ML20040C892

Forwards Info Re RCS Expansion & Restraint & Integrated Hot Functional Heatup & Testing,To Be Included in Next Amend to FSAR

ML20040C892
Person / Time
Site:	Byron, Braidwood, 05000000
Issue date:	01/21/1982
From:	Tramm T COMMONWEALTH EDISON CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
References
820120-1, NUDOCS 8201290350
Download: ML20040C892 (15)

Text

. _ .

,' Commonwealth' Edison S'

'//'D) orts First National Plaza, Chictgo, lilinois (O Address Reply to: Post Office Box 767

~ Chicago, Illinois 60690 -

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Janua ry 21, 1982

\ N g

Mr. Harold R. Denton, Director Of fice of Nuclear Reactor Regulation S

U.S. SEC!3 PED 9 Nuclear Regulatory Commission . .

Washington, DC 20555 T s[$#jj;yM2319825 vg, ,,.

1

Subject:

. Byron Station Units 1 and 2 k Braidwood Station Units 1 and 2 g Advance FSAR Information '

NRC Docket Nos. 50 A54/455/456/45 7

Dear Mr. Denton:

1.

be included in the Byron /Braidwood FSAR in the next amenca

, Attachment A to this letter lists the information enclosed.

-letter are provided.One (1) signed original and fif ty-nine (59) copies o f this included for your review and approval.Fif teen (15) copies of the enclosures are Please address' further questions to this o ffice.

Very truly yours, i Sk

. T. R. Tramm

[ Nuclear Licensing. Administrator Pressurized Wate r - Reactors l Attachment #

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8201290350 820121 PDR ADOCK 05000454 I

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i 4 Attachment A.

LIST OF ENCLOSED INFORMATION l 'I. FSAR Question Responses' i ,

1

New

- 251.5 Revised: 022.15' ,

022.25

.423.35 450.2 I  !

) II. FSAR Text Changes i

Preop Tests: Tables 14.2-54, 58, 60

j. New Chapter 16.0 Figures 3.4-4a, 4b, Sa, Sb i

III. Miscellaneous Items 2 RSB Open Item (Capability to borate to Cold Shutdown) i I

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B/B Re' actor Systems Branch Open Item Address the issue of'the capability to borate the plant to the cold shutdown condition, using safety grade equip-ment with_ letdown isolation. Is thert sufficient volume in the system to accomodate the volume of bcrated water required to bring the plant to a cold shutdown condition?

RESPONSE

The capability to borate to the cold shutdown condition, with letdown isolation, exists at the Byron plant. We feel that there is sufficient volume available to inject enough borated water to bring the plant to the cold shut-down condition.

We base our conclusion on the analysis performed for the Comanche Peak plant. It was shown that Comanche Peak had the capability to borate to the cold shutdown condition, as reported in the Comanche Peak SER. The NSSS systems at Byron /Braidwood-are nearly identical to the Comanche Peak NSSS systems and we feel that the analysis done for Comanche Peak is directly applicable to Byron /Braidwood.

However, we are persuing a plant specific analysis. The assumptions made for this analysis are the following:

1. The plant is in hot standby condition following a trip from 100% power with the most reactive rod stuck out.

2. Letdown has isolated.

3. -Safety grade equipment is used to borate the plant to

, the cold shutdown condition.

The results of this analysis will be available February 1, 1982.

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. , , B/B-ESAR TABLE 14. 2-54

REACTOR COOLAtJT SYSTEM EXPAtJSIOli AtID RESTPE!!i'

"(Preoperational Test)

Plant Condition or Prerequisite

. Durina hot functional testing prior to core load.

Test chiective To verify that components and piping of the reactor coolant i

system can expand unrestricted with acceptable clearances.

L Test Summary Baseline data will be taken at cold plant conditions prior to l heatup. During the heatuu to operating ecmperatures, selected points on components, piping, and snubbers will be checked at various l temperatures to verify that they can expand unrestricted with acceptable clearances. Any potential points of interference detected during the heatup will be corrected prior to increasing the temperature. Following ecoldown to ambient temperature, the piping and components will be checked to confira that they return to their approximate caseline positions to verify unrestricted movenent during cooldown. .

Acceptance Criteria The pipina and components are verified to expand without restricted movement in accordance wi th Subsection 3.9.2.1.

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14.2-66

B/B-FSAR TABLE 14.2-58 INTEGRATED HOT FUNCTIONAL HEATUP (Preoperational Test) 1 Plant Condition or Prerequisite 1

Prior to core load following hydrostatic testing of primary and secondary systems with essentially all associated systems preoperational testing completed.

Test Objective '

To demonstrate ability to heat primary system to normal operating temperature and pressure.

Te_st Su.nmary The reactor coolant system will be taken to normal operating temperature and pressure using reactor coolant pump heat input. Tests will be performed to demonstrate operation of excess letdown and seal water flow paths and letdown flow rates. Thermal expansion checks including snubbers l

will be conducted. Isothermal calibration of reci. stance temperature detectors and incore thermocouples will be performed.

Acceotance Criteria Properational tests to be performe 3uring plant heatup are accomplished and the +aactor coolant system taken to normal operating temperature and pressure in accordance with subsection 3.9.2.

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14.2-70

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,' B/B-FSAR TABLE 14.2-60 INTEGRATED HOT FUNCTIONAL TESTING COOLDOWN (Preoperational Test)

Plant Condition or Prerecuisite Prior to core load with the RCS at normal no-load temp 2tature l and integrated hot functional testing at temperature completed. l Test Objective To demonstrate the ability to cooldown the' plant from normal operating temperature and pressure to cold shutdown conditions.

Test Summary The plant will be taken from hot to cold conditions using steam generator. steam dump and the residual heat removal sys-tem as applicable. The thermal contraction of piping rystems including snubbers will be monitored. Auxiliary systems required for cooldown will be operationally demonstrated.

Acceptance Criteria The preoperaticnal tests required to be performed during cooldown of the system are completed and reviewed. Steam dump and residual system cool the plant from normal operating temperature and pressure to cold shutdown conditions, thermal contraction of piping systems, and auxiliary systems required l for cooldown are in accordance with subsection 3.9.2.

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14.2-72

G/B-FSAR AF1END2!EST 36 JANUARY 1982 QUESTION 022.15 <

"In accordance with the NRC request to all applicants contained in Task Action Plan A-2 of NUREG-0609, " Asymmetric

?

Blowdown Loads on PWR Primary Systems," provide the following information for the reactor coolant system break that results in the peak differential pressure loads within the reactor cavity:

a. Peak and transient loading on the reactor pressure vessel that includes forces and moments separated into their X,Y,Z components,

b. Provide projected areas used to calculate these loads and the location of these areas shown on detailed plan and elevation drawings.

" NOTE: This is a reiteration of the request made in previous question number 0022.3.j."

RE,SPONSE a-. This item is answered in the response to Question 110.62 and the revision to Section 3.9 of the FSAR.

b. The drawings requested were provided under separate cover in response to Question 22.16.

I In addition, in letter WCO-256-81, L. J. Kripps to R. A.

Victor, " Byron Reactor Cavity and Inspection Cavity Confir-matory Subcompartment Analysis Results," dated December 9, 1981, confirmatory dif ferential pressure loc.ds associated with the reactor cavity were presented. The Applicant was requested to review these results and evaluate the structural adequacy of the reactor cavity.

This evaluation has been completed and it has been determined that the existing design of the reactor cavity shield wall 1 i is adequate to accept the pressure loadings presented in l .the subject letter.

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I Q22.15-1

B/B-FSAR QUESTION 022.25 "FSAR Section 6.5.2.2 states ' Containment spray injection and caustic education...will continue until...the low-low level alarm of the RWST is annunciated. Containment spray injection and caustic addition may then be terminated, and the operating personnel may transfer the containment spray pumps from the injection to the recirculation

. node by first closing the motor-operated valves in the

.uction line from the RWST, the water and caustic lines _

to the eductor, and then opening the motor-operated valves in the suction lines from the containment sumps.'

State clearly whether transferring the containment spray pumps from the injection to the recirculation mode involves stopping and restarting the containment spray pumps as implied in the above statement because the valves in the suction line from the RWST are riosed before the valves in the suction lines from the containment sumps are opened."

RESPONSE

The containment spray pumps will be run for at least 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> following a LOCA. During this time, switchover of pump suction from the injection to the recirculation mode of operation will be manually initiated and completed.

The containment spray pumps do not have to be stopped when transferring from the injection mode to the recirculation mode of operation. A summary of the sequence of events leading up to and during switchover follows.

The RWST level is initially one volume inaccuracy below the low alarm setpoint.

gpm.

RWST cutflow during injection is 18,200 ECCS switchover begins at one volume inaccuracy below the low-low alarm setpoint. The volume consumed prior to switchover is 257,454 gallons and requires 14.15 minutes. e ECCS switchover is given in Table 0212.65-2 in response to Question 212.65. It requires 235 seconds (3.92 min.)

and consumes 73,618 gallons assuming two trains and worst single ECCS failure. Following completion of ICCS switchover, the outflow from the RWST is 14,400 gra and continues until 20.9 minutes have elapsed, consuming an additional 40,752 gallons.

Q22.25-1

B/B-FSAR QUESTION 251.5

" Provide actual pressure-temperature limits for Byron Unit 2 and Braidwood Unit 2 based upon the limiting fracturc toughness of the reactor vessel material and the predicted shift in the adjusted reference temperature ,

RT resulting from radiation damage. The pressure-teMB3r,aturelimitsforthefo110wingconditionsmust be included in the technical specifications when they are submitted:

1. Preservice hydrostatic' tests,

2. Inservice leak and hydrostatic tests,

3. Heatup and cooldown operations, and

4. Core operation."

RESPONSE

The requested information is given in new Chapter 16.0 Figures 3.4-4a, 3.4-4b, 3.4-Sa and 3.4-5b.

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B/B-FSAR QUESTION 423.35 "The response to Item 423.14 is inadequate. Modify the initial test program to provide a description.of the inspections or tests'that will be performed following system operation to assure that all snubbers are operable."

RESPONSE

Snubbers will be inspected to be operable as defined in the

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response to Question 110.63 during integrated hot functional testing. See revised Tables 14.2-54, 14.2-5P, and 14.2-60.

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0423.35-1

B/B-FSAR QUESTION 450.2

" Standard Review Plan Section 6.5.2 (part II.2.a. 'Spe-cific D3 sign Requirements for Iodine Removal Function')

specifies : hat the containment spray system be designed

'to be initiated automatically...and should be capable of continuous operation thereafter until the design objectivcs of the system have been achieved. In all cases the operating period should not be less than two houre.' This criterion is normally met by automatic initiation and automatic switchover of the spray pumps to the recirculation mode. To determine if these criteria are met with the operator action proposed for Byron, discuss:

1) all the actions required of the operator to transfer the containment spray pumps to the recirculation mode,

2) the timing for the operator actions, including timing of instruments indicating that these actions are required, and

3) the permissible time intervals for operator actions, and the effects on system performance, including spray and sump pH variations, of delayed operator response."

RESPONSE

Refer to the response to Question 022.25.

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0450.2-1

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