05000298/LER-1978-030, Forwards LER 78-030/03L-0

From kanterella
(Redirected from ML20148A484)
Jump to navigation Jump to search
Forwards LER 78-030/03L-0
ML20148A484
Person / Time
Site: Cooper Entergy icon.png
Issue date: 09/12/1978
From: Lessor L
NEBRASKA PUBLIC POWER DISTRICT
To: Seyfrit K
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML20148A487 List:
References
NUDOCS 7810300173
Download: ML20148A484 (2)


LER-1978-030, Forwards LER 78-030/03L-0
Event date:
Report date:
2981978030R00 - NRC Website

text

,

~

Ji CoOPcR NUCLEAR STATION P.O. BOX 98 BROWNVILLE, NEBRASKA 68321 Nebraska Pubh.c Power D. tn. t 1cLcPsoNe <4023823 3 i>

is c

.=

September 12, 1978 Mr. K. V. Seyfrit U.S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region IV 611 Ryan Plaza Suite 1000 Arlington, Texas 76011

Dear Sir:

This report is submitted in accordance with Section 6.7.2.B.2 of the Technical Specifications for Cooper Nuclear Station and discusses a reportable occurrence that was discovered on August 15, 1978. A li-consee event report form is also enclosed.

Report No.:

50-298-78-30 Report Date:

September 12, 1978 Occurrence Date: August 15, 1978 Facility:

Cooper Nuclear Station Brownville, Nebraska 68321 Identification of Occurrence:

A condition was discovered which could lead to operation in a degraded mode due to not meeting the surveillance requirements of Section 4.7.A.2.f of the Technical Specifications.

Conditions Prior to Occurrence:

Reactor was at steady state power level of approximately 95% of rated thermal power.

Description of Occurrence:

While reviewing the drawings of the drywell, thirteen (13) primary containment testable penetrations were identified which had not i

been previously noted and have not been leak tested as required by Technical Specification 4.7.A.2.f.

These penetrations are X-35A thru E (TIP penetrations) and eight (8) drywell stabilizer assembly inspection ports.

Designation of Apparent Cause of Occurrence:

The cause of these penetrations not being tested was that they were overlooked when the preoperational test was performed. The preop-erational test data was used as a base in preparation of the surveil-lance test and therefore these penetrations were not included in the inspection program.

p9' 17 t\\

787030 o/73

1 a

Mr. K. V. Seyfrit September 12, 1978 Page 2.

Analysis of Occurrence:

Penetrations X-35A thru E are used for the TIP piping to enter the d rywell.

The double 0-ring is around the outside of the flange and provides a seal between the penetration, a 2" line, and the atmosphere.

If these seals were leaking, they could allow leakage from the drywell to the atmosphere.

The eight (8) stabilizer assembly inspection ports are 16" 0.D. and are located around the perimeter of the drywell at elevation 961'10-3/4".

They are for inspection of the drywell stabilizer connections from inside the drywell. A leak from these penetrations would be from the drywell to the area between the drywell and the concrete, and eventually to atmosphere.

None of the penetrations have been opened since the last integrated leak rate test.

There has been no evidence of deterioration in the sealing material of other penetrations that were opened. Based on this fact, leakage from these penetrations would have been included during the last integrated leak rate test.

The results of this test were within acceptable limits.

This occurrence presents no adverse consequences from the standpoint of public health and safety.

Corrective Action

At the time the occurrence was noted all records were reviewed to determine if these penetrations had ever been opened. All checks were negative. All previous leak tests and the preoperational test were reviewed and indicated these penetrations had not been tested.

Penetration X-35A thru E were checked for external leakage by soap bubble inspection and no leaks were identified.

Due to location and radiation levels in the TIP area, it was prudent not to leak test between the seals while operating.

The thirteen (13) penetrations have been added to the procedure for local leak rate testing (S.P. 6.3.1.1) and a revision to Table 3.7.2 of the Technical Specifications has been initiated.

These penetrations will be leak tested at the first available opportunity.

Sincerely, L. C. Lessor i

Station Superintendent Cooper Nuclear Station LCL:cg Attach.