ML20101J909
| ML20101J909 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 03/28/1996 |
| From: | NORTHEAST NUCLEAR ENERGY CO. |
| To: | |
| Shared Package | |
| ML20101J903 | List: |
| References | |
| NUDOCS 9604020185 | |
| Download: ML20101J909 (6) | |
Text
.
Docket No. 50-336 B15464 Millstone Nuclear Power Station, Unit No. 2 Proposed Technical Specifications Revision Sealed Source contamination Marked-up Version of Current Technical Specifications March 1996 9604020105 960328 PDR ADOCK 05000336 P
[.. '
obruary 26,19 PLANT SYSTEMS 3/4.7.7 SEALED SOURCE CONTAMINATION LIMITING CONDITION FOR OPERATION 3.7.7.1 Each sealed source containing radioactive material either in excess jef J.;;; q;:ntitte: Of by;r:d :t ::t:ri9 li:t:d '- 10 CP 30.71 ;r 0.1 J
(;icr;;;ri::, in;hdin;; ebh; ea'tter_,yshall be free of 2 D.005 microcuries of removable contamination.
w too microcurs'as. btb a.c.J/w
,,.,g g g,g,g (, g g,,,c,,;,3 %. a.
APPLICABILITY: AT All TIMES.
,,i ACTION:
"If
'
- O "O * ^h" I" I
~ Each sealed source with removable contamination in excess of the a.
above limit shall be immediately withdrawn from use and:
1.
Either decontaminated and repaired, or 2.
Disposed of in accordance with Commission Regulations.
b.
The provisions of Specification 3.0.3 are not applicable.
j SURVEILLANCE REQUIREMENTS 4.7.7.1.1 Test Recuirements - Each sealed source shall be tested for leakage and/or contamination by:
a.
The licensee, or b.
Other persor,s specifically authorized by the Commission or an Agreement State.
The test method shall have a detection sensitivity of at least 0.005 microcuries per test skmple.
4.7.7.1.2 Test Frecuencies - Each category of sealed sources shall be tested at the frequencies described below.
Sources in use (excludino startue sources ereviously subiected to a.
core flux) - At least once per six months for all sealed sources containing radioactive material:
MILLSyE-UNIT 2 3/4 7-19 AmendmentNo.[
l_.
j g.
Septe'aber 1 1987 l.
(,M@
PLANT 5YSTEMS BASES 3/4.7.7 SE ALED SOURCE CONTAMINAT N The ilmitations on sealed source r movable contamination ensure that the total body or individual organ irradiati does not exceed allowable ilmits in the event of ingestion or inhalation of source material. The ilmitations on removable contamination for sou requiring leak testing, including alpha i
emitters,is based on 10 CFR 70.3 'c) imits for plutonium. Leakage of sources less than excluded from the requirements of this specification represent one maximum permissible body burden for total body irradiation if the source j
material is inhaled or ingested.
3/4.7.8 SNUBBERS All snubbers are required OPERABLE to ensure that the structural integrity of the reactor coolant system and a!! other safety-related systems is maintained during and following a seismic or other event Initiating dynamic Snubbers excluded from this inspection program are those installed on loads.
norrsafety-related systems and then only if their failure or failure of the system en which they are installed would have no adverse effect on any safety-related system.
A list of individual snubbers with detailed information of snubber location and size and of system affected shall be available at the plant in accordance with 5ection 50.7)(c)of 10 CFR Part 50. The accessibility of each snubber shall be determined and approved by the Plant operations Review Committee. The determination shall be based upon the existing radiation levels and the expected time to perform a visual inspection in each snubber location as well as other factors associated with accessibility during plant operations (e.g., temperature, atmosphere, location, etc.), and the recommendations of Regulatory Guide 8.8 and 8.10. The addition or deletion of any hydraulic or mechanical snubber shall j
he made in accordance with Section 30.59 of 10 CFR Part 30.
The visual inspection frequency is based upon maintaining a constant level Therefore, the required inspection interval af snubber protection to systems.
varies inversely with the observed snubber failures and is determined by the trumber of inoperable snubbers found during an inspection. Inspections performed before that interval has elapsed may be used as a new reference point to However, the results of such early inspections determine the next inspection.
performed before the original required time interval has elapsed (nominal time less 25%) may not be used to lengthen the required inspection interval. Any inspection whose results require a shorter inspection interval wii! override the previous schedule.
\\
AmendeentMos./,[76,g ME.1.5 TONE - UNIT 2 83/47-5
- - _ ~ ~ _
1 Docket No. 50-33_6 B15464 Millstone Nuclear Power Station, Unit No. 2 Proposed Technical Specifications Revision Sealed Source Contamination 1
Retyped Technical Specifications I
l l
i i
i i
1 l
1 l
I j
March 1996 1
PLANT SYSTENS 3/4.7.7 SEALED SOURCE CONTANINATION LIMITING COPWITION FOR OPERATION 3.7.7.1 Each sealed source containing radioactive material either in excess of 100 microcuries of beta and/or gamma emitting material or 5 microcuries of alpha emitting material shall be free of 10.005 microcuries of removable contamination.
APPLICABILITY: AT ALL TINES.
l ACTION:
a.
Each sealed source with removable contamination in excess of the above limit shall be immaMately withdrawn from use and:
1.
Either decontaminated and repaired, or 2.
Disposed of in accordance with Commission Regulations.
I 4
b.
The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS l
4.7.7.1.1 Test Reauirements - Each sealed source shall be tested for leakage and/cr contamination by:
a.
The licensee, or i
b.
Other persons specifically authorized by the Commission or an Agreement State.
The test method shall have a detection sensitivity of at least 0.005 l
microcuries per test sample.
4.7.7.1.2 Test Freauencies - Each category of sealed sources shall be tested at the frequencies described below, l
a.
Sources in use (excludina startuo sources previousiv subiected to core flux) - At least once per six months for all sealed sources containing radioactive material:
l I
I MILLSTONE - UNIT 2 3/4 7-19 Amendment No. JJJ, 02C6 l
i PLANT SYSTEMS 1
j BASES d
J 3/4.7.7 SEALED SOURCE CONTAMINATION The limitations on sealed source removable contamination ensure that the total body or individual organ irradiation does not exceed allowable limits in the j
event of ingestion or inhalation of the source material.
The limitations on
{
removable contamination for sources requiring leak testing, including alpha emitters, is based on 10 CFR 70.39(a)(3) limits for plutonium.
Leakageofsourcesl excluded from the requirements of this specification represent less than j
one maximum permissible body burden for total body irradiation if the source i
material is inhaled or ingested.
3/4.7.8 SNUBBERS f
1 l
All snubbers are required OPERABLE to ensure that the structural integrity of the reactor coolant system and all other safety related systems is 1
maintained during and following a seismic or other event initiating dynamic j
loads.
Snubbers excluded from this inspection program are those installed on i
nonsafety-related systems and then only if their failure or failure of the system 1
on which they are installed would have no adverse effect on any safety-related system.
A list of individual snubbers with detailed information of snubber location and size and of system affected shall be available at the plant in accordance with Section 50.71(c) of 10 CFR Part 50.
The accessibility of each snubber shall i
be determined and approved by the Plant Operations Review Committee.
The determination shall be based upon the existing radiation levels and the expected time to perform a visual inspection in each snubber location as well as other factors associated with accessibility during plant operations (e.g., temperature, atmosphere, location, etc.), and the recommendations of Regulatory Guide 8.8 and 8.10.
The addition or deletion of any hydraulic or mechanic snubber shall
,j be made in accordance with Section 50.59 of 10 CFR Part 50.
i The visual inspection frequency is based upon maintaining a constant level of snubber protection to systems.
Therefore, the required inspection interval i
varies inversely with the observed snubber failures end is determined by the number of inoperable snubbers found during an inspection.
Inspections performed i
before that interval has elapsed may be used as a new reference point to determine the next inspection.
However, the results of such early inspections performed before the original required time interval has elapsed (nominal time j
less 25%) may not be used to lengthen the required inspection interval.
Any j
inspection whose results require a shorter inspection interval will override the j
previous schedule.
NILLSTONE - UNIT 2 8 3/4 7-5 Amendment Nos. JJ, J), pp, JJ7, 0268