ML20212R184

Proposed Changes Deleting Refs to Charging Sys,Iodine Cleanup Sys & Hydrogen Recombiner Sys & Adding RCS Sample Sys to Tech Spec Section 6.8.5.a.NSHC & Justification Encl

ML20212R184
Person / Time
Site:	Sequoyah
Issue date:	04/17/1987
From:	TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML20212R179	List: ML20212R178 ML20212R184
References
NUDOCS 8704240337
Download: ML20212R184 (6)

Text

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ENCLOSURE 1 PROPOSED TECHNICAL SPECIFICATION CHANGE SEQUOYAH NUCLEAR PLANT UNIT 1 DOCKET NOS. 50-327 2

d (TVA SQN TS 87-12)

CORRECTING LIST OF SYSTEMS SHOWN .

IN SECTION 6.8.5.a LIST OF AFFECTED PAGES UNIT 1 1

6-15a j

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8704240337 870417 PDR ADOCK 05000327 PDR p  !

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ADMINISTRATIVE CONTROLS I

b.

j Quality Assurance Program for environmental monitoring, using the s guidance contained in Regulatory Guide 4.15, December 1977. .

c.

Surveillance requirements and environmental monitoring requirements shown in Table 6.1-1.

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6.8.5 ~

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The following programs shall be established, implemented, and maintained: .

a. Primary Coolant Sources Outside Containment A program to reduce leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to as The systems include +'- -'- ;' ; ryr'- ,gl w as practical levels.

i heatremovalsystem,chemicalandvoIumecontrolsystem,containmentsa 4 -

spray system i;di;. :1;;;;; ;y;t;;, and by 90 The program s, hall include the following:b g;t rec g ~"' ,,

tr tyrter l ,

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(i) Preventive maintenance and periodic visual inspection requirements, and (ii)

Integrated cycle leak or intervals testless..

requirements for each' system at refueling

b. In-Plant Radiation Monitoring i

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A program which will ensure the capability to accurately determine the airborne iodine concentrations in vital areas under accident conditions. This program shall include the following:

i (1) Training of personnel, 2

(ii) Procedures for monitoring, and -

(iii)

Provisions for maintenance of sampling and analysis equipment.

c. Secondary Water Chemistry i A programtube generator for monitoring degradation.of secondary water chemistry to inhibit steam This program shall include:

i (1)

) Identification of a sampling schedule for the critical variables and control points for'these variables, (ii)

Identification of the procedures used to measure,the values of q

the critical variables, (iii) Identification of process sampling points, i

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January 14, 1986 '

l SEQUOYAH - UNIT 1 6-15a Amendment No. 42 I

ENCLOSURE 2 PROPOSED TECHNICAL SPECIFICATION CHANCE SEQUOYAH NUCLEAR PALNT UNIT 1 DOCKET NOS. 50-327 (TVA SQN TS 87-12)

DESCRIPTION AND JUSTIFICATION FOR PROPOSED CHANGES TO THE LIST OF SYSTEMS SHOWN IN SECTION 6.8.5.a l

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I DESCRIPTION OF CHANGE -

This change corrects section 6.8.5.a. " Primary Coolant Sources Outside Containment," on page 6-15a in the unit 1 technical specifications. The list of systems shown is revised by deleting the charging system, the iodine cleanup system, and the hydrogen recombiner system, and by adding the Reactor Coolant System (RCS) sample system, i

REASON FOR CHANGE A review of Sequoyah technical spec.ifications revealed some unjustified discrepancies between section 6.8.5.a of unit 1 technical specifications and the same section of unit 2 technical specifications. Section 6.8.5.a contains a list of systems which have portions outside containment that could contain j highly radioactive primary coolant fluids during a serious transient or accident. The list given in the unit 1 technical specifications erroneously I includes the charging system, iodine cleanup system, and hydrogen recombiner system. At Sequoyah the charging system.is part of the chemical and volume control system (CVCS). Because the CVCS is included in the list, the charging system should not be listed separately. An iodine cleanup system does not exist at Sequoyah, therefore, it should not be included in the list. The hydrogen recombiner system does exist,at Sequoyah, but this system does not have portions outside containment, therefore, it should not be included in the list.

The RCS sample system is listed in this section in the unit 2 technical ,

specifications, but it is not listed in the unit 1 technical specifications.  ;

j The RCS sample system is appropriate for the section, and it should be added to the list given in the unit 1 technical specifications.

} In an effort to determine the cause of these unjustified discrepancies TVA reviewed previous technical specification revisions, previous technical i specification change requests, and previous issuances of technical

! specification amendments. A review of the original version of unit 1 and unit

! 2 technical specifications showed that the list of systems was initially

! correct and consistent. A review of technical specification change requests

) and associated NRC-approved amendments revealed that TVA has never requested a 3 change for section 6.8.5.a; however, Amendment No. 13 to Facility Operating

License No. DPR-77 (reference letter dated May 4, 1982, from Elinor G. Adensam, NRC, to H. G. Parris, TVA) did include the erroneous ,

information, i JUSTIFICATION FOR CHANGE This change will correct an erroneous and apparently inadvertent amendment -

made to section 6.8.5.a of Sequoyah's unit 1 technical specifications. This change will make the systems listed in section 6.8.5.a appropriate for the design at Sequoyah and will reestablish consistency between the list of systems shown in the unit 1 and unit 2 technical specifications, i

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ENCLOSURE 3 PROPOSED TECHNICAL SPECIFICATION CHANCE SEQUOYAH NUCLEAR PLANT UNIT 1 l

DOCKET NOS. 50-327 i

(TVA SQN TS 87-12) i i DETERMINATION OF NO SIGNIFICANT HAZARDS CONSIDERATIONS I FOR PROPOSED CHANGES TO THE LIST OF SYSTEMS SHOWN

[ IN SECTION 6.8.5.a I

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SIGNIFICANT HAZARDS EVALUATION

1. Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated?

No. This change will correct an erroneous and apparently inadvertent amendment made to section 6.8.5.a of Sequoyah's unit 1 technical specifications. This change will make the systems listed in section 6.8.5.a appropriate for the design at Sequoyah and will reestablish consistency between the list of systems shown in the unit 1 and unit 2 technical specifications.

2. Does the proposed amendment create the possibility of a new or different kind of accident from any accident previously evaluated?

No. The proposed change-does not change the plant's design, procedures, or testing; therefore, it will not create any new accidents.

j 3. Does the proposed amendment involve a significant reduction in a margin of safety?

No. The proposed change does not affect the plant's design basis or its operation.

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