ML20128F657

Comment on Proposed Generic Communication Re Primary Water Stress Corrosion Cracking of Control Rod Drive Mechanism & Other Vessel Head Penetrations

ML20128F657
Person / Time
Site:	Fort Calhoun
Issue date:	09/26/1996
From:	Tira Patterson OMAHA PUBLIC POWER DISTRICT
To:	NRC OFFICE OF ADMINISTRATION (ADM)
References
FRN-61FR40253 61FR40253-00002, 61FR40253-2, NUDOCS 9610080152
Download: ML20128F657 (2)

Text

'

gj D

~

.,y 6/ 69 VO22 T A4'ak,e gyp, ,, pyg

""M=-== ,p.

Omaha P7blicP7werDistrict L U US 444 South 16th Street Mall PYl * '**. "

Omaha NE 681F'-2247 9Q September 26, 1996 LIC-96-0122 U. S. Nuclear Regulatory Commission Attn: Chief, Rules Review and Directives Branch Mail Stop T-6D-69 Washington, D.C. 20555-0001

References:

1. Docket No. 50-285

2. Federal Register Volume 61, No.149, dated August 1, 1996 (61 FR 40253)

Subject:

Comments on Proposed Generic Communication Regarding Primary Water Stress Corrosion Cracking of Control Rod Drive Mechanism and Other '

Vessel Head Penetrations The Omaha Public Power District (0 PPD) has reviewed the proposed generic communications regarding primary water stress corrosion cracking of control rod drive mechanisms and other vessel head penetrations. OPPD, as the licensee for Fort Calhoun Station and a member of the Combustion Engineering Owner's Group (CEOG), has been monitoring this issue and has been involved in the development of the initial CE0G susceptibility assessments for the CEDM nozzles at CE0G >

plants. OPPD plans to participate in an updated assessment of the CEDM nozzles, which will incorporate the results of the CEDM testing performed at the Palisades nuclear plant.

OPPD has the following specific comments on the proposed Generic Letter:

1. It should be noted in the background information that no CEDM nozzles in any plants worldwide have failed during plant operation. Evidence of .

cracking has been revealed during planned inspections. As alluded to in the proposal, any through-wall cracking would be slow, result in ..

detectable leakage, and provide an opportunity to take corrective action, because the leak rates of primary systems are tracked during the operation of all nuclear plants.

2. The proposed response period of 90 days may be insufficient given the recognized potential data collection difficulties and the fact that the owners groups may still be completing or updating their susceptibility assessments. We suggest that the NRC staff coordinate the issuance and response timing of the Generic Letter with the owners groups.

ggooy 52 960926 } , ( ([,

MISC PDR 45 5124 Employment with Equal Opportunny p ?yg jg

e n-

,i ll U. S. Nuclear Regulatory Commission LIC-96-0122 Page 2 Please contact me if you have any questions.

Sincerely, -

db(w c)Ak)

T. L. Patterson I#' i Division Manager Nuclear Operations TCM/ tem

, c: Winston & Strawn l L. J. Callan, NRC Regional Administrator, Region IV L. R. Wharton, NRC Project Manager W. C. Walker, NRC Senior Resident Inspector

,