ML18096B215: Difference between revisions
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
||
| Line 17: | Line 17: | ||
=Text= | =Text= | ||
{{#Wiki_filter:Public Service Electric and Gas | {{#Wiki_filter:Public Service Electric and Gas | ||
* Stanley LaBruna Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-120Q Vice President | * Company Stanley LaBruna Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-120Q Vice President - Nuclear Operations JAN 2 1 *1993 NLR-N92124 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen: | ||
-Nuclear Operations JAN 2 1 *1993 NLR-N92124 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen: | REQUEST FOR AMENDMENT REACTIVITY CONTROL SYSTEMS. | ||
REQUEST FOR AMENDMENT REACTIVITY CONTROL SYSTEMS. SALEM GENERATING STATION UNIT NOS. 1 AND 2 FACILITY OPERATING LICENSES NOS. DPR-70 AND DPR-75 DOCKET NOS. 50-272 AND 50-311 In accordance with the*requirements of 10CFR50.90, Public Service Electric and Gas Company (PSE&G) hereby transmits a request for amendment of Facility Operating Licenses DPR-70 and DPR-75 for Salem Generating Station, Units Nos 1 and 2, respectively. | SALEM GENERATING STATION UNIT NOS. 1 AND 2 FACILITY OPERATING LICENSES NOS. DPR-70 AND DPR-75 DOCKET NOS. 50-272 AND 50-311 In accordance with the*requirements of 10CFR50.90, Public Service Electric and Gas Company (PSE&G) hereby transmits a request for amendment of Facility Operating Licenses DPR-70 and DPR-75 for Salem Generating Station, Units Nos 1 and 2, respectively. In accordance with 10CFR50.91 (b) (1) requirements, a copy of this request has been sent to the State of New Jersey. | ||
In accordance with 10CFR50.91 (b) (1) requirements, a copy of this request has been sent to the State of New Jersey. The proposed amendment modifies Technical Specification 3/4.1.1 Reactivity Control Systems -Boration Control -Shutdown Margin T > 200°F Surveillance Requirements. | The proposed amendment modifies Technical Specification 3/4.1.1 Reactivity Control Systems - Boration Control - Shutdown Margin T > 200°F Surveillance Requirements. The proposed change p~Z~ides clarification of the method of shutdown margin verifications. | ||
The proposed change clarification of the method of shutdown margin verifications. | I Attachment 1 includes a description, reason, justification and significant hazards analysis for the proposed change. | ||
I Attachment 1 includes a description, reason, justification and significant hazards analysis for the proposed change. Attachment 2 contains the Technical Specification pages revised with pen and ink changes. PSE&G is requesting a 60 day implementation period after amendment approval. | Attachment 2 contains the Technical Specification pages revised with pen and ink changes. | ||
280033 ./---930l"2'90202-*9ao12r | PSE&G is requesting a 60 day implementation period after amendment approval. | ||
------1 PDR ADOCK 05000272 P PDR | 280033 | ||
*.*' Document Control Desk NLR-N92124 | ./-- -930l"2'90202-*9ao12r - ----- | ||
1 PDR ADOCK 05000272 P PDR | |||
-Nuclear Operations of Public Service Electric and Gas .company, and | |||
*.*' | |||
\ ' Attachment 1 NLR-N92124 LCR 92-06 REACTIVITY CONTROL SYSTEMS BORATION CONTROL -SHUTDOWN MARGIN -T >200°F Description of Change Modify Technical Specification 3/4 .. 1.1, Boration Control, as indicated to clarify the method of performing Shutdown Margin verifications in Modes 1 and 2. Change Surveillance Requirement 4.1.1.1.lb. | Document Control Desk 2 JAN 211993 NLR-N92124 Should there be any questions with regard to this submittal, please do not hesitate to contact us. | ||
to read: When in MODE 1 or MODE 2 with K greater than or equal to 1.0, at least once hours by verifying that control bank withdrawal is within limits of Specification 3.1.3.5. ** Change Surveillance Requirement to read: When in MODE 2 with K f less than 1.0, within 4 hours prior to achieving criticality by verifying that the predicted critical control rod position is within the limits of specification 3.1.3.5. ** At bottom of page, add notation ** to read: During performance of testing under Special Test Exception 3.10.2 and 3.10.3, calculation of Shutdown Margin considering power level and the factors of Surveillance requirement 4.1.1.1.le shall be performed at least once per 12 hours. For Unit 1, at the bottom of the page, Delete notation # and notation ##. II. Reason and Justification for Change Surveillances 4.1.1.1.lb and 4.1.Ll.lc require shtitdown margin to be verified by maintaining control rods within the rod insertion limits of specification 3.1.3.5. During performance of control rod worth measurements, it is not possible to verify shutdown margin by rod insertion limits. Adequate shutdown margin can be verified by calculation methods as identified in surveillances 4.1.1.1.ld and 4.1.1.1.le. | Sincerely, | ||
Performing shutdown margin calculations during control rod worth measurements does not alter the normal operation of the facility. | ~~ | ||
NLR-N92124 | c Mr. J. c. Stone Licensing Project Manager Mr. T. Johnson Senior Resident Inspector Mr. T. Martin, Administrator Region I Mr. Kent Tosch, Chief New Jersey Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625 | ||
Notations | |||
# and ## are deleted from Unit 1 specifications because the information concerning K ff is now contained in the surveillance requirements. | REF: NLR-N92124 STATE OF NEW JERSEY SS. | ||
e III. Significant Hazards Consideration In accordance with 10CFR50.92, PSE&G has reviewed the proposed changes and concluded the proposed changes do not involve a significant hazards consideration because the changes would not: 1. Involve a significant increase in the probability or consequences of an accident previously analyzed. | COUNTY OF SALEM | ||
The proposed changes clarify the method of verifying that the shutdown margin is within limits during control rod worth measurements. | : s. LaBruna, being duly sworn according to law deposes and says: | ||
Deletion of the notations for k ff for Unit 1 is an administrative change to incluae the information within the specific surveillance requirement. | I am Vice President - Nuclear Operations of Public Service Electric and. | ||
The proposed changes do not alter the normal operation of the facility. | Gas .company, | ||
Therefore, these changes would not increase the probability or consequences of a previously analyzed accident. | . | ||
and as such, I find the matters set forth :in the above | |||
- | |||
referenced | |||
. | |||
letter, concerning the Salem | |||
. ' : . | |||
Generating Station, Unit Nos. 1 and 2, are true to the best of my knowledge, information and belief. | |||
Subscribed this cli/st 1993 KIMBERLY A. HILL | |||
- 'I NOTARY PUBLIC qF NEW JERSEY My Commission Expires March 9, 1997 | |||
~y*commission expires on | |||
''* --------------- | |||
\ ' | |||
Attachment 1 NLR-N92124 LCR 92-06 REACTIVITY CONTROL SYSTEMS BORATION CONTROL - SHUTDOWN MARGIN - T >200°F | |||
~ Description of Change Modify Technical Specification 3/4.. 1.1, Boration Control, as indicated to clarify the method of performing Shutdown Margin verifications in Modes 1 and 2. | |||
Change Surveillance Requirement 4.1.1.1.lb. to read: | |||
When in MODE 1 or MODE 2 with K greater than or equal to 1.0, at least once peref~ hours by verifying that control bank withdrawal is within limits of Specification 3.1.3.5. ** | |||
Change Surveillance Requirement 4.1.1.l~lc. to read: | |||
When in MODE 2 with K f less than 1.0, within 4 hours prior to achieving re~ctor criticality by verifying that the predicted critical control rod position is within the limits of specification 3.1.3.5. ** | |||
At bottom of page, add notation ** to read: | |||
During performance of testing under Special Test Exception 3.10.2 and 3.10.3, calculation of Shutdown Margin considering power level and the factors of Surveillance requirement 4.1.1.1.le shall be performed at least once per 12 hours. | |||
For Unit 1, at the bottom of the page, Delete notation # and notation ##. | |||
II. Reason and Justification for Change Surveillances 4.1.1.1.lb and 4.1.Ll.lc require shtitdown margin to be verified by maintaining control rods within the rod insertion limits of specification 3.1.3.5. During performance of control rod worth measurements, it is not possible to verify shutdown margin by rod insertion limits. | |||
Adequate shutdown margin can be verified by calculation methods as identified in surveillances 4.1.1.1.ld and 4.1.1.1.le. Performing shutdown margin calculations during control rod worth measurements does not alter the normal operation of the facility. | |||
NLR-N92124 The addition of the note will allow the flexibility to perform the calculations necessary to verify the shutdown margin and satisfy the surveillance without any significant hazards increase. | |||
Notations # and ## are deleted from Unit 1 specifications because the information concerning K ff is now contained in the surveillance requirements. e III. Significant Hazards Consideration In accordance with 10CFR50.92, PSE&G has reviewed the proposed changes and concluded the proposed changes do not involve a significant hazards consideration because the changes would not: | |||
: 1. Involve a significant increase in the probability or consequences of an accident previously analyzed. | |||
The proposed changes clarify the method of verifying that the shutdown margin is within limits during control rod worth measurements. Deletion of the notations for k ff for Unit 1 is an administrative change to incluae the information within the specific surveillance requirement. The proposed changes do not alter the normal operation of the facility. Therefore, these changes would not increase the probability or consequences of a previously analyzed accident. | |||
: 2. Create the possibility of a new or different kind of accident. | : 2. Create the possibility of a new or different kind of accident. | ||
The proposed changes clarify the method of verifying that the shutdown margin is within limits during control rod worth measurements. | The proposed changes clarify the method of verifying that the shutdown margin is within limits during control rod worth measurements. The proposed changes do not alter the normal operation of the facility. | ||
The proposed changes do not alter the normal operation of the facility. | Deletion of the notations for k fr for Unit 1 is an administrative change to includ~ ehe information within the specific surveillance requirement. Therefore, these changes would not create the possibility of a new or different kind of accident. | ||
Deletion of the notations for k fr for Unit 1 is an administrative change to ehe information within the specific surveillance requirement. | |||
Therefore, these changes would not create the possibility of a new or different kind of accident. | -~- | ||
-- | NLR-N92124 3. Involve a significant reduction in a margin of safety. | ||
The proposed changes do not alter the normal operation of the facility. | The proposed changes clarify the method of verifying that the shutdown margin is within limits during control rod worth measurements. The proposed changes do not alter the normal operation of the facility. | ||
Deletion of the* notations for k ff for Unit 1 is an administrative change to ehe information within the specific surveillance requirement. | Deletion of the* notations for k ff for Unit 1 is an administrative change to includ~ ehe information within the specific surveillance requirement. Therefore, these changes would not involve a significant reduction in a margin of safety. | ||
Therefore, these changes would not involve a significant reduction in a margin of safety. IV. Conclusions Based on the information presented above, PSE&G has concluded there is no significant hazards consideration.}} | IV. Conclusions Based on the information presented above, PSE&G has concluded there is no significant hazards consideration.}} | ||
Revision as of 10:04, 21 October 2019
| ML18096B215 | |
| Person / Time | |
|---|---|
| Site: | Salem |
| Issue date: | 01/21/1993 |
| From: | Labruna S Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML18096B216 | List: |
| References | |
| NLR-N92124, NUDOCS 9301290202 | |
| Download: ML18096B215 (6) | |
Text
Public Service Electric and Gas
- Company Stanley LaBruna Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-120Q Vice President - Nuclear Operations JAN 2 1 *1993 NLR-N92124 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
REQUEST FOR AMENDMENT REACTIVITY CONTROL SYSTEMS.
SALEM GENERATING STATION UNIT NOS. 1 AND 2 FACILITY OPERATING LICENSES NOS. DPR-70 AND DPR-75 DOCKET NOS. 50-272 AND 50-311 In accordance with the*requirements of 10CFR50.90, Public Service Electric and Gas Company (PSE&G) hereby transmits a request for amendment of Facility Operating Licenses DPR-70 and DPR-75 for Salem Generating Station, Units Nos 1 and 2, respectively. In accordance with 10CFR50.91 (b) (1) requirements, a copy of this request has been sent to the State of New Jersey.
The proposed amendment modifies Technical Specification 3/4.1.1 Reactivity Control Systems - Boration Control - Shutdown Margin T > 200°F Surveillance Requirements. The proposed change p~Z~ides clarification of the method of shutdown margin verifications.
I Attachment 1 includes a description, reason, justification and significant hazards analysis for the proposed change.
Attachment 2 contains the Technical Specification pages revised with pen and ink changes.
PSE&G is requesting a 60 day implementation period after amendment approval.
280033
./-- -930l"2'90202-*9ao12r - -----
- .*'
Document Control Desk 2 JAN 211993 NLR-N92124 Should there be any questions with regard to this submittal, please do not hesitate to contact us.
Sincerely,
~~
c Mr. J. c. Stone Licensing Project Manager Mr. T. Johnson Senior Resident Inspector Mr. T. Martin, Administrator Region I Mr. Kent Tosch, Chief New Jersey Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625
REF: NLR-N92124 STATE OF NEW JERSEY SS.
COUNTY OF SALEM
- s. LaBruna, being duly sworn according to law deposes and says:
I am Vice President - Nuclear Operations of Public Service Electric and.
Gas .company,
.
and as such, I find the matters set forth :in the above
-
referenced
.
letter, concerning the Salem
. ' : .
Generating Station, Unit Nos. 1 and 2, are true to the best of my knowledge, information and belief.
Subscribed this cli/st 1993 KIMBERLY A. HILL
- 'I NOTARY PUBLIC qF NEW JERSEY My Commission Expires March 9, 1997
~y*commission expires on
* ---------------
\ '
Attachment 1 NLR-N92124 LCR 92-06 REACTIVITY CONTROL SYSTEMS BORATION CONTROL - SHUTDOWN MARGIN - T >200°F
~ Description of Change Modify Technical Specification 3/4.. 1.1, Boration Control, as indicated to clarify the method of performing Shutdown Margin verifications in Modes 1 and 2.
Change Surveillance Requirement 4.1.1.1.lb. to read:
When in MODE 1 or MODE 2 with K greater than or equal to 1.0, at least once peref~ hours by verifying that control bank withdrawal is within limits of Specification 3.1.3.5. **
Change Surveillance Requirement 4.1.1.l~lc. to read:
When in MODE 2 with K f less than 1.0, within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> prior to achieving re~ctor criticality by verifying that the predicted critical control rod position is within the limits of specification 3.1.3.5. **
At bottom of page, add notation ** to read:
During performance of testing under Special Test Exception 3.10.2 and 3.10.3, calculation of Shutdown Margin considering power level and the factors of Surveillance requirement 4.1.1.1.le shall be performed at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
For Unit 1, at the bottom of the page, Delete notation # and notation ##.
II. Reason and Justification for Change Surveillances 4.1.1.1.lb and 4.1.Ll.lc require shtitdown margin to be verified by maintaining control rods within the rod insertion limits of specification 3.1.3.5. During performance of control rod worth measurements, it is not possible to verify shutdown margin by rod insertion limits.
Adequate shutdown margin can be verified by calculation methods as identified in surveillances 4.1.1.1.ld and 4.1.1.1.le. Performing shutdown margin calculations during control rod worth measurements does not alter the normal operation of the facility.
NLR-N92124 The addition of the note will allow the flexibility to perform the calculations necessary to verify the shutdown margin and satisfy the surveillance without any significant hazards increase.
Notations # and ## are deleted from Unit 1 specifications because the information concerning K ff is now contained in the surveillance requirements. e III. Significant Hazards Consideration In accordance with 10CFR50.92, PSE&G has reviewed the proposed changes and concluded the proposed changes do not involve a significant hazards consideration because the changes would not:
- 1. Involve a significant increase in the probability or consequences of an accident previously analyzed.
The proposed changes clarify the method of verifying that the shutdown margin is within limits during control rod worth measurements. Deletion of the notations for k ff for Unit 1 is an administrative change to incluae the information within the specific surveillance requirement. The proposed changes do not alter the normal operation of the facility. Therefore, these changes would not increase the probability or consequences of a previously analyzed accident.
- 2. Create the possibility of a new or different kind of accident.
The proposed changes clarify the method of verifying that the shutdown margin is within limits during control rod worth measurements. The proposed changes do not alter the normal operation of the facility.
Deletion of the notations for k fr for Unit 1 is an administrative change to includ~ ehe information within the specific surveillance requirement. Therefore, these changes would not create the possibility of a new or different kind of accident.
-~-
NLR-N92124 3. Involve a significant reduction in a margin of safety.
The proposed changes clarify the method of verifying that the shutdown margin is within limits during control rod worth measurements. The proposed changes do not alter the normal operation of the facility.
Deletion of the* notations for k ff for Unit 1 is an administrative change to includ~ ehe information within the specific surveillance requirement. Therefore, these changes would not involve a significant reduction in a margin of safety.
IV. Conclusions Based on the information presented above, PSE&G has concluded there is no significant hazards consideration.