ML19290F197
| ML19290F197 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 03/06/1980 |
| From: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Daltroff S PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| References | |
| NUDOCS 8003180292 | |
| Download: ML19290F197 (1) | |
Text
.V.
m o,,
UNITED STATES 8
p g
NUCLEAR REGULATORY COMMISSION 3
E REGION I
,e'[
C, 631 PARK AVENUE KING OF PRUSSIA. PENNSYLVANIA 19406 March 6, 1980 Occket Nos. 50-277 50-278 Philadelphia Electric Company ATTN:
Mr. S. L. Daltroff Vice President Electric Production 2301 Market Street Philadelphia, Pennsylvania 19101 Gentlemen:
The enclosed IE Circular No. 80-03, " Protection from Toxic Gas Hazards", is forwarded to you for information.
No written response is required.
If you desire additional information regarding this matter, please contact this office.
Sincerely,
./fd f M
Boyce H. Grier
' Director
Enclosures:
1.
IE Circular No. 80-03 with Attachments 2.
List of Recently Issued IE Circulars CONTACT:
R. J. Bores (215-337-5260) cc w/encls:
W. T. Ullrich, Station Superintendent Troy B. Conner, Jr., Esquire Eugene J. Bradley, Esquire Raymond L. Hovis, Esquire Michael J. Scibinico, II, Assistant Attorney General 8003]802 9 2
f ENCLOSURE 1 SSINS:
6830 Accession No.:
UNITED STATES 7912190685 NUCLEAR REGULATORY COMMISSION 0FFICE OF INSPECTION AND ENFORCEMENT
{r
-- g )a _6; WASHINGTON, D.C.
20555
_= m -BJ$
IE Circular No. 80-03 Date:
March 6, 1980 Page 1 of 2 PROTECTION FROM T0XIC GA5 HAZARDS Chlorine gas releases have been reported at two different reactor facilities in the past two years.
At Millstone, in March 1978, a leak of about 100 standard cubic feet of chlorine (about a gallon of liquid) occurred over a ten minute period, resulting in the hospitalization of 15 people.
The ventilation system carried the chlorine into the plant buildings, where personnel distress was noted.
No injuries occurred in the buildings due to the small size of the release.
At Browns Ferrv, in June 1979, a small leak from a diaphragm on a chlorine reducing valve resulted in the hospitalization of five people, including a control room operator.
Chlorine is highly toxic, producing symptoms after several hours exposure in concentrations of only one ppm.
Concentrations of 50 ppm are dangerous for even short exposures and 1000 ppm is fatal for brief exposures.
- Chlorine, used at some power stations to control organisms in the circulating water, is normally supplied in one ton containers or in tank cars of up to 90 tons capacity.
Other potential sources of toxic gas that have been identified at nuclear power plants include:
Nearby industrial facilities.
At Waterford, in July 1979, construction forces had to be evacuated for two and a half hours due to a chlorine gas release from a nearby chemical plant.
Chlorine transportation on adjacent highways, railways and rivers.
Large tanks of aqueous ammonia stored near plant buildings.
Both acid and caustic storage tanks located in a common building near the control room.
At the Dresden site, in August 1977, accidental mixing of acid and caustic solutions resulted in toxic fumes that entered the control room via the ventilation system.
IE Circular No. 80-03 Date:
March 6, 1980 Page 2 of 2 Criterion 19 of Appendix A to 10 CFR 50 requires a control room from which action can be taken to maintain the reactor in a safe condition under accident conditions.
The control room designs in current license applications are reviewed for operator protection from toxic gases (as well as radiation), in accordance with Standard Review Plan (SRP) 6.4 (NUREG 75/087 dated 11/24/75).
Related information on the identification of potential hazards and the evalua-tion of potential accidents can be found in SRP sections 2.2.1-2.2.2 and 2.2.3 respectively.
The SRP references Regulatory Guide 1.78 (dated June 1974) on control room hcoitability during chemical releases.
It also references Regula-tory Guide 1.95 on requirements for protection against chlorine releases specifically.
The majority of the plants currently operating, however, were built and licensed prior to the development and implementation of this guidance.
A review of some older plants, with respect to toxic gas hazards indicates that they do not have the degree of protection that would be required for present day plants.
Evaluation of the protection of control rooms from toxic gas releases is part of the systematic evaluation program currently being carried out on certain older plants.
Also, as older facilities submit requests for significant license amendments, their design features and controis for protection of control rooms are reviewed and, if appropriate, are required to be changed.
However, the recent history of frequent toxic gas release incidents appears to warrant a more rapid impicmentation of the newer toxic gas protection policies.
For the above reasons, it is strongly recommended that:
You evaluate your plant (s) against section 6.4 and applicable parts of sections 2.2.1-2.2.2 and 2.2.3 of the SRP with respect to toxic gas hazards.
Where the degree of protection against toxic gas hazards is found to be significantly less than that specified in the SRP, provide tha controls or propose the design changes necessary to achieve an equialer.t level of protection.
No written response to this circular is required.
If you desire additional information regarding this matter, contact the Director of the appropriate NRC Regional Office.
Attachments:
Sections 2.2.1-2.2.2; 2.2.3 and 6.4 of NUREG 75/087
Attachment to IE Circular No. 80-03 o
NUREG 75/087 fgass o
y
",g U.S. NUCLEAR REGULATORY COMMISSION i
STANDARD REVIEW PLAN OFFICE OF NUCLEAR REACTOR REGULATION SECTIONS 2.2.1 - 2.2.2 IDENTIFICATION OF FOTENTIAL HAZARDS IN SITE VICINITY l
REVIEW RESPONSIBILITIES Primary - Accident Analysis Branen (AAS)
Secondary - None I.
AREAS OF REVIEW
, Locations and separation distances from the site of industrial, military, and transportation facilities and routes in the vicinity of the site. Such facilities and routes include air, ground, and water traffic, pipelines, and fixed manufacturing, processing, and storage facilities. Potential external hazarcs or ha:ardous materials that are present or wnich may reasonably be expected to be present during the projected life time of the proposed plant. The purpose of this review is to establish tne infomation concerning the presence of potential external ha:ards wnich is to be used in further review in Sections 2.2.3, 3.5.1.5, and 3.5.1.6.
II. ACCEPTANCE CRITERIA 1.
Data in the SAR adequately describes the locations and distances of incustrial, l
military, and transportation facilities in the vicinity of the plant, and is in agreement with data obtained from other sources, when available.
2.
Cescriptions of tre nature and extent of activities conducted at nenroy facilities, including the products and materials likely to be processed, stored, used, or trans-ported, are adequate to permit evaluations of ;ossible hazards in Part 3 review sections dealing, with scecific hazards.
3.
Where potentially hazarcous materials may be processed, stored, used, or transported in the vicinity of the plant, sufficient statistical data on such materials are l
provided to establish a basis for evaluating the potential ha:ard to the plant.
III. REVIEW PROCEDURES Selection and empnasis of various aspects of the areas covered by this review plan will be made by the reviewer on each case. The judgment of the areas to be given attention during the review is to be based on an inspection of the material presented, the similarity of the material to that recently reviewed on other piants, and whether items of special safety significance are involved. The following procadures are followed:
l USNI DUPLICATE DOCUMENT U.".C" O"."."."r~i.' '.".'.'.."".-,".,.. 5 Entire document previous 1y 1'.'.'.' *,',O,,.."O r R.***. O entered into Gys
....~~a--
~
===- -
a No. of pages:
'I
Attachment to IE Circular No. 80-03
-e pa afog NUREG 75/087 h
a fhg U.S. NUCLEAR REGULATORY COMMISSION M {!
STANDARD REVIEW PLAN
\\...f./
OFFICE OF NUCLEAR REACTOR REGULATION SECTION 2.2.3 EVALUATION OF POTENTIAL ACCIDENTS REVIEW RESPCNSIBILITIES Primary - Accident Analysis Branch (AAB)
Secondary - Applied Statistics Branch (ASB/MPA) 1.
AREAS OF AEVIEW The applicant's identification of potential accident situations in the vicinity of the plant is reviewed to determine the comoleteness of and the bases upon which these potential accidents were or were not accormcdated in the design. (See Standard Review Plans 2.2.1 and 2.2.2.)
The applicant's precability analyses of potential accidents involving hazardous materials or activities in the vicinity of the plant, if such analyses have been oerfor ed, are also reviewed by ASS /MPA on request by AAB to detarmine that appropriate data and analytical models have been utilized.
The analyses of the consequences of accidents involving nearby industrial, militar.<, and transportation facilities which have been identified as design basis events are reviewed.
II. ACCEPTANCE CRITERIA The identification of desig basis events resulting frcm the presence of hazardous materials or activities in the vicinity of the plant is accectable if the design basis events include each postulatad type of accident for which the expected rate of occurrence of potential l
exposures in excess of the 10 CFR Part 100 guidelines is estimated to exceed the NRC staff objective of approximately 10~ per year. :lecause of the difficulty of assigning accurate numerical values to the expected rate of unprecedented ;otential hazards generally con-sidered in this review plan, judgment must be used as to the acceptability of the overall risk presented.
The pr bability cf occurrence of the initiating events leasing to potential consequences in exesss of 10 CM Part 100 exposure guidelines shculd be estimated using assumptions that are as representai;ive of the specific site as is practicable. In addition, tecause of the low procabilities of the events under consiceratien, data are often not available to permit accurate calculation of probabilities. Accordingly, the expected rate of cccur-rence of potential exposures in excess of the 10 CFR Part 100 guidelires of approximately 10-6 per year is acceptable if, when ccmbined with reasonable qualitative arguments, the realistic probability can be shown to be 10wer.
USNRC STANDARD REVIEW PLAN ll~l7 ~.~~~ T":!L*',"*r'.".e. *l.'*.'""l' *..:. Ole'*!"e' *,""*'.*"*".'" "'Ce" '". ""s *e** '."l'*,'l-*," *' ""l"'". '." ',"C. '"o
- =.".".*.;';"T:'*:: !e'e". "or",,l"."
"o '2"."'*l.*.*, **.0" e*~e ":'."e.". ',:*i", lTe '".t*
',1**".*; ".*.,*l.*.~.";"e,14",e.*"*"'s "*
.e, -o o.
.r. %.
ee..;
hsNeopted se te W reusew piene e*5 be reussed pe.neess.ey, s..peaterte.g.,e.cte.unated.ee to sme.tes.nd,e. emes,.neus soferest.eee.e ed.mpone. nee Coch.ne.sts e,td twgge.he.te fee t.Ime.eet te.ut weG b.4.nedered.pd.Roued be pers,,e me W.J. J0ws6eer Aegunstery CeMee.sesen.0mee er as ee, mee,ie, neg.*
toeem, wneaang,e a. O C. 3ME y
I
Attachment to IE Circular No. 80-03 The effects of design basis events have been ade;uately considered if analyses of the l
effects of those accidents on the safety-related features of the plant have been perfomed N
and measures (e.g., hardening, fire protection) to mitigate the consequences of such events have been taken.
III. REVIEW PROCEDURES In some cases it may be necessary to consult with or obtain specific data from other eranches, such as the Structural Engineering Branch (SEB) or Auxiliary Systems Branch l
(ASB), regarding possible effects of external events on plant structures or components.
The applicant's probability calculations are reviewed, and an independent probability analysis is performed by the staff if the potential hazard is considered significant enough to affect the licensability of the site or is important to the identification of design basis events.
All stochastic variables that affect the occurrence or severity of the postulated event are identified, and judged to be either independent or conditioned by other variables.
Probabilistic models should be tested, where possible, against all available information.
If the model or any portion of it, by simple extension, can be used to predict an observ-able accident rate, this test should be perfomed.
The design parameters (e.g., overpressure) and physical pnenomena (e.g., gas concentration) selected by the applicant for each design basis event are reviewed to ascertain that the values are comparable to the values used in previous analyses and found to be acceptable by the staff.
Each design basis event is reviewed to determine that the effects of the event on the safety features of the plant have been adequately accomodated in the design.
If accidents involving release of smoke, flammable or nonflammable gases, or chemical bearing clouds are considered to be design basis events, an evaluation of the effects of these accidents on control room habitability should be made in SAR Section 6.4 and on the operation of diesels and otner safety-related equipment in SAR Chapter 9.
Special attention should be given to the review of standardized designs which propose criteria involving individual numerkal probability criteria for indivicual classes of external man-made hazards. In such instances the reviewer should establish that the envelope also includes an overall criterion that limits the aggregate probability of exceed-ing design criteria associated with all of the identified external man-made hazards.
Similarly, special attention should be given to the review of a site where several man-made hazards are identified, but none of which, individually, has a probability exceeding the acceptance cr,1teria stated herein. The objective of this special review should be to assure that the aggregate probability of an outcome that may lead to unacceptable plant damage meets the acceptance criteria of Part II of this SRP Section. (A hypothetical example is a situation where the probability of snock wave overpressure greater than design Rev. 1 2.2.3-2
Attachment to IE Circular No. 80-03 overpressure is about 10"I per reactor yeaf from accidents at a nearby industrial facility, and approximately equal probabilities of exceeding design pressure from railway accidents, highway accidents and from shipping accidents. Individually each may be judged acceptably i
low; the aggregate probability may be judged sufficiently great that additional features of design are warranted.)
IV.
EVALUATION FINDINGS If the reviewer verifies that sufficient information has been provided and that his evaluation is sufficiently complete and adequate to meet the acceptance criteria in Section II of this SRP, conclusions of the following type may be prepared for the staff's safety evaluation report:
"The applicant has identified potential accidents which could occur in the vicinity of the plant, and from these has selected these which should be considered as design l
basis events and has provided analyses of the effects of these accidents on the safety-related features of the plant. The applicant has deconstrated that the plant is adecuately protected and can be operated with an acceptable degree of safety with regard to potential accidents which may occur as the result of activities at nearby industrial, military, and transportation facilities."
V.
REFERENCES Regulatcry Guide 1.70, " Standard Fomat and Content of Safety Analysis Reports for Nuclear Power Plants," Revision 2.
Affidavit of Jacques B. J. Read b2 fore the Atomic Safety and Licensing Board in the matter of Skagit Nuclear Power Project, Units 1 and 2 July 15,1976. Docket Nos. STN 50-522, 523.
Atomic Safety and Licensing Board, Supplemental Initial Decision in the Matter of Hope Creek Generating Station, Units 1 and 2, March 28, 1977. Docket Nos. 50-354, 355.
Section 2 Supplement 2 to the Floating Nuclear Plant Safety Evaluation Report, Docket No STN 50-437, September 1976.
s 2.2.3-3 Rev. I
Attachment to IE Circular No. 80-03 n afog NUREG 75/087 a
b
/
o f h 3.,7 [',g U.S. NUCLEAR REGUl.ATORY COMMISSION d'%....f*#Q i STANDARD REV]EW PLAN OFFICE OF NUCLEAR REACTOR REGULATION SECTION 6.4 HABITABILITY SYSTEMS REVIEW RESPCNSIBILITIES Primary - Accident Analysis Branch (AAB)
Secondary - Hydrology-Meteorology Branch (HMB)
Auxiliary Systems Branch (ASB)
Effluent Treatment Systems Branch (ETSB)
I.
AREAS OF REVIEW The control room ventilation system and control building layout and structures, as described in the applicant's safety analysis report (SAR), are reviewed with the oojective of assuring that plant operators are acequately protected against the effects of accidental releases of toxic or radioactive gases. A further objective is to assure that the control room cari be maintained as the center from which emergency teams can safely operate in the case of a design basis radiological release. To assure that these objectives are accom-plished the folicwing items are reviewed:
1.
The zone serviced by the control room emergency ventilation system is examined to ascertain that all critical areas requiring access in the event of an accident are included within the zone (control room, kitchen, sanitary facilities, etc.) and to I
aosure that those areas not requiring access are generally excluded from the zone.
2.
The capacity of the control room in terms of the numeer of people it can accommodate for an exterded period of time is reviewed to confirm the adequacy of emergency food and medical supplies and self-contained breathing apparatus and to determine the length of time '.ne control room can be isolated before CO levels bec me excessive.
2 3.
The control r om ventilation system layout and functional design is reviewed to determina fitw rates and filter efficiencies for input into the AA8 analyses of the builduo of radioactive or toxic gases inside the control room, assuming a design basis release. Basic deficiencies that might impair the effectiveness of the system are examined. In addition, the system operation and procedures are reviewed. The ASB has primary responsibility in the system review area under Standard Review Plan (SRP) 9.4.1.
The ASB is consulted wnen reviewing hardware and operating procedures.
DUPLICATE DOCUMENT USNRC ST Entire document previously entered into system under:
-..-....o.....
=. =u====
b..//7G#S
_====.:.====
-o Pw.si.a se.a..r.
.e.a. eds b. r.w aee.e
[
N o.
of pages:
/
,c. y 77 nev. i