ML19094A147

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Letter Regarding Unreviewed Safety Questions with Potential Impact on the Operation
ML19094A147
Person / Time
Site: Surry  
Issue date: 08/26/1976
From: Stallings C
Virginia Electric & Power Co (VEPCO)
To: Reid R, Rusche B
Office of Nuclear Reactor Regulation
References
Download: ML19094A147 (6)
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Dear Nr. Rusche:

Serial No. 211 FR/JTR:agp Docket Nos. 50-280 50-281 On August 5, 1976, the Virginia Electric and Power Company (Vepco) was informed by the Westinghouse Electric Corporation of two unreviewed safety questions with potential impact on the operation of Surry Units 1 and

2.

These unreviewed questions are concerned with the impact of higher upper head fluid temperatures on the Loss of Coolant Accident ECCS Analysis and a greater,than anticipated effect on DNBR of fuel rod bowing in thimble cells.

An evaluation of these concerns and their potential impact on the operation of Surry Units 1 and 2 was conducted by Vepco, and on August 6, 1976, volun-tary reductions in all hot channel peaking factor limits were put into effect.

Notification of these actions was then provided to the U. S. Nuclear Regulatory Commission (NRC).

On August 13, 1976, additional guidance on an interim mechanism for conservatively accommodating any potential impact from the above concerns was informally received from the NRC Staff.

Evaluations were then performed to determine the appropriate limits on the operation of Surry Units 1 and 2 con-sistent with the guidance received from the Staff.

These evaluations and associated operating limits were reviewed with the Staff on August 16, 1976, and were formally submitted, as required, on August 18, 1976, in our letter Serial No. 194.

On August 24, 1976, the Staff informed us that our evaluation and associated limits for the impact of higher upper head fluid temperature on the Surry LOCA/ECCS were not acceptable.

During further discussions on August 25, 1976, the Staff informed us that the reason the evaluation was unacceptable was that it did not contain sufficient information to confirm that the most conservative value of the discharge coefficient (CD) was used, notwithstanding our specific discussion on this point on August 16, 1976, and the fact that we addressed and justified our position on this point directly in our August 18, 1976, submittal.

The Staff further indicated that until confirmatory analyses could be submitted, reviewed, and approved, an addi-tional penalty of 0.05 on the Fq limits contained in our August 18, 1976, submittal would be required.

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'vrnorn1A ELECTRIC AND PowER COMPANY To Mr. Benard C. Rusche 8/26/76 2

Our position on this matter is that our evaluations and associated limits contained in our August 18, 1976, submittal are technically correct and complete; however, we will accept the Staff's position until confirmatory analyses can be approved.

Accordingly, we have revised the operating limits contained in our August 18, 1976, submittal.

These limits are contained in to this letter.

Very truly yours,

~Jn.Jatt+

C. M. Stallings Vice President-Power Supply and Production Operations Attachment cc:

Mr. Norman C. Moseley, Director

-Office of Inspection and Enforcement Region II

e August 26, 1976 The limiting values of the following power distribution parameters shall be changed:

a.

heat flux hot channel factor, Fq(Z)

N

b.

enthalpy rise hot channel factor, F8H, and

c.

quadrant power tilt ratio.

The heat flux hot channel factor, Fq(Z) shall be limited to the.*following values:

For Unit 1 Fq(Z) ~ (1. 80/P) x K(Z) for P > 0.5 Fq(Z) ~ (3.60) x K(Z) for P ~ 0.5 For Unit 2 Fq(Z) ~ (1.82/P) x K(Z) for P > 0.5 Fq(Z) ~ (3.64) x K(Z) for P ~ 0.5 where P is the fraction o'.f rated power at which the core is operating, K(Z) is the function given in Figure 1, and Z is the core height location of Fq(Z).

Additionally, the limiting behavior of Fq(Z) for nominal transient operation of each unit shall be periodically evaluated.

If this evaluation shows that Fq(Z) could potentially violate its limiting values either.:

a.

reactor thermal power shall be reduced appropriately in order to accomodate this potential violation, or

b.

APDMS type surveillance shall be performed to directly monitor Fq(Z).

N The enthalpy rise hot channel factor, F8H, shall be limited to the following values:

N FAH~ 1.55 { 1 + 0.2(1-P)} x T(BU) where Pis the fraction of rated power at which the core is operating and N

T(BU) is the thimble cell penalty on F8H, which is given in Figure 2.

The quadrant power tilt ratio shall be limited to values < 1, 02.

e e

ATTACHMENT 1 CHANGES TO LIMITING VALUES OF POWER DISTRIBUTION PARAMETERS FOR CYCLE 3 OPERATION OF SURRY UNITS NO. 1 AND 2 AS THE RESULT OF HIGHER UPPER HEAD FLUID TEMBERATURES AND THIMBLE CELL ROD BOW EFFECT

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