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{{#Wiki_filter:P RIDRIT'Y Z UDOCS OFFSITE FACILITY)-REGUGATOi INFORMATION DISTRIBUTIOhl'ÃPfEM (RIDS)ACCESSION NBR:9512140083 DOC.DATE:'95/12/04 NOTARIZED:
{{#Wiki_filter:P RIDRIT'Y               Z FACILITY)
NO DOCKET¹FACIL:50-335 St.Lucie Plant, Unit 1, Florida Power&Light Co.05000335 50-389 St.Lucie Plant, Unit 2, Florida Power&Light Co.05000389 AUTH.NAME AUTHOR AFFILIATION BOHLKE,W.H.
UDOCS OFFSITE
Florida Power&Light Co.RECIP.NAME RECIPIENT AFFILIATION Division of Freedom of Information
                          -REGUGATOi         INFORMATION DISTRIBUTIOhl'ÃPfEM (RIDS)
&Publications Services SIZE: R)-Misc Notice;Reg NOTES:
ACCESSION NBR:9512140083                     DOC.DATE:'95/12/04 NOTARIZED: NO               DOCKET ¹ FACIL:50-335 St. Lucie Plant, Unit 1, Florida Power & Light Co.                           05000335 50-389 St. Lucie Plant, Unit 2, Florida Power & Light Co.                     05000389 AUTH. NAME               AUTHOR AFFILIATION BOHLKE,W.H.               Florida Power & Light Co.
RECIP.NAME             RECIPIENT AFFILIATION Division of Freedom of Information             & Publications Services


==SUBJECT:==
==SUBJECT:==
Comment opposing proposed generic communication,"Boraflex Degradation in SFP Storage Racks." DISTRIBUTION CODE: DS09DiCOPIES RECEIVED:LTR ENCL TITLE: SECY/DSB Dist: Public Comment on Propose Rule R, G p RECIPIENT ID CODE/NAME INTERNAL:>>
Comment         opposing proposed generic communication, "Boraflex                       R, Degradation in         SFP   Storage Racks."
CENTER 0~6&/NR 1'~-18 RES/DRA/DEPY EXTERNAL: NRC PDR COPIES LTTR ENCL RECIPIENT ID CODE/NAME NMSS/IMOB T8F5 RES DIR RES/DST COPIES LTTR ENCL D 0 C u NOTE TO ALL'RIDS" RECIPIENTS:
DISTRIBUTION CODE: DS09D iCOPIES RECEIVED:LTR                       ENCL     SIZE:
PLEASE HELP US TO REDUCE WASTEI CONTACTTHE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT.504-2083)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS I'OR DOCUMENTS YOU DON'T iVEED!'l,'O'.I"AL NUMBER OF COPIES REQUIRED: LTTR 7 ENCL  
TITLE: SECY/DSB         Dist: Public Comment on Propose               Rule   R)-Misc Notice;Reg  G p
NOTES:
RECIPIENT               COPIES              RECIPIENT          COPIES ID CODE/NAME             LTTR ENCL          ID CODE/NAME      LTTR ENCL INTERNAL:>>             CENTER     0                         NMSS/IMOB    T8F5
            ~6&/NR 1'~-18                                   RES  DIR RES/DRA/DEPY                                 RES/DST EXTERNAL: NRC PDR D
0 C
u NOTE TO ALL'RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTEI CONTACTTHE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 504-2083 ) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS I'OR DOCUMENTS YOU DON'T iVEED!
  'l,'O'.I"AL NUMBER OF   COPIES REQUIRED: LTTR               7   ENCL


g/Sc/f~'an W+r.lc~/0 WR., Cc'5 Z'9'z/oI j%W Xl~zZ.Florida Power&Light Company, P.O.Box 14000, Juno Beach, FL 33408-tt420
Sc/f                                                                                       / 0 WR.,             '5   Z'9 g/
~mn,~~~WZ.DEC<<~995 r L-95-325 r Chief, Rules Review and Directives Branch U.S.Nuclear Regulatory Commission Mail Stop T-6D-69 Washington, DC 20555-0001
~'an W+ r.lc~                                                                      'z/oIXl~zZ.j%W                 Cc Florida Power & Light Company, P.O. Box 14000, Juno Beach, FL 33408-tt420
                                                                                              ~mn,~~                     ~WZ.
DEC       <<~995 r                             L-95-325 r
Chief, Rules Review and Directives Branch U. S. Nuclear Regulatory Commission Mail Stop T-6D-69 Washington, DC 20555-0001


==Subject:==
==Subject:==
Proposed Generic Communication; Boraflex Degradation in Spent Fuel Pool Storage Racks 60 FR 56359 R ue t for mmen rr GiI r gl, Af-I A On November 8, 1995, the Nuclear Regulatory Commission (NRC)published for pqbTic comment,"Proposed Generic Communication; Boraflex Degradation in Spent Fuel Pool Storage Racks." These comments are submitted on behalf of Florida Power&Light (FPL), licensed operator of two nuclear power plant units in Dade County, Florida and two unifs in St.Lucie County, Florida.FPL notes that the EPRI studies reported in the draft generic letter were documented in 1993, and further investigations are ongoing.Specifically, EPRI report TR-103300 that states that the access of water to and around Boraflex panels is perhaps the most significant factor influencing the rate of Silica dissolution from Boraflex.In the"Requested Information" section of the draft, the NRC requests licensees to provide a description of the physical condition of the Boraflex, including any deterioration, on the basis of current, as well as, future projected accumulated gamma exposure and possible water ingress to the Boraflex.FPL contends that Blackness Tests and trending of Silica levels in the spent fuel pool (SFP)coolant is sufficient to monitor the performance of Boraflex in the SFPs.It is not necessary, nor is the information available, to project future degradation based on the access of water to and around the Boraflex.The NRC staff recognizes in the draft generic letter that the presence of borated water in pressurized water reactor (PWR)SFPs contribute to the margin on subcriticality.
Proposed Generic Communication; Boraflex                                             rr Degradation in Spent Fuel Pool Storage Racks                                       Gi I r 60 FR 56359 R ue t for       mmen                                                                               gl, Af-I A
However, the staff indicates that licensees will be requested to provide information on maintaining margin in unborated water.We believe that such a request is inconsistent with the stated benefit of borated water, particularly for PWRs.We note that the Westinghouse Owners Group (WOG)has submitted a topical report to the staff in an effort to credit boron in solution for criticality control in PWRs.In light of the WOG effort, we urge the staff to reconsider this information request to account for actual plant conditions.
On November 8, 1995, the Nuclear Regulatory Commission (NRC) published for pqbTic comment, "Proposed Generic Communication; Boraflex Degradation in Spent Fuel Pool Storage Racks." These comments are submitted on behalf of Florida Power & Light (FPL), licensed operator of two nuclear power plant units in Dade County, Florida and two unifs in St. Lucie County, Florida.
FPL notes that the EPRI studies reported in the draft generic letter were documented in 1993, and further investigations are ongoing. Specifically, EPRI report TR-103300 that states that the access of water to and around Boraflex panels is perhaps the most significant factor influencing the rate of Silica dissolution from Boraflex. In the "Requested Information" section of the draft, the NRC requests licensees to provide a description of the physical condition of the Boraflex, including any deterioration, on the basis of current, as well as, future projected accumulated gamma exposure and possible water ingress to the Boraflex. FPL contends that Blackness Tests and trending of Silica levels in the spent fuel pool (SFP) coolant is sufficient to monitor the performance of Boraflex in the SFPs. It is not necessary, nor is the information available, to project future degradation based on the access of water to and around the Boraflex.
The NRC staff recognizes in the draft generic letter that the presence of borated water in pressurized water reactor (PWR) SFPs contribute to the margin on subcriticality. However, the staff indicates that licensees will be requested to provide information on maintaining margin in unborated water. We believe that such a request is inconsistent with the stated benefit of borated water, particularly for PWRs. We note that the Westinghouse Owners Group (WOG) has submitted a topical report to the staff in an effort to credit boron in solution for criticality control in PWRs. In light of the WOG effort, we urge the staff to reconsider this information request to account for actual plant conditions.
We appreciate the opportunity to comment on this proposed generic'letter.
We appreciate the opportunity to comment on this proposed generic'letter.
Very truly yours, W.H.Bohlke I PDR ADQCK 05000335 95i2i40083 95i204 Vice President H PDR.-+Nuclear Engineering and Licensing an FPL Group company t t 4 tt\g'k 1 f}}
Very truly yours, W. H. Bohlke I           95i2i40083 95i204 PDR   ADQCK 05000335 Vice President           H                       PDR.-+
Nuclear Engineering and Licensing an FPL Group company
 
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Revision as of 21:02, 29 October 2019

Comment Opposing Proposed Generic Communication, Boraflex Degradation in SFP Storage Racks.
ML17228B355
Person / Time
Site: Saint Lucie  NextEra Energy icon.png
Issue date: 12/04/1995
From: Bohlke W
FLORIDA POWER & LIGHT CO.
To:
NRC OFFICE OF ADMINISTRATION (ADM)
References
FRN-60FR56359 60FR56359-00002, 60FR56359-2, L-95-325, NUDOCS 9512140083
Download: ML17228B355 (4)
v • d • e


Text

P RIDRIT'Y Z FACILITY)

UDOCS OFFSITE

-REGUGATOi INFORMATION DISTRIBUTIOhl'ÃPfEM (RIDS)

ACCESSION NBR:9512140083 DOC.DATE:'95/12/04 NOTARIZED: NO DOCKET ¹ FACIL:50-335 St. Lucie Plant, Unit 1, Florida Power & Light Co. 05000335 50-389 St. Lucie Plant, Unit 2, Florida Power & Light Co. 05000389 AUTH. NAME AUTHOR AFFILIATION BOHLKE,W.H. Florida Power & Light Co.

RECIP.NAME RECIPIENT AFFILIATION Division of Freedom of Information & Publications Services

SUBJECT:

Comment opposing proposed generic communication, "Boraflex R, Degradation in SFP Storage Racks."

DISTRIBUTION CODE: DS09D iCOPIES RECEIVED:LTR ENCL SIZE:

TITLE: SECY/DSB Dist: Public Comment on Propose Rule R)-Misc Notice;Reg G p

NOTES:

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL INTERNAL:>> CENTER 0 NMSS/IMOB T8F5

~6&/NR 1'~-18 RES DIR RES/DRA/DEPY RES/DST EXTERNAL: NRC PDR D

0 C

u NOTE TO ALL'RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTEI CONTACTTHE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 504-2083 ) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS I'OR DOCUMENTS YOU DON'T iVEED!

'l,'O'.I"AL NUMBER OF COPIES REQUIRED: LTTR 7 ENCL

Sc/f / 0 WR., '5 Z'9 g/

~'an W+ r.lc~ 'z/oIXl~zZ.j%W Cc Florida Power & Light Company, P.O. Box 14000, Juno Beach, FL 33408-tt420

~mn,~~ ~WZ.

DEC <<~995 r L-95-325 r

Chief, Rules Review and Directives Branch U. S. Nuclear Regulatory Commission Mail Stop T-6D-69 Washington, DC 20555-0001

Subject:

Proposed Generic Communication; Boraflex rr Degradation in Spent Fuel Pool Storage Racks Gi I r 60 FR 56359 R ue t for mmen gl, Af-I A

On November 8, 1995, the Nuclear Regulatory Commission (NRC) published for pqbTic comment, "Proposed Generic Communication; Boraflex Degradation in Spent Fuel Pool Storage Racks." These comments are submitted on behalf of Florida Power & Light (FPL), licensed operator of two nuclear power plant units in Dade County, Florida and two unifs in St. Lucie County, Florida.

FPL notes that the EPRI studies reported in the draft generic letter were documented in 1993, and further investigations are ongoing. Specifically, EPRI report TR-103300 that states that the access of water to and around Boraflex panels is perhaps the most significant factor influencing the rate of Silica dissolution from Boraflex. In the "Requested Information" section of the draft, the NRC requests licensees to provide a description of the physical condition of the Boraflex, including any deterioration, on the basis of current, as well as, future projected accumulated gamma exposure and possible water ingress to the Boraflex. FPL contends that Blackness Tests and trending of Silica levels in the spent fuel pool (SFP) coolant is sufficient to monitor the performance of Boraflex in the SFPs. It is not necessary, nor is the information available, to project future degradation based on the access of water to and around the Boraflex.

The NRC staff recognizes in the draft generic letter that the presence of borated water in pressurized water reactor (PWR) SFPs contribute to the margin on subcriticality. However, the staff indicates that licensees will be requested to provide information on maintaining margin in unborated water. We believe that such a request is inconsistent with the stated benefit of borated water, particularly for PWRs. We note that the Westinghouse Owners Group (WOG) has submitted a topical report to the staff in an effort to credit boron in solution for criticality control in PWRs. In light of the WOG effort, we urge the staff to reconsider this information request to account for actual plant conditions.

We appreciate the opportunity to comment on this proposed generic'letter.

Very truly yours, W. H. Bohlke I 95i2i40083 95i204 PDR ADQCK 05000335 Vice President H PDR.-+

Nuclear Engineering and Licensing an FPL Group company

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