ML20114B126

From kanterella
Jump to navigation Jump to search
Proposed TS 4.0.5 Re Applicability & 3/4.4.4.3 Re RCS Leakage to Address Inservice Insp Program for Piping Noted in GL-88-01
ML20114B126
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 08/19/1992
From:
ENTERGY OPERATIONS, INC.
To:
Shared Package
ML20114B123 List:
References
GL-88-01, GL-88-1, NUDOCS 9208250039
Download: ML20114B126 (9)
v • d • e


Text

. _ - _ -.

e a

- to GNRO-92/00092 s,

l l

PROPOSED CilANGE TO Tile OPEllATING LICENSE MARKED.UP TECilNICAL SPECIFICATION PAGES (GGNS PCOL-92/06) 9 ROB 250039 920019 PDR ADOCK'OSOOO416 PDR p

. to GNRO 92/00092 Page i of 4 I

p APPLICABILITY For ifwwab.on cdt? -

,5URVE!LLANCE REQUIREPENTS 4.0.1 Surveillance Requirements shall be met during the OPERATIONAL CONDITIONS or other conditions specified for individual limiting Conditions for Operation unless otherwise stated in an individual Surveillance Requirement.

4.0.2 Each Surveillance Requirement shall be performed within the specified surveillance interval with a maximum allowable extension not to exceed 25% of the specified surveillance interval.

i 4.0.3 Failure to perform a Surveillance Requirement within the allowed surveillance interval, defined by Specificatioe 4.0.2. shall constitute noncom-pliance with the OPERABILITY requirements for e Limiting Condition for Operation.

The time limits of the ACTION requirements are applicable at the time it is identified that a Surveillance Requirement has not been performed.

The ACTION requirements may be delayed for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to permit the completion of the surveillance when the allowable outage time limits of the ACTION requirements are less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Surveillance Requirements do not have to be performed on inoperable equipment.

condition knall not be made unless the Surveillance Requirement (plicableinto an OPERA 4,0.4 friry 1

with the Limiting Condition for Operation have been perfonned within the a)plicable surveillance interval or as otherwise specified.

This provision siall not prevent passage through or to OPERATIONAL CONDITIONS as required to comply with ACTION requirements.

4.0.5 Surveillance Requirements for inservice inspection and testing of ASME Code Class 1, 2, & 3 components.shall be applicable as follows:

.a.

Inservice inspection of ASME Code Class 1, 2, and 3 components and inservice testing of ASME Code Class 1, 2, and 3 pumps and valves shall be performed in accordance with Section XI of the ASME-Boiler and Pressure Vcnel Code and applicable Addenda as required by 10 CFR 50, Section 50.55a(g), except where specific written relief has been granted by the Connission pursuant to 10 CFR 50. Section 50.55a(g)

(6)(1).

b.

Surveillance intervals specified in Section XI of the ASME Boiler and Pressure Vessel' Code and applicable Addenda for the inservice inspection and testing activities required by the ASME Boiler and Pressure Vessel Code and applicable Addenda shall be applicable as follows in these Technical Specificationst Of.0 0 GULF-UNIT _1 3/4 0-2 Amendment No. 77

. to GNRO 92/00092

- APPLICABILITY SURVEILLANCE REQUIREMENTS (Continued)

ASME Boiler and Pressure Vessel Required frequencies Code and applicable Addenda for performing inservice terminology for instrvice inspection and testing 1nspection and testing activities activities Weekly At least once per 7 days Monthly At least once per 31 days Quarterly or every 3 months At least once per 92 days Semiannually or every 6 mo-ths At least once per 184 days Every 9 months At least once per 276 days Yearly or annually At least once per 366 days c.

The provisions of Specification 4.0.2 are applicable to the above required frequencies for performing inservice inspection and testing activities, d.

Performance of the above inservice inspection and testing activities shall be-in addition to other specified Surveillance Requirements.

Nothing-in the ASME Boiler and Pressure Vessel Code shall be construed e.

to supersede the raquirements-of any Technical Specification.

, - e.

p.

Tne. inservice. inspecMon p<oy e piei9 idenMied in Nec 6eneric lea +er Be -o) shan t be performed in accordance w i+h On

$Chedule.,

+he.

NRC.

6bff pos M Ps melheds, pe.rsonne3, and campic exP M 5 ion i rtcluded i n 6eneric Letter 86-01 or in accordance.

mi+h alfernate measures approved by

-h Ned. stoM W

i GRAND GULF-UNIT 1 3/4 0-3 Amendment No. 69,

l to GNRO-92/00092 Page 3 of 4 REACTOR COOLANT SYSTEM OPERATIONAL LEAKAGE LIMITING CONDITION FOR OPERATION 3.4.3.2 Reactor coolant system leakage shall be limited to:

7 a.

Nn PRESSURE BOUNDARY LEAKAGE.

b.

S gpm--UNIDENilflED LEAKAGE.

c.

30 gpm total leakage, d.

1 gpm leakage at a reactor coolant system pressure of 1050 1 10 psig from any reactor cociant system pressure isolation valve specified in Table 3.4.3.2-1.

2 gpm increase in UNIDENTiflED LEAKAGE within anyf-hour period or Ic%.

e.

APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2 and 3.

ACTION:

With any PRESSURE B0UNDARY LEAKAGE, be in at least HOT SHUTDOWN within s.

12 nours and in COLD SHUT 00WN within the next E4 hours, b.

With any reactor coolant system leakage greater than the limits in b and/or c, above, reduce the leakage rate to within the limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, With any reactor coolant system pressure isolation valve leakage c.

greater than the above limit, isolate the high pressure portion of the affected system from the low pressure portion within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least two closed manual or deactivated automatic valves, or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDCWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

d.

With one or more high/ low pressure interface valve press'ure moni-l tors and/or interlocks inoperable, restore the inoperable monitor (s) l and/or interlock (s) to OPERABLE status within 30 days or be in at least

-HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUT 00WN within the I

following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

t system UNIDENTIFIED LEAKAGE increase org.ater e.

--With'any reactor cool-24

^Gan 2 gpm within any hour periodf identify the ~ source of leakage-D l

increase as not service sensitive Type 304 or 316 austenitic stainless steel within'4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in at least H0f SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

l GRAND GULF-UNIT 1 3/4 4-9 Anyng y,

. ~. -

. to GNRO-92/00092 Page 4 of 4

O11 a.

Mon _itoring _t_,he_ drwell atmoscheric particulate and gaseous radioactivity at least once per",4' hours, b.

Monitorino the drwell floor and equipment drain sump level and flow p

rateitleastonceper/ hours, d

c.

Monitoring he drywell air coolers condensate flow rate at least

\\

8 E

_)--

once pe hours, and d.

Monitoring the reactor vessel head flange leak detection system at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

4.4.3.2.2 Each reactor coolant system pressure isolation valve specified in Table 3.4.3.2-1 shall be demonstrated OPERABLE by leak testing pursuant to Specification 4.0.5 and verifying the leakage of each valve to be within the specified limit:

a.

At least once per 18 ms < s, ana b.

Prior to returning the valve to service following maintenance, repair or replacement work on the valve which could affect its leakage rate.

lernoVE 5paCC The provisions of Specification 4.0.4 are not applicable for entry into OPERATIONAL ~ CONDITION 3.

4.4.3.2.3 The high/ low pressure interface valves leakage pressure monitors shall be demonstrated OPERABLE with alarm and interlock setpoints per Table 3.4.3.2-2 and Table 3.4.3.2*3 by performance of a:

a.

CHANNEL FUNCTIONAL TEST at least once per 31 days, and l

b.

CHANNEL CALIBRATION at least once per 18 months.

GRAND. GULF-UNIT 1 3/4 4-10 Amendment No. 20 6 Effective Date: 150er 84

1 l to GNRO-92/00092

)

PROPOSED CilANGE TO THE OPERATING LICENSE PROPOSGD TECilNICAL SPECIFICATION PAGES (GGNS PCOL-92/06)

Nelqi Wese pages are provided only for information to aid in the review of the proposed Technical Specification changes.

=

. to GNRO-92/00092 Page 1 of 3

' APPLICABillTY SURVEILLANCE F.EQUIREMENTS (Continued) 1 ASME Boiler and Pressure Vessel Rcquire frequencies for Code and applicable Adder.da for performing inservice terminology for inservice inspection and testing iniggetion and testine activities Activities Weekly At least once per 7 days Monthly At least once per 31 days quarterly or every 3 months At least once per 92 days Semiannually or every 6 months At least once per 184 days Every 9 months At least once per 276 days Yearly or annually At least once per 366 days c.

The provisions of Specification 4.0.2 are' applicable to the above required frequencies for performing ir.jervice inspection and testing

_ activities.

d.

.arformance of the above inservice inspection and testing activities shall be in addition to other specified Surveillance Requirements.

e.

Nothing in the ASME Boiler and Pressure Vessel Code shall be construed to supersede the requirements of any Technical Specification.

-f.

The inservice inspection program for piping identified in NRC Generic Letter 88-01 shall be performed in accordance with the NRC staff positions-on schedule, methods, personnel, and sample expansion included in Generic Letter 88-01 or in accordance with alternate measures approved by the NRC staff.

GRAND GULF-UNIT 1 3/4 0-3 Amendment No. 69, o

. to GNRO 92/00092 Page 2 of 3

  • REACTOR COOL ANT SYSTEM REACTOR COOL ANT SYSTEM OPERATIONALiEAKAGI LlHITING CONDITION FOR OPERATION 3.4.3.2 Reactor coolant system leakage shall be limited to:

a.

No PRESSURE B0UNDARY LEAKAGE.

b.

5 gpr UNIDENTIFIED LEAKAGE.

c.

30 gpm total leakage.

d.

I gpm leakage at a reactor coolant system pressure of 1050 1 10 psig from any reactor coolant system pressure isolation valve specified in Table 3.4.3.2-1.

e.

2 gym increase in UNIDENTIFIED LEAKAGE within any 24-hour period or less.

APPLICABil.ITY:

OPERATIONAL CONDITIONS 1, 2 and 3.

ACTION:

a.

With any PRES 5URE BOUNDARY LEAKAGE, be in at least IDT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, b.

With any reactor coolant system leake ge greater than the limits in b and/or c, above, reduce the leakage rate to within the limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in C010 SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, c.

With any reactor coolant system pressure isolation valve leakage greater than t'ne above limit, isolate the high pressure portion of the affected system from the low pressure portion within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least two closed manual or deactivated automatic valves, m be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

d.

With one or more high/ low pressure interface valve pressur:. moni-tors and/or interlocks inoperable, restore the inoperable monitor (s) and/or interlock (s) to OPERABLE status within 30 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, e.

With any reactor coolant system "hiUENTIFIED LEAKAGE increase greater than 2 gpm within any 24-hour period or less, identify the source of leakoa increase as not service sensitive Type 304 oc 316 austenitic stain h ss steel within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

GRAND GULF-UNIT 1 3/4 4-9 Amendment No.

l

....--=.

b

. to GNP.0-92/00092 i.

Page 3 of 3

  • BfACTOR COOLANT SYSTDj SURVEILLANCE P.EQUIREMENTS w

4.4.3.2.1 The reactor coolant system leakage shall be demonstrated to be within each of the above limits by:

a.

Monitoring the drywell atmospheric particulate and gaseous radioactivity at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, b.

Monitoring the drywell floor and equipment drain sump level and flow rate at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, c.

Monitoring the drywell air coolers condensate flow rate at 'least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, and d.

Monitoring the reactor vessel head flange leak detection system at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

4.4.3.2.2 Each reactor coolant system pressure isolation valve specified in Table 3.4.3.2-1 shall be demonstrated OPERABLE by leak testing pursuant to Specification 4.0.5 and verifying the leakage of each valve to be within the specified limit:

a.

At least once per 18 months, and b.

Prior to returning the valve to service following maintenance, repair or replacement work on the valve which could affect its leakage rate.

The provisions of Specification 4.0.4 are not applicable for entry into OPERATIONAL CONDlil0N 3.

4.4.3.2.3 The high/ low pressure interface valves leakage pressure monitors shall be demonstrated OPERABLE with alarm and interlock setpoints per l

Table 3.4.3.?-2 and Table 3.4.3.2-3 by performance of a:

a.

CHANNEL FUNCTIONAL TEST at least once per 31 days, and b.

CHANNEL CALIBRATION at least once per 18 nanths.

L GRAND GULF-UNIT 1 3/4 4-10 Amendment No. 20B,

.Fw-

' ' +7

  • W

'u--'9-=a-w-

'a&

we- -

tree ur - : w---r W--+g-r+-%

4-9 1*

w va r9

+

Retrieved from "https://kanterella.com/w/index.php?title=ML20114B126&oldid=4290673"