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{{#Wiki_filter:Public Service Electric and Gas Company, Stanley LaBruna Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-1200 | {{#Wiki_filter:Public Service Electric and Gas Company, Stanley LaBruna Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-1200 Vice President | ||
Vice President | -Nu_clear Operations | ||
-Nu_clear Operations | * AUG 1 O 1992 NLR-N92100 United States Nuclear Regulatory Commission Document Control Desk Was.hington, DC 20555 Gentlemen: | ||
* AUG 1 O 1992 NLR-N92100 | RESPONSE TO NOTICE OF VIOLATION NRC INSPECTION REPORT NOS. 50-272/92-07, 50-311/92-07, 50-354/92-06 DOCKET NOS. 50-272 I 50-3_11 AND 50-354 Public Service Electric and. Gas (PSE&G) has received the Inspection Report dated' July 2, 1992. Within the scope of this inspection, one apparent violation of NRC requirements was identified (VIO 272 and 311/92-07-02) | ||
United States Nuclear Regulatory | The violation concerns the failure to adequately assess and provide information relative to the on-site storage of ammonium hydroxide and its potential effect on control room habitability as required by a July 10, 1981 NRC Order. Pursuant to.the requirements of 10 CFR 2.201, PSE&G hereby submits its response to the notice of violation. | ||
Commission | * Should you have any questions in regard to this.transmittal, qo not hesitate to call. Attachment 920010 05000272 PDR Sincerely, | ||
Document Control Desk Was.hington, DC 20555 Gentlemen: | .Document Control Desk NLR-N92100 2* c Mr. T. T. Martin, Administrator | ||
RESPONSE TO NOTICE OF VIOLATION | -Region I. u. S.; Nuclear Regulatory Commission. | ||
NRC INSPECTION | 475 Allendale Road King of Prussia, PA 19406 Mr. J. C. Stone, Licensing Project Manager u. s. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852 Ms. A. *Keller u. s. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852 Mr. T. P. Johnson (509) USNRC Senior Resident Inspector | ||
REPORT NOS. 50-272/92-07, 50-311/92-07, 50-354/92-06 | * Mr. K. Tosch, Chief NJ Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625 AUG 1 O 1992 | ||
DOCKET NOS. 50-272 I 50-3_11 AND 50-354 Public Service Electric and. Gas (PSE&G) has received the Inspection | * Document Control Desk NLR-N92100 ATTACHMENT As a result of the inspection at Salem Station during December 16-20, 1991, and in accordancewith the "General Statement of .Policy and Procedure forNRC Enforcement Actions," 10 CFR Part 2, Appendix C (1992), the following violation was identified: | ||
Report dated' July 2, 1992. Within the scope of this inspection, one apparent violation | On July 10, 1981, an Order Confirming Licensee Commitments on Post-TM! Related Issues was issued to PSE&G. Section IV of the Order stated in part, "IT IS HEREBY ORDERED EFFECTIVE IMMEDIATELY THAT the licensee shall comply with the following conditions: | ||
of NRC requirements | The licensee shall.satisfy the specific requirements described in. the Attachment to this Order (as appropriate to the licensee's facility) as early as practicable but no later than 60 days after the effective date of the The Attachment to the Order provided specific requirements for, among other matters, NUREG-0737 Item III.D.3.4, Control Room -Habitability. | ||
was identified (VIO 272 and 311/92-07-02) | The Attachment to the Order required that the 'licensee submit, by January 1, 1981, a control room habitability evaluation meeting the requirements of NUREG-0737 Item III.D.3.4. | ||
The violation | Contrary to the above, PSE&G failed to satisfy the specific requirements of NUREG-0737 Item III.D.3.4 in that, as of September 13, 1991, PSE&G failed to evaluate the potential impact, relative to NUREG-0737 Item III.D.3.4, of a release* of ammonium hydroxide from transfer to and storage in a 3000 gallon storage tank located o.n the | ||
concerns the failure to adequately | * 12 O foot elevation of the Unit 1 Turbine Building, on control room habitability. | ||
assess and provide information | In addition, PSE&G's responses dated July 1, 1980 and August 13, 1980, submitted in response to NUREG-0737 Item III.D.3.4, failed to provide information relative to the presence of ammonium hydroxide. | ||
relative to the on-site storage of ammonium hydroxide | PSE&G DOES NOT DISPUTE THE VIOLATION ROOT CAUSE The root cause was to inadequate depth of evaluation. | ||
and its potential | A contributfng cause was inadequate documentation of analysis. | ||
effect on control room habitability | Salem Unit 1 FSAR was approved and an operating license issued with no commitment to the then recently issued Regulatory Guide 1. 78 * | ||
as required by a July 10, 1981 NRC Order. Pursuant to.the requirements | * Document Control Desk NLR-N92100 In the process of licensing Saiem Unit 2, an-assessment was made on compliance to Regulatory Guide 1.78. An internal memorandum, -dated September 14, 1977, qualitatively evaluated several chemicals, including ammonium hydroxide, for impact on control room habitability. | ||
of 10 CFR 2.201, PSE&G hereby submits its response to the notice of violation. | It was concluded at that time (September 14, 1977), that since ammonium hydroxide was not listed in Regulatory Guide 1.78 nor its reference | ||
* Should you have any questions | :documents, it was not considered a hazardous chemical concern for control room habitability. | ||
in regard to this.transmittal, qo not hesitate to call. Attachment | In responding to TMI Action Item III.D.3.4 the previous qualitative evaluation of September 14, 1977 and additional assessments, were used to support PSE&G's responses dated July 1, 1980 and August 13, 1980. -As a result of evaluations conducted in the fall of 199i, it was -concluded, that even though ammonium hydroxide is a dilute liquid, ammonia gas could evolve from spilled ammonium hydroxide under postulated accident conditions. | ||
920010 05000272 PDR Sincerely, | Therefore, a postulated accident of ammonium hydroxide storage was evaluated for impact on control room habitability. | ||
.Document | CORRECTIVE ACTIONS TAKEN Upon notification of the discrepancy, a preliminary safety assessment was conducted using the computer code "CHARM", and a site survey performed for identification of any additional* | ||
Control Desk NLR-N92100 | potentially hazardous chemicals. | ||
2* c Mr. T. T. Martin, Administrator | The preliminary "CHARM".results concluded that there was no impact on control room habitability from a postulated ammonium hydroxide accident. | ||
-Region I. u. S.; Nuclear Regulatory | In order _to provide a timely response for a final safety evaluation, a different computer code "VAPOR'' was used because "CHARM" was not validated and verified to PSE&G software requirements. | ||
Commission. | PSE&G used the "VAPOR" code for the safety evaluation because its software had been documented and verified to comply with appropriate QA requirements for use in "important to safety" evaluations. | ||
475 Allendale | As a result of finalizing the safety evaluation for control room habitability using the "VAPOR" computer code; additional actions were taken to address the analysis conclusion | ||
Road King of Prussia, PA 19406 Mr. J. C. Stone, Licensing | *that the toxic limit in the control *room may be exceeded. | ||
Project Manager u. s. Nuclear Regulatory | The immediate compensatory measures included placing a temperature indicator and strip chart recorder in the storage tank area, limiting the amount of ammonium hydroxide volume stored, performed an engineering evaluation and subsequently reduced the concentration of ammonium hydroxide used at Salem to 15 wt%, and initiating precautionary administrative controls for tanker truck deliveries. | ||
Commission | * | ||
One White Flint North 11555 Rockville | * Document Control Desk NLR-N92100 A preliminary analysis was conducted for the two additional chemicals, hydrazine and sodium hydroxide, -identified as a *result of the site survey.* The preliminary assessment resulted in chemical concentrations within the control room that did not | ||
Pike Rockville, MD 20852 Ms. A. *Keller u. s. Nuclear Regulatory | * exceed the toxic limits provided in authoritative sources. -Therefore, it was concluded there.would be no impact on control room habitability as* a result of a postulated accident regarding either hydrazine or sodium hydroxide. | ||
Commission | -During the approval cycle for the control room habitability calculation, PSE&G questioned the "VAPOR" model assumptions and design input and determined they were very conservative. | ||
One White Flint North 11555 Rockville | As a result, the "CHARM" model was validated*and verified and used to complete the final evaluations. | ||
Pike Rockville, MD 20852 Mr. T. P. Johnson (509) USNRC Senior Resident Inspector | The additional evaluations used .NRC regulatory criteria in the validated and verified "CHARM 1 i computer code for the postulated accidents for both 27.5 and 15 wt.% ammonium hydroxide storage tank concentrations. | ||
* Mr. K. Tosch, Chief NJ Department | * The evaluations, utilizing the "CHARM" code model, concluded that the Regulatory Guide .1.78 toxic limit for anhydrous ammonia, based on the concentration that can be tolerated for two minutes, will not be exceeded in the control room during a postulated release at the*tank containing either 27.5 wt% or 15 .wt.% ammonium hydroxide. | ||
of Environmental | since the concentration of ammonium hydroxide was reduced, the .amount of deliveries on an annual basis, was anticipated to exceed the frequency threshold value for truck traffic of ten per year per Regulatory Guide 1.78. When the frequency criteria are applicable, Regulatory Guide 1.78 requires evaluation of the shipments for impact on control room habitability. | ||
Protection | Therefore, included in the additional evaluations were postulated accidents to tanker delivery trucks containing 15 wt.% ammonium hydroxide at the site main access point and.Salem unloading dock. A final evaluation of the two additional chemicals was conducted using the validated and verified "CHARM" computer code for hydrazine and a quaiitative analysis for sodium hydroxide. | ||
Division of Environmental | The final evaluation confirmed the preliminary assessment that control room habitability would not be impacted. | ||
Quality Bureau of Nuclear Engineering | |||
CN 415 Trenton, NJ 08625 AUG 1 O 1992 | |||
* Document Control Desk NLR-N92100 | |||
ATTACHMENT | |||
As a result of the inspection | |||
at Salem Station during December 16-20, 1991, and in accordancewith | |||
the "General Statement | |||
of .Policy and Procedure | |||
forNRC Enforcement | |||
Actions," 10 CFR Part 2, Appendix C (1992), the following | |||
violation | |||
was identified: | |||
On July 10, 1981, an Order Confirming | |||
Licensee Commitments | |||
on Post-TM! Related Issues was issued to PSE&G. Section IV of the Order stated in part, "IT IS HEREBY ORDERED EFFECTIVE | |||
IMMEDIATELY | |||
THAT the licensee shall comply with the following | |||
conditions: | |||
The licensee shall.satisfy | |||
the specific requirements | |||
described | |||
in. the Attachment | |||
to this Order (as appropriate | |||
to the licensee's | |||
facility) | |||
as early as practicable | |||
but no later than 60 days after the effective | |||
date of the | |||
The Attachment | |||
to the Order provided specific requirements | |||
for, among other matters, NUREG-0737 | |||
Item III.D.3.4, Control Room -Habitability. | |||
The Attachment | |||
to the Order required that the 'licensee | |||
submit, by January 1, 1981, a control room habitability | |||
evaluation | |||
meeting the requirements | |||
of NUREG-0737 | |||
Item III.D.3.4. | |||
Contrary to the above, PSE&G failed to satisfy the specific requirements | |||
of NUREG-0737 | |||
Item III.D.3.4 | |||
in that, as of September | |||
13, 1991, PSE&G failed to evaluate the potential | |||
impact, relative to NUREG-0737 | |||
Item III.D.3.4, of a release* of ammonium hydroxide | |||
from transfer to and storage in a 3000 gallon storage tank located o.n the * 12 O foot elevation | |||
of the Unit 1 Turbine Building, on control room habitability. | |||
In addition, PSE&G's responses | |||
dated July 1, 1980 and August 13, 1980, submitted | |||
in response to NUREG-0737 | |||
Item III.D.3.4, failed to provide information | |||
relative to the presence of ammonium hydroxide. | |||
PSE&G DOES NOT DISPUTE THE VIOLATION | |||
ROOT CAUSE The root cause was | |||
to inadequate | |||
depth of evaluation. | |||
A contributfng | |||
cause was inadequate | |||
documentation | |||
of analysis. | |||
Salem Unit 1 FSAR was approved and an operating | |||
license issued with no commitment | |||
to the then recently issued Regulatory | |||
Guide 1. 78 * | |||
* Document Control Desk NLR-N92100 | |||
In the process of licensing | |||
Saiem Unit 2, an-assessment | |||
was made on compliance | |||
to Regulatory | |||
Guide 1.78. An internal memorandum, -dated September | |||
14, 1977, qualitatively | |||
evaluated | |||
several chemicals, including | |||
ammonium hydroxide, for impact on control room habitability. | |||
It was concluded | |||
at that time (September | |||
14, 1977), that since ammonium hydroxide | |||
was not listed in Regulatory | |||
Guide 1.78 nor its reference | |||
:documents, it was not considered | |||
a hazardous | |||
chemical concern for control room habitability. | |||
In responding | |||
to TMI Action Item III.D.3.4 | |||
the previous qualitative | |||
evaluation | |||
of September | |||
14, 1977 and additional | |||
assessments, were used to support PSE&G's responses | |||
dated July 1, 1980 and August 13, 1980. -As a result of evaluations | |||
conducted | |||
in the fall of 199i, it was -concluded, that even though ammonium hydroxide | |||
is a dilute liquid, ammonia gas could evolve from spilled ammonium hydroxide | |||
under postulated | |||
accident conditions. | |||
Therefore, a postulated | |||
accident of ammonium hydroxide | |||
storage was evaluated | |||
for impact on control room habitability. | |||
CORRECTIVE | |||
ACTIONS TAKEN Upon notification | |||
of the discrepancy, a preliminary | |||
safety assessment | |||
was conducted | |||
using the computer code "CHARM", and a site survey performed | |||
for identification | |||
of any additional* | |||
potentially | |||
hazardous | |||
chemicals. | |||
The preliminary "CHARM".results | |||
concluded | |||
that there was no impact on control room habitability | |||
from a postulated | |||
ammonium hydroxide | |||
accident. | |||
In order _to provide a timely response for a final safety evaluation, a different | |||
computer code "VAPOR'' was used because "CHARM" was not validated | |||
and verified to PSE&G software requirements. | |||
PSE&G used the "VAPOR" code for the safety evaluation | |||
because its software had been documented | |||
and verified to comply with appropriate | |||
QA requirements | |||
for use in "important | |||
to safety" evaluations. | |||
As a result of finalizing | |||
the safety evaluation | |||
for control room habitability | |||
using the "VAPOR" computer code; additional | |||
actions were taken to address the analysis conclusion | |||
*that the toxic limit in the control *room may be exceeded. | |||
The immediate | |||
compensatory | |||
measures included placing a temperature | |||
indicator | |||
and strip chart recorder in the storage tank area, limiting the amount of ammonium hydroxide | |||
volume stored, performed | |||
an engineering | |||
evaluation | |||
and subsequently | |||
reduced the concentration | |||
of ammonium hydroxide | |||
used at Salem to 15 wt%, and initiating | |||
precautionary | |||
administrative | |||
controls for tanker truck deliveries. | |||
* | |||
* Document Control Desk NLR-N92100 | |||
A preliminary | |||
analysis was conducted | |||
for the two additional | |||
chemicals, hydrazine | |||
and sodium hydroxide, -identified | |||
as a *result of the site survey.* The preliminary | |||
assessment | |||
resulted in chemical concentrations | |||
within the control room that did not * exceed the toxic limits provided in authoritative | |||
sources. -Therefore, it was concluded | |||
there.would | |||
be no impact on control room habitability | |||
as* a result of a postulated | |||
accident regarding | |||
either hydrazine | |||
or sodium hydroxide. | |||
-During the approval cycle for the control room habitability | |||
calculation, PSE&G questioned | |||
the "VAPOR" model assumptions | |||
and design input and determined | |||
they were very conservative. | |||
As a result, the "CHARM" model was validated*and | |||
verified and used to complete the final evaluations. | |||
The additional | |||
evaluations | |||
used .NRC regulatory | |||
criteria in the validated | |||
and verified "CHARM 1 i computer code for the postulated | |||
accidents | |||
for both 27.5 and 15 wt.% ammonium hydroxide | |||
storage tank concentrations. | |||
* The evaluations, utilizing | |||
the "CHARM" code model, concluded | |||
that the Regulatory | |||
Guide .1.78 toxic limit for anhydrous | |||
ammonia, based on the concentration | |||
that can be tolerated | |||
for two minutes, will not be exceeded in the control room during a postulated | |||
release at the*tank containing | |||
either 27.5 wt% or 15 .wt.% ammonium hydroxide. | |||
since the concentration | |||
of ammonium hydroxide | |||
was reduced, the .amount of deliveries | |||
on an annual basis, was anticipated | |||
to exceed the frequency | |||
threshold | |||
value for truck traffic of ten per year per Regulatory | |||
Guide 1.78. When the frequency | |||
criteria are applicable, Regulatory | |||
Guide 1.78 requires evaluation | |||
of the shipments | |||
for impact on control room habitability. | |||
Therefore, included in the additional | |||
evaluations | |||
were postulated | |||
accidents | |||
to tanker delivery trucks containing | |||
15 wt.% ammonium hydroxide | |||
at the site main access point and.Salem | |||
unloading | |||
dock. A final evaluation | |||
of the two additional | |||
chemicals | |||
was conducted | |||
using the validated | |||
and verified "CHARM" computer code for hydrazine | |||
and a quaiitative | |||
analysis for sodium hydroxide. | |||
The final evaluation | |||
confirmed | |||
the preliminary | |||
assessment | |||
that control room habitability | |||
would not be impacted. | |||
A qualitative | A qualitative | ||
-evaluation | -evaluation was conducted for sodium hydroxide because-of its high boiling point and very low volatility. | ||
was conducted | Under postulated accident conditions no credible. | ||
for sodium hydroxide | toxic airborne source can be determined. | ||
because-of | The short term corrective actions immediately implemented, that are currently in place, are the administrative controls for tanker truck deliveries and use of 15 wt.% concentration ammonium hydroxide. | ||
its high boiling point and very low volatility. | However, the "CHARM" code model evaluations support future use of 27.5 wt.% ammonium hydroxide, and the.elimination of both tank volume restrictions and continued temperature monitoring of the storage tank area. | ||
Under postulated | -Document Control Desk NLR-N92100 Administrative controls were instituted, per issuance of Chemistry procedure SC.CH-AD.z*z-0474, for the operators at Salem to isolate the control room when riotif ied that a tanker truck transporting ammonium hydroxide is*requesting site access for delivery.* | ||
accident conditions | The administrative controls also included notification of Hope Creek operators that an ammonium hydroxide delivery is being made for Salem. Evaluations, utilizing the "CHARM" code model, conclude that Regulatory Guide 1.78 toxic limits will *not be exceeded in the aope Creek control room therefore, *operator action is not required to isolate the control Operator training was conducted to identify.the odor of ammonia and ammonia was added to the annual olfactory recognition testing performed by the Medical Department on licensed | ||
no credible. | *An Abnormal Operating Procedure, SC.OP-AB.CR-0003(Q),. "Toxic Gas Release", was issued for Salem Generating Station to isolate the control room upon notification or detection by odor of ammonia in the control room. Hope Creek is also required to be notified. | ||
toxic airborne source can be determined. | A similar procedure for Hope Creek already existed. Changes to the Salem and Hope Creek UFSAR's have been completed that revise appropriate Sectio*ns to identify additional chemicals transported to and stored onsite, discuss the evaluations for control room habitability for these. additional cnemicals, and describe Salem's position on Regulatory Guide 1.78. The UFSAR changes will be incorporated in the next scheduled revision update. -CORRECTIVE ACTIONS TAKEN TO PREVENT RECURRENCE Procedure*NC.NA-AP.ZZ-0019(Q), "Procurement of Materials and Services" is being revised to limit the procurement of quantities of new chemicais to be brought onsite to less than 100 pound containers unless analyzed for their impact on control room habitability. | ||
The short term corrective | In the interim, direction on chemical procurement concerning toxic hazards*was provided by PSE&G memorandum, GM Nuclear Services to GM Procurement Material Control,. | ||
actions immediately | dated April 8, 1992. Nuclear Administrative Procedure NC.NA-AP.ZZ-0038(Q), "The Chemical Control Program", was revised to require review of chemicals for control room habitability before use. Procedure NC.DE-AP.ZZ-OOOl(Q), "Design Bases/Input", was revised to address the possible impact from hazardous chemicals, used in conjunction with or added by Design Changes, on control r.oom habitability. | ||
implemented, that are currently | ' , *. Document Control Desk NLR-N92100 In addition to the above specific changes, improvements to the engineering process have been implemented since the review and evaluation for* the original response to the TMI Action Item III.D.3.4. | ||
in place, are the administrative | Safety Evaluations (10CFR50.59) are more defined and comprehensive today to include nonsafety system interaction on safety systems such as the Chemical.Feed System using ammonium hydroxide. | ||
controls for tanker truck deliveries | Design Changes require a formalized design *bases/input process that include use of design considerations and specialty review checklists, interface record sheets, multiple . reviews including peer review in addition to independent design verification, and cross discipline and programmatic review. PSE&G .is in full compliance}} | ||
and use of 15 wt.% concentration | |||
ammonium hydroxide. | |||
However, the "CHARM" code model evaluations | |||
support future use of 27.5 wt.% ammonium hydroxide, and the.elimination | |||
of both tank volume restrictions | |||
and continued | |||
temperature | |||
monitoring | |||
of the storage tank area. | |||
-Document Control Desk NLR-N92100 | |||
Administrative | |||
controls were instituted, per issuance of Chemistry | |||
procedure | |||
SC.CH-AD.z*z-0474, for the operators | |||
at Salem to isolate the control room when riotif ied that a tanker truck transporting | |||
ammonium hydroxide | |||
is*requesting | |||
site access for delivery.* | |||
The administrative | |||
controls also included notification | |||
of Hope Creek operators | |||
that an ammonium hydroxide | |||
delivery is being made for Salem. Evaluations, utilizing | |||
the "CHARM" code model, conclude that Regulatory | |||
Guide 1.78 toxic limits will *not be exceeded in the aope Creek control room therefore, *operator | |||
action is not required to isolate the control | |||
Operator training was conducted | |||
to identify.the | |||
odor of ammonia and ammonia was added to the annual olfactory | |||
recognition | |||
testing performed | |||
by the Medical Department | |||
on licensed | |||
*An Abnormal Operating | |||
Procedure, SC.OP-AB.CR-0003(Q),. "Toxic Gas Release", was issued for Salem Generating | |||
Station to isolate the control room upon notification | |||
or detection | |||
by odor of ammonia in the control room. Hope Creek is also required to be notified. | |||
A similar procedure | |||
for Hope Creek already existed. Changes to the Salem and Hope Creek UFSAR's have been completed | |||
that revise appropriate | |||
Sectio*ns | |||
to identify additional | |||
chemicals | |||
transported | |||
to and stored onsite, discuss the evaluations | |||
for control room habitability | |||
for these. additional | |||
cnemicals, and describe Salem's position on Regulatory | |||
Guide 1.78. The UFSAR changes will be incorporated | |||
in the next scheduled | |||
revision update. -CORRECTIVE | |||
ACTIONS TAKEN TO PREVENT RECURRENCE | |||
Procedure*NC.NA-AP.ZZ-0019(Q), "Procurement | |||
of Materials | |||
and Services" is being revised to limit the procurement | |||
of quantities | |||
of new chemicais | |||
to be brought onsite to less than 100 pound containers | |||
unless analyzed for their impact on control room habitability. | |||
In the interim, direction | |||
on chemical procurement | |||
concerning | |||
toxic hazards*was | |||
provided by PSE&G memorandum, GM Nuclear Services to GM Procurement | |||
Material Control,. | |||
dated April 8, 1992. Nuclear Administrative | |||
Procedure | |||
NC.NA-AP.ZZ-0038(Q), "The Chemical Control Program", was revised to require review of chemicals | |||
for control room habitability | |||
before use. Procedure | |||
NC.DE-AP.ZZ-OOOl(Q), "Design Bases/Input", was revised to address the possible impact from hazardous | |||
chemicals, used in conjunction | |||
with or added by Design Changes, on control r.oom habitability. | |||
' , *. Document Control Desk NLR-N92100 | |||
In addition to the above specific changes, improvements | |||
to the engineering | |||
process have been implemented | |||
since the review and evaluation | |||
for* the original response to the TMI Action Item III.D.3.4. | |||
Safety Evaluations | |||
(10CFR50.59) | |||
are more defined and comprehensive | |||
today to include nonsafety | |||
system interaction | |||
on safety systems such as the Chemical.Feed | |||
System using ammonium hydroxide. | |||
Design Changes require a formalized | |||
design *bases/input | |||
process that include use of design considerations | |||
and specialty | |||
review checklists, interface | |||
record sheets, multiple . reviews including | |||
peer review in addition to independent | |||
design verification, and cross discipline | |||
and programmatic | |||
review. PSE&G .is in full compliance | |||
}} | |||
Revision as of 19:33, 31 July 2019
| ML18096A879 | |
| Person / Time | |
|---|---|
| Site: | Salem |
| Issue date: | 08/10/1992 |
| From: | Labruna S Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NLR-N92100, NUDOCS 9208140125 | |
| Download: ML18096A879 (7) | |
Text
Public Service Electric and Gas Company, Stanley LaBruna Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-1200 Vice President
-Nu_clear Operations
- AUG 1 O 1992 NLR-N92100 United States Nuclear Regulatory Commission Document Control Desk Was.hington, DC 20555 Gentlemen:
RESPONSE TO NOTICE OF VIOLATION NRC INSPECTION REPORT NOS. 50-272/92-07, 50-311/92-07, 50-354/92-06 DOCKET NOS. 50-272 I 50-3_11 AND 50-354 Public Service Electric and. Gas (PSE&G) has received the Inspection Report dated' July 2, 1992. Within the scope of this inspection, one apparent violation of NRC requirements was identified (VIO 272 and 311/92-07-02)
The violation concerns the failure to adequately assess and provide information relative to the on-site storage of ammonium hydroxide and its potential effect on control room habitability as required by a July 10, 1981 NRC Order. Pursuant to.the requirements of 10 CFR 2.201, PSE&G hereby submits its response to the notice of violation.
- Should you have any questions in regard to this.transmittal, qo not hesitate to call. Attachment 920010 05000272 PDR Sincerely,
.Document Control Desk NLR-N92100 2* c Mr. T. T. Martin, Administrator
-Region I. u. S.; Nuclear Regulatory Commission.
475 Allendale Road King of Prussia, PA 19406 Mr. J. C. Stone, Licensing Project Manager u. s. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852 Ms. A. *Keller u. s. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852 Mr. T. P. Johnson (509) USNRC Senior Resident Inspector
- Mr. K. Tosch, Chief NJ Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625 AUG 1 O 1992
- Document Control Desk NLR-N92100 ATTACHMENT As a result of the inspection at Salem Station during December 16-20, 1991, and in accordancewith the "General Statement of .Policy and Procedure forNRC Enforcement Actions," 10 CFR Part 2, Appendix C (1992), the following violation was identified:
On July 10, 1981, an Order Confirming Licensee Commitments on Post-TM! Related Issues was issued to PSE&G.Section IV of the Order stated in part, "IT IS HEREBY ORDERED EFFECTIVE IMMEDIATELY THAT the licensee shall comply with the following conditions:
The licensee shall.satisfy the specific requirements described in. the Attachment to this Order (as appropriate to the licensee's facility) as early as practicable but no later than 60 days after the effective date of the The Attachment to the Order provided specific requirements for, among other matters, NUREG-0737 Item III.D.3.4, Control Room -Habitability.
The Attachment to the Order required that the 'licensee submit, by January 1, 1981, a control room habitability evaluation meeting the requirements of NUREG-0737 Item III.D.3.4.
Contrary to the above, PSE&G failed to satisfy the specific requirements of NUREG-0737 Item III.D.3.4 in that, as of September 13, 1991, PSE&G failed to evaluate the potential impact, relative to NUREG-0737 Item III.D.3.4, of a release* of ammonium hydroxide from transfer to and storage in a 3000 gallon storage tank located o.n the
- 12 O foot elevation of the Unit 1 Turbine Building, on control room habitability.
In addition, PSE&G's responses dated July 1, 1980 and August 13, 1980, submitted in response to NUREG-0737 Item III.D.3.4, failed to provide information relative to the presence of ammonium hydroxide.
PSE&G DOES NOT DISPUTE THE VIOLATION ROOT CAUSE The root cause was to inadequate depth of evaluation.
A contributfng cause was inadequate documentation of analysis.
Salem Unit 1 FSAR was approved and an operating license issued with no commitment to the then recently issued Regulatory Guide 1. 78 *
- Document Control Desk NLR-N92100 In the process of licensing Saiem Unit 2, an-assessment was made on compliance to Regulatory Guide 1.78. An internal memorandum, -dated September 14, 1977, qualitatively evaluated several chemicals, including ammonium hydroxide, for impact on control room habitability.
It was concluded at that time (September 14, 1977), that since ammonium hydroxide was not listed in Regulatory Guide 1.78 nor its reference
- documents, it was not considered a hazardous chemical concern for control room habitability.
In responding to TMI Action Item III.D.3.4 the previous qualitative evaluation of September 14, 1977 and additional assessments, were used to support PSE&G's responses dated July 1, 1980 and August 13, 1980. -As a result of evaluations conducted in the fall of 199i, it was -concluded, that even though ammonium hydroxide is a dilute liquid, ammonia gas could evolve from spilled ammonium hydroxide under postulated accident conditions.
Therefore, a postulated accident of ammonium hydroxide storage was evaluated for impact on control room habitability.
CORRECTIVE ACTIONS TAKEN Upon notification of the discrepancy, a preliminary safety assessment was conducted using the computer code "CHARM", and a site survey performed for identification of any additional*
potentially hazardous chemicals.
The preliminary "CHARM".results concluded that there was no impact on control room habitability from a postulated ammonium hydroxide accident.
In order _to provide a timely response for a final safety evaluation, a different computer code "VAPOR was used because "CHARM" was not validated and verified to PSE&G software requirements.
PSE&G used the "VAPOR" code for the safety evaluation because its software had been documented and verified to comply with appropriate QA requirements for use in "important to safety" evaluations.
As a result of finalizing the safety evaluation for control room habitability using the "VAPOR" computer code; additional actions were taken to address the analysis conclusion
- that the toxic limit in the control *room may be exceeded.
The immediate compensatory measures included placing a temperature indicator and strip chart recorder in the storage tank area, limiting the amount of ammonium hydroxide volume stored, performed an engineering evaluation and subsequently reduced the concentration of ammonium hydroxide used at Salem to 15 wt%, and initiating precautionary administrative controls for tanker truck deliveries.
- Document Control Desk NLR-N92100 A preliminary analysis was conducted for the two additional chemicals, hydrazine and sodium hydroxide, -identified as a *result of the site survey.* The preliminary assessment resulted in chemical concentrations within the control room that did not
- exceed the toxic limits provided in authoritative sources. -Therefore, it was concluded there.would be no impact on control room habitability as* a result of a postulated accident regarding either hydrazine or sodium hydroxide.
-During the approval cycle for the control room habitability calculation, PSE&G questioned the "VAPOR" model assumptions and design input and determined they were very conservative.
As a result, the "CHARM" model was validated*and verified and used to complete the final evaluations.
The additional evaluations used .NRC regulatory criteria in the validated and verified "CHARM 1 i computer code for the postulated accidents for both 27.5 and 15 wt.% ammonium hydroxide storage tank concentrations.
- The evaluations, utilizing the "CHARM" code model, concluded that the Regulatory Guide .1.78 toxic limit for anhydrous ammonia, based on the concentration that can be tolerated for two minutes, will not be exceeded in the control room during a postulated release at the*tank containing either 27.5 wt% or 15 .wt.% ammonium hydroxide.
since the concentration of ammonium hydroxide was reduced, the .amount of deliveries on an annual basis, was anticipated to exceed the frequency threshold value for truck traffic of ten per year per Regulatory Guide 1.78. When the frequency criteria are applicable, Regulatory Guide 1.78 requires evaluation of the shipments for impact on control room habitability.
Therefore, included in the additional evaluations were postulated accidents to tanker delivery trucks containing 15 wt.% ammonium hydroxide at the site main access point and.Salem unloading dock. A final evaluation of the two additional chemicals was conducted using the validated and verified "CHARM" computer code for hydrazine and a quaiitative analysis for sodium hydroxide.
The final evaluation confirmed the preliminary assessment that control room habitability would not be impacted.
A qualitative
-evaluation was conducted for sodium hydroxide because-of its high boiling point and very low volatility.
Under postulated accident conditions no credible.
toxic airborne source can be determined.
The short term corrective actions immediately implemented, that are currently in place, are the administrative controls for tanker truck deliveries and use of 15 wt.% concentration ammonium hydroxide.
However, the "CHARM" code model evaluations support future use of 27.5 wt.% ammonium hydroxide, and the.elimination of both tank volume restrictions and continued temperature monitoring of the storage tank area.
-Document Control Desk NLR-N92100 Administrative controls were instituted, per issuance of Chemistry procedure SC.CH-AD.z*z-0474, for the operators at Salem to isolate the control room when riotif ied that a tanker truck transporting ammonium hydroxide is*requesting site access for delivery.*
The administrative controls also included notification of Hope Creek operators that an ammonium hydroxide delivery is being made for Salem. Evaluations, utilizing the "CHARM" code model, conclude that Regulatory Guide 1.78 toxic limits will *not be exceeded in the aope Creek control room therefore, *operator action is not required to isolate the control Operator training was conducted to identify.the odor of ammonia and ammonia was added to the annual olfactory recognition testing performed by the Medical Department on licensed
- An Abnormal Operating Procedure, SC.OP-AB.CR-0003(Q),. "Toxic Gas Release", was issued for Salem Generating Station to isolate the control room upon notification or detection by odor of ammonia in the control room. Hope Creek is also required to be notified.
A similar procedure for Hope Creek already existed. Changes to the Salem and Hope Creek UFSAR's have been completed that revise appropriate Sectio*ns to identify additional chemicals transported to and stored onsite, discuss the evaluations for control room habitability for these. additional cnemicals, and describe Salem's position on Regulatory Guide 1.78. The UFSAR changes will be incorporated in the next scheduled revision update. -CORRECTIVE ACTIONS TAKEN TO PREVENT RECURRENCE Procedure*NC.NA-AP.ZZ-0019(Q), "Procurement of Materials and Services" is being revised to limit the procurement of quantities of new chemicais to be brought onsite to less than 100 pound containers unless analyzed for their impact on control room habitability.
In the interim, direction on chemical procurement concerning toxic hazards*was provided by PSE&G memorandum, GM Nuclear Services to GM Procurement Material Control,.
dated April 8, 1992. Nuclear Administrative Procedure NC.NA-AP.ZZ-0038(Q), "The Chemical Control Program", was revised to require review of chemicals for control room habitability before use. Procedure NC.DE-AP.ZZ-OOOl(Q), "Design Bases/Input", was revised to address the possible impact from hazardous chemicals, used in conjunction with or added by Design Changes, on control r.oom habitability.
' , *. Document Control Desk NLR-N92100 In addition to the above specific changes, improvements to the engineering process have been implemented since the review and evaluation for* the original response to the TMI Action Item III.D.3.4.
Safety Evaluations (10CFR50.59) are more defined and comprehensive today to include nonsafety system interaction on safety systems such as the Chemical.Feed System using ammonium hydroxide.
Design Changes require a formalized design *bases/input process that include use of design considerations and specialty review checklists, interface record sheets, multiple . reviews including peer review in addition to independent design verification, and cross discipline and programmatic review. PSE&G .is in full compliance