ML20111C935
| ML20111C935 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 05/09/1996 |
| From: | Hutchinson C ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GNRO-96-00055, GNRO-96-55, IEB-96-002, IEB-96-2, NUDOCS 9605170125 | |
| Download: ML20111C935 (11) | |
Text
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Ent? y Cpirati:ns,Inc.
Port Gtson. MS 39150 Tel 601437 2800 C. R. Hutchinson Vre Pesderd Operahons May 9, 1996 Gram GuHenav %e U.S. Nuclear Regulatory Commission Document Control Desk Nhil Stop P1-37 Washington, D.C. 20555
Subject:
Grand Gulf Nuclear Station Docket No. 50-416 License No. NPF-29 i
Response to NRC Bulletin 96-02, " Movement of Heavy Loads Over Spent Fuel, Over Fuel in the 4
Reactor Core, or Over Safety Related Equipment" GNRO-96/00055 Gentlemen:
The Nuclear Regulatory Commission (NRC) issued the subject bulletin to alert licensees to the importance of complying with existing regulatory guidelines for the control ~and handling of heavy loads at their facilities.
Licensees are requested to review cheir plans and capabilities for. handling heavy loads in accordance with existing regulatory guidelines and within their licensing basis, as previously analyzed in their Final Safety Analysis Report (FSAR).
Upon completion of the review, licensees are requested to provide a response to the Staff stating whether and to what extent they have complied with the requested actions of Bulletin 96-02.
We understand that the scope of Bulletin 96-02 is limited to the handling and controlling of heavy loads while the reactor is at power.
The bulletin specifically requests that licensees address any plans to handle heavy loads over spent fuel, fuel in the reactor or safety-related equipment within the next 2 years.
Additionally,Bulletin 96-02 requests that licensees address the handling of loads not previously evaluated in the FSAR load drop analyses, movement of dry storage casks and loads for which a Technical Specification amendment may be required prior to performing.
9605170125 960509 PDR ADOCK 05000416 1
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S 160066 eg i
l GNRO-95/00055 Page 2 of 4 The GGNS current licensing basis, including heavy loads handling and controlling analyses contained in the FSAR and commitments made in the Phase I and Phase II Report in response to the unnumbered generic letter dated December 22, 1980, along with current plans for heavy load movements have been reviewed against the actions specified in Bulletin 96-02.
The response to Bulletin 96-02 for GGNS is provided in.
Any heavy load movements performed at GGNS will be performed in accordance with our licensing basis. The GGNS licensing basis addresses the movement of heavy loads over spent fuel, fuel in the reactor and over safe shutdown equipment rather than load moves over safety-related equipment as delineated in the bulletin.
This information is being submitted under affirmation in accordance with 10 CFR 50.54 (f) (Attachment 2).
Please contact Charles E. Brooks at (601) 437-6555 should you have any questions, or require additional information.
Your truly,
/ J
)
/ f CRH/CEB/
attachments: 1)
Grand Gulf Nuclear Station Response to NRC Bulletin 96-02 2)
Affirmation of the GGNS Response to NRC Bulletin 96-02 pursuant to 10CFR50.54 (f) cc: See Next Page
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l GNRO-96/00055 Page 3 of 4 l
l cc:
Mr. R. B. McGehee (w/h)
Mr. N. S. Reynolds (w/a)
M. J. E. Tedrow (w/a) r Mr. H. L. Thomas (w/o)
Mr. J. W. Yelverton (w/a) l Mr. L. J. Callan (w/a)
Regional Administrator U.S. Nuclear Regulatory Commission l
Region IV.
611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011 Mr. J. N. Donohew, Project Manager (w/2)
Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop 13H3 Washington, D. C.
20555 J
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! to GNRO-96/00055 l
Response to NRC Bulletin 96-02
" Movement of Heavy Loads Over Spent Fuel, Over Fuel in the Reactor Core and Over Safety Related Equipment" i
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NRC Bulletin 96-02 Requested Actions Licensees are requested to review their plans and capabilities for handling heavy loads while the reactor l
is at power (in all modes other than shutdown, refueling, l
or defueled) in accordance with existing regulatory l
guidelines. Upon completion of the review, licensees are required to submit a written response to the following l
Requested Actions within 30 days from the date of NRC l
Determine whether the activities are within the licensing basis and, if necessary, submit a license amendment request.
Determine whether changes to Technical Specifications will be required in order to allow the handling of heavy loads (e.g.,
the dry storage canister shield j
plug and associated lifting devices) over fuel assemblies in the spent fuel pool.
i Response to the Requested Actions of Bulletin 96-02 l
A review of plans and capabilities for handling heavy loads at GGNS while the reactor is at power (in all i
modes other than shutdown, refueling, or defueled) has been performed in accordance with existing regulatory guidelines. The review has determined that the heavy load movement plans and capabilities are within the licensing basis of the facility. However, as l
previously stated, the GGNS licensing basis addresses l
the movement of heavy loads over spent fuel, fuel in the reactor and over safe shutdown equipment rather than load moves over safety-related equipment as i
l delineated in the bulletin. As such, our responses to the Requested Actions are based upon this premise.
Heavy loads are not addressed in the GGNS Technical Specifications. The GGNS licensing basis outlines the appropriate actions for handling loads that must be carried over irradiated fuel.
i NRC Bulletin 96-02 Required Information (Item 1) l (1)
For licensees planning to implement activities involving the handling of heavy loads over spent fuel, fuel in the reactor core, or safety related equipment within the next 2 years from the date of this bulletin, provide the following information:
A report within 30 days of the date of this bulletin, that addresses the licensee's review of its plans and capabilities to handle heavy loads while the reactor is at power (in all modes other than cold shutdown, refueling or defueled) in accordance with existing regulatory guidelines. The report should also indicate whether the activities are within the licensing basis and should include, if necessary, a schedule for submission of a license amendment request. Additionally, the report should indicate whether changes to Technical Specifications will be required.
Response to Required Information (Item 1)
Any heavy load movements performed at GGNS will be performed in accordance with our licensing basis.
A heavy load move evolution is scheduled for June 1996. This evolution will traverse a TM-RAM Cask liner from Elevation 133'ft. (ground e'levation) up to plant elevation 208' ft. The cask liner has a empty weight of approximately 1.5 tons and will be used for the storage of control blades.
NRC Bulletin 96-02 Required Information (Item 21, (2)
For licensees planning to perform activities involving the handling of heavy loads over spent fuel, fuel in the reactor core, or safety related equipment while the reactor is at power (in all l
modes other than cold shutdown, refueling, and defueled) and that involve a potential load drop l
accident that has not previously been evaluated in l
the FSAR, submit a license amer.dment request in I
advance (6-9 months) of the planned movement of the loads so as to afford the staff sufficient time to perform an appropriate review.
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l Response to Required Information (Item 2)
Any heavy load movements performed at GGNS will be performed in accordance with our licensing basis.
The GGNS FSAR establishes guidelines to support a defense-in depth approach for minimizing the probability of load drop accidents. Loads that do not meet these guidelines are evaluated to verify that any resultant consequences are bound by previously evaluated load drop analyses.
l NRC Bulletin 96-02 Reauired Information (Itam 3) l (3)
For licensees planning to move dry storage casks j
over spent fuel, fuel in the reactor core, or safety related equipment while the reactor is at power (in all modes other than cold shutdown, refueling, or l
defueled) include in item 2 above, a statement of the capability of performing the actions necessary for safe shutdown in the presence of radiological source term that may result from a breach of the dry storage cask, damage to the fuel, and damage to l
safety related equipment as a result of a load drop l
inside the facility.
Response to Required Information (Item 3)
Any heavy load movements performed at GGNS will be performed in accordance with our licensing basis.
GGNS has no present plans to move dry storage casks.
Should the need for such a load movement arise, the load move evolution would be evaluated in accordance with our defense-in-depth approach of handling and I
controlling heavy loads as outlined in the licensing basis.
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NRC Bulletin 96-02 Ramuired Information (Iten 4)
(4)
For licensees planning to perform activities involving the handling of heavy loads over spent fuel, fuel in the reactor core, or safety-related equipment while the reactor is at power (in all
{.
modes other than cold shutdown, refueling, and f
- defueled), determine whether changes to Technical' i
Specifications will be required in order to allow the handling of heavy loads (e.g.,
the dry storage j
canister shield plug) over fuel assemblies in the j
spent fuel pool and submit the appropriate
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information in advance (6-9 months) of the planned movement of the loads for NRC review and approval.
Resnonne to Required Information (Itam 4)
Any heavy load movements performed at GGNS will be performed in accordance with our licensing basis. As previously stated, heavy-loads are not addressed in the GGNS Technical Specifications. The GGNS licensing basis outlines the appropriate actions for handling loads that must be carried over irradiated fuel.
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References:
- 1. Letter Mississippi Power & Light Company to the U.S.
Nuclear Regulatory Commission, dated November 23, 1981
" Control of Heavy Loads" provided Results of the Phase I j
review required by the December 22, 1980 Letter for GGNS.
- 2. Letter Mississippi Power & Light Company to the U.S.
Nuclear Regulatory Commission, dated May 4, 1982 " Heavy Loads Final Report" Provided Results of the Phase II i
review required by the December 22, 1980 Letter for GGNS.
- 3. Grand Gulf Nuclear Station Final Safety Analysis Report l
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GNRO-96/00000 i
l Affirmation Per 10CFR50.54 (f)
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a BEFORE THE s
UNITED STATES NUCLEAR REGULATORY COtMISSION I
I j.
I LICENSE NO. NPF-29 i
DOCKET NO. 50-416 IN THE MATTER OF MISSISSIPPI POWER & LIGHT COMPANY
[
and SYSTEM ENERGY RESOURCES, INC.
and i
SOUTH MISSISSIPPI ELECTRIC POWER ASSOCIATION I
l and ENTERGY OPERATIONS, INC.
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AFFIRMATION I, C. R. Hutchinson, being duly sworn, state that I am Vice President, Operations GGNS of Entcrgy Operations, Inc.; that on behalf of Entergy Operations, Inc., System Energy Rescurces, Inc., and South Mississippi Electric Power Association I am authorized by Entergy Operations, Inc. to sign and file with the Nuclear Regulatory Commission, this rOrponse to NRC Bulletin 96-02 for Grand Gulf Nuclear Station; that I signed this response cc Vice President, Operations GGNS of EM. orgy Operat ons, Inc., and that the statements j
sid2 and the matters set forth thereha are true an orrec opebestofmyknowledge, l
inferaation and belief.
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C. R' Tiut6hinson STATE OF MISSISSIPPI l
COUNTY OF CLAIBORNE SUBSCRIBED AND g f TO before me, a Notary Public, in and for the County and State above nam:d tMs 7
day of May
, 1996.
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'(StG.L) y y ///
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Notary Public
!M!bSE57 KNOT ElC
!R COMMISSION EXPIRES JUNE 5.1998 BCNDED TliRU SIECALL NOTARY SERVICS
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