ML18086A964: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(Created page by program invented by StriderTol)
Line 15: Line 15:
| page count = 4
| page count = 4
}}
}}
See also: [[followed by::IR 05000272/1980028]]


=Text=
=Text=
{{#Wiki_filter:Frederick  
{{#Wiki_filter:Frederick W. Schneider Vice President Public Service Electric and Gas Company 80 Park Plaza Newark, N.J. 07101 201/430-7373 Production
W. Schneider  
* August 21, 1981 Mr. Boyce H. Grier, Director Off ice of Inspection and Enforcement U.S. Nuclear Regulatory Commission Region.I 631 Park Avenue King of Prussia, Pa. 19406  
Vice President  
 
Public Service Electric and Gas Company 80 Park Plaza Newark, N.J. 07101 201/430-7373 Production  
==Dear Mr. Grier:==
* August 21, 1981 Mr. Boyce H. Grier, Director Off ice of Inspection  
NRC INSPECTION 50-272/80-28 UNIT NO. 1 SALEM GENERATING STATION Our letter of March 13, 1981, responded to Inspection No. 50-272/80-28.
and Enforcement  
We are now providing supplemental information, as requested,which is based upon further analyses, investigations, and changes implemented following the inspection.  
U.S. Nuclear Regulatory  
*rnspe*ctio*n Report Details F'ue'l' Tra*nsfe*r*
Commission  
Tube Event Personnel Intake Estimates  
Region.I 631 Park Avenue King of Prussia, Pa. 19406 Dear Mr. Grier: NRC INSPECTION  
*c5*0'-272/80-'28-0l).
50-272/80-28  
of your report states: The licensee has indicated an intake evaluation is to be submitted to the Director, Region I. This evaluation will include evaluation ef possible beta and alpha emitter intakes which are not readily detected by whole body counting.
UNIT NO. 1 SALEM GENERATING  
An evaluation for possible beta and alpha emitter intakes which are not readily detected by whole body counting has been completed.
STATION Our letter of March 13, 1981, responded  
The evaluation, which consisted of an examination of analyses J!>erf,ormed on primary coolant samples and resin samples of primary coolant derriineralizers, indicated that intake exposure due to alpha and beta emitters, which are not readily detected by whole body counting, would result in insignificant doses to the personnel involved in the event. In addition, all previous station gross alpha analyses of air samples and liquid rad waste samples have been undetectable.
to Inspection  
We will continue to examine and quantify the alpha and beta emitters for possible dose contribution to workers . Any s*ignificant differences between our find in gs and those that might result from this review will be reported to your office. ,/8110090237 810929\ ADOCK I
No. 50-272/80-28.  
* Mr. Boyce H. Grier, Director U.S. Nuclear Regulatory Commission 8/21/81 Fuel Trans*fer Tube Event Personnel Radiation Exposure (50-272/80'-'28-02) of your report states: The licensee is to submit personnel exposure estimates in a. report to the Director, Region I. Re*spohse:
We are now providing  
The personnel exposure estimates have been revised. The dose commitments to their skin, eyes, GI-tract, and lungs are summarized below. Details on the methodology and assumptions are available at the Salem Station. As*s i'gned no*s*e* Commitments Individual A Individual Dose to Skin (mrad) 830 830 Dose to Eyes (mrad) 30 30 Assigned MPC Hours 14 8 13 Week Dose to Lung (mrem) 28 13 1 Year Dose to Lung (mrem} 54 25 50 Year Dose to Lung (mreml 61 28 13 Week Dose to GI-Tract (mrem} 23 30 1 Year Dose to GI-Tract Cmrem) 41 55 50 Year Dose to GI-Tract (mrem} 46 62 (50-272/80'-28-10) bf your report states: Licensee's representatives indicated .action will be taken to ensure that the equivalent to Form 5 will reflect incomplete previous history for those individuals who do not have an date exposure history. *Re*st>on:se:
supplemental  
The station's equivalent of Form NRC-5 has been revised to reflec't incomplete previous history for those individuals who do not have an*up-to-date exposure history. * (5'0'-272/80:-2s-111 o*f your report states:
information, as requested,which  
radiation protection representatives indicated all contractor resumes will be required to be written in a manner to provide a concise time break down versus function which had been performed
is based upon further analyses, investigations, and changes implemented  
* B
following  
* Mr. Boyce H. Grier, Director U.S. Nuclear Regulatory Commission 8/21/81 Response:
the inspection.  
All contractor resumes are reviewed upon arrival of contractor on site. This review assures that the individual meets the time and experience requirements for which he was hired.
*rnspe*ctio*n  
of your report states: Licensee representatives indicated action will be taken to ensure routine entry permits will not be used.for entries into areas with significant radiological hazard potential and the control of access sign in forms. Response:
Report Details F'ue'l' Tra*nsfe*r*  
A review of Procedure PD 15.1.013, "REP and EREP Usage", which ensures routine entry permits will not be for entries into areas with significant radiological hazard potential, has*been completed.
Tube Event Personnel  
Your report suggests REP No. 0541, "Routine Surveys, Valving and Inspection for HP, Chemistry Operations, and Station QA", was used for routine as well as non-routine entries. This REP had specific requirements for survey points outside the biological shield. It also had specific requirements for entries inside the biological shield where workers were required to be accompanied oy' a heal th physics technician.
Intake Estimates  
The title of this REP may-have been misleading but the functional role of REP was correct. At Salem, an EREP is used for routine entries. Normally, REP/EREP Access Sign-in forms are utilized at the control points. As noted in your report, inspector discussions with the* entry party personnel did indicate that the individuals had signed i.n and out, however, the sign-in form apparently had been misplaced.
*c5*0'-272/80-'28-0l).  
This occurrence is considered to be an isolated case and present controls are adequate.
of your report states: The licensee has indicated  
The REP rooin supervisor has Been made aware of the continued need for control of access si:gn-in forms. Sincerely, cc D.trector, Off,i;ce of :i:nspection and Enforcement Nuclear Regulatory Commission Wash;tngton, DC. 20555 IA
an intake evaluation  
* STATE OF NEW JERSEY SS: COUNTY OF ESSEX COUNTY OF ESSEX FREDERICK
is to be submitted  
: w. SCHNEIDER, being duly sworn according to law deposes and says: I am a Vice President of Public Service Electric and Gas Company, and as such, I find the matters set forth in our response dated August 21, 1981 to the NRC's inspection report 50-272/80-28 are true to the best of my knowledge, information and belief. ;FREDERICK W. SCHNEIDER Subscril5ed and sworn to before me th+/-s.JtfYA-day , 1981 Jersey My Commission expires on (flet.0 /91'-:J'}}
to the Director, Region I. This evaluation  
will include evaluation  
ef possible beta and alpha emitter intakes which are not readily detected by whole body counting.  
An evaluation  
for possible beta and alpha emitter intakes which are not readily detected by whole body counting has been completed.  
The evaluation, which consisted  
of an examination  
of analyses J!>erf,ormed  
on primary coolant samples and resin samples of primary coolant derriineralizers, indicated  
that intake exposure due to alpha and beta emitters, which are not readily detected by whole body counting, would result in insignificant  
doses to the personnel  
involved in the event. In addition, all previous station gross alpha analyses of air samples and liquid rad waste samples have been undetectable.  
We will continue to examine and quantify the alpha and beta emitters for possible dose contribution  
to workers . Any s*ignificant  
differences  
between our find in gs and those that might result from this  
review will be reported to your office. ,/8110090237  
810929\ ADOCK  
I
* Mr. Boyce H. Grier, Director U.S. Nuclear Regulatory  
Commission  
-2-8/21/81 Fuel Trans*fer  
Tube Event Personnel  
Radiation  
Exposure (50-272/80'-'28-02)  
of your report states: The licensee is to submit personnel  
exposure estimates  
in a. report to the Director, Region I. Re*spohse:  
The personnel  
exposure estimates  
have been revised. The dose commitments  
to their skin, eyes, GI-tract, and lungs are summarized  
below. Details on the methodology  
and assumptions  
are available  
at the Salem Station. As*s i'gned no*s*e* Commitments  
Individual  
A Individual  
Dose to Skin (mrad) 830 830 Dose to Eyes (mrad) 30 30 Assigned MPC Hours 14 8 13 Week Dose to Lung (mrem) 28 13 1 Year Dose to Lung (mrem} 54 25 50 Year Dose to Lung (mreml 61 28 13 Week Dose to GI-Tract (mrem} 23 30 1 Year Dose to GI-Tract Cmrem) 41 55 50 Year Dose to GI-Tract (mrem} 46 62 (50-272/80'-28-10)  
bf your report states: Licensee's  
representatives  
indicated .action will be taken to ensure that the equivalent  
to Form 5 will reflect incomplete  
previous history for those individuals  
who do not have an  
date exposure history. *Re*st>on:se:  
The station's  
equivalent  
of Form NRC-5 has been revised to reflec't incomplete  
previous history for those individuals  
who do not have an*up-to-date  
exposure history. * (5'0'-272/80:-2s-111  
o*f your report states:  
radiation  
protection  
representatives  
indicated  
all contractor  
resumes will be required to be written in a manner to provide a concise time break down versus function which had been performed  
* B
* Mr. Boyce H. Grier, Director U.S. Nuclear Regulatory  
Commission  
-3-8/21/81 Response:  
All contractor  
resumes are reviewed upon arrival of contractor  
on site. This review assures that the individual  
meets the time and experience  
requirements  
for which he was hired.  
of your report states: Licensee representatives  
indicated  
action will be taken to ensure routine entry permits will not be used.for entries into areas with significant  
radiological  
hazard potential  
and the control of access sign in forms. Response:  
A review of Procedure  
PD 15.1.013, "REP and EREP Usage", which ensures routine entry permits will not be  
for entries into areas with significant  
radiological  
hazard potential, has*been completed.  
Your report suggests REP No. 0541, "Routine Surveys, Valving and Inspection  
for HP, Chemistry  
Operations, and Station QA", was used for routine as well as non-routine  
entries. This REP had specific requirements  
for survey points outside the biological  
shield. It also had specific requirements  
for entries inside the biological  
shield where workers were required to be accompanied  
oy' a heal th physics technician.  
The title of this REP may-have been misleading  
but the functional  
role of REP was correct. At Salem, an EREP is used for routine entries. Normally, REP/EREP Access Sign-in forms are utilized at the control points. As noted in your report, inspector  
discussions  
with the* entry party personnel  
did indicate that the individuals  
had signed i.n and out, however, the sign-in form apparently  
had been misplaced.  
This occurrence  
is considered  
to be an isolated case and present controls are adequate.  
The REP rooin supervisor  
has Been made aware of the continued  
need for control of access si:gn-in forms. Sincerely, cc D.trector, Off,i;ce of :i:nspection  
and Enforcement  
Nuclear Regulatory  
Commission  
Wash;tngton, DC. 20555
IA * STATE OF NEW JERSEY SS: COUNTY OF ESSEX COUNTY OF ESSEX FREDERICK  
w. SCHNEIDER, being duly sworn according  
to law deposes and says: I am a Vice President  
of Public Service Electric and Gas Company, and as such, I find the matters set forth in our response dated August 21, 1981 to the NRC's inspection  
report 50-272/80-28  
are true to the best of my knowledge, information  
and belief. ;FREDERICK  
W. SCHNEIDER  
Subscril5ed  
and sworn to before me th+/-s.JtfYA-day , 1981 Jersey My Commission  
expires on (flet.0 /91'-:J'
}}

Revision as of 20:58, 31 July 2019

Responds to NRC 810313 Ltr Re Violations Noted in IE Insp Rept 50-272/80-28.Corrective Actions:Personnel Exposure Estimates Revised & Evaluation of Possible Beta & Alpha Emitter Intakes Completed
ML18086A964
Person / Time
Site: Salem PSEG icon.png
Issue date: 08/21/1981
From: Schneider F
Public Service Enterprise Group
To: Grier B
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML18086A963 List:
References
NUDOCS 8110090237
Download: ML18086A964 (4)
v • d • e


Text

Frederick W. Schneider Vice President Public Service Electric and Gas Company 80 Park Plaza Newark, N.J. 07101 201/430-7373 Production

  • August 21, 1981 Mr. Boyce H. Grier, Director Off ice of Inspection and Enforcement U.S. Nuclear Regulatory Commission Region.I 631 Park Avenue King of Prussia, Pa. 19406

Dear Mr. Grier:

NRC INSPECTION 50-272/80-28 UNIT NO. 1 SALEM GENERATING STATION Our letter of March 13, 1981, responded to Inspection No. 50-272/80-28.

We are now providing supplemental information, as requested,which is based upon further analyses, investigations, and changes implemented following the inspection.

  • rnspe*ctio*n Report Details F'ue'l' Tra*nsfe*r*

Tube Event Personnel Intake Estimates

  • c5*0'-272/80-'28-0l).

of your report states: The licensee has indicated an intake evaluation is to be submitted to the Director, Region I. This evaluation will include evaluation ef possible beta and alpha emitter intakes which are not readily detected by whole body counting.

An evaluation for possible beta and alpha emitter intakes which are not readily detected by whole body counting has been completed.

The evaluation, which consisted of an examination of analyses J!>erf,ormed on primary coolant samples and resin samples of primary coolant derriineralizers, indicated that intake exposure due to alpha and beta emitters, which are not readily detected by whole body counting, would result in insignificant doses to the personnel involved in the event. In addition, all previous station gross alpha analyses of air samples and liquid rad waste samples have been undetectable.

We will continue to examine and quantify the alpha and beta emitters for possible dose contribution to workers . Any s*ignificant differences between our find in gs and those that might result from this review will be reported to your office. ,/8110090237 810929\ ADOCK I

  • Mr. Boyce H. Grier, Director U.S. Nuclear Regulatory Commission 8/21/81 Fuel Trans*fer Tube Event Personnel Radiation Exposure (50-272/80'-'28-02) of your report states: The licensee is to submit personnel exposure estimates in a. report to the Director, Region I. Re*spohse:

The personnel exposure estimates have been revised. The dose commitments to their skin, eyes, GI-tract, and lungs are summarized below. Details on the methodology and assumptions are available at the Salem Station. As*s i'gned no*s*e* Commitments Individual A Individual Dose to Skin (mrad) 830 830 Dose to Eyes (mrad) 30 30 Assigned MPC Hours 14 8 13 Week Dose to Lung (mrem) 28 13 1 Year Dose to Lung (mrem} 54 25 50 Year Dose to Lung (mreml 61 28 13 Week Dose to GI-Tract (mrem} 23 30 1 Year Dose to GI-Tract Cmrem) 41 55 50 Year Dose to GI-Tract (mrem} 46 62 (50-272/80'-28-10) bf your report states: Licensee's representatives indicated .action will be taken to ensure that the equivalent to Form 5 will reflect incomplete previous history for those individuals who do not have an date exposure history. *Re*st>on:se:

The station's equivalent of Form NRC-5 has been revised to reflec't incomplete previous history for those individuals who do not have an*up-to-date exposure history. * (5'0'-272/80:-2s-111 o*f your report states:

radiation protection representatives indicated all contractor resumes will be required to be written in a manner to provide a concise time break down versus function which had been performed

  • B
  • Mr. Boyce H. Grier, Director U.S. Nuclear Regulatory Commission 8/21/81 Response:

All contractor resumes are reviewed upon arrival of contractor on site. This review assures that the individual meets the time and experience requirements for which he was hired.

of your report states: Licensee representatives indicated action will be taken to ensure routine entry permits will not be used.for entries into areas with significant radiological hazard potential and the control of access sign in forms. Response:

A review of Procedure PD 15.1.013, "REP and EREP Usage", which ensures routine entry permits will not be for entries into areas with significant radiological hazard potential, has*been completed.

Your report suggests REP No. 0541, "Routine Surveys, Valving and Inspection for HP, Chemistry Operations, and Station QA", was used for routine as well as non-routine entries. This REP had specific requirements for survey points outside the biological shield. It also had specific requirements for entries inside the biological shield where workers were required to be accompanied oy' a heal th physics technician.

The title of this REP may-have been misleading but the functional role of REP was correct. At Salem, an EREP is used for routine entries. Normally, REP/EREP Access Sign-in forms are utilized at the control points. As noted in your report, inspector discussions with the* entry party personnel did indicate that the individuals had signed i.n and out, however, the sign-in form apparently had been misplaced.

This occurrence is considered to be an isolated case and present controls are adequate.

The REP rooin supervisor has Been made aware of the continued need for control of access si:gn-in forms. Sincerely, cc D.trector, Off,i;ce of :i:nspection and Enforcement Nuclear Regulatory Commission Wash;tngton, DC. 20555 IA

  • STATE OF NEW JERSEY SS: COUNTY OF ESSEX COUNTY OF ESSEX FREDERICK
w. SCHNEIDER, being duly sworn according to law deposes and says: I am a Vice President of Public Service Electric and Gas Company, and as such, I find the matters set forth in our response dated August 21, 1981 to the NRC's inspection report 50-272/80-28 are true to the best of my knowledge, information and belief. ;FREDERICK W. SCHNEIDER Subscril5ed and sworn to before me th+/-s.JtfYA-day , 1981 Jersey My Commission expires on (flet.0 /91'-:J'
Retrieved from "https://kanterella.com/w/index.php?title=ML18086A964&oldid=1871054"