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| issue date = 04/11/1985 | | issue date = 04/11/1985 | ||
| title = Responds to NRC 850312 Ltr Re Violations Noted in Const Appraisal Team Insp Rept 50-400/84-41,as Noted in Insp Rept 50-400/85-04.Corrective Actions Listed | | title = Responds to NRC 850312 Ltr Re Violations Noted in Const Appraisal Team Insp Rept 50-400/84-41,as Noted in Insp Rept 50-400/85-04.Corrective Actions Listed | ||
| author name = | | author name = Parsons R | ||
| author affiliation = CAROLINA POWER & LIGHT CO. | | author affiliation = CAROLINA POWER & LIGHT CO. | ||
| addressee name = | | addressee name = Grace J | ||
| addressee affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) | | addressee affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) | ||
| docket = 05000400 | | docket = 05000400 | ||
Line 16: | Line 16: | ||
| page count = 10 | | page count = 10 | ||
}} | }} | ||
=Text= | =Text= | ||
{{#Wiki_filter:Carolina Power 5 Light Company P.O.Box 101, New Hill, NC 27562 April ll, 1985 Dr.3.Nelson Grace United States Nuclear Regulatory | {{#Wiki_filter:Carolina Power 5 Light Company P. O. Box 101, New Hill, NC 27562 April ll, 1985 Dr. 3. Nelson Grace NRC-351 United States Nuclear Regulatory Commission Region II 101 Marietta Street, Northwest (Suite 2900) | ||
Commission | Atlanta, Georgia 30323 SHEARON HARRIS NUCLEAR POWER PLANT UNIT NO. 1 DOCKET NO. 50-000 IE INSPECTION REPORT NO. 50-000/85-00 | ||
Region II 101 Marietta Street, Northwest (Suite 2900)Atlanta, Georgia 30323 | |||
REPORT NO.50-000/85-00 | ==Dear Dr. Grace:== | ||
Dear Dr.Grace: Carolina Power and Light Company (CPAL)has received Mr.R.D.Walker's letter, dated March 12, 1985, which references | |||
the results of the Construction | Carolina Power and Light Company (CPAL) has received Mr. R. D. Walker's letter, dated March 12, 1985, which references the results of the Construction Appraisal Team (CAT) inspection by the NRC in October and November 1980. You requested that CPRL respond to three specific items identified during the CAT Inspection Report No. 50-000/80-01 Appendix A, Executive Summary, Overall Conclusions, Page A-l. | ||
Appraisal Team (CAT)inspection | We consider the CAT inspection to have been a beneficial experience for the project. The thoroughness and professionalism demonstrated by the team rriembers was noteworthy. | ||
by the NRC in October and November 1980.You requested that CPRL respond to three specific items identified | The findings and observations noted in the conclusion paragraphs of the several sections of the report are being given management attention as we continue our internal evaluations of program improvement. In addition to the response requested by Mr. Walker's letter, we would like to take notice of several strengths reported by the NRC appraisal. | ||
during the CAT Inspection | : 1. There was evidence of good project management and construction practices at the Shearon Harris Site. These good practices include a capable project management organization, the fact that site engineering and inspection activities are primarily located and controlled on-site, and there is extensive use of field engineers. | ||
Report No.50-000/80-01 | : 2. In the pipe support area, site engineering and inspection personnel were knowledgeable of procedures, requirements, and responsibilities. Procedures and inspection checklists were thorough and detailed. | ||
Appendix A, Executive Summary, Overall Conclusions, Page A-l.We consider the CAT inspection | : 3. The Quality Check Program appears to be a viable method of addressing employee concerns which may help preclude future problems with employee concerns experienced at other nuclear facilities. | ||
to have been a beneficial | In addition to the strengths noted above, we acknowledge the three program weaknesses that were identified. We herewith submit (Attachment) our responses to those items in accordance with your request contained in Report No. 50-000/85-00. | ||
experience | 8505210497 850423 PDR *DOCK 05000400 8 PDR XEX-se10/ I-OS5 | ||
for the project.The thoroughness | |||
and professionalism | P | ||
demonstrated | * t I f ff | ||
by the team rriembers was noteworthy. | ,I | ||
The findings and observations | ~- ~ r It tl t | ||
noted in the conclusion | J t' C l | ||
paragraphs | / It I | ||
of the several sections of the report are being given management | tt I | ||
attention as we continue our internal evaluations | ~I It ~ lt It ~ III+ ( | ||
of program improvement. | t P | ||
In addition to the response requested by Mr.Walker's letter, we would like to take notice of several strengths reported by the NRC appraisal. | tl J' ~ | ||
1.There was evidence of good project management | |||
and construction | Dr. 3. Nelson Grace | ||
practices at the Shearon Harris Site.These good practices include a capable project management | ~ ~ NRC-351 We consider the management actions being taken are satisfactory for the resolution of the items. | ||
organization, the fact that site engineering | Thank you for the consideration in this matter. | ||
and inspection | Yours very truly, R. M. Parsons Project General Manager Completion Assurance . | ||
activities | Shearon Harris Nuclear Power Plant RMP:bs A ttachment cc: Messrs. G. Maxwell/R. Prevatte (NRC-SHNPP) | ||
are primarily located and controlled | Mr. B. C. Buckley (NRC) | ||
on-site, and there is extensive use of field engineers. | XE X-se l 0/2-OS5 | ||
2.In the pipe support area, site engineering | |||
and inspection | ~ ~ | ||
personnel were knowledgeable | g I | ||
of procedures, requirements, and responsibilities. | 0 | ||
Procedures | !1'R l h | ||
and inspection | ~ Ik W | ||
checklists | ~ | ||
were thorough and detailed.3.The Quality Check Program appears to be a viable method of addressing | |||
employee concerns which may help preclude future problems with employee concerns experienced | ATTACHMENTTO CPRL LETTER OF RESPONSE TO NRC REPORT NO. 50-000/85-00 The following is a summary of management actions taken as a result of the three construction program items reported as requiring management attention by the "CAT" Inspection Report 50-000/80-01 Appendix A, Executive Summary; Overall Conclusions, page A-1 issued on December 20, 1980. | ||
at other nuclear facilities. | ITEM NO. 1: Conflicts were identified between design inputs and FSAR commitments with regard to electrical cable and raceway separation which resulted in separation deficiencies. (The response for this item is provided in two parts: (A) cable, and (B) raceway.) | ||
In addition to the strengths noted above, we acknowledge | RESPONSE A (Cable): FCR-E-3693 was issued December 17, 1980, which provided design details for the installation and inspection of exposed cables to exposed cables. | ||
the three program weaknesses | The Harris Plant Engineering Section (HPES) has initiated an evaluation of separation requirements for equipment to equipment, equipment to raceway, equipment to exposed cable, and exposed cable to raceway. | ||
that were identified. | After the design details for exposed cable to equipment are issued, Construction Inspection-Electrical will inspect safety-related equipment for exposed cable separation violations. | ||
We herewith submit (Attachment) | Exposed cable separation violations at tray to tray, or tray to conduit entrances and exits will be inspected as a portion of the inspection of the safety-related raceways. | ||
our responses to those items in accordance | After the above items are completed, the inspection results can be evaluated, and a projected completion date of the rework and final inspection can be established. | ||
with your request contained in Report No.50-000/85-00. | At the same time or prior to the initiation of the separation reinspection of safety-related exposed cable and safety-related raceway, new installations of scheduled non-nuclear safety cable will be inspected for separation. | ||
8505210497 | RESPONSE B (Raceway): HPES has prepared an analysis of non-nuclear safety conduit to safety-related tray without covers which justifies the validity of the 1" separation criteria. | ||
850423 PDR*DOCK 05000400 8 PDR XEX-se10/I-OS5 | HPES is revising the FSAR commitments to reflect the results of the analysis. | ||
P*t I f ff ,I~-~r It | HPES is currently clarifying separation requirements for raceway to equipment. | ||
Dr.3.Nelson Grace~~NRC-351 We consider the management | After the design information is issued for separation requirements between raceway and equipment, Construction Inspection will issue a procedure or revise existing procedures to incorporate new design information and reinspect appropriate inspection points for safety-related raceway separation requirements. | ||
actions being taken are satisfactory | At the same time or prior to the initiation of the reinspection of safety-related raceway separation, new installations of scheduled non-nuclear safety raceway will be inspected for separation. | ||
for the resolution | XE X-sell/3-OS 5 | ||
of the items.Thank you for the consideration | |||
in this matter.Yours very truly, R.M.Parsons Project General Manager Completion | 4 | ||
Assurance.Shearon Harris Nuclear Power Plant RMP:bs A ttachment cc: Messrs.G.Maxwell/R. | ~ | ||
Prevatte (NRC-SHNPP) | 4 1 $ | ||
Mr.B.C.Buckley (NRC)XE X-se l 0/2-OS5 | 4 4 p g g ( s r s | ||
~~ | ~ | ||
g Ws. ~ ' ( IS P ~ ~ IV 'tIV IV Il S vt 1 | |||
~ | |||
The following is a summary of management | t ~ | ||
actions taken as a result of the three construction | Vt 4 | ||
program items reported as requiring management | VV I A I, | ||
attention by the"CAT" Inspection | I d | ||
Report 50-000/80-01 | ll I | ||
Appendix A, Executive Summary;Overall Conclusions, page A-1 issued on December 20, 1980.ITEM NO.1: Conflicts were identified | 41 I | ||
between design inputs and FSAR commitments | 4 VV .(~ r II | ||
with regard to electrical | 'r I | ||
cable and raceway separation | 4 | ||
which resulted in separation | ' I AF I F I | ||
deficiencies.(The response for this item is provided in two parts: (A)cable, and (B)raceway.)RESPONSE A (Cable): FCR-E-3693 | ~ | ||
was issued December 17, 1980, which provided design details for the installation | * A III ~ | ||
and inspection | I s I is PJ C 1 lt I I I 4 | ||
of exposed cables to exposed cables.The Harris Plant Engineering | 1 A S r s - ~ ~ I I | ||
Section (HPES)has initiated an evaluation | 4 1 P | ||
of separation | ,A | ||
requirements | ~ 11 1 'I 4 P | ||
for equipment to equipment, equipment to raceway, equipment to exposed cable, and exposed cable to raceway.After the design details for exposed cable to equipment are issued, Construction | s I | ||
Inspection-Electrical | A 'I 4 " VV s lf II I | ||
will inspect safety-related | I A | ||
equipment for exposed cable separation | ~ s I'I I | ||
violations. | II | ||
Exposed cable separation | 'I I 1 4 P 1'V 4 VV Nh | ||
violations | |||
at tray to tray, or tray to conduit entrances and exits will be inspected as a portion of the inspection | ITEM NO. 2: Hardware discrepancies were found in non-seismic items installed over Seismic Category I items. Failure of these discrepant non-seismic items could adversely affect Class 1E electrical components. | ||
of the safety-related | RESPONSE: The Regulatory Guide 1.29 Verification Walkdown commenced on February 26, 1985, utilizing a formal CPRL Engineering Procedure 7.6.B. Since Regulatory Guide 1.29 is followed in the design of the Shearon Harris NPP, this wall<down serves as a confirmation of design controlled components and a verification of field run components. As we stated during the CAT inspection, we had planned to perform this walkdown later in the construction phase of the project. As a result of the CAT identification of this item, we have accelerated the walkdown schedule by initiating a preliminary walkdown to gain an early start on problem identification and resolution. The final walkdown will still occur later in the construction sequence. | ||
raceways.After the above items are completed, the inspection | Potential problems identified during this phase will be subjected to a detailed evaluation and/or resolution which may consist of rework . | ||
results can be evaluated, and a projected completion | r The following buildings have been completed under Phase 1 of the program: | ||
date of the rework and final inspection | : 1. Waste Processing Building (Gas Decay Tank Area) | ||
can be established. | : 2. Emergency Service Water Intake Structure | ||
At the same time or prior to the initiation | : 3. Emergency Service Water Screening Structure Diesel Generator Building | ||
of the separation | : 5. Diesel Oil Storage Tank Building | ||
reinspection | : 6. Tank Building | ||
of safety-related | : 7. Fuel Handling Building Phase 2 will consist of a second walkdown of the buildings in which non-seismic components are located in safety-related areas. This will start as the areas approach completion. A system will be developed by Planning and Scheduling which will track construction progress and identify ar eas which are approaching completion. It is estimated that the Phase 2 Walkdown will mainly take place during the last quarter of 1985. This will ensure an area check for components added between the Phase 1 and Phase 2 Walkdowns. After an area has been walked down the final time, controls will be initiated to monitor further work in the area and ensure Reg. Guide 1.29 considerations are factored into follow-up work performed in the area. The walkdowns will be detailed enough to include checks for deficiencies of the type noted by the CAT inspectors. | ||
exposed cable and safety-related | In addition to the above, as of January 10, 1985, the Construction Inspection (CI) Unit has implemented an inspection program for non-Q expansion anchors in accordance with Technical Procedure TP-39 titled "Inspection of Drilled in Expansion Anchors". This program will ensure proper installation of future non-Q expansion anchors for non-seismically designed supports which are designed to survive a seismic event (SSE). | ||
raceway, new installations | XE X-sell/0-OS5 | ||
of scheduled non-nuclear | |||
safety cable will be inspected for separation. | 1 | ||
RESPONSE B (Raceway): | \ | ||
HPES has prepared an analysis of non-nuclear | n J | ||
safety conduit to safety-related | 1 0 | ||
tray without covers which justifies the validity of the 1" separation | I r f( | ||
criteria.HPES is revising the FSAR commitments | 'I C | ||
to reflect the results of the analysis.HPES is currently clarifying | b e | ||
separation | ~ | ||
requirements | w 1 | ||
for raceway to equipment. | Jf I | ||
After the design information | P pl f~ | ||
is issued for separation | v W | ||
requirements | ~, ' | ||
between raceway and equipment, Construction | (, | ||
Inspection | I II e | ||
will issue a procedure or revise existing procedures | P j I | ||
to incorporate | 4 I. | ||
new design information | II C | ||
and reinspect appropriate | |||
inspection | ITEM NO. 3: Deficiencies identified in the area of interdisciplinary and pipe to pipe clearances indicated that the identification and resolution of these interferences were not being ef fectively addressed. | ||
points for safety-related | RESPONSE: The Interdisciplinary Clearance Verification Walkdown began on February 26, 1985, governed by a formal CPRL Engineering Procedure 7.6.C. Because various structures, systems and components have been designed with consideration for minimum clearance requirements, this walkdown is a verification of these requirements and to evaluate any violations of this criteria due to physical constraints during the installation of these components. This program is divided into two phases. Phase 1 began February 26, 1985, and is performed concurrently with the Regulatory Guide 1.29 Verification Walkdown. Phase 1 is a walkdown of the buildings in which safety-related components are located. The intent of Phase 1 is to identify as soon as possible any modifications or reroutings that may be required to ensure no detrimental interaction with the existing components prior to system turnover. The following buildings have been completed under Phase 1 of the program: | ||
raceway separation | : l. Waste Processing Building (Gas Decay Tank Area) | ||
requirements. | : 2. Emergency Service Water Intake Structure | ||
At the same time or prior to the initiation | : 3. Emergency Service Water Screening Structure Diesel Generator Building | ||
of the reinspection | : 5. Diesel Oil Storage Tank Building | ||
of safety-related | : 6. Tank Building | ||
raceway separation, new installations | : 7. Fuel Handling Building HPES is developing a site unique comprehensive clearance matrix. This matrix will be utilized by Construction Inspection (CI) and incorporated in the respective inspection Technical Procedures (TPs). | ||
of scheduled non-nuclear | Phase 2 of this program will consist of a second complete walkdown of the buildings which contain safety-related components. This will begin as areas approach completion. | ||
safety raceway will be inspected for separation. | A system will be developed by Planning and Scheduling which will track construction progress and identify areas which are approaching completion. | ||
XE X-sell/3-OS | XE X-sell/5-OS5 | ||
4 | 0 rq I}} | ||
ITEM NO.2: Hardware discrepancies | |||
were found in non-seismic | |||
items installed over Seismic Category I items.Failure of these discrepant | |||
non-seismic | |||
items could adversely affect Class 1E electrical | |||
components. | |||
RESPONSE: The Regulatory | |||
Guide 1.29 Verification | |||
Walkdown commenced on February 26, 1985, utilizing a formal CPRL Engineering | |||
Procedure 7.6.B.Since Regulatory | |||
Guide 1.29 is followed in the design of the Shearon Harris NPP, this wall<down serves as a confirmation | |||
of design controlled | |||
components | |||
and a verification | |||
of field run components. | |||
As we stated during the CAT inspection, we had planned to perform this walkdown later in the construction | |||
phase of the project.As a result of the CAT identification | |||
of this item, we have accelerated | |||
the walkdown schedule by initiating | |||
a preliminary | |||
walkdown to gain an early start on problem identification | |||
and resolution. | |||
The final walkdown will still occur later in the construction | |||
sequence.Potential problems identified | |||
during this phase will be subjected to a detailed evaluation | |||
and/or resolution | |||
which may consist of rework.r The following buildings have been completed under Phase 1 of the program:1 | |||
Building (Gas Decay Tank Area)Emergency Service Water Intake Structure | |||
components | |||
are located in safety-related | |||
areas.This will start as the areas approach completion. | |||
A system will be developed by Planning and Scheduling | |||
which will track construction | |||
progress and identify ar eas which are approaching | |||
completion. | |||
It is estimated that the Phase 2 Walkdown will mainly take place during the last quarter of 1985.This will ensure an area check for components | |||
added between the Phase 1 and Phase 2 Walkdowns. | |||
After an area has been walked down the final time, controls will be initiated to monitor further work in the area and ensure Reg.Guide 1.29 considerations | |||
are factored into follow-up work performed in the area.The walkdowns will be detailed enough to include checks for deficiencies | |||
of the type noted by the CAT inspectors. | |||
In addition to the above, as of January 10, 1985, the Construction | |||
Inspection (CI)Unit has implemented | |||
an inspection | |||
program for non-Q expansion anchors in accordance | |||
with Technical Procedure TP-39 titled"Inspection | |||
of Drilled in Expansion Anchors".This program will ensure proper installation | |||
of future non-Q expansion anchors for non-seismically | |||
designed supports which are designed to survive a seismic event (SSE).XE X-sell/0-OS5 | |||
1\n J 0 | |||
identified | |||
in the area of interdisciplinary | |||
and pipe to pipe clearances | |||
indicated that the identification | |||
and resolution | |||
of these interferences | |||
were not being ef | |||
RESPONSE: The Interdisciplinary | |||
Clearance Verification | |||
Walkdown began on February 26, 1985, governed by a formal CPRL Engineering | |||
Procedure 7.6.C.Because various structures, systems and components | |||
have been designed with consideration | |||
for minimum clearance requirements, this walkdown is a verification | |||
of these requirements | |||
and to evaluate any violations | |||
of this criteria due to physical constraints | |||
during the installation | |||
of these components. | |||
This program is divided into two phases.Phase 1 began February 26, 1985, and is performed concurrently | |||
with the Regulatory | |||
Guide 1.29 Verification | |||
Walkdown.Phase 1 is a walkdown of the buildings in which safety-related | |||
components | |||
are located.The intent of Phase 1 is to identify as soon as possible any modifications | |||
or reroutings | |||
that may be required to ensure no detrimental | |||
interaction | |||
with the existing components | |||
prior to system turnover.The following buildings have been completed under Phase 1 of the program: l | |||
Building (Gas Decay Tank Area)Emergency Service Water Intake Structure Emergency Service Water Screening Structure Diesel Generator Building Diesel Oil Storage Tank Building Tank Building Fuel Handling Building HPES is developing | |||
a site unique comprehensive | |||
clearance matrix.This matrix will be utilized by Construction | |||
Inspection (CI)and incorporated | |||
in the respective | |||
inspection | |||
Technical Procedures (TPs).Phase 2 of this program will consist of a second complete walkdown of the buildings which contain safety-related | |||
components. | |||
This will begin as areas approach completion. | |||
A system will be developed by Planning and Scheduling | |||
which will track construction | |||
progress and identify areas which are approaching | |||
completion. | |||
XE X-sell/5-OS5 | |||
0 rq I | |||
}} |
Latest revision as of 19:25, 3 February 2020
ML18018B946 | |
Person / Time | |
---|---|
Site: | Harris ![]() |
Issue date: | 04/11/1985 |
From: | Parsons R CAROLINA POWER & LIGHT CO. |
To: | Grace J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
Shared Package | |
ML18018B945 | List: |
References | |
CON-NRC-351 NUDOCS 8505210497 | |
Download: ML18018B946 (10) | |
Text
Carolina Power 5 Light Company P. O. Box 101, New Hill, NC 27562 April ll, 1985 Dr. 3. Nelson Grace NRC-351 United States Nuclear Regulatory Commission Region II 101 Marietta Street, Northwest (Suite 2900)
Atlanta, Georgia 30323 SHEARON HARRIS NUCLEAR POWER PLANT UNIT NO. 1 DOCKET NO.50-000 IE INSPECTION REPORT NO. 50-000/85-00
Dear Dr. Grace:
Carolina Power and Light Company (CPAL) has received Mr. R. D. Walker's letter, dated March 12, 1985, which references the results of the Construction Appraisal Team (CAT) inspection by the NRC in October and November 1980. You requested that CPRL respond to three specific items identified during the CAT Inspection Report No. 50-000/80-01 Appendix A, Executive Summary, Overall Conclusions, Page A-l.
We consider the CAT inspection to have been a beneficial experience for the project. The thoroughness and professionalism demonstrated by the team rriembers was noteworthy.
The findings and observations noted in the conclusion paragraphs of the several sections of the report are being given management attention as we continue our internal evaluations of program improvement. In addition to the response requested by Mr. Walker's letter, we would like to take notice of several strengths reported by the NRC appraisal.
- 1. There was evidence of good project management and construction practices at the Shearon Harris Site. These good practices include a capable project management organization, the fact that site engineering and inspection activities are primarily located and controlled on-site, and there is extensive use of field engineers.
- 2. In the pipe support area, site engineering and inspection personnel were knowledgeable of procedures, requirements, and responsibilities. Procedures and inspection checklists were thorough and detailed.
- 3. The Quality Check Program appears to be a viable method of addressing employee concerns which may help preclude future problems with employee concerns experienced at other nuclear facilities.
In addition to the strengths noted above, we acknowledge the three program weaknesses that were identified. We herewith submit (Attachment) our responses to those items in accordance with your request contained in Report No. 50-000/85-00.
8505210497 850423 PDR *DOCK 05000400 8 PDR XEX-se10/ I-OS5
P
- t I f ff
,I
~- ~ r It tl t
J t' C l
/ It I
tt I
~I It ~ lt It ~ III+ (
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tl J' ~
Dr. 3. Nelson Grace
~ ~ NRC-351 We consider the management actions being taken are satisfactory for the resolution of the items.
Thank you for the consideration in this matter.
Yours very truly, R. M. Parsons Project General Manager Completion Assurance .
Shearon Harris Nuclear Power Plant RMP:bs A ttachment cc: Messrs. G. Maxwell/R. Prevatte (NRC-SHNPP)
Mr. B. C. Buckley (NRC)
XE X-se l 0/2-OS5
~ ~
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0
!1'R l h
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ATTACHMENTTO CPRL LETTER OF RESPONSE TO NRC REPORT NO. 50-000/85-00 The following is a summary of management actions taken as a result of the three construction program items reported as requiring management attention by the "CAT" Inspection Report 50-000/80-01 Appendix A, Executive Summary; Overall Conclusions, page A-1 issued on December 20, 1980.
ITEM NO. 1: Conflicts were identified between design inputs and FSAR commitments with regard to electrical cable and raceway separation which resulted in separation deficiencies. (The response for this item is provided in two parts: (A) cable, and (B) raceway.)
RESPONSE A (Cable): FCR-E-3693 was issued December 17, 1980, which provided design details for the installation and inspection of exposed cables to exposed cables.
The Harris Plant Engineering Section (HPES) has initiated an evaluation of separation requirements for equipment to equipment, equipment to raceway, equipment to exposed cable, and exposed cable to raceway.
After the design details for exposed cable to equipment are issued, Construction Inspection-Electrical will inspect safety-related equipment for exposed cable separation violations.
Exposed cable separation violations at tray to tray, or tray to conduit entrances and exits will be inspected as a portion of the inspection of the safety-related raceways.
After the above items are completed, the inspection results can be evaluated, and a projected completion date of the rework and final inspection can be established.
At the same time or prior to the initiation of the separation reinspection of safety-related exposed cable and safety-related raceway, new installations of scheduled non-nuclear safety cable will be inspected for separation.
RESPONSE B (Raceway): HPES has prepared an analysis of non-nuclear safety conduit to safety-related tray without covers which justifies the validity of the 1" separation criteria.
HPES is revising the FSAR commitments to reflect the results of the analysis.
HPES is currently clarifying separation requirements for raceway to equipment.
After the design information is issued for separation requirements between raceway and equipment, Construction Inspection will issue a procedure or revise existing procedures to incorporate new design information and reinspect appropriate inspection points for safety-related raceway separation requirements.
At the same time or prior to the initiation of the reinspection of safety-related raceway separation, new installations of scheduled non-nuclear safety raceway will be inspected for separation.
XE X-sell/3-OS 5
4
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ITEM NO. 2: Hardware discrepancies were found in non-seismic items installed over Seismic Category I items. Failure of these discrepant non-seismic items could adversely affect Class 1E electrical components.
RESPONSE: The Regulatory Guide 1.29 Verification Walkdown commenced on February 26, 1985, utilizing a formal CPRL Engineering Procedure 7.6.B. Since Regulatory Guide 1.29 is followed in the design of the Shearon Harris NPP, this wall<down serves as a confirmation of design controlled components and a verification of field run components. As we stated during the CAT inspection, we had planned to perform this walkdown later in the construction phase of the project. As a result of the CAT identification of this item, we have accelerated the walkdown schedule by initiating a preliminary walkdown to gain an early start on problem identification and resolution. The final walkdown will still occur later in the construction sequence.
Potential problems identified during this phase will be subjected to a detailed evaluation and/or resolution which may consist of rework .
r The following buildings have been completed under Phase 1 of the program:
- 1. Waste Processing Building (Gas Decay Tank Area)
- 2. Emergency Service Water Intake Structure
- 3. Emergency Service Water Screening Structure Diesel Generator Building
- 5. Diesel Oil Storage Tank Building
- 6. Tank Building
- 7. Fuel Handling Building Phase 2 will consist of a second walkdown of the buildings in which non-seismic components are located in safety-related areas. This will start as the areas approach completion. A system will be developed by Planning and Scheduling which will track construction progress and identify ar eas which are approaching completion. It is estimated that the Phase 2 Walkdown will mainly take place during the last quarter of 1985. This will ensure an area check for components added between the Phase 1 and Phase 2 Walkdowns. After an area has been walked down the final time, controls will be initiated to monitor further work in the area and ensure Reg. Guide 1.29 considerations are factored into follow-up work performed in the area. The walkdowns will be detailed enough to include checks for deficiencies of the type noted by the CAT inspectors.
In addition to the above, as of January 10, 1985, the Construction Inspection (CI) Unit has implemented an inspection program for non-Q expansion anchors in accordance with Technical Procedure TP-39 titled "Inspection of Drilled in Expansion Anchors". This program will ensure proper installation of future non-Q expansion anchors for non-seismically designed supports which are designed to survive a seismic event (SSE).
XE X-sell/0-OS5
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ITEM NO. 3: Deficiencies identified in the area of interdisciplinary and pipe to pipe clearances indicated that the identification and resolution of these interferences were not being ef fectively addressed.
RESPONSE: The Interdisciplinary Clearance Verification Walkdown began on February 26, 1985, governed by a formal CPRL Engineering Procedure 7.6.C. Because various structures, systems and components have been designed with consideration for minimum clearance requirements, this walkdown is a verification of these requirements and to evaluate any violations of this criteria due to physical constraints during the installation of these components. This program is divided into two phases. Phase 1 began February 26, 1985, and is performed concurrently with the Regulatory Guide 1.29 Verification Walkdown. Phase 1 is a walkdown of the buildings in which safety-related components are located. The intent of Phase 1 is to identify as soon as possible any modifications or reroutings that may be required to ensure no detrimental interaction with the existing components prior to system turnover. The following buildings have been completed under Phase 1 of the program:
- l. Waste Processing Building (Gas Decay Tank Area)
- 2. Emergency Service Water Intake Structure
- 3. Emergency Service Water Screening Structure Diesel Generator Building
- 5. Diesel Oil Storage Tank Building
- 6. Tank Building
- 7. Fuel Handling Building HPES is developing a site unique comprehensive clearance matrix. This matrix will be utilized by Construction Inspection (CI) and incorporated in the respective inspection Technical Procedures (TPs).
Phase 2 of this program will consist of a second complete walkdown of the buildings which contain safety-related components. This will begin as areas approach completion.
A system will be developed by Planning and Scheduling which will track construction progress and identify areas which are approaching completion.
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