ML20087A711
| ML20087A711 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 12/05/1969 |
| From: | Kirkman R US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Ritter G JERSEY CENTRAL POWER & LIGHT CO. |
| Shared Package | |
| ML20086U000 | List:
|
| References | |
| FOIA-95-36 NUDOCS 9508070135 | |
| Download: ML20087A711 (1) | |
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DEC 5 19N 34-l t
Jersey Central power and Light Ccapany Hadison Avenue at punchbowl Road Morristown, !!aw Jersey 0740 Atteention: Mr. Ocorse E. Ritter, Vice President i
Centlemma:
This letter relates to the discussion Messrs. R. T. Carlsen, R. T. Dodds, and D. L. Caphtoa of this offios held with yes and se veral members or your staff concerning a recent insp<ction of your Oyster Creek reactor facility.
As a result of this inspection, three of yoor Licensed activities appear
- to be in moncompliance with Atc requiream:ats. The items and references te i
the pertinent requirements are listed La pesagraph 5 on Foss ACC=$12, en-closed.
The purposa of this letter is to give you as opportunity to advise us in writing of (a) your position concerning these items, (b) any corrective steps you have taken er plan to take with respect to.the itees listed on the eeclosed form, and (e) the date corrective action was or will be com-pleted. Year reply abould be sent to me within 20 days of the date of this letter to assure that it will ressive proper attentian is our further evaluation of the metter.
i Should you have any questions concerning this matter, you any communicate directly with this office.
i Very truly yours,
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Robert W. Eithman f"./ !
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e 3944 December 18, 1969 J. P. O'Reilly, Chief, Reactor Inspection & Enforcement Br.,
Division of Compliance, Headquarters INQUIRY MEMORANDUM JERSEY CENTRAL POWER AND LIGHT CO. (OYSTER CREEK 1), 219/69-I LEAKAGE THROUGH MAIN STEAM ISOLATION VALVE Information obtained during the inspection at OC-1 on December 3-5,1969, disclosed that there may be significant steam leakage through one of the steam isolation valves (numbered as either V-1-8 or NSO3B) when closed.
Data obtained following the isola-tion valve trip test at 800 Mwt on November 9, 1969, showed that the pressure in the 24" downstream lines and 30" header increased from 440 psig to 660 psig within 5 minutes, apparently from leakage from V-1-8.
Little or no leakage was apparent through the other three steam isolation valves.
At the time of the December inspection, Mr. Diefenderfer, GE Principal Test and Design Analysis Engineer, stated that the November test only indicated there may be steam leakage and that the leakage rate would be measured during the isolation valve trip test at 1600 Mwt.
Mr. McCluskey, Oyster Creek Station Superintendent, was contacted on December 9, 1969, subsequent to the isolation valve trip test to obtain the results of the leakage rate measurements.
t Mr. McCluskey stated that he was not aware of a steam leakage f
problem with the isolation valves but he would look into this matter.
The following day Mr. McCluskey informed the inspector, R. T. Dodds,
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that it appears there may be steam leakage through the valve when f
a high differential steam head exists across the valve.
- However, they could not correlate the steam leakage problem to the technical specification limit of 11.5 cubic feet per hour of air with a differential pressure head of 20 psi.
He stated that this was the first time he or his principal staff as well as Mr. Hess, GE Site Manager, had been made aware of the fact that there may be a steam leakage problem.
Evidently, the test engineers had neglected I
M to properly inform their management of this problem.
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9 Additional-isolation valve tests were run at the conclusion of-the 1600 Mwt transient test program on December 12-13, 1969.
The results of the test were as follows:
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Reactor
. Initial Header Final Header Length of Valve No.
Pressure Pressure Pressure Test NS03A 1035 peig 270 peig 320 psig 2 min.
NS038 880 psig 180 psig 360 peig 2 sin.
N804A 1000 psig 210 psig 260 psig 2 min.
NSO4B 850 psig 160 peig 210 psig 2 min.
The Plant Operations Review Committee (PORC) met on December 13, l
1969, to review the results of the steam leakage test.
They concluded that-the transient test program has subjected the valve to at least the equivalent of a year's usage under normal operating conditions and that DRL'must have made allowances for deteriora-tion of the system in establishing the surveillance test criteria.
No one, after extensive research and study, was able to correlate the steam leakage problem to the technical specification limit for air leakage.
Also, the system when isolated (all four valves closed) was tight.
Therefore, the accident analysis should be predicated upon a steam line break with maximum steam leakage through the valve (calculated by GE to be 100 lbs/ min of steam with 0.1 lbs/ min of water carryover) and having the reactor coolant contained the maximum allowable radioactivity.
The GE i
analysis indicated that, under these~ conditions, the ground level release rate would be 300,000 uCi/see which would'give a thyroid dose at the site boundary of 0.1 mr/hr.
Pending verification of GE's calculations PORC roccamended that the 1600 Mwt warranty run.
be conducted and that the plant be shutdown at some future date (timely date) to check the isolation valve.
PORC believed that there was technical justification for the position that no provisions of the technical specifications had been or would be violated by proceeding in this manner.
On December 15, 1969, the General Office Review Board (GORB) met with representatives of the OC-1 operating staff and GE to review the entire valve leakage question.
They satisfied themselves as
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. to the validity of GE's calculations for site boundary exposure in the event of steam line break.
GORB concluded that it was acceptable to continue with the 1600 Mwt warranty run and that the plant should be shutdown in a timely manner to check the isolation valves and repair as necessary.
The outage would occur
-some time after January 1, 1970, but not entil the necessary materials were on hand to effect modification of the turbine I
steam separator and reheater drain tank systems as well as the air ejector drain tank system.
The reactor was not operated from the time of the turbine trip test on December 13, 1969, until after GORB had completed its meeting and the results of this meeting as well astthe JC-manage-ment decision had been communicated to the inspector on December 15, 1969.
Messrs. McCluskey and Kelcoc stated that Mr. Ritter, JC Vice President, would inform Dr. Morris, Director, DRL by telephone on December 16, 1969, of the results of their evaluation.
Presumably this communique would be followed with a written report.
The inspector had frequent discussions with Mr. McCluskey during the period of December 9-15, 1969.
This matter will be reviewed furhher during the next inspection tentatively scheduled for the week of January 5, 1970.
R. T. Carlson Senior Reactor Inspector cca E. G. Case, DRS R. S. Boyd, DRL (2)
S. Levine, DRL D. J. Skovholt, DRL (2)
L. Kornblith, Jr., CO Regional Directors, CO REG Files
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DEC P31969 J. P. O'Reilly, Chief, Reactor Inspection and Enforcement Branch, l
Division of Compliance, Headquarters i
INQUIRY HDiORANDUM JERSEY CENTRAL POWER AND LIGHT COMPANY (OYSTER CREEK 1) 219/69-J i
INITIATION OF CO)MERCIAL OPERATION i
A telecon with T. McCluskey, Station Superintendent, on December 23, 1969 revealed that the 100 hour0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> full power warranty run was completed at 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br /> on December 22 and the plant declared in commercial' operation at 0001 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> on December 23, 1969.
r R. T. Carlson j
Senior Reactor Inspector cc:
E. G. Case, DRS R. S. Boyd, DRL (2)
S. Levine, DRL D. J. Skovholt, (2)
L. Kornblith, Jr., CO Regional Directors Reg. File e
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