ML20212N039

Amend 17 to License NPF-29,revising Tech Spec Section 5.6, Fuel Storage to Allow Increased Upper Containment Pool Capacity & Increased Spent Fuel Storage Pool Capacity

ML20212N039
Person / Time
Site:	Grand Gulf
Issue date:	08/18/1986
From:	Butler W Office of Nuclear Reactor Regulation
To:
Shared Package
ML20209G133	List: ML20209G129 ML20212N039 ML20212N056
References
TAC-57619, NUDOCS 8608280057
Download: ML20212N039 (7)

Text

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NUCLEAR REGULATORY COMMISSION 7;

.' j W ASHINGTON, D. C. 20555

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MISSISSIPPI POWER & LIGHT COMPANY MIDDLE. SOUTH ENERGY, INC.

SOUTH MISSISSIPPI ELECTRIC POWER ASSOCIATION DOCKET NO. 50-416 GRAND GULF NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 17 License No. NPF-29 1.

The Nuclear Regulatory Comission (the Comission) has found that A.

The application for amendment by Mississippi Power 8 Light Company, Middle South Energy, Inc., and South Mississippi Electric Power Association, (the licensees) dated May 6, 1985 as revised and supplemented by letters dated July 29, August 15, August 30, September II, September 12, November 1, and December 18, 1985; and March 14, March 15, June 5, June 9, and July 25, 1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of 'the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technic.J. Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-29 is hereby amended to read as follows:

Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 17

, are hereby incorporated into this license.

Mississippi Power & Light Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

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, 3.

This license amendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

/s/

Walter R. Butler, Director BWR Project Directorate No. 4 Division of BWR Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: August lE, 1986 e

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ATTACHMENT TO LICENSE AMENDMENT NO. 17 TACILITY OPERATING LICENSE NO. NPF-29 DOCKET N0. 50-416

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Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change. Overleaf page(s) provided to maintain document completeness.*

Remove Insert 5-5 5-5*

5-6 5-6 3/4 7-33 3/4 7-33*

3/4 7-34 3/4 7-34 s

e 1

9

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o DESIGNFEhTURES 5.3 REACTOR CORE 5'-

FUEL ASSEMBLIES 5.3.1 The reactor core shall contain 800 fuel assemblies with each fuel assembly containing 62 fuel rods and two water rods clad with Zircaloy -2.

Each fuel rod shall have a design nominal active fuel length of 150 inches.

The initial ~ core loading shall have a design nominal enrichment of 1.708 weight percent U-235.

Reload fuel shall be similar in physical design to the initial core loading.

CONTROL ROD ASSEMBLIES 5.3.2 The reactor core shall contain 193 control rod assemb' lies, each consisting of a cruciform array of stainless steel tubes containing a design nominal 143.7 inches of boron carbide, B C, powder surrounded by a cruciform 4

shaped stainless steel sheath.

5.4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE 5.4.1 The reactor coolant system is designed and shall be maintained:

a.

In accordance with the code requirements specified in Section 5.2 '

of the FSAR, with allowance for normal degradation pursuant to the applicable Surveillance Requirements, b.

For a pressure of:

1.

1250 psig on the suction side of the recirculation pump.

2.

1650.psig from the recirculation pump discharge to the outlet side of the discharge shutoff valve.

3.

1550 psig from the discharge shutoff valve to the jet pumps, c.

For a temperature of 575*F.

VOLUME 5.4.2 The total water and steam volume of the reactor vessel and recirculation system is approximately 22,000 cubic feet at a nominal T,y, of 533*F.

1 GRAND GULF-UNIT 1 5-5

e DESIGN FEATURES 5.5 METEOROLOGICAC' TOWER LOCATION 5.5.1 The meteorological tower shall be located as shown on Figure 5.1.2-1.

5.6 FUEL STORAGE CRITICALITY 5.6.1 The spent fuel storage racks are designed and shall be maintained with:

A k,ff equivalent to less than or equal to 0.95 when flooded with a.

unborated water, including all calculational uncertainties and biases as described in Section 4.3 of the FSAR.

b.

A nominal 6.26-inch center-to-center distance between fuel assemblies l

I placed in the storage racks.

i 5.6.1.2 The k,ff for new fuel for the first core loading stored dry in the spent fuel storage racks shall not exceed 0.98 when aqueous foam moderation is assumed.

DRAINAGE 5.6.2 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 202'5 1/4".

CAPACITY 5.6.3 The spent fuel storage capacity is designed and shall be maintained with a storage capacity limited to:

a.

No nore than 2324* spent fuel assemblies in the spent fuel pool, and I

b.

No more than 800 spent' fuel assemblies in the upper containment pool.

I Placement of fuel in the upper containment pool is limited to temporary storage of fuel during refueling operations.

Prior to return to reactor criticality, all spent fuel shall be removed from the upper containment pool.

5.7 COMP 0HENT CYCLIC OR TRANSIENT LIMIT i

5.7.1 The components identified in Table 5.7.1-1 are designed and shall be maintained within the cyclic or transient limits of Table 5.7.1-1.

1

• The physical limit is 4348. The 2324 limit reflects the number of spent fuel assemblies that can be stored in the spent fuel pool without excessive reliance on RHR supplement cooling; i.e., for a time period in excess of a i

normal refueling duration.

l l

l GRAND GULF-UNIT 1 5-6 AmendmentNo.17l l

TABLE 3.7.8-1 AREA TEMPERATURE MONITORING 3_

AREA TEMPERATURE LIMIT (*F) a.

Containment Inside Drywell 150 CR0 Cavity 185 Outside Drywell 105 Steam Tunnel 125 b.

Auxiliary Building General 104 ECCS Rooms 150 ESF Electrical Rooms 104 Steam Tunnel 125 c.

Control Building ESF Switchgear and Battery Rooms 104 Control Room 90 d.

Diesel Generator Rooms 125 e.

SSW Pumpnouse 104*

"For this area, the limit shall be the greater of 104*F or outside ambient temperature plus 20*F, not to exceed 122*F for greater than one hour.

t I

e GRAND GULF-UNIT 1 3/4 7-33

c PLANT SYSTEMS 3/4.7.9 SPENT FUEL STORAGE POOL TEMPERATURE LIMITINGCONDITION'FdROPERATION 3.7.9 The spent fuel storage pool temperature shall be maintained at less than or equal to 140 F.

I APPLICABILITY: Whenever irradiated fuel is in the spent fuel storage pool.

ACTION: With the spent fuel storage pool temperature greater than 140 F but less than 210 F, perform the following:

a.

Restore the pool temperature' to less than or equal to 140*F within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and b.

If at any time after exceeding 140 F an extrapolated temperature plot indicates that the pool temperature will exceed 210 F in less than-20 hours, be in at least STARTUP within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

SURVEILLANCE REQUIREMENTS J

4.7.9.1 The spent fuel storage pool temperature shall be verified to be less than or equal to 140 F at least ence per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

l 4.7.9.2 Start each fuel pool cooling and cleanup pump not already running at least once per 92 days and run ea:h. pump for at least 15 minutes.

'l GRAND GULF-UNIT 1 3/4 7-34 Amendment No. 17. l