ML20212H218

Proposed Tech Specs,Deleting Conflicting Submittal Directions Per 10CFR50 & 51 Final Rule

ML20212H218
Person / Time
Site:	Sequoyah
Issue date:	02/27/1987
From:	TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML20212H214	List: ML20212H209 ML20212H218
References
NUDOCS 8703060044
Download: ML20212H218 (11)

Text

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i ENCLOSURE 1 PROPOSED TECHNICAL SPECIFICATION CHANGES SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 DOCKET NOS. 50-327, -328

' (TVA.SQN TS 87-01)

DELETION OF CONFLICTING SUBMITTAL DIRECTIONS CONTAINED IN TECHNICAL' SPECIFICATIONS AS AUTHORIZED BY NRC IN 10 CFR PARTS 50 AND 51 FINAL RULE LIST OF,AFFECTED PAGES UNIT 1 6-16 6-19 6-22

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UNIT 2 6-21 6-24 6-27

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ADMINISTRATIVE CONTROLS 6.9 REPORTING REQUIREMENTS R40 ROUTINE REPORTS 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted ta=the=9 erector

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ut QCC:tcw ma ;wd/ /C dM JD t' STARTUP REPORT 6.9.1.1 A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating li' cense, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant.

6.9.1.2 The startup report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required in license conditions

based on other commitments shall be included in this report.

6. 9.1. 3 Startup reports shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or commencement of. commercial power operation, or (3) 9 months following initial criticality, whichever is earliest. If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or commencement of commercial power operation), supplementary reports shall be submitted at least every three months until all three events have been completed.

e November 23, 1984 SEQUOYAll - UNIT 1 6-16 Amendment No. 36

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ADMINISTRATIVE CONTROLS determined by sampling frequency and measurement) shall be used for determining

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the gaseous pathway doses. The assessment of radiation doses shall be performed in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM).

The annual radioactive effluent release report to be submitted after January 1 of each year shall also include an assessment of radiation doses to the likely most exposed members of the public from reactor releases and other nearby ura-nium fuel cycle sources (including doses from primary effluent pathways and direct radiation) for the previous calendar year to show conformance with 40 CFR 190, Environmental Radiation Protection Standards for Nuclear Power Op-eration. Acceptable methoaY for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev. 1.

The semiannual radioactive effluent release reports shall include the following information for each type of solid waste identified in Regulatory Guide 1.21, Rev. 1,' Table 3, Part A, which is shipped offsite during the report period:

a. Total' volume of containers,

b. Total curie quantity (specify whether determined by measurement or

. estimate),

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c. Principal radionuclides (specify whether determined by measurement or estimate),

d. Type of quantity (e.g., LSA, Type A, Type B, etc.)

' The semiannual radioactive effluent release reports shall include unplanned.re-leases from the site to unrestricted areas of radioactive materials in gaseous and liquid effluents on a quarterly basis and shall include any changes to the PROCESS CONTROL PROGRAM (PCP) and the Offsite Dose Calculation Manual (ODCM) made during the reporting period. It shall include the type of solidification '

agent used, if applicable.

TI MONTHLY REACTOR OPERAFTNG REPORT I

6.9.1.10 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the PORVs or Safety Valves, shall be submitted on a monthly basis e- -

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no later than the 15th of each month following the calendar month covered by the report.

Any changes to the OFFSITE DOSE CALCULATION MANUAL shall be submitted with the Monthly Operating Report within 90 days in which the change (s) was made effective.

In addition, a. report of any major changes to the radioactive waste treatment systems shall be submitted with the Monthly Operating Report for the period in which the evaluation was reviewed and accepted by the PORC.

January 14, 1986 SEQUOYAH - UNIT 1 6-19 Amendment No.42

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ADMINISTRATIVE CONTROLS "-

l I R40 RADIAt. PEAKING FACTOR LIMIT REPORT 6.9.1.14 The W(z) function for normal op'eration shall be provided'te-the=Givece  !

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9&Meap= Regulatory:Commissioni=Washins i.wm&&,-2655$ at least 60 days ,

prior to cycle initial criticality. In the event that these values would be submitted at some other time during core life, it will be submitted 60 days prior to the date the values would become effective unless otherwise exempted by the Commission.

Any information 'needed to suport W(z) will be by request from the NRC and need not be included in this report.

SPECIAL REPORTS 6.9.2 Special reports shall be submitted u; ;a; Diretiur vi d:: Gi'!;: er 4W_iM-Enfc+r--- 1 2=gi <=1 ^ ;ur within the time period specified for each report)in accor dance with to CM2 SC,j i

6.10 RECORD RETENTION

. In addition to the applicable record retention requirements of Title 10, Code.

of Federal Regulations, the following records shall be retained for at least the minimum period indicated.

6.10.1 The following records shall be retained for at least five years:

a. Records and logs of unit operation covering time interval at each ---

power level.

b. Records and logs of principal maintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety.

c. All REPORTABLE EVENTS submitted to the Commission, g40

d. Records of surveillance activities, inspections and calibrations required by these Technical Specifications.

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Records of changes made to the procedures required by Specification 6.8.1 and 6.8.4.

f. Records of radioactive shipments.

g. Records of sealed source and fission detector leak tests and results.

h. Records of annual physical inventory of all sealed source material of record. -

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%+e, November 23, 1984 SEQUOYAH - UNIT 1 6-22 Amendment No. 36

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6.9 REPORTING REQUIREMENTS lR28 ROUTINE REPORTS 6.9.1

• In addition to the applicable-reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted ta=tharDirectae '

oduthe>Regionah0ffice. of Inspection =and: Enforcement =unless otherwine-mates.

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STARTUP REPORT d 6.9.1.1 A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has'a different design or has been manufactured by a different fuel supplier,'nd a (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant.

6.9.1.2 The s'tartup report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications. Any corrective actions that were required to obtain satisft: tory operation shall also be described. Any additional specific details required in license conditions based on other commitments shall be included in this report.

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G. 9.1. 3 Startup reports shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest. If the Startup Report does not cover all three events (i.e. , initial criticality, completion of startup test program, and resumption or commencement of commercial power operation), supplementary reports shall be submitted at least every three months until all three events have been completed.

Y November 23, 1984 SEQUOYAH - UNIT 2 6-21 Amendment No. 28 e

ADMINISTRATIVE CONTROLS exposure time and location) shall be included in these reports. The mete-orological conditions concurrent with the time of release of radioactive materials in gaseous effluents (as determined by sampling frequency and measure-ment) shall be used for determining the gaseous pathway doses. The assessment of radiation doses shall be performed in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM).

The annual radioactive effluent release report to be submitted after January 1 of each year shall also include an assessment of radiation doses to the likely most exposed members of the public from reactor releases and other nearby uranium fuel cycle sources (including doses from primary effluent pathways and direct radiation) for the previous calendar year to show conformance with 40 CFR 190, Environmental Radiation Protection Standards for Nuclear Power Operation.

Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev. 1.

The semiannual radioactive effluent release re' ports shall include the following information for each type of solid waste identified in Regulatory Guide 1.21, Rev. 1, Table 3, Part A, which is shipped offsite during the report period:

a. Total volume of containers, b.

Total curie quantity (specify whether determined by measurement or estimate),

c.

Principal radionuclides (specify whether determined by measurement or estimate), ':

d.

Type of quantity (e.g., LSA, Type A, Type B, etc.)

The semiannual radioactive effluent release reports shall include unplanned releases from the site to unrestricted areas of radioactive materials in gaseous and liquid effluents on a quarterly basis, and shall include any changes to the PROCESS CONTROL PROGRAM (PCP) and the Offsite Dose Calculation Manual (ODCM) made during the reporting period. It shall include the type of i solidification agent used, if applicable.

MONTHLY REACTOR OPERATING REPORT 6.9.1.10 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the PORVs or Safety Valves, shall be submitted on a monthly basis te m -ni w g -ars % ;  :- '

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. no later than the 15th of each month following the calendar month covered by the report.

Any changes to the OFFSITE DOSE CALCULATION MANUAL shall be submitted with the Monthly Operating Report within 90 days in which the change (s) was made effective.

In addition, a report of any major changes to the radioactive waste treatment systems shall be submitted with the Monthly Operating Report for the period in which the evaluation was reviewed and accepted by the PORC.

January 14, 1986 SEQUOYAH - UNIT 2 6-24 Amendment No. 34

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ADMINISTRATIVE CONTROLS

'R2 RADIAL PEAKING FACTOR LIMIT REPORT 6.9.1.14 The W(z) function for normal operation shall be provided ta

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20569 at least 60 days prior to cycle initial criticality..__.In..the _..,event

_ _. these values would be submitted at some other time during core life, it will be submitted 60 days prior to the date the values would become effective unless otherwise exempted by the Commission.

Any information needed to support W(z) will be by request from the NRC and need not be included in this report.

SPECIAL RE' PORTS 6.9.2 Special reports shall be submitted ^_ 21__ ^ - _- ^~^ - "

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- :reportraad=8a*WhMfice within the time period specified for each y m accce r'a,rm <w en /C C M 3*C,.4 6.16 RECORD RETENTION In addition to the applicable record retention requirements of Title 10, Code of Federal Regulations, the following records shall be retained for at least (w- the minimum period indicated, 6.10.1 The following records shall be retained for at least five years:

a. Records and logs of unit operation covering time interval at each power level.

b.

Records and logs of principal maintenance activities, inspections, repair and replacement of principal items of equipment rel.ated to nuclear safety.

c.

All REPORTABLE EVENTS submitted to the Commission. R21

d. Records of surveillance activities, inspections and calibrations required by these Technical Specifications.

e. Records of changes made to the procedures required by Specification 6.8.1 and 6.8.4.

f. -$ecords of radioactive shipments.

g.

Records of sealed source and fission detector leak tests and results.

h. Records of annual physical inventory of all sealed source material of record.

y November 23, 1984 SEQUOYAH - UNIT 2 6-27 Amendment No. 28

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ENCLOSURE 2 PROPOSED TECHNICAL SPECIFICATION CHANGES SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 DOCKET NOS. 50-327, -328 (TVA SQN TS 87-01).

DESCRIPTION AND JUSTIFICATION FOR DELETION OF CONFLICTING SUBMITTAL DIRECTIONS CONTAINED.IN TECHNICAL SPECIFICATIONS AS AUTHORIZED'BY NRC IN-10 CFR PARTS 50 AND S1 FINAL RULE .

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! ENCLOSURE 2 l

Description of Change ,

i Amend ~the technical specifications of Sequoyah Nuclear Plant units 1 and 2 so that directions'given by the technical specifications on submittals to NRC are consistent with those' determined in the 10 CFR Parts 50 and 51 Final Rule as published in the Federal Register on November 6,1986, and made effective January 5,' 1987.

Reason for Change -

Because of varying and sometimes conflicting requirements for the submittal of

.information by applicants and licensees, confusion'has arisen with regard to copy requirements and proper submittal procedures. In an effort to clarify these matters,'the NRC issued Regulatory Cuide 10.1 (Revision 4), _ " Compilation-of Reporting Requirements for Persons Subject to NRC Regulations," and on August 8, 1982, the Director, Division of Licensing, Office of Nuclear Reactor Regulation, issued Generic Letter 82-14 " Submittal of Documents to the Nuclear Regulatory Commission." While these efforts at clarification resolved much of the confusion, these guidance documents contain outdated information.

and, in many cases, conflict with requirements in regulations or individual

-licenses. Therefore, NRC has issued the 10 CFR Parts 50 and 51 Final Rule to specify copy requirements and provide mailing instructions for submittals to NRC.

Licensees whose technical' specifications contain submittal directions that conflict with those determined in the 10 CFR Parts 50 and 51 Final Rule.were authorized by the Final Rule to delete the conflicting directions by pen and ink changes to the technical specifications. The distribution of these pen and ink changes for all controlled copies of Sequoyah Nuclear Plant units 1 and 2 technical specifications has been initiated with the subject changes noted as a."Special Revision." For the purpose of complete documentation and to formally incorporate the pen and ink changes into the licenses of the respective units, these changes are also being submitted to NRC.

Justification for Change r

The determinations made in the 10 CFR Parts 50 and 51 Final Rule supersede all existing requirements and guidance with respect to the number of copies and i mailing procedures for submittals to NRC. The Rule also authorizes licensees to delete conflicting submittal directions by pen and ink changes to their technical specifications, where required, to make them consistent with the rule. Although neither required nor expected by NRC, this submittal will formally record and incorporate the subject changes into the licenses for i Sequoyah Nuclear Plant units 1 and 2.

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' ENCLOSURE 3 PROPOSED TECHNICAL SPECIFICATION CHANCES SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 DOCKET NOS. 50-327, -328 (TVA SQN TS 87-01) -

DETERMINATION OF NO SICNIFICANT HAZARDS CONSIDERATIONS FOR THE DELETION OF' CONFLICTINC SUBMITTAL DIRECTIONS CONTAINED IN TECHNICAL SPECIFICATIONS AS AUTHORIZED BY NRC IN 10 CFR PARTS 50 AND 51 FINAL RULE p

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9 (r ENCLOSURE 3 I

i SIGNIFICANT HAZARDS EVALUATION

1. Does.the proposed amendment involve a significant increase in;the

- probability or consequences of ~ an accident previously evaluated?

No. This amendment, already authorized by NRC in their determination of the.10 CFR Parts 50 and 51 Final Rule, deletes conflicting-submittal directions contained in'the technical specifications. In -

~ that this amendment affects only submittal directions, it follows.

that;the amendment results in no changes in either 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. Again,'as the amendment only deletes conflicting submittal

directions contained in the technical specifications, the 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 margin

of safety?

No. .Ageln, as the amendment only deletes conflicting submittal

. directions contained in the technical specifications, the amendment involves no reduction in margin of safety.

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