PY-CEI-NRR-0817, Application for Amend to License NPF-58,revising First Stage Turbine Pressure Setpoints Based on Test Data in Tech Spec Tables 3.3.1-1,note (H) & 3.3.4.2-1,note (B) & Sections 2.2.1.10 & 2.2.1.11.Fee Paid

Application for Amend to License NPF-58,revising First Stage Turbine Pressure Setpoints Based on Test Data in Tech Spec Tables 3.3.1-1,note (H) & 3.3.4.2-1,note (B) & Sections 2.2.1.10 & 2.2.1.11.Fee Paid

ML20154H544
Person / Time
Site:	Perry
Issue date:	05/20/1988
From:	Kaplan A CLEVELAND ELECTRIC ILLUMINATING CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML20154H547	List: ML20154H551 PY-CEI-NRR-0817, Application for Amend to License NPF-58,revising First Stage Turbine Pressure Setpoints Based on Test Data in Tech Spec Tables 3.3.1-1,note (H) & 3.3.4.2-1,note (B) & Sections 2.2.1.10 & 2.2.1.11.Fee Paid
References
PY-CEI-NRR-0817, PY-CEI-NRR-817, NUDOCS 8805250391
Download: ML20154H544 (3)

Text

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THE CLEVELAND ELECTRIC ILLUMIN ATING COMPANY P O. BOX 97 o PERRY. OHIO 44081 e TELEPHONE (216) 259 3737 e AD DR E S S - 10 CENTER ROAD Somng The Best Location in the Nation PERRY NUCLEAR POWER PLANT Al Kaplan V1CE PRES: DENT May 20, 1986 uucum caoup PY-CEI/NRR-0317 L U.S. Ibclear Regulatory Commission Doc ume nt Control Desk Washington, 13. C. 20555 Per ry Nuclear Power Plant Docket No. 50 440 Technical Specitication Change Request on Turbine First Sy ge Pressare Ge ntlemen :

The Cleveland Electric Illuminating Company (CC1) hereby requests amendment of Facility Operating License NPF-58 for the Perry Nuclear Power Plant, Unit 1.

t.n acco rdance wi tn the requirements of 10 CFR 170.12 a check in the cmount of

$ 150.00 is enclosed. In accordance with the requirements of 10 CFR 50.91(b)(1), a copy of this request for amendment has been sent to the State of Ottio as indicated below.

Titis amendment requests revision of note (h) to Technical Specification Taole

3. 3.1-1, no te ( b) to Technlcal Specification Table 3.3.4.2-1 and the Bases Sec tions 2.2.1.10 and 2.2.1.11 to revise the first stage turbine pressure setpoints based on te st data.

Attachmant I provides the Summa ry , Saf e ty Analysis , Significant Hazards and Environmental Impact Considerations. Attachment 2 is a copy of the marked up Technical Specification pages.

Should you have any questions, please feel f ree to call.

Very truly yours, f.

Ai Kaplan Vice President Nuclear Group i l

AK: cab At tac hna nt s  !

cc: K. Connaughton D i T. Colburn i f J. Harris (State of Ohio) j 4

gh 8805250391 880520 PDR P

ADOCK 05000440 DCD j(, g lh

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Attachmont PY-CEI/NRR-0817 L Page 1 of 2 Summary The proposed amendment changes the initial setpoints for turbine first stage pressure on Technical Specification tables 3.3.1-1 (note h) and 3.3.4.2-1 (note b). The existing values vere based on turbine thermal heat balance calculations, and have been shown to be overly conservative through testing.

The original requirement that the turbine valve closure scrams should be bypassed below the turbine first stage pressure equivalent to 40% of RATED THERMAL POVER has not changed. The Setpoints and Allovable Values are being established based on data determined by startup testing. The basis for reducing the setpoints due to reduced feedvater temperature also has not changed. In the proposed change, the setpoints and allovable values vould be depicted in terms of actual pressure, instead of a certsin span on the instrument. The actual pressure is more meaningful and permits future instrument replacements without necessitating a Technical Specification change merely due to instrument scaling differences.

Safety Analysis As stated above the proposed change does not change the bases for the Setpoint or Allovable Value. The change request is based on test data which provided the actual value of turbine first stage pressure corresponding to 40% Rated Thermal Pover. The Setpoints and Allovable Values vere then calculated for normal operation and for reduced Feedvater heating operation.

The purpose of this setpoint is to establish when a turbine trip vill cause an anticipatory reactor trip, ar.d an end of cycle recirculation pump trip. This trip bypass is discussed in various places in the Updated Safety Analysis Report (USAR) including Sections 7.2.1.1.b.5 and 6, Section 7.6.1.6, Sections 15.2.2 and 15.2.3 and Appendix 15D, Section 15D.9. Turbine first stage pressure is used to sense power since this pressure increases approximately linearly with pover. The existing Technical Specifications have established the Setpoint and Allovable Value as a percentage of calibration span of the existing instruments. The proposed Setpoint and Allovable Value are in units of pressure (PSIG). In both cases the setpoint and Allovable Value are based on 40% of Rated Thermal Pover. Testing has been performed since the establishment of the initial setpoints, which provided actual data for first stage pressure at 40% of Rated Thermal Pover. Using this data, Allovable Values and Trip Setpoints vere established, with allovance for instrument accuracies, calibration accuracy and instrument drift. Since the basis for the setpoint has not changed there is no safety significance to the proposed changes.

Significant Hazards Analysis e j The standards used to arrive at a determination that a request for amendment requires no significant hazards consideration are included in the Commission's Regulations, 10 CFR 50.92, which state that the operation of the facility in accordance with the proposed amendment vould not (1) involve a significant increase in the probability or consequences of an accident previously evaluated, (2) create the possibility of a new or different kind of accident from any accident previously evaluated, or (3) involve a significant reduction in a margin of safety. CEI har reviewed the proposed change with respect to pl these three factors.  ! l 9\ck O W

- AD33M

. i Attachm:nt  !

PY-CEI/NRR-0817 L Page 2 of 2 The proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.

The basis for establishing the Trip Setpoint and Allovable Values has not changed (40% of Rated Thermal Power). The Trip Setpoint and Allovable Value are being changed based on test data of actual turbine first stage pressure when the plant was operating at 40% of Rated Thermal Pover. As such there is no change to the probability of previously evaluated accidents. Furthermore the consequences of an accident vould not change since the basis for this scram bypass has not changed. Thus there is no increase in the probability or consequences of any accident previously evaluated.

The proposed change does not create the possibility of a new or dif ferent kind of accident.

As previously stated the basis for establishing the Setpoint and Allovable Value has not changed, nor has the function of the turbine first stage pressure instruments. Therefore this proposed change has not created the possibility of a new or different kind of accident.

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

The proposed change continues to be based upon 40% of Rated Thermal pover.

Test data has accurately determined what turbine first stage pressure is equivalent to 40% of Rated Thermal Power. Based on this test data, the proposed Setpoints and Allovable Values were determined, and are conservative with respect to the observed pressure at 40% pover. Therefore the proposed change more accurately represents the Setpoint and Allovable Value for turbine first stage pressure, as described in the bases of this Technical Specification. Therefore the change does not involve a reduction in the margin of safety.

Therefore, CEI has concluded that this proposed amendment involves no significant hazards considerations.

Environmental Impact The Cleveland Electric. Illuminating Company has reviewed the proposed Technical Specification change against the criteria of 10 CFR 51.22 for environmental considerations. As shovn above, the proposed change does not involve a significant hazards consideration, nor increase the types and amounts of effluents that may be released offsite, nor significantly increase individual or cumulative occupational radiation exposures. Based on the foregoing, CEI concludes that the proposed Technical Specification change meets the etiteria given in 10 CFR 51.22(c)(9) for a categorical exclusion from the requirement for an Environmental Impact Statement.