ML20041C432

Proposed Tech Spec Change Request 42,changing Tech Specs 15.4.2,15.4.5,15.4.7,15.4.8 & 15.6.9 Re Inservice Insp of Safety Class Components

ML20041C432
Person / Time
Site:	Point Beach
Issue date:	02/17/1977
From:	WISCONSIN ELECTRIC POWER CO.
To:
Shared Package
ML20041C405	List: ML20041C404 ML20041C407 ML20041C430 ML20041C432
References
NUDOCS 8203010384
Download: ML20041C432 (8)

Text

, 15.4.2 IN-SERVICE INSPECTION OF SAFETY CLASS COMPONENTS l l

. Applicability '

Applies to in-service inspection of Safety Class Components. f  ;

1 Objectives I

1 To provide assurance of the continuing integrity of the safety class systems. l Specifications A. Steam Generator Tube Inspection Requirements

1. Tube Inspection Entry from the hot-leg side with examination from the point of entry completely around the U-bend to the top support of the cold-leg is considered a tube inspection.

2. Sample Selection and Testing Selection and testing of steam generator tubes shall be made on the following basis:

(a) One steam generator of each unit shall be inspected during inservice inspection in accordance with the following requirements:

1. The inservice inspection may be limited to one steam generator on an alternating sequence basis. This e=aintion shall include at least 6% of the tubes if the results of the first or a prior inspection indicate that both generators are performing in a comparable manner.

( 2. When both steam generators are required to be examined l by Table 15.4.2.1 and if the condition of the tubes in one l generator is found to be more severe than in the other steam generator of a unit, the steam generator sa=pling l sequence at the subsequent inservice inspection shall be i

modified to examine the steam gensrator with the more I

severe condition.

(b) The minimum sample size, inspection result classification' and the associated required action shall be in conformance with the requirements specified in Table 15.4.2-1. The l results of each sampling examination of a steam generator i

shall be classified into the following three categories:

1 l

! 15.4.2-1 8203010394 820223 PDR ADOCK 05000266 G PDR

Defect So an imperfecGBcn o[i suelB severSty tlI5t h8 cac n D

( . the minimum acesptablo tube wall thickntec-of 50%. A tube

- containing a d2fect 1c daftetivo.

Pluqqing Limit is the imperfection depth beyond which the tuu must be removed from service, because the tube may becona defective prior to the next scheduled inspection.

The pitgging limit is 40% of the nominal tube wall thickness.

6. Corrective Measures All' tubes that leak or have degradation exceeding the plugging limit shall be plugged prior to return to power from a refueling or inservice inspection condition.

7. Reports (a) After each inservice examination, the number of tubes plugged in each steam generator shall be reported to the Conunission as soon as practicable.

(b) The complete results of the steam generator tube inservice inspection shall be included in the Operating Report for the period in which the inspection was completed. In addition all results in Category C-3 of Table 15.4.2-1 shall be reported to the Commission prior to resumption of plant operation.

(c) Reports shall include:

1. Number and extent of tubes inspected

2. Location and percent of all thickness penetration for each indication

3. Identification of tubes plugged (d) Reports required by Table 15.4.2 Steam Generator Tube Inspection shall provide the information required by Specification 15.4.2.C.2 and a description of investigations conducted.to determine cause of the tube degradation and corrective measures taken to prevent recurrence.

B. In-service Inspection of Safety Class Components Other Than l Steam Generator Tubes  ;

l

1. Inservice inspection of ASME Code Class 1, Class 2 and Class 3 components shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as .

required by 10 CFR 50, Section 50.55a(g) modified by Section

50. 55a (b) , except where specific written relief is granted by the NRC, pursuant to 10 CFR 50, Section 50.55a(g) (6) (1) . Where difficulty l

15.4.2-lc

10 cnc:unt: red in perfcrming an in:pecti:n in cccordanca with tha  !

c:de, the modificd plan or citernativa method will be fully i '

documentcd for sub cquint reviiw by tha NRC. Should th3 NRC n3t agree with the documented changes, the item in question will be  ;

re-examined in a mutually agreeable manner. -

2. Inservice testing of ASME Code Class 1, Class 2 and Class 3 pumps and valves shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 QFR 50, Section 50.55a(g) modified by Section 50.55a(b), except where specific written relief is granted by the NRC pursuant to 10 CFR 50, Section 50.55a(g) (6) (1) . Where difficulty is encountered in performing a test in accordance with  ;

the code, the modified plan or alternative method will be fully l documented for subsequent review by the NRC. Should the NRC not ,

agree with the documented changes, the pump er valve in que'stion j will be retested in a mutually agreeable manner. i

3. Containment isolation valves will be tested in accordance with I Technical Specification 15.4.4 instead of Section IWV-3420, Valve Leak Rate Test.

I e

i s

I e

9 15.4.2-1d

That 10, th3 cpproprint) pump motor braakera chall have epen:d cnd clostd, and all valvsa chall have complstid 4

their travel.

B. Containment Scray System

1. System tests shall be performed during reactor shutdowns for major fuel reloading. The test shall be performed with the isolation valves in the spray supply lines at the containment blocked' closed. Operation of the system is initiated by tripping the normal actuation instrumentation. The motor breakers for the pumps shall be placed in the " test" position m

for this test -

2. The test will be considered satisfactory if visual observations indicate all components have operated satisfactorily.

3. The spray noz=les shall be checked to verify that they are not obstructed at intervals not exceeding five years.

C. Containment Fan Coolers Each fan cooler unit shall be tested at each refueling to verify proper operation of the backdraft dampers and the service water bypass valves.

5 s

15.4.5-2 s

N g 14 -  %

T-

I i

Basis The Safety Injection System and the Containment Spray System are principal plant Safety Systems that are normally inoperative during reactor operation. Complete systems tests cannot be performed when the reactor is operating because a safety injection signal causes containment isolation and a Containment Spray System test requires the system to be temporarily disabled. The method of assuring operability of these systems is therefore to combine systems tests to be performed during refueling shutdowns, with more frequent component tests,

! which can be performed during reactor operation.

t l

l l

l The systems tests demonstrate proper automatic operation of the Safety Injection and Containment Spray Systems. With the pumps blocked from starting a test signal is applied to initiate automatic action and verificat:.on made that the components receive the safety injection in the proper sequence. The test demonstrates the operation of the valves, pump circuit breakers, and automatic l

! circuitry. (1) 15.4.5-3 i

( During rxctor operation, the inntrumentatien which 10 dcpended on to initists

! c.nf;ty injection and containment spray is g:nsrally ch:ckcd werkly and tha initiating circuits are tested monthly (in accordance with Specification 15.4.1) .

Other systems that are also important to the emergency cooling function are the accumulators, the Component Cooling System, the Service Water System and the containment fan coolers. The accumulators are a passive safeguard. In accordance with Specification 15.4.1 the water volume and pressure in the accumulators are checked periodically. The other systems mentioned operate when

~

the reactor is in operation and by these means are continuously monitored for satisfactory performance.

References (1) FSAR Section 6.2 i

i 4

15.4.5-4

15.'4.7 MAIN STEAM STOP' VALVES l e

'The main steam stop valves are tested in accordance with specification 15.4.2.B. l G

15.4.7-1

ggr.tr.w geg6cd,Tm sysgg -

9 o

• ,The cuxiliary facdwat:r pump 2 cra t ct d in'accordanca with spccific^. tion 15.4.2.n.,

15.4.8-1