ML20138A906

Application for Amend to License DPR-6,requesting Change to TS to Withdraw Petition to Implement Option B Performance Based Requirements to App J of 10CFR50

ML20138A906
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	04/22/1997
From:	Addy R CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML20138A904	List: ML20138A899 ML20138A906 ML20138A913
References
NUDOCS 9704280282
Download: ML20138A906 (4)

Text

. _ _ __ _ _ __ _. _. .. . . ..

I g, CONSUMERS ENERGY COMPANY D0CKET 50-155 Request for Change to the Technical Specifications ,

License DPR-6 l r

for the reasons hereinafter set forth, it is requested that the Technical l Specifications contained in the Facility Operating License DPR-6, Docket 50-  ;

155, issued to Consumers Energy Company on May,1, 1964, for the Big Rock Point Plant be changed as described in Section I below: ,

Revised Technical Specification pages are attached. Proposed changes are shown i by a back-slash (/) in the right-hand margin. -

I. CHANGES

1) Technical Specification section 4.1.2(b); Chloride Ion (Ppm) and Boron l (Ppm) need to be revised to read Chloride Ion (ppm) and Boron (ppm).  !

2) Technical Specification section 6.1.3 Reactor Safety System Bypass; trip ,

function bypassed when the mode relector switch is in the shutdown position, requires revision. Delete ".None", and insert the following:

Low Steam Drum Level" Steam Line Backup Isolation Valve Closed High Condenser Pressure Recirculation Line Valves Closed In the same section, note (c) also requires revision. Delete the last sentence of the note "None of the reactor safety system signals are bypassed since there is no need to withdraw control rods."

3) Technical Specification section 6.9.2.2.A 4, Radiological Impact on Man, needs revision to be consistent with Technical Specification section 6.9.2.2.A. Delete "to be submitted within 60 days after January 1 of each year shall", so that the paragraph reads "The Radiological Effluent Release Report shall include potential doses to individuals and populations calculated using measured effluent and averaged meteorological data in accordance with the methodologies in the Offsite Dose Calculation Manual."

i

4) Technical Specification section 6.12.1.c. has a reference to the l Chemistry and Radiation Protection Supervisor. Delete " Chemistry and" so l that the section reads "...specified by the Radiation Protection Supervisor in the RWP."

5) Technical Specification 6.12.2 needs correction. " Service" needs to be deleted and replaced with " surface", so that the sentence will read.."from the radiation source or from any surface from which the radiation penetrates..."

6) Technical Specification 11.3.5.3.7, Action 3 should read " Action a."

7) Bases for 13.1.3.1 - Gaseous Effluent Dose Rate requires a correction to the units described to measure skin dose. 3000 mr/hr should read 3000 4

mr/yr.

9704290282 970422 PDR ADOCK 05000155 p PDR

's 1. BIG ROCK POINT Pl. ANT 2

, . TECH SPEC CHANGE REQUEST II. DISCUSSION Changes 1),5),6),and7)

These changes correct typographical errors.

Change 2)

This change is requested to make the Technical Specifications consistent with plant procedures and current design. As evidenced by the proposed change, four trip functions have always been bypassed when the reactor mode switch is in the shutdown position:

LOW STEAM DRUM WATER LEVEL A trip signal from this condition anticipates a loss of water which could lead  ;

to a low reactor water level. Four level switches LS-RE06A and LS-RE20A connected to Protection Channel 1 and LS-RE06B and LS-RE20B connected to protection Channel 2, detect this condition. When the steam drum water level drops to 8.0 inches below steam drum center line, a control rod scram is initiated. These switches are located on the steam drum wall, across from the C-30 panel.

The steam drum water level trip signals are bypassed by contacts of auxiliary relays K11 and K12 in the annunciator control units. K11 and K12 are energized by contacts 2-2C (Channel 1) and 9-9C (Channel 2) on the reactor mode switch, S4, in the shutdown, refuel and bypass dump tank positions.

MAIN STEAM ISOLATION VALVE Closure of main steam isolation valve M0-7050 to 50%, whether by remote manual control RMC-5500, malfunction or penetration closure switch SS, initiates a control rod scram. This is accomplished by opening limit switch contacts LS-9 and LS-10 connected to Protection Channel 1 and LS-15 and LS-16 connected to Protection Channel 2, on the valve drive unit.

These trip signals are bypassed by contacts of auxiliary relays K11 and K13 in the annunciator control units. K11 and K13 are energized by contacts 2-2C (Channel 1) and 9-9C (Channel 2) on the reactor mode switch, S4, in the shutdown, refuel and bypass dump tank positions.

HIGH CONDENSER PRESSURE High condenser pressure is used as an indication that the main condenser is no longer available as a heat sink for the reactor output, thereby making a control rod scram necessary.

Pressure switches PS-654 and PS-655 connected to Protection Channel 1 and PS-652 and PS-653 connected to Protection Channel 2, detect this condition when condenser pressure reaches 8.0 inches Hg absolute.

The high condenser pressure trip signal is automatically bypassed any time steam drum pressure is below 500 psig (the definition of shutdown is all or all but one of the control rods fully inserted in the reactor core; and Primary System Coolant water temperature less than 212*F). This automatic bypass is accomplished by PS-REISA and PS-RE15B connected to Protection

[* ; *i,, BIG ROCK POINT PLANT 3 1., TECH SPEC CHANGE REQUEST 4

5 Channel 1 and PS-RE15C and PS-RE150 connected to Protection Channel 2. These pressure switches are set to operate at 450 psig. They are located on the steam drum wall across from the C-30 panel. .

RECIRCULATION LINE VALVE CLOSED 5

, The closure of these valves would prevent coolant circulation to the reactor core and a control rod scram is initiated to prevent development of excessive fuel temperatures.

A trip signal is received at approximately 10% of full simultaneous closure of both discharge valves M0-N001A and M0-N001B, or both suction valves M0-N003A '

and M0-N003B, or 50% of full simultaneous closure of both Butterfly Valves M0-N006A and M0-N0068, or any combination of these valves, one in each loop. That is, if recirculation is restricted in both loops, a trip signal will be inserted. The sensors are limit switch / position switch contacts on each of the drive units of the valves.

1 These trip signals are bypassed by contacts of auxiliary relays K12 and K13 in the annunciator control units. K12'and K13 are energized by contacts 2-2C (Channel 1) and 9-9C (Channel 2) on the reactor mode switch, S4, in the  !

shutdown, refuel, and bypass dump tank positions.

J Change 3) l This change is requested to make the Technical Specifications consistent.

Technical Specification section 6.9.2.2.A.4, Radiological Impact on Man, needs revision to be consistent with Technical Specification section 6.9.2.2. A.

Change 4)

This change is required to reflect a recent organizational change that created separate supervisory positions for Chemistry and Radiation Protection.

III. ANALYSIS OF NO SIGNIFICANT HAZARDS CONSIDERATION l l

In accordance with 10 CFR 50.92, Consumers Energy Company has made a determination that the proposed amendment involves no significant hazards considerations. To make this determination, Consumers Energy Company has i

established that operation in accordance with the proposed amendment will not: 1) involve a significant increase in the probability or consequences of

an accident previously evaluated, or 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.

t The proposed Technical Specification Change does not present an undue risk to the public, and does not impact common defense and security.

The proposed change does not:

1) Involve a significant increase in the probability or consequences of an accident previously evaluated.

4

=

. - . . - - - - - . - - - . - . - . - _ - . - . - . ~ _ _ - - . . _ . -

.J BIG ROCK POINT PLANT 4

! --(:- TECH SPEC CHANGE REQUEST The proposed changes are clarifications within the Technical Specifications, and do not alter the technical content of the technical specifications. Plant

, o)eration or configuration-is not affected. The postulated doses received by tie general public and plant personnel as a direct result of accidents '

4 previously described, are not affected. Plant operation or configuration is not affected. Therefore the proposed changes do not. involve a significant increase in the probability or consequences of an accident previously r evaluated. i l

j 2) Create the possibility of a new or different kind of accident from any  !

accident previously evaluated.  !

l The proposed changes are. either clarifications to correct. inconsistencies )

1 _w ithin the Technical Specifications, or corrections of typographical errors.  ;

The proposed changes do not alter the facility in any way,' therefore the proposed changes do not create the possibility of a new or different kind of accident from any accident previously evaluated.  ;

3)ilnvolve a significant reduction in a margin of safety

' The proposed change does not affect any margin of safety as defined by the ,

Plant Technical Specifications. .

IV. CONCLUSION  ;

The Big Rock Point Plant Review Committee has reviewed this Technical Specification Change Request and has determined this change does not involve

, an unreviewed safety question and, therefore, involves no significant hazards consideration. This change has been reviewed by the Nuclear Performance Assessment Department. A copy of this change request has been sent to the State of Michigan official designated to receive such Amendments to the 1

Operating License.

CONSUMERS ENERGY COMPANY

] To the best of my knowledge, information and belief, the contents of this submittal are truthful and complete.

By ~ -

w Rot,ert J Addy \ i

. Plant Manger Sworn and subscribed to before me this 22nd day of April- 1997. t' i

havM, *n OhSM nniff. r Lynn Kelms, Notary Public Ch4rlevoix County, Michigan

-My commission expires August.29, 1999.

2 (SEAL).

__ _ _ ._ - -. .. _ . .-. _ . . _ - . - . ._!