ML17292B672

From kanterella
Jump to navigation Jump to search

Informs That Encl Questions Were Transmitted by Fax to Arbuckle of WNP-2,in Preparation for Upcoming Telephone Call
ML17292B672
Person / Time
Site: Columbia Energy Northwest icon.png
Issue date: 05/26/1999
From: Jack Cushing
NRC (Affiliation Not Assigned)
To:
NRC (Affiliation Not Assigned)
References
TAC-M96928, NUDOCS 9906030307
Download: ML17292B672 (5)


Text

May 26, 1999 MEMORANDUMFOR: File FROM:

SUBJECT:

Jack Cushing, Project Manager, Section 2/s/

Project Directorate IV 8 Decommissioning Division of Licensing Project Management Office of Nuclear Reactor Regulation WASHINGTON PUBLIC POWER SUPPLY SYSTEM (WPPSS)

NUCLEAR PROJECT NO. 2 (WNP-2) - FACSIMILETRANSMISSION, QUESTIONS ON THE LICENSEE'S AMENDMENTREQUEST FOR SECONDARY CONTAINMENTAND STANDBYGAS TREATMENT SYSTEM (TAC NO. M96928)

The attached questions were transmitted by fax to Mr. Arbuckle of WNP-2 to prepare him and others for an upcoming telephone call. This memorandum and the attachment do not convey a formal request for information or represent an NRC staff position.

Docket No. 50-397 DISTRIBUTION:

PUBLIC PD4-2 r/f J. Gushing DOCUMENT NAME: GAWNP2.96928.WPD To RECEIVE A COPY OF THIS DOCUMENT, INDICATEIN THE BOX: "C" = COPY WITHOUTENCLOSURES "E" = COPY WITH ENCLOSURES "N" OFFICE PM:PD4-2 NAME JCushing:sp DATE 5/

/99 PDIV-2/SC SDeITI 5'.

/99 LAD42 C

EPeyton,&

5/&6

/99 OFFICIAL RECORD COPY RS 1

9906030307 990526 PDR ADOCK 050003'P7 P

PDR

~R REGS

~o Cy 0O IVl0 IP

~O

++*++

Jt UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 May, 26, 1999 MEMORANDUMFOR:

File FROM:

SUBJECT:

Jack Cushing, Project Manager, Secti 2

Project Directorate IV& Decom 'i i

Division of Licensing Project Mana Office of Nuclear Reactor Regul io WASHINGTON PUBLIC POWER SUPPLY SYSTEM (WPPSS)

NUCLEAR PROJECT NO. 2 (WNP-2) - FACSIMILETRANSMISSION, QUESTIONS ON THE LICENSEE'S AMENDMENTREQUEST FOR SECONDARY CONTAINMENTAND STANDBYGAS TREATMENT SYSTEM (TAC NO. M96928)

The attached questions were transmitted by fax to Mr. Arbuckle of WNP-2 to prepare him and others for an upcoming telephone call. This memorandum and the attachment do not convey a formal request for information or represent an NRC staff position.

Docket No. 50-397

I' L

I H

h J

I r

lh n

E 1

Ik fy I'

~"

ll'UPPLEMENTAL RE VEST FOR ADDITIONALINFORMATION WASHINGTON PUBLIC POWER SUPPLY SYSTEM NUCLEAR PROJECT NO. 2 WNP-2 DOCKET NO. 50-397 1)

What atmospheric dispersion factors used in this review have been previously reviewed and approved by the NRC'? Ifthese dispersion factors have been previously reviewed and approved please identify or provide the documents that approved them.

Ifthey have not been reviewed and approved please provide the calculations or the data and assumptions used to calculate these values.

2)

Time 0-20 minutes 20 min-720 hr 5014 cfm 5014 cfm 0%

98.7%

Provide more detail of the radiological modeling of the standby gas treatment system.

Is the following table an accurate description of your model?

Ifso please provide the basis for this model. Ifthis is not an accurate description please provide the timing, filter efficiency and flow rates assumed and the bases for this model.

Filter Efficienc Assumed Flow Rate 3)

Provide more detail of the modeling of the secondary containment bypass in your radiological model for the Loss of Coolant Accident (LOCA). The WNP2 containment bypass leakage rates are specified in terms of standard cubic feet per hour. To model these activity releases under Design Basis Accident LOCA conditions, these leakage rates are typically adjusted to account for the post-accident pressure'nd temperature conditions inside the drywell and wetwell. Please describe,how your model does or does not address this.

4)

The impact of the proposed increased containment drawdown time and secondary containment bypass leakage has been incorporated in the LOCA accident dose analysis presented in the submittal.

Please address the impact of these changes on your other design basis radiological accidents.

Provide adequate justification for only addressing the LOCA. Please addre'ss both the control room and offsite doses.

0

,/

~ v

~

~ +

I, I

'P f