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{{#Wiki_filter:<<6 REGULATORY INFORMATION DISTR IBU                 SYSTEN (R IDB)
{{#Wiki_filter:<<6 REGULATORY INFORMATION DISTR IBU SYSTEN (R IDB)
ACCESSION NBR: 8606060024                 DOC. DATE: 86/06/03     NOTARIZED: NQ             DOCKET FACIL: 50-400 Sheav on Harv is Nucleav Power Plant> Unit 1> Cav olina                       05000400 AUTH. NAi'1E               AUTHOR AFFILIATION Zli'fNERI'fAN>S. R.       Cav olina Powev'c Light Co.
ACCESSION NBR: 8606060024 DOC. DATE: 86/06/03 NOTARIZED:
RECIP. NAI iE              RECIPIENT AFFILIATION DENTQN, H. R.             Office of Nuclear     Reactov   Regulation. Div ec tor (post 851125
NQ DOCKET FACIL:50-400 Sheav on Harv is Nucleav Power Plant>
Unit 1>
Cav olina 05000400 AUTH. NAi'1E AUTHOR AFFILIATION Zli'fNERI'fAN>S. R.
Cav olina Powev'c Light Co.
RECIP. NAIiE RECIPIENT AFFILIATION DENTQN, H. R.
Office of Nuclear Reactov Regulation.
Div ec tor (post 851125


==SUBJECT:==
==SUBJECT:==
Fov wav'ds addi       info v.e implementation of Rev 1 to Reg Guide
Fov wav'ds addi info v.e implementation of Rev 1 to Reg Guide
: 1. 127> "Insp       of Water-Control     structures Associated w/nuclear Power Plants. " SER (NUREQ 1038)               wc Tech Specs should be v evised as indicated.
: 1. 127>
DISTRIBUTION CODE: 0001D               COPIES RECEIVED: LTR TITLE: Licensing Submittal: PBAR/FBAR Amdts                 Zc JRelated ENCL      l SIZE:
"Insp of Water-Control structures Associated w/nuclear Power Plants. " SER (NUREQ 1038) wc Tech Specs should be v evised as indicated.
Correspondence NOTES: App    li  cation  for permit renewal f iled.                                       05000400 RECIPIENT               COPIEB            REC IP IENT              COPIES ID CODE/NAI'1E         LTTR ENCL        ID CODE/NAi~fE          LTTR ENCL PNR-A ADTB                         1      PWR-* EB                          1 PNR-A ElCSB                   2    2      PWR-A FOB PNR-A PD2 LA                               PWR-A PD2 PD                      1 BUCKLEY> B           01      2    2      PWR-A PSB                          1 PNR-A RSB                           1 INTERNAL: AD1'1/LFf'fB                           0      ELD/HDSi                    1    0 IE FILE                             1      IE/DEPER/EPB 36 IE/DGAW'/GAB 21               1    1      NRR BWR ADTS                      0 NRR PNR-A ADTS                     0      NRR PWR-B ADTS                    0 NRR RQE> i'f. L                     1      N    H      FIB            1 NRR/DHFT/ifTB                       1                          04            1 R('N2                         3     3     RN/DDANI /1'f IB                  0 EXTERNAL: 24X                                    1      BNL(AMDTS ONLY)                   1 DNB/DSS      ( Ai'1DTS )                  LPDR               03           1 iNRC PDR            02                    NSIC               05           1 PNL CRUEL> R                        1 TOTAL NUi'1BER OF COPIES REQUIRED: LTTR                 34   ENCL     28
DISTRIBUTION CODE:
0001D COPIES RECEIVED: LTR J ENCL l SIZE:
TITLE: Licensing Submittal:
PBAR/FBAR Amdts Zc Related Correspondence NOTES: Application for permit renewal filed.
05000400 RECIPIENT ID CODE/NAI'1E PNR-A ADTB PNR-A ElCSB PNR-A PD2 LA BUCKLEY> B 01 PNR-A RSB INTERNAL: AD1'1/LFf'fB IE FILE IE/DGAW'/GAB 21 NRR PNR-A ADTS NRR RQE> i'f. L NRR/DHFT/ifTB R('N2 EXTERNAL: 24X DNB/DSS
( Ai'1DTS )
iNRC PDR 02 PNL CRUEL> R COPIEB LTTR ENCL 1
2 2
2 2
1 0
1 1
1 0
1 1
3 3
1 1
REC IP IENT ID CODE/NAi~fE PWR-* EB PWR-A FOB PWR-A PD2 PD PWR-A PSB ELD/HDSi IE/DEPER/EPB 36 NRR BWR ADTS NRR PWR-B ADTS N
H FIB 04 RN/DDANI /1'fIB BNL(AMDTS ONLY)
LPDR 03 NSIC 05 COPIES LTTR ENCL 1
1 1
1 0
0 0
1 1
0 1
1 1
TOTAL NUi'1BER OF COPIES REQUIRED:
LTTR 34 ENCL 28


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C$ QE Carolina Power & Light Company 3                             SERIAL: NLS-86-206 JUN        1986 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC     20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT NO. I - DOCKET NO. 50-000 DRAFT TECHNICAL SPECIFICATION ON MAXIMUMSEDIMENT DEPTH
C$QE Carolina Power & Light Company JUN 3
1986 SERIAL: NLS-86-206 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT NO. I - DOCKET NO. 50-000 DRAFT TECHNICALSPECIFICATION ON MAXIMUMSEDIMENT DEPTH


==Dear Mr. Denton:==
==Dear Mr. Denton:==
 
As requested by a member of your staff, Carolina Power R Light Company (CPi!t:L) submits additional information regarding the=implementation of Regulatory Guide I.l27 (Revision I), "Inspection of Water-Control Structures Associated with Nuclear Power Plants."
As requested by a member of your           staff, Carolina Power R Light Company (CPi!t:L) submits additional information regarding the=implementation of Regulatory Guide I.l27 (Revision I), "Inspection of Water-Control Structures Associated with Nuclear Power Plants." CPRL also requests that the Safety Evaluation Report (NUREG-l038) and the Technical Specifications'be revised as indicated in the attachments to this letter.
CPRL also requests that the Safety Evaluation Report (NUREG-l038) and the Technical Specifications'be revised as indicated in the attachments to this letter.
Attachment l provides the CPRL position and the justification for the Technical Specification change. Attachment 2 provides the proposed changes to the Technical Specifications.
Attachment l provides the CPRL position and the justification for the Technical Specification change. provides the proposed changes to the Technical Specifications.
If you have any questions, please contact me at your convenience.
If you have any questions, please contact me at your convenience.
Yours very truly,
Yours very truly, SDC/pgp (3953S DC)
                                                                . Zim erman ger Nuclear Licensing Section SDC/pgp     (3953S DC)
Attachments
Attachments CC:   Mr. B. C. Buckley (NRC)                                 Mr. 3ohn D. Runkle      "
. Zim erman ger Nuclear Licensing Section CC:
Mr. G. F. Maxwell (NRC-SHNPP)                           Dr. Richard D. Wilson Dr. 3. Nelson Grace (NRC-RII)                           Mr. G. O. Bright (ASLB)
Mr. B. C. Buckley (NRC)
Mr. Travis Payne (KUDZU)                                Dr. 3. H. Carpenter (ASLB)
Mr. G. F. Maxwell (NRC-SHNPP)
Mr. Daniel F. Read (CHANGE/ELP)                          Mr. 3. L. Kelley (ASLB)
Dr. 3. Nelson Grace (NRC-RII)
Wake County Public Library                              Mr. T. S. Moore (ASLAB)
Mr. Travis Payne (KUDZU)
Mr. Wells Eddleman                                      Dr. R. L. Gotchy (ASLAB)
Mr. Daniel F. Read (CHANGE/ELP)
Mr. R. Gonzalez                                          Mr. H. A. Wilber (ASLAB)
Wake County Public Library Mr. Wells Eddleman Mr. R. Gonzalez Mr. 3ohn D. Runkle Dr. Richard D. Wilson Mr. G. O. Bright (ASLB)
Bb0b0b0024 8b0b0~
Dr. 3. H. Carpenter (ASLB)
PDR     ADQCK 0 5000400p i
Mr. 3. L. Kelley (ASLB)
Mr. T. S. Moore (ASLAB)
Dr. R. L. Gotchy (ASLAB)
Mr. H. A. Wilber (ASLAB)
Bb0b0b0024 5000400 i
8b0b0~
PDR ADQCK 0 p
E 411 Fayettevilte Street o P. O. Box 1551 o Raleigh. N. C. 27602 youl
E 411 Fayettevilte Street o P. O. Box 1551 o Raleigh. N. C. 27602 youl


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ATTACHMENT 1 Shearon Harris Nuclear Power (SHNPP)
ATTACHMENT1 Shearon Harris Nuclear Power (SHNPP)
Safety Evaluation Report (SER)
Safety Evaluation Report (SER)
(NUREG-1038), Section 2.0.11.2, Page 2-26 Because plant site drainage, including overland runoff, flows into the ESWI and ESWD channels, there is a potential for sediment to build up in these channels and in the auxiliary reservoir channel and the auxiliary reservoir, especially while heavy construction is still in progress. The applicant has furnished cross-sectional and profile data for the channels. These data show very little sediment buildup, except in the ESWD channel where as much as 3.5 feet of sediment has accumulated close to the discharge structure. However, the staff expects that this sediment will not accumulate once the plant is in operation and there is flow through the channel.
(NUREG-1038), Section 2.0.11.2, Page 2-26 Because plant site drainage, including overland runoff, flows into the ESWI and ESWD channels, there is a potential for sediment to build up in these channels and in the auxiliary reservoir channel and the auxiliary reservoir, especially while heavy construction is still in progress.
The applicant has furnished cross-sectional and profile data for the channels.
These data show very little sediment buildup, except in the ESWD channel where as much as 3.5 feet of sediment has accumulated close to the discharge structure.
However, the staff expects that this sediment willnot accumulate once the plant is in operation and there is flow through the channel.
To preclude sediment from building up to an unacceptable level during operation, the')
To preclude sediment from building up to an unacceptable level during operation, the')
applicant has committed to monitor the channels for sediment buildup in accordance with Regulatory Guide 1.127, Revision l. Details of the monitoring program have not been provided; however, the details which will define the depth of sediment that will be allowed to accumulate before removal is necessary and a procedure for removal will be included in a Technical Specification that will be required by the staff at the appropriate stage of staff review before plant operation begins.
applicant has committed to monitor the channels for sediment buildup in accordance with Regulatory Guide 1.127, Revision l. Details of the monitoring program have not been provided; however, the details which willdefine the depth of sediment that will be allowed to accumulate before removal is necessary and a procedure for removal will be included in a Technical Specification that will be required by the staff at the appropriate stage of staff review before plant operation begins.
~Res ense:
~Res ense:
CPRL reaffirms our commitment to Regulatory Guide 1.127, Revision l. CPRL has been performing inspections, in accordance with this Regulatory Guide, since the reservoir was filled in 1981. The data indicates very little sediment buildup and no significant change in channel flow area. Therefore, CPRL requests that the staff revise the SER to delete the requirement that the Technical Specifjcations define the depth of sediment that will be allowed to accumulate before removal is necessary..
CPRL reaffirms our commitment to Regulatory Guide 1.127, Revision l. CPRL has been performing inspections, in accordance with this Regulatory Guide, since the reservoir was filled in 1981.
Regulatory Guide 1.127 recommends that inspections be performed at periodic intervals to check the conditions of the water-control structures and to evaluate their operational adequacy. Specifically, it recommends that channels be examined for any conditions that may impose constraints on the functioning of the structure. Given any significant change, an evaluation should be performed to determine whether performance would be adversely af fected.
The data indicates very little sediment buildup and no significant change in channel flow area.
In terms of the Emergency Service Water Intake and Discharge Channels, CPRL examines the channels in terms of cross-sectional flow area. This type of performance evaluation is much more appropriate than a single parameter monitoring/action point; i.e., channel cross-sectional flow area vs. maximum sediment depth, as proposed in 6.8.0(F)(3). Therefore, CPRL requests that the SHNPP Technical Specifications be revised as indicated in Attachment 2.
Therefore, CPRL requests that the staff revise the SER to delete the requirement that the Technical Specifjcations define the depth of sediment that willbe allowed to accumulate before removal is necessary..
Regulatory Guide 1.127 recommends that inspections be performed at periodic intervals to check the conditions of the water-control structures and to evaluate their operational adequacy.
Specifically, it recommends that channels be examined for any conditions that may impose constraints on the functioning of the structure.
Given any significant change, an evaluation should be performed to determine whether performance would be adversely affected.
In terms of the Emergency Service Water Intake and Discharge Channels, CPRL examines the channels in terms of cross-sectional flow area.
This type of performance evaluation is much more appropriate than a single parameter monitoring/action point; i.e., channel cross-sectional flow area vs. maximum sediment depth, as proposed in 6.8.0(F)(3). Therefore, CPRL requests that the SHNPP Technical Specifications be revised as indicated in Attachment 2.
(3958SOC/pgp)
(3958SOC/pgp)


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PROOF Ai90 REEVE COPY ADMINISTRATIVE CONTROLS PROCEDURES   AND PROGRAMS     Continued                                 IIQ I&h.t-
ADMINISTRATIVE CONTROLS g/Ing>.~ie f <
: c. Seconda       Water Chemist       Continued               F 9     eels
PROOF Ai90 REEVE COPY PROCEDURES AND PROGRAMS Continued c.
: 6. A procedure identifying (a) the authority responsible for the interpretation of the data and (b) the sequence and timing of administrative events required to initiate corrective action.
Seconda Water Chemist Continued IIQI&h.t-F 9 eels d.
: d. Backu     Method   for Determinin   Subcoolin Mar in A program that will ensure the capability to monitor accurately the Reactor Coolant System subcooling margin. This program shall include the following:
6.
                                                                      \
A procedure identifying (a) the authority responsible for the interpretation of the data and (b) the sequence and timing of administrative events required to initiate corrective action.
: l. Training of personnel, and
Backu Method for Determinin Subcoolin Mar in e.
: 2. Procedures for monitoring.
A program that will ensure the capability to monitor accurately the Reactor Coolant System subcooling margin.
: e. Post"Accident Samolin A program that will ensure the capability to obtain and analyze, under accident conditions, reactor coolant, radioactive iodines and particulates in plant gaseous effluents, and containment atmosphere.
This program shall include the following:
samples.     The program shall include the following:
\\
1.r     Training of personnel,
l.
: 2.     Procedures   for sampling and analysis, and
Training of personnel, and 2.
: 3.     Provisions for maintenance of sampling and analysis equipment.
Procedures for monitoring.
: f. Ins ections of Water Control Structures A program to implement an ongoing inspection program in accordance with Regulatory Guide 1.127 (Revision 1, March 1978) for the main and auxiliary dams, the auxiliary separating dike, the emergency service water and discharge channels, and the auxiliary reservoir channel. The program shall include the following:
Post"Accident Samolin A program that will ensure the capability to obtain and analyze, under accident conditions, reactor coolant, radioactive iodines and particulates in plant gaseous effluents, and containment atmosphere.
iqtake provisions of Regulatory Guide 1.127, Revision 1, to
samples.
                                      '.
The program shall include the following:
The                                                          be implemented as a part, of plant startup operations.
1.r Training of personnel, 2.
: 2.     Subsequent   inspections at yearly intervals for at least the next 3 years. If adverse conditions are not revealed by these inspections, inspection at 5-year intervals will be performed.
Procedures for sampling and analysis, and 3.
SHEARON HARRIS   "   UNIT 1               6-19}}
Provisions for maintenance of sampling and analysis equipment.
f.
Ins ections of Water Control Structures A program to implement an ongoing inspection program in accordance with Regulatory Guide 1.127 (Revision 1, March 1978) for the main and auxiliary dams, the auxiliary separating dike, the emergency service water and discharge
: channels, and the auxiliary reservoir channel.
The program shall include the following:
iqtake The provisions of Regulatory Guide 1.127, Revision 1, to be implemented as a part, of plant startup operations.
2.
Subsequent inspections at yearly intervals for at least the next 3 years.
If adverse conditions are not revealed by these inspections, inspection at 5-year intervals will be performed.
SHEARON HARRIS " UNIT 1 6-19}}

Latest revision as of 05:02, 7 January 2025

Forwards Addl Info Re Implementation of Rev 1 to Reg Guide 1.127, Insp of Water-Control Structures Associated W/Nuclear Power Plants. SER (NUREG-1038) & Tech Specs Should Be Revised as Indicated
ML18019A868
Person / Time
Site: Harris 
Issue date: 06/03/1986
From: Zimmerman S
CAROLINA POWER & LIGHT CO.
To: Harold Denton
Office of Nuclear Reactor Regulation
References
RTR-NUREG-1038, RTR-REGGD-01.127, RTR-REGGD-1.127 NLS-86-206, NUDOCS 8606060024
Download: ML18019A868 (7)
v • d • e


Text

<<6 REGULATORY INFORMATION DISTR IBU SYSTEN (R IDB)

ACCESSION NBR: 8606060024 DOC. DATE: 86/06/03 NOTARIZED:

NQ DOCKET FACIL:50-400 Sheav on Harv is Nucleav Power Plant>

Unit 1>

Cav olina 05000400 AUTH. NAi'1E AUTHOR AFFILIATION Zli'fNERI'fAN>S. R.

Cav olina Powev'c Light Co.

RECIP. NAIiE RECIPIENT AFFILIATION DENTQN, H. R.

Office of Nuclear Reactov Regulation.

Div ec tor (post 851125

SUBJECT:

Fov wav'ds addi info v.e implementation of Rev 1 to Reg Guide

1. 127>

"Insp of Water-Control structures Associated w/nuclear Power Plants. " SER (NUREQ 1038) wc Tech Specs should be v evised as indicated.

DISTRIBUTION CODE:

0001D COPIES RECEIVED: LTR J ENCL l SIZE:

TITLE: Licensing Submittal:

PBAR/FBAR Amdts Zc Related Correspondence NOTES: Application for permit renewal filed.

05000400 RECIPIENT ID CODE/NAI'1E PNR-A ADTB PNR-A ElCSB PNR-A PD2 LA BUCKLEY> B 01 PNR-A RSB INTERNAL: AD1'1/LFf'fB IE FILE IE/DGAW'/GAB 21 NRR PNR-A ADTS NRR RQE> i'f. L NRR/DHFT/ifTB R('N2 EXTERNAL: 24X DNB/DSS

( Ai'1DTS )

iNRC PDR 02 PNL CRUEL> R COPIEB LTTR ENCL 1

2 2

2 2

1 0

1 1

1 0

1 1

3 3

1 1

REC IP IENT ID CODE/NAi~fE PWR-* EB PWR-A FOB PWR-A PD2 PD PWR-A PSB ELD/HDSi IE/DEPER/EPB 36 NRR BWR ADTS NRR PWR-B ADTS N

H FIB 04 RN/DDANI /1'fIB BNL(AMDTS ONLY)

LPDR 03 NSIC 05 COPIES LTTR ENCL 1

1 1

1 0

0 0

1 1

0 1

1 1

TOTAL NUi'1BER OF COPIES REQUIRED:

LTTR 34 ENCL 28

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PROOF Ai90 REEVE COPY PROCEDURES AND PROGRAMS Continued c.

Seconda Water Chemist Continued IIQI&h.t-F 9 eels d.

6.

A procedure identifying (a) the authority responsible for the interpretation of the data and (b) the sequence and timing of administrative events required to initiate corrective action.

Backu Method for Determinin Subcoolin Mar in e.

A program that will ensure the capability to monitor accurately the Reactor Coolant System subcooling margin.

This program shall include the following:

\\

l.

Training of personnel, and 2.

Procedures for monitoring.

Post"Accident Samolin A program that will ensure the capability to obtain and analyze, under accident conditions, reactor coolant, radioactive iodines and particulates in plant gaseous effluents, and containment atmosphere.

samples.

The program shall include the following:

1.r Training of personnel, 2.

Procedures for sampling and analysis, and 3.

Provisions for maintenance of sampling and analysis equipment.

f.

Ins ections of Water Control Structures A program to implement an ongoing inspection program in accordance with Regulatory Guide 1.127 (Revision 1, March 1978) for the main and auxiliary dams, the auxiliary separating dike, the emergency service water and discharge

channels, and the auxiliary reservoir channel.

The program shall include the following:

iqtake The provisions of Regulatory Guide 1.127, Revision 1, to be implemented as a part, of plant startup operations.

2.

Subsequent inspections at yearly intervals for at least the next 3 years.

If adverse conditions are not revealed by these inspections, inspection at 5-year intervals will be performed.

SHEARON HARRIS " UNIT 1 6-19

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