ML20128G040
| ML20128G040 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 06/28/1985 |
| From: | NRC |
| To: | |
| Shared Package | |
| ML20128G043 | List: |
| References | |
| NUDOCS 8507090019 | |
| Download: ML20128G040 (19) | |
Text
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ATTACHvENT TO LICENSE AMENOMENT NO. 39 FACILITY OPERATING LICENSE NO. OPR-77 DOCKET NO. 50-327 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change.
Amended Page 3/4 4-15a 3/4 7-21 3/4 7-25 3/4 7-26 3/4 7-27 3/4 7-28 B3/4 7-6 B3/4 7-7 83/4 7-8 6-23 8507090019 850628 PDR ADOCK 05000327 P
- PDR,
TABLE 3.4-1 i
REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVES VALVE NUMBER FUNCTION 63-560 Accumulator Discharge 63-561 Accumulator Discharge 63-562 Accumulator Discharge i
63-563 Accumulator Discharge 63-622 Accumulator Discharge 63-623 Accumulator Discharge 63-624 Accumulator Discharge i
63-625 Accumulator Discharge 63-551 Safety Injection (Cold Leg)63-553 Safety Injection (Cold Leg)63-557 Safety Injection (Cold Leg) 4'63-555 Safety Injection (Cold Leg)
)63-632 Residual Heat Removal (Cold Leg)63-633 Residual Heat Removal (Cold Leg) j 63-634 Residual Heat Removal (Cold Leg)63-635 Residual Heat Removal (Cold Leg)63-641 Residual Heat Removal / Safety Injection (Hot Leg)63-644 Residual Heat Removal / Safety Injection (Hot Leg)63-558 Safety Injection (Hot Leg)63-559 Safety Injection (Hot Leg)63-543 Safety Injection (Hot Leg)63-545 Safety Injection (Hot Leg)63-547 Safety Injection (Hot Leg)63-549 Safety Injection (Hot Leg)63-640 Residual Heat Removal (Hot Leg)63-643 Residual Heat Removal (Hot Leg)87-558 Upper Head Injection 87-559 Upper Head Injection l
87-560 Upper Head Injection 87-561 Upper Head Injection 87-562 Upper Head Injection l
87-563 Upper Head Injection FCV-74-1*
Residual Heat Removal FCV-74-2*
Residual Heat Removal "These valves do not have to be leak tested following manual or automatic actuation or flow through the valve.
SEQUOYAH - UNIT 1 3/4 4-15a Amendment No.39
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PLANT SYSTEMS 3/4.7.9 SNUBBERS LIMITING CONDITION FOR OPERATION 1
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3.7.9.
All safety-related snubbers shall be OPERABLE.
I APPLICABILITY: MODES 1, 2, 3 and 4.
(MODES 5 and 6 for snubbers located on 2
systems or partial systems required OPERABLE in those MODES.)
ACTION:
l With one or more snubbers inoperable, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> replace or restore the inoperable snubber (s) to OPERABLE status and perform an engineering evaluation on the attached component or declare the attached system inoperable and follow the appropriate ACTION statement for that system.
i SURVEILLANCE REQUIREMENTS 4.7.9.
Each safety-related snubber shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program and the requirements 4
of Specification 4.0.5.
t a.
Inspection Groups The snubbers may be categorized into two major groups based on whether the snubbers are accessible or inaccessible during reactor operation.
These major groups may be further subdivided into subgroups based on design, environment, or other features which may be expected to affect the OPERABILITY of the snubbers within the subgroup. Each subgroup or group may be inspected independently in accordance with 4.7.9.b through 4.7.9.h.
i b.
Visual Inspection Schedule and Lot Size The first inservice visual inspection of snubbers shall be completed by October 31, 1981, and shall include all snubbers on safety related systems.
i If less than two (2) snubbers are found inoperable during the first inservice visual inspection, the second inservice visual inspection shall be performed 18 months i 25% from the date of the first inspection or during an outage of sufficient duration (at least 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in Mode 5). Otherwise, subsequent visual inspections shall be performed in accordance with the following schedule:
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SEQUOYAH - UNIT 1 3/4 7-21 Amendment No. 39
t PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 1.
Snubber Service Life Program (Continued) expire during a period when the snubber is required to be operable. The seal replacements shall be documented and the documentation shall be retained in accordance with 6.10.2.n.
Mechanical snubber drag force increases greater than 50 percent of previously measured values shall be evaluated as an indication of impending failure of the snubber. These evaluations and any associated corrective action shall be documented and the documentation shall be retained in accordance with 6.10.2.n.
j.
Exemption From Visual Inspection or Functional Tests Permanent or other exemptions from the surveillance program for individual snubbers may be granted by the Commission if a justifiable basis for exemption is presented and if applicable snubber life destructive testing was performed to qualify snubber operability for the applicable design conditions at either the completion of their fabrication or at a subsequent date.
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SEQUOYAH - UNIT 1 3/4 7-27 Amendment No. 39
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i SE@0YAH - UNIT 1 3/4 7-28 Amendment No. 39
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PLANT SYSTEMS BASES SNUBBERS (Continued) that may be generically susceptible and operability verified by inservice func-tional testing, if applicable, that snubber may be exempted from being counted as inoperable. Generically susceptible snubbers are those which are of a specific make or model and have the same design features directly related to rejection of the snubber, or are similarly located or exposed to the same environmental conditions such as temperature, radiation, and vibration.
Inspection groups may be established based on design features and installed conditions which may be expected to be generic. Each of these inspection groups are inspected and tested separately unless an enganeoring analysis indicates the inspection group is improperly constituteo. All suspect snub-bers are subject to inspection and testing regardless of inspection groupings.
To further increase the assurance of snubber reliability, functional tests shall be performed during each refueling outage. These tests will include stroking of the snubbers to verify proper movement, activation, and bleed or release. The performance of hydraulic snubbers generally depends on a clean, deaerated fluid contained within variable pressure chambers, flowing at closely controlled rates. Since these characteristics are subject to change with expo-sure to the reactor environment, time, and other factors, their performance within the specified range should be verified. Mechanical snubbers which depend upon overcoming the inertia of a mass and the braking action of a capstan spring contained within the snubber for limiting the acceleration of the attached compo-nent (within the load rating of the snubber) are not subject to changes in per-formance in the same manner as hydraulic snubbers. Pending the development of information regarding the change during the service of the snubber of the acceleration / resistance relationship and the optimum method for detecting this change, these mechanical snubbers may be tested to verify that when subjected to a large change in velocity the resistance to movement increases greatly.
The performance change information is to be developed in order to establish test methods to be used during and after the first refueling outage.
Ten percent of the total population of approximately 700 snubbers is an adequate sample for functional tests. The initial sample is to be proportioned among the groups in order to obtain a representative sample. Observed failures of more than two snubbers in the initial lot will require an engineering analysis and testing of additional snubbers selected from snubbers likely to have the same defect. A thorough inspection of the snubber threaded attach-ments to the pipe or components and the anchorage will be made in conjunction with all required functional tests.
A list of individual snubbers with detailed information of snubber loca-tion and size shall be available at the plant in accordance with Section 50.71(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, SEQUOYAll - UNIT 1 B 3/4 7-6 Amendment No. 39
s PLANT SYSTEMS BASES SNUBBERS (Continued) location, etc.), and the recommendations of Regulatory Guide 8.8 and 8.10.
The addition or deletion of any hydraulic or mechanical snubber shall be made in accordance with Section 50.59 of 10 CFR Part 50.
3/4.7.10 SEALED SOURCE CONTAMINATION The limitations on removable contamination for sources requiring leak test-ing, including alpha emitters, is based on 10 CFR 70.39(c) limits for plutonium.
This limitation will ensure that leakage from byproduct, source, and special nuclear material sources will not exceed allowable intake values. Sealed sources are classified into three groups according to their use, with surveil-lance 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 continu-ously enclosed within a shielded mechanism (i.e., sealed sources within radia-tion monitoring or boron measuring devices) are considered to be stored and need not be tested unless they are removed from the shielded mechanism.
3/4.7.11 FIRE SUPPRESSION SYSTEMS The OPERABILITY of the fire suppression systems ensures that adequate fire suppression capability is available to confine and extinguish fires occuring 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
the fire suppression systems is 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
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the affected areas until the inoperable equipment is restored to service.
When the inoperable fire fighting equipment is intended for use as a backup means of fire suppression, a longer period of time is allowed to provide an alternate means of fire fighting than if the inoperable equipment is the l
primary means of fire suppression.
The surveillance requirements provide assurance that the minimum OPERABILITY requirements of the fire suppression systems are met.
In the event the fire suppression water system becomes inoperable, immediate j
corrective measures must be taken since this system provides the major fire l
suppression capability of the plant. The requirement for a twenty-four 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.
I SEQUOYAH - UNIT 1 B 3/4 7-7 Amendment No. 39 I.
PLANT SYSTEMS BASES 3/4.7.12 FIRE BARRIER PENETRATIONS The functional integrity of the fire barrier penetrations ensures that fires will be confined or adequately retarded from spreading to adjacent portions of the facility. This design feature minimizes the possibility of a single fire rapidly involving several areas of the facility prior to detection and extinguishment. The fire barrier penetrations are a passive element in the facility fire protection program and are subject to periodic inspections.
Fire barrier penetrations, including cable penetration barriers, fire doors and dampers are considered functional when the visually observed condi-tion is the same as the as-designed condition. For those fire barrier penetrations that are not in the as-designed condition, an evaluation shall be performed to show that the modification has not degraded the fire rating of the fire barrier penetration.
3 During periods of time when a barrier is not functional, either,1) a continuous fire watch is required to be maintained in the vicinity of the affected barrier, or 2) the fire detectors on at least one side of the affected barrier must be verified OPERABLE and a hourly fire watch patrol established,
-5 until the barrier is restored to functional status.
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SEQUOYAH - UNIT 1 B 3/4 7-8 Amendment No. 39 I
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ADMINISTRATIVE CONTROLS 6.10.2 The following records shall be retained for the duration of the Unit Operating License:
a.
Records and drawing changes reflecting unit design modifications made to systems and equipment described in the Final Safety Analysis Report.
b.
Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.
c.
Records of radiation exposure for all individuals entering radiation control areas.
d.
Records of gaseous and liquid radioactive material released to the environs.
e.
Records of transient or operational cycles for those unit components identified in Table 5.7-1.
f.
Records of reactor tests and experiments.
g.
Records of training and qualification for current members of the unit staff.
h.
Reco'rds of in-service inspections performed pursuant to these Technical Specifications.
i.
Records of Quality Assurance activities required by the Operational Quality Assurance Manual.
j.
Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.
k.
Records of meetings of the PORC, RARC, and the NSRB.
1.
Records of analyses required by the radiological environmental monitoring program.
m.
Records of secondary water sampling and water quality.
n.
Records of the service life monitoring of all safety-related hydraulic and mechanical snubbers, required by T/S 3.'29, including the maintenance performed to renew the service life.
o.
Records for Environmental Qualification which are covered under the provisions of Paragraph 2.c.(12)(6) of License No. DPR-77.
6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adherea to for all operations involving personnel radiation exposure.
SEQUOYAH - UNIT 1 6-23 Amendment No. 39
G ATTACHMENT TO LICENSE AMENDMENT NO. 31 FACILITY OPERATING LICENSE NO. DPR-79 DOCKET NO. 50-378 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amenchnent number and contain vertical lines indicating the areas of change.
Amended Page 3/4 7-21 3/4 7-25 3/4 7-26 3/4 7-27 3/4 7-28 R3/4 7-6a 6-29 l
PLANT SYSTEMS 3/4.7.9 SNUBBERS LIMITING CONDITION FOR OPERATION 3.7.9 All safety-related snubbers shall be OPERABLE.
APPLICABILITY: MODES 1, 2, 3 and 4.
(MODES 5 and 6 for snubbers located on systems or partial systems required OPERABLE in those MODES.)
ACTION:
With one or more snubbers inoperable, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> replace or restore the inoperable snubber (s) to OPERABLE status and perform an engineering evaluation on the attached component or declare the attached system inoperable and follow the appropriate ACTION statement for that system.
SURVEILLANCE R'QUIREMENTS E
4.7.9 Each safety-related snubber shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program and the requirements of Specification 4.0.5.
a.
Inspection Groups The snubbers may be categorized into two major groups based on whether the snubbers are accessible or inaccessible during reactor operation. These major groups may be further subdivided into subgroups based on design, environment, or other features which may be expected to affect the OPERABILITY of the snubbers within the subgroup. Each subgroup or group may be inspected independently in accordance with 4.7.9.b through 4.7.9.h.
b.
Visual Inspection Schedule The first inservice visual inspection of snubbers shall be performed after 4 months but within 10 months of commencing POWER OPERATION and shall include all snubbers on safety-related systems. If less than two (2) snubbers are found inoperable during the first inservice l
SEQUOYAH - UNIT 2 3/4 7-21 Amendment No. 31 l
PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) g.
Functional Test Failure - Attached Component Analysis For snubbers (s) found inoperable, an engineering evaluation shall be performed on the components which are restrained by the snubber (s).
The purpose of this engineering evaluation shall be to determine if the components restrained by the snubber (s) were adversely affected by the inoperability of the snubbers (s), and in order to ensure that the restrained component remains capable of meeting the designed service.
h.
Functional Testing of Repaired and Spare Snubbers Snubbers which fail the visual inspection or the functional test acceptance criteria shall be repaired or replaced. Replacement 4
snubbers and snubbers which have repairs which might affect the functional test results shall be tested to meet the funtional test criteria before installation in the unit. These snubbers shall have met the acceptance criteria subsequent to their most recent service, and the functional test must have been performed within 12 months i
before being installed in the unit.
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Snubber Service Life Program The seal service life of hydraulic snubbers shall be monitored to ensure that the seals do not fail between surveillance inspections.
The maximum expected service life for the various seals, seal materials, and applications shall be estimated based on engineering information, and the seals shall be replaced so that the maximum i
expected service life does not expire during a period when the snubber is required to be operabyle. The seal replacements shall be documented and the documentation shall be retained in accordance wth 6.10.2.n.
Mechanical snubber drag force increases greater than 50 percent of previously measured values shall be evaluated as an indication of impending. failure of the snubber. These evaluations and any associated corrective action, shall be documented, and the documentation shall be retained in accordance with 6.10.2.n.
i j.
Exemption From Visual Inspection or Functional Tests Permanent or other exemptions fors'the surveillance program for individual snubbers may be granted by the Commission if a justifiable basis for exemption is presented and if applicable snubber life destructive testing was performed to qualify snubber operability for the applicable design conditions at either the completion of their fabrication or at a subsequent date.
f SEQUOYAH - UNIT 2-3/4 7-25 Amendment No. 31 4
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SEQUOYAH - UNIT 2 3/4 7-27 Amendment No. 31
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t SEQUOYAH - UNIT 2 3/4 7-28 Amendment No. 31 l
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G BASES 3/4.7.9 SNUBBERS (cont'd)
A list of individual snubbers with detailed information of snubber location and size shall be available at the plant in accordance with Section 50.71(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 be made in accordance with Section 50.59 of 10 CFR Part 50.
3/4.7.10 SEALED SOURCE CONTAMINATION The limitations on removable contamination for sources requiring leak testing, including alpha emitters, based on 10 CFR 70.39(c) limits for plutonium. This limitation will ensure that leakage from byproduct, 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 within radiation monitoring or boron measuring devices) are considered to be stored and need not be tested unless they are removed from the shielded mechanism.
SEQUOYAH - UNIT 2 B 3/4 7-6a Amendment No. 31
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ADMINISTRATIVE CONTROLS 6.10.2 (Continued)
Records of secondary water sampling and water quality.
m.
Records of the service life monitoring of all safety-related hy-n.
draulic and mechanical snubbers, required by T/S 3.7.9, including the maintenance performed to renew the service life.
6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.
6.12 HIGH RADIATION AREA 6.12.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.203(c) (2) of 10 CFR 20, each high radiation area in which the intensity of radiation is greater than 100 mrem /hr but less than 1000 mrem /hr shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Special (Radiation)
Work Permit *. Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:
A radiation monitoring device which continuously indicates the a.
radiation dose rate in the area.
b.
A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received. Entry into such areas with this monitoring device may be made after the dose rate level in the area has been established and personnel have been made knowledgeable of them.
c.
An individual qualified in radiation protection procedures who is equipped with a radiation dose rate monitoring device. This individual shall be responsible for providing positive control over the activities within the area and shall perform control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the facility Health Physicist in the Special (Radiation) Work Pernit.
6.12.2 The requirements of 6.12.1, above, shall also apply to each high radiation area in which the intensity of radiation is greater than 1000 mrem /hr.
In addition, locked doors shall be provided to prevent unauthorized entry into such areas and the keys shall be maintained under the administrative control of the Shift Engineer on duty and/or the Health Physicist.
" Health Physics personnel or personnel escorted by Health Physics personnel in accordance with approved emergency procedures, shall be exempt from the SWP issuance requirement during the performance of their assigned radiation protection duties, provided they comply with approved radiation protection procedures for entry into high radiation areas.
SEQUOYAH - UNIT 2 6-29 Amendment No. 31