ML20095D022
| ML20095D022 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood  |
| Issue date: | 04/13/1992 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20095D015 | List: |
| References | |
| NUDOCS 9204240253 | |
| Download: ML20095D022 (5) | |
Text
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SAFETY EVALUATION BY THE OFFICEJF NUCLEAR REACTOR REGULATIQH RELATED TO AMENDMENT N0. 46 TO FACILITY OPERATING llCENSE NO. NPF-E,
AMENDMENT NO. 46 TO FACILITY OPERATING LICENSE N0. NPF-66, AMENDMENT NO. 35 TO FACILITY OPERATING LICENSE NO. NPF-72, AND AMENDMENT N0. 35 TO FACILITY OPERATING LICENSE NO. NPF-77 COMMONWEALTH EDIS0N COMPANY BYRON STATION. UNIT NOS 1 AND 2 BRAIDWOOD STATION. UNIT NOS 1 AND 2 DOCKET NOS. STN 50-454. STN 50-455. STN 50-456 AND STN 50-457
1.0 INTRODUCTION
By letter dated June 10, 1991, as supplemented on October li, 1991, Commonwealth Edison Company, (CECO, the licensee) proposed to incirporate programmatic controls for radiological effluents and radiological environmental monitoring in the Administrative Controls section of the Technical Specifications (TS) consistent with the requirements of 10 CFR 20.106, 40 CFR Part 190, 10 CFR 50.36a, and Appendix 1 to 10 CFR Part 50. At the same time, the licensee proposed to transfer the procedural details of the Radiological Effluent Technical Specifications (RETS) from the TS to the Offsite Dose Calculation Manual (0DCM) or to the Process Control Program (PCP) for solid radioactive wastes as appropriate.
With these changes, the l
specifications related to RETS reporting requirements were simplified.
l Finally, changes to the definitions of the 00CM and PCP were proposed consistent with these changes.
Guidance on these proposed changes was provided to all power reactor licensees and applicants by Generic Letter (GL) 89-01 dated January 31, 1989. The October 17, 1991, submittal provided clarifying information that did not change the initial proposed no significant hazards consideration.
2.0 EVALUATION The licensee's proposed changes to the TS are in accordance with the guidance provided in GL 89-01 and are addressed below.
(1)
The licer.see has proposed to incorporate programmatic controls for radioactive effluents and radiological environmental monitoring in TS 6.8.4 " Procedures and Programs," of the TS as noted in the guidance provided in GL 89-01.
The programmatic controls ensure that programs 9204240253 920413 DR ADOCK 0500 4
e-are established, implemented, and maintained to ensure that operating procedures are provided to control radioactive effluents consistent with the requirements of 10 CFR 20.106, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50.
(2)
The licensee has confirmed that the detailed procedural requirements addressing Limiting Conditions for Operation, their applicability, remedial actions, associated surveillance requirements, or reporting requirements for the following specifications have been prepared to implement the relocation of these procedural details to the ODCM or PCP.
Tnese changes to the 00CM and PCF have been prepared in accordance with the new Administrative Controls in the TS on changes to the ODCM and PCP so that they will be implemented in the ODCM or PCP when this amendment is issued.
SPECIFICATION TITLE 3/4.3.3.9 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 3/4 3.3.10 RADI0 ACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION 3/4.11.1.1 RADI0 ACTIVE EFFLUENTS:
LIQUID EFFLUENTS CONCENTRATION 3/4.11.1.2 RADI0 ACTIVE EFFLUENTS:
LIQUID EFFLUENTS DOSE 3/4.11.1.3 RADI0 ACTIVE EFFLUENTS:
LIQUID RADWASTE TREATMENT SYSTEM 3/4.11.2.1 RADI0 ACTIVE ErFLUENTS:
GASE0US EFFLUENTS DOSE RATE 3/4 11.2.2 RADI0 ACTIVE EFFLUENTS:
DOSE - N0BLE GASES 3/4.11.2.3 RADI0 ACTIVE EFFLUENTS: DOSE - 10 DINE-131, 10 DINE-133, TRITIUM, AND RADI0 ACTIVE MATERIAL IN PARTICULATE FORM 3/4.11.2.4 RADI0 ACTIVE EFFLUENTS: GASE0US RADWASTE TREATMENT SYSTEM 3/4.11.3 RADI0 ACTIVE EFFLUENTS:
SOLID RADI0 ACTIVE WASTES 3/4.11.4 R.4DI0 ACTIVE EFFLUENTS: TOTAL DOSE 3/4.12.1 RADI0 ACTIVE ENVIRONMENTAL MONITORING:
MONITORING PROGRAM 3/4.12.2 RADIOACTIVE ENVIRONMENTAL' MONITORING:
LAND USE CENSUS 3/4.12.3 RADI0 ACTIVE ENVIRONMENTAL MONITORING:
INTERLABORATORY COMPARISON PROGRAM 6.9.1.6 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT l
1
3 G 6.9.1.7 SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 6.15 MAJOR CHANGES TO LIQUID, GASE0US, AND SOLID RADWASTE TREATMENT SYSTEMS These procedural details that have been removed from the TS are not required by the Commission's regulations to be included in TS. They have been prepared for incorporation in the ODCM or PCP upon issuance of this license amendment and may be subsequently changed by the licensee without prior NRC approval.
Changes to the ODCM and PCP are documented and will be retained for the duration of the cperating license in accordance with TS 6.10.20.
(3)
The licensee has proposed replacing the existir, specifications in the Administrative Controls section of the TS for the Annual Radiological Environmental Operating Report, TS 6.9.1.6 for the Semiannual Radioactive Effluent Release Report, TS 6.9.1.7, for the Process Control Program, TS 6.13, and for the Offsite Dose Calculation Manual, TS 6.14, with the updated TSs that were prr" i in GL 89-01.
The following TS that are included under the heading of Radioactive Effluents have been retained in the TS.
This is in accordance with the guidance of GL 89-01.
SPECIFICATION TITLE 3/4.3.3.10 EXPLOSIVE GAS MONITORING INSTRUMENTATION (Retained existing requirements of this specification) 3/4.11.1.4 LIQUID HOLDUP TANKS 3/4.11.2.5 EXPLOSIVE GAS MIXTURE 3/4.11.2.6 GAS STORAGE TANKS Several administrative chances were made to the pages affected by this request.
Besides page numbers changing due to deletions of some of these specifications, the following administration changes were made:
(1)
Sections 3/4.9.6, 3/4.9.7, and 3/4.9.8 in the Braidwood TS index was repeated on pages XVII and XVIII.
These sections were deleted on page XVII to make it consistent with the Byron TS.
(2)
Added definitions 1.9a and 1.19a to index page.
Also changed page numbers for definitions 1.23,1.30 and 1.31 to reflect the text.
(3)
" Motor-0perate Valves Thermal Overload Protection Devices" on top of index page XII for Braidwood was deleted because it was a repeat from page XI.
(4)
On index page XVIII in Byron and Braidwood TS for section 3/4.9.12, the word " System" was deleted to match the title of section 3/4.9.12 in the TS on page 83/4 9-3.
I I
?
_,. (5)
On index o. ge XIX in Byron and Braidwood TS for Table 5.7-1, an "s" was added to Uie words Limit to reflect Table 5.7-1 in the TS on page 5-6.
(6)
Deleted " Table 6.2-la (This figure Not Used)" from Braidwood index page X" and deleted p ge 6-Sa from the TS to match the Byron TS.
(7)
On Byron TS index page Vill Figure 3.4-4b was added and an "a" was added to the titles of Figures 3.4-3a and 3.4-4a.
This was done to reflect the TS text.
(8)
In the Byron and Braidwood TS index for specification 6.9.1., Routine Reports, " Radical Peaking Factor Limit Report" was deleted and
" Operating Limits Report" and " Criticality Analysis of Byron and-Braidwood Station Fuel Storage Racks" were added to reflect TS Sectian 6.9.1.
(9)
Corrected page number on Byron index for specification 3/4.7.9 (10)
Added TS Sections 3/4.7.10 and 3/4 7.11 to Byron TS and the index to ir.a.cate these sections are not being used. This was done to be consistent with the Braidwood TS and to eliminate confusion.
(11) Moved three lines trom Byron TS page 6-18a to 6-18 to make Byron consistent with Braidwood TS.
(12) Moved TABLE 3.4-1 and specification 3/4.4.7 in Byron index from page VIII to page VII. Also added "High Energy Line Break Isolating Sensors" after TABLE 4.3-9 in page VII. This was done to make Byron and
-Braidwood TS consistent.
(13)
Added specification 3.3.3.7 to the Byron TS to indicate specification is not used.
Also added Table 3.3-11 (this table number is not being used) in the Byron and Braidwood index.
This was done to provide consistency between Byron and Braidwood TS and to eliminate possible confusion of a l
missing specification.
(14)
Braidwood TS 6.9.1.9, on page 6-19, the word PHOENIX was capit"Tized to l
make-it consistent with Byron TS.
On the basis of the above, the staff finds that the changes included in the proposed TS amendment request are consistent with the guidance provided in GL t
89-01.
Because the control of radioactive effluents continues to be limited
[
in accordance with operating procedures that must satisfy the regulatory requirements of 13 CFR Part 50, the NRC staff concludes that this change is administrative in nature and there is no impact on plant safety as a consequence. Accordingly, the staff finds the proposed changes acceptable.
e s
67 3.0 SJATr CONSULTATION in accordance with the Commission's regulations, the Illinois State official was notified of the proposed issuarice of the amendment.
The State official had no comments.
4.0 ENVIRONMENTAL CONSIDERATION
These amendments involve changes in recordkeeping, reporting, or administrative procedures and program requirements.
The Commission made proposed determinations that the amendments involve no significant hatards consideration, which were published in the Federal Register (56 FR 37578) on August 7, 1991. Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(10).
Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of these amendments.
5.0 CONCLUSION
On the basis of the considerations discussad above, the staff concludes 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 these amendments will no be inimical to the common
- defense and security or to the health and safety of the public.
Principal Contributors:
W. Wayne Meinke, PRPB/DREP Thomas G. Dunning, OTSB/DOEA Robert M. Pulsifer, PDIII-2/ORPW Dated:
April 13, 1992