site records T
and visually confirmed on a sampling basis, is tabulated 3
below:
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~h Valve
- il Number Set Point, psig Capacity, #/hr
,p-BK-6268 1212
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BK-6270 1212
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630,150 each BK-6278 1212
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(630,120)*
BK-6310 1212
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i BK-6266 1221
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BK-6274 1221
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'634,780 each BK-6311 1221
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(634,240)*
BK-6534 1221
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l BK-6233 1230
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j BK-6259 1230
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639,400 each i
BK-6265 1230
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(639,360)*
j BK-6315 1230
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BK-6247 1239
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BK-6264 1239
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644,030 each BK-6320 1239
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(643,990)*
BK-6324 1239
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j The site records indicate that the valves set points were tested, using steam, in the Dresser facilities in Louisiana
.i j ust prior to shipment to the site.
The set points as shown above are in accordance with the requirements of the l
Technical Specifications, paragraph 2.3.6).
The records show that a GE representative witnessed the testing of 8 of the valves.
A letter from B. G.
Brunson, Chief Inspector',-
Dresser, certifies to the proper testing of the other 8 l
valves.
The wrong valve capacity numbers had originally been stamped on the name plates.
Dresser discovered this subsequent to shipping the valves to the site.
GE was in-the process of stamping the correct capacity numbers on the i
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- Valve capacity numbers presented in Amendment 45, page IV-2-6.
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valves at the tima of this visit.
2.
Reactor-Building Leak Rate Test s- ;
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Installation of the permanent cam style latches'on.the rail '
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road. air lock doors, in an attempt to achieve greater sealing s
capabilityilhad been completed at the time of this visit.
. j; Sub' sequent testing wit'h the inner door open and the outer i
door closed gave a leak rate. indication of: 0.28 inches water ;
-'t vacuum at a wind velocity of 17 mph.
(Technical Specifica-tion requirement - 0.25-inches water vacuum at calm wind conditions.)
A test performed with both doors closed:gavev results of 0.252 ' inches water vacuum at a wind velocity of 15 mph.
JC-GE had expected to achieve better results in the both doors closed case.
Discussions with Mr. Ross.
(coordinator of reactor building leak rate: testing for'JC) indicated that the problem appeared to be associatedivith the recently installed permanent door sealing. mechanisms.
At the. time of the visit, JC-GE were 'att'empting -to locate and correct the source of leakage.
In addition,-per Mr.
McCluskey, further tests will be conducted at varicos wind conditions with both railroad air lock doors closed and with the inner door open.
C.
Exit Interviews Exit interviews were held with Messrs. McCluskey and Hess at the conclusion-of each of the visits.
The discussions centered principally around the reactor building leak rate tests and-the work related thereto that remained to be.done at the conclusion of each visit. ~ Pertinent comments. pertaining to this matter are contained within the body of the report.
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