ML20058L650
| ML20058L650 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 08/01/1990 |
| From: | Hebdon F Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20058L652 | List: |
| References | |
| NUDOCS 9008070372 | |
| Download: ML20058L650 (13) | |
Text
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'i NUCLEAR REGULATORY COMMISSION
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WASHING TON. D. C. 20555 g
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l TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-327 SE000YAH NUCLEAR PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.144 License No. DPR-77 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennestee Valley Authority (the licensee) dated Pay 4, 1990, as supported by the letter dated February 14, 1990, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission'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 Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendrent can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the comon 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, i
9008070372 900801 PDR ADOCK 05000327 P
'2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. DPR-77 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.144, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance.
FOR THE HUCLEAR REGULATORY COMMISSION 1% > -
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Frederick J. Heb don, Director Project Directorate 11-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Charges to the Technical Specifications Date of 1ssuance: August 1, 1990
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ATTACLFENT TO LICENS,E,,A,M,E,N,D,M,E,N,T NO.,,1,44 -
FACILITY OPERATING _ LICENSE NO. DPR i o-
~ DOC.KET NO. 50-327-i i
V revise-the Appendix ~ A Technical Specifications by removing the pages
- identified telcw and inserting tre' enclosed pages. The revised pages are identified by the captiened amendrent nutiber and contain marginal
,linesiindicating the area of r.hange.
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' INSERT LE 3/4 9-1 3/4 9-1 3/4 9-la i
t 5/4 5/4 5-5 5-5 l-
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3/4.9 REFUELING OPERAIIONS 3/4.9.1 BORON CONCENTRATION LIMITING CONDITION FOR OPERATION 3.9.1 With the reactor vessel head closure bolts less than fully tensioned or with the head removed, the boron concentration of all filled portions of the Reactor Coolant System and the refueling canal shall be maintained uniform and t
i sufficient to ensure that the more restrictive of the following reactivity conditions is met:
?
Either a K,ff of 0.95 or less which includes a 1% delta k/k conser a.
vative allowance for uncertainties, or b.
A boron concentration of greater than or equal to 2000 ppm, which includes a 50 ppm conservative allowance for uncertainties.
APPLICABILITY:
MODE 6*
ACTION:
With the requirements of the above specification not satisfied, immedia.ely suspend all operations involving CORE ALTERATIONS or positive reactivity changes and initiate and continue boration at greater than or equal to 10 gpm of a solution containing greater than or equal to 20.000 ppm boron or its equivalent until Keff is reduced to less than or equal to 0.95 or the boron concentration is restored to greater than or equal to 2000 ppm, whichever is i
the more restrictive.
The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS
- 4. 9.1.1 The more restrictive of the above two reactivity conditions shall be determined prior to:
a.
Removing or unbolting the reactor vessel head, and b.
Withdrawal of any full length control rod in excess of 3 feet from its fully inserted position within the reactor pressure vessel.
4.9.1.2 The boron concentration of the reactor coolant system and the refueling canal shell be determined by chemical analysis at least once per 7l hours.
1 l'
i
- The reactor shall be maintained in MODE 6 whenever fuel is in the reactor l
vessel with the vessel head closure bolts less than fully tensioned or with l
the head removed.
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SEQUOYAH - UNIT 1 3/4 9-1 Amendment No. 12, 144 l
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4 1
3/4.9 REFUELING OPERAI1ONS SURVEILLANCE REQUIREMENTS (Continued)
~
- 4. 9.1. 3 One of the following valve combinations shall be verified closed under administrative control at least once per 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />s:
Combination A Combination B Combination C Combination 0 a.
1-81-536 a.
1-81-536 a.
1-81-536 a.
1-81-536 b.
1-62-922 b.
1-62-922 b.
1-62-907 b.
1-62-907 c.
1-62-916 c.
1-62 916 c.
1-62-914 c.
1-62-914 d.
1-62-933 d.
1-62-940 d.
1-62-927 d.
1-62-921 e.
1-62-696 e.
1-62-s33 e.
1-62-940 i
f.
1-62-929 f.
1-62-929 g.
1"62-932 q.
1-62-932 h.
1.FCV-62-128 h,
1-62-696 1.
1-FCV-62-128
- 4. 9.1. '-
- Se boron concentrition in the spent fuel pool shall be determined by chemica'l analysis to ba gyg;4er than or equal to 2,000 parts per million (ppm) at least once per 72 hec's during fuel movement and until the configuration of the assemblies in the sterage racks is verified to comply with the criticality loading criteria specified in Design Feature 5.6.1.1.c SEQUOYAH - UNIT 1 3/4 9-la Amendment No.12,144
i 5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The reactor core shall contain 193 fuel assemblies with each fuel assembly containing 264 fuel rods clad with Zircaloy-4.
Each fuel rod shall have a nominal active fuel length of 144 inches.
The initial core loading
.shall have a maximum enrichment of 3.15 weight percent U-235.
Reload fuel shall be similar in physical design to the initial core loading and shall have a maximum enrichment of 5.0 weight percent U-235.
CONTROL ROD ASSEMBLIES t
5.3.2 The reactor core shall contain 53 full length and no part length control rod assemblies.
The full length control rod assemblies shall contain a nominal 142 inches of absorber material.
The nominal values of absorber material shall be 80 percent silver, 15 percent indium and 5 percent cadmium.
All control rods shall be clad with stainless steel tubing.
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 2485 psig, and c.
For a temperature of 650 F, except for the cressurizer which is 680 F.
0LUME 5.4.2 The total water and steam volume of the reactor cociant system is 12,612 + 100 cubic feet at a nominal T f 525 F.
avg 5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1.
SEQUOYAH - UNIT 1 5-4 Amendment No. 45,144
T f
DESIGN FEATURES
- 5. 6 FUEL STORAGE CRITICALITY - SPENT FUEL
- 5. 6.1.1 The spent fuel storage racks are designed for fuel enriched to 5.0
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weight percent U-235 and shall be maintained with:
i A k,ff equivalent to less than 0.95 when flooded with unborated a.
water, which includes a conservative allowance of 3.06% delta k/k for uncertainties.*
b.
A nominal 10.375 inch center-to-center distance between fuel assemblies placed in the storage racks.
Fuel assemblies with onrichment greater than 4.0 weight percent c.
U-235 and burnup less than 7,500 megawattday/ metric ton (Wd/mtu) shall be placed in cells in the spent fuel storage racks that face l
adjacent cells containing either:
1.
Fuel assemblies with accumulated burnup of at least 22,000 Wd/mtu, or 2.
Water CRITICALITY - NEW FUEL 5.6.1.2 The new fuel pit storage racks are designed and shall be maintained with a nominal 21.0 inch center-to-center distance between new fuel assemblies such that k,ff will not exceed 0.98 when fuel having.an enrichment of 4.5 weight percent U-235 is in place and optimum achievable moderation is assumed.
DRAINAGE 5.6.2 The spent fuel pit is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 722 ft.
CAPACITY 5.6.3 The' spent fue.1 storage pool is designed and shall be maintained with a l
storage capacity limited to no more than 1386 fuel assemblies.
5.7 COMPONENT CYCLIC C.1 TRANSIENT LIMIT 5.7.1 The components identified in Table 5.7-1 are designed and shall be maintained within the cyclic or transient limits of Table 5.7-1.
- For some accident conditions, the presence of dissolved boron in the pool water may be taken into account by applying the double contingency principle which requires two unlikely, independent, concurrent events to produce a criticality accident.
SEQUOYAH - UNIT 1 5-5 Amendment No. 13, 60, 114, 144
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UNITED STATES r',.
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TENNESSEE VALLEY AUTHORITY p0CKETNO.50-328 SEQUOYAH NUCLEAR PLAtlT, UNIT 2 Af1EllDfiENT TO FACILITi OPERATING LICENSE i
.1 Amendment No.125 License No. DPR-79 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the iicensee) dated May 4, 1990, as supported by the letter dated
' February 14, 1990, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) -and the Commission'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 Commission; 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 Commission's regulations;
'i D.
The issuance of this amendment will not be inimical to the common defense and security or tr *he health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51
'l of the Commission's regulations and all applicable requirements have 1
been satisfied.
-I
y
- 2.
Accordingly, the license is amended by char.ges to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. DPR-79 is hereby amended to read as_follows:
(2) Technical Specifications
-1 The Technical Specifications contained in Appendices A and B, as revised through Amendment No.125, are hereby incorporated in the license. The licensee shall operate the facility.in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION c
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- v..
Frederick J. Hebdon, Director Project Directorate 11-4 Division of Reactor Projects
.1/11 Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: August 1,1990 117
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ATTACHMENT _T0JHENSE AMENDMENTllL_1_21 FACILITY OPERATING LICENSE _NO. DPR-79 DOCKET NO. 50-328 Revise the Aopendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The' revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.
REMOVE INSERT 3/4 9-2 3/4 9-2
^
5-4 5-4 5-5 5-5 i
REFUELING OPERATIONS SURVEILLANCE REQUIREMENTS (Continued) 4.9.1.2 The boron concentration of the reactor coolant system and the refueling canal shall be determined by. chemical analysis at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
4.9.1.3 One of the following valve combinations shall be verified closed under administrative control at least once per 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />s:
Combination A Combination B Combination C Combination 0 a.
2-81-536 a.
2-81-536 a.
2-81-536 a.
2-81-536 b.
2-62-922 b.
2-62-922 b.
2-62-907 b.
2-62-907 c.
2-62-916 c.
2-62-916 c.
2-62-914 c.
2-62-914 d.
2-62-933 d.
2-62-940 d.
2-62-921 d.
2-62-921 e.
2-62-696 e.
2-62-933 e.
2-62-940 f.
2-62-929 f.
2-62-929-g.
2-62-932 g.
2-62-932 h,
2-FCV-62-128 n.
2-62-696 1.
2-FCV-62-128 4.9.1.4 The boron concentration in the spent fuel pool shall be determined by chemical ~ analysis to be greater than or equal to 2000 ppm at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> during fuel movement and until the configuration of the assemblies in the storage racks is verified to comply with the criticality loading criteria specified in Design Feature 5.6.1.1.c.
I
-SEQUOYAH - UNIT 2 3/4 9-2 Amendment Ne. 125
DESIGN FEATURES 5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The reactor core shall contain 193 fuel assemblies with each fuel assembly containing 264 fuel rods clad with Zircaloy -4.
Each fuel rod shall have a nominal active fuel length of 144 inches.
The initial core loading shall have a maximum enrichment of 3.15 weight percent U-235.
Reload fuel shall be similar in physical design to the initial core loading ud shall have a maximum enrichment of 5.0 weight percent U-235.
CONTROL ROD ASSEMBLIES 5.3.2 The reactor core shall contain 53 full length and no part length control rod assemblies.
The full length control rod assemblies shall centain a nominal 142 inches of absorber material.
The nominal values of absorter material shall be 80 percent silver, 15 percent indium and 5 percent cadmium.
All control rods shall be clad with stainless steel tubing.
5.4 REACTOR COOLANT SYSTEM DESIGN PRLSSURE 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 2485 psig, and c.
For a temperature of 650 F, except for the pressurizer which is 680 F.
VOLUME 5.4.2 The total water and steam volume of the reactor coolant system is 12,612 1 100 cubic feet at a nominal T,yg of 525*F.
5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1.
SEQUOYAH - UNIT 2 5-4 Amendment No. 37,125
N DESIGN FEATURES 5.6 FUEL STORAGE CRITICALITY - SPENT FUEL
- 5. 6.1.1 The spent fuel storage racks are designed for fuel enriched to 5.0 weight percent U-235 and shall be maintained with:.
l A k,ff equivalent to less than 0.95 when flooded with unborated a.
water, which includes a conservative allowance of 3.06% delta k/k l
for uncertainties.*
I b.
A nominal 10.375 inch center-to-center distance between fuel assemblies placed in the storage racks.
Fuel assemblies with enrichment greater than 4.0 weight percent c.
U-235 and burnup less than 7,500 megawattday/ metric ton (mwd /mtu) shall be placed in cells in the spent fuel storage racks that face adjacent ce_lls-containing either:
1.
Fuel assemblies with accumulated burnup of at least 22,000 mwd /mtu, or 2.
Water CRITICALITY - NEW FUEL 5.6.1.2 The new fuel pit storage racks are designed and shall be maintained with a' nominal 21.0. inch center-to-center distance between new fuel assemblies
- h that k,ff will not exceed 0.98 when fuel having an enrichment of 4.5 weight percent U-235 is in place and optimum achievable 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 722 ft.
CAPACITY
-5.6.3 The spent fuel storage pool is designed and shall be maintained with a storage. capacity limited to no more than 1386 fuel assemoiies.
5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT 5.7.1 The components identified in Table 5.7-1 are designed and shall be maintained within the cyclic or transient limits of Table 5.7-1.
^For some accident conditions, the presence of dissolved boron in the pool' water may-be taken into account by applying the double contingency principle which requires two unlikely, independent, concurrent events to produce s criticality accident.
I SEQUOYAH - UNIT 2 5-5 Amendment No. 4, 52, 125
..