ML20207D639

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Proposed Tech Spec Surveillance Requirements 4.6.1.2.g & 4.6.3.2 & Table 3.6-2,re Containment Sys
ML20207D639
Person / Time
Site: Sequoyah  Tennessee Valley Authority icon.png
Issue date: 08/10/1988
From:
TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML20207D637 List:
References
NUDOCS 8808150407
Download: ML20207D639 (11)
v • d • e


Text

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CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

d. Type B and C tests shall be conducted with gas ata P 02 psig) at intervals no greater than 24 months except for tests involving:
1. Air locks,
2. Penetrations using continuous leakage monitoring systems, and
3. Valves pressurized with fluid from a seal system.
e. The combined bypass leakage rate shall be determined to be less than or equal to 0.25 L aby 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 c v'ainment is pressurized to Pa (12 psig) during each Type A test.
f. Air locks shall be tested and demonstrated OPERABLE per Surveillance Requirement 4.6.1.3.
g. Leakage from isolation valves that are sealed with fluid from a seal system may be excluded, subject to the provisions of Appendix J,Section III.C.3, when determining the combined leakage rate provided the seal system and valves are pressurized to at least 1.10 Pa (I3'2 psig) and the seal system capacity is adequate to maintain s stem ko FS75>efM pressure (or fluid head for the containment spray systemqvalves at penetrations 48 A 4Mj48 for at least 30 days.

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h. Type B tests for penetrations employing a continuous leakage -

monitoring system shall be conducted at Pa (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 I 3/4 6-4 8808150407 880810 PDR ADOCK 05000327 P PNU -- -

d CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

c. Verifying that on a Containment Ventilation isolation test signal, each Containment Ventilation Isolation valve actuates to its isolation position.

4.6 3.3 The isolation time of each power operated or automatic valve of R16 Table 3.6-2 shall be determined to be within its limit when tested pursuant to Specification 4.0.5.

4.6.3.4 Each Containment Purge isolation valve shall be demonstrated OPERABLE within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after each closing of the valve, except when the g g, valve is being used for multiple cyclings, then at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, by verifying that when the measura leakage rate of these valves is added to the leakage rates determined pursuant to Specification 4.6.1.2.d for all other Typ'e 8 and C penetrations, the combined leakage rate is 3 0.60 L,.

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SEQUOYAH - UNIT 1 3/4 6-18 Amendment No. 12

TABLE 3.6-2 (Continued) ,

l CONTAINMENT ISOLATION VALVES E

. VALVE NUMBER FUNCTION MAXIMUM ISOLATION TIME (Seconds)

C. PHASE "A" CONTAINMENT VENT ISOLATION (Cont.)

l 13. FCV-30-50 Upper Compt Purge Air Exh 4*

l 14. FCV-30-51 Upper Compt Purga Air Exh 4*

15. FCV-30-52 Upper Compt Purge Air Exh 4*

1 16. FCV-30-53 Upper Compt Purge Air Exh 4*

l 17. FCV-30-56 Lower Compt Purge Air Exh 4*

18. FCV-30-57 Lower Compt Purge Air Exh 4*
19. FCV-30-58 Inst Room Purge Air Exh 4*
20. FCV-30-59 Inst Room Purge Air Exh 4* R74
21. FCV-90-107 Cntat Bldg LWR Compt Air Mon 5*

R 22. FCV-90-108 Cntmt Bldg LWR Compt Air Mon 5*

23. FCV-90-109 Cntet Bldg LWR Compt Air Mon 5*

T 24. FCV-90-110 Cntmt Bldg LWR Compt Air Mon 5*

O 25. FCV-90-111 Cntet Bldg LWP. Compt Air Mor. 5*

26. FCV-90-113 Cntet Bldg UPR Compt Air Mon 5*
27. FCV-90-114 Cntat B1dg UPR Compt Air Mon 5*
28. FCV-90-115 Cntat Bldg UPR Compt Air Mon 5*
29. FCV-90-116 Cntat Bldg UPR Compt Air Mon 5*
30. FCV-90-117 Cntat B'.dg UPR Compt Air Mon 5*

D. OTHER if$I 1. FCV-30-46 Vacuum Relief Isolation Vaive 25

  • @ 2. FCV-30-47 Vacuum Relief Isolation Valve 25 59 3. FCV-30-48 Vacuum Relief Isolation Valve 25
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4. FC V -(.2-90 N J d.,;g Is-/<h.,, sin 12

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U R41 y # Provisions of LCO 3.0.4 are not applicable if valve is secured in its isolated position with power removed and either FCV-62-73 or FCV-62-74 is maintained operable.

CONTAVNMENT SYSTEMS SURVEILLANCE DE0VIREMENTS (Continued)

3. Valves pressuri:ed with fluid from a seal system.
e. The combined bypass leakage rate shall be determined to be less than of equal to 0.25 L aby applicable Type 8 and C tests at least once per 24 months except for pene,trations 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.
f. Air locks shall be t'sted e and demonstrated OPERABLE per Surveillance Requi rcment 4. 6.1. 3.
g. Leakage from isolation valves that are sealed with fluid from a seal system may be excluded, subject to the provisions of Appendix J,Section III.C.3, when determining the combined leakage rate provided the seal system and valves are pressurized to at least 1.10 Pa , 13.2 psig, and the seal system capacity is adequate to maintain system pressure (or fluid head for the containment spray systemgvalves at penetrations 48A ad,480) for at least 30 days.

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h. Typo B tests for penetrations employing a continuous leakage monitoring system shall be conducted at aP , 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.

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SEQUOYAH - UNIT 2 3/4 6-4

CONTAINMENT SYSTEMS l

SURVEILLANCE RECUIREMENTS (Continuec) 4.6.3.2 Each isolation valve specified in Table 3.6-2 snall be demonstrated OPERABLE during the COLD SHUTCOWN or REFUELING MCOE at least once per 18 montns oy:

a. Verifying thct on a Phase A containment isolation test signal, each Phase A isolation valve actuates to its isolation position.
b. Verifying that on a Phase 3 containment isolation test signal, each Phase B isolation valve actuates to its isolation position,
c. Verifying that on a Containment Ventilation isolation test signal, each Containment Ventilation valv9 actuates to its isolation position.
3. 3 The isclation time of eacn power coerated or automatic valve af Table 3.5-2 snall ce determined to ce within its limit wnen tested pursuant to Specification a.0.5.

4.6.3.a Each containment purge isolation valve shall be demonstrated OPERABLE within 24 haers after eacn closing of the valve, except wnen the valve is being used for multiple cyclings, then at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, by verifying that when the measured leakage rate is added to the leakage rat's determined pursuant to Soecification 4.6.1.2d. for all otner Type 3 and C penetrations, the comoined leakage rate is less than or equal to 0.60 L3 .

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y, IABLE 3.6-2 (Continued)

E 8 CONTAINMENT 13DLATION VALVES s

I VALVE NUMBER FUNCTION MAXIMUM ISOLATION TIME (Seconds)

E C. PHASE "A" CONTAINMENT VENT ISOLATION (Cont.)

Z m 13. FCV-30-50 Upper Compt Purge Air Exh 4*

14. FCV-30-51 Upper Compt Purge Air Exh 4*
15. FCV-30-52 Upper Compt Purge Air Exh 4*
16. FCV-30-53 Upper Compt Purge Air Exh 4*
17. FCV-30-56 Lower Compt Purge Air Exh 4*

, 18. FCV-30-57 Lower Compt Purge Air Exh 4* R62

19. FCV-30-58 Inst Room Purge Air Exh 4*
20. FCV-30-59 Inst Room Purge Air Exh 4*
21. FCV-90-107 Cntat Bldg LWR Compt Air Mon 5*

w 22. FCV-90-108 Cntat Bldg LWR Compt Air Mon 5*

1 23. FCV-90-109 Cntat Bldg LWR Compt Air Mon 5*

. 24. FCV-90-110 Cntat Bldg LWR Compt Air Mon 5*

4 25. FCV-90-111 Cntat Bldg LWR Compt Air Mon 5*

" 26. FCV-90-113 Catst Bldg UPR Compt Air Mon 5*

27. FCV-90-114 Cntat Bldg UPR Compt Air Hon 5*
28. FCV-90-115 Cntat Bldg UPR Compt Air Mon 5*
29. FCV-90-116 Catst Bldg UPR Compt Air Hon 5*
30. FCV-90-117 Cntet Bldg UPR Compt Air Mon 5*
0. OTHER
1. FCV-30-46 Vacuum Relief Isolation Valve 25

, 2. FCV-30-47 Vacuum Relief Isolation Valve 25

., p a 3. FCV-30-48 Vacuum Relief Isolation Valve 25 l

-i 4. FCv-G2-90 Mo=~) CL.6 sol.b I do./ve- /z.

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{ 2 R29 l' # Provisions of LCO 3.0.4 are not applicable if valve is secured in its isolated position with l

r@- power removed and either FCV-62-73 or FCV-62-74 is maintained operable.

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s ENCLOSURE 2 PROPOSED TECHNICAL SPECIFICATION CHANGE i SEQUOYAH NUC. EAR PLANT UNITS 1 AND 2 1

DOCKET NOS. 50-327 AND 50-328  !

(TVA-SQN-TS-88-22) [

i DESCRIPTION AND JUSTIFICATION FOR  ;

CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS l g =

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ENCLOSURE 2 8

Description of Change l

, Tennessee Valley Authority proposes to modify the Sequoyah Nuclear Plant

. Units 1 and 2 Technical Specifications to revise containment system surveillance requirements 4.6.1.2.g and 4.6.3.2 and table 3.6-2. These  ;

changes will provide added assurance of valve operability by specifying surveillance testing for the residual heat removal (RHR) spray lines (penetrations X-49A and -498) and normal charging containment isolation

valve.

l Reason for Change 1

IE Inspection Report Nos. 50-327/86-20 and 50-328/86-20 identified problems with the containment isolation design. In resolution of the problems identified. TVA redesignated one of the outboard automatic isolation valves (FCV-62-90) as the outboard containment isolation valve for the normal charging line. TVA also redesignated the remote-manual i valves on the RHR spray lines as outboard containment isolation valves.

With redesignation of these valves, containment isolation testing is

! required. TVA also thought it was prudent to add these penetrations and valves to the appropriate technical specification for completeness.

Justification for Change 2 TVA redesignated one of the outboard automatic isolation valves l

(FCV-62-90) as the outboard containment i.clation barrier for the normal charging line (penetraticn X-16). This designation ensures the containment isolation design for this pentaration is in explicit

compliance with General Design Criteria (G'C) 55. The redesignated outboard isolation valve has been evaluates with reference to testing i requirements for containment isolation barriers in accordance with i 10 CFR 50, Appendix J. This valve is not subject to type C testing j because a water seal is provided on this penetration postaccident with a
guaranteed 30-day water supply and injection pressure greater than 1.1 Pa l as a result of the continuous operation of the centrifugal charging pump

, as required by the SQN Emergency Cperating Procedures, even with I consideration of a single active failure. This seal system satisfies the j provisions of Standard Review Plan (SRP) section 6.2.6. NRC concluded in the Safety Evaluation Report for TVA's Sequoyah Nuclear Performance Plan (NUREG-1232, Volume 2) that the new designation of FCV-62-90 as a containment isolation valve--subject to appropriate operability, i surveillance, and testing requirements--renders the isolation design for

} this penetration acceptable and in compliance <ith the explicit r requirements of GDC 55. The addition of surveillance requirement 4.6.3.2.e and the addition of FCV-62-90 to table 3.6-2 will provide  !

long-term assurance that operability and surveillance testing requirements j

! are maintained.

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TVA redesignated the available remote-manual valves on the RHR spray lines as outboard containment isolation valves. This designation ensures the

! design for these penetrations is in compliance with GDC 56 as endorsed in j SRP section 6.2.4. e I  :

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v The redesignated remote-manual valves for the two RHR spray lines have also been evaluated with reference to leak testing requirements for containment isolation barriers in accordance with 10 CFR 50, Appendix J.

A water leg is maintained in the risers for the RHP spray lines under normal operation. It is intended that the RHR pamps operate continuously  ;

postaccident, thereby maintaining pressure on the system and a water seal  !

on the back side of the remote manual valves and preventing loss of the water leg in the riser. If, for some unforeseen reason, one of the RHR l

j pumps should be taken out of service, the water seal on the back side of the remote-manual valves cannot be guaranteed. Thus, the motor-operated remote-manual valves will be leak tested (with water) to verify there is sufficient fluid inventory in the risers to maintain a water seal on the valves for 30 days even after shutoff of an RHR pump, thereby ensuring there will be no leakage of containment atmosphere to the environment.

This test is identical to that performed for the containment spray lines. '

The provisions of the test are described in Final Safety Analysis Report section 6.2.4.2.1. Additionally, any through-line leakage that may occur l 1 would be contained within the closed, seismically qualified. IVA Class B  ;

system outside containment. The containment spray lines (penetrations l X-48A and -48B) are also water-serled, and the present testing of

  • penetrations X-48A and -48B is acceptable. NRC concluded in NUREG-1232 Volume 2, that, if TVA performed the same type testing for the RHR lines, the NRC staff would find it acceptable. TVA committed to perform the same type of testing in a letter to NRC dated January 2, 1987. The addition of penetrations X-49A and -49B to surveillance requirement 4.6.1.2.g will provide long-term assurance that operability and surveillance testing requirements are maintained.

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ENCLOSURE 3 PROPOSED TECHNICAL SPECIFICATION CHANGE SEQUOYAH N11 CLEAR PLANT UNITS 1 AND 2 DOCKET NOS. 50-327 AND 50-328 (TVA-SQN-TS-88-22)

DETERMINATION OF NO SIGNIFICANT HAZARDS CONSIDERATIONS

ENCLOSURE 3 Significant Hazards Evaluation TVA has evaluated the proposed technical specification change and has determined that it does not represent a significant hazards consideration based on criteria established in 10 CFR 50.92(c). Operation of SQN in accordance with the proposed amendment will nott (1) involve a significant increase in the probability or consequences of an accident previously evaluated. The designation of the nornal charging isolation valve FCV-62-90 for penetration X-16 and the available remote-manual valves on RHR containment penetrations X-49A and -49B as containment isolation valves has been previously evaluated by NRC in NUREG-1232 Volume 2. The NRC review also evaluated containment leak test requirements for these penetrations.

The proposed changes to table 3.6-2 and surveillance requirements 4.6.1.2.g and 4.6.3.% will simply add these same requirements to the technical specifications to provide long-term assurance that cperability and surveillance testing requirements are maintained. No new hardware or testing requirements are proposed. Consequently, the probability or consequences of an accident previously evaluated are not changed.

(2) create the possibility of a new or different kind of accident from any previously analyzed. The designation of the normal charging isolation valve FCV-62-90 for penetration X-16 and the available remott-manual valves on RHR containment penetrations X-49A and -49B as containment isolation valves has been previously evaluated by NRC in NUREG-1232 Volume 2. The NRC review also evaluated containment leak test requirements for these penetrations. The proposed changes to table 3.6-2 and surveillance requirements 4.6.1.2.g and 4.6.3.2 will simply add these same requirements to the technical specifications to provide long-term assurance that operability and surveillance testing requirements are maintained. No new hardware or testing requirements are proposed. Consequently, the possibility of a new or different kind of accident from any previously analyzed is not created.

(3) involve a significant reduction in a margin of safety. The margin of safety afforded by the technical specifications is increased by the addition of explicit surveillance and operability requirements for the outboard containment isolation valves associated with containment penetrations X-16. -49A. and -49B. The addition of these requirements to the technical specifications will provide long-term assurance-that the operability and surveillance testing requirements evaluated by NRC in NURFG-1232, Volume 2. are ma'.ntained.

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