ML20215H112

From kanterella
Jump to navigation Jump to search

Forwards marked-up Radiological Environ Tech Spec Reflecting Correction to Amend 86 for License DPR-40,issued on 860403. Annotation of Amend Number on Page 2-46 Also Requested in Future Amend
ML20215H112
Person / Time
Site: Fort Calhoun 
Issue date: 10/08/1986
From: Andrews R
OMAHA PUBLIC POWER DISTRICT
To: Sells D
Office of Nuclear Reactor Regulation
References
LIC-86-487, TAC-62967, NUDOCS 8610210462
Download: ML20215H112 (2)


Text

,

Omaha Public Power District 1623 Harney Omaha, Nebraska 68102 2247 402 536 4000 October 8, 1986 LIC-86-487 Mr. Donald E. Sells, Project Manager PWR Project Directorate #8 Division of ?WR Licensing - B U.S. Nuclear Regulatory Commission Washington, DC 20555

References:

(1)

Docket No 50-285 (2)

Amendment 86 to Facility Operating License DPR-40, dated April 3, 1986

Dear Mr. Sells:

Radiological Environmental Technical Specifications (RETS) for the Fort Calhoun Station The Omaha Public Power District received, in 1985, Amendment 86 to the Fort Cal-houn Station Technical Specifications incorporating RETS.

Consistent with OPPD procedures, a review of the amendment "as-issued" against the "as-subraitted" version was conducted.

Since that time onc item has been found which was sub-mitted to the NRC in an earlier version of RETS, was verbally concurred with, and which was incorrectly submitted in the final application.

Attached is the "as-issued" page of the Fort Calhoun Station Technical Specifications with the item noted.

This information has been previously discussed with you.

Additionally, Page 2-46 was issued as a part of the Amendment 86 package. How-ever, " Amendment 86" does not appear at the bottom of the page.

OPPD requests 1

that these items be corrected in a future amendment.

If you have further ques-tions, please do not hesitate to contact us.

Sincerely, 8610210462 861008

~^,[g:p

/

PDR ADOCK 05000285 P

PDR R. L. Andrews Division Manager Nuclear Production RLA/DJM/rh Attachment cc:

LeBoeuf, Lamb, Leiby & MacRae I

1333 New Hampshire Avenue, Pl.W.

Washington, DC 20036 Mr. P. H. Harrell, NRC Senior Resident Inspector v,,, e,

, mm...gn,.nn, o e on.ii om,nunay

%t e I t*m.llt' l

  • 1.

+

I 2.0 LIMITING CONDITIONS FOR OPERATION 29 Radioactive Effluents (Continued) g

'2.9.1

_Liould and Gaseous Effluents (Continued)

(1) Specificaticns for Liould Waste Effluents a.

(i)

The release rate of radioactive material in liquid effluents shall be controlled such that the instan-taneous concentrations for radionuclides, other then dissolved or entrained noble gases, do not exceed the values specified in 10 CFR Part 20, Appendix B, for unrestricted areas. For dissolved or entrained noble rasee the concentration shall be limited to 2.0 E-04 4

mci / ' total activity.

,jaCi'ry)(

(ii)

With the concentration of radioactive material released

/

to unrestricted areas exceeding the above limits,

appropriate corrective actions shall be taken immediately to restore concentrations within the above limits, b.

The cumulative dose contributions from radicactive materials in liquid effluents released to unrestricted areas shall be deter-mined, in accordance with the ODCM, on a quarter'ly basis.

If the dose contributions, due to the cumulative release of liquid effluents averaged over a calendar quarter, exceed one-half of the design objectives, the folleving course of actions shall be taken:

(i)

Make an investigation to identify the causes for such releases.

(ii)

Define and initiate a program of action to reduce such releases to the design levels.

(iii) Submit a special report, pursuant to Specification 5 9.3, within 30 days from the end of the quarter during which release occurred, identiRying the causes and describing the proposed program of action to reduce such release to the design levels.

The equipment or subsystem (s) of the liquid radvaste treatment c.

system as identiried in the ODCM shall be operated prior to the discharge of radioactive materials in liquid vastes.

If the radioactive liquid vastes were discharged without treatment by one or more of the pieces of equipment or subsystem (s) identified in the ODCM and it appears that one-half of the annual objective vill be exceeded during the calendar quarter, a special report, pursuant to Specification 5.9.3, shall be prepared and submitted to the Commission within 30 days.

This report shall include the following information:

(i)

Identificaticn of equipment or subsystens not operable and reason for inoperability.

2 kl Amendment No. 23, 86