ML20136G773

Safety Evaluation Approving Amends 155,150,174 & 170 to Licenses DPR-19,DPR-25,DPR-29 & DPR-30,respectively

ML20136G773
Person / Time
Site:	Dresden, Quad Cities
Issue date:	03/14/1997
From:	NRC (Affiliation Not Assigned)
To:
Shared Package
ML20136G765	List: ML20136G773
References
NUDOCS 9703180193
Download: ML20136G773 (3)

Text

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4 SAFETY EVALVATION BY THE OFFICE OF NVCLEAR REACTOR REGULATION 9

RELATED TO AMENDMENT NO.155 TO FACILITY OPERATING LICENSE NO. DPR-19.

AMENDMENT NO.150 TO FACILITY' OPEPATING LICENSE N0. DPR-25.

AMENDMENT N0. 174 TO FACILITY OPERATING LICENSE N0. DPR-29 AND AMENDMENT NO. 170 TO FACILITY OPERATING LICENSE N0. DPR-30 COMMONWEALTH EDIS0N COMPANY AND MIDAMERICAN ENERGY COMPANY DRESDEN NUCLEAR POWER STATION. UNITS 2 AND 3. AND OVAD CITIES NUCLEAR POWER STATION. UNITS 1 AND 2 DOCKET NOS. 50-237. 50-249. 50-254 AND 50-265

1.0 INTRODUCTION

By letter dated January 6,1997, Commonwealth Edison Company (Comed, the licensee) submitted an amendment requesting to clarify and maintain consistency between the operability requirements for protective instrumentation and associated bypass features of the Technical Specifications (TS) for the Dresden Nuclear Power Station, Units 2 and 3, and the Quad Cities Nuclear Power Station, Units 1 and 2.

2.0 EVALUATION A.

Tables 3.1. A-1 and 4.1. A-1: Items 9. 10. and 11 Tables 3.1. A-1 and 4.1. A-1, Items 9,10, and 11 include functional units for the turbine stop valve closure scram (Item 9), the turbine EHC control oil low pressure scram (Item 10), and the turbine - control valve fast closure scram (Item 11).

These items include a footnote with the applicable OPERATIONAL MODE which addresses when these functional units are applicable.

The current footnote (d) in Table 3.1.A-1 states that the function shall be automatically bypassed when thermal power is less than 45 percent of RATED THERMAL POWER and current footnote (1) in Table 4.1.A-1 states that the function is not required to be OPERABLE when THERMAL POWER is less than 45 percent of RATED THERMAL POWER.

The current Reactor Protection System (RPS) design at Dresden and Quad Cities incorporates an automatic bypass of these functions when first stage pressure 9703180193 970314 PDR ADOCK 05000237 P

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s v is less than 400 psi, or approximately 45 percent of rated steam flow. When reactor power is below 45 percent of RATED THERMAL POWER, the applicable transient for these protective functions do not threaten the fuel integrity.

Also when the RPS system instrumentation for these items don't meet the specified minimum number of OPERABLE CHANNELS, ACTION 16 requires that a power reduction be initiated within 15 minutes and THERMAL POWER be reduced to less than 45 percent of RATED THERMAL POWER within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

The licensee proposes to make footnote (d) of Table 3.1.A-1 and footnote (1) for Table 4.1.A-1 identical.

This change would clarify the APPLICABLE MODE for Items 9, 10, and 11 as being MODE 1 when THERMAL POWER is greater than or equal to 45 percent of RATED THERMAL POWER.

This is consistent with the Improved Standard Technical Specifications (ISTS) (NUREG-1433).

This change is administrative in nature and is consistent with the design of the systems at Dresden and Quad Cities and is, therefore, acceptable.

B.

Table 3.2.E-1: Items 1.a. b and c Table 3.2.E-1, Items 1.a, b, and c are functional units for the Rod Block Monitors (RBM), upscale, inoperative, and downscale trips.

The RBM is designed with an automatic bypass feature when a peripheral control rod is selected and when the power level is less than 30 percent RATED THERMAL POWER.

When reactor power is less than 30 percent of RATED THERMAL POWER, the worst case rod withdrawal error will not challenge fuel integrity limits.

Footnote (a) for the RBM in Table 3.2.E-1 states that the RBM shall be automatically bypassed when the referenced average power range monitor (APRM) channel indicates less than 30 percent of RATED THERMAL POWER.

Footnote (e) states that the applicable OPERATIONAL MODE for the RBM is MODE 1 when THERMAL POWER is greater than or equal to 30 percent RATED THERMAL POWER.

The licensee proposes to eliminate the reference to the automatic bypass feature in footnote (a).

Footnote (e) clearly indicates when the RBM shall be operable.

By deleting the automatic bypass reference in footnote (a) these footnotes become consistent with other table notations in providing clearer guidance regarding the applicability of this TS. The actual automatic feature will not be affected.

This change is also consistent with the ISTS.

Because this change maintains consistency with the RBM design and provides clarity as to the applicability of the RBM, it is acceptable.

C. Tables 3.2.E-1 and 4.2.E-1: Item 3.a Tables 3.2.E-1 and 4.2.E-1 define the applicability and surveillance requirements for the control rod block instrumentation, respectively. A design feature of Item 3.a, Source Range Monitors (SRM), " detector not full in," rod block position is to be automatically bypassed if the Intermediate Range Monitor (IRM) channels are on range 3 or higher or when the count rate exceeds 100 counts per second (cps). These features ensure that the SRM is available at low power operation only when there is posit.ive detection of an adequate neutron flux (100 cps) to be detected up to when the IRMs are

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adequately detecting neutron flux which is at range 3 or higher, otherwise there is a rod block.

The licensee is proposing to eliminate the reference of the count rate in footnote (b) for Table 3.2.E-1 and footnote (f) for Table 4.2.E-1 and provide a new footnote (j) for Table 3.2.E-1 and footnote (k) for Table 4.2.E-1 to specifically identify that there is a rod block if the detector count rate is less than or equal to 100 cps when determining the operability of the SRM when the detector is not full in. This change maintains the design of the control rod block instrumentation, however, more clearly defines the operability requirements of the system.

This change is acceptable.

3.0 STATE CONSULTATION

In accordance with the Commission's regulations, the Illinois State official l

was notified of the proposed issuance of the amendments.

The State official had no comments.

4.0 ENVIRONMENTAL CONSIDERATION

The amendments change a requirement with respect to the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20.

The NRC staff has determined that the amendments involve no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure.

The Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration, and there has been no i

public comment on such finding (62 FR 6573). Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).

Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.

5.0 CONCLUSION

The Commission has concluded, based on the considerations discussed above, that:

(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 amendments will not be inimical to the common defense and security or to the health and safety of the public.

Principal Contributor: Robert M. Pulsifer Date:

March 14, 1997 5

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