ML20214U229

Proposed Tech Specs,Consisting of Tech Spec Change 87-06, Deleting Table 4.4-5, Reactor Vessel Matl Surveillance Program - Withdrawal Schedule

ML20214U229
Person / Time
Site:	Sequoyah
Issue date:	05/29/1987
From:	TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML20214U169	List: ML20214U165 ML20214U229
References
TAC-R00151, TAC-R00152, TAC-R00164, TAC-R151, TAC-R152, TAC-R164, NUDOCS 8706110102
Download: ML20214U229 (7)

Text

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ENCLOSURE 1 PROPOSED TECHNICAL SPECIFICATION CHANGE SEQUOYAH NUCLEAR PLANT UNIT 1 DOCKET NO. 50-327 (TVA SQN TS 87-06)

AMENDMENT OF SECTION 3/4 4.9 PRESSURE / TEMPERATURE LIMITS OF THE REACTOR COOLANT SYSTEM LIST OF AFFECTED PACES UNIT 1 3/4 4-23 3/4 4-23a

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REACTOR COOLANT SYSTEM 3/4.4.9 PRESSURE / TEMPERATURE LIMITS REACTOR COOLANT SYSTEM LIMITING CONDITION FOR OPERATION

'3.4.9.1 The Reactor Coolant System (except the pressurizer) temperature and pressure shall be limited in accordance with the limit lines shown on Figures 3.4-2 and 3.4-3 during heatup, cooldown, criticality, and inservice leak and hydrostatic testing with: ,

a. A maximum heatup of 100*F in any one hour period.

b. A maximum cooldown of 100*F in any one hour period.

c. A maximum temperature change of less than or equal to 5*F in any one hour period during inservice hydrostatic above the heatup and cooldown limit cubve.and s. leak testing operations APPLICABILITY: At all times.

ACTION:

k With any of the above limits exceeded, restore the temperature and/or pressure to within the limit within 30 minutes; perform an engineering evaluation to determine the effects of the out-of-limit condition on the structural integrity of the Reactor Coolant System; determine that the Reactor Coolant System remains acceptable for continued operations 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 reduce the RCS T,yg and pressure to less than 200*F and 500 psig, respectively, 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 4.4.9.1.1 The Reactor Coolant System temperature and pressure shall be determined to be within the limits at least once per 30 minutes during system heatup, cooldown, and inservice leak and hydrostatic testing operations.

4.4.9.1.2 The reactor vessel material irradiation surveillance specimens shall be removed and examined, to determine change in material properties,-at-

-the-inteevais-required-by$ts in-Table-A 4 The resu of these examinationFshall be used to update 10 CFR 50, R A Figures 3.4-2 and 3.4-3. '

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O ENCLOSURE 2 -

4 PROPOSED TECHNICAL SPECIFICATION CHANGE SEQUOYAH NUCLEAR PLANT UNIT 1 DOCKET NO. 50-327 (TVA SQN TS 87-06)

DESCRIPTION AND JUSTIFICATION FOR PROPOSED AMENDMENT OF SECTION 3/4 4.9 PRESSURE / TEMPERATURE LIMITS OF THE REACTOR COOLANT SYSTEM i

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ENCLOSURE 2 Description of Channes The proposed amendment would effect the following changes: l

. 1. Delete Table 4.4-5, " Reactor Vessel Material Surveillance Program -

Withdrawal Schedule." i

2. Delete all references to the aforementioned table 4.4-5 in the Surveillance Requirement (SR) 4.4.9.1.2.

Reason for Changes The reasons for making the changes to the unit 1 technical specifications that would be affected by the proposed amendment are:

1. Table 4.4-5 is of little use to the intended user of the technical specifications, the reactor operator.

2. The unit 1. technical specifications would be simplified by the deletion of table 4.4-5 and all references to that table.

3. The requirements for surveillance of reactor vessel material, including the definition of a withdrawal schedule that is approved by NRC, are stated in 10 CFR Part 50, Appendix H.

Justification for Channes The changes that would be affected by the proposed amendment are justified as follows:

1. TVA is required to comply with 10 CFR Part 50, Appendix H. " Reactor Vessel Material Surveillance Program Requirements." The requirements of Appendix H provide for NRC approval of a proposed withdrawal schedule before implementation and identify both the applicable American Society for Testing of Materials (ASTM) and American Society of Mechanical Engineers (ASME) Codes and the applicable reporting requirements. Thus, the inclusion of table 4.4-5 in SR 4.4.9.1.2 is redundant to requirements of 10 CFR Part 50, Appendix H. The deletion of table 4.4-5 is, therefore, consistent with improvement of technical specifications by removing specifications that are redundant to regulation, as recommended by both the NRC Technical Specification Improvement Project and the Atomic Industrial Forum (AIF) Subcommittee on Technical Specification Improvements in October 1985.

2. The data of table 4.4-5 would be placed in Section 5.4.3.7, " Reactor Vessel Material Surveillance Program Requirements," of the Sequoyah Final Safety Analys.is Report (FSAR). This would occur at the next scheduled annual update of the FSAR that would occur following TVA's receipt of notification of approval of the proposed technical specification amendment by NRC. Thus, surveillance schedule would be available to NRC in an administratively controlled document that is reviewed and revised on a regular basis.

ENCLOSURE 3

• PROPOSED TECHNICAL SPECIFICATION CHANGE SEQUOYAH NUCLEAR PLANT UNIT 1 DOCKET No. 50-327 (TVA SQN TS 87-06)

DETERMINATION OF NO SIGH!FICANT HAZARDS CONSIDERATIONS FOR PROPOSED AMENDMENT OF SECTION 3/4 4.9 PRESSURE / TEMPERATURE LIMITS OF THE REACTOR COOLANT SYSTEM

ENCLOSURE 3 SICNIFICANT HAZARDS EVALUATION

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

No. The proposed technical specification would amend surveillance requirement (SR) 4.4.9.1.2 in SectLon 3/4 4.9, " Pressure / Temperature Limits, Reactor Coolant System," of the Sequoyah unit 1 technical specifications by deleting Table'4.4-5, " Reactor Vessel Material Surveillance Program - Withdrawal Schedule." Deletion of the subject table from the technical specifications will not affect the reactor vessel surveillance program requirements as specified in 10 CFR Part 50, Appendix H " Reactor Vessel Material Surveillance Program Requirements"; rather, the deletion will eliminate a license requirement that is redundant to regulation requirements. The proposed amendment is therefore administrative in nature and does not change plant hardware, plant operating setpoints or limits, or plant operating procedures. The potential for reactor vessel embrittlement affecting a postulated transient or accident conditions that have been previously evaluated is not increased as TVA is required to comply with 10 CFR Part 50, Appendix H. Thur, the proposed amendment involves no increase in the probability or consequences of an accident previously evaluated.

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

No. As previously stated, the proposed amendment is administrative in nature and does not change plant hardware, plant operating setpoints or limits, or plant operating procedures. Also, the evaluation of reactor vessel embrittlement is not affected as TVA is required to comply with 10 CFR Part 50, Appendix H. Thus, the proposed amendment does not create the possibility of a new or different kind of accident from any accident previously evaluated.

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

No. Again, as previously stated, the proposed amendment is administrative in nature and does not involve a change in plant hardware, plsnt operating setpoints or limits, or plant operating procedures. The evaluation of reactor vessel embrittlement is not affected as TVA is required to comply with 10 CFR Part 50, Appendix H. Thus, the proposed amendment involves no reduction in the margin of safety of the plant.

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