ML17130A935
| ML17130A935 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 06/27/2017 |
| From: | Mahesh Chawla Plant Licensing Branch III |
| To: | Coffey R Point Beach |
| Chawla M L/LPL3/415-8371 | |
| References | |
| CAC MF7352, CAC MF7353 | |
| Download: ML17130A935 (7) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr Robert Coffey Site Vice President NextEra Energy Point Beach, LLC 6610 Nuclear Road Two Rivers, WI 54241 June 27, 2017
SUBJECT:
POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 - CORRECTION LETTER FOR AMENDMENT NOS. 258 AND 262 RE: REMOVAL OF COMPLETED LICENSE CONDITIONS AND CHANGES TO THE VENTILATION FILTER TESTING PROGRAM (CAC NOS. MF7352 AND MF7353)
Dear Mr. Coffey:
On February 22, 2017 (Agencywide Documents Access and Management System Accession (ADAMS) Accession No. ML17039A300), the U.S. Nuclear Regulatory Commission (NRG) issued Amendment Nos. 258 and 262 to Renewed Facility Operating License Nos. DPR-24 and DPR-27 for the Point Beach Nuclear Plant (PNBP), Units 1 and 2, respectively. This amendment consisted of changes to the technical specifications (TSs) in response to your application dated February 12, 2016, supplemented by letters dated July 11, 2016, and November 4, 2016. The amendments removed license conditions that have been completed and are no longer in effect and revised a charcoal testing criterion for the control room emergency filtration system Following issuance of the amendments, the licensee informed the NRC staff that while the attached pages of the Renewed Facility Operating Licenses were correct, there were errors in the description of the changes on page 2 of Enclosure 1 and page 2 of Enclosure 2.
Specifically:
1 The amendment deleted Section 4.E, "Safety Injection Logic," of Renewed Facility Operating Licenses OPR-24 and DPR-27. However, the description of the change on page 2 of Enclosure 1 and page 2 of Enclosure 2 inadvertently left the title.
The previous text read:
E.
Safety Injection Logic Deleted The revised text reads:
E.
Deleted
- 2. The description of the changes in Item 3 on page 2 of Enclosure 2 inadvertently identified the deletion of the Additional Condition associated with Amendment no. 178.
This Additional Condition associated with Amendment no. 178 was deleted by a previous amendment.
The previous text read:
- 3.
The following additional conditions of the Appendix C, "Additional Conditions,"
of the Renewed Facility Operating License No. DPR-27 are deleted:
Amendment Number 178 206 206 The revised text reads:
'Additional Condition Implementation Date Deleted Deleted Deleted.
- 3.
The following additional conditions of the Appendix C, "Additional Conditions,"
of the Renewed Facility Operating License No. DPR-27 are deleted:
Amendment Number 206 206 Additional Condition Implementation Date Deleted Deleted.
In addition, the licensee identified an error in the NRC staff Safety Evaluation. Section 3.4.3 of the NRC Safety Evaluation incorrectly references the American Society for Testing Materials (ASTM) standard ASTM D-3803-1991. The correct version is ASTM D-3803-1989.
The NRC staff determined that these errors were entirely administrative in nature, were inadvertently introduced, and did not affect the associated notice to the public. Enclosed are the following replacement pages for the amendments dated February 22, 2017: Enclosure 1, page 2; Enclosure 2, page 2; and Enclosure 3, page 7. The revised pages contain marginal lines indicating the areas of change.
These corrections do not change any of the conclusions in the safety evaluation associated with the amendments. We regret any inconvenience this may have caused. If you have any questions regarding this matter, I may be reached at 301-415-8371.
Docket Nos. 50-266 and 50-301
Enclosure:
Correction Pages cc: Distribution via LlstServ Sincerely, Mahesh L. Chawla, Project Manager Plant Licensing Branch Ill Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
ML17130A935 OFFICE DORL/LPL3-1 /PM NAME MChawla DATE 05/11/17 OFFICE DORL/LPL3-1 /BC NAME D.Wrona DATE 06/27/17 DORULPL3-1/LA
$Rohrer 05/11/17 DORL/LPL3-1/PM MChawla 06/27/17
Enclosure Correction Pages E.
Deleted I.
Deleted J.
Deleted
- 3.
The following additional conditions of the Appendix C, "Additional Conditions," of the Renewed Facility Operating License No. DPR-24 are deleted:
Amendment Number Additional Condition Implementation Date 201 Deleted 201 Deleted 238 Deleted 238 Deleted 240 Deleted 240 Deleted 240 Deleted 240 Deleted 240 Deleted 240 Deleted 240 Deleted 240 Deleted 241 Deleted 241 Deleted E.
Deleted H.
Deleted I.
Deleted
- 3.
The following additional conditions of the Appendix C, "Additional Conditions," of the Renewed Facility Operating License No. DPR-27 are deleted:
Amendment Number Additional Condition Implementation Date 206 Deleted 206 Deleted 242 Deleted 242 Deleted 244 Deleted 244 Deleted 244 Deleted 244 Deleted 244 Deleted 244 Deleted 244 Deleted 244 Deleted 245 Deleted 245 Deleted 3.4.3 Staff Evaluation Change in methyl iodide penetration test criterion The change in methyl iodide penetration from :s; 1.0 percent to s 2.5 percent is based on the credit taken in the dose consequence analysis for the removal of methyl (organic) iodide as a result of the operation of the control room filter system. As shown in Table 3.2-9 of the NRC staffs AST SE entitled, "Point Beach Nuclear Plant Units 1 and 2 Control Room Parameters," the control room dose consequence analyses credits a removal efficiency of 95 percent for methyl iodide (Ref. 8.10). As shown below, Table 1 from RG 1 52, Revision 3, indicates that in order to credit an elemental and organic removal efficiency of 95 percent the acceptance criterion is a penetration of s 2.5 percent when tested in accordance with ASTM 0-3803-1989.
Activated Carbon Total Bed Depth 2inches 4 inches or greater Table 1 from RG 1.52, Revision 3 Laboratory Tests for Activated Carbon Maximum Assigned Credit for Methyl Iodide Penetration Activated Carbon Acceptance Criterion for Decontamination Efficiencies Representative Sample Elemental iodine 95°/o Penetrations 2.5% when tested in accordance with ASTM 0-3803-Organic iodide 95%
1989 Elemental iodine 99%
Penetration :5 0.5°/o when tested in accordance with ASTM D-3803-Organic iodide 99%
1989 The licensee's proposed change in testing criteria is consistent with the RG 1.52 guidance for the credit assumed in the AST dose consequence analyses.
TS 5.5.10.c currently requires that testing a sample of the carbon adsorber from CREFS filter (F-16) results in a methyl iodide penetration of less than or equal to 1.0 percent.
The NRG staff notes that the TS 5.5.1 O current acceptance criteria, of a methyl iodide penetration of less than or equal to 1.0 percent, is consistent with the acceptance criteria of Table 2, "Laboratory Tests for Activated Carbon," of RG 1.52, Revision 2 (Ref. 8.26), for a 2 inch "Activated Carbon Bed Depth" air filtration system operated outside the containment.
Generic Letter (GL) 99-02, "Laboratory Testing of Nuclear-Grade Activated Charcoal" (Ref. 8.23), and NUREG-1431, Standard Technical Specifications (STS), Westinghouse Plants (Ref.8.22), discuss that the methyl iodide efficiency should be the value that was incorporated in the licensee's accident analysis. These two NRC documents also state that the staff will accept a safety factor greater than or equal to two when ASTM 03803-1989 (Ref 8 21 ), is used with 30 ° C (86 ° F) and 95 percent relative humidity (RH) for charcoal bed filtration trains without humidity control.