ML20059D502

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Safety Evaluation Supporting Amends 57 & 46 to Licenses NPF-76 & NPF-80,respectively
ML20059D502
Person / Time
Site: South Texas  
Issue date: 12/30/1993
From:
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20059D497 List:
References
NUDOCS 9401070335
Download: ML20059D502 (6)


Text

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SAFETY EVALUATION BY THE OFUCE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NOS. 57 AND 46 TO FACILITY OPERATING LICENSE NOS. NPF-76 AND NPF-80 HOUSTON LIGHTING & POWER COMPANY CITY PUBLIC SERVICE BOARD OF SAN ANTONIO CENTRAL POWER AND LIGHT COMPANY CITY OF AUSTIN. TEXAS DOCKET NOS. 50-498 AND 50-499 SOUTH TEXAS PR,0 JECT. UNITS 1 AND 2

1.0 INTRODUCTION

By applica. tion dated September 15, 1993, as supplemented by letter dated Novemt- - 30, 1993, Houston Lighting & Power Company, et.al., (the licensee) reque. k d changes to the Technical Specifications (Appendix A to Facility Operating License Nos. NPF-76 and NPf-80) for the South Texas Project, Units 1 and 2 (STP). The proposed changes would implement the revised'10 CFR Part 20.

The changes consist of editorial changes to provide consistency between the technical specifications (TS) and the revised 10 CFR Part 20 and changes to the effluent limits cross referenced to the former 10 CFR Part 20 in the implementation of 10 CFR Part 50, Appendix I limits. The November 30, 1993, submittal did not expand the scope of the original application, and did not change.the proposed no significant hazards consideration determination.

2.0 EVALUATION On May 21, 1991, the Nuclear Regulatory Commission issued a revision to 10 CFR Part 20, Standards for Protection Aaainst Radiation.

The licensee has revised the technical specifications to include wording that is consistent.with the revised 10 CFR Part 20 and will retain the same overall level of effluent control required to meet the design objectives of Appendix I to 10 CFR-Part

50. An evaluation was not performed on item 1(c) regaraing the definition of.

" UNRESTRICTED AREA" because this item is still being evaluated.

The proposed TS changes and evaluations follow:

1.

(a) TS 1.18 DEFINITIONS The licensee has. proposed to change the definition of MEMBER (S) 0F THE PUBLIC to conform to the' wording in 10 CFR 20.1003.

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t The change is administrative in nature to implement the corresponding-l revised 10 CFR Part 20 definition and is acceptable.

(b) TS 1.31 DEFINITIONS L

The licensee has proposed to change the definition of SITE BOUNDARY to conform to the wording in 10 CFR 20.1003.

The change is administrative in nature to implement the corresponding revised 10 CFR Part'20 definition and is acceptable.

(c)'TS 1.39 DEFINITIONS

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E The licensee has proposed to change the definition of UNRESTRICTED AREA to conform to the wording in 10 CFR 20.1003.

The staff is continuing to evaluate this definition as a generic issue and guidance will be forthcoming. Therefore, this item is not approved at this time.

2.

BASES 3/4.11.1.4 LIQUID HOLDUP TANKS The licensee has proposed to revise the BASES to replace the. reference to :

" Appendix B, Table II" with " Appendix B, Table'2" and to clarify that the tanks have a 10 curie limit.

The changes are administrative in nature.and are acceptable, 3.

TS 5.1.3 MAP DEFINING UNRESTRICTED AREAS AND SITE B0UNDARY FOR RADI0 ACTIVE GASE0US AND LIQUID EFFLUENTS The licensee has proposed to delete the reference to "10 CFR 20.3(a)(17)"

and update the site maps to make the notes on the maps more legible and "i

to clarify the location of unrestricted, controlled, and restricted areas.

The changes are administrative in nature and are acceptable.

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TS 6.8.3.g Radioactive Effluent Controls Program The licensee has proposed to revise item 2 of this TS to change.the liquid effluent release coricentration values to "10 times 10 CFR Part 20.1001-20.2401, Appendix B, Table 2 Column 2."

The licensee has proposed this change in order to retain operational flexibility consistent with Appendix-I to 10 CFR Part 50,' concurrent with the implementation of.the revised 10 CFR Part 20.

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.< The current requirements for the content of the licensee's TS concerning radioactive effinents are contained in 10 CFR 50.36a. Section 50.36a of Title 10 of the Code of Federal Regulations requires licensees to maintain control over radioactive material in gaseous and liquid effluents to unrestricted areas, produced daring normal reactor operations, to levels that are as low as reasonably achievable (ALARA).

For power reactors, Appendix I to 10 CFR Part 50 contains the numerical guidance to meet the ALARA requirement. The dose values specified in Appendix I of 10 CFR Part 50 are small percentages of the implicit. limits in 10 CFR 20.106 and the explicit limits in 10 CFR 20.1301. As secondary controls, the instantaneous dose rates required by this TS were chosen by the staff to help maintain annual average releases of radioactive material in gaseous and liquid effluents to within the dose values-specified in Appendix I of 10 CFR Part 50.

For the purposes of this TS, 10 CFR Part 20 is used as a source of reference values only. These TS requirements allow operational flexibility, compatible with considerations of health and safety, which may temporarily result in release rates which, if continued for the calendar quarter, would result-in radiation doses higher than specified in Appendix I of 10 CFR Part 50.

l However, these releases are within the implicit limits in 10 CFR 20.106 and the explicit limits in 10 CFR 20.1302 which references Appendix B, Table 11 concentrations. These referenced concentrations in the old 10 CFR Part 20 are specific values which relate to an annual dose of 500 mrem. The liquid effluent radioactive effluent concentration limits given in Appendix B, Table 2, Column 2 to 10 CFR 20.1001-20.2401 are based on an annual dose of 50 mrem total effective dose equivalent.

Since an instantaneous release concentration corresponding to a dose. rate of 500 mrem / year has been acceptable as-a TS limit for liquid effluents, which applies at all times to assure that the values in Appendix 1 of 10 CFR Part 50 are not likely to be exceeded, it is not necessary to reduce this limit by a factor of ten.

The licensee states that operational history at STP has demonstrated that the use of the concentration values associated with 10 CFR 20.106 as TS limits has resulted in calculated maximum individual doses to a member of the public that are small percentages of the values given-in Appendix I to 10 CFR Part 50.

Therefore, the use of effluent concentration values that are ten times those listed in Appendix B, Table 2, Column 2 to 10 CFR 20.1001-20.2t01 will not have a negative impact on the ability to continue to operate within the design objectives in Appendix I to 10 CFR Part 50 which are a fraction of the 10 CFR 20.1301 limits.

Based on the above, it is acceptable that the instantaneous limits L

associated with the liquid release rate TS are based on ten times the effluent concentration values given in Appendix B, Table 2, Column 2 to 10 CFR 20.1001-20.2401.

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TS 6.8.3.g Radioactive Effluent Controls Program The licensee has proposed to revise item 3 of this TS to replace the reference."10 CFR 20.106" with "10 CFR 20.1302."

The change is administrative in nature to incorporate the corresponding revised 10 CFR Part 20 section number and is acceptable.

6.

TS 6.8.3.g Radioactive Effluent Controls Program The licensee has proposed to revise item 7 of this TS which specifies the limitations on the concentrations of radioactive material released in gaseous effluents. The licensee has proposed that the TS be revised to read as follows:

" Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas at or beyond the SITE BOUNDARY shall be limited to the following:

a.

For noble gases: Less than or equal to a dose rate of 500 mrem /yr to the total body and less than or equal to a dose rate of 3000 mrem /yr to the skin, and b.

For Iodine-131, Iodine-133, for tritium, and for all radionuclides in particulate form with half-lives greater than 8 days:

Less than or equal to a dose rate of 1500 mrem /yr to any organ."

The licensee has proposed this change in order to retain operational flexibility consistent with 10 CFR Part 50, Appendix I, concurrent'with the implementation of the revised 10 CFR Part 20.

The current requirements for the content of the licensee's TS concerning radioactive effluents are contained in 10 CFR 50.36a.

Section 50.36a of Title 10 of the ~ Code of Federal Regulations requires licensees to maintain control over radioactive material in gaseous and liquid effluents to unrestricted areas, produced during normal reactor operations, to levels that are ALARA. For power reactors, Appendix I to 10'CFR Part 50 contains the numerical guidance to meet the ALARA requirement.

The do e values specified in Appendix I of 10 CFR Part 50.

are small percentages of the implicit limits in 10.CFR 20.106 and the explicit limits in 10 CFR 20.1301. As secondary controls, the instantaneous dose rates required by this specification were chosen by the staff to help maintain annual average releases of radioactive material in gaseous and liquid effluents to.within the dose values.

specified in Appendix I of 10 CFR Part-50.

For purpose of the bases of this TS,10 CFR Part 20 is used as a source of reference values only.

These TS requirements allow operational flexibility, compatible with i

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considerations of health and safety, which'may temporar'ly result in i

release. rates' which, if continued. for the calendar quarter, would resulti in radiation doses higher than specified in Appendix I of 10 CFR Part-50.-

1 However, these releases are within the limits specified in 10 CFR 20.106 (10 CFR 20.1302).

This specification, which is based on guidance contained.in NUREG-0133,.

is acceptable as a TS limit for gaseous effluents, which applies at~ all' times as an assurance that the values in Appendix'I of 10 CFR Part 50 are.

.i not likely to be exceeded.

Based on the above, it is acceptable that the gaseous release: rate.TS for radioactive material be based on the stated dose rates.

7.

TS 6.9.1.2 ANNUAL REPORTS i

The licensee has proposed to revise this TS to replace the word

" personnel" with " individuals, for whom monitoring was required," and to' j

replace the reference "20.407".with "20.2206."

These changes are. administrative in nature to be consistent with the revised 10 CFR Part 20 and are acceptable.

8.

TS 6.10.3 RECORD RETENTION The licensee has proposed to reword item c of thisLspecification from

" Records of radiation exposure for all individuals entering radiation controls" to " Records of doses received by'all individuals for.whom-3

. monitoring was required."

The change.is' consistent with the revised 10 CFR Part 20 andLis acceptable.

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TS 6.12 HIGH RADIATION. AREA-The licensee:has proposed.several changes.to this specification in order.

to be consistent with'the revised 10 CFR Part 20. The references "20.203(c)(5)" and."20.203(c)" are changed to "20.1601(c)":and:

"20.1601(a)," respectively. The radiation level measurement distance-for.

classifying a high radiation area is changed from 18-inches to 30 cm. An upper limit of 500 rads in _one' hour at one meter is included to distinguish'the'TS requirements from those needed for a very high-radiation area. The phrase referencing ths' Health and Safety Services Manager.is changed to health' physics supervision to eliminate an:

organizational title. ~ Additionally, other terminology. changes were proposed (i.e., Mr/h'to mrem /h, exposure to dose,-and personnel to-t individuals) for consistency with the: revised 10 CFR Part 20.-

The changes-are consistent with the revised 10 CFR Part 20 and are acceptable.

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. 10. TS 6.14 0FFSITE DOSE CALCULATION MANUAL (ODCM)

The licensee has proposed to change the reference "10 CFR 20.106" to " loo CFR 20.1302."

The change is administrative in nature to incorporate the corresponding revised 10 CFR Part 20 section number and is acceptable.

3.0 STATE CONSULTATION

In accordance with the Commission's regulations, the Texas State official was notified of the proposed issuance of the amendments. The State official had no comments.

4.0 ENVIRONMENTAL CONSIDERATION

Pursuant to 10 CFR 51.21, 51.32 and 51.35, an environmental assessment and finding of no significant impact was published in the Federal Reaister.on December 27, 1993 (58 FR 68445).

Accordingly, based upon the environmental assessment, the Commissi a has determined that issuance of.the amendments will not have a significant effect on the-quality of the human environment.

5.0 CONCLUSION

The Commission has concluded, based on the considerations discussed above, that:

(1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations,-

and (3) the issuance of the amendments will not be inimical to the common-defense and security or to the health and safety of the public.

Principal Contributor: Steve Klementowicz Date:

December 30, 1993

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