L-2013-162, Response to NRC Request for Additional Information Regarding License Amendment Request No. 217 - Administrative Changes to Operating License Conditions and Technical Specifications
| ML13179A351 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 05/30/2013 |
| From: | Kiley M Florida Power & Light Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| L-2013-162 | |
| Download: ML13179A351 (16) | |
Text
May 30,2013 L-2013-162 10 CFR 50.90 FPL.
U. S. Nuclear Regulatory Commission Attn.: Document Control Desk Washington, D.C. 20555-0001 Re: Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 Response to NRC Request for Additional Information Regarding License Amendment Request No. 217 - Administrative Changes to Operating License Conditions and Technical Specifications
References:
(1) M. Kiley (FPL) to U.S. Nuclear Regulatory Commission (L-2012-130), "Administrative License Amendment Request No. 217 Regarding Operating License Conditions and Technical Specifications," Accession No. ML12262A290, September 14, 2012.
(2) M. Kiley (FPL) to U.S. Nuclear Regulatory Commission (L-2013-019), "Supplement to Administrative License Amendment Request No. 217 Regarding Operating License Conditions and Technical Specifications," Accession No. ML13037A387, January 29, 2013.
(3) M. Kiley (FPL) to U.S. Nuclear Regulatory Commission (L-2013-042), "Response to NRC Request for Additional Information Regarding License Amendment Request No. 217 -
Administrative Changes to Operating License Conditions and Technical Specifications,"
Accession No. ML13050A028, February 14, 2013.
(4) F. E. Saba (NRC) to M. Nazar (FPL), "Turkey Point Nuclear Plant, Units Nos. 3 and 4 -
Request for Additional Information Regarding License Request No. 217 and Changes to Operating License Conditions and Technical Specifications (TAC Nos. MF0602 and MF0603)," Accession No. ML13137A460, May 23, 2013.
By letter L-2012-130 dated September 14, 2012 [Reference 1], Florida Power & Light Company (FPL) requested to amend Renewed Facility Operating Licenses DPR-31 and DPR-41 and revise the Turkey Point Units 3 and 4 Technical Specifications (TS). The proposed amendments will (1) close and remove license conditions that have been fully satisfied, (2) revise TS 5.5.1 to remove related license conditions, (3) correct several inadvertent errors identified in the TS, and (4) update the reference to the Physical Security Plan (PSP) to the latest approved revision in the related license conditions. The license conditions that had been fully satisfied included 3.H on AST Modifications, 3.1 on Control Room Habitability, and 3.J on EPU Modifications for DPR-31 and license conditions 3.H on the Boraflex Remedy, 3.1.1 & 3.1.3 on AST Modifications, 3.J on Control Room Habitability, and 3.K on EPU Modifications for DPR-41.
By letter L-2013-019 dated January 29, 2013 [Reference 2], FPL submitted a supplement to License Amendment Request (LAR) No. 217 to (1) add 3.1.2 on AST Modifications for DPR-41 to the list of requested license conditions to be deleted, (2) add Control Room Envelope (CRE) to the Limiting Condition for Operation (LCO) listed system components, and (3) update the TS Index, delete TS pages that were no longer applicable and repaginate affected section pages.
Florida Power & Light Company 9760 SW 344 St., Florida City, FL 33035
Turkey Point Units 3 and 4 L-2013-162 Docket Nos. 50-250 and 50-251 Page 2 of 2 By letter L-2013-042 dated February 14, 2013 [Reference 3], FPL submitted its response to the U.S. Nuclear Regulatory Commission's (NRC) Request for Additional Information (RAI) dated January 24, 2013 regarding the results of unfiltered air inleakage (tracer gas) and pressurization testing of the Turkey Point Control Room Envelope (CRE) that was completed in July 2012.
By letter from the NRC Project Manager (PM) dated May 23, 2013 [Reference 4], the NRC staff requested additional information regarding FPL's request to implement proposed administrative changes to PTN's Operating Licenses and TS under LAR No. 217. The RAIs consisted often questions regarding several identified discrepancies in the proposed changes to the TS Index and to the repaginated TS pages. The RAI questions and applicable FPL responses are provided in the Enclosure to this letter.
This submittal does not alter the significant hazards consideration or environmental assessment previously submitted by FPL letter L-2012-130 [Reference 1].
This submittal contains no new commitments and no revisions to existing commitments.
In accordance with 10 CFR 50.91(b)(1), a copy of this letter is being forwarded to the State Designee of Florida.
Should you have any questions regarding this submittal, please contact Mr. Robert J. Tomonto, Licensing Manager, at (305) 246-7327.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on May 30, 2013.
Very truly yours, Michael Kiley Site Vice President Turkey Point Nuclear Plant Enclosure cc: USNRC Regional Administrator, Region II USNRC Project Manager, Turkey Point Nuclear Plant USNRC Senior Resident Inspector, Turkey Point Nuclear Plant Ms. Cindy Becker, Florida Department of Health
~~4 Turkey Point Units 3 and 4 L-2013-162 Docket Nos. 50-250 and 50-251 Enclosure Page 1 of 9 Turkey Point Units 3 and 4 Response to NRC Request for Additional Information Regarding License Amendment Request No. 217 - Administrative Changes to Operating License Conditions and Technical Specifications ENCLOSURE
Turkey Point Units 3 and 4 L-2013-162 Docket Nos. 50-250 and 50-251 Enclosure Page 2 of 9 Response to Request for Additional Information The following information is provided by Florida Power & Light Company (FPL) in response to the U. S. Nuclear Regulatory Commission's (NRC) Request for Additional Information (RAI). This information was requested to support License Amendment Request (LAR) No. 217 on Administrative Changes to Operating License Conditions and Technical Specifications, for Turkey Point Nuclear Plant (PTN) Units 3 and 4 that was submitted to the NRC by FPL letter L-2012-130 on September 14, 2012
[Reference 1] and supplemented by FPL letter L-2013-019 on January 29, 2013 [Reference 2].
In a letter dated May 23, 2013 [Reference 3], the NRC staff requested additional information regarding FPL's request to implement proposed administrative changes to PTN's Operating Licenses and Technical Specification (TS) under LAR No. 217. The RAls consisted of ten questions involving discrepancies identified during the NRC's review of proposed changes to the TS Index and to some of the repaginated TS pages. The RAI questions and applicable FPL responses are documented below.
Background
By letter dated September 14, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12262A290), as supplemented by letter dated January 29, 2013 (ADAMS Accession No. ML13037A387), Florida Power & Light Company (FPL, the licensee) requested an amendment to the Turkey Point Nuclear Plant, Units 3 and 4, Renewed Facility Operating Licenses. The January 29, 2013 supplement replaced the September 14, 2012, request in its entirety. The licensee proposed changes to license conditions and revisions to Technical Specifications for Turkey Point Nuclear Plant, Units 3 and 4. The U.S. Nuclear Regulatory Commission (NRC) staff reviewed the information provided by the licensee in its January 29, 2013, letter and determined that additional information is needed to complete the review.
Request for Additional Information #1 TS pages 3/4 2-6a, 3/4 2-9a, 3/4 2-10a, 3/4 2-12a, and 3/4 3-40a are not on the pagination list in the application and are not shown as deleted in Attachment 1. Discuss the differences between pages 3/4 2-6 and 3/4 2-6a, 3/42-9 and 3/4 2-9a, 3/42-10 and 3/4 2-10a, 3/42-12 and 3/4 2-12a, and 3/4 3-40 and 3/43-40a. Explain if a page is proposed to be deleted. Include which page is the appropriate page to delete between the two pages, and provide the basis for the deletion.
There are no current or proposed TS pages 3/4 2-6a, 3/4 2-9a, 3/4 2-10a, 3/4 2-12a, or 3/4 3-40a in either the current TS or this proposed license amendment request (LAR 217).
Request for Additional Information #2 Current TS page 3/4 9-14 is stated to become new page number 3/4 9-13 in the application enclosure; however, Attachment 2 shows the page as 3/4 9-12. Which page number will TS page 3/4 9-14 become: 3/4 9-13 or 3/4 9-12? Also provide any further corrections to the page numbers for the TS pages that follow current TS page 3/4 9-14 if needed (i.e., current page 3/4 9-15 and 3/4 9-16).
The current TS page 3/4 9-13 is proposed to be deleted. Therefore, TS page 3/4 9-14 should become 3/4 9-12 and the pagination table in Section 4.1.20 should be corrected. Attachment 2 for this entry is correct as shown. In addition, TS page 3/4 9-15 should become 3/4 9-13 and the pagination table in Section 4.1.20 and Attachment 2 should be corrected. See revised Section 4.1.20 and Attachment 2.
Turkey Point Units 3 and 4 L-2013-162 Docket Nos. 50-250 and 50-251 Enclosure Page 3 of 9 Request for Additional Information #3 Current TS page 3/4 9-16 is not on the pagination list in the application, and there is no request in this application for changes to or deletion of this page. Explain what FPL is proposing for TS page 3/4 9-16. Include the basis for any changes and any changes to the page number?
There is no current or proposed TS page 3/4 9-16 in either the current TS or this proposed license amendment request (LAR 217).
Request for Additional Information #4 Current TS page 3/4 5-17 contains a requirement that states:
5.6 COMPONENT CYCLIC OR TRANSIENT LIMIT 5.6.1 The components identified in Table 5.6-1 are designed and shall be maintained within the cyclic or transient limits of Table 5.6-1.
However, Attachment 1 does not show any requirement on TS page 3/4 5-17; rather, only that it is being deleted. The application does not discuss the deletion of such a requirement, nor does the index reference TS 5.6 or Table 5.6-1. Is FPL proposing to delete TS 5.6? If so provide a discussion that explains the basis for deletion. If not, reflect current TS 5.6 in this amendment and explain where Table 5.6-1 is located.
The current TS page 5-17 shows that "This Page Intentionally Left Blank." TS 5.6 and Table 5.6-1 were deleted from the TS under Amendments 251 and 247 and the Component Cyclic or Transient Limits were relocated to Table 4.1-10 of the Updated Final Safety Analysis Report (UFSAR).
Request for Additional Information #5 shows the index listing title for Figure 3.4-2 as, "TURKEY POINT UNITS 3&4 REACTOR COOLANT SYSTEM HEATUP LIMITATIONS APPLICABLE UP TO 32 EFPY."
However, Attachment 2 shows the index listing title for Figure 3.4-2 as, "TURKEY POINT, UNITS 3&4 REACTOR COOLANT SYSTEM HEATUP LIMITATIONS (Heatup Rates of 60 and 100 0 f/hr) APPLICABLE FOR 48 EFPY (Without margins for instrumentation errors)."
This is different from the current approved TS and the application does not discuss the requested change. Provide a discussion that explains this proposed change or return the title to what is currently approved.
TS Index listing (page viii) for Figure 3.4-2 shown in Attachment 1 should be revised to read:
"Turkey Point Units 3 and 4 Reactor Coolant System Heatup Limitations (Heatup Rates of 60 and 100°F/hr) Applicable for 48 EFPY (Without Margins for Instrumentation Errors)." This is consistent with the current TS Figure 3.4-2. The proposed change to the title of Figure 3.4-2 on page viii of the index listing should have been noted in Section 4.1.18 on miscellaneous index changes. Attachment 2 is correct as shown. See revised Section 4.1.18 and Attachment 1.
Request for Additional Information #6 shows the index listing title for Figure 3.4.3 as, "TURKEY POINT UNITS 3&4 REACTOR COOLANT SYSTEM COOLDOWN LIMITATIONS (100°F/hr) APPLICABLE UP TO 32 EFPY." However, Attachment 2 shows the index listing title for Figure 3.4-3 as, "TURKEY POINT, UNITS 3&4 REACTOR COOLANT SYSTEM COOLDOWN LIMITATIONS (Cooldown Rates of 0, 20, 40,60 and 1001F/hr) APPLICABLE FOR 48
Turkey Point Units 3 and 4 L-2013-162 Docket Nos. 50-250 and 50-251 Enclosure Page 4 of 9 EFPY (Without margins for instrumentation errors)." This is different from the current approved TS and the application does not discuss the requested change. Provide a discussion that explains this proposed change or return the title to what is currently approved.
TS Index listing (page viii) for Figure 3.4-3 shown in Attachment 1 should be revised to read:
"Turkey Point Units 3 and 4 Reactor Coolant System Cooldown Limitations (Cooldown Rates of 0, 20, 40, 60 and I00°F/hr) Applicable for 48 EFPY (Without Margins for Instrumentation Errors)."
This is consistent with the current TS Figure 3.4-3. The proposed change to the title of Figure 3.4-3 on page viii of the index listing should have been noted in Section 4.1.18 on miscellaneous index changes. Attachment 2 is correct as shown. See revised Section 4.1.18 and Attachment 1.
Request for Additional Information #7 shows the index listing title for Table 3.7-1 as, "MAXIMUM ALLOWABLE POWER RANGE NEUTRON FLUX LEVEL HIGH SETPOINT WITH INOPERABLE STEAM LINE SAFETY VALVES DURING THREE LOOP OPERATION," with "RANGE NEUTRON FLUX" being deleted and replaced by "LEVEL." However, the title of Table 3.7-1 in the TS is, "MAXIMUM ALLOWABLE POWER LEVEL WITH INOPERABLE STEAM LINE SAFETY VALVES DURING THREE LOOP OPERATION," which does not include "HIGH SETPOINT" and the application does not discuss this requested change.
Provide a discussion that explains this proposed change and correct the title so that it matches the title in the Table 3.7-1.
TS Index listing (page x) for Table 3.7-1 shown in Attachment 1 should be revised to read:
"MAXIMUM ALLOWABLE POWER LEVEL WITH INOPERABLE STEAM LINE SAFETY VALVES DURING THREE LOOP OPERATION." This is consistent with the current TS Table 3.7-1. The proposed change to the title of Table 3.7-1 on page x of the index listing should be noted in Section 4.1.18 on miscellaneous index changes. Attachment 2 is correct as shown. See revised Section 4.1.18 and Attachment 1.
Request for Additional Information #8 shows the index listing title as "Standby Steam G.ncrato Feedwater System,"
with "Steam Generator" being deleted. However, the application does not discuss this proposed change. Provide a discussion that explains this proposed change.
The title of current TS 3.7.1.6 on page 3/4 7-11 is "Standby Feedwater System." The proposed change to page x of the index listing should be included in Section 4.1.18 on miscellaneous index changes. Attachments 1 and 2 are correct as shown. See revised Section 4.1.18.
Request for Additional Information #9 shows the index listing title as "Feedwater Line Isolation Valves," with "Line" being deleted. However, the title in the TS is, "Feedwater Isolation," which does not include "Valves" and the application does not discuss this proposed change. Provide a discussion that explains this proposed change and correct the title so that it matches the title in TS.
The title of current TS 3.7.1.7 on page 3/4 7-1 lb is "Feedwater Isolation." The proposed change to page x of the index listing should be included in Section 4.1.18 on miscellaneous index changes.
Attachments 1 and 2 are correct as shown. See revised Section 4.1.18.
Turkey Point Units 3 and 4 L-2013-162 Docket Nos, 50-250 and 50-251 Enclosure Page 5 of 9 Request for Additional Information #10 In the application FPL stated, "The text on 5-4 moved to 5-1, on 6-12 moved to 6-5, on 6-23 moved to 6-22a, and on 6-25 moved to 6-24." However, Attachment 1 shows other TS pages where the text is proposed to be relocated; the page is being deleted, and the pages are not reflected in the application. Provide a discussion that reflects every deleted page that has relocated text. Include the page number, what text is on the page, and the text's relocated position.
All pages that are proposed to be deleted are correctly listed in Section 4.1.19 on miscellaneous page deletions. There were five additional instances in which text is proposed to be moved from one page to another to facilitate the deletion of otherwise blank pages and should be included in Section 4.1.19. There are a total of nine such instances: The text "3/4.4.10 DELETED" on page 3/4 4-38 is moved to page 3/4 4-37; the text "3/4.6.3 Not Used" on page 3/4 6-16 is moved to page 3/4 6-15; the text "3/4.9.7 DELETED" on page 3/4 9-7 is moved to page 3/4 9-6; the text "3/4.9.12 DELETED" on page 3/4 9-13 is moved to page 3/4 9-12; the text "3/4.10.4 (This specification number is not used)" on page 3/4 10-4 is moved to page 3/4 10-3; the text on Sections 5.3 and 5.4 on page 5-4 is moved to page 5-1; the text "6.6 DELETED and 6.7 DELETED" on page 6-12 is moved to page 6-5; the text "6.10 DELETED" on page 6-23 is moved to page 6-22a; and the text on high radiation areas under 6.12.2 and "6.13 DELETED" on page 6-25 is moved to page 6-24.
See revised Section 4.1.19.
References
- 1. M. Kiley (FPL) to U.S. Nuclear Regulatory Commission (L-2012-130), "Administrative License Amendment Request No. 217 Regarding Operating License Conditions and Technical Specifications," Accession No. ML12262A290, September 14, 2012.
- 2. M. Kiley (FPL) to U.S. Nuclear Regulatory Commission (L-2013-019), "Supplement to Administrative License Amendment Request No. 217 Regarding Operating License Conditions and Technical Specifications," Accession No. ML13037A387, January 29, 2013.
- 3. F. E. Saba (NRC) to M. Nazar (FPL), "Turkey Point Nuclear Plant, Units Nos. 3 and 4 -
Request for Additional Information Regarding License Request No. 217 and Changes to Operating License Conditions and Technical Specifications (TAC Nos. MF0602 and MF0603),"
Accession No. ML13137A460, May 23, 2013.
a Turkey Point Units 3 and 4 L-2013-162 Docket Nos. 50-250 and 50-251 Enclosure Page 6 of 9 4.1.18 Technical Specification Miscellaneous Index Changes (Revised)
In addition to 4.1.1 through 4.1.8 above, the following index changes apply:
Page iii - Delete "FIGURE 2.1.1 DELETED.....2-2" Page iv - Delete "FIGURE 3.1-1 DELETED.....3/4 1-3" Page v - Delete "FIGURE 3.2-1 DELETED..... 3/4 2-3" Page vi - Delete "Fire Detection Instrumentation ..... (DELETED)"
Page vi - Delete "Radioactive Liquid Effluent Monitoring Instrumentation (DELETED)"
Page vi - Delete "TABLE 3.3-7 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION ........................ (DELETED)"
Page vi - Delete "TABLE 4.3-5 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS ... (DELETED)"
Page viii - Revise FIGURE 3.4-2 title to read; TURKEY POINT UNITS 3 AND 4 REACTOR COOLANT SYSTEM HEATUP LIMITATIONS (Heatup Rates of 60 and 100'F/hr)
APPLICABLE FOR 48 EFPY (Without Margins for Instrumentation Errors)
Page viii - Revise FIGURE 3.4-3 title to read; TURKEY POINT UNITS 3 AND 4 REACTOR COOLANT SYSTEM COOLDOWN LIMITATIONS (Cooldown Rates of 0, 20, 40, 60 and 100°F/hr)
APPLICABLE FOR 48 EFPY (Without Margins for Instrumentation Errors)
Page viii - Revise "3/4.4.10 DELETED" to drop page 3/4 6-16 reference Page ix - Revise "3/4.6.3 Not Used" to DELETED and drop page 3/4 6-19 reference Page x - Revise TABLE 3.7-1 title to read:
MAXIMUM ALLOWABLE POWER LEVEL WITH INOPERABLE STEAM LINE SAFETY VALVES DURING THREE LOOP OPERATION Page x - Revise "Standby Steam Generator Feedwater System" to read:
Standby Feedwater System Page x - Revise "Feedwater Line Isolation Valves" to read:
Feedwater Isolation Page xi - Delete "TABLE 4.8-1 NOT USED ..... 3/4 8-10" Page xii - Revise "3/4.9.7 DELETED" to drop page 3/4 9-7 reference Page xiii - Revise "3/4.9.12 DELETED" to drop page 3/4 9-13 reference Page xiii - Revise "3/4.10.4 (This specification number is not used)"
to drop page 3/4 10-4 reference Page xv - Revise 6.4 and 6.5 to drop page 6-5 reference Page xvi - Revise 6.6 and 6.7 to drop page 6-12 reference Page xvi - Revise 6.10 to drop page 6-23 reference Page xvii - Revise 6.11 to drop page 6-24 reference Page xvii - Revise 6.13 to drop page 6-25 reference
Turkey Point Units 3 and 4 L-2013-162 Docket Nos. 50-250 and 50-251 Enclosure Page 7 of 9 4.1.19 Technical Specification Miscellaneous Page Deletions (Revised)
The following TS pages marked Deleted, Not Used, or Left Intentionally Blank are to be deleted: 2-2, 3/4 1-3, 3/4 1-16, 3/4 1-27, 3/4 2-3, 3/4 2-5, 3/4 4-12, 3/4 4-13, 3/4 4-14, 3/4 4-15, 3/4 4-16, 3/4 4-17, 3/4 4-27, 3/4 4-29, 3/4 4-33, 3/4 4-34, 3/4 4-38, 3/4 6-3, 3/4 6-16, 3/4 6-19, 3/4 6-20, 3/4 6-21, 3/4 8-10, 3/4 9-7, 3/4 9-13, 3/4 10-4, 5-2, 5-3, 5-4, 5-8, 5-9, 5-11, 5-12, 5-17, 6-3, 6-6, 6-7, 6-8, 6-9, 6-10, 6-11, 6-12, 6-23, 6-25, and 6-27.
The text "3/4.4.10 DELETED" on page 3/4 4-38 is moved to page 3/4 4-37; the text "3/4.6.3 Not Used" on page 3/4 6-16 is moved to page 3/4 6-15; the text "3/4.9.7 DELETED" on page 3/4 9-7 is moved to page 3/4 9-6; the text "3/4.9.12 DELETED" on page 3/4 9-13 is moved to page 3/4 9-12; the text "3/4.10.4 (This specification number is not used)" on page 3/4 10-4 is moved to page 3/4 10-3; the text on Sections 5.3 and 5.4 on page 5-4 is moved to page 5-1; the text "6.6 DELETED and 6.7 DELETED" on page 6-12 is moved to page 6-5; the text "6.10 DELETED" on page 6-23 is moved to page 6-22a; and the text on high radiation areas under 6.12.2 and "6.13 DELETED" on page 6-25 is moved to page 6-24.
Turkey Point Units 3 and 4 L-2013-162 Docket Nos. 50-250 and 50-251 Enclosure Page 8 of 9 4.1.20 Technical Specification Pagination Changes (Revised)
Old Page # New Page # Old Page # New Page # Old Page # New Page#
2-3 2-2 3/4 2-9 3/4 2-7 3/4 3-49 3/4 3-53 2-4 2-3 3/42-10 3/42-8 3/4 4-1Oa 3/44-11 2-5 2-4 3/42-11 3/42-9 3/44-11 3/44-12 2-6 2-5 3/42-12 3/42-10 3/44-18 3/44-13 2-7 2-6 3/42-13 3/42-11 3/44-19 3/44-14 2-8 2-7 3/42-14 3/42-12 3/44-20 3/44-15 2-9 2-8 3/42-15 3/42-13 3/44-21 3/44-16 2-10 2-9 3/42-16 3/42-14 3/44-22 3/44-17 3/4 1-4 3/4 1-3 3/4 3-31a 3/43-32 3/44-23 3/44-18 3/4 1-5 3/4 1-4 3/4 3-32 3/4 3-33 3/4 4-24 3/4 4-19 3/4 1-6 3/4 1-5 3/4 3-32a 3/4 3-34 3/4 4-25 3/4 4-20 3/4 1-7 3/4 1-6 3/4 3-33 3/4 3-35 3/4 4-26 3/4 4-21 3/4 1-8 3/4 1-7 3/4 3-33a 3/4 3-36 3/4 4-28 3/4 4-22 3/4 1-9 3/4 1-8 3/4 3-34 3/4 3-37 3/4 4-30 3/4 4-23 3/4 1-10 3/4 1-9 3/4 3-34a 3/4 3-38 3/4 4-31 3/4 4-24 3/4 1-11 3/4 1-10 3/4 3-35 3/4 3-39 3/4 4-32 3/4 4-25 3/4 1-12 3/4 1-11 3/43-36 3/43-40 3/44-35 3/44-26 3/4 1-13 3/4 1-12 3/43-37 3/43-41 3/44-36 3/44-27 3/4 1-14 3/4 1-13 3/4 3-38 3/4 3-42 3/4 4-37 3/4 4-28 3/4 1-14a 3/41-14 3/43-39 3/43-43 3/44-39 3/44-29 3/41-17 3/41-16 3/43-40 3/43-44 3/46-4 3/46-3 3/4 1-18 3/4 1-17 3/43-41 3/43-45 3/46-5 3/46-4 3/4 1-19 3/4 1-18 3/43-42 3/43-46 3/46-6 3/46-5 3/41-20 3/41-19 3/43-43 3/43-47 3/46-7 3/46-6 3/4 1-20a 3/4 1-20 3/4 3-44 3/4 3-48 3/4 6-8 3/4 6-7 3/4 2-4 3/4 2-3 3/4 3-45 3/4 3-49 3/4 6-9 3/4 6-8 3/4 2-6 3/4 2-4 3/4 3-46 3/4 3-50 3/4 6-10 3/4 6-9 3/42-7 3/42-5 3/43-47 3/43-51 3/4 6-1Oa 3/46-10 3/42-8 3/42-6 3/43-48 3/43-52 3/46-17 3/46-16
Turkey Point Units 3 and 4 L-2013-162 Docket Nos. 50-250 and 50-251 Enclosure Page 9 of 9 Old Page # New Page# Old Page # New Page# Old Page # New Page#
3/46-18 3/46-17 3/4 8-4a 3/48-5 5-16 5-9 3/4 7-1 la 3/47-12 3/48-5 3/48-6 6-4 6-3 3/4 7-11b 3/47-13 3/48-6 3/48-7 6-5 6-4 3/47-12 3/47-14 3/48-7 3/48-8 6-13 6-5 3/47-13 3/47-15 3/48-8 3/48-9 6-14 6-6 3/47-14 3/47-16 3/48-9 3/48-10 6-15 6-7 3/47-15 3/47-17 3/49-8 3/49-7 6-16 6-8 3/47-16 3/47-18 3/49-9 3/49-8 6-17 6-9 3/4 7-16a 3/47-19 3/49-10 3/49-9 6-18 6-10 3/4 7-16b 3/47-20 3/49-11 3/49-10 6-18a 6-11 3/47-17 3/47-21 3/49-12 3/49-11 6-18b 6-12 3/47-18 3/47-22 3/49-14 3/49-12 6-18c 6-13 3/4 7-18a 3/47-23 3/49-15 3/49-13 6-19 6-14 3/4 7-18b 3/4 7-24 3/4 10-5 3/4 10-4 6-20 6-15 3/4 7-19 3/4 7-25 5-5 5-2 6-21 6-16 3/4 7-20 3/4 7-26 5-6 5-3 6-21a 6-17 3/4 7-21 3/4 7-27 5-7 5-4 6-22 6-18 3/4 7-22 3/4 7-28 5-10 5-5 6-22a 6-19 3/4 7-23 3/4 7-29 5-13 5-6 6-24 6-20 3/4 7-24 3/4 7-30 5-14 5-7 6-26 6-21 3/47-25 3/47-31 5-15 5-8
k' Turkey Point Nuclear Plant L-2013-162 License Amendment Request No. 217 Attachment 1 Turkey Point Units 3 and 4 Response to NRC Request for Additional Information Regarding License Amendment Request No. 217 - Administrative Changes to Operating License Conditions and Technical Specifications ATTACHMENT 1 Corrected TS Index Markups This coversheet plus 2 pages.
(Heatup rates of 60 and 100°F/hr)
-APPLICABLE for 48 EFPY
/I(Without Margins for Instrumentation Errors)
LIMITING CONDITlION S FOR OPERATION AND SURVEILLANCE REQUIREMENTS LIMITIN PONS F R PERATI N AND SURVEILLANCE RE UIRE ENTS
]
I(Cooldown Rates of 0, 20, 40, 60 and 100°F/hr)
SECTION I--APPLICABLE for 48 EFPY PAGE
/ F(Without Margins for Instrumentation Errors) 3/4.4.9 rKV,'jlUKl/ I IMl-tA I UKI LIMI I Z5 p Lc tor C oolant System ................................................................................. 3/4 4-30 FIGURE 3.4-2 RKEY POINT UNITS 3&4
~~ACTOR COOLANT SYSTEM HEATUP LIMITATIONS
- i11it 3.I J- i.L r -t- 3/4 4-31
°*U~ ..... . .. .. ......................................................................
FIGURE 3.4.3 RKEY POINT UNITS 3&4
,REACTOR COOLANT SYSTEM COOLDOWN LIMITATIONS OQýF4*F
.1~I,~.fA~ _. III rIx PIP11 - .................................................................... 3/4 4-32 TAR' S,4 WIT H DRAA-'...W L ,,- UL- .......................................................................... 2144 Pressurizer ................................................................................................... 3/4 4-35 Overpressure Mitigating Systems ................................................................... 3/4 4-36 3/4.4.10 DELETED ................................................................................................... 3/14 4 38 3/4.4.11 REACTOR COOLANT SYSTEM VENTS ....................................................... 3/4 4-39 3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 AC C UMULATO R S ......................................................................................... 3/4 5-1 3/4/5.2 ECCS SUBSYSTEMS - TaVg GREATER THAN OR EQUAL TO 350°F .......... 3/4 5-3 FIGURE 3.5-1 RHR P UMP CURV E ....................................................................................... 3/4 5-6 3/4.5.3 ECCS SUBSYSTEMS - Tavg LESS THAN 350°F ........................................... 3/4 5-9 3/4.5.4 REFUELING WATER STORAGE TANK ........................................................ 3/4 5-10 TURKEY POINT - UNITS 3 & 4 viii AMENDMENT NOS. 242 AND 238
., 4' INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE ,-[ILEVE j S afety Valves ............................... ..... .............................................. 3/4 7-1 TABLE 3.7-1 MAXIMUM ALLOWABLE POWER RANGE NEUTRON FLUX HIGH
,E--T-PNT-WITH INOPERABLE STEAM LINE SAFETY VALVES DURING THREE LOOP OPERATION .......................................................................... 3/4 7-2 TABLE 3.7-2 STEAM LINE SAFETY VALVES PER LOOP ................................................. 3/4 7-2 A uxiliary Feedw ater System ........................................................................... 3/4 7-3 TABLE 3.7-3 AUXILIARY FEEDWATER SYSTEM OPERABILITY ..................................... 3/4 7-5 C ondensate Storage Tank .............................................................................. 3/4 7-6 S pe cific A ctiv ity ............................................................................................... 3/4 7-8 TABLE 4.7-1 SECONDARY COOLANT SYSTEM SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PROGRAM .......................................................................... 3/4 7-9 Main Steam Line Isolation Valves .................................................................. 3/4 7-10 Standby Stcem Genctcr Feedwater System ............................................... 3/4 7-11 Feedwater L4e Isolation Vale ..................................................................... 3/4 7-11b 3/4.7.2 COMPONENT COOLING WATER SYSTEM ................................................. 3/4 7-12 3/4.7.3 INTAKE COOLING WATER SYSTEM ........................................................... 3/4 7-14 3/4.7.4 ULTIMATE HEAT SINK .................................................................................. 3/4 7-15 3/4.7.5 CONTROL ROOM EMERGENCY VENTILATION SYSTEM ......................... 3/4 7-16 3/4 .7 .6 S N UB B E R S ................................................................................................... 3/4 7-18 TABLE 4.7-2 SNUBBER VISUAL INSPECTION INTERVAL ............................................... 3/4 7-18a 3/4.7.7 SEALED SOURCE CONTAMINATION .......................................................... 3/4 7-22 3/4.7.8 EXPLOSIVE GAS MIXTURE .......................................................................... 3/4 7-24 3/4.7.9 GAS DECAY TANKS ...................................................................................... 3/4 7-25 TURKEY POINT - UNITS 3 & 4 X AMENDMENT NOS. 249 AND 245
Turkey Point Nuclear Plant L-2013-162 License Amendment Request No. 217 Attachment 2 Turkey Point Units 3 and 4 Response to NRC Request for Additional Information Regarding License Amendment Request No. 217 - Administrative Changes to Operating License Conditions and Technical Specifications ATTACHMENT 2 Corrected Clean Copy of Selected TS Changes This coversheet plus 1 page
.' U N REFUELING OPERATIONS 3/4.9.14 SPENT FUEL STORAGE LIMITING CONDITION FOR OPERATION 3.9.14 The following conditions shall apply to spent fuel storage:
- a. The minimum boron concentration in the Spent Fuel Pit shall be 2300 ppm.
- b. The combination of initial enrichment, bumup, and cooling time of each fuel assembly stored in the Spent Fuel Pit shall be in accordance with Specification 5.5.1.
APPLICABILITY: At all times when fuel is stored in the Spent Fuel Pit.
ACTION:
- a. With boron concentration in the Spent Fuel Pit less than 2300 ppm, suspend movement of spent I fuel in the Spent Fuel Pit and initiate action to restore boron concentration to 2300 ppm or greater.
- b. With condition b not satisfied, suspend movement of additional fuel assemblies into the Spent Fuel Pit and restore the spent fuel storage configuration to within the specified conditions.
- c. The provisions of Specification 3.0.3 are not applicable.
SURVEI LLANCE REQUIREMENTS 4.9.14.1 The boron concentration of the Spent Fuel Pit shall be verified to be 2300 ppm or greater at least once per month.
4.9.14.2 A representative sample of inservice Metamic inserts shall be visually inspected in accordance with the Metamic Surveillance Program described in UFSAR Section 16.2. The surveillance program ensures that the performance requirements of Metamic are met over the surveillance interval.
TURKEY POINT - UNITS 3 & 4 3/4 9-13 AMENDMENT NOS. AND