ML14210A159

NRR E-mail Capture - RAI - Eliminate Certain ESF Eequirements During Fuel Movement

ML14210A159
Person / Time
Site:	Vermont Yankee
Issue date:	07/29/2014
From:	James Kim Division of Operating Reactor Licensing
To:	Couture P Entergy Corp
References
MF3068
Download: ML14210A159 (3)

Text

NRR-PMDAPEm Resource From: Kim, James Sent: Tuesday, July 29, 2014 8:58 AM To: Couture III, Philip Cc: cchappe@entergy.com; Meyer, Jeffrey T (jmeyer5@entergy.com)

Subject:

RAI - Eliminate Certain ESF Eequirements During Fuel Movement (TAC No. MF3068)

Mr. Couture, The Nuclear Regulatory Commission staff is reviewing the submittal and has determined that additional information is needed to complete its review. The specific request for additional information (RAI) questions are shown below. Based on our discussions we understand that a response to the RAI will be provided by August 22, 2014.

Jim Kim NRR/DORL Vermont Yankee PM 301-415-4125 REQUEST FOR ADDITIONAL INFORMATION BY CONTAINMENT AND VENTILATION BRANCH REVIEW OF TECHNICAL SPECIFICATIONS PROPOSED CHANGE NO. 306 VERMONT YANKEE NUCLEAR POWER STATION DOCKET NO. 50-271 By letter dated November 14, 2013 (Reference 1), Entergy Operations, Inc. (Entergy, or the licensee) submitted a license amendment request (LAR) for Vermont Yankee Nuclear Power Station (VY), which proposes to change the requirements associated with handling irradiated fuel and performing core alterations in its Renewed Facility Operating License and Technical Specifications (TS).

The Containment and Ventilation Branch (SCVB) staff has reviewed the LAR and is requesting responses to the following items to complete its review:

SCVB-RAI-1: TSTF-51 Section 2.2 of Reference 1, Attachment 1 describes that VY will commit the two guidelines as described in the Reviewers Note of TSTF-51, "Revise Containment Requirements During Handling Irradiated Fuel and Core Alterations" if the term recently is to be added to the TS. Regarding the commitment, please address the following questions:

(a) For the first guideline, has VY assessed the ventilation system and radiation monitor availability with respect to filtration and monitoring of release from the fuel? Please provide the assessment.

(b) For the second guideline, justify that the proposed contingency plans will meet the prompt purpose with respect to enabling ventilation systems to draw the release from a postulated fuel handling accident in the proper direction such that it can be treated and monitored.

SCVB-RAI-2: Water Level 1

In Table 3-1, VYNPP-Design Input for FHA, of Reference 1, Attachment 4, the data for required water depth above fuel (B3) is input as 23 ft to support the overall pool decontamination factor data as input (B2). Is there any plant procedure in place to assure such a minimum water level of spent fuel pool or reactor cavity pool to be maintained?

SCVB-RAI-3: Release Path In Table 3-3, Atmospheric Dispersion Factors for the Postulated FHA, of Reference 1, Attachment 4, it indicates that the only release path from reactor building is via the reactor building blowout panel. Is there any other leakage path to plant personnel, main control room, existing?

SCVB-RAI-4: Fuel Assembly Drop or Fuel Cask Drop?

In Section 3.6, Fuel Cask Movement, of Reference 1, the statement starting from the third sentence in the first paragraph looks like described for the drop of fuel assembly not for fuel cask drop. Clarify the information presented in this paragraph is for fuel assembly drop or fuel cask drop.

SCVB-RAI-5: Audit Other than RG 1.183, there are four major references providing the input data and information for the re-analysis of AST/FHA (Attachment 4 of Reference 1). To have a complete review and facilitate the review, provide the following references for audit via electronic reading room:

3.* ENTERGY Calculation VYC-2299, "Radiological AST Fuel Handling Accident Analysis [PSAT 3019CF.QA.05, Rev. 0]"

(Jun. 2003)

4. AREVA NP Document 32-9053350-001, "ELISA-2 -A Software Package for the RadiologicalEvaluation of Licensing and Severe Accidents at Light-Water Nuclear Power Plants Based on the Classical and Alternative-Source-Term Methodologies" (Aug. 2008) [See also AREVA NP Document 2A4.26-2A4-ELISA2-2.4_UsersManual-000, "ELISA-2 Version 2.4 User's Manual - Revision 2".]

9.* ENTERGY Calculation VYC-2260, "Bounding Core Inventories of Actinides and Fission Products for Design-Basis Applications at 1950 MWt" (Rev. 0, Feb. 2003) 10.* ENTERGY Calculation VYC-2275, "Control Room Air Intake X/Q Due to Release from Reactor Building Blowout Panel Using Arcon96 Methodology" (Rev. 0, April 2003)

REFERENCES

1. Letter from VY to NRC dated November 14, 2013, Technical Specifications Proposed Change No. 306, Eliminate Certain ESF Requirements during Movement of Irradiated Fuel, Vermont Yankee Nuclear Power Station, Docket No. 50-271 License No. DPR-28, (ADAMS Accession Number ML13323A516) 2

Hearing Identifier: NRR_PMDA Email Number: 1457 Mail Envelope Properties (James.Kim@nrc.gov20140729085700)

Subject:

RAI - Eliminate Certain ESF Eequirements During Fuel Movement (TAC No.

MF3068)

Sent Date: 7/29/2014 8:57:40 AM Received Date: 7/29/2014 8:57:00 AM From: Kim, James Created By: James.Kim@nrc.gov Recipients:

"cchappe@entergy.com" <cchappe@entergy.com>

Tracking Status: None "Meyer, Jeffrey T (jmeyer5@entergy.com)" <jmeyer5@entergy.com>

Tracking Status: None "Couture III, Philip" <pcoutur@entergy.com>

Tracking Status: None Post Office:

Files Size Date & Time MESSAGE 4644 7/29/2014 8:57:00 AM Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:

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