ML20114D493
| ML20114D493 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 08/27/1992 |
| From: | Black S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20114D494 | List: |
| References | |
| GL-90-01, GL-90-1, NUDOCS 9209090029 | |
| Download: ML20114D493 (12) | |
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UNITED ST ATES n
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NUCLEAR RECULATORY COMMISSION
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HOUSTON llGHTING & POWER COMPANY i
CITY PUBLIC SERVICE BOARD OF SU{ ANTQ!iLQ 3
CENTRAL POWER AND LIGHT r0N ANY CITY OF nUSTIN. lEXAS DOCKET NO. 50-498 SOUTH TEXAS _PE WECT. UNIT 1 j
AMENDMENT TO FACIllTY OPERATING LICENSE Amendment No. 44 License No. NPF-76 1.
The Nuclear Regulatory Commi:sion (the Commission) his found that:
A. The application for aundment by Houston Lighting & Power Company' (HL&P) acting on behalf of itself and for the City Public Service Board of San Antonio (CPS), Central Power and Light Company (CPL), and City of Austin, Texas (C0A) (the licensees) dated June 19, 1992, complies with the standards and requirt.ments 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 wi'l operate in conformity with the application, as amer.ded, the provisions of the Act, and the rules and regulations of the Commission; C. Tuere is rrasonr 3 assurance: -(i) that the activities authorized by this amesment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conductea in compliance with the Commission's regulations; D. The issuance of this license 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.
- Houston Lighting & Power Company is authorized to act for the City Public Service Board of San Antonio, Central Power and Light Company and City of Austin, Texas and has exclusive responsibility and control over the physical constructien, operation and maintenance of the facility, v209090029 920827 dDR-ADOCK 05000498 P
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e o 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license a:ner.dment and Paragraph 2,C.(2) of Facility Operating License No. NPF-76 is hereby amended to read as fciiows:
- 2. Technical Soecifications The Technicel Specifications contained in App.adix A, as revised through Arner.Mnt No.
44, and the Environmental Protection Plan contained ;n Appendix B, are hereby incorporated in the license.
The licensee shall operate the f acility in accordance with the Technical Specifications and the Environruental Protection Plan.
3.
The license amendment is effective as of its date of issuance and is to be implemented within ten days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION r
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( 3 '.. Q,. R Suzanne C/ Black, Director Project Directorate IV-2 Division of Reactor Projects Ill/IV/V Office of Nuclear keacter Regulation 4
Attachment:
Changes to the Technical Specifications Date of Issuance:
August 27, 1992
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N UNITED STATES n
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2 NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D C. 20566 o%*,v f HOUSTON LIGHTING % POWER COMPANY.
Cl?Y PUBLIC SERVICE BOARD OF SAN ANTONIO CENTRAL POWid AND LIGHT COMPANY CITY OF AUSTIN. TEXAS E9CKET NO. 50 399 SOUTH TEXAS PROJECT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICEN E Amendment No. T License No. NPF-80 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Houston Lighting & Power Compe.ny*
(HL&P) acting on behalf of itself and for the City Public Service Board of San Antonio (CPS), Central Power ana Light Coi.pany (CPL), and City of Austin, Texas (C0A) (the licensees) dated June 19, 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 set forth -in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, as amended, the prmisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance:
(i) that the' activities authorited 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; D.
The issuance of this license amendment will not be inimical t3 the common defense and security cr 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 Ccmmission's regulations and all applicaMe requirements have been satisfied.
-* Houston Lighting,& Power Company is huthorized to act fer the City Public Service BoarJ of San Antonio, Central Power and Light Company and City of Austin, Texas ind has exclusive responsibility and control over the physical construction, operation and maintenance of the facility.
9 2.
Accordingly, the license is amended by changes to the Technical Spec'fications as indicated in the attachment to this license amendment and Paragraph ?.C.(2) of Facility Operating License No. NPF-8C is hereby amended to read as follows:
2.
Technical Scecificationi The Technical Specifications contained in Appendix A, as revised through,'eendment No.
33, and the Environmental Protection Plan containeo in Appendia B, are hereby incorporated in the license.- The-licensee shall operate the facility in accordance with the Technical Specificatior,s and the Environmental Protection Plan.
3.
The license amendment is effective as of its date of issuance and is to be implemented within ten days of issuance.
FOR THE NUCLtAR REGULATORY COMMISSION-
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1 Suzanne C. Black, Director Project Directorate IV-;
Division of Reactor Project 3 Ill/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
August 27, 1992 l
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ATTACHMENT TO LICENSE AMENDMENT N05,44 AND 33 FACll!TY OPERATING LICENSE NOS. NPF-76 AND NPF-80 DOCKET N05. 50-498 AND 50-499 Replace the following pages of the Appendix A Technical Specification: with the attached pager.
The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change.
The corresponding overle9f pages are also provided to maintain document completeness.
REMOVE INSERT 3/4 7-21 3/4 7-21 3/4 7-22 3/4 7-22 3/4 7-22a 3/4 7-22b B 3/4 7-5 B 3/4 7-5 B 3/4 7-6 B 3/4 7-6 B 3/4 7-7 t
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4 PLANT SYSTEMS-3/4.7.9 SNUBBIES_
llMITING CONDITION FOR OPERATION All snubbers shall be OPERABLE.
The only snubbers excluded from the
?.7.9 requirements are those installed on nonsafety-related systems cnd then only if their failure or failure of the system on which they are installed would have no adverse effect on any safety-related system.
&EPLICABILITY: MODES 1, 2, 3, and 4.
MODES 5 and 6 for snubbers located on systems required OPERABLE in those MODES.
ACTION:
With one or more snubbers,
serable...
.; evstem, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> replace or restore the _ inoperable snubb:r(s) to OPERABLE status and perform an engineering evaluation per Specification 4.7.90, on the attached component or declare the attached system inoperable and follow the appropriate ACTION statement for that system.
SURVEILLANCE REQUIREMENTS 4.7.9 Each snubber shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program in lieu of the requirement of-Specification 4.0.5.
a.
JDEpection Types As used in.this -specification, type of snubber shall mean snubbers of the same design and manuf acturer, irrespective of capacity.
y_itual - Inspections u
Snubbers are categorized as inaccessible or accessible during reactor operation.
Each of these categories (Inaccessible ant Accessiole) ~
- may be inspected independently or jointly according to the schedule determined by Table 4.7-?.
The visual inspection interval for each papulation or category of snubber shall-be determined based upon the criteria provided in Table 4.7-2 and the first inspection interval determined 'using this criteria shall be based upon the previous inspection. interval as established by the requirements in effect before amendment nos. 44 and 33.
-SOUTH TEXAS UNITS 1 & 2 3/4 7-21 Unit 1 - Amendment No. 44 Unit 2 - Amtndment No. 33
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Table 4.7-2 (Continued)
SNUBBER VISUAL INSPECTION INTERVAL Note 4:
If the number of unacceptable snubbers is equal to or less than the number in Column B but greater than the number in Column A, the next inspection interval shall be the same as the previous interval.
Note 5:
If the number of unacceptable snubbers is aqual to or greater than the number in Column C, the next inspection interval shall be two-thirds of the previous interval.
However, if the number of unacceptable snubbers is less than the number in Column C b.' greater than s he number in Column B, the next interval shall be reCuced
. proportional?
by interpolation, that is, the previous interval shall be reduced by a factor that is one-third of the ratio of the difference between the number of unacceptable snubtors found during the previous interval and the number in Column B t-a the difference in the numbers in Columns B and C.
Note 6:
The provisions of Specification 4.0.2 are applicable for all inspection intervals up to and including 48 r;:nths, l
L SOUTH. TEXAS - UNITS 1 & 2 3/4.7-22a Unit 1 - Amendment No. 44 Ur.it 2 - Amendment No. 33
PLANT SYSTEMS BASES SHMBELRS (Continued) with Section 50.71(c) of 10 CFR I2rt 50. The accessibility of each snubbar shall be determined and approved by the Plant Operations Review Committee.
The determination shall be based upon the existing radiat on levels and the expected time to perform a visual inspection in each snubber location as well as other-factors associated with accessibility during plant operations (e.g.,
temperature, atmosphere, location, etc.), and the recommendations of Regulatory Guides 8.8 and 8.10.
The addition or deletion of any hydraulic or mechanical snubber shall be made in accordance with Section 50.59 of 10 CFR Part 50.
lhe visual inspection frequency is based upon maintaining a constant level of snubber protection to safety-related systems during an earthquake or severe transient.
Therefore, the required inspection interval varies inversely with the observej snubber failures and is determined by the number of inoperable snubbers found during the previous inspection, the total population or category size, and the previous inspection interval.
Snubbers may be categorized, basad upon their accessibility'during power operation, as accessible or inaccessible. These categories may be examined separately or jointly.
However, that decision must be made and documented before any. inspection,~ and that decision shall be used as the basis upon which to determine the next inspect'in interval for that category.
Inspections performed before that intervai has elapsed may be used as a new reference point to determine the next inspection.
However, the results of such early inspections performed f.re the original required time interval has elapsed (nominal time less 25%)..ay not be used to lengthen the required inspection interval.. Any~ inspection whose results require a shorter inspectior interval will' override the previous schedule.
The acceptance' criteria are to be used in the visual inspection to determine OPERABILITY of the snubbers.
For example, if a fluid port of a hydraulic snubber is found to be uncovered, the snubbcr shall be declared unacceptable and may be re-classified as acceptable for determining the next inspection interval provided that:
(1) an analysis for the hydraulic fluid of
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that particular snubber had indicated that the fluid still meets its required L
specifications; and.(2) the affected snubber is functionally tested in the as-found. condition and determined OPERABLE per Specification 4.7.9f.
To provide assurance of snubber functional reliability, one of three functional testing methods is used with the stated acceptance criteria:
1.
Functionally test 10% of a type of snubber with an additional 10%
tested for each functional testing failure, or 2.
Functionally test a sample size and determine sample acceptance or rejection using Figure 4.7-1, or SOUTH TEXAS - UNITS 1 & 2 B 3/4 7-5 Unit 1 - Amendment No. 17, 44 Unit 2 - Amendment No. 9, 33
PLANT SYSTEMS BASES SNUBBERS (Continued) 3.
Functionally test a representative sample size and determine sample acceptance or rejection using the stated equation.
Figure 4.7-1 was developed using "Wald's Sequential Probability Ratio Plan" as described in " Quality Control and Industrial Statistics" by Acheson J.
Duncan.
Permanent or other exemptions from the surveillance program for in 'vidual d
snubbers may be granted by the Commission if a justifiable basis for exemption is presented and, if applicable, snubber life destructive testing was performed to qualify the snubbers for the applicable design conditions at either the completion of their fabrication or at a subsequent date.
Snubbers so exempted shall be listed in the list of individual snut,bers inuicating the extent of the exemptions.
The service life of a snubber is established <!a manufacturer input and information through consideration of the snobber service conditions and associatcd installation and maintenance records (newly installed snubbers. seal replaced, spring replaced, in high radirtion area, in high temperature area, etc.). The requirement to monitor the snubber service life is included to ensure that the snubbers periodically undergo a performance evaluation in view of their age and operating conditions.
These records will provide statistical bases for future consideration of snubber service life.
3/4.7.10 SEALED SOURCE CONTAMINATION The limitations on removable contamination for sources requiring leak testing, including alpha emitters, is based on-10 CFR 70.39(M '3) limits for plutonium.
This limitation will ensure that leakage-from Bypioduct, Source, and Special Nuclear Material sources will not exceed allowable intake values.
Sealed sources are classified into three groups according to their use, with Surveillance Requirements commensurate with the probability of damage to a source in that group._ Those sources which are iraquently hancied are required to be tested more often than those wnich are not.
Sealed sources which are continuously enclosed within a shielded mechanism (i.e., sealed sources within radiation monitoring or boron measuring devices) are considered to be stored and nr.ed not be tested unless they-are removed frm the shielded mechanism.
3/4.7.11 (Not used) 3/4.7.12 (Not used)
SOUTH TEXAS - UNIla 1 &2 B 3/4 7-6 Unit 1 - Amendment No. I.9, 44 Unit 2 - Amendment No. 9, 23
4 PLANT SYSTEMS BASFS 3/4.7.13 AREA TEMPERATURE MONITORING The area temperature limitations ensure that safety-related equipment will not be subjected to temperatures in excess of their environmental qualification temperatures.
Exposure to excessive temperatures may degrade equlpment and can cause a loss of its OPERABILITY.
The temperature limits include an allowance for instrument error of i 3*F maximum.
3/4.7.14 ESSENTIAL CHILLED WATER SYSTEM The OPERABILITY of the Essential Chilled Water System ensures that sufficient cooling capacity is available fcr continued operation of safety-
~
related equipment during normal and accident conditions, ine redundant cooling capacity of this system, assuming a single failure, is consistent with the assumptions used in the safety analyses, jl 8
SOUTH TEXAS - UNITS 1 & 2 B 3/4 7-7 Unit 1 - Amendment No. 44 Unit 2 - Amendment No. 33
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