ML20058L827

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Forwards Info Addressing SSAR Chapter 3,ABWR Piping,W/Regard to Concern of Suppl 3 of NRC Bulletin 88-008, Thermal Stresses in Piping Connected to Rcs
ML20058L827
Person / Time
Site: 05200001
Issue date: 05/07/1993
From: Fox J
GENERAL ELECTRIC CO.
To: Poslusny C
Office of Nuclear Reactor Regulation
References
IEB-88-008, IEB-88-8, NUDOCS 9305130011
Download: ML20058L827 (8)
v • d • e


Text

. _. _

GENuclearEnergy l

GeneralEle:tnc Comparv i

175 Curtnet hvenue. San. lase CA 35125

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l May 7,1993 Docket No. STN 52-001 i

Chet Poslusny, Senior Project Manager Standardization Project Directorate Associate Directorate for Advanced Reactors and License Renewal Office of the Nuclear Reactor Regulation e

Subject:

Submittal Supporting Accelerated ABWR Review Schedule - SSAR Chapter j

3, ABWR Piping: Concern of Supplement 3 of NRC Bulletin 88-08 t

Dear Chet:

j

addresses the subject concern identified by the staff during resolution of the DFSER piping open items. The concern is associated with, but distinct from, the one evaluated t

l in DFSER Subsection 14.1.33.5.9; no DFSER issue item number has been assigned.

Please provide copies of this transmittal to Shou Hou, Dave Terao, Son Ninh, Jim Brammer and i

Mark Hartzman.

Sincerely,

[

t i

l W

Jack Fox 4

Advanced Reactor Programs l

cc: Frank Cooke (GE) i Giuliano De Grassi (BNL)

Norman Fletcher (DOE)

Maryann Herzog(GE)

Nil Patel(GE)

Ed Swain (GE)

]

l.

BillTaft (GE) l JIW137 f

m 9305130011 930507 PDR.ADOCK-05200001 1J.)

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O 3

3 ATTACHMENT 1 May 7,1993 j

l ABWR Piping ; Concern of Supplement 3 of NRC Bulletin 88-08, j

j Thermal Stresses in Piping Connected to Reactor Coolant Systems l

Subject:

ABWR Piping, DFSER Subsection 14.1.3.3.5.9, Thermal Oscillations m Piping Connected to the Reactor Coolant System; NRC Bulletin 88-08

Purpose:

The subject DFSER subsection discusses the concern of NRC Bulletin 88-08 (June 22,1989) addressed in RAI Question 210.50. This l

attachment addresses an additional associated concern which was identified by the NRC staff during resolution of the DFSER piping open items. The concern is associated with, but distinct from, the one ed ated in DFSER Subsection 14.1.3.3.5.9; no DFSER issue item nmuoer has been assigned.. This attachment identifies the ABWR piping sections that could be potentially susceptible to unacceptable thermal stresses identified in Reference 1. The design actions taken to i

preclude such concern are also identified.

l References.

i (1) NRC Bulletin No. 88-08, Supplement 3, " Thermal Stresses in Piping Connected to Reactor Coolant Systems," dated April 11,1989.

l

-i (2) Docket No. 50-461, Letter fromJ. S. Perry (Illinois Power Company) to the j

Nuclear Regulatory Commission, "Clinton Power Station (CPS), Revision of j

Response to Bulletin 88-08, Supplement 3," Letter No.JSP-164-92, dated

-l March 30,1992.

t I

(3) Docket No. 50-461, Letter from Anthony T. Gody'(NRC) to Mr. Frank A.

Spangenberg (Clinton Power Station), "NRC Bulletin 88-08, ' Thermal Stresses in Piping Connected to Reactor Coolant Systems,' (TAC No. 69616)," dated November 261991.

i I. IDENTIFICATION OF PIPING SFCTIONS 1

The concern involves a potential phenomenon of periodic stratified flow (with I

associated thermal striping) in the unisolable (normally stagnant) sections of pipmg between the. reactor pressure vessel (RPV) and the first normally closed gate valve.

The periodic flow may occur because of possible leakage past the valve disk and out the valve stem packing gland, when the pressure on the other side of the valve is less than the RPV system pressure during normal operation. In the ABWR design, such piping sections are in the residual heat removal (RHR) system and the high pressure core flooding (HPCF) system of the emergency core cooling system (ECCS) network.

ATTACHMEAT I May 7,1993 In the residual heat removal (RHR) system, the unisolable sections of piping connected to the RPV are in two areas:

(a) Two low pressure flooder (LPFL) injection lines of the ECCS network: A section of the pipe between the RPV nozzle and the upstream (in injection mode) gate valve, l

which is a motor-operated outboard containment isolation vahc. This section includes an inboard check valve which would diminish the possibility of significant stratification and leakage through the gate valve even if there is a possibility of a leakage through the check valve; the leakage through check valve would create mixing and minimize stratification and would reduce the flow out of l

the check valve stem packing. However,it is postulated that a small amount of l

periodic leakage could flow past the check valve and then eventually out the gate l

valve stem packing gland.

(b) Three RHR shutdown cooling (SDC) suction lines: A section of pipe between the RPV nozzle and the downstream (in SDC mode) gate valve, which is a motor-operated inboard containment isolation valve. This section includes a normally open maintenance (shut-off) valve.

In the two lines of the high pressure core flooding (HPCF) system of the ECCS network, the unisolable section of piping connected to the RPV is between the RPV nozzle and the upstream (in injection mode) gate valve, which is a motor-operated outboard containment isolation valve. As in an LPFL piping section, each HPCF piping section includes an inboard check valve, which is postulated to allow a small amount ofleakage.

II. DESIGN ACTIONS Based on guidance in References 2 and 3, one of the following design actions is taken:

(1) Locate the gate valve in each of the unisolable piping sections that are identified in Section I at a distance greater than or equal to 25 pipe diameters from the RPV nozzle, or (2) Perform stress analysis to show that stresses and fatigue from potential thermal stratification and thermal striping are acceptable per the ASME Code.

Based on preliminary layouts of piping, the first option seems viable.

III. SSAR UPDATE The design requirements of Section 11 are incorporated in the SSAR by including a i

note with the above identified piping sections shown on P&lD's of RHR system (Figure 5.4-10, Sheets 1,2,5 and 7) and HPCF system (Figure 6.3-7, Sheet 1). See attached markups.

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