ML20135A840
| ML20135A840 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 08/28/1985 |
| From: | CAROLINA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20135A808 | List: |
| References | |
| (85TSB08), (85TSB8), NUDOCS 8509100290 | |
| Download: ML20135A840 (6) | |
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l ENCLOSURE 1 TO NLS-85-066 PROPOSED TECHNICAL SPECIFICATION PAGES BRUNSWICK-1 SEALED SOURCE CONTAMINATION (85TSB08) 1 1
i OS 91 O g
4 g
(1197NLU/crs)
P
l l
l Summary List of Revisions Brunswick-1 Page No.
Description B 3/4 7-4 Replace TS basis 3/4.7.6 to be consistent with GE BWR/4 STS ei I
n 4
2 0
l 4
1 4
4 i
4 s
d.
L l
t (1197NLU/crs) l
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'~
(BSEP-1-53)
PLANT SYSTEMS BASES (Continued)
SNUBBERS (Continued)
The service life of a snubber is established via manufacturer input and information through consideration of the snubber cervice conditions and associated installation and maintenance records (newly installed snubber, seal replaced. spring replaced, in high radiation area, in high temperature area, Ltc.).
The requirement to monitor the snubber service life is included to ensure that the snubbers periodically undergo a performance evaluation in view of their age and operating conditions. These records will provide statistical bases for future consideration of snubber service life.
3/4.7.6 SEALED SOURCE CONTAMINATION The limitation on removable contamination for sources requiring leak testing, including alpha emitters, is based on.10 CFR 70.39(c) Limits for plutonium. This limitation will ensure that igakage from by product, source, and special nuclear material sources will not exceed allowable intake values. Sealed sources are classified into three groups according to their use, with surveillance requirements commensurate with the probability of damage to a source in that group. Those sources which are frequently handled are required to be tested more often than those which are not.
Sealed sources which are continuously enclosed within a shielded mechanism, i.e., sealed sources with radiation monitoring or boron measuring devices, are considered
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to be stored and need not be tested unless they are removed from the shielding mechanism.
3/4.7.7 FIRE SUPPRESSION SYSTEMS The OPERABILITY of the fire suppression systems ensures that adequate fire suppression capability is available to confine and extinguish fires occurring in any portion of the facility where safety-related equipment j
is located. The fire suppression system consists of the water system, spray and/or sprinklers, CO, and fire hose stations. The collective capability of 2
the fire suppression systems i~s adequate to minimize potential damage to safety-related equipment and is a major element in the facility fire protection program.
In the event that portions of the fire suppression systems are inoperable, alternate backup fire fighting equipment is required to be made available in the affected areas until the inoperable equipment is restored to service.
1 In the event the fire suppression water system become inoperable, immediate corrective measures must be taken since this system provides the major fire suppression capability of the plant..The requirement for a 24-hour report to the Commission provides for prompt evaluation of the acceptability of the corrective measures to provide adequate fire' suppression capability for the continued protection of the nuclear plant.
BRUNSWICK - UNIT 1 B 3/4 7-4 Amendment No.
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j 4
4 ENCLOSURE 2 TO NLS-85-066 PROPOSED TECHNICAL SPECIFICATION PAGES BRUNSWICK-2 SEALED SOURCE CONTAMINATION (85T5808) 7 i
o j
j 1
(1197NLU/ces)
f Summary List of Revisions 1
Brunswick-2 Page No.
Description B 3/4 7-4 Replace TS basis 3/4.7.6 to be consistent with GE BWR/4 STS 4
)
l i
4 e
d 4
i l
Y (1197NLU/crs)
j.
- e (BSEP-2-48)
PLANT SYSTEMS BASES (Continued)
SNUB 3ERS (Continued)
The service life of a snubber is established via manufacturer input and information through consideration of the snubber service conditions and associated installation and maintenance records (newly installed snubber, seal replaced, spring replaced, in high radiation area, in high temperature area, etc.).
The requirement to monitor the snubber service life is included to ensure that the snubbers periodically undergo a performance evaluation in view of their age and operating conditions. These records will provide statistical bases for future consideration of snubber service life.
3/4.7.6 SEALED SOURCE CONTAMINATION The limitation on removable contamination for sources requiring Leak testing, including alpha emitters, is based on 10 CFR 70.39(c) Limits for i
plutonium. This limitation will ensure that leakage from by product, source, and special nuclear material sources will not exceed allowable intake values. Sealed sources are classified into three groups according to their use, with surveillance requirements commensurate with the probability of damage to a source in that group. Those sources which are frequently handled are required to be tested more often than those which are not.
Sealed sources which are continuously enclosed within a shielded mechanism, i.e., sealed sources with radiation monitoring or boron measuring devices, are considered j
to be stored and need not be tested unless they are removed from the shielding i
mechanism.
i 3/4.7.7 FIRE SUPPRESSION SYSTEMS The OPERABILITY of the fire suppression systems ensures that adequate fire suppression capability is available to confine and extinguish i
fires occurring in any portion of the facility where safety-related equipment is located. The fire suppression system consists of the water system, spray and/or sprinklers, CO, and fire hose stations. The collective capability of 2
1 the fire suppression systems is adequate to minimize potential damage to safety-related equipment and is a major element in the facility fire l
protection program.
2 In the event that portions of the fire suppression systems are inoperable, alternate backup fire fighting equipment is required to be made available in the affected areas until the inoperable equipment is restored to service.
a In the event the fire suppression water system become inoperable, immediate corrective measures must be taken since this system provides the major fire suppression capability of the plant. The requirement for a 24-hour report to the Commission provides for prompt evaluation of the acceptability l
of the corrective measures to provide adequate fire suppression capability for the continued protection of the nuclear plant.
r BRUNSWICK - UNIT 2 B 3/4 7-4 Amendment No.
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