ML20062B776

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Proposed Tech Specs Deleting Requirement That Plant Operations Manager Hold Senior Reactor Operator License
ML20062B776
Person / Time
Site: South Texas  STP Nuclear Operating Company icon.png
Issue date: 10/15/1990
From:
HOUSTON LIGHTING & POWER CO.
To:
Shared Package
ML20062B775 List:
References
NUDOCS 9010260134
Download: ML20062B776 (5)


Text

{{#Wiki_filter:. f ATTACHMENT 2 PROPOSED REVISION TO SECTION 6.2.2,g s h l l l l 9010260134 901015 DR ADOCK 05000499 PDC A1/001.NL8

_ ~. Page 1 ADtESIEADYLCONJROLL-I UNIT STAFF (Continued) U 4. Except during extended shutdown periods, the use of overtime should be considered on an individual basis and not for the entire staf f on a shif t. Any deviation from the above guidelines shall be authert2ed by the Plant Manager or his deputy, or higher levels of management, in ~ i accordance with established procedures and with documentation of the i basis for granting the deviation. Controls shall be included in the 1 procedures such that individual overtime shall be reviewed monthly hy j the Plant Manager or his designee to assure that excessive hours have j not been assigned. Routine deviation from the above guidelines is not authorized. g. Senior reactor operator licenses shall be held hy: Dl:nt Oper&44en: ":r.;ger-Unit Operations Manager -l ) Shift Supervisors Unit Supervisors Reactor operator licenses shall be held by: Reactor Operators i i I SOUTH TEXAS - UNITS 1 & 2 6 Unit 1 --Amendment No. ),4: i i 1 ~

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Taste 3.12-1 (Contirued) Regulatory Guide senTaf t megulatory Guide Revision Status 50. Title tNSaa neference (ki STPEGS STPEGS Position 1.7 Control of C h tible Gas Concentrations in 3.11.5.1 Rev 2 (11/78) A Conteirment folteming e Loss-of-Coolant 6.2.5.1 Accident 6.2.5.2.1 6.2.5.2.4 6.2.5.2.5 6.2.5.3.3 Table T.1-1 Figure T.1-1 1.8 Personnel Selection and Training 13.1.3.1 Rev 1-a (5/TT) A see note T4 1.9 selectite of Dieset Generator set Capacity 8.3.1.2.3 new 2 (12/79) C (Exception is for Staruby Power steptles 3.3.1.1.4.2 discussed in p W 8.3.1.1.4.T 8.3.1.2.3) c) sn 1.10 nechanicet (Codmeld) sptices in seinforcing 3.8.1.2.2 new 1 (1/73) C.(Esceptions are c sers of Category Concrete Structures 3.8.1.6.2.3 discussed in twsma 3.8.1.6.5 References) g 3.8.3.2.2 see mete 45 3.8.3.6.2 3.8.4.2.2 1.11 Instrument Lines Penetrating Primary acactor 3.1.2.5.6.1 mev 8 (3/71) A Containment 6.2.4.1 T.3.1.1.2 Table 7.1-1 Figure 7.1-1 1.12 Instrumentation for Earthepsakes 3.7.4.1 Rev 1 (4/74) 8, D -See note 55 Table 7.1-1 1.13 spent Fuet storage recitity Design sesis 3.1.2.6.3.1 new 1 (12/75) FC A my -3.8.4.2.2 j y" 9.1.1.3 oo g 9.1.2.3 9.1.4.3 g a O n D w O

l STPECS UFSAR Page 2 { TABLE 3.12 1 (Cont'd) RECULATORY CUIDE MATRIX NOTES 66. The quality of diesel generator (DC) fuel oil is be checked as ) identified in Section 9.5.4.4. 67. The QA program during construction conformed to RC 1.28. Rev. 0. This p *d-is not applicable during the operations phase. l 68. Revision 4 of RC 1.16 does not reflect current regulations. - STPECS j conforms to regulatory requirements that supercede the requirements of' this RC; i.e.,10CFR50.72 and 10CTR50.73. 69. STPECS conforms to RC 1.118 concerning IEEE 338 1977'- Section 6, " Testing Program, however, during ongoing procedures development, a additional exceptions and clarifications may be identified. Refer to section 7,1.2.11 for discussion of conformance to RC 1.118 and IEEE 388-1977. 70. As stated in Section 8.3.2.2.5 the class 1E-DC system at STPECS 'is -in. compliance with RC 1.128 with partial exception. 71. STPECS is not committed to RC 1.143. Most components of the radwaste system are housed within Category I Sr.ructures. Those-components which are not housed within Category I Structures are either housed:in or supplied on structures conforming to NRC BTP ETSB 11 1,-Rev l', or their failure would not cause radiation release in excess of those considered-in the accident analysis. See Sections 11.2, 11.3 and 11.4 72. The steam generator tube inspection program meets the: requirements of RC 1.83, Rev 1. positions C.1 and C.2. - The scope of RC 1.83 positions C 3 through C.8 are addressed by the STPECS Technical Specifications which use the Standard Technical Specifications as a guida'- The Standard Technical Specification recommendations.diffor-from portions of positions C.3 through C.8 of the RC 1.83. 73. .STPECS conforms to RC 1.53 with clarifications as discussed.in Section-7.1.2.7. a i 74 Experience and training are substituted for the degree requirement for-the Health and Safety Service Manager, 75. The STPECS simulator was operati by, February 1986. This simulator ] will be certified in accor a with RC 1.149 by March 1991. 7%.e.; p)k=Aff tc>4)$ MA/MGM 'fe QU Ae 6 Y29 k @,- mc.6.o'c ec ea.. ond'4. preen.h A-1 0c W D p & t m Plca n cpts ? 3.12 32 Revision 0 ] _}}