ML20011F282
| ML20011F282 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 02/16/1990 |
| From: | Black S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20011F283 | List: |
| References | |
| NUDOCS 9003050026 | |
| Download: ML20011F282 (15) | |
Text
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UNITED STATE 8 -
4 w-NUCLEAR RESULATCRY COMMISSION g
WASHINGTON. D. C. 30806 e
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TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-327 SE0VOYAH NUCLEAR PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.130 License No. ops-77 i
1.
The Nuclear' Regulatory Commission (the Commission) has found that:-
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated October 5,1989, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Commission's rules and regulations set forth in 10 CFR I
l Chapter I; i
B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; j ~.
C.
There is reasonable assurance-(1) that the activities authorized by this amendment can be conducted without endangering the health and safety of. the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
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Accordingly, the license is amended by changes to the Technical
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Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. OPR-77-is hereby amended to read as follows:
i (2) Technical Specifications j
The Technical Specifications contained in Appendices A and B, as I
revised through Amendment No.13.0, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance.
4-FOR THE NUCLEAR REGULATORY COMMISSION Suzanne B ck, Assistant Director for Projects TVA Projects Division Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: February 16, 1990 I
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ATTACHMENT TO LICENSE AMEN 0 MENT NL.130 FACILITY OPERATING LICENSE NO. DPR-77 DOCKET NO. 50-327 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain marginal' lines indicating the area of change. Overleaf pages* are provided to maintain document completeness.
REMOVE INSERT 1-1 1-1*
4 1-2 1-2 3/4 6 3/4 6-1 4
3/4 6-4 3/4 6-4 i
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,1. 0 OEFINITIONS l
DEFINED TERMS The defined terms of this section appear in capitalized type and are applicable throughout these Technical Specifications.
ACTION 1.1 ACTION shall'be that part of a Specification which prescribes remedial
.I measures required under designated conditions.
AXIAL FLUX 01FFERENCE
- 1.2 AXIAL FLUX DIFFERENCE shall be the difference in normalized flux signals between the top and bottom halves of a two section excore neutron detector.
BYPASS LEAKAGE PATH l
- 1. 3 A BYPASS LEAKAGE PATH is a potential path for leakage to escape from both L
the primary containment and annulus pressure boundary.
Only one type'of L
BYPASS LEAKAGE PATH is recognized:
a.
BYPASS LEAKAGE PATHS TO THE AUXILIARY BUILDING are those paths that would potentially allow leakage from the primary containment to circumvent the annulus secondary containment enclosure and escape L
directly to the Auxiliary Building secondary containment enclosure.
l' L
CHANNEL CALIBRATION L
l
- 1. 4 A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the l
channel output such that it responds with the necessary range and accuracy to H
known values of the parameter which the channel monitors.
The CHANNEL CALIBRA-TION shall ancompass the entire channel. including the sensor and alarm and/or trip furctions, and shall include the CHANNEL FUNCTIONAL TEST.
The CHANNEL CALIBRATION may be performed by any series of sequential, overlapping or total channel steps such that the entire channel is calibrated.
l CHANNEL CHECK
- 1. 5 A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation.
This determination shall include, where possible, comparison of the channel indication and/or status with other indica-tions and/or status derived from independent instrument channels meesuring the same parameter.
SEQUOYAH - UNIT 1 1-1 Amendment No. 12, 71 4
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5; DEFINITIONS CHANNEL FUNCTIONAL TEST 1.6 A CHANNEL FUNCTIONAL TEST shall be:
- a. -
Analog channels - the injection of a simulated signal into tne channel as close to the sensor as practicable to verify OPERABILITY including alarm and/or trip functions.
b.
Bistable channels - the injection of a simulated signal into the sensor to verify OPERABILITY including alarm and/or trip functions.
CONTAINMENT INTEGRITY 1.7 CONTAINMENT INTEGRITY shall exist when:
a.
All penetrations required to be closed during accident conditions are either:
1)
Capable of being closed by an OPERABLE containment automatic isolation valve system, or 2)
Closed by manual valves, blind flanges, or deactivated automatic valves secured in their closed positions, except as provided in Table 3.6-2 of Specification 3.6.3.
b.
All equipment hatches are closed and sealed, c.
Each air lock is in compliance with the requirements of Specification 3.6.1.3, d.
The containment leakage rates are within the limits of Specification 3.6.1.2, and e.
The sealing mechansim associated with each penetration (e.g.,
welds, bellows, or 0-rings) is OPERABLE.
CONTROLLED LEAKAGE
- 1. 8 CONTROLLED LEAKAGE shall be that seal water flow supplied to the reactor coolant pump seals.
i-CORE ALTERATION 1.9 CORE ALTERATION shall be the movement or manipulation of any component within the reactor pressure vessel with the vessel head removed and fuel in the-vessel.
Suspension of CORE ALTERATION shall not preclude completion of movement of a component to a safe conservative position.
SEQUOYAH - UNIT 1 1-2 Amendment No. 12, 71,130 J
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'3/4.6 CONTAIN:iENT SYSTEMS t
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-3/4'6.1 CONTAINMENT INTEGRITY LINITING CONDITION FOR OPERATION l
- 3. 6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained.
APPLICABILITY:
MODES 1, 2, 3 and 4.
ACTION:
Without primary CONTAINMENT INTEGRITY, restore CONTAINMENT INTEGRITY within one hour or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD 4
SHUTOOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated:
L a.
At least once per 31 days by verifying that all penetrations
- not capable of being closed by OPERABLE containm.ent automatic-isolation valves and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured in their positions, except as provided in Table 3.6-2 of Specification 3.6.3.
b.
By verifying ~ that each containment air lock is in compliance with the. requirements-of Specification 3.6.1,3.
c.
After each c~ losing of each penetration subject to Type B testing, except the containment-air locks, if opened following a Type A or B test, by leak rate testing the seal with gas at P,, 12 psig, and verifying that when the measured leakage rate for these seals is added to the leakage rates determined pursuant to Specification l
4.6.1.2.d for all other Type B and C penetrations, the combined 1.
I leakage rate is less than or equal to 0.60 L,.
"Except valves, blind flanges, and deactivated automatic valves which are located inside the annulus or containment and are locked, sealed or otherwise secured in the closed position.
These penetrations shall be verified closed during each COLD SHUTOOWN except that such verification need not be performed more often than once per 92 days.
SEQUOYAH - UNIT 1 3/4 6-1 Amendment No. 12, 130 A
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,gNTAINMENTSYSTEMS S,U,RVEILLANCE REQUIREMENTS (Continued) e.-
The combined bypass leakage rate to the auxiliary building shall be determinedtobelessthanorequalto0.25L;byapplicableTypeB and C tests at least once per 24 months except for penetrations which o
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!are not individually testable; penetrations not. individually. testable shall be determined to have no detectable leakage when tested with soap bubbles while the containment is pressurized to P, (12 psig) 6uring each Type A test.
L f.
By verifying that each containment air lock is in compliance 'with L
the requirements of Specification 3.6.1.3.
8 4
g.
Leakage from isolation valves that are sealed with fluid from a seal system may be excluded, subject to the provisions of Appendix J, i
Section III.C.3, when determining the combined leakage rate'provided the seal system and valves are pressurized to at least 1.10 P, (13.2 psig) and the seal system capacity is adequate to maintain system l.
pressure (or fluid head for the containment spray system and RHR spray system valves at penetrations 48A, 488, 49A and 498) for at least 30 days.
L h.
Type B tests for penetrations employing a continuous leakage L
monitoring -system shall be conducted at P, (12 psig) at intervals no -
greater than once per 3 years.
i.
All test leakage rates shall be calculated using observed data E
converted to absolute values.
Error analyses shall be performed to select a balanced integrated leakage measurement system.
J.
The provisions of Specification-4.0.2 are not applicable.
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L SEQUOYAH - UNIT 1 3/4 6-4 Amendment No. 12, 71, 101 130 s
Revised 3/15/89 l
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NUCLEAR RECULATORY COMMISSION 1
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WASHINGTON, 0, C. 20585 '
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'l TENNESSEE VALLEY AUTHORITY 1
l DOCKET NO. 50-328' SE0VOYAH NUCLEARPLANT,UNIM AMENDMENT TO FACILITY OPERATING LICENSE 4
4 E
Amendment No.117 License No. DPR-79 1.
The Nuclear Regulatory Commission (the Comission) has found that:-
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated October 5, '1989, complies with the standards and l-
' requirements of the Atomic Energy Act of 1954, as ' amended (the Act),
L dnd the Commission's rules and regulations set forth in 10 CFR
. Chapter I; B.
The facilicy will operate in conformity with the application, the p
provisions of the Act, and the rules and regulations of the
.i Commission; C.-
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.
The issuance of this-amendment is in accordance with 10 CFR Part El i
of the Commission's regulations and all applicable requirements have been satisfied.
4
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,i '
2.
'Accordingly, the license is amended by changes to the Technical Specifications as indicated in the att&chment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. DPR-79 is hereby '
amended to read as. follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.117, are hereby incorporated in.the license.
The licensee shall operate the facility in occordance with the Technical Specifications.
4 3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR-REGULATORY COMMISSION Suzanne Black, Assistant Ofrector for Projects TVA Projects Divisicn Office of Nuclear Reactor Regulation f
Attachment:
l Changes to the Technical Specifications Date of Issuance: February 16, 1990 t-i l
L l
f5-1 4
1
~
e ATTACHMENT-TO LICENSE AMENDMENT NO. 117 FACILITY OPERATING LICENSE NO. OPR-7_9 DOCKET NO. 50-328 l-Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by the captioned emendment number and contain marginal lines indicating the area of change.
Overleaf pages* are provided to maintain document completeness.
REMOVE INSERT 1-1 1-1*
4 1-2 1-2 3/4 6-1 3/4 6-1 3/4 Ge2 3/4 6-2*
3/4 6-4 3/4 6-4 L
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l-
4
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' 1.0- DEFINITIONS DEFINED TERMS The defined terms of this section appear in capitalized type and are applicable throughout these Technical Specifications.
ACTION 1.1 ACTION shall be that part of a Specificatior which preteribes remedial.
measures required under designated conditions.
AXIAL FLUX DIFFERENCE 4
1.2 AXIAL FLUX DIFFERENCE shall be the difference in normalized flux signals between the top and bottom halves of a two section excore neutron detector.
BYPASS LEAKAGE PATH
- 1. 3 A BYPASS LEAKAGE PATH is a potential path for leakage to escape from both the primary containment and annulus pressure boundary.
Only one typa x
of BYPASS LEAKAGE PATH is recognized:
a.
BYPASS LEAKAGE PATHS TO THE AUXILIARY BUILDING are those paths that would potentially allow leakage from the primary containment to circumvent the annulus secondary containment enclosure and escape directly to the auxiliary building secondary containment enclosure.
I CHANNEL CALIBRATION l
L 1.4 A CHANNEL CALIBRATION shall-be.the adjustment, as necessary, of the channel output such that it responds with the necessary range and accuracy to known values of the parameter which the channel monitors. - The CHANNEL CALI-BRATION shall encompass the entire channel including the sensor and alarm l
and/or trip functions, and shall include the CHANNEL FUNCTIONAL TEST.
The L
CHANNEL CALIBRATION may be performed by any series of sequential, overlapping or total' channel steps such that the entire channel is calibrated.
CHANNEL CHECK 1.5 A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation.
This determination shall include, where possible, comparison of the channel indication hnd/or status with other indications and/or status derived from independent instrument channels measuring the same parameter.
SEQUOYAH - UNIT 2 1-1 Amendment No. 63 4
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1 1
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- DEFINITIONS CPANNEL FUNCTIONAL TEST
- 1. 6 A CHANNEL FUNCTIONAL TEST shall be:
a.
-Analog channels - the injection of a simulated signal into the i
channel as close to the sensor as practicable to verify OPERABILITY l
including alarm and/or trip functions.
q b.
Bistable channels - the injection of a simulated signal into the sensor to verify OPERABILITY including alarm and/or trip functions.-
CONTAINMENT INTEGRITY g
1.7' CONTAINMENT INTEGRITY shall exist when:
a.
All penetrations required to be closed during accident conditions are either:
1)
Capable of being closed by an OPERABLE containment auton,stic isolation valve system, or 2)
Closed by manual valves, blind flanges, or deactivated auto-matic valves secured in their closed positions, except as provided in Table 3.6-2 of Specification'3.6.3.
b.
All equipment hatches are closed and sealed, c.
Each air lock is in compliance with the requirements of Specification 3.6.1.3, 1-d.
The containment leakage rates are within the limits of Specification p
3.6.1.2, and j
1 E
e.
The sealing mechanism associated with each penetration (e.g., welds, p
bellows or 0-rings) is OPERABLE.
1 l-CONTROLLED LEAKAGE
- 1. 8 CONTROLLED LEAKAGE shall be that seal water flow supplied to the reactor coolant' pump seals.
CORE ALTERATION
- 1. 9 CORE ALTERATION shall be the movement or manipulation of any component within the reactor pressure vessel with the vessel head removed and fuel in the vessel.
Suspension of CORE ALTERATION shall not preclude completion of i.
H movement of a component to a safe conservative position.
SEQUOYAH - UNIT 2 1-2 Amendment No. 63,117 e
9
' 3/4.6 ' CON'TAINMENT SYSTEMS 5
3/t.6.1 PRIMARY CONTAINMENT CONTAINMENT INTEGRITY LIMITING CONDITION FOR OPERATION 3.6.1.1 Primary _ CONTAINMENT INTEGRITY shall be maintained.
APPLICABILITY:
MODES 1, 2, 3 and 4.
ACTION:
Without primary CONTAINMENT INTEGRITY, restore CONTAINMENT INTEGRITY within one hour or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTOOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
4' SURVEILLANCE REQUIREMENTS
- 4. 6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated:
a.
At 1. east once per 31 days by verifying that all penetrations
- not capable of being closed by OPERABLE containment automatic isolation L
valves and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured.in their positions, except as provided in Table 3.6-2 of Specification 3.6.3.
b.
By verifying that each containment air lock is in compliance with the requirements of Specification 3.6.1.3.
c.
After each closing of each penetration subject to Type B testing, except the containment air locks, if opened following a Type A or B test, by leak rate testing the seal with gas at P,, 12 psig, and verifying that when the measured leakage rate for these seals is I
added to the leakage rates determined pursuant to Specification 4.6.1.2.d for all other Type B and C penetrations, the combined leakage rate is less than or equal to 0.60 L,.
- Except valves, blind flanges, and deactivated automatic valves which are located inside the annulus or containment and are locked, sealed or otherwise secured in the closed position.
These penetrations shall be verified closed during each COLD SHUT 00WN except that such verification need not be performed more often than once per 92 days.
SEQUOYAH - UNIT 2 3/4 6-1 Amendment llI 4
fCONTAINNENT' SYSTEMS p'
CONTAINMENT LEAKAGE LIMITING' CONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited to:
An overall integrated leakage rate of less than or equal to L,, 0.25 a.-
percent by weight of the containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at P,,
12 psig.
b A combined-leakage rate of less than or equal to 0.60 L, for all penetrations and valves subject to Type 8 and C tests, when pressurized to P,.
A combined bypass leakage rate of less than or equal to 0.25 L, for c.
all penetrations identified in Table 3.6-1 as secondary containment BYPASS LEAKAGE PATHS TO THE AUXILIARY BUILDING when pressurized to P,,
L APPLICABILITY:
MODES 1, 2, 3 and 4 l
ACTION:
With either (a) the measured overall integrated containment leakage rate exceeding 0.75 L,, or (b) with the measured combined leakage rate for all l
penetrations and valves subject to Types B and C tests exceeding 0.60 L,, or L
(c) with the combined bypass leakage rate exceeding 0.25 L, for BYPASS LEAKAGE
' PATHS TO THE AUXILIARY BUILDING, restore the overall integrated leakage rate-to less than or equal to 0.75 L,, and the combined leakage rate for all penetra-tions and valves subject to Type B and C te'sts to less than or equal to 0.60 L,,
and the combined bypass leakage rate from BYPASS LEAKAGE PATHS TO THE AUXILIARY BUILDING to less than or equal to 0.25 L,, prior to increasing the Reactor Coolant System temperature above 200'F.
SEQUOYAH - UNIT 2 3/4 6-2 Amendment No. 63
t CONTAINMENT SYSTEMS SL'RVEILLANCE REQUIREMENTS (Continued) 3.
Valves pressurized with fluid _from a seal system, e.
The combined bypass leakage rate to the auxiliary building shall be determined to be less than or equal to 0.25 L, by applicable Type B and C tests at least once per 24 months except for penetrations which are not individually testable; penetrations not individually testable shall be determined to'have no detectable leakage when tested with soap bubbles while the containment is pressurized to P,, 12 psig, during each Type A test.
p
- f.. By verifying that each containment air lock is in compliance with the 4-requirements of Specification 3.6.1.3.
y i
g.
Leakage from isolation valves that are sealed with fluid from t. seal l
1.
i l
system may be excluded, subject to the provisions of Appendix J.
Section III.C.3, when determining the combined leakage rate provided L
the seal system and valves are pressurized to at least 1.10 P,, 13.2 y
psig, and the seal system capacity is adequate to maintain system E
pressure (or fluid head for the containment spray system and RHR spray system valves at penetrations 48A, 488, 49A and 49B) for at least 30 days, l-i h.
Type B tests for penetrations employing a continuous leakage monitoring system shall be conducted at P,, 12 psig, at intervals no greater.than once per 3 years.
i.
All test leakage rates shall be calculated using observed data converted to absolute values.
Error analyses shall be performed to select a balanced integrated leakage measurement system.
J.
The provisions of Specification 4.0.2 are not applicable.
SEQUOYAH - UNIT 2 3/4 6-4 Amendment No. 63, 90, 104, 117 4
(Correction Letter of 7-11-88)
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