ML19274D321
| ML19274D321 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 01/18/1979 |
| From: | Johnson W YANKEE ATOMIC ELECTRIC CO. |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19274D322 | List: |
| References | |
| WYR-79-5, NUDOCS 7901230170 | |
| Download: ML19274D321 (112) | |
Text
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Proposed Change No. 166 Telephone 617 366-9011 m
710-390-0739 YANKEE ATOMIC ELECTRIC COMPANY PC 166-1 B.3.2.1 20 Turnpoke Road Westborough, Massachusetts 01581
.Ya&
uxse WYR 79-5 January 16, 1979 United States Nuclear Regulatory Commission Washington, D. C.
20555 Attention: Office of Nuclear Reactor Regulation
References:
(a) License No. DPR-3 (Docket No. 50-29)
(b) Letter from B. K. Grimes, Assistant Director for Engineering and Projects, USNRC, to All Pressurized Water Reactor Licensees, dated July 11, 1978 (c) Letter frc,m B. K. Grimes, Assistant Director for Engineering and Projects, USNRC, to All Pressurized Water Reactor Licensees, dated November 15, 1978
Dear Sir:
Subject:
Yankee Rowe Radiological Effluent Technical Specifications Pursuant to Section 50.59 of the Commission's Rules and Regulations, Yankee Atomic Electric Company hereby proposes the following modification to Appendix A of the Operating License.
Proposed Change: Reference is made to the Operating License DPR-3 and the Technical Specifications contained in Appendix A issued to the Yankee Atomic Electric Company for the Yankee Nuclear Power Station (Yankee Rowe). We propose to make the following changes:
(1) Add to Section 1.0 " Definitions," new definitions for " Source Check,"
"Offsite Dose Calcu1.ation Manual," " Gaseous Radwsste Treatment System," and " Vent aation Exhaust Treatment System" in accordance with the use of these terms in the new specifications outlined below.
(2) Section 3/4.3.3.1 " Radiation Monitoring Instrumentation" is revised by moving radiation monitoring instrumentation alarm setpoint and measurement range data from the technical specifications to appro-priate station procedures in accordance with NRC model Technical Specification guidance. Effluent instrumentation has been taken from Section 3/4.3.3.1 and placed in Sections 3/4.3.3.5 and 3/4.3.3.6.
(3) Add new section 3.3.3.5 " Radioactive Liquid Effluent Instrumentation."
The inclusion of this section reflects new criteria put forth by p
USNRC in their Effluent Standard Technical Specifications.
1 b
(4) Add new section 3.3.3.6 " Radioactive Caseous Process and Ef fluent i
Monitoring Instrumentation." The addition of this specification
[
reflects new criteria put forth by USNRC in their Effluent Standard 790123o(70
T United States Nuclear Regulatory Commission January 18, 1979 Attention: Office of Nuclear Reactor Regulation Page 2 Technien1 Specifications.
(5) Delete section 3/4.7.7.1 " Radioactive Solid Waste." The contents of this section dealing with the handling of solid radioactive waste have been renumbered to a new section 3/4.11.3 in accordance with the format of the USNRC Effluent Standard Technical Specifications.
(6) Delete sections 3/4.7.7.2 " Radioactive Liquid Waste," 3/4.7.7.3
" Radioactive Gaseous Waste," and 3/4.7.8 " Environmental Monitoring."
The contents of these sections have been revised to reflect the guidance put forth by the USNRC and have been renumbered to sections 3/4.11.1, 3/4.11.2, and 3/4.12.1 respectively in order to reflect the format of the USNRC Effluent Standard Technical Specifications.
(7) Add new section 3/4.11.1 " Liquid Effluents." The contents of this specification reflect the guidance put forth in the USNRC Effluent Standard Technical Specifications. It insures that the requirements of 10CFR20 and 10CFR50, including Appendix I, with respect to liquid effluent concentrations, resulting dose to the general public, and the availability and use of liquid radwaste equipment, are met.
(8) Add new section 3/4.11.2 " Gaseous Effluents." The contents of this specification reflect the guidance put forth in the USNRC Effluent Standard Technical Specifications. It insures that the requirements of 10CFR20, 10CFR50, including Appendix I and 40CFR190 with respect to doses to the general public resulting from plant effluents, and the availability, integrity and use of the gaseous radwaste equipment, are met.
(9) Add new section 3/4.12.2 " Land Use Census." The contents of this section deal with the identification and location of land uses which could affect the calculated dose to individuals from plant -
effluents. This specification reflects the guidance given by the USNRC in the Effluent Standard Technical Specifications.
- (10) Add new section 3/4.12.3 "Interlaboratory Comparison Program."
This new specification deals with quality control of laboratory analyses performed on samples collected as part of the Environmental Monitoring Program and is in accordance with the USNRC Effluent Standard Technical Specifications.
(11) As part of the Administrative Controls, add to section 6.5.2.9
" Audits," the ' Radiological Environmental Monitoring Program,'
and 'The Offsite Dose Calculation Manual,' in order to reflect the inclusion of these items in the specifications.
(12) As part of the Administrative Controls, add to section 6.8 " Pro-cedures," the requirement to include the Radiological Environmental Monitoring Program, the offsite releases of gaseous and liquid effluents and effluent mon 1toring instrumentation seti7ints in accordance with the new specifications which address these items.
United States Nuclear Regulatory Commission January 18, 1979 Attention: Office of Nuclear Reactor Regulation Page 3 (13) As part of the Administrative Controls, add to section 6.9.4.b.
" Thirty Day Written Reports," the requirement to report the content of gaseous holdup tanks in excess of that permitted under the new specification 3/4.11.2.7, the unplanned release of radioactive materials above given quantities, and the measured levels of radio-activity in environmental sampling media in excess of given limits.
(14) In section 6.9.5 " Unique Reporting Requirements" of the Administrative Controls, add new requirement for reporting results of the radio-logical environmental monitoring program, and the semiannual effluent release report in accordance with the guidance put forth in the Effluent Standard Technical Specifications.
(15) In section 6.9.6 for "Special Reports," add requirements for
' Liquid Effluents,' Specifications 3.11.1.2 and 3.11.1.3; ' Gaseous Effluents,' Specifications 3.11.2.2., 3.11.2.3 and 3.11.2.4;
'Sclid Radioactive Waste,' Specification 3.11.3.1; and ' Radiological Environmental Monitoring,' Specifications 3.12.1, 3.12.2, and 3.12.3.
Revised Technical Specification pages are provided with this letter.
Reason for Change: The proposed changes are in direct response to the USNRC's request (references b and c) that Yankee Atomic Electric Company amend Yankee Rowe's Operating License.
Basis for Change: The proposed technical specifications address issues put forth by the USNRC in their Draft Radio 1cgical Effluent Standard Technical Specifications (references b and c) and are intended to implement the following Federal Regulations; 10 CFR Part 50, Section 50.36a, Section 50.34a(a), Section 50.34a,10 CFR Part 20,10 CFR Part 50, Appendix A, General Design Criteria 60 and 64, and 50 CFR Part 190.
Since the waste dispcsal system at Yankee Rowe complies with the regula-tiots set forth an 10 CFR 50.34a and Appendix A Criterion 60, we believe that further commitments to your requests in Reference (c) cannot be made at this time.
We would be interested in discussing this topic further with your staff, af ter receipt and review of the generic value-impact and specific value-impact assessment for Yankee Rowe, in support of your proposed regulatory actions. As you are aware, NRC Chairman Joseph Hendrie committed to provide value-impacts in his July 21, 1978, response to Executive Order 12044. This response has been documented in Federal Register Vol. 43, No. 150, dated August 3, 1978, pages 34358 and 34359 which states in part:
"The Policy of the Nuclear Regulatory Commission is that value-impact analysis be conducted for any proposed regu-latory actions that might impose a significant burden on the public... [end] where there are alternative means of realizing equivalent benefits... cost should be a prime consideration."
Certainly the resultant modifications of the waste disposal systems of many nuclear power plants to provide for the intended conversion of
United States Nuclear Regulatory Commission January 18, 1979 Attention: Office of Nuclear Reactor Regulation Page 4 radioactive wastes from liquid systems to a homogeneous monolithic, immobilized free standing solid under the process control requirements of Reference (c) will impose a significant economic impact "... on the nuclear industry and hence on electric consumers." Lastly, we are interested in the documentation upon which your staff concluded that these proposed actions will provide substantial additional protection of the public health and safety as stipulated under 10 CFR 50.109.
We have included with this letter a draft of the "Offsite Dose Calculation Manual (CJCM)" for implementing the dose requirements of the proposed Technical Specifications. Work on this manual is continuing and a final version will be forwarded to you for your review within sixty days.
Along with the ODCM, we have included one-line diagrams indicating the effluent flow paths for both liquid and gaseous radwaste, the location of all effluent monitors, and those equipment items which are included in the liquid and gaseous radwaste treatment system.
Safety Considerations: The changes proposed were requested by the USNRC Draft and are not considered to constitute an unreviewed safety question.
This change has been reviewed by the Nuclear Safety Audit and Review Committee.
Fee Determination: The major portion of the proposed change is an exten-sion of the 10 CFR Part 50, Appendix I design study submitted to the USNRC on June 2, 1976, and constitutes completion of the requirements of Appendix I for the submittal of technical specifications. We conclude that this amendment is exempt from any fees defined in 10 CFR Part 170.12(c) since fees were not applicable when the requirements put forth by Appendix I to 10 CFR Part 50 became effective, and since submittal of this infor-nation has been delayed pending guidance from the USNRC which was issued in July,1978 (reference b).
Schedule of Change: These changes will be incorporated into Yankee Rowe's Technical Specifications 90 days af ter approval by the Commission, but in no case before September 30, 1979.
Very truly yours, YANKEE ATOMIC ELECTRIC COMPANY W. P Johnson Vice President Enclosures COMMONWEALTH OF MASSACHUSETTS)
January 18, 1979
)ss COUNTY OF WORCESTER
)
Then personally appeared before me, W. P. Johnson, who, being duly sworn, did state that he is a Vice President of Yankee Atomic Electric Company, that he is duly authorized to execute and file the foregoing request in the name and on the behalf of Yankee Atomic Electric Company, and that the statements therein are true to the best of his knowledge and belief.
N A.h Robert H, Croce ~
Notary Public My Commission Expires September 14, 1984