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{{#Wiki_filter:* Public Service Electric and Gas Company 80 Park Place Newark, N.J. 07101 Phone 201/430-7000 April 24, l979 Director of Nuclear Reactor Regulation U. s. Nuclear Regulatory Commission Washington, D. C. 20555 Attention: | {{#Wiki_filter:PS~G | ||
* Public Service Electric and Gas Company 80 Park Place Newark, N.J. 07101 Phone 201/430-7000 April 24, l979 Director of Nuclear Reactor Regulation U. s. Nuclear Regulatory Commission Washington, D. C. | |||
20555 Attention: | |||
Mr. Olan D. Parr, Chief Gentlemen: | Mr. Olan D. Parr, Chief Gentlemen: | ||
Light Water Reactors Branch 3 Division of Project Management RESPONSE TO REQUESTS FOR ADDITIONAL INFORMATION NO. 2 UNI'I' SALEM NUCLEAR GENERATING STATION DOCKET NO. 50-3ll Public Service Electric and Gas Company hereby transmits sixty (60) copies to your request for additional information related to the report "Structural Integrity Test of Containment" submitted on March 30, 1979. In addition, is sixty (60).copies of valve data for the 36" and 10" valves associated with the Containment Purge and Pressure Vacuum Relief System (Q5.66). Should you have any questions, please do not hesitate to contact us. Enclosure The Energy People Very.truly | Light Water Reactors Branch 3 Division of Project Management RESPONSE TO REQUESTS FOR ADDITIONAL INFORMATION NO. 2 UNI'I' SALEM NUCLEAR GENERATING STATION DOCKET NO. 50-3ll Public Service Electric and Gas Company hereby transmits sixty (60) copies to your request for additional information related to the report "Structural Integrity Test of Containment" submitted on March 30, 1979. | ||
In addition, is sixty (60).copies of valve data for the 36" and 10" valves associated with the Containment Purge and Pressure Vacuum Relief System (Q5.66). | |||
Should you have any questions, please do not hesitate to contact us. | |||
Enclosure The Energy People Very.truly yours, RI#~ | |||
R. L. Mittl General Manager - | |||
Licensing and Environment Engineering and Construction 79050405\\9 95-2001 (400M) 9-77 | |||
J t | |||
Request for Additional Information on SIT Report Question: | |||
Page 2-9 of the Report said that liquid penetrant and/or magnetic particle inspection of the weld was performed. | Page 2-9 of the Report said that liquid penetrant and/or magnetic particle inspection of the weld was performed. | ||
The new Regulatory Guide does not permit the use of liquid penetrant method, please explain. Response | The new Regulatory Guide does not permit the use of liquid penetrant method, please explain. | ||
===Response=== | |||
The liner plate seam welds in the cylindrical walls and dome were radiographic inspected. | The liner plate seam welds in the cylindrical walls and dome were radiographic inspected. | ||
In the bottom liner plate where the seams are directly over the embeded tural tees, radiographic inspection of the weld could not be conducted. | In the bottom liner plate where the seams are directly over the embeded struc-tural tees, radiographic inspection of the weld could not be conducted. | ||
These bottom plate welds were 1003 vacuum box tested to 5 psi differential pressure. | These bottom plate welds were 1003 vacuum box tested to 5 psi differential pressure. | ||
Magnetic particle inspection was used as the weld qualification. | Magnetic particle inspection was used as the weld qualification. | ||
The alternate method of liquid penetrant was only used in areas inaccessible for magnetic particle inspection. | The alternate method of liquid penetrant was only used in areas inaccessible for magnetic particle inspection. | ||
We have requested our Q.A. Department to make a random check on their file regarding the bottom liner plate weld inspection. | We have requested our Q.A. Department to make a random check on their file regarding the bottom liner plate weld inspection. | ||
All the inspection record they have checked were made by the magnetic particle process. Question: | All the inspection record they have checked were made by the magnetic particle process. | ||
On Fig. 5-15 of the report, the crack photos at 47 and 54 psig, one of the cracks exhibits a double line. Is it one crack or two cracks adjacent to each other? Response | Question: | ||
It is a single crack with black markings at edges of the crack. Question: | On Fig. 5-15 of the report, the crack photos at 47 and 54 psig, one of the cracks exhibits a double line. | ||
On Fig. 5-18 of the report, the last sentence at the bottom of the page says: "Post test at zero psig, no width". Does that mean the crack is closed altogether? | Is it one crack or two cracks adjacent to each other? | ||
Response | |||
===Response=== | |||
It is a single crack with black markings at edges of the crack. | |||
Question: | |||
On Fig. 5-18 of the report, the last sentence at the bottom of the page says: | |||
"Post test at zero psig, no resid~al width". | |||
Does that mean the crack is closed altogether? | |||
===Response=== | |||
The residual crack width is defined as the residual width of new cracks or increased width of the existing cracks after containment pressure is reduced to atmosphere. | The residual crack width is defined as the residual width of new cracks or increased width of the existing cracks after containment pressure is reduced to atmosphere. | ||
The questioned crack has a pretest crack width of .015". When pressure returned to zero after the pressure test, the subject crack measured .015", which is the same as the ginal crack. Our statement of no residual width is meant to be no increase in crack width from the pretest crack. SJT-1 | The questioned crack has a pretest crack width of.015". | ||
When pressure returned to zero after the pressure test, the subject crack measured.015", which is the same as the ori-ginal crack. | |||
Our statement of no residual width is meant to be no increase in crack width from the pretest crack. | |||
How do you predict crack width? RESPONSE | SJT-1 | ||
Crack width was predicted based on the maximwn expected stress and strain of the reinforcing steel during the pressure test. The reference paper is "Crack width and crack spacing in Reinforced Concrete Members "by Bengt B. Broms, ACI Journal, 1965. QUESTION: | |||
Page 7 -6 of the Report said three (3) strain gages were not functioning properly, what is the effect of the strain readings? | 11 QUESTION: | ||
RESPONSE | How do you predict crack width? | ||
Each set of strain gages consist of four gages attached at each face of the rebar (90° apart). Normally the strain reading for the particular rebar location is the average of the four gages. The three (3) gages that were not functioning properly were in three different sets. The strain reading for these three sets were based on the average of three gages instead of the regular four, omitting the reading of the functioning gage. QUESTION: | |||
Liner rosette R 17 measured a rnaximwn principal stress of 39,483 psi. How does it behave? RESPONSE | ===RESPONSE=== | ||
Liner plate A 442 Grade 60 has a minimum guaranteed yield stress of 32,000 psi. However, the actual yield stress is usually higher than that value. We have plotted the stress measurements in the decompression stages (Table 5-1.C) for rosettes No. 2, No. 17 and No. 19 to see if the elastic behavior for R 17 is still maintained. | Crack width was predicted based on the maximwn expected stress and strain of the reinforcing steel during the pressure test. | ||
Rosette No. 17 in question showed a faster rate of stress reduction than the other two that staged within the minimtim yield stress. We have concluded the material monitored by R 17 was still in the elastic range. QUESTION: | The reference paper is "Crack width and crack spacing in Reinforced Concrete Members "by Bengt B. Broms, ACI Journal, 1965. | ||
Which crack has a residual crack width exceeded .02" and "by how much? How deep? RESPONSE | QUESTION: | ||
The crack is in area No. 9, coordinate M 3 as listed in Table 5 -6 .d. The residual crack was .04" wide and only six inches long. After chipped out the entire length of the crack to a depth of 1/8" to the crack width measured .005" to .015" maximum. RWS:kd SIT-Z. ----- | Page 7 - | ||
F. | 6 of the Report said three (3) strain gages were not functioning properly, what is the effect of the strain readings? | ||
These stops vere factory 1et by Masoneilan to rotation to 90 degree during bench test. The bench test was performed on the assembled valve and actuator as outlined on Drawing M-6696 (Valve Control System) and APS 1515 (Inspection and Test Procedures). | |||
Test were witnessed and approved by the customer source inspec-tcr. One (1) 36" valve and Jettis Actuator was seismic vibration tested by the Acton Environmental Testing Corporation, Acton, Mass. Their test Report No. 11262, dated 10/24/75 dicated no evidence of mechanical damage or deterioration as a result of seismic vibration test; and noted the valve operated properly before, during and after the simulated seismic event. 2. Assurance of sufficient Actuator Torque conditions: | ===RESPONSE=== | ||
Each set of strain gages consist of four gages attached at each face of the rebar (90° apart). | |||
Normally the strain reading for the particular rebar location is the average of the four gages. | |||
The three (3) gages that were not functioning properly were in three different sets. | |||
The strain reading for these three sets were based on the average of three gages instead of the regular four, omitting the reading of the non-functioning gage. | |||
QUESTION: | |||
Liner rosette R 17 measured a rnaximwn principal stress of 39,483 psi. | |||
How does it behave? | |||
===RESPONSE=== | |||
Liner plate A 442 Grade 60 has a minimum guaranteed yield stress of 32,000 psi. | |||
However, the actual yield stress is usually higher than that value. | |||
We have plotted the stress measurements in the decompression stages (Table 5-1.C) for rosettes No. 2, No. 17 and No. 19 to see if the elastic behavior for R 17 is still maintained. | |||
Rosette No. 17 in question showed a faster rate of stress reduction than the other two that staged within the minimtim yield stress. | |||
We have concluded the material monitored by R 17 was still in the elastic range. | |||
QUESTION: | |||
Which crack has a residual crack width exceeded.02" and "by how much? | |||
How deep? | |||
===RESPONSE=== | |||
The crack is in area No. 9, coordinate M 3 as listed in Table 5 - | |||
6.d. | |||
The residual crack was.04" wide and only six inches long. | |||
After chipped out the entire length of the crack to a depth of 1/8" to ~", the crack width measured.005" to.015" maximum. | |||
RWS:kd SIT-Z. | |||
-------~----------------------------" | |||
F. | |||
~:' | |||
\\1 CONTROL VENTILATION ISOLATION VALVE DATA | |||
: 1. | |||
Assurance of Rat~d Vane Rotation (90 Degree) | |||
The Bettis Actuator bas an external adjusting screw in the end of each cylinder, for adjustment of angular rotart output of the actuator. | |||
These stops vere factory 1et by Masoneilan to li~it rotation to 90 degree during bench test. | |||
The bench test was performed on the assembled valve and actuator as outlined on Drawing M-6696 (Valve Control System) and APS 1515 (Inspection and Test Procedures). | |||
Test were witnessed and approved by the customer source inspec-tcr. | |||
One (1) co~plete 36" valve and Jettis Actuator was seismic vibration tested by the Acton Environmental Testing Corporation, Acton, Mass. | |||
Their test Report No. 11262, dated 10/24/75 in-dicated no evidence of mechanical damage or deterioration as a result of seismic vibration test; and noted the valve operated properly before, during and after the simulated seismic event. | |||
: 2. | |||
Assurance of sufficient Actuator Torque conditions: | |||
Air supply is 100 PSI Angle of opening is 90 degrees Max Delta P at LOCA is 60 PSI Tcrque required for Delta P 60 is 27,000 in/lbs. (based on Masoneilan Test Data and experience). | Air supply is 100 PSI Angle of opening is 90 degrees Max Delta P at LOCA is 60 PSI Tcrque required for Delta P 60 is 27,000 in/lbs. (based on Masoneilan Test Data and experience). | ||
36" Valve Data Available Torque Bettis Actuator: | 36" Valve Data Available Torque Bettis Actuator: | ||
##Break Torque vitb 100 PSI Supply Pressure 1s 77,200 in/lbs. ##End Torque vitb 100 PSI Supply Pressure is 39,000 in/lbs. 10" Valve Data Available Torque Bettis Actuator: (Torque required for Delta P 60 equals 1390 in/lbs.) ##Break Torque with 100 PSI Supply Pressure equals 9,100 in/lbs. ##End Torque witb 100 PSI aupply Pressure equal1 *,550 in/lbs. ##Bettis Corp. Telex dated 4/3/79. On the basis of tbe above data the available Actuator Torque la well in excess of the to operate the yalTe. l}} | ##Break Torque vitb 100 PSI Supply Pressure 1s 77,200 in/lbs. | ||
##End Torque vitb 100 PSI Supply Pressure is 39,000 in/lbs. | |||
10" Valve Data Available Torque Bettis Actuator: | |||
(Torque required for Delta P 60 equals 1390 in/lbs.) | |||
##Break Torque with 100 PSI Supply Pressure equals 9,100 in/lbs. | |||
##End Torque witb 100 PSI aupply Pressure equal1 *,550 in/lbs. | |||
##Bettis Corp. Telex dated 4/3/79. | |||
On the basis of tbe above data the available Actuator Torque la well in excess of the requl_re~_~orque to operate the yalTe. | |||
l}} | |||
Latest revision as of 06:12, 6 January 2025
| ML18079A211 | |
| Person / Time | |
|---|---|
| Site: | Salem |
| Issue date: | 04/24/1979 |
| From: | Mittl R Public Service Enterprise Group |
| To: | Parr O Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7905040519 | |
| Download: ML18079A211 (4) | |
Text
PS~G
- Public Service Electric and Gas Company 80 Park Place Newark, N.J. 07101 Phone 201/430-7000 April 24, l979 Director of Nuclear Reactor Regulation U. s. Nuclear Regulatory Commission Washington, D. C.
20555 Attention:
Mr. Olan D. Parr, Chief Gentlemen:
Light Water Reactors Branch 3 Division of Project Management RESPONSE TO REQUESTS FOR ADDITIONAL INFORMATION NO. 2 UNI'I' SALEM NUCLEAR GENERATING STATION DOCKET NO. 50-3ll Public Service Electric and Gas Company hereby transmits sixty (60) copies to your request for additional information related to the report "Structural Integrity Test of Containment" submitted on March 30, 1979.
In addition, is sixty (60).copies of valve data for the 36" and 10" valves associated with the Containment Purge and Pressure Vacuum Relief System (Q5.66).
Should you have any questions, please do not hesitate to contact us.
Enclosure The Energy People Very.truly yours, RI#~
R. L. Mittl General Manager -
Licensing and Environment Engineering and Construction 79050405\\9 95-2001 (400M) 9-77
J t
Request for Additional Information on SIT Report Question:
Page 2-9 of the Report said that liquid penetrant and/or magnetic particle inspection of the weld was performed.
The new Regulatory Guide does not permit the use of liquid penetrant method, please explain.
Response
The liner plate seam welds in the cylindrical walls and dome were radiographic inspected.
In the bottom liner plate where the seams are directly over the embeded struc-tural tees, radiographic inspection of the weld could not be conducted.
These bottom plate welds were 1003 vacuum box tested to 5 psi differential pressure.
Magnetic particle inspection was used as the weld qualification.
The alternate method of liquid penetrant was only used in areas inaccessible for magnetic particle inspection.
We have requested our Q.A. Department to make a random check on their file regarding the bottom liner plate weld inspection.
All the inspection record they have checked were made by the magnetic particle process.
Question:
On Fig. 5-15 of the report, the crack photos at 47 and 54 psig, one of the cracks exhibits a double line.
Is it one crack or two cracks adjacent to each other?
Response
It is a single crack with black markings at edges of the crack.
Question:
On Fig. 5-18 of the report, the last sentence at the bottom of the page says:
"Post test at zero psig, no resid~al width".
Does that mean the crack is closed altogether?
Response
The residual crack width is defined as the residual width of new cracks or increased width of the existing cracks after containment pressure is reduced to atmosphere.
The questioned crack has a pretest crack width of.015".
When pressure returned to zero after the pressure test, the subject crack measured.015", which is the same as the ori-ginal crack.
Our statement of no residual width is meant to be no increase in crack width from the pretest crack.
SJT-1
11 QUESTION:
How do you predict crack width?
RESPONSE
Crack width was predicted based on the maximwn expected stress and strain of the reinforcing steel during the pressure test.
The reference paper is "Crack width and crack spacing in Reinforced Concrete Members "by Bengt B. Broms, ACI Journal, 1965.
QUESTION:
Page 7 -
6 of the Report said three (3) strain gages were not functioning properly, what is the effect of the strain readings?
RESPONSE
Each set of strain gages consist of four gages attached at each face of the rebar (90° apart).
Normally the strain reading for the particular rebar location is the average of the four gages.
The three (3) gages that were not functioning properly were in three different sets.
The strain reading for these three sets were based on the average of three gages instead of the regular four, omitting the reading of the non-functioning gage.
QUESTION:
Liner rosette R 17 measured a rnaximwn principal stress of 39,483 psi.
How does it behave?
RESPONSE
Liner plate A 442 Grade 60 has a minimum guaranteed yield stress of 32,000 psi.
However, the actual yield stress is usually higher than that value.
We have plotted the stress measurements in the decompression stages (Table 5-1.C) for rosettes No. 2, No. 17 and No. 19 to see if the elastic behavior for R 17 is still maintained.
Rosette No. 17 in question showed a faster rate of stress reduction than the other two that staged within the minimtim yield stress.
We have concluded the material monitored by R 17 was still in the elastic range.
QUESTION:
Which crack has a residual crack width exceeded.02" and "by how much?
How deep?
RESPONSE
The crack is in area No. 9, coordinate M 3 as listed in Table 5 -
6.d.
The residual crack was.04" wide and only six inches long.
After chipped out the entire length of the crack to a depth of 1/8" to ~", the crack width measured.005" to.015" maximum.
RWS:kd SIT-Z.
~----------------------------"
F.
~:'
\\1 CONTROL VENTILATION ISOLATION VALVE DATA
- 1.
Assurance of Rat~d Vane Rotation (90 Degree)
The Bettis Actuator bas an external adjusting screw in the end of each cylinder, for adjustment of angular rotart output of the actuator.
These stops vere factory 1et by Masoneilan to li~it rotation to 90 degree during bench test.
The bench test was performed on the assembled valve and actuator as outlined on Drawing M-6696 (Valve Control System) and APS 1515 (Inspection and Test Procedures).
Test were witnessed and approved by the customer source inspec-tcr.
One (1) co~plete 36" valve and Jettis Actuator was seismic vibration tested by the Acton Environmental Testing Corporation, Acton, Mass.
Their test Report No. 11262, dated 10/24/75 in-dicated no evidence of mechanical damage or deterioration as a result of seismic vibration test; and noted the valve operated properly before, during and after the simulated seismic event.
- 2.
Assurance of sufficient Actuator Torque conditions:
Air supply is 100 PSI Angle of opening is 90 degrees Max Delta P at LOCA is 60 PSI Tcrque required for Delta P 60 is 27,000 in/lbs. (based on Masoneilan Test Data and experience).
36" Valve Data Available Torque Bettis Actuator:
10" Valve Data Available Torque Bettis Actuator:
(Torque required for Delta P 60 equals 1390 in/lbs.)
- Bettis Corp. Telex dated 4/3/79.
On the basis of tbe above data the available Actuator Torque la well in excess of the requl_re~_~orque to operate the yalTe.
l