Text

Technical Specification (TS) Change 02-06, Increased Condensate Storage Tank (CST) Minimum Volume
	ML023290410
Person / Time
Site:	Sequoyah
Issue date:	11/15/2002
From:	Salas P; Tennessee Valley Authority
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	TVA-SQN-02-06
	Download: ML023290410 (113)
	v • d • e

Tennessee Valley Authority, Post Office Box 2000, Soddy-Daisy, Tennessee 37384-2000 November 15, 2002 TVA-SQN-TS-02-06 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555 Gentlemen:

In the Matter of

)

Docket Nos. 50-327 Tennessee Valley Authority

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50-328 SEQUOYAH NUCLEAR PLANT (SQN) - UNITS 1 AND 2 - TECHNICAL SPECIFICATION (TS) CHANGE 02-06, "INCREASED CONDENSATE STOARAGE TANK (CST) MINIMUM VOLUME" Pursuant to 10 CFR 50.90, TVA is submitting a request for a TS change (TSC 02-06) to licenses DPR-77 and DPR-79 for Units 1 and 2. The proposed change will revise TS 3.7.1.3, "Condensate Storage Water," Limiting Condition for Operation for SQN Units 1 and 2 by increasing the required minimum amount of stored water from 190,000 gallons to 240,000 gallons. TVA is requesting this change to support the replacement steam generator requirements. Greater steam generator structural mass and upgraded regulatory standards were used to reevaluate the minimum CST volume. This request is similar to the approved license amendment request by South Carolina Electric & Gas Company's (SCE&G)

Virgil C. Summer Nuclear Station, Amendment Number 145 issued July 7, 2000.

TVA has determined that there are no significant hazards considerations associated with the proposed change and that the TS change qualifies for 0"d Printed on recycled paper

U.S. Nuclear Regulatory Commission Page 2 November 15, 2002 categorical exclusion from environmental review pursuant to the provisions of 10 CFR 51.22 (c)(9). The SQN Plant Operations Review Committee and the SQN Nuclear Safety Review Board have reviewed this proposed change and determined that operation of SQN Units 1 and 2, in accordance with the proposed change, will not endanger the health and safety of the public. Additionally, in accordance with 10 CFR 50.91 (b)(1), TVA is sending a copy of this letter and attachments to the Tennessee State Department of Public Health. As part of the proposed license amendment request, no commitments have been made by TVA.

TVA requests approval of this TS change to support the Unit 1 Cycle 12 outage currently scheduled for March 2003. TVA requests that the implementation of the revised TS be within 45 days of NRC approval. This letter is being sent in accordance with NRC RIS 2001-05.

If you have any questions about this change, please telephone me at (423) 843-7170 or J. D. Smith at (423) 843-6672.

Licensing and Industry Affairs Manager I declare under penalty of perjury that the foregoing is true and correct. Executed on this 15.f-day of Cl~ eC Enclosures

1. TVA Evaluation of the Proposed Changes

2. Proposed Technical Specifications Changes (mark-up)

3. Changes to Technical Specifications Bases pages

4. Framatome ANP's SQN Condensate Volume Requirement Verification TENNESSEE VALLEY AUTHORITY SEQUOYAH PLANT (SQN)

UNITS 1 AND 2 TVA Evaluation of the Proposed Change

1.

DESCRIPTION This letter is a request to amend Operating License(s) DPR-77 and DPR-79 for SQN Units 1 and 2. The proposed change would revise the Limiting Condition of Operation (LCO) of Technical Specification (TS) 3.7.1.3, "Condensate Storage Water (CST)," to require an additional inventory of water storage, as the preferred coolant source during credible design accidents. In addition, the associated TS Bases will be modified for clarity. This proposed change will address the requirement of additional coolant water for plant transients resulting in the need for auxiliary feedwater after replacement steam generators installation. contains the proposed TS Bases revision associated with the proposed revised LCO.

2.

PROPOSED CHANGE This amendment request proposes to revise SQN's TS 3.7.1.3, "Condensate Storage Water," for Units 1 and 2 by increasing the minimum amount of stored water.

Specifically, the minimum water volume value of 190,000 gallons will be replaced by 240,000 gallons such that the revised LCO will state:

"The condensate storage tank system (CST) shall be OPERABLE with a contained water volume of a least 240,000 gallons of water."

The associated TS Bases 3/4.7.1.3, "Condensate Storage Tank," also includes a proposed revision. This proposed revision will clarify the basis for the minimum amount of water. This revision, as can be seen in Enclosure 3, will include the statement:

"and to subsequently reduce the reactor coolant system temperature to HOT SHUTDOWN conditions in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months at which time the heat removal load is transferred to the residual heat removal system."

In summary, the minimum condensate storage tank water volume of 190,000 gallons to be maintained during applicable modes will be increased to 240,000 gallons. This change reflects the necessary minimum amount of feedwater, with an additional 12,000 gallon margin, to assist in steam generator recovery of Unit 1 by removing primary stored and residual core energy for such events as loss of normal feedwater supply or secondary system pipe rupture. This proposed change is conservatively requested for both units since the Unit 1 CST is inter-connected to the Unit 2 CST.

El-I

3.

BACKGROUND Each of SQN's CST's consist of a non-seismic qualified carbon steel tank with capacity of 385,000 gallons. The CST's are connected to the condenser hotwell and hotwell pumps discharge for the addition and dumping of water, respectively, to maintain water inventory in the secondary system. Storage tank level is maintained by makeup from the water treatment plant. Each tank is equipped with an electronic level indicator which provides continuous tank level indication and provides a signal in the main control room for annunciation of abnormal tank levels. In addition, each tank is provided with a local level indicator. The current minimum water amount of 190,000 gallons in each tank is reserved for the auxiliary feedwater (AFW) Systems by means of an administrative limit based upon indicated level set points.

A CST is the preferred and primary source of clean water for the AFW. An alternate unlimited source of cooling water is supplied by the seismic Category 1 essential raw cooling water (ERCW) system. The ERCW supply can be remote-manually aligned based on CST level or automatically on a two-out-of-three low-pressure signal in the condensate suction line. In addition, the fire protection system can be aligned to supply feedwater in the event of a flood above plant grade. (Reference 1)

TS 3.7.1.3 currently requires the CST of both Unit 1 and 2 be operable by maintaining a minimum water volume of 190,000 gallons. This minimum volume of water in the CST is specified, as stated in TS Bases 3.7.1.3, to ensure sufficient water is available to the AFW system to maintain the reactor coolant system (RCS) at hot standby for two hours.

(Reference 2)

Sequoyah is currently working towards replacement of its Unit 1 steam generators in the Spring of 2003. The design of the replacement steam generator provides additional structural mass over the original steam generator and consequently an increase in stored energy content. TVA has chosen to reevaluate the minimum CST volume using a newer standard for decay heat generation and associated conservative input parameters. These changes have resulted in an increase in the minimum CST inventory. In addition to this proposed TS LCO change, a TS Bases change is proposed to clarify that the CST minimum volume includes capacity to reduce the RCS temperature to hot shutdown conditions within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months of reactor trip.

There is precedence for allowing an increase in the minimum required water volume in the CST as a result of replacement steam generators. The South Carolina Electric &

Gas Company (SCE&G) operating license for the Virgil C. Summer Nuclear Station, has been amended to allow an increase in the required minimum water volume of the CST as a result of replacement steam generators, uprate, and recalculated value of the unusable volume of the CST. This amendment, Number 145, was issued on July 7, 2000.

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4. TECHNICAL ANALYSIS The minimum required volume of water in the CST, as specified by LCO 3.7.1.3, is being changed from 190,000 gallons to 240,000 gallons. This change is based on the increased requirements created by installing replacement steam generators on Unit 1, newer standard for modeling decay heat generation (Reference 3), and revised input assumptions for the calculation to determine the minimum water volume necessary during plant transients.

The previous required inventory of 190,000 gallons was originally based on a very conservative decay heat model and the time from a reactor trip to placing the residual heat removal (RHR) system in service (References 4 and 5). The core decay heat model for the original CST inventory determination was based on the conservative Westinghouse Electric Company decay heat model (circa 1970), a precursor to ANS 5.1-1971. To determine the new CST inventory requirements, the core heat production associated with decay heat is based on the 1994 ANS standard with B&W heavy actinide contribution.

Several of the original assumptions were incorporated into the calculation. These assumption are as follows:

1. Following reactor trip, no reactor coolant pumps are operating,

2. Following the reactor trip, the RCS temperature is reduced to 350 degrees Fahrenheit (OF) over a period of 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , at which time the heat removal load is transferred to the RHR system, (NOTE: The sequence and length of time at hot standby and for cooldown do not affect the water requirement; rather, the time from reactor trip to RHR operation determines the water requirement.)

3. All feedwater is assumed to be delivered to the steam generator for heat removal by evaporation and released through the main steam safety valves. Release of feedwater other than through the main steam safety valves, such as spillage due to a feedline break, is not considered.

The following assumptions have been changed from the original CST inventory calculations to allow greater operation freedom and support emergency response guidelines:.

1. The original AFW temperature assumption of 100OF used by Westinghouse Electric Company in 1971 was increased by 20 degrees for an AFW temperature input value of 1200F, E1-3

2. The original AFW requirement did not include the quantity of water needed to refill the steam generators; whereas this calculation considered steam generator refill to the normal zero load level, and

3. The assumption of the reactor operating at 102% of the power level (corresponding to the turbine-generator unit maximum calculated heat balance) was changed to 100.7%. This is the result of the recent installation of a new main feedwater leading edge flow measurement system which provided a 1.3% reduction in the calorimetric uncertainty of the secondary side power measurement.

The calculation to determined the minimum volume requirements of the CST is included in Enclosure 4.

The proposed increase in the minimum water volume of the CST ensures that a sufficient quantity of the preferred source of clean feedwater is available for use during plant transients that require use of the AFW system. However, the CST's are not seismically qualified and NRC Branch Technical Position (RSB 5-1) Section G, "Auxiliary Feedwater Supply," states:

The Seismic Category I water supply for the auxiliary feedwater system for a PWR (pressure water reactor) shall have sufficient inventory to permit operation at hot shutdown for at least 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , followed by cooldown to the conditions permitting operation of the residual heat removal (RHR) system. The inventory needed for cooldown shall be based on the longest cooldown time needed with either only onsite or only offsite power available with an assumed single failure.

The AFW system is backed by an unlimited supply of water from the ERCW system, which is designed for seismic conditions (i.e., seismic Category 1) and meets single failure requirements (References 6 and 7). Hence, Sequoyah meets RSB 5-1 Section G.

In summary, the proposed revision to TS 3.7.1.3, "Condensate Storage Tank,"

minimum water volume from 190,000 gallons to 240,000 gallons reflects the additional amount of water necessary to cool the replacement steam generators of Unit I with the revised assumptions. TVA has proposed that both the Unit 1 and 2 TSs be revised because Unit 1 and Unit 2 CSTs are inter-connected. The proposed minimum water volume increase is the result of calculations performed by Framatome ANP. These calculations took into consideration the original calculations basis for the LCO for TS 3.7.1.3; the increase in structural mass of the new steam generators; a more limiting AFW temperature of 1200F, refill to the normal steam generator zero load level, and the recent upgrade in rated thermal power. Since the calculations were performed with a more limiting replacement steam generator for Unit 1, they are also applicable to the original Unit 2 steam generators.

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5.

REGULATORY SAFETY ANALYSIS This license amendment request proposes to revise SQN's TS 3.7.1.3, "Condensate Storage Water," for Units I and 2 by increasing the minimum amount of stored water.

Specifically, the minimum water volume value of 190,000 gallons will be replaced by 240,000 gallons such that the revised LCO will state:

"The condensate storage tank system (CST) shall be OPERABLE with a contained water volume of a least 240,000 gallons of water."

The associated TS Bases 3/4.7.1.3, "Condensate Storage Tank," also includes a proposed revision. This proposed revision will clarify the base for the minimum amount of water. This revision, as can be seen in Enclosure 3, will include the statement:

"and to subsequently reduce the reactor coolant system temperature to HOT SHUTDOWN conditions within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months at which time the heat removal load is transferred to the residual heat removal system."

In summary, the minimum CST water volume of 190,000 gallons to be maintained during applicable modes will be increased to 240,000 gallons. This change reflects the necessary minimum amount of feedwater, with administrative margin, to assist in steam generator recovery of Unit 1 by removing primary stored and residual core energy for such events as loss of normal feedwater supply or secondary system pipe rupture.

Because Unit 1 CST is inter-connected to the Unit 2 CST, this proposed change is conservatively requested for both units.

5.1 No Significant Hazards Consideration TVA has evaluated whether or not a significant hazards consideration is involved with the proposed amendment(s) by focusing on the three standards set forth in 10 CFR 50.92, "Issuance of amendment," as discussed below:

1.

Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?

Response: No.

The proposed change does not change the physical design and construction of the condensate storage tank (CST). The purpose of the increased water volume is to ensure that the required volume of water, preserved by the technical specification (TS), is sufficient to meet Sequoyah Nuclear Plant (SQN) Licensing and Design Basis after installation of the replacement steam generators. The change in the administratively controlled inventory of the CST will not increase the probability of an accident. Therefore, the proposed change does not involve a significant increase in the probability of consequences of an accident previously evaluated.

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2.

Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?

Response: No.

This change increases the minimum required volume of water in the CST, thus ensuring that the auxiliary feedwater (AFW) system can perform its required safety function, using a preferred water source for plant transient mitigation.

The maximum and normal water levels in the CST are not being changed.

Additionally, increasing the minimum water volume requirement will not initiate any accident. Therefore, the proposed change does not create the possibility of a new or different kind of accident from any previously evaluated.

3.

Does the proposed change involve a significant reduction in a margin of safety?

Response: No.

This change does not reduce any margin associated with the CST inventory available to AFW. The requirement for sufficient CST volume to maintain hot standby and subsequent cooldown to hot shutdown continues to be met by the minimum volume increase. Additionally, the essential raw cooling water (ERCW) system still provides the long-term supply of safety grade cooling water to the AFW in the event that all inventory of the CST is lost. Therefore, the proposed change does not involve a significant reduction in a margin of safety.

Based on the above, TVA concludes that the proposed amendment(s) present no significant hazards consideration under the standards set forth in 10 CFR 50.92 (c), and accordingly, a finding of "no significant hazards consideration" is justified.

5.2 Applicable Regulatory Requirements/Criteria The regulatory basis for TS 3.7.1.3, "Condensate Storage Tank," is to provides a safety grade source of water to the steam generators for removing decay and sensible heat from the reactor coolant system (RCS). Sequoyah CST provides the primary and preferred source of AFW during plant transients. The ERCW is the backup safety-related system which meets the basis for providing a safety grade source of water.

10 CFR Part 50 General Design Criteria (GDC) 2, "Design bases for protection against natural phenomena," requires structures, systems, and components (SSCs) important to safety shall be designed to withstand the effects of natural phenomena such as earthquakes, tornadoes, hurricanes, floods, tsunami, and seiches without loss of capability to perform their safety functions.

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GDC 5, "Sharing of structures, systems, and components," requires that SSCs important to safety shall not be shared among nuclear power units unless it can be shown that such sharing will not significantly impair their ability to perform their safety functions, including, in the event of an accident in one unit, an orderly shutdown and cooldown of the remaining units.

GDC 44, "Cooling water," describes that a system to transfer heat from SSCs important to safety, to an ultimate heat sink shall be provided.

GDC 45, "Inspection of cooling water system," defines that the cooling water system shall be designed to permit appropriate periodic inspection of important components, such as heat exchangers and piping, to assure the integrity and capability of the system.

GDC 46, "Testing of cooling water system," requires that the cooling water system shall be designed to permit appropriate periodic pressure and functional testing.

Regulatory Guidance 1.29, "Seismic Design Classification," describes the acceptable method for identifying and classifying those features of a light-water cooled nuclear power plant that should be designed to withstand the effects of a Safe Shutdown Earthquake.

NRC Branch Technical Position RSB 5-1, "Design Requirements of the Residual Heat Removal System," dated July 1981.

NUREG -0800, "U.S. NRC Standard Review Plan," Section 9.2.6, "Condensate Storage Facilities," provides guidance to the NRC staff for the review and evaluation of system design features from the CST to the connections or interfaces with other systems associated with the condensate storage facilities, which may or may not be safety related.

The CST is aligned to the AFW system as the primary and preferred source of cooling water for plant transients that result in a need for AFW. NUREG-0800, Standard Review Plan, Section 9.2.6, "Condensate Storage Facility," provides guidelines to assure conformance with the requirements of General Design Criteria 2, 5, 44, 45, and 46. A condensate storage facility may not be safety related as in the case of Sequoyah's CST, but it is recognized that a CST may have provisions to automatically transfer to a seismic Category I source. Sequoyah conforms with these requirements.

The TSs for the CST has once been amended to extend the limiting condition for operation of the CSTs to Mode 4 when steam generators are relied upon for heat removal. In the accompanying NRC safety evaluation report (SER) it was written that following a reactor trip, decay heat is dissipated by evaporating water in the steam generator and venting the steam either to the condensers or to the E1-7

atmosphere. In such situations, steam generator water inventory must be maintained at a level sufficient to ensure adequate heat transfer and decay heat removal. The AFW system pumps deliver this emergency water supply to the steam generators. The AFW system provides emergency water to the steam generators until either normal feed water flow is established or the residual heat removal (RHR) system can assume the decay heat removal function. The primary sources of water for the AFW system pumps are the CSTs. On low suction pressure, the AFW pumps are designed to automatically swap to the ERCW.

The ERCW is a seismic Category 1 system (Reference 6). However in order to maintain our current license basis, preferred source, and an adequate amount of the primary source of cooling water, SQN has chosen to request a license amendment to increase the minimum amount of CST inventory.

In conclusion, based on the considerations discussed above, (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.

6.

ENVIRONMENTAL CONSIDERATION A review has determined that the proposed amendment would change a requirement with respect to installation or use of a facility component located within the restricted area, as defined in 10 CFR 20, or would change an inspection or surveillance requirement. However, the proposed amendment does not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluent that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure. Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22( c)(9). Therefore, pursuant to 10 CFR 50.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed amendment.

7.

REFERENCES

1. Sequoyah Nuclear Plant, Final Safety Analysis Report (As Updated) Revision 17, Section 10.4.7.2.2, "System Description"

2. Sequoyah Nuclear Plant, Technical Specification Bases 3/4.7.1.3, "Condensate Storage Tank"

3. American Nuclear Society Document ANSI/ANS-5.1-1994, "American National Standard for Removing Decay Heat Power in Light Water Reactors," dated August 23, 1994 E1-8

4. Letter to TVA from Westinghouse Electric Corporation, "AFW Flows and Condensate Storage Tank Volume," dated May 23, 1993 (B38930607811)

5. Letter to TVA from Westinghouse Electric Corporation, "Required Auxiliary Feedwater Storage Quantity," dated November 20, 1981 (811218F0714)

6. Sequoyah Nuclear Plant, Final Safety Analysis Report (As Updated) Revision 17, Section 9.2.2, "Essential Raw Cooling Water (ERCW)"

7. NUREG 0011 - Safety Evaluation Report for Sequoyah Nuclear Plant dated March 1979, Section 10.4.2, "Auxiliary Feedwater System" E1-9

ENCLOSURE 2 TENNESSEE VALLEY AUTHORITY SEQUOYAH PLANT (SQN)

UNITS 1 AND 2 Proposed Technical Specification Changes (mark-up)

1.

AFFECTED PAGE LIST Unit 1 3/4 7-7 Unit 2 3/4 7-7

11.

MARKED PAGES See attached.

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PLANT SYSTEMS CONDENSATE STORAGE TANK LIMITING CONDITION FOR OPERATION 3.7.1.3 A condensate storage tank system (CST) shall be OPERABLE with a contained water volume of at least 1 gallons of water.

I -

I l'

1 240,000 i APPLICABILITY:

MODES 1, 2 and 3, MODE 4 when steam generator is relied upon for heat removal.

ACTION With the condensate storage tank system inoperable, within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months either.

a.

Restore the CST to OPERABLE status or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months without reliance on steam generator for heat removal, or

b.

Verify by administrative means OPERABILITY of the Essential Raw Cooling Water System as a backup supply to the auxiliary feedwater pumps* and restore the condensate storage tank to OPERABLE status within 7 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months without reliance on steam generator for heat removal.

SURVEILLANCE REQUIREMENTS 4.7.1.3.1 The condensate storage tank system shall be demonstrated OPERABLE at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by verifying the contained water volume is within its limits when the tank is the supply source for the auxiliary feedwater pumps.

OPERABILITY shall be verified once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months following initial verification SEQUOYAH - UNIT 1 November 19, 1998 Amendment No. 238 3/4 7-7 E2-2 I

PLANT SYSTEMS CONDENSATE STORAGE TANK LIMITING CONDITION FOR OPERATION 3.7.1.3 The condensate storage tank system (CST) shall be OPERABLE with a contained water volume of at least 488;j.gallons of water.

2 4 0, 00 r'

1240,000, APPLICABILITY:

MODES 1,2and3, MODE 4 when steam generator is relied upon for heat removal.

ACTION:

With the condensate storage tank system inoperable, within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months either:

a.

Restore the CST to OPERABLE status or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months without reliance on steam generator for heat removal, or

b.

Verify by administrative means OPERABILITY of the Essential Raw Cooling Water System as a backup supply to the auxiliary feedwater pumps* and restore the condensate storage tank to OPERABLE status within 7 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months without reliance on steam generator for heat removal.

SURVEILLANCE REQUIREMENTS 4.7.1.3.1 The condensate storage tank system shall be demonstrated OPERABLE at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by verifying the contained water volume is within its limits when the system is the supply source for the auxiliary feedwater pumps.

OPERABILITY shall be verified once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months following initial verification.

SEQUOYAH - UNIT 2 November 19, 1998 Amendment No. 228 3/4 7-7 E2-3 I

ENCLOSURE3 TENNESSEE VALLEY AUTHORITY SEQUOYAH PLANT (SQN)

UNITS I AND 2 Changes to Technical Specifications Bases Pages I.

AFFECTED PAGE LIST Unit 1 B3/4 7-2b Unit 2 B3/4 7-2b II.

MARKED PAGES See attached.

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PLANT SYSTEMS BASES which are designated as Train A, receive A-train air, and provide flow to the same steam generators that are supplied by the B-train motor-driven auxiliary feedwater pump. The remaining two LCVs are designated as Train B, receive B-train air, and provide flow to the same steam generators that are supplied by the A-train motor-driven pump. This design provides the required redundancy to ensure that at least two steam generators receive the necessary flow assuming any single failure. It can be seen from the description provided above that the loss of a single train of air (A or B) will not prevent the auxiliary feedwater system from performing its intended safety function and is no more severe than the loss of a single auxiliary feedwater pump. Therefore, the loss of a single train of auxiliary air only affects the capability of a single motor-driven auxiliary feedwater pump because the turbine-driven pump is still capable of providing flow to two steam generators that are separate from the other motor-driven pump.

Two redundant steam sources are required to be operable to ensure that at least one source is available for the steam-driven auxiliary feedwater (AFW) pump operation following a feedwater or main steam line break. This requirement ensures that the plant remains within its design basis (i e., AFW to two intact steam generators) given the event of a loss of the No 1 steam generator because of a main steam line or feedwater line break and a single failure of the B-train motor driven AFW pump. The two redundant sources must be aligned such that No. 1 steam generator source is open and operable and the No. 4 steam generator source is closed and operable.

For instances where one train of emergency raw cooling water (ERCW) is declared inoperable in accordance with technical specifications, the AFW turbine-driven pump is considered operable since it is supplied by both trains of ERCW. Similarly, the AFW turbine-driven pump is considered operable when one train of the AFW loss of power start function is declared inoperable in accordance with Technical Specifications because both 6.9 kilovolt shutdown board logic trains supply this function. This position is consistent with American National Standards Institute/ANS 58.9 requirements (i e., postulation of the failure of the opposite train is not required while relying on the TS limiting condition for operation) 3/4 7.1 3 CONDENSATE STORAGE TANK The OPERABILITY of the condensate storage tank with the minimum water volume ensures that sufficient water is available to maintain the RCS at HOT STANDBY conditions for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months with steam discharcqe to the atmosphere concurrent with total loss of off-site powe* The contained water volume limit includes an allowance for water not useable because of tank discharge line location or other physical characteristics.

,SENIENIEINSERT and to subsequently reduce the reactor coolant system temperature torn HOT SHUTDOWN conditions in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months at which time the heat removal "load is transferred to the residual heat removal system I

August 22, 1995 SEQUOYAH - UNIT 1 B 3/4 7-2b Amendment No 115, 155, 182,188 196, 207 E3-2

PLANT SYSTEMS BASES train air, and provide flow to the same steam generators that are supplied by the A-train motor-driven pump. This design provides the required redundancy to ensure that at least two steam generators receive the necessary flow assuming any single failure. It can be seen from the description provided above that the loss of a single train of air (A or B) will not prevent the auxiliary feedwater system from performing its intended safety function and is no more severe than the loss of a single auxiliary feedwater pump.

Therefore, the loss of a single train of auxiliary air only affects the capability of a single motor-driven auxiliary feedwater pump because the turbine-driven pump is still capable of providing flow to two steam generators that are separate from the other motor-driven pump.

Two redundant steam sources are required to be operable to ensure that at least one source is available for the steam-driven auxiliary feedwater (AFW) pump operation following a feedwater or main steam line break. This requirement ensures that the plant remains within its design basis (i e., AFW to two intact steam generators) given the event of a loss of the No 1 steam generator because of a main steam line or feedwater line break and a single failure of the B-train motor driven AFW pump. The two redundant sources must be aligned such that No. 1 steam generator source is open and operable and the No 4 steam generator source is closed and operable.

For instances where one train of emergency raw cooling water (ERCW) is declared inoperable in accordance with technical specifications, the AFW turbine-driven pump is considered operable since it is supplied by both trains of ERCW. Similarly, the AFW turbine-driven pump is considered operable when one train of the AFW loss of power start function is declared inoperable in accordance with technical specifications because both 6.9 kilovolt shutdown board logic trains supply this function. Similarly, the AFW turbine-driven pump is considered operable when one train of the AFW loss of power start function is declared inoperable in accordance with Technical Specifications because both 6.9 kilovolt shutdown board logic trains supply this function. This position is consistent with American National Standards Institute/ANS 58.9 requirements (i.e., postulation of the failure of the opposite train is not required while relying on the TS limiting condition for operation).

3/4 7.1 3 CONDENSATE STORAGE TANK The OPERABILITY of the condensate storage tank with the minimum water volume ensures that sufficient water is available to maintain the RCS at HOT STANDBY conditions for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months with steam discharge to the atmosphere concurrent with total loss of off-site power The contained water volume limit includes an allowance for water not usable because of tank discharge line location or other physical characteristics.

LSMTENCE INSERT--

and to subsequently reduce the reactor coolant system temperature to HOT SHUTDOWN conditions in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months at which time the heat removal

' load is transferred to the residual heat removal system n

I August 22, 1995 SEQUOYAH - UNIT 2 B 3/4 7-2b Amendment No. 105, 174, 180, 187, 197 E3-3

ENCLOSURE4 TENNESSEE VALLEY AUTHORITY SEQUOYAH PLANT (SQN)

UNITS 1 AND 2 Framatome ANP, SQN Condensate Volume Requirement Verification F.4-1

B38 021104 802 QA Record NOV 0 4 202 Framatome Advanced-Nuclear Power (FANP)

P. 0. Box 10935 Lynchburg, Virginia 24506-0935 Attention-Mr. W. L. Redd Gentlemen:

SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 - ENGINEERING AND ANALYSIS SUPPORT SERVICES - CONTRACT 99NNQ-256540 - LETTER TVFTI-071 CONTRACT WORK AUTHORIZATION NO. N2000-001 DOCUMENT SUBMITTAL CONDENSATE STORAGE TANK MINIMUM CONTAINTED VOLUME EVALUATION - N2N-057 We acknowledge receipt of the document listed below submitted by Letter FANP-02-2442 and return herewith one copy marked (A), "Approved".

Document No Revision Title 32-5014532 00 Condensate Storage Tank (CST) Minimum Contained Volume Calculation, Unit 1 and 2 The subject calculation evaluates the Sequoyah replacement steam generators with respect to the minimum contained CST volume requirement in Section 3.7.1.3 of the Sequoyah Technical Specifications.

The calculation models the changes in the steam generator tube heat transfer surface area and heat transfer coefficient and establishes the minimum CST volume requirements for plant cooldown following a full power reactor trip to residual heat removal operating conditions. The calculation also evaluates the effect of assumed condensate temperature and steam generator level on the minimum volume requirements.

We have reviewed the subject calculation and note that the minimum required CST volume for the replacement steam generators using the currently assumed nominal condensate temperature (100'F) and post-trip steam generator level (no refill) is 188,700 gallons. However, we also note that the calculation is based on decay heat calculated using the 1994 American Nuclear Society (ANS) decay heat standard.

Since the current condensate temperature and steam generator refill assumptions are predicated on the use of a conservative decay heat generation model (i.e., the 1970 Westinghouse Electric Company decay heat

NOV 0 4 2002 Framatome Advanced Nuclear Power Page 2 model), we do not consider continued use of these assumptions to be appropriate for use with the 1994 ANS decay heat standard. Based on a bounding condensate temperature of 120'F and a steam generator post-trip refill level assumption consistent with current operating practice (i e., 39 percent of the narrow range instrument span), the subject calculation establishes a minimum CST contained volume requirement of 228,000 gallons. We plan to adopt this value as the revised safety analysis limit for operation with the replacement steam generators. Since this value exceeds the 190,000 gallon minimum contained volume requirement in Section 3.7.1.3 of the Sequoyah Technical Specifications, we have initiated Sequoyah Technical Specification Change Request No. TVA-SQN-TS-02-06 to increase the current CST contained volume operability limit from 190,000 gallons to 240,000 gallons. Because the Sequoyah Unit 1 and Unit 2 condensate storage tanks are interconnected, this change will be made to the Unit 2 Technical Specifications as well as the Unit I Specifications.

Please note we have made the following annotations to the TVA approved copies of the subject document.

1. Page 4 - To be consistent with the operating mode definitions given in Table 1.1 of the Sequoyah Technical Specifications, we have annotated the second paragraph in Section 1.1 on this page to read, "The reactor is tripped and the plant is cooled in hot standby conditions for a 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months time frame. In the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , the plant is cooled from hot standby to hot shutdown (i.e., residual heat removal cut in conditions)."

2. Page 85 -To be consistent with Section 1.1, we have annotated Section 8.1 on this page to read, "...the plant is tripped from full power and cooled in hot standby conditions over a 2-hour period followed by a cool down to RHR cut-in conditions in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; a total of 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ."

Please adjust your records as necessary to reflect these annotations. Please incorporate these annotations in the text of the document should it be revised for any other reason.

The above document was prepared as part of the nuclear steam supply and balance-of-plant systems review performed by FANP under Section 2.7 of the proposal submitted by Letter FTI-99-2241. The calculation is based on design input information provided by Letter TVFTI-057 concerning the technical basis for the current CST contained volume requirement.

Please contact D. M. Lafever at Sequoyah (423-843-8377) if you have any questions or comments regarding the content of this submittal.

Sincerely, P. G. Trudel, Project Engineer Steam Generator Replacement Project

NOV 0 4 2002 Framatome Advanced Nuclear Power Page 3 Enclosure

DML:JS cc: Framatome Advanced Nuclear Power Attn: Mr. F. X. Masseth P. 0. Box 10935 Lynchburg, Virginia 24506-0935 T. L. Aaron, MPB 1A-SQN P. C. Askins, OPS IA-SQN Rt H. Bryan, LP 4J-C C. Carey, OPS 2B-SQN, w/1 R. E. Griffith, OPS 2B-SQN, w/1 D. M. Lafever, OPS 3C-SQN, w/l R. R. Rausch, MPB IA-SQN J. D. Smith, OPS 4C-SQN, w/1 J. F. Thomas, OPS 2B-SQN P. G. Trudel, MPB 1A-SQN, w/1

RIMS, WTC A-K, w/1 B88 021104

B38 021014 804, B38 990930 805, B38 011220 802 800

A Record B88 021104 FRAMATOME ADVANCED NUCLEAR POWER CONDENSATE STORAGE TANK MINIMUM CONTAINED VOLUME CALCULATION FOR STEAM GENERATOR REPLACEMENT SEQUOYAH UNIT 1 AND 2 DOCUMENT NO. 32-5014532 REVISION 00 I

I N

PROJECT Sequovah DISCIPLINE N

CONTRACT 99NN0-256540 UNIT 1 and 2 DESC. SG ReRplacemernt CST Minimum Volume DWG/IDOC NO.

32-5014532 SHEET OF REV.

00 DATE 11/04/02 ECN/DCN FILE N2N-057 RIMS, WTC A-K 80(Q APP ROVED T?"h approvat do" not fatese the Cofitroator trom any part of his 1*

sponsibl~itl for the Correctness of ds*egn. detail and dlm4no1iona.

Letter No. TVFTI-071 O,,.:

November 04, 2002 TNEP 1 (N)

DYP.Q.

AUTHRdITY SC*E P K*

BY'P.O. Trudel

20697-5 (4/2001)

AFRAMATOME AMP CALCULATION

SUMMARY

SHEET (CSS)

Document Identifier 32-5014532 -00 Title SQN CONDENSATE VOLUME REQUIREMENT VERIFICATION PREPARED BY:

REVIEWED BY:

METHOD: 19 DETAILED CHECK [] INDEPENDENT CALCULATION NAME MARK L MILLER NAME SD Blair SIGNATURE

/ 2..f72.-SIGNATURE TITLE PE DATE

/,*/0,?.

TITLE 1=J &

DATE

,-?__!.

COST REF.

TM STATEMENT:

CENTER 41016 PAGE(S) 86 REVIEWER INDEPENDENCE

(/Z PURPOSE AND

SUMMARY

OF RESULTS:

TVA will replace steam generators at SQN, Unit 1. Scoping calculations reveal that slightly more auxiliary feedwater (AFW,) is required to cool the replacements (RSGs) from normal operation to RHR cut-in than it would to cool the original steam generators (OSGs). This file provides verification that the plant cooldown with RSGs can be accommodated within the existing Technical Specification requirement of 190,000 gallons of condensate storage tank (CST) water, given the current calculational basis.

The calculations of this file were extended beyond a simple verification of existing Technical Specification. CST volume requirements were defined for (J) a more limiting AFW temperature of 120 F - the onginal calculations were performed with an AFW temperature of 100 F and (2) for varied final "re-filled" steam generator secondary states at RHR cut-in - current calculational bases do not account for re-fill. Since the calculations were performed with the more limiting RSGs, they are applicable to the OSGs as well and allow TVA the flexibility of improving plant margins commensurate with a Technical Specification change with regards to the CST volume reqUirement.

CST volume requirements were generated with a special formulation of the First Law of Thermodynamics. Calculations consider the removal of decay heat, the cooling of primary and secondary metals and contained fluids, and accounts for the normal makeup required to balance the shrinkage of the primary system fluid owing to the cooldown. The following CST requirements were generated in this file:

CST Requirement, Cooldown from Full Power to RHR Cut-in, Gallons 100FAFW 120FAFW Initial SG Mass at RHR Cut-in 188,700 193.000 SG Tubes Covered by Liquid at RHR Cut-In 195.200 199,600 0% NRL at RHR Cut-In 207,400 212,000 39% NRL at RHR Cutin 223,000 228,000 THE FOLLOWING COMPUTER CODES HAVE BEEN USED IN THIS DOCUMENT:

THE DOCUMENT CONTAINS ASSUMPTIONS THAT MUST BE VERIFIED PRIOR TO USE ON SAFETY-RELATED WORK CODE/VERSIONREV CODENERSIONIREV RELAP5IMod2-BW v. 24.OHP YES NO Page 1

of 8.S

SQN CONDENSATE VOLUME REQUIREMENT VERIFICATION 32-5014532-00 1.1 Introduction This calculation seeks to establish a basis for the Sequoyah Technical Specification condensate storage tank (CST) inventory requirement. The work herein is performed as part of the SG replacement program.

Although the replacement steam generator is used in these calculations the difference in energy content between the original and the replacement steam generator is minimal. The calculations in this file are applicable to both generator designs - to both Units 1 and 2.

Iln ho+"

CC4L,

/ CC%.A*,,%4 0¢ Inputs to the riginal calculations related to the existing CST inventory requirement were examined and the cooldown ass ciated with the original calculation was adapted for this work. The reactor is tripped and the plant is cooled a 2-hour time frame. In the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , the plant is cooled from hot residual heat removal (RHR) cut-in conditions).

Plant parameters are initially based on a RELAP5 steady-state rutf conducted in Reference I. The energy content associated with the heat structures and fluid content contained in the reactor coolant system (RCS) pressure boundary and the SG secondary from the main feedwater piping (at the point of auxiliary feedwater (AMW) entry) to the steam lines (at the turbine) are considered. Core heat production associated with decay heat is simulated with the 1994 ANS standard with B&W heavy actinide contribution.

Thermodynamic "first law" formulation was ultimately applied to determine the needed volume of AFW needed to cool the plant to each operational statepoint. Parametric studies are included in these calculations, allowing TVA to make decisions regarding AFW temperature and final, RHR cut-in, SG secondary inventory.

1.2 Important Inputs

"* Full power core energy content is accounted for in these calculations. Only decay heat is modeled, however, and the initial core heat generated during the reactor trip is ignored in these calculations. The coastdown and isolation of the main feedwater sstem - also not modeled - is sufficiently delayed to provide the inventory needed to accommodate the rapidly decaying core power.

"* All steel heat structures, stainless and carbon-, are combined for simplification. Material properties are compared and those properties resulting in the maximum heat content difference between operational modes (maximized AFW requirement) are applied.

The original calculations performed as the basis for the existing CST volume Technical Specification requirement do not account for the operation of reactor coolant pumps. The plant is, therefore, cooled by natural circulation. As a result, there is a measurable difference between the hot and cold leg fluid temperature for shut-down conditions. This difference is accounted for in the calculation of plant structure and fluid energy content via a conservative approximation of this hot - to - cold leg temperature difference.

~7

~&

Q1/22k 4

SQN CONDENSATE VOLUME REQUIREMENT VERIFICATION 32-5014532-00 8.1 Results and Conclusions The condensate storage tank inventory requirement was examined in this calcuion.

b regarding cooldown is adapted - the plant is tripped from full power and cooled

'ot conditions over a 2-hour period followed by a cool-down to RHR cut-in conditions in ours; a total o hours. Parametric studies regarding the auxiliary feedwater temperature and SG secotlary inventory conditions - at RHR cut-in - were performed. Results of the study are detailed in Tabla15.

Table 15 Condensate Storage Tank Inventory Requirement Cooldown from full-power to hot shutdown conditions:

100 F AFW temperature 68,400 gal 120 F AFW temperature 70,000 gal Cooldown from full-power to RHR cut-in conditions:

No change in SG secondary inventory 100 F AFW temperature 188,700 gal 120 F AFW temperature 193,000 gal SG tubes covered by secondary inventory at RHR cut-in 100 F AFW temperature 195,200 gal f

120 F AFW temperature 199,600 gal 0% Narrow Range Level at RHR cut-in 100 F AFW temperature 207,400 gal 120 F AFW temperature 212,000 gal 39% Narrow Range Level at RHR cut-in 100 F AFW temperature 223,000 gal 120 F AFW temperature 228,000 gal 85

206g7.5 (4Jnflfj

, ý"/RAMATOME ANP CALCULATION

SUMMARY

SHEET (CSS)

Document Identifier 32 - 5014532- 00 Title SQN CONDENSATE VOLUME REQUIREMENT VERIFICATION PREPARED BY:

REVIEWED BY:

METHOD: 1 DETAILED CHECK []INDEPENDENT CALCULATION NAME MARK L. MILLER SIGNATURE 4/d1~/'

zfir 2 1 TITLE PE COST CENTER 41016 NAME SD Blair SIGNATURE DATE TITLE-F-=,3j C, J

REF.

PAGE(S)

TM STATEMENT:

REVIEWER INDEPENDENCE 86 PURPOSE AND

SUMMARY

OF RESULTS:

"TVA will replace steam generators at SQN, Unit 1. Scoping calculations reveal that slightly more auxiliary feedwater (AFW) Is required to cool the replacements (RSGs) from normal operation to RHR cut-in than It would to cool the original steam generators (OSGs). This file provides verification that the plant cooldown with RSGs can be accommodated within the existing Technical Specification requirement of 190,000 gallons of condensate storage tank (CST) water, given the current calculational basis.

ýThe calculations of this file were extended beyond a simple verification of existing Technical Specification. CST volume requirements were defined for (1) a more limiting AFW temperature of 120 F-the original calculations were performed with an AFW temperature of 100 F and (2) for varied final "re-filled" steam generator secondary states at RHR cut-in - current calculational bases do not account for re-fill. Since the calculations were performed with the more limiting RSGs, they are applicable to the OSGs as well and allow TVA the flexibility of Improving plant margins commensurate with a Technical Specification change with regards to the CST volume requirement CST volume requirements were generated with a special formulation of the First Law of Thermodynamics. Calculations consider the removal of decay heat, the cooling of primary and secondary metals and contained fluids, and accounts for the normal makeup required to balance the shrinkage of the primary system fluid owing to the cooldown. The following CST requirements were generated in this file:

CST Requirement, Cooldown from Full Power to RHR Cut-n, Gallons Initial SG Mass at RHR Cut-In SG Tubes Covered by Liquid at RHR Cut-In 0% NRL at RHR Cut-in 39% NRL at RHR Cutin 100 FAFW 188,700 195,200 207.400 223,000 120 F AFW 193,000 199,600 212,000 228,000 THE FOLLOWING COMPUTER CODES HAVE BEEN USED IN THIS DOCUMENT:

THE DOCUMENT CONTAINS ASSUMPTIONS THAT MUST BE VERIFIED PRIOR TO USE ON SAFETY-RELATED WORK CODE/VERSION/REV CODENERSION/REV RELAP5/Mod2-BW v. 24.OHP YES NO Page I

of 8.

DATE 20697-5 (AI20011 OwAaeý

SQN CONDENSATE VOLUME REQUIREMENT VERIFICATION 32-5014532-00 Revision Lo*

Revision Level 00 K27K

6/f

Description Original Issue 2

SQN CONDENSATE VOLUME REQUIREMENT VERIFICATION SQN CONDENSATE VOLUME REQUIREMENT VERIFICATION 32-5014532-00 Table of Contents Pane 1.1 Introduction.............................................................................................................................

4 1.2 Important Inputs............................................

4 2.1 Primary and Secondary Heat Structures.................................................................................

5 2.2 Steam Line Piping.......................................................................................................................

12 2.3 M ain Feedwater Line Piping......................................................................................................

14 2.4 M aterial Properties......................................................................................................................

16 2.5 Structure Initial Internal Energy Content.......................

18 2.6 Structure Energy Content, M ode 2...........................................................................................

28 2.7 Structure Energy Content, M ode 3...........................................................................................

38 3.1 Initial RCS Energy Content.................................................................

48 3.2 M ode 2 RCS Energy Content...................................................................................................

50 3.3 M ode 3 RCS Energy Content................................................................................................

51 3.4 Pressurizer Energy Content.......................................................................................................

52 4.1 Initial SG Secondary Energy Content........................................................................................

55 4.2 M ode 2 SG Energy Content........................................................................................................

56 4.3 M ode 3 SG Energy Content....................................................................................................

58 4.4 M FW Line Fluid Internal Energy Calculation.........................................

61 5.1 Calculation of RCS M akeup Addition.....................................................................................

63 5.2 Calculation of Net Secondary Mass Addition..........................

65 6.1 Decay Heat Calculation - 1994 Standard..............

67 7.1 First Law Form ulation, Auxiliary Feedwater Requirem ent.........................................................

80 8.1 Results and Conclusions............................................................................................................

85 References......................................................................................................................................

86 Computer Run Listing.........................................

86 Appendix A........................................................................................................................................

87 3

SQN CONDENSATE VOLUME REQUIREMENT VERIFICATION 32-5014532-00 1.1 Introduction This calculation seeks to establish a basis for the Sequoyah Technical Specification condensate storage tank (CST) inventory requirement. The work herein is performed as part of the SG replacement program.

Although the replacement steam generator is used in these calculations the difference in energy content between the original and the replacement steam generator is minimal. The calculations in this file arc applicable to both generator designs - to both Units I and 2.

Inputs to the original calculations related to the existing CST inventory requirement were examined and the cooldown associated with the original calculation was adapted for this work. The reactor is tripped and the plant is cooled to hot shutdown conditions within a 2-hour time frame. In the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , the plant is cooled from hot shutdown to residual heat removal (RHR) cut-in conditions.

Plant parameters are initially based on a RELAP5 steady-state run conducted in Referencel. The energy content associated with the heat structures and fluid content contained in the reactor coolant system (RCS) pressure boundary and the SG secondary from the main feedwater piping (at the point of auxiliary feedwater (AFW) entry) to the steam lines (at the turbine) are considered Core heat production associated with decay heat is simulated with the 1994 ANS standard with B&W heavy actinide contribution.

Thermodynamic "first law" formulation was ultimately applied to determine the needed volume of AFW needed to cool the plant to each operational statepoint. Parametric studies are included in these calculations, allowing TVA to make decisions regarding AFW temperature and final, RHR cut-in, SG secondary inventory.

1.2 Important Inputs a

Full power core energy content is accounted for in these calculations. Only decay heat is modeled, however, and the initial core heat generated during the reactor trip is ignored in these calculations The coastdown and isolation of the main feedwater system - also not modeled - is sufficiently delayed to provide the inventory needed to accommodate the rapidly decaying core power.

All steel heat structures, stainless and carbon-, are combined for simplification. Material properties are compared and those properties resulting in the maximum heat content difference between operational modes (maximized AFW requirement) are applied.

The original calculations performed as the basis for the existing CST volume Technical Specification requirement do not account for the operation of reactor coolant pumps. The plant is, therefore, cooled by natural circulation. As a result, there is a measurable difference between the hot and cold leg fluid

- temperature for shut-down conditions. This difference is accounted for in the calculation of plant structure and fluid energy content via a conservative approximation of this hot - to - cold leg temperature difference.

SQN CONDENSATE VOLUME REQUIREMENT VERIFICATION 32-5014532-00 2.1 Primary and Secondary Heat Structures The primary and secondary heat structure inputs are compiled from an examination of the Reference I RELAP5 input deck for run sqslbocnul/XVDG, dated 10/17/00, This deck is the null transient deck used in the preparation of the steam line break outside containment RELAP5 model in Reference 1 and includes the W/CE replacement steam generator. The deck is retrieved and exercised over a period of 0.5 seconds to give a good copy of the input summary for the compilation of heat structure data. This "short" run is identified as sqss/XWEL, dated 2/7/02.

Table I lists all of the heat structures associated with the reactor coolant system, core, and steam generator secondary model components. Geometric data is included in Table 1: structure geometries, the inside dimensions, outside dimensions, and surface area factors. Structure volume is not available in the short run output but is calculated in Table 1 as follows:

Slab:

vs 121 =Q(R. -Ri)&-A Cylinder:

Sphere:

where, V-Ri ASF -

VCy!indcr =7(Ro - Ri).As VSpheýe =17(R. 3 R13). ASF structure volume outside dimension inside dimension surface area factor Structure volumes are summed for each major model structure component in Table 1.

5-alz,&-ý-

ý/?/b IL-

Table I RELAP5 Model Heat Structure Geometry Compilation structure d

left right surface structure number escription geometry dimension, ft dimension, ft areaentry volume, ft RCS 1001001 3x hot leg noz cyl 1.2098 1.473 1.0017E+01 22.22 1051001 3x hot leg cyl 1.2098 1.4136 1.5285E÷01 25.67 1051002 3x hot leg cyl 1.2098 1.4136 2.3490E+01 39.45 1051003 3x hot leg cyl 1.2098 1.4136 1.9107E+01 32.09 120100113x rsg In sph 5.2342 5.7925 7.5000E-01 160.08 1202001 3x rsg div plate rec 0

0.16667 1.2910E+02 21.52 1211001 13x rsg in ts rec 0

2.10413 1.1312E+02 238.02 I-';3 IJUU I I.X [sU wuoes I IC I LUL 1251003 1251004 o.x rsg toues 3x rsg tubes 3x rsg tubes 25i 100 17R ax r4s!2 tues C

cyl 0.277 0.315 6.1017E+04 40-u~ut

(

0.03125 6 1017E+04A An AA~

43

_I 1,

1 It L..

s...,..

a, V.

U I

U

.U.1,'4 1251005 3x rsg tubes cyl 0.02767 0.03125 6.1017E+04 40.43 1251006 3x rsg tubes cyl 0.02767 0.03125 6.1017E+04 40.43 1251007 3x rsg tubes cyl 0.02767 0.03125 3.4673E+04 22.98 1251008D 3x rsg tubes cyl___

0.02767 0.03125 3.4673E+04 22.98 1251009 3x rsg tubes cyl 0.02767 0.03125 3A673E+04 22.98

_ 1251010 3x rsg tubes cyl 0.02767 0.03125 3.4673E+04 22.98 1251011 3x rsg tubes cy,

-, 0.02767 0.03125 6.1017E+04 40.43 1251012 3x rsgtubes

_cy]

002767 0.03125 6.101E+04 40.43 1251013 3x rsg tubes cyl

.002767 0.03125 6.1017E+04 140.43 1251014 3x rsg tubes cyl 0.02767 0.03125 6.1017E+04 40.43 1251015 3x rsg tubes PS cyl 1.292767 1.091256.

E+01 25.91 1251016 3x rsg tubes

- yl -

0.02767 0.03125 610 1 7E+04 40.43 1291001 3x rsg

-outts rc0 2.10413

-1.1-312E+02 238 02 1301003 3x rsg out sph 5.2342

-- 5.7925 7.5070E-01 160.08 1351001 3x cold leg ps cyl 1.2927 1.5094 1.4631E+01 27.91 1351002 3x cold l~eg -ps -cyl 1 -.2927 1.5094 1.3584E+01 25.91 1351003 3x cold leg ps cyl 1.2927 1.5094 2.1207E+01 40.45 1351004 3x cold leg. ps cyl.

1.2927 1.5094I 1.0560E+01 20.14 1351D05 3x cold leg ps cyl 1.2927 1.5094 2.120'7E+01 40.45 1601001 3x pump metal cyl 4.3315 4 8405 7.2034E+02 10564.98 1651001 3x cold leg cyl 1.1475 1.34125 1.1688E+01 17.71 1651002 3x col.leg

. cyl_

1.1475 1.34125 4.5597E+01 69.07 1701001 3x cold leg noz cyl 1.1475 1.4761 1.4475E+01 39.19 2001001 x hot leg cyr 1.2098 1.473" 3.3390E+00 7.41 2051001 lx hot leg

__cyl 1.2098 1.4136 5.0950E+00 8.56 2051002 x hot leg cyl 1,2098 1.413 1 7.8300E+00 13.15 2051003 lx hot leg c.yl 1.2098 1.413q 6 3690E+00 10.70

.220100DI1 x rsq in sph 5.2342 5.7925$

2.5000E-01 53.36 2202001 lxrsg div plate rec 0

0.1666 4.3034E+01 7.17 2211001 lx rsg in ts rec 0

2.10413 3.7705E+01 79.34 2251001 lx rsg tubes cyl 0.02767 0.03125 2.0339E+04 13.48 2251002 lx rsg tubes cyl 0.02767 0.03125 2.0339E+04 13.48 2251003 lx rsg tubes cyl 0.02767 0.03125 2.0339E+04 13.8 25 lxrsgI tubes -'

_24 13.48 2251004 lx rsgtubs cl 0.2767 0.0312ý 12.0339E+'041 13.48 3

1-5014532-00 n] riTri7 A n'2_ 4 15r, r-An

'40) -&ýý q-7mz-6 cv]

A n-77R7 A M41=

Sd r14 -Tr-*_rl j 4n CYI cv]

A 0.02767 0.03125 6.1017E÷04 0.02767 0.03125 6 1017Fer*

R Aq

Table I RELAP5 Model Heat Structure Geometry Cilmpilation structure description geometry left righ!t surface structure number dimension, ft dimension, ft area entry volume, ftl 2251005 lx'rsg-tubes ""cyl 0.02767 0.03125 2.0339E+04 13.48 2251006 1lx rsg_ tubes cyl 0.02767 0,03125 2.0339E+04 13.48 2251007 lx rsg tubes cyl 0.02767 0,03125 1.1558E+04 7.66 2251008 lx rsg tubes cyl 0.02767 0.03125 1.1558E+04 7.66 2251009 lx rsg tubes cyl 0.02767 0.03125 1.1558E+04 7.66 2251010 lx rsg tubes cyl 0.02767 0.03125 1.1 558E+04 7.66 2251011 lx rsg tubes cyl_

0.02767 0.03125 2.0339E+04 13.48 2251012 lx rsg tubes _cyl 0.02767 0.03125 2.0339E+04 13.48 2251013 lx rsg tubes cyl 0.02767 0.03125 2 0339E+04 13.48 2251014 lx rsg tubes.... cyl 0.02767 0.03j25 2.0339E+04 13.48 2251015 lx rsg tubes cyl 0.02767 0.031125 2.0339E+04 13.48 2251016 lx rsg tubes.

cyl 0.02767 0.031.25 2.0339E+04 13.48 2291001 lx rsg outts Jrec _-"

0 2.104,13 3.7705E+01 79.34 2301001 lx rsg out sph 5.2342 5,7925 2.50OOE-01 53.36 2351001 lx cold leg ps cyl 1.2927 1.5094 4.8770E+00 9.30 2351002 lx cold leg ps cyl___

1.2927 1.5094 4.5280E+00 8.64 2351003 lx cold leg ps cyl 1.2927 1.5094 7.0690E+00 13.48 2351004 lx cold leg ps cyl 1.2927 1.5094 3.5200E+00 6.71 2351005 lx cold leg-ps cyl 1.2927 1.50P4 7.0690E+00 1348 2601001 lx pump metal cyyl 4.3315 4.8405 2.4011E+02 3521.66 2651001 lx cold leg cyl 1.1475 1.34125 3.8960E+00 5.90 2651002 lx cold leg cyl 1.1475 1.34125 1.5199E+01 23.02 2701001 lx cold leg noz cyl 1.1475 1.476 4.8250E+00 13.06 3001001 3x de shell--

cyl 7.2083 8.0838 5 2500E+0D 220.82 3001002 3x dc shell cyl 7.2083 8.0838 2.9380E+00 123.57 3001003 3x dc shell cyl.-....

7.2083 8.0838 4.9630E+00 208.75

_3001004 3x dc shell cyl__ ____

7.2083 8.0838 4.9630E+00 208.75 3021001 3x therm sh cyl 6.604 6.837 2.4375E+00 23.98 3021002 3x therm sh cyl 6.604 6.837 2.5425E+00 25.01 3021003 3x therm sh cyl 6.604 6.837 3.1350E+00 30.84 3021004 3x therm sh cyl 6.604 6.837 3.3975E+00 33.43 3081001 3Xi shell cy_______l 7.2083 7.9064 5.6070E+00 185.86 3101001 rvbottom sph 7.346 8.01235 1.9810E-01 97.88 3121001 3xbh internals rec 0

0.041P7 9.6940E+02 40.39 3121002 3x bh internals rec 0

0.04167 1.2081E+03 5034 3121 003 3xbh internals rec____'"

0 0.04167 1.4699E+03 61.25 3131001 lx bh internals rec 0

0.04167 4.0270E+02 16.78 3131002 lx bh internals rec 0

0.04167 4.9000E+02 20.42

____ 3401001 3x barfpl rec 0

0.09375 1.6012E+02 15.01 3401002 3xbaf-pl rec

' 0 0.09375 1.6012E+02 15.01 3401003 3x batfpl retc 0

0.09375 1.6012E+02 15.01 3411001 lx baf pl rec 0

0.09375 5.3370E+01 5.00 3411002 Ix baf pl rec 0

0.09375 5.3370E+01 5.00 3411003 lx baf pl rec 0

0.09375 5.3370E+01 500 3481001 3xn shield cyl 6.1667 6.3542 1.5000E+00 11.06 3481002 3x n shield cyl 6.1667 6.3542 1.5000E+00 11.06 32'O 1.45 32- 0 0 1

7

Table 1 RELAP5 Model Heat Structure Geometry Cc T

1 7

T t

geometry cyl left dimension, ft 6.1667 8.54

,f~lFff

.I~t rig61t structure number 3481003 3481004 impilation dimension, ft L ___________ I _______

area entry I volume, ft3 LCyI 3481005 3481006 3491001 3491002 3491003 3491004 3491005 3491006 3531001 3551001 3551002 3551003 3551004 3551005 3551005 3551007 3551008 3601001 3601002 3601003 3601004 3601005 3601006 3641001 3641002 3661001 3661002 3661003 3661004 36B1001 descripti 3x*n shield

.3x nshield 3x n shield 3x n shield Ix n shield lx-nWshield lx n shield lxn shield lx n shield Ix up int ern' core barrel

_core barrel core barrel core barrel core barrel core Iarrel core barrel core barrel 3x up interna 3x up interna 3xup internsa 3xup -int e rnsa 3x up interna 3x up lnterFna rv head rv head lx dc shell lx dc shell ix dc shell lx dc shell Tx therm sh' ilx therm sh lx therm sh lx therm sh lx rv shell.

surge line" pzr pzr pzr pzr pzr pzr pzr pzr gel rec rec "rec re*c sph sph_

cyl cyl c

c_

cy cy c¥ 6.354,

,.01.53lf

, 61.75 o~qw 1.06E+03, 3

__.__1

'.4b

.67 32.17 0.04157 7.7200E+02.4.

42.34 161.90 161.90 1361.9 73.61/

J3607 638+0 40 U

0 6.9583 7.891 2.5000E-01 6.9583 7.891, 2.5000E-01

+

7.2083 8.83

,6150E0 cyl -

cyl cyl.

cyl cyl 3.5 3.5ý I

303 6.53 4608 3.07 653 8

,0 4608

,i U(4 6.5318E+00 460OR ib7i 65318E+00 4608R 6.5318E+00 46 OR 3.5 3 8074 6.5318E+00 46.08 3.5 3.8071 16.5318E+00 46.08 RCS Mtal V~i~m194O171-1 8

32-150 145 32-- 0

N 6MI.

.1

,J

.47 y1 7.2083 8.083,8 1.6540E+00 69.57

.*1 7.2083 8.0838 1.6540E+00 69.57 l

6.604 6.837 8.1250E-01 7.99 yl 6.604 6.8373 8.4750E-01 8.34 yl 6.604 6.8373 1.0450E+00 10.28 yl 6.604 6.8373 1.1325E+00 11.14 yl 7.2083 7.9064 1.8690E+00 61.95 yl 0.4662 0.583*

5 9120E+01 22.83 yl 3.5 3.8073 6.5318E+00 46.08 0

3681002 3681003 3681004 3741001 4001001 4101001 4101002 4101003 4101004 4101005 4101006 4101007 4101008 c_

cy 3.8073 6.538E..

46 08 3.8073 cyl 3,.5 380U74 6.5318E+00 460R 3t.5 3.8073 S6.5316E+00 4R NR 3.5 3.8073 6.531BF+NO A* t3*

RCS Metal Vol~me, ft=

4*474

=

I 0

041q7 1O

,fl m

.ov cyl 6.1667 6.3542 1.5000E+00 0 1.06 cyl 6.1667 6.352 1.500EO+00 11.06 cyl 6.1667 6.35 2 5.OOOOE-01 3.69

-cyl 6.1667 6.3 2

5.00OE-01 369 cyl 6.1667 6.3542 5.OOOOE-01 3.69 cyl 6.1667 6.352 5.OOOOE-01 3.69 cyl.......

6.1667 6.3542 5.00O0E-01 3.69 cyl 6.1667 6.3542 5.0000E-01 3.69

alýs -re-c 0

0.041P7 4.9400E+02 20.58 cyl 6.1667 6.3542 3.1220E+00 23.03

_ cyl 6.1667 6.3542 3.8630E+00 28.49 cyl 6.1667 6.3542 3.0620E+00 22.58 cyl _ _

6.1667 6.3542 3.4430E+00 25.39 cyl 6.1667 6.3 2

1.0410E+00 7.68 cyl 6.1667 6.3542 1.2880E+00 9.50 1.0160E+03,

-*1..--! ---

lllJll/

l i i i on surface structure 6.1667 6.3,S, [*

44

61667/

6.3* 2-1.5000E+00 11 *R als I

ls ls 6.l1667 6.3542 1.0210E+D9 7.*

.1*57 6.3542 1.1480*÷RR R A7 0

0.04167 1.4820E+03 61.75 0.04167 1.O65OE+03 443R 0

0.1)41P7 1.480OE+03 R1 R7 U

0.04167 7.7200E+09 32.17 0 04167 0.046 1.0160E+03 8.08 17500OE+00 7.2083 8.0838

Table I RELAP5 Model Heat Structure Geometry Compilation structure number description Core 330100113x clad 330100213x clad 3301003 3301004 3301005 3x clad 3x claJ 3x clad 3301006 3x clad 3301001 3x fuel 3301002 3x fuel 3301003 3x fuel 3301004 3x fuel 3301005 3x fuel 3301006 3x fuel 3311001 1x clad 3311002 lx clad 3311003 1x clad 3311004 1x clad

.4-- 331100511 x clad 33110061 It33110011 3311002 3311003 lx clad lx fuel lx fuel L

3311004 lx fuel left geometry dimension, ft right dimension, 0.0155833 ft surface area entry T

T structure volume, ft3

-+

4 4

-4.

4.

4

.4.

o' c1__

0.0135833 0.0155833 7.6428E+04 14.01 cyl 0.0135833 0.0155833 7.6428E+04 14.01 cyl 0.0135833 0.0155833 7.6428E+04 14.01 cyl 0.0135833 0.0155833 7.6428E+04 14.01 cyl 0.0135833 0.0155833 7.6428E+04 14.01 cyl 0

0.0133125 7.6428E+04 42.55 cyl 0

0.0133125 7.6428E+04 42.55 cy. 71 0

0.0133125 7.6428E+04 42.55 cyl 0

0.0133125 7.6428E+04 42.55 cyl-0 0.0133125 7.65428E+04 42.55 4.67L y0 0.0135833 0.0155833 2.5476E+04 4.67 yl 0.0135833 0.0155833 2.5476E+04 4.67 yl 0.0135833 0.0155833 2.5476E+04 4.67 yl 0.0135833 0.0155833 2.5476E+04 4.67 y4l0 0

0.0133125 2.5476E+04 14.18 yl 0

0.0133125 2.5476E+04 14.18 y-0 0.0133125 2.5476E+04 14.18 i

0

.0 3 12 2..

14.1 "yl

_3311005 lxfuel cyl.

0 0.0133125 2.5476E+04 14.18 3311006 lxfuel

-- cyl 0

0.0133125 2.5476E+04 14.18 clad volume, ft =

112.0 fuel volume, ft =

340.4 cy c_

cy Ic Ic

'c'

c.

cy CyyI U

32-5014532-00 f

I 0.0135833 7.6428E+04 14.01 cyl 0.0135833 0.0155833 7.6428E+04 14.01 cyl 0.0135833 0.01551533 2..5476E+04 4.67 0 0135833 0.0155833 2.5476E+04 4.67 0.0133125 2.5476E+04 14.1R

Table I RELAPS Model Heat Structure Geometry Co rnpilation structure left righ.

surface structure number description geometry dimension, ft dimenslitn, ft area entry volume, ft3 lx SG Sec 6001001 lx feedring cyl 0.40625 0.474 4.4110E+01 4.93 6201001 lx lo shell cyl 5.3908 5.6253 1.1500E+01 93.53 6201002 1x lo shell Cyl 5.3908 5.625 8.1633E+00 66.39 6201003 lx io shell cyl 5.3908 5.625p 8.1633E+00 66.39 6201004 1lx Io shell cyl 5.3908 5.625p 8.1633E+00 66.39 6202001 lxlo shell cyl.

7.0208 7.3301 9.9000E-01 13.84 6301001 lx shroud cyl 5

5.083r 4.0817E+00 10.77 6301002 lx shroud-cyl

.5 5.083 4.0817E+00 10.77 6301003 lx shroud cyl 5

5.083 4.0817E+00 10.77 6301004 lx shro-ud_-.

cyl-5 5.0833 4.0817E+00 10.77 6301005 lx shroud jcyl 5

5.083*

4,0817E+00 10.77 6301006 lx shroud CcyI 5

5.083 4.0817E+00 10.77 6301007 lx shroud cyl 5

5.0831 7.7000E+00 20.32 6301008 lx shroud cyl 5

5.083P 13.3500E+00 8.84 6302001 ix tube supp_ rec 0

0.04167 5.3900E+01 2.25 6302002 lx tube supp rec 0

0.04167 5.3900E+01 2.25 6302003 lx tube supp rec _

0 0.04167 5.3900E+01 2.25 6302004 1x tube supp rec..

0 0.04167 5.3900E+01 2.25 6302005 lx tube supp rec__

60416,7 5.3900E+01 2.25 6302006 lx tube supp rec 0

0.04167 5.3900E+01 2.25 6303001 1lxu sup pWort rec 0

0.2 1.0057E+02 20.11 6361001 lx up shell cyl 7.0208 7.3308 2.1800E+00 30.47

_J6361002 lx up shell cyl..

7.0208 7.3308 7.6800E+00 107.34 6361003 lx up shell cyl 7.0208 7.3308 5.3700E+00 75.06 6361004 Ixup shell.__

cyl 7.0208 7.3308 3.OOOOE+00 41.93 6451001 lx sep cyl 0.48875 0.50875 3.9600E÷01 2.48 6451002 lx Sep_....

cyl 0.48875 0.5087P 8.7200E+01 5.47 6451003 lx sep cyl 0.48875 0 50875 3.0720E+02 19.25 6601001 lx sec sep rec 0

0.08333 3.2034E+02 26.69 6701001 1x st dome sph-_-

12.255 12.565 1.4360E-01 6

L Ix SG Metal Volume, ft=

833.7 82"5014582--0 0

,:O2 ý

</-7,407-10

structure number Table I RELAP5 Model Heat Structure Geometry Connpilation T

description 3x SG Sec 7001001 13x feedring 7201001 7201002 t

+

-t 7201003 7201004 7202001 7301001 7301002 7301003 7301004 7301005 7301006 7301007 7301008

.4 3x lo shell 3x lo shell 3x lo shell 3x lo shell 3x lo shell 3x shroud 3x shroud 3x shroud 3x shroud 3x shroud 3x shroud 3x shroud 3x s-hroud" geometry cyl Cyl cyf cAi cyl cyl cyl cyl cyl cyi cyl left right dimension, ft dimension, ft

~ga 56258 adOF

,l

.60 7.006 7.30~

2.9700E+00 411 surface structure area entry volume, fte 4-I 4

Jz1..

47

.33

~l d7 5.625A 1Ag~o 10

~A490+C1 199.18 2.4490JE+01 199I18 1.2250E+01 I3232 5

6.83

.25E0 32.32 5.0833 12250E+01l 323 5.0833 2 3100El+01 609o6 1.2250E+01 33 1.2250E+01.'

32 1.2250E+/-01l 3232 41.7711E+1 C.

5 r

508 '.u.*,

' I.0U50-TU I 26.52 7302001 3x tubesupp rec 0

0.04167 1.6170E+02 6.74 7302002 3x tube supp rec 0

0.04167 1.6170E+02 6.74 7302003 3x tube supp rec 0

0.04167 1.6170E+02 6.74 7302004 3x tube supp rec 0

0.0416*7 1.6170E+02 6.74 7302005 3x tube supp rec 0

0.0416 1 1.6170E+02 6.74 7302006 3x tube supp rec 0

0.04167 1-6170E+02 6.74 7303001 3x u support rec 0

0.2 1 3.0170E+02 60.34 7361001 3x up shell cyl 7.0208 7.3304 6.5400E÷00 91.41 7361002 3x up shell cyl 7.0208 7.330_

2.3040E+01 322.03 7361003 3x up shelF cyl 7.0208 7.330_

1.,6110E+01 225.17 7361004 3xup shell cyl 7.0208 7.3304 9.OOOOE+00 125.79 7451001 3x sep-

-- cyl 0.48875 0.5087P 1.1880E+02 7.45 7451002 3x sep cyl 0.48875 0.50875 2.6160E+02 16.40 7451003 3x sep cyl 0.48875 0.50875 9.2160E+02 57.76 7601001 3x sec sep rec 0

0.08333 9.6102E+02 80.08 7701001 3x st dome sph 12.255 12.565 4.3000E-01 257.99 3x SG Metal Volume, ft, 2500.7 82-150 145 32 - 0 0 11 5.0833 1.2250E+01 6

5.0833 R9 *9 5

5.0833 R*I OR qLVl R #'lJ* J* R C*JLtl 4 I

I

,5

0. 40 C2, 0.4479

1.3233E+0*

ld 7Q 5.3908 5.6258 3_dSONF+*I 9Rn R*

5.3908 5.625B 2.4490E+01 19g.1R 6.3908 5.6258 2.4490E+01 I*RIR

,5.3908 5.6258 2_44goF+01 1QBIR 7.0208 7.330P 2.9700E+00 4151-5 5.0835 1.2250E+0*

R9 R9 5

623 1.2250E+01 32.32

3 O.UU3*

1.?.250E÷01 32_3?

5.083 1.2250E+01 3? R*

6

SQN CONDENSATE VOLUME REQUE 2.2 Steam Line Pipin2 There are no steam line piping heat structures in the RELAP5 m6del Howevr with hydraulic control volumes and give good information regarding line lengi includes control volume data (flow area and CV length) from the RELAP5 shc 2/7/02.

Table 2 also includes information taken from Section 3.12 of Reference 1, the development documentation. Piping outside diameter (OD) and the number ol control volume from this section are included in Table 2. The steam line pipe control volume is calculated as:

Vrioig =cn D----Acv JL

where, VD Do =

L =

structure volume number of parallel piping runs in CV outside piping diameter CV length Structure volumes are summed for the steam lines in Table 2.

IEMENT VERIFICATION 32-5014532-00 r, the steam line is modeled hs, flow area, etc. Table 2 rtrun sqss/XWEL, dated

team line model parallel piping runs in each

tructural volume for a given 12

Table 2 Steam Line Piping Structural Volume Comp I

node designation Iflowfa length od, anch number pipe 2e Iegt ad Znh~

arael Volume, ft3 675010000 st I-ne 1 4.8512 14.2321 32 1

10.44 675020000 st line 2 4.8512 8

32 1

5.87 675030000 st line 3 4.8512 44137 32 1

32.39 675040000 st line 4 4.8512 35555 32 1

26.09 676010000 st line 5 4.8512 25.189 32 1

18.49 677010000 st line 6 4.8512 44.401 32 1

32.58 680010000 st line 7 4.8512 19.031 32 1

13.97 680020000 st line 8 6.1509 46.343 36 1

42.53 680030000 st line 9

-6.1509 46.343 36 1

42.53 680040000 st line 10 6.1509 46.343 36 1

42.53 680050000 st line 11 6.1509 46.343 36 1

42.53 680060000 st 1ine 12 6.1509 46.343 36 1

42.53 680070000 st line 13 6.1509 46,343 36 1

42.53 680080000 st line 14 6.1509 46.343 36 1

42.53 680090000 st line 15 6.1509 46.343 36 1

42.53 680100000 st line 16 6.1509 46.343 36 1

42.53 680110000 Tst line 17 61509 46.343 36 1

42.53 681010000

!st line 18 6.1509 39.779 36 1

36.50 683010000 st line 19 24.6036 16.569 36 4

60.82 683020000 st line 20 24.6036 14.647 36 4

53.77 683030000 st line 21

-24.6036 15.569 36 4

57.15 683040000 st flne 22, 14.884-13 28 4

28.86 692010000 st line 23 6.1509 53.894 36 1

49.46 692020000 st line 24 6.1509 69.66 36 1

63.93 692030000 st line 25 6.1509 69.66 36 1

63.93 775010000 st line26__

14.5536 14.2321 32 3

31.33 775020000 st line 27 14.5535 8

32 3

17.61 775030000 st line 28 14.5536 44.137 32 3

97.17 775040000 st Fline 29 14.5536 3-1.758 32 3

69.92 776010000 st line 30.

14.5536 15.073 32 3

33.18 777010000 st line 3 14.5536 4.401 32 3

97.75 780010000 stline32.

14.-5536 25.296 32 3

55.69 780020000 st line 33 18.4527 55.005 36 3

151.43 780030000 st.line 34 =

18.4527 46.343 36 3

127.58 780040000 st line 35 18.4527 46.343 36 3

127.58 780050000 st line-36 18.4-527 46.343 36 3

127.58 780060000 st line 37 18.4527 46.343 36 3

127.58 780070000 st line 38 18".4527 46.343 36 3

127.58 780080000 st-line-39 18.4527 46.343 36 3 3 12758 steam line metal volum=,"ft 2299.12 ilation

-A 3 -50 14532-00 13

SQN CONDENSATE VOLUME REQUI 2.3 Main Feedwater Line Pininf Only the volume of main feedwater piping from the entry-point of the auxiliar considered in calculations leading to the condensate storage tank water volum.

shows the estimation process. Fluid volumes are taken from Reference 2, Fig]

generator, attached as Appendix A for ease of reference. Reference 3 indicate 16-inch pipe. Reference 4, Section 3.7.2.1 indicates that the pipe is Schedule D, = 14.312 inches Ar(= flow area = 1.1172 ft2 A. = pipe x-section area - 0.27907 ft Using these parameters and the volume information from Reference 2, Table 3 main feedwater piping length and piping volume from the auxiliary feedwater L=Y~

Vx =A p

rul where V. = pipe structure volume REMENT VERIFICATION 32-5014532-00 y feedwater line is requirement. Table 3 ire I for each steam

that the feedwater piping is

0. For Schedule 80 pipe:

shows the calculation of

.ntry to the steam generator.

The total structure volume of the main feedwater piping from the auxiliary feedwater entry is shown in Table 3.

c Z?7 14

Table 3 Main Feedwater Piping Structural Compi ation 32-5014532-00 15 Fluid Volumes, Wft MFW piping from AFW entry sg 1 93.55 sg 2 31.56 sg 3 33.67 sg4 am.6 Total:

257.39 Lengths, ft sg 1 83.74 sg 2 28.25 sg 3 30.14 sg 4 88.27 Pipe Volumes, ftl sg 1 23.37 sg2 7.88 sg(3 8.41 sg 4 24.6 Total.

64.30

SQN CONDENSATE VOLUME REQUI:

2.4 Material Properties Material properties, specifically volumetric heat capacities for the materials cc heat structures are compiled in Table 4. The heat capacities are taken from tht sqss/XWEL, dated 2t7/02 and are shown as a function of material temperatur 533 steel, SA 508 steel, fuel - Uranium dioxide, clad - Zircaloy IV, and Incone Volumetric heat capacity is plotted for steel below from the data of Table 4. 1 process, all steel structures are combined, lumping stainless steel cladding and conservative application of the material properties is proposed by picking the i capacity for initial, full power conditions.

Volume Heat Capacity

75.

70.

IL ~65 55 50.

0 100 200 300 400 500 600 Temperature, F 700 ZEMENT VERIFICATION 32-5014532-00 nprising the RELAP5 model RELAP5 short run for stainless steel (ss), SA 690 (inc).

simplify the heat balance

tructural steel. A aximum volumetric heat 4.

0oo 900 Minimum heat capacities are conservatively applied to the beat structures for calculation of the mode 2 energy content. This maximizes the AU calculation for heat structures between initial conditions and mode 2 conditions. The only exception is associated with the pressurizer and surge line structural components.

In mode 2, it is assumed that the pressurizer remains at saturated conditions wit a pressure equivalent to the initial conditions (2250 psia) Structural heat capacities in the pressurizer and surge line at mode 2 are maintained at the maximum of the stainless and structural steel heat capacity to Lnaintain equivalent structural energy both initially and in mode 2.

Minimum heat capacities are conservatively applied to the heat structures for cal energy content. This maximizes the AU calculation for heat structures between 3 conditions.

1/7-/0 2-culation of the mode 2 initial conditions and mode 16 sa 508

__I.

I

Table 4 RELAP5 Model Structure Material Volumetric Heat Capacity ss Temp, F C, BTU/ft3F sa 533 Tenp, F C, BTU/fttF 70

_. 56.95 100 52.93 100 57.24 200 55.71 200 59.62 3

58.33 300 61.25 400 61.18 400 63.03 0"0 64.21 500

__64.12 600 67.25 600 -

64.94 700 59.91 700_._

65.92 80Q0 73.56 sa 508 Temp, F C, BTUIfteF inc TernS, F C, BTUIft3F 100" 53.02 2(0 57.3 200 56.21 4(90 60.9 Z30_0 58-87 60_0 64.4 400 61.3 800 68 500 63.81 1000 71.6 600 66.08 1200 75.7 700 68.67 1400 79.3 6d0--

7T1.67 1600 82.9

.180 86.4 clad Temp. F C, BTU/fteF fuel Temp, F C, BTUIft'F 32 28.346 771 33.8 1062-33.23"2 200 40.62 1140 35.432 400 43.87 1480 35.432 600 45.82 1510 49.44 80 1

47.12 1530 56.444 100,0 48.1 1560 58.916 120-0 48.88 1590 61.8 16090 49.92 1610

.332 200ý0 50.37 1620 76.22 240p 51.35 1650 80.34 280p 53.62 1680 78.28 320P 58.17 1700._-.;

74.16 360P 66.3 1780' 35432 4000 78.97 3000 35-432 440 90.8 4800 99.12 5100 101.4

<YY2 6/7/0 Z-82-50 145 32-00 17

SQN CONDENSATE VOLUME REQUI 2.5 Structure Initial Internal Energy Content Table 5 shows the calculation of the initial internal energy for each, of many, r summarizes the total energy associated with the plant metal mass at full power The identification number in Table5 refers to either (1) the structure number if the short RELAP5 run sqss/XWEL, dated 2/7102, or (2) the adjacent fluid con portion of the main feedwater piping considered in this calculation has no relat RELAP5 model The material of the relevant structure is indicated in Table 5. Initial "average" structure is taken from the RELAPS run sqss/XWEL, dated 217/02 major edit case of the steam piping, the control volume temperature is used - feedwater tei initialize the main feedwater piping). Given the material and the structure temr capacity is determined, by interpolation, from Table 4. Note that, as mentioned steel the initial volumetric heat capacity is the maximum value of all the steels.

LENIENT VERIFICATION 32-5014532-00 todel heat structures and operation.

the structure is simulated in trol volume number. The d component in the emperatures of each heat it time = 0 seconds (in the nperature is used to erature volumetric heat above, if the material is The initial internal energy is then estimated for each heat structure in the following manner:

U, z ciVTi

where, q =

volumetric heat capacity, BTU/ft-F, based on structure material and t(

V =

structure volume in ftP, taken from Table I for model heat structures, I piping, and Table 3 for main feedwater piping.

T1 =

structure temperature, F.

A summary of the structure internal energies is included at the bottom of Table structure volume and internal energy for the RCS metal, clad and fuel, steam ge steam line piping, and main feedwater piping. The sum of all the internal energ considered:

Ab?

mperature, Table 4 able 2 for steam line

. The summary indicates ierator secondary metal, es of all the plant structures 18 ZUi -9.3030ESBTU

)

Table 5 Initial Metal Internal Energy

<Vl-----Vo.u.etic Heat Capacity, BTUIR3,-----

Identification cVol Heat Internal Number Description Material Initial T=,

c,,

Cgs cI3 Ccc CAW Cr VolCHat Energy, Ui,

.cp BTU Primary metal I

I I

I CA CO a

0*

S......

o o o6o5o

.8 4 3

6 5.8 4 3 0.8 2 6 3.5 9 6 3.9.38 9 5 1251008 3x rsg tubes inc 552.6 64.55 65.81 65.00 65.81 3082 63.57 4536 63.57 807156 1251009 3x rsg tubes,

Inc 551.63 64.54 65.78 64.98 65.78 30.81 63.55 45.35 63.55 1251010 3xrsgtubes inc 1

55068

.54 65.75 64.96 65.75 30.81 63.54 45.34 63.54 803926 1251011 3x rsgtubes Inc 5149.07 64.52 65.70 64.92 I

65.70 30.80 63.51 45.32 63.51 1409960 1251012 3xrsg tubes Inc 547.62 64.51 65.65 64.89 65.66 30.79 63.48 45.31 63.48 1405675 1251013 3x rsg tubes Inc 546.29 64.50 65.62 64,86 65.62 30.79 63.46 45,30 63.46 1401746 1251014 3x rsg tubes inc 545.29 64.49 65.59 64.84 65.59 30.78 6344 45.29 63.44 1398795 1251015 3x rsg tubes Inc 544.3 64.48 65.56 64.82 65.56 30.78 63.43 45.28 63.43 1395874 1251016 3x rsg tubes inc 543.12 64.47 65.52 64.79 65.52 T 30.77 63.40 45.27 63.40 1392394 1291001 3x rsg out ts steel 551.23 64.54 65.77 64.97 65.77 30.81 63.55 45.34 65.77 8628900 1301001 3x rsg out steel 551.24 64.54 65.77 64,97 65.77 30.81 6355 45.34 65.77 5803556 1351001 3x cold leg ps steel 551.21 64.54 65.77 64.97 65.77 30.81 63.55 45.34 65.77 1011789 1351002 3x cold leg ps steel 551.21 64.54 65.77 64.97 65.77 30.81 63.55 45.34 65.77 939385 1351003 3x cold leg ps steel 551.22 64.54 65.77 64.97 65.77 30.81 63.55 45.34 65.77 1466578 1351004 3x cold leg ps steel 551.22 64,54 65.77 64.97 65.77 30.81 63.55 45.34 65.77 730281 1351005 3x cold leg ps steel 551.21 64.54 65.77 64.97 65.77 30.81 63.55 45.34 65.77 1466545 1601001 3x pump metal steel 551.54 64.54 65.78 64.98 65.78 30.81 63.55 45.35 65.78 383262060 1651001 3x cold leg steel 55165 64.54 65.78 64.98 65.78 30.81 63.55 45.35 65.78 642498 1651002 3x cold leg steel 551.67 64.54 65.78 64.98 65.78 30.81 63.55 45.35 65.78 2506614 1701001 3x cold leg noz steel 551.67 64.54 65.78 64.98 65.78 30.81 63.55 45.35 65.78 1422208 19 i

1001001 3x hot leg noz steel 615.48 65 09 67.66 66.48 67.66 31.11 45.92 67.66 925378 1051001

" 3xhotleg steel 615.47 65.09

- 67.66 66.48 67.66 31.11 64.68 45.92 67.66 1069135 1051002 3x hot leg steel 615.47 65 09" 67.66 66.48 67.66 31.11 64.68 45.92 67.66 1643047 1051003 3xhotleg steel 615.47 65.09 67.66 66.48 67.66 31.11

' 64.68 45.92 67.66 1336471 1201001 3xrsg in steel 615.51 65,09 67.66 66.48

_67.66 31.11 64.68 45.92 67.66 6666907 1o220 3x rsg div plate steel 583.53 64,80 66.75 65.71 66.75 30.9-64.11 4566 66.75 838096 "12*1"001 3xrsgints steel 615.48 65.09 67.66 66.48 67.66 31.11 54.68 45.92 67.66 9912182 1251001 3x rsg tubes inc 56634 6465 66"23 65.32 66.23 30.88 63.81 45,49 6381 1461228 125100 3xrsgtubes inc 563.45 64.64 66.14 65.25 56.14

-0.87 6 3,76 ÷45.46 63.76 1452'20 1 2 51003 3xrsgtubes inc 560.89 64.62 66.06 65,19 66.06 30.85 63.72 4544 63.72 1445004 1251004 3x rsg tubes Inc 558.48 64.6' 65-99 65.14 65.99 30.84 53.67 45,42 63.67 1437842 1251005 3x rsg tubes...

.n 556.6 64.58 65.93 65.09 65.93 30.83 63.64 45-40 63.64 1432262 1251005 3x rsg tubes Inc 554.73 64-57 65.87 65.05 65.87 30.83 63.61 64538 03.61

" 1426716 t

12510 7

Iv r*

I-*

1

ý

IA Table 5 Initial Metal Internal Energy I

I I-SDoscrpton I

I Vol Heat, ntergy al NumberiDoscrloo Materral Initial T.,..

c, CZES 33 c

0 6

it. cCtl czire c,,,

C.

Vo Cap Energy, Ul, 2010 xhte tel 654 I

BTU 20D001 xhotleg

_steel 1 615.44 65.09 67.66 J6648

67.66 31.11 64.68 45.92 67.66 308434 2051001 ix hotleg steel 615.44 65.09 57.66 66.48 67.66 31.11

'-64.68 445.92 67.66 356357 205100m3 xhot steel 615.44 65.09 67.66 66.48 T767.66 31.11 64,68 45.92 67.66 445453 2201001 lx rsg in steel 615.47 65.09 67.66 6648 67.66-31.11 64.68 45.92 67.66 2222123 2202001 lx rsg div plate

- steel 583.7 64.81 66.75

" 65.71 66.75 3096 64.11 45 66 66.75 279473 2211001 1xrsgInts steel 615.45 65.09 67.66 66.48 67.66 31.11 64.68 45.92 67.66 3303732 2251001 lx rsg tubes Inc 566.53 64.67-- 66.23 65.32

66.23" 30.88 63.81 45.49 63.81 487265 2251002 lx rsg tubes inc 563.67 64.64 66.15 65.26 66.15 30.87 63.76 45.47 63.76 484425 2251003 lx rsg tubes

-Inc 561.14 6"4.62 "

66.07 65.20 66.07 30.86 63.72 "45.'44 63.72.

481916 2251004 ix rsg tubes inc 558 74 64.60 66.00 65.14 66.00 3084 63.68 4542 6368 479538 2251005 lx rsg tubes Inc 556.88 64,59 65.94.

6"5.10 65.94 "30.84 63.65-..

45.4_0-63.6"5 47y69 "2251"006

'l x'rsg itubes inc.

5-55.032' 64.57 65.88 8 65.06 65.88 30.83 63.61 45;36 -

'63.6"1 475-859 2251007 lx rsg tubes

.Inc 553.97 64.56 65.85 6504 65.85 30.82 63.59 45.37 63.59 269821 2251008 lx rsg tubes inc 552.9 64.55 65.82 65.01 65.82 30.82 63.58 45.36 63 58 269220 2251009 lx rsg tubes inc 551.92 64.55 65.79 64.99 65.79 30.81 63.56 45.35 63.56 268671 2251010 lxrsgtubes inc 550.98 64.54 65.76 64 97 65.76 30.81 63.54 45.35 63.56 268614 2251011 1 x r n t*,hi in,-

,A0

ý 1.7Z

3.

5 S.

v-t.U.

0 i

.80 63.51 45.33 63.51 470272 2251012_ "

ix rsgtubes inc 547.91 64.51 65.67 64.90 65.67 30.79 63,49 45.31 63.49 t

468844 2251013 lx rsg tubes inc I

546.57 64.50 65.63 64.87 65 63 30.79 63.46 45.30 63.45 I 467524 2261014 F 1Xrsgtubes I nc 545.56 64.49 65.60 64.84 65.60

,30.7 63.45 45.29 63.45 486531 2251015 lxrsgtubes Inc 544.56 64.49 65.56 64.82 65.560 30.78 63.43 45.28 63.43 465547 2251016 lx rsg tubes inc 543.38 64.48 65.53 64.79 65.53 30.77 63.41 45.27 63.41 464387 2291001 lx rsg out ts steel 551.61 64.54 65.78 64.98 65.78 30.81 63.55 45.35 65.78 2878676 2301001 lx rsg out steel 551.62 64.54 65,78 64.98 65.78 30.81 63.55 45.35 65.78 1936192 2351001 lx cold leg ps steel 551.59 64.54 65.78 64.98 65.78 30.81 63.55 45.35 65.78 337555 2351002 lx cold leg ps steel 551.59 64.54 65.78 64.98 65.78 30.81 63.55 45.35 65.78 313399 2351003 lx cold leg ps steel 551.6 64.54 65.78 64.98 65.78 30.81 63.55 45.35 65.78 489282 2351004 lx cold leg ps steel 551.6 64.54 65.78 64.98 65.78 30.81 63.55 45.35 65.78 243638 2351005 lx cold leg ps steel 551.59 64.54 65.78 64.98 65.78 30.81 63.55 45.35 65.78 489271 2601001 lx pump metal steel 551.91 64.55 65.79 64.99 65.79 30.81 63.56 45.35 65.79 127868257 2651001 lx cold leg steel 552.02 64.55 65.79 64.99 65.79 30.81 63.56 45.35 65.79 214346 2651002 lx cold leg steel 552.04 64.55 65.79 64 99 65.79 30.81 63.56 45.35 65.79 836241 2701001 lx cold leg noz steel 552.04 64.55 65.79 64.99 65.79 30.81 6356 45.35 65.79 474468 3001001 3x dc shell steel 551.74 64.54 65.78 64.98 65.78 30.81 63.56 45.35 65.78 8014564 3001002 3x dc shell steel 1

551 67 1 64.54.

65.78 64.98 65.78 30.81 63.55 45.35 85.78 4484389 20 V

Co 0

I-.n CO I

-folumet-wftý4 Pý,

IN, OT

Ta1e 6 Initial Metal Internal Energy S...---

.-Volumetric Heat CapacityBTU/ft3

. S{

V o H e at In rem a l Identification Vo -et I era Number Description Material Initial T Ci,,

c,,s.

cusos ct,6,,

czlr cinc Vo l Energy, Ui, Number Cap 3001003 3x dc shell steel 551.69

'64.54 65.78 64.98 65.78 3081 6355 45.35 65.78 7575573 64.54 65.78 64.98 65.78 30.81 63 55

_ 45.35 65.78 5757645 3021001 3x therd sh e

steel 551.67 "

64.54 65,78 64.98 65.78 30.81" 63.55 45.35 65.78 870283 xt-r ih.

4.98-.

4

-3021i002 3xtherm sh steel 551.69 64.54 65.78 64.98 65.78 30.81 63.55 45.35 65,78 T 907813 3021003' 3xthermrsh steel 551.7 64.54 65.78 64.98 65.78 30.81 63.55 45.35 65.78 111939-4 3021004 3xthermsh steel 551.71 64.54 65.78 64.98 65.78 30.81 63.55 45.35 65.78 1213150 3081001 3r shell steel 551.71 64.54 65.78 64.98 '65.78 30.8+

-01

63.

46 3.5 5-.35 65.78 6745-320 310T001

-'rvbottom steel 585.82 6

b4,.821 6.82 65.76 66.82 30.97 64.15 45.68 66.82 3831440 3-1"21001

-"3xbhintemals" -st'ejl 785.82 64.82 66.82

65.76 66.82

÷ 30.97 6U4.15 45.68 66.82 1581212" "3"1-0-0'" 3xbh'intermals steel 551.71 64.54 65.78 64.98 65.78 3081 63.,5 45.35 65.78 1827024 3121003" 3xbhinternrals steel 551.7 64.54 65.78 64.98 65.78 "3081 63 55 45.35 65.78 2222895

" 313 i0-01 ix'6W' eirin.s.. sieel 5-- 2.2:0"9

'64-.5 5 S.'7 b "6F..g

"-9 65.79" 30*.8-"'

635 "45.-35 65.79 6095-34 3131002 Ix'ihnte-rin-a--" steel-55-2.08-'-

64.5"5

"'65.79 641.99 65.79 30.81 63.56 4535 65.79

'741"657 3400"0:1 3-ba-rp steel 5

7 h47 6"5.78 64.98 65.78 30.81 63.55 45.3-5"-

65.78 544772

-S47O~~~o-oý-

-3x-ba------------

-S-1--- -

6-516---------------------

S-----15.155 7-.-5'

4 65.7f--TV 3401002 3x baf pl steel 551.65 64.54 65.78 64.98 65.78 30.81 63.55 45.35-657C'. "

544723 3401003

_ 3xbafpl steel 551.62 64.54 65.78 64.98 65.78 30.81 63.55 45.35

-"-765_60 7 81368 3411002 1

x bafspl stiee-l" 552.07 64.55 65.79 65.79 30.81 63.56 45.35 65.79 181736 3411002 Ix bat P s

552 64.55 65.79 64.99 65.79 30.81 63.56 45.35 65.79 i

181724 3411003 "

lxbafpl i steel 5555 6579 64.99 65.79 30.81 63.56 45.35 6579 181707 3481001 13x n shield steel 551.7 j

64.54 65.78 64.96 65.78 30.81 63.55 45,35 65.78 401500 3481002 3x n shield steel 551.7 6R454 I R 7 r on

=

.Aq.

7.

4 3481003 3x..

. n sib 65.78 401500 3481003 3xnshield steel 551.68 64.54 65.78 64.98 65.78 30.81 63.55 45.35 65.78 401482 3481004 3x n shield steel 551.67 64.54 65.78 64.98 65.78 30.81 63.55 45.35 65.78 401473 3481005 3xn shield I

steel 551.66 64.54 65.78 64.98 65.78 30.81 1 63.55 45.35 65.78 401464 3481006 3x n shield steel 551.66 64.54 65.78 64.98 65.78 30.81 1 63.55 45.35 65.78 401464 3491001 6 x n shield steel 551.66 64.54 65.78 64.98 65.78 30.81 63.55" 45.35 65.78 401464 3491001 lx n shield steel 552.08 64.55 65.79 64.99 65.79 30.81 63.56 45.35 65.79 133949 3491002 lx n shield steel 552.08 64.55 65.79 64.99 65.79 30.81 63.56 45.35 65.79 133949 3491003 Ix n shield steel 55206 64.55 65.79 64.99 6,9 3.1 6.6 4.5 6.9 134 3491004 lx n shield steel 552.05 64.55 65.79 64.99 65.79 30.81 63.56 45.35 65.79 133940 3491005 Ix n shield steel 552.04 64.55 65.79 64.99 65.79 30.81 63.56 45.35 65.79 133937 3491006 lx n shield steel 552.04 64.55 65.79 64.99 65.79 30.81 63.56 45.35 65.79 133937 3531001 1x up internals steel 615.5 65 09 67.66 66.48 67.66 31.11 64.68 45.92 67.66 857285 3551001 core barrel steel 551.7 64.54 65.78 64.98 65.78 30.81 63.55 45.35 65.78 835656 3551002 core barrel steel 583.09 64.80 66.74 65.70 66.74 30.96 64.10 45.66 66.74 1108681 3551003 core barrel steel 581.'63 64.79 66.69 65,66 66.69 30.95 64.08 45.64 66.69 876011 3551004 core barrel steel 551.75 64.54 65.78 64.98 65.78 3081 1 63.561 45.35 65.78 9268 21 co CAT C,'

Co 0:

0*

, t,}.

p e I

"Taole 5 Initial Metal Internal Energy Volumetric Heat Capacity, BTUIft Identification Description Material Initial Ta.

C csVol Heat Enternal Number Intac..

C c1,333 c,,"S

COW, cft C-Cu.2 Energy, Ul, I

Cap BTU 3551005 core barrel steel 552.09 64.55 _

65.79 64.99 65.79 30.81 63,56 45 35 65.79 27888 h3551006 core ba steel 583.13 64.80 66.74 65.70 66.74 30.96 64.10 4566 66.74 369688 "35510)'7" -

core barrel steel F,

581.85 64.79 66.70

- 65.67 66.70 364 292239 3551008-.

F 4-30-95l6aTBre.64 6t.70 2÷2,

-. 3551008 "'x core barerl s

te.

581.85 64J.9 66.70 6567 66.70 30.95 64.08 45.64 66.70 *328590 3601001 U up internals steel 61557

65. 6

7.

6 6 8

67.66

_ 31.1 1 64.68 4.9.

6.

. 2 7 3C01002 3xup

'inte"mals steel 615.56 65.09 6766 6648 67.66 31.11 6468

45. 92 67.66 1848419 3601003 3x up internals steel 551.77 64.54 65.78 64.99 T6578 30.81 63.56

- "45.35

-65.78 2'-23-852-7 3601004 3x up intemafs steel 551.77 64.54 65,78 64".99

65.

8

-63.56 45-5

.65.78 116764 F-608; 0,8 55.7 63.56 655.65781 67 6 36010"05 3x up internals steel 551.76 64.54 65.78 64.98 65.78 30.81 63.56 45.35 65.78 2754233 3

60"0" h3xup internals "steel 585.86 64.82 66.82 55.76 66.82 30.97

" 64.15 45.68 66.82 j157366 3641001 rv head stee 551.76 64.54 65.78 64.98 65.78"-

3081 63.56 45-.35-65.78-5876271 3641002 rv head steel 585.86 64.82 6"

65.78 66.82 30.97 64.15 45.66 66.82 6337761 366101 1x dc shell steel 552.19 64.55 65.80 6499 65"80" 30.81 6"3.6 45.35" 65.80 2674256 366002 l...

Sell steel 552.06"÷ 64.5Y5 65.79 64.99

.65-.79 "-30ý.O81 63.56 45.35 65.79 1495613 3661003 lx dcshell

-'steel-.

552.07 64.55 5

65.79" 30.81 45.35 65.79 2526865 3661004 lxdc shell steel 552.08 64.55 65.79 64.99

,65.79 30.81 63.56 45.35 65.79 2526922 3681001 Tx theýrm sh stee

-s 55.t

-e.

"1 52.06 64.55 65.79 64.99 65.79

30 81 63.56 45.35 65.79 290352 36381002 lx therm sh steel 552.07 64.55 65.79 64.99 65.79

-3081 6.6 4.5 6.9 326 9.3 81 63.56 53 65.79 302866 3681003 lx therm sh steel 552.08 6

64.55 68.58 67.35 65.79 30.81 6--5-.

45.5 6858.0 3681064 1 lx- '

sh.

stee 35.9 49 57 08 35 53 5

79345473 3741001 hen s-h-*

steel 552.09 64.55 765.79 64.99 65.79

30.81 356 4.5 579 G73 55.0 645 57 4991

-57 08 63.56 45.35 65.79 2250450 4001001 surge line steel 616.41 65.10 676 166.51 67.69-3112 6

4.70676 924 4101001 pzr steel 650.04 65.43 68.58.8 1 2 6.0 61 67.6 58 20 34 7

4101003 pzr steel 650.06 65.43 68.58 67.38 68.5--8-- 31.28 65.30 46.15 68.58 2054495 pzr steel 650.11 65.43 68.58 67.38 68.58 31.28 65.30 46.15 68.58 2054495

1.

44110100010 pzrP~

steel~te 650.32'11 65.43 68.59 67,38 68.59 31.28 653 46.15 658 20544532 C

4101007 pzr L

steel 65032 5.3 6.9 6 38 6 591 2853-'

46.3 68.59 20 5 2 S41107 zr tel 49.9 5.3 8.57 I67.37 58.57 31.28 65.30 46.14 685 2522 4101008 pzr steel 624.95 65.18 67.91 66.73 67.91 31.16 64.85 45.98 67.01 1955711 RCS Metal Heat =

7 CD 0O 0

22

Table 5 Initial Metal Internal Energy Identification Description Material Initial T,,.

Ime Core 3301001 3x clad zrc 570.35 64.70 66.35 65.41.

66.35 30.90+

63.88 45.53" 30.90 246840 3301002 '--

3x"clad zirc

'607*."-1 65.01 "67.44 66.26 67.44 31.07 64.53 4587.

31.07 264232.

3301"0"03

" 3x clad zirc 637.32 65.31

"" 68.24 "-67.05

' 682-4 31.'22 65 6'0*07 46.06 31.22 278559 3301004 3x clad zfrc 652.96

+ 65'46 68.66..

67.45

-68.66 31.29 65,35 46.16 31.29 286176 3-301005 3xclad zrc 650.7 6544 68.60 67.39"-

6860 31".28 65.3 46.15"g 31.28 285121 33010-6 3x clad zPrc 632.59 65.26 68.12 66.92 68.12 31.20 64.99 4603 31.20 276392 3301"001 3xfuel uo2 868.19 67.57 76.05 73.72 76.05 32.31 6923 47.45 47.45 1753115 3301006 3x'fuel uo2 1475.44 73.52 98.2'1 91.93 98.21 35.43

_ 80.66 4960 49.60 3113803 3301-003 3x-fuel uo2 1867.33 77.36 112.52 103.69 112.52"-

353.

.87.58 50.22 50.22' 3990480 3301004 3xfuel R2 1T8-82.28 77.51 113.06 4

104.1-4 10

" 35.43 "884 j

50.24 5024 4023782

""3"3-.005

'3x fu3el "I

uo2 1517.49 73.9"3i 99.U5 93.19 99-5 52.06 81.41 49.71 49.71 3209606 330b!00b6 3x'fuel uo 92"7.9" 68.15 78.23 75.51 78.23 32.60 70.30 47.75 47.75 1885327 "3-31001.

1xclad zrc - -

.7 747 64.70-66.35 35-30.90 6"3.88 45.3 30.90" 8229 3311002 lx clad zirc 607.07 6501 67.44 66.26 67.44 31.07 64.53 45.87 31.07 86071 3311003 1 xclad zirc 637.05...

65.30 68.24 67.04 68.24 31.22 65.07 46.06 31.22 "

92843 3311004 lx clad

zirc, 652.58 65.46 68.65 67.44 68.65 31.29' 65.35 46.16 31.29 95331 3311005 lx clad zirc 650.44 65.43 6

9--

8 67.39 68.59 31.28 65.31 46.15

31. 2 8 94988 3311006 lx clad zirc 632.29 I 65.26 68.11 66.92 68.11 31.19 64.98 46.03 31.19 92083 I.

3311001 1x fuel uo2 867.67 67.56 76.03 73.70 176.03 32.31 69.22 ! 47.45 47.45 583990 3311002 lxfuel uo2 1476.12 73.53 98.24 91.95 98.24 35.43 80.67 49.60 49.60 1038450 3311003 lx fuel uo2 1867.07 77.36 112.51 103,68 112,51 35.43

[

87.57 50.22 50.22 1329969 3311004 lx fuel uo2 1881.92 77.50 113.05 104.13 113.05 35.43 87.83 50.24 50.24 1340993 3311005 lx fuel uo2 1517.88 73.94 99.76 93.21 99.76 52.20 81.42 49.71 49.71 1070165 3311006 lx fuel uo2 927.03 68.14 78.20 75.48 78.20 32.59 70.29 1 47.74 47.74 627767 C lad H e at =

2.1 830E +0 6]

_...._Fuel Heat =

2.3967E+n07 23 V

PJ w

CoR

I Table 5 Initial Metal Internal Energy

<------.... ""Volumetric Heat Capacity, BTUft3 Identification ItI I

MaterealInternal N umertfc t o D escription M aterial Initial T,,,,

¢.

c... s3 c=

c~t et

c. ccr-C CU0 E ner y U,

Number nrllTg

~

,Cf; C~

o

etEoy,

'if, SI ap BTU Single SG Secondary "6001001 lx feedrlng steel 516.21

-64.25 64.70 64.18 64.70 -

3064 62.93 45.00 4 64.70 164659 6201001 - ---

flx lo shell steel 516.27 6425 64.70 64.18 64.70 30.64 62.93 45.00 64,70 3124462 6201002 0xloshell steel 516.32 64.25 64.71 64.18 66471 30.64 62."4 500 64.71 2218184 1 6201003 "lxlo sheli

-steel

-5i6 38 64.25 64.71 64.18 6471

3-a.64 r62.94 45.00 64.71 2218504 6201004 Ix tloshell steml 5167,42 6425 64.71 64.18 64.71

' 3064 62.94 45.01F' 641

. 2218718 6202001 lx lo shell steel 516.21 64.25 64.70 64.18 64 70 '

30.64 62 93 45.00 64.70 4621"64 6301001 lx shroud steel 523.06 64.31 64:91 64.33 64.91 30 68 63.05 45.07 64'.91 365684 6301002 i._lx shroud steel 54-9 64J32 "64.97 64.38 64.97 30.68 "6309" 4-5"'09 6*97

" 37286 631

3.

I s5h.27

64.

3 648 643 694.9" 3--- 69 63.09

-.45d9" 64.98 367609 "6"30100 1-xshrod "steel 525.3-64.3 "64.98 64.39-*

64798 "30.69 63.09 45.09 64.98 367687 6301005 lx shroud

.steel 52544 64.33 64.98 64.39 6498 30.69 63,10 45.09 64.98 367757 S-"63"01006

-xshroiJ -

steel 525..

"" ",3" 64.99'"

"64.39" 64.99 30 69 63.10 45.09 64.99 3

9 6301007 lx shroud steel 64.f3...

"60 6-5.00 30.69 63.10 45.,1 65.00 694540 6 0xshroud steel 526.41 64.34 65.01 64.41 65.01 30.69 63.1 510 650 6302002 lx ueshru_____

ste'Tel 53 52.38..

64,341 65.29 64.61 65.29

'3"06 73 6"3.27

'-'45.'19) 65 2952 6302003 lx tube supp steel 531.53 64.4 65.30 64.63 65.1 30.74 63.20

.45.1 65.17 77800 6 38 17o 553 3D.72

5 6302005 lx tube supp steel 535.53-64.41 65.29 64.62 6529 63.27

4.

6 78531 6302006 1x tube sup' steel 535.7 64.41 65.30 64.62 65.30 30.73 63.27 45.19 65230 78508 63062104 0

x tube Sup steel 53512.

64.1

65.16 64.52

,65. 30.74 63.27 45.15 65.16 8590 I4-1 IU"5p 32 65.29 784 6302005 1 x tube supp steel 535.53 "*64.41 65.29 64.62 65.29 30_......- 3 45.19 5.9 7531 6302006 lxtube supp steel 535.4 64,41 65.29 64.61 65.29 30.73 63.27 45.19 6529 7850855 6303001 1.x u suppo---t steel 527.69 64.35 65.05 4.4 65.05 30.70 63.13 45.11 65.05 690442 6361001 lx up steel 534.63 64.40 65.26 64.60 65.26 30.73 63.26 5.1 8 65.26 1063132 63610u..-._.*

I-'x up shell --

stee 534.54 64.4 65.25 64.9-R5.2 3M.73 63.25 45.1K' 65.26 3744557 6361003 lx up shell steel 534.43 64.40 65.26 64.59 65.26 30.73 63.25 45.1-8 65.26 2617592 63-10-04 Ix up s'--

hell steel 534,42 64.4"--

65.2*

64.59 65,2 30.73 63.25 4T5.1 8 65.26---*

1462308 to 6451001 Ix sep ste 531.19 64,3"- -

65.1---

64152-

65. 1 30.--'--'7-1 63,20 45.15 651 890 lf1510 x sep steei 535 64-41 65.27 64.60 65.27

.30.73 63 26 45.19 55.27 19085._ _5 6451003

.Ix sep steel 5

-- 34.8-5 64.41 65.27 64.60

-65.2-'-

30.73 63.26-45.18 65.27 672-134,__,_

S 6601001.

x lsec sepE[7steele1::

534.42 64.40 665.2265 74.59 65.26 30.73-63.25 051 5.26 930932 6701001 lx st dome steel 534.31 64.40 65.25 64.59 65.25 30.73 63.25 45.18 65.25 3003904 I* xGMta I Heat=

to 24 I

Table 5 Initial Metal Internal Energy Identifcation Description Material Initial T.,,

Number I

Triple SO Secondary 64 I

7001001 3x feedrng steel 516.26 64,25 64-.7d 64.18 64 70 30.64

+ 62.93 45.00 64.70-494036

-7201001 3x Io shell steel 516.32 64.25 64.71 64.18 64.71 30.64 62.94 45.00 64.71 9374514 7201002 3xlo shell steel 516.37 64.25 64.71 64.18 64.71 30.64 6294 45.00 64.71 6655347 7201003 3x lo shell steel 516.43 64.25 64.71 64.1864.71 30.64 "62.94 45.01 64.71 6656308 7201004 -"

3"x-o sheli ste-el-5516.477' 64.26 64.71

-64.8

-64,71

-30.64" 62.94 45.01 64.71 6656949 7202001 3x lo shell steel 516.26 64.25 64.7.0 64.18 64.70 30.64 62.93 45.00 64.70 1386660 7301001 3xshroud steel 523.06 64.31 64.91 64.33 64.9i 30.68

'63.05 45.07 "64 91 1097498 50"1062 3x shroud steel 524.88 64.32 64.97 64.37 64,97 30,68

"63'0 6

" 45"09 64.97 1102255 7301003 3x shroud steel 525.25 64.33 64.9

" 64.38 64.98 30.69 666

"". 45,09 64'98 1103"23 7301004 shroud steel 525.34 64.33 64.98 64.39 64.98 30.69 6309

" 4".09

- 64.9"8" 1103459 "7301005 3x shroud steel/-

525.42 64.33 64.98 64 39 64.98 3069 63,09 45.09 64.98"*

1103668 73010-06

' 3x shroud steel 525.47 64.33 64.9"8 6439

'64.98-30.6ý9 63.10"

45.09 64.98 "

i 03799 7301007 3x shroud steel 525,88 64.33 65,00

__64-0 65.00 30.69 63.10 45.10 6500 K

"2083473 7301008 3x shroud steel 526.37 64.34 65.01 6441 65.01 3069 63.11 45.10 65.01 907499 7302001 3x tubesupp steel I

531.46 r64.38 65.17 64.52,65.17 30.72 63.20 1 45.15 65.17 233361 C.t' CD 0

0x 7302004 3x tube suppr steel 555 64.1 65.29 6462 6529 307 63 27 45 19 1 52 235578 7302004 3x tube supp

_-" steel 535.5 64.41 65.29 64.62 65.29 I 30.73 6327 i 45.19

__65.29 23557_

7302005__

3x tube supp steel 535.41 64.41 65 29 64 61 65.29 30.73 63.27 45.19 65.29 235528 7302006 3xtubesupp steel 53528 64.41 65.28 64.61 65.28 30.73 6327 4519 6528 235457 7303001 3x u support steel 527.64 64.35 65.05 64.44 65.05 30.70 63.13 45.11 65.05 2071057 7361001 3x up shell steel 534.51 64.40 65.26 6459 6526 30.73 63.25 45.18 65.26 3185501 7361002 3x up shell steel 534.42 64.40 65.26 64.59 65.26 30.73 63.25 45.18 65.26 11230523 7361003 3x up shell steel 534.31 64.40 65.25 64.59 65.25 30.73 63.25 45.18 65,25 7850573 7361004 3x up shell steel 534.3 64,40 65.25 64.59 65.25 30.73 63.25 45.18 65.25 4385693 7451001 3x sep steel 531.12 64.38 65.16 64.52 65.16 30.71 63.19 45.15 65.16 257666 7451002 3x sep steel 534.88 64.41 65.27 64.60 65.27 30.73 6326 45.19 65.27 572404 7451003 3x sep steel 534.72 64.40 65.27 6460 65.27 30.73 63.26 45.18 65.27 2015790 7601001 3x sec sep steel 534.3 64.40 65.25 64.59 65.25 30.73 63.25 45.18 65.25 2792014 7701001 3x st dome steel 534.27 64.40 65.25 64.59 65.25 30.73 63.25 45.18 65.25 8994137 S3xsG Metal Vol ume=

8.5598E+071 25 7302002 3x tube supp -

steel 535.26 64.41 65.28 64.61 65.28_'

30.73 1 6327 1 45.19

! 65.28 235446 7302003 -

3x tube suco-steel

!535.58

"*64.41 65.29 64.62 65.29 30.7-3" 63.27

'451Q Ri 759 9'*3AA*

)

Initial Metal Internal Energy I <--

-Volumetric Heat Capacity, BTUft*

"Identifcation I

I I

Vol Heat Number Description Material Initial T,,,

cm c,,413 cso c,

Cap

CEnergy, Ui, I~p BTU Steam Lines 6750200006 st line I..."-'tel

-" " 53.-----

643-52 64 5 65.22 30.72

÷ 32

-51 52 3636 6750200"06 st line2 steel 533.016 64.39 65.22 64.56 65.22 30.72 63.23 45.17

- 65.22 204091 67503o0600 slinie 3 steel 5399 64.39" 65.2164.56 65.21 30.72 63.23 45,17 65.21 1125809 16"75040"0"0 st line 4 steel 532.9B

" 64.39"-

65.21 64.56 65.21 30.72

- 63.23-'"

45.17 "65.21 906886" 67601 00"00.-

st ne 5 st'el 532 88 64.3"9 6"5.21 64.56-"'65.21 30.72 63.23 5.'17 65.21 642334 677010000 st ne6.

.steel

""5,2-1 64.46 65.46 64.76" 654-9 3"0.77 63.39 45.2 5 659 1156552 680010000 stline 7-steel 532.49 84.39 6520 64.55 65.20 30.72 63.22 45.16 65e.20 484858 6800200(0 st line 8 steel 532.54 64.39 65.20 64.55 65.20 30.72 6 63.22 '

45.16 65.20 1476630 680306)6b stiin-e' steel 532.51 64.39

" 6520 64.55 65.26

" 30.72 63.22 45 16 65.20

" 1476526 680040000 stlne 10 steel" 1

532.46

' 64.39 65.20 6455

"" 65.20 30.72 63.22 45.-16 65.20 476353 "680050006

'st line 11 steel 532.42 64.39 65.20 64.55 65.20 30.72

-63.22 45.16 65:20 147621"5""

'68660060 stline l2 steel 532.39 64.39 65.19 64.55 65.19 30.72 "3.22 45.16 65.19 1476111 680070000

-st li'ne 13 stFel.

53233"-

64.39 4

65.19 64.54" 65.19 "

39:72"-.63:i2

,4516 -

65.19 1475903 680080000 st line 14 steel 532.3 64.38 65.19 64.54 65.19 30.72 63.22 -

45.16 1475799 680090000 st line 15 steel 532.26 64.38 65.19 6454 65.19 30.72 63.21 45.16 65.19 1475661 680100000 stfine 6 steel 1 532.1 E.638 6454 65.19 30.72 63.21 45-.16 6519 1475107 680110000 st line 17 steel 532.02 64.38 65.18 64.54 65.18 30.72 63.21 45.16 65.18 1474830 681010000 stline 18 steel

ý 528 13 64.35 65.07 6445 65.07 30.70 63.14 45.12 6507 1254400 cisvinfnnnn I

,~.

__I~ruj te

.S4 43 52 45 52 07 32 51 52 161 ivru steel 533.42 64.39 65.23 64.57 165.23 30.72 i

63.23 1145.17 65ý.23 1161 683020000 st line 20 steel 533.32 64.39 65.22 64.57 65.22 30.72 63.23 45.17 65.22 1870207 683030000 st line 21 steel 533.1 64.39 65.22 64.56 65.22 30.72 63.23 45.17 65.22 1986909 683040000 st line 22 steel 532-22 64.38 65.19 64.54 65.19 30.72 63.21 1 45.16 65,19 1001404 692010000 st line 23 steel 536.91 64.42 65.33 64.65 65.33 30.74 63.30 45.20 65.33 1734847 692020000 st line 24 steel 54006 64.45 65.43 64.72 65.43 30.76 63.35 45.24 65.43 2258816 692030000 st line 25 steel 542.86 64.47 65,51 64.78 65.51 30.77 63.40 45.26 65.51 2273481 775010000 st line 26 steel 533.06 64.39 65.22 6456 65.22 30.72 63.23 45.17 65.22 1089240 775020000 st line 27 steel 532.96 64.39 65.21 64.56 65.21 30.72 63.23 45.17 65.21 612129 775030000 st line 28 steel 532.88 64.39 65.21 64.56 65.21 30.72 63.23 45.17 65.21 3376557 775040000 st line 29 steel 532.9 64.39 65.21 64.56 65.21 30.72 63.23 45.17 65.21 2429656 776010000 st line 30 steel 532.79 64.39 65.21 64.55 65.21 3072 63.22 45.16 65.21 1152868 777010000 st line 31 steel 541.39 64.46 65.47 64,75 65.47 30.76 63.37 45.25 65.47 3464690 780010000 st line 32 steel 532.45 64.39 65.20 64.55 65.20 30.72 63.22 45.16 65.20 1933239 780020000 st line 33 steel 532.45 64.39 65.20 64.55 65.20 30.72 63.22 45.16 65.20 5256774 780030000 st line 34 steel 532,43 64.39 65.20 64.55 65.20 30.72 63.22 45.16 65.20 4428748 26 Co CJI Co Tablie 5

Tablo 5 Initial Metal Internal Energy Identification Description Material InitialT c,T C

c,1,1 CVlHa CrIn ITU 780040000 st ine 35 steel 532.41 64.39 65.20 64.55 65.20 30.72 63.22 45.16 65.20 4428540 780050000 st line 36 steel 532.38 64.39 65.19 64.55 65.19 30.72 63.22 45.16 65.19 4428228 760060000 st ine 37 steel 53.34 S49 6.9

-64.54' 65.19 350.72 63.22 45.16 65.19' 4420713 "78007 0"000 st line 38 steel 532.18 64.38 65.19 6454 65.19 "30.72 "63.21 45.16 65.19 4426152 7-8"008-0-0"0"0

- -ie...

.steel 21 4

- 65.19 364.54 65.19 30.72 63.21 45.16 65.19" 4425322 Main Feedwater Lines MFW Pipe steel 435 Initial Condition Summary for Metals V

MFW Lines I

4 17E I

30.26 61.51 44.21 63.41 1773517 MFW Line Metal Heat =

1.7735E+06 63.41 62.24 62.18 63.41

4.

+

.- 4.

.

4.

+

4 4 -

4..,

4-. ---.- -,

+-. -.

_______________________*1--.

**

-

I ouL2 I

26657.39 19.3030E+0BI,

'----t

r--- -----

1 27

/

I I

Volumetric Heat Capacity, BTU/ft..-

.>1 I

V.yolume Heat RCS Metal" 19517.08 7.1606E+-(}

Cladi-112.05 2.1830E+06 Fuel 340.42

. 2.3967E+07 Ix SG Metal2-833,71 2.8540E+07 3x SG Metal 2500.72 8.5598E+07 Steam Lines 2299.12 7.2182E+07 Co CR 0

CR I

0 0

i I

I I Steam Line Metal Heat=-

7.2182E-+07 I.

4.

T IL..I I

SQN CONDENSATE VOLUME REQUIREMENT VERIFICATION 32-5014532-00 2.6 Structure Energy Content. Mode 2 Table 6 shows the calculation of the "Mode 2" internal energy for each, of many, model heat structures and summarizes the total energy associated with the plant metal mass at the hot shutdown mode of operation.

Table 6 is a duplicate of the initial energy table, Table 5, with the following exceptions.

The average temperature of each heat'structure is based on the conditions presumed to exist during Mode 2 operation. The no-load average RCS temperature at Sequoyah is 547 F (see Reference 5, Figure 5.3.4-1).

Reference 6, Figures 5-9 and 5-10 illustrate the RCS temperature response to a loss of offsite power event.

The event is characterized by, for one, a loss of power to the RCS pumps and an immediate reactor trip.

Examining these figures at about 2-hours, the time frame for cooling from full power to the Mode 2 state assumed in this work, the RCS AT is about 30 F. The following coolant temperatures for Mode 2 are, therefore:

TNU = 562 F T., 2 -

547F T Id.2 = 532 F For those primary RCS structures deemed "cold-side", Teod.2 is applied. For the hot side structures, Th,,,z is applied. For those structures transferring (adding or extracting) heat, T,,,.2 is applied The metal temperature in the pressurizer components are left at their initial, full power, values. This reflects the fact that the RCS pressure is unchanged from full power operation to Mode 2 operation and the fluid in the pressurizer is saturated.

Secondary, or steam-side, structures should be nearly at To1d42, reflective of the temperature of the fluid exiting the primary side of the steam generator. This includes the steam lines. The feedwater lines are assumed to be full of auxiliary feedwater within two hours so the piping structures are set to the auxiliary feedwater temperature of 120 F.

Given the material and the structure temperature volumetric heat capacity is determined, by interpolation, from Table 4. Note that, as mentioned above, if the material is steel the Mode 2 volumetric heat capacity is the minimum value of all the steels. In this way, the AU and the heat structure contribution to the condensate storage tank requirement is maximized.

The initial internal energy is then estimated for each heat structure in the following manner:

U 2 %C 2 VT 2

where, C2 =

volumetric heat capacity, BTU/f9-F, based on structure material and temperature, Table 4 V =

structure volume in ft1, taken from Table 1 for model heat structures, Table 2 for steam line piping, and Table 3 for main feedwater piping.

T -

structure temperature, F.

A summary of the structure internal energies is included at the bottom of Table 6. The summary indicates structure volume and internal energy for the RCS metal, clad and fuel, steam generator secondary metal, steam line piping, and main feedwater piping. The sum of all the internal energies of all the plant structures considered:

BTU 28

ML023290410

Text

SUMMARY

SUMMARY

SUMMARY

SUMMARY

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