ML18092A325

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Proposed Tech Spec,Revising Specs to Match Unit 1 Limits for K(Z) Normalized Fq(Z) as Function of Core Height Curve for Cycle 3 & Correcting Typo
ML18092A325
Person / Time
Site: Salem PSEG icon.png
Issue date: 10/15/1984
From:
Public Service Enterprise Group
To:
Shared Package
ML18092A324 List:
References
NUDOCS 8410190210
Download: ML18092A325 (8)
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Text

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e LCR 84-08 ATTACHMENT 1 PROPOSED TECHNICAL SPECIFICATION CHANGE FOR SALEM UNIT 2, CYCLE 3 FOR "K(Z) NORMALIZED FQ(Z)

AS A FUNCTION OF CORE HEIGHT" Description of Change The final acceptance criteria envelop for "K(Z) Normalized FQ(Z) as a Function of Core Height" presently used in the Technical Specification as Figure 3.2-2 must be revised for Unit 2, Cycle

3.

The revision includes elevating the limits of the third line segment of the K(Z) curve for Unit 2 to match the current Unit 1 limits.

The current and proposed K(Z) curves are shown in Figures 1 and 2. A typographical correction is made to ~he word, "measu~ed" on page 3/4 2-7 for clarity, as well.

In.1979, a small break LOCA analysis was performed to support the revision of the K(Z) curve for both Salem Units 1 and 2.

The license change request was then submitted for only Unit 1 and was approved by the NRC (Reference 1).

This LCR for Unit Z is identical to the earlier approved LCR for Unit 1.

Reason for Change The revision to the current K(Z) curve, which is associated with the FQ limits is necessary to eliminate the potential violation of the third line segment of the curve during the cycle 3 operation of Unit 2.

The need for the revised K(Z) curve was identified in the design phase of Cycle 3.

This cycle is the first 18 month.reload cycle designed for Unit 2~*~~~~~~~~~~~~~~

/

8410190210 841015 PDR ADOCK 05000311 P

PDR

.e LCR 84-08 Preliminary analysis have indicated that the current tech spec limit on the heat flux. hot channel f~ctor (PQ(Z)) would be violated during reactor maneuvers near.the end of cycle* 3.

The FQ(Z) values for Unit 2. cycle 3 are quite similar to those of Unit l cycle 6 which is also an 18 month cycle.

However, the F Q <~i) tech spec for Unit* 1 cycle 6 was not violated because tlle rev~sed KC Z) curve for Unit l was alread:y in place.

The revised K(Z) curve for Unit 2 will eliminate the potential violation of FQ(Z) tech spec.

Technical Specification Changes The current K(Z) curve in Unit 2 T~ch Spec is shown in Figure 1.

The proposed K(Z) curve for Unit 2* cycle 3 and beyond is shown in Figure.2.

Significant*aazard Consideration It has been determined-that the LCR involves no significant safety hazards consideration under 10CFRS0.92.

Using the K(Z) curve as indicated:in figure 2, a most severe small break LOCA analysis was performed for Salem_ Units l and 2.

The analysis was '*reviewed

  • and approved by NRC to effect the change for Unit 1 (Reference 1).

The analysis concluded that sufficient. core flooding was provided by the high head portion of the ECCS and accumulators to maintain peak clad temperatures and meet the requirements of 10 CFR 50.46.

  • LCR 84-08 Thus the current safety analysis design bases continue to be met and operation of Salem Unit 2 in accordance with the proposed K(Z) curve amendment:

0 0

0 would not involve a significant increase in the probability or consequences of an accident previously evaluated for Salem Unit 2, since the increase showed that the current core safety limits were still applicable.

in no way creates the possibility of a new or dif-ferent kind of accident from any accident previously evaluated for Salem Unit 2, since no plant modifications resulted from this change.

does not involve a significant reduction in the margin of safety.

Based on the above evaluation, we have determined that the proposed amendment, elevating the third line segment of the K(Z) curve, does not constitute a significant hazards consideration.

References

1.

Salem Nuclear Generating Station, Unit 1, Appendix A to License No. DPR-70, Amendment No. 20.

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NOTE FIGURE 2 PROPOSED UNIT 2* K(Z) VERSUS CORE HEIGHT FIGURE 12*2*

IUZt - NORMALIZED folZtAI A FUNCTION OF CORE HEIGHT IC ( Z) CURVE FOR SALEM UNIT 2, CYCLE l. AND. BEYOND t-3

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CORRECTED TECHNICAL SPECIFICATION PAGES L___ ____

POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (Continued)

~--------------------------------------~----------------------------------------

b) At least once per 31 EFPD. whichever occurs first.

2.

When the F,& 1s less than _or equal to the ~

l1111it for the appropriate measured care plane. additional power d1stribut1on

  • C RD I.

maps shall be-taken and Fxy compared to Fq and Fxy at least once per 31 EFPD.

e. The Fxy limit for RATED THERMAL POWER CFW) shall be provided for all core planes coAtaining bank.. D~ control rods and all unrodded core planes in a Radial Peaking.Factor Limit Report per spec1 ficat1on 6.9.1.10.

f *. The Fxy limits of e ** above. are not applicable 1n the following co.re plane regions as measured 1n percent of core height fra11 the bottom of the fuel:

1. Lawer core reg~on from OS to 151, inclusive.
2. Upper core region frOll SSS to tooi. inclusive.

3 *. Grid plane regions at 17.81 + 2S, 32.l + ZS, 46.4S + zs.

60.6S + 2S and 74.91 + 2S, inclusive.

4. Core. plane reg1 ans w1th1 n !. 2S of core height (!. 2.88 inches)

.about the bank demand position of the bank *o* control rods.

g. Evaluating the effl!cts of Fxy ~ FQ (Z-) to tterm1ne if Fq (Z) is within _1ts limit wheneYer Fxy exceeds Fxy*

4.2.Z.3 When FQ CZ:> 1s measured pur$uant to spec1 fication 4.10.Z.Z, an overal 1 measured F (Z) shall be obtained from a power distribution map and increased by Q

~S to account for manufacturing tolerances and further increased by SS to account for measurement uncertainty.

SALEM - UNIT 2 3/4 2-7

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10 12 14 CORE HEOOHT lfJl-r FIGURE J.2*2 KIZI - NORMALIZED f olZI AS A FUNCTION Of CORE HEIGHT I if

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