ML17255A432
| ML17255A432 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 09/28/1983 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17255A433 | List: |
| References | |
| NUDOCS 8310070372 | |
| Download: ML17255A432 (8) | |
Text
gp,ll AE0II c>
0 Op 0
h
+0
++*++
UN/TED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REAC OR REGULATION SUPPORTING AMEHDNEHT NO.
TO PROVISIONAL OPERATING LICENSE NO.
D CK N.
0244
1.0 INTRODUCTION
To comply with Section V of Appendix I of 10 CFR Part 50, the Rochester Gas and Electric Corporation has filed with the Commission plans and proposed technical specifications developed for the purpose of keeping releases of radioactive materials to unrestricted areas during normal operations, including expected operational occurrences, as low as is reasonably achievable.
The Rochester Gas and Electric Corporation filed this information with the Commission by letter dated August 12, 1982*
which requested changes to the Technical Specifications appended to Provisional Operating License No.
DPR-18 for R. E. Ginna Nuclear Power Plant.
The proposed technical specifications update those portions of the technical specifications addressing radioactive waste management and make them consistent with the current staff positions as expressed in NUREG-0472.
These revised technical specifications would reasonably assure compliance, in radioactive waste management, with the provisions of 10 CFR Part 50.36a, as supplemented by Appendix I to 10 CFR Part 50, with 10 CFR Parts 20.105(c),
106(g),
and 405(c); with 10 CFR Part 50, Appendix A, General Design Criteria 60, 63, and 64; and with 10 CFR Part 50, Appendi x B.
8310070372 830'729 PDR ADQCK 05000244 P
PDR t
~um>
a s
y oc ester as an ectric Corporation dated 02/14/79, 05/29/79, 01/10/83 and 03/04/83 also relate to this evaluation.
I
2.0 BACKGROUND
AND DISCUSSION 2.1 Reaulations 10 CFR Part 50, "Domestic Licensing of Production and Utilization Facilities", Section 50,36a, "Technical Specifications on Effluents from Nuclear Power Reactors",,
provides that each license authorizing operat'on of a nuclear power reactor will include technical specifications that (1) require compliance with applicable provisions of Part 20.106, "Radioactivity in Effluents to Restricted Areas";
(2) require that operating procedures developed for the control of effluents be established and followed; (3) require that equipment installed in the radioactive waste system be maintained and used; and (4) require the
-- - "-":~eriodic submission of reports to the NRC specifying the quantity of each of the principal radionuclides released to unrestricted areas in liquid and gaseous effluents, any quantities of radioactive materials released that are significantly above design objectives, and such other information as may be required by the Commission to estimate maximum
- - potential radiation dose to the public resulting from the effluent releases.
10 CFR Part 20, "Standards for Protection Against Radiation," paragraphs 20.105(c),
20.106 (g), and 20.405 (c), require that nuclear power plant and other licensees comply with 40 CFR Part 190," 'Environmental Radiation Protection Standards for Nuclear Power Operations" and submit reports to the NRC when the 40 CFR Part 190 limits have been or may be exceeded.
2.1 10 CFR Part 50, Appendix A General Design Criteria for Nuclear Power
- Plants, contains Criterion 60, Control of releases of radioactive materials to the environment; Criterion 63, Honitoring fuel and waste storage; and Criterion 64, Honitoring radioactivity releases.
Criterion 60 requires that the nuclear power unit design include means to control suitably the release of radioactive materials in gaseous and liquid effluents and to handle radioactive solid wastes produced during normal reactor operation<
including anticipated operational occurrences.
Criterion 63 requires that app opriate systems be provided in radioactive waste systems and associated handl:ng areas to detect conditions that may
'I
result in excessive radiation levels and to initiate appropriate safety actions.
Criterion 64 requires that means be provided for monitoring effluent discharge paths and the plant environs for radioactivity that may be released from normal operations, including. anticipated operational occurrences and postulated accidents.
10 CFR Part 50, A'ppendix B, establishes quality assurance requirements for nuclear power plants.
10 CFR Part 50, Appendix I, Section IV< provides guides on technical specifications for limiting conditions for operation for light-water-
-- -~"-"~cooled nuclear power reactors licensed under 10 CFR Part 50.
2.2 Standard Radiolo ical Effluent Technical S ecifications NUREG-0472 provides radiological effluent technical specifications for pressurized water reactors which the staff finds to be an acceptable standard for licensing actions.
Further clarification of these acceptable methods is provided in NUREG-0133, "Preparation of Radiological Ff fluent Technical Specifications for Nuclear Power Plants."
NU~-0133 describes methods found acceptable to the staff of the NRC for the calculation of certain key values required in the preparation of proposed radiological effluent technical specifications for light-water-cooled nuclear power plants.
NUREG-0133 also provides guidance to licensees in preparing requests" for changes to existing radiological effluent technical specifications for operating reactors.
't also describes current staff positions on the methodology for estimating radiation exposure due to the release of radioactive materials in effluents and on the administrative control of radioactive waste treatment systems.
The above NUREG documents address all of the radiological effluent technical specifications needed to assure compliance with the guidance and requirements provided by the regulations previously cited.
- However, alternative approaches to the preparation of radiological effluent
technical specifications and alternative radiological effluent technical specifications may be acceptable if the staff determines that the alternatives are in compliance with the regulations and with the intent of the regulatory guidance.
2.2 The standard wadiological effluent technical specifications can be grouped under the following categories:
(1)
Instrumentation (2)
Radioactive effluents (3)
Radiological environmental monitoring (4)
Design features (5)
Administrative controls Each of the specifications under the first three categories are comprised of two parts:
the limiting condition for operation and the surveillance requirements.
The limiting condition for operation provides a statement of the limiting condition, the times when it is applicable, and the actions to be taken in the event that the limiting condition is not met.
In general, the specifications established to assure compliance with 10 CZR Part 20 standards provide, in the event the limiting conditions of operation are exceeded, that without delay conditions are restored to within the limiting conditions.
Otherwise, the facility is required to effect approved shutdown procedures.
In general, the specifications established to assure compliance with 10 CPR Part 50 provide, in the event the limiting conditions of operation are exceeded, that within specified times corrective actions are to be taken, alternative means of operation are to be employed, and certain reports are.to be submitted to the NRC describing these conditions and actions.
The specifications concerning design features and administrative controls contain no limiting conditions of operation or surveillance requirements.
2.2 Table 1 indicates the standard radiological effluent technical specifications that are needed to assure compliance with the particular provisions of the regulations described in Section 1.0.
Table 1.
Relat>on Between Provisions of the Regulations and and Boiling Water React,ors I
I J
the Standard Radiological Effluent TechnIcal Specifications for Pressurized Water Reactors n" nstru-nenta-t ion Liquid aseous K~~W PW Rad oactive vents Rad. Envir.
lionitorin Oesign Features Administrative Control 0 indicate the specifications that are needed to assure compliance with the identified provision of the regulations.
rov>s ons o
t e 0
o e
o edera e
u ations OI C
~t OI C
Q
't L.
~t Q
C0 tC0 au al
~
W au au
'0 W
Ct ah/Il LJ C0 u
/OLuC Cl IJC0V C
Cl ae an
~I 0 W CI C
Cl
/aj Ol Ih I A C
nS Ol I In a nl3 D Dt nS 0
'D D t t O'J t
t uI CL D Cl C L,
~ X anu't CJ~Z an L
/O I In nj t LO Cl~
OJ t Iej Cl 0
I t Y
m I/I0 OJ Ol Ol t I/I I/I ah 0.
000 X
CS CS W uC OJ nj Cl I
Ol nIC Ih /O nS I D
OJ nj C7I OO
/OL
~n O 0 I/I OJI/I I/I nj nj LS Lj C
Ol u g ol nj u
E Ol C
L Cl nl I C
Cl C
L u 4
I In nju OJ nj C0 I/I X I V njW OJI/I~
0 C C~
0 Cl SL 't D L C 0 I/I /O 0 0 t 0 t olu c ahCt I
ns ol /0 nl Lj WZZ OJu OJ t
U 0
~t OJ D
ah nj O OO CI
~t
/lju 0 0 I/I I L.
CJI Cll 0
0 I
S CL CL OI C
C 0Ih I0 L
ah taj
~
0 a C
Ih 0
C 0
Z Ol V V
Cl O
C Ih IO W
L
~
'D OJ
'0 C
nl nj C
CL OJ I
0Ijj Cl II/l D
I/I C
CS nj L,
Ih 3
'0 CJ Cl S
U 0
0 a
OJ L
Ol OO SL SL E
Ol C
0 I/I C
L.
nj
~
Cti0 nj CL U
O O
t nj u
0 V
I In c
u ol cl OJ C
an OI 0
0 C'l V
D nl ISO ah Cl V
D an u
Cl
~
I 0
U In 0
U 0
4-Ol L
au ns CL CL CI E:
i 50.36a Technlical specifications on effluents from nuclear power reactors Remain within limits of Si 20.106 Establish and follow procedures to control eff luents Haintain and use radioactive waste system equipment Submit re orts semi-annual and other 0.
c
. 06 g
0.
05 c omp ance w t 40 CFR 190 e o eoep 0
e oooo 0 ~
04i P
~ epo 0 ep
~ara ppeeea>>
Criterion 60-Criterion 61-Criterion 63-Criterion 64-enera es>gn Cr teria Control of releases of radioactive materials to the environment Fuel storage and handling and radioactivity control flonitoring fuel and waste storage Honitorin radioactivit'eleases e ~ p 0
art en
>x 0 -
ua 1t ssurance Crl teria art 50 ppend x
I -
u des to Hect " s Low s is Reasonably Achievable (ALARA)"
Haintain releases within design objectives.
Establish surveillance E monitoring program to provide data on:
(1) quantities of rad. matls.
in effluents (2) radiation l rad. matls.
in the environment
~
(3) changes in use of unrestricted areas Exert best efforts to keep releases "ALARA" Submit report if calculated doses exceed the design objective Oemonstrate conform. to des.
ob b
calc.
roced.
petra 00
'Rote:
Weeded to fully implement other specif ications.
BO OQ o
de P
ee o
0
- 3. 0 EVALUATION The enclosed report (TER-C5506-117) was prepared by Franklin Research Center (FRC) as part of our technical assistance contract program.
Their report provides their technical evaluation of the compliance of the licensee's submittal with HRC provided criteria.
We have reviewed the FRC report and concur with the conclusions therein.
3.1.
SUMMARY
The proposed changes to the radiological effluent technical speci--
fications for the R.
E. Ginna Nuclear Power Plant have been evaluated,
- reviewed, and found to be in compliance with the require-ments of the HRC regulations and with the intent of NUREG-0133 and NUREG-0472 (the Ginna plant is comprised of one pressurized water reactor) and thereby fulfillall the requirements of the regulations related to radiological effluent technical specifications.
The proposed changes would not remove or relax any existing requirement related to the probability or consequences of accidents previously considered and do not involve a significant hazards consideration.
The proposed changes would not remove or relax any existing requirement needed to provide reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner.
The staff therefore, finds the proposed changes acceptable.
- 4. 0 ENVIRONMENTAL CONSIDERATIONS We have determined that the issuance of the proposed amendment to the Technical Specifications appended to Provisional Operating License Ho.
OPR-18 for R. E. Ginna Nuclear Power Plant would not authorize a
significant change in the types, or a significant increase in the
- amounts, of effluents or in the authorized power level, and that the
'mendment will not result in any significant environmental impact.
Having made these determinations, we have further. concluded that the amendment involves 'an action which is insignificant from the stand-.
point of environmental impact and, pursuant to 10 CFR Part 51.5(d)(4),
that environmental impact statement or negative declaration, and environmental impact appraisal need not be prepared in connection with the issuance of this amendment.
5.0 CONCLUSION
We have concluded, based on the considerations discussed above, that:
(1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed
- manner, and (2) such activities will be conducted in compliance with the Commission
's regulations and the issuance of this amendment will not be inimical to the common defense and security or the health and safety of the public.
- 6. 0 ACKNOWLEDGEMENT W. Meinke contributed to this evaluation.
Attachment:
TER dated 01/19/83 pate:
September 28, 1983
The requirement for participation in an interlaboratory comparison program is provided to ensure that independent checks on the precision and accuracy of the mes'surements, of radioactive material in environmental sample matrices are performed as part of a quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid.
Only samples with radioactivity levels comparable to levels in environmental samples need be analyzed.
3.16-6 Amendment No.: