ML19321A095

From kanterella
Revision as of 04:39, 1 February 2020 by StriderTol (talk | contribs) (Created page by program invented by StriderTol)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
First Interim Deficiency Rept Re Reactor Pressure Vessel Shroud Head & Moisture Separator Assembly Fire.Reactor Pressure Vessel Assembly Was Initially Hydroblasted W/ Demineralized Water.Assembly Will Be Cleaned Thoroughly
ML19321A095
Person / Time
Site: Phipps Bend  Tennessee Valley Authority icon.png
Issue date: 07/14/1980
From:
TENNESSEE VALLEY AUTHORITY
To:
References
NCR-PBNP-106, NUDOCS 8007220450
Download: ML19321A095 (3)


Text

-

.w ., a TENNESSEE VALLEY AUTHORITY CHATTANOOGA. TENNESSEE 37401 -

400 Chestnut Street Tower II l

July 14, 1980 i

Mr. James P. O'Reilly, Director Office of Inspection and Enforcement l U.S. Nuclear Regulatory Commission Region II - Suite 3100 101 Marietta Street Atlanta, Georgia 30303

Dear Mr. O'Reilly:

l l

PHIPPS BEND NUCLEAR PLANT - REPORTABLE DEFICIENCY - RPV SHROUD HFC AND MOISTURE SEPARATOR ASSEMBLY FIRE (NCR PBNP-106)

Initial notification of the subject deficiency was made to R. W. Wright l on June 13, 1980. In compliance with paragraph 50.55(e) of 10 CFR '

Part 50 we are enclosing the first interim report of the subject deficiency. TVA anticipates transmitting the final report on or before September 23, 1980. If you have any questions, please call Jim Domer at FTS 857-2014.

Very truly yours, l TJNESSEE VALLEY AUTHORITY l

L. M. Mills, Manager Nuclear Regulation and Safety Enclosure cca Mr. Victor Stallo, Jr., Director Office of Inspection and Inforcement

[

U.S. Nuclear Regulatory Commissian Washington, DC 20555 30/f

'r 8007220pgG An Equal Opportunity Emotoyer

~

PHIPPS EEND NUCLEAR PLANT UNIT 1 REACTOR PR3SSURE VESSEL SHROUD HEAD AND MOISTURE SEPARATOR ASSEMBLY FIRE- -

10 CFR PART 50.55(e) REPORT NO. 1 (INTERIM)- ,

NCR PBNP-106 On June 13, 1980, TVA notified NRC-0IE, Region II, Inspector R. W. Wright, of a potentially reportable condition under 10 CFR Part 50.55(e) regarding a fire which was ignited in and around the Phipps Bend unit 1 reactor pressure vessel (RPV) shroud head and moisture separater assembly (MS assembly).

This is the first interim report on the subject reportable ccndition. A final report will be transmitted to you on or before September 23, 1980.

Description of Deficiency -

In the process of shipping the Phipps Bend unit 1 vessel or

  • RPV MS assembly to the site, personnel of the VSL Corporation, Los Gatos, california, *

(the hauling contractor) attempted to remove lugs near the RPV MS assembly shipping crate by are air gouging and inadvertently ignited the shipping crate. The fire partially consumed the shipping crate and tarpaulin and burned and/or melted the polyethylene cover which was around the RPV MS assembly inside the crate.

The damage to the RPV MS assembly includes:

(a) Discoloration of the stainless steel due to smoke.

(b) Melted polyethylene adhering to the inside and outside surfaces of the steam separators.

(c) Possible halogen contamination as the fire was extinguished with chlorinated water.

(d) Possible material sensitization due to the heat generated from the fire.

The GE data package on the RPV MS assembly indicates that it is made of 304L stainless steel except for the bolting assemblies which are made of inconel and are on the periphery of the assembly. These materials would" not be expected to exhibit sensitization or cracking problems due to the fire and subsequent contamination.

Corrective Action TVA initially hydroblasted the RPV MS assembly with demineralized water.

TVA and GE metallurgists have examined the contaminated surfaces of the RPV MS assemblf. They found the surface contamination of " free Halogens" to be low (less than the RDT 0.08 mg/dm2 acceptance criteria). Random liquid penetrant examination of several of the moisture separator tubes which appeared to have the most severe (worst case) heat damage showed no indication of cracking. Also, in situ metallographic examination of two random worst case locations disclosed no evidence of sensitization in these areas.

  • w6 .,.~=ee

. O 46 g g Qhl$ O 'y l"

> e y hw ,

6 ee[ ne m

_* 90 e e ' **

  • _,

. --, n. .. - .---..-:_..~-~.~...;.-

" a TVA and GE removed three samples (two from the worst case locations and one from a clean area for comparison) for additional laboratory examination and tests by GE in their San Jose, California, laboratory.

TVA has recommended that the following steps be taken:

(a) The RPV MS assembly should be thoroughly cleaned using approved cleaning procedures.

(b) Areas from which samples were taken should have the rough edges smoothed and blended with surrounding metal (GE has indicated replacement of sampled areas is not necessary).

(c) Dimensional verification be performed. .

(d) A verification check of the assembly should be made to ensure contaminants have been removed to an established acceptable level before acceptance for use.

(e) The MS assembly should be repackaged and protected from further -

damage. _

l

)

i l

l 1

. I l

\

1 ---,,-

.e_