ML20101L126
| ML20101L126 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 06/26/1992 |
| From: | Matthews D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20101L129 | List: |
| References | |
| NUDOCS 9207060281 | |
| Download: ML20101L126 (7) | |
Text
_ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ - _ - - _ - _ _ _ _ _ _ _ _ _ - _ _ - - _ _ _ _ _ - _ -
bQ CE0g S
3N UNITED STATES E
E NUCLEAR REGULATORY COMMISSION o
WASHINGTON. D.C. 20066 DUKE POWER COMPANY NORTli CAROLINA ELECTRIC MEMBERSHIP CQBPQRATION SALUDA RIVER ELECTRIC COOPERATIVE. INC.
D_0CKET N0.60-413 CATAWBA fiUCLEAR. STATION. UNIT 1 AMENDMENT TO FACILITY QfERATING LICENSE Amendment No. 98 License No. NPF-35 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The app'ication fcr amendment to the Catawba Nuclear Staticn, Unit 1 (the facility) Facility Operating License No. NPF-35 filed by the Duke Power Company, acting for itself, North Carolina Electric Membership Corporation and Saluda River Electric Coopera6ive, Inc.
(licensees) dated April 13, 1992, as supplemented on June 8,1992, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as set forth in 10 CFR Chapter I; B.
The faditt! <ill operate in conformity with the application, the provisions of the Act, and the rules and regulations of the b
Commission; C.
There is reasonable assurance (i) that the activities authorized by this an.adment can be conducted without endangering the health a.d safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; 0.
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 Commission's regulations and all applicable requirements have been satisfied.
D t
9207060281 920626 PDR ADOCK 05000413 P
PCR l
4 2,
Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 2.C.(2) of Facility Oper% ting License No. NPF-35 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 9f,, and tae Environmental Protection Plan contained in Apper. dix B, both of which are attached hereto, are hereby incorporated into this license.
Duke Power Company shall operate the facility in accordance with the Technicsl Specifications and the Envi *onmental Protection Plan.
3, This 11:ense amendn,ent is affective as o! its date of issuance, FOR THE NUC'_ EAR GEGULATORY COMMISSION p'
cU David B Ma" hews, Direc',or Project Directorate II-3 Division of Re' actor Projects-1/II Office of Nuclear Reactor regulation
Attachment:
l Technical Specification Changes Date of Issuance:
June 26, 1992 t
r
poM0 0
?%
/
UNITED STATES hlN. n i
' f i
NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. 206%
g * *s p
DUKE POWER COMPANY
![0_R_TtLCAROLINA MJti1CRM POWER AGENCl }l0.1 ELEDMONT MUNICIPAL POWER AGENCY JQ[KU NO. 50-411 CATAWBA NELEAR SThTION. UNIT 2 AMEND _MLNT TO FACILITY OPERATING LIC.QLSE I
Amendment No. 92 License No. NPF-52 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The applicdior for amendment to the Catawba nuclear Station, Unit 2 (the facility) Frility Operating License No. NPF 52 filed by the Duke Power Company, acting for itself, North Carolina Municipal Power Tsgency No. I und Piedaont Municipal Pcwer Agency (licensees) dated April 13, 1992, as suppleniented on June 8,1992, complies with 1
the standards and requirements of the Atomic Energy Act of 1954, a.,
uended (the Act), and the Commission's rules and regulations as s9t forth in 10 CFR Chapter I; 8.
The facility will operate in conformity with the application, the provision of the Act, and the rules and regulations of the
[
c.enmission; i
C.
There is' reasonable assurance (i) that the activities authorized by this amendment can be crmducted without endangering the health and safety of the public, had (ii) that such activi*ies will be conducted in compliance with the Comissic1's regulat'.ons set forth in 10 CFR Chapter I; D.
The issuance of this amendment will no+ be inimical to the ccmon de'ense and security er to the health and safety of the pubilc; and 3
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements bive
,=
been satisfied.
[
~
4 2.
Accordingly, the license is hereby amended by pags changes to the
{
Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 2.C.(2) of facility Operating License No. NPF-52 is hereby amended to read as follows:
lEAnlcJ]_SAtgiflqallons j
The Te:Snical Specifications contained in Appendix A, as revised through Amendment No. 92
, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are-hereby incorporated into this license.
Duke Power Company shall operate-the facility in accordance with the Technical Specifications and the Environ:aental Protection Plan.
3.
This license amendment is effective ?s of its date of issuance.
FOR THE NUI, LEAR REGULATORY COMMISSION ff Davi* B. Matthews, Otrector d
Project Directorate 11-3 Division of Reactor Projects-1/11 Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance.
June 26, 1992 t
I
l l
eliACR!i[NT TO L1CJRSLNiEfMEfjLJ10. 98 FAtU ITY QP.ERALIllA_(L(11S_E NO, NPF-35 P
00CKE1 NO 50-413 AND 10_.LLCENSE AliLNMENT NO, 9L
[ACJ1LTLAP_ERATING LICENSE NO NPE-51 2
DHGKET NQ, 50-414 Replace the followina page of the Appendfx "A" Technical Specifications with the enclosed page, lne re/ised page are identiffed by Amendment number and contains vertical lints indicating the areas of change.
Remove Pagg Jysert Pacie 3/4 6-47 3/4 6-47 3/4 6-48*
3/4 6-48*
e
- overleaf page - no change 0
5
?
O
.a____--- _ - - _ - _ - - - - - - - _ - - _ - _ - _ _ _ _ _ _ _ _ _ _ - _ _ _ - - _ _ _ - _ _ - - - _ _ _ - _ _ _ _ _ _ _. _ _ - _ _ _ _ -. - _. - - _ - _ _ -. _ _ _ _ _ _ - - - - _ - _ _ - - - - - - -
4
. CONTAINMENT SYSTEMS DIVIDER BARRIER PERSONNEL,A_C, CESS DOORS AND EQUIPMENT HATCHES LIMIT,ING CONDITION FOR OPERATION 3.6.5,5 The personnel access doors and equipment hatches between the contain-ment's upper and lower compartments shall be OPERABLE and closed.
APPLICABILITY:
MODES 1, 2, 3, and 4.
ACTIR:
a.
With a personnel access door or equipment hatch (other than one pressurizer enclosure hatch) inoperable or open except for personnel transit entry, restore the door or hatch to OPERABLE status or to its closed pcsition (as applicable) within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be in at least HOT STANDBY within the next 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 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
b.
With one pressurizer enclosure hatch open or inoperable, restore the hatch to operable status or to its closed position (as applicable) within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, or be in at least HOT STANDBY within the next 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 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILIANCE REQUIRtMiNTS 4
4.6.5.5.1 The personnel access doors and equipment hatches between the con-tainment's upper and lower compartments shall be determined closed by a visual inspection prior to increasing the Reactor Coolant System T above 200 F and af ter each personnel transit entry when the Reactor Coolant 5fstem T.V9 a
is above 200 F.
4.E.5.5.2 The personnel access doors and equipment hatches between the con-tainment's upper and lower comparttents shall be determined OPERABLE by visually inspecting the seals and sealing surfaces of these penetrations and verifying no detrimental misalignments, cracks or defects in the sealing surfaces, or apparent deterioration of the seal material:
a.
Prior to final clcsure of the penetration each time it has been opened, and b.
At least once per 10 years for penetrations containing seals fabri-cated from resilient materials.
CATAWBA - UNITS 1 & 2 3/4 6-47 Amendment No. 98 (Unit 1)
Amendment No. 92 (Unit 2)
S l=
CONTAINMENT SYSTEMS CONTAINMENT AIR RETURN AND HYDROGEN SUMMER SYSTEMS LIMITING CONDITISN FOR OPERATION 3.6.5.6 Two independent Cnntainmer t Air Return and Hydrogen Skimmer Systems shall ba 0.'ERABL.
APPLICABILITY:
MODES 1, 2, 3, and 4.
ACTION:
With one Containment Air Return and Hydrogen Skim.mer System inoperable, restore the inoperable system to OPERJ4BLE status within 72 iuc s or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUT 00V' within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.6.5.6.1 Eacn Containment Air Return and Hydrogen Skimmer System shall be dettonstrated OPERABLE at least once per 92 days on a STAGGERED TEST BASIS by:
a.
Verifying that the air return and hydrogen skimmer fans start autornatically on a Containment Pressure-High-High test signal after a 9 1 1 minuta delay and operate for at lear.t 15 minutes; b.
Verifying that during air return fan operation with the air return fan damper closed anti *sith the bypass dumpers open, tne fan motor current is less than or equal to 59 amps when the fan speed is 1187 i 13 rpm; y
c.
Veritying that with the hydrogen skimmer fan operating and the motor-operated valve in its suction line closed, the fan motor current is less than or equal to 69 amps when the fan speed is 3580 1 20 rpm; d.
Verifying that with the air return fan off, the motor-operated damper in the air return fan discharge line to the containment's lower com-partment opens automatically with a 10 1 1 second delay after a Containment Dressure-High-High test signal; e.
Verifying '.nat with the air return f an operating, the check damper in the ait return fan discharge line to the containment's lower compartment is open; CATAWBA - UNITS 1 & 2 3/4 6-48
~
-