ML20041C210

Proposed Tech Spec Change 82-3,consisting of Sections 3.6.D,safety & Relief Valves & 4.6.D,basis

ML20041C210
Person / Time
Site:	Pilgrim
Issue date:	02/19/1982
From:	BOSTON EDISON CO.
To:
Shared Package
ML20041C209	List: ML20041C208 ML20041C210
References
NUDOCS 8202260343
Download: ML20041C210 (6)

Text

.

Proposed Technical Specification Proposed Chanae Reference is made to Pilgrim Nuclear Power Station, Unit #1 Technical Specifications, Section G.6.0, " Safety and Relief Valves" and Section 4.6.D contained on Page 126, the " Basis" for these sections contained on Page 145, and Table 3.2.F on pages 58 a (new) and 59.

Currently, Section 3.6.D consists of two paragraphs, denoted 1 and 3.

Boston Edison proposes the addition of two new paragraphs, denoted 3 and 4. These paragraphs shall state:

3. If the temperature of any safety relief discharge pipe exceeds 212 F during normal reactor power operation, a Report shall be issued per T.S. Section 6.9.B.1 which shall address the actions that have been taken or a schedule of actions to be taken.

4. The limiting conditions of operation for the instrunientation that monitors tail pipe temperature are given in Table 3.2.F.

The paragraph currently designated 3.6.D.3 will be re-designated 3.6.D.2.

Section 4.6.D currently consists of two paragraphs, denoted 1 and 2.

Boston Edison proposes the addition of two new paragraphs denoted 3 and 4. These paragraphs shall state:

3. Whenever the safety relief valves are required to be operable, the discharge pipe temperature of each safety relief valve shall be logged daily.

4. Instrumentation shall be talibrated and checked as indicated in Table 4.2.F.

We proposed to add a paragraph to the " Basis" (pg.145) in explanation of these additions, it shall state:

Pilgrim's experience with 2 stage safety / relief valves has demonstrated that minimum leakage exists when the tailpipe temperature is 215 Farenheit. Therefore, a reporting requirement triggered by a .

temperature of 212 F is conservative, and assures timely reporting before leakage reaches significant proportions.

8202260343 820219 PDR ADOCK 05000293 P PDR o  : . . _ _ . _. _ _ _ _ __

t The Table 3.2.F, Note (5) will have an asterisk

• added to the.

word back-up to reference it to the addition of Note (6). -

Note (6) shall state:

(6) At a minimum, the above listed SRV tail pipe temperature thermo-couples will be operable for each valve when the valves are required to be operable. If a thermocouple becomes inoperable, it shall be returned to an operable condition within 31 days or the reactor shall be placed in a shutdown mode within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Add page 58a to Table 3.2.F (Continued) to incorporate Note (6).

Reason for Change We propose these changes at the behest of USNRC, as stated in a meeting conducted between Boston Edison and NRC on December 18, 1981 and restated on page 3 of a meeting summary issued January 5,1982.

Safety Considerations These proposals are made at the request of NRC. They do not present unreviewed safety questions. They have been reviewed and approved by the Operations Review Committee, and reviewed by the Nuclear Safety Review and Audit Committee.

Schedule of Change These changes will be put into effect upon our receipt of the Commission's approval.

Fee Determination i

Pursuant to 10 CFR Section 170.12, Boston Edison Company proposes this change as a Class III.

l l

l l

I

l TIMITE G CONDITION FOR OPERATION SURVEII.I.ANCE REQUIREMENT 31 3.6.C Coolant chemistry (Cont'd) 4.6 l

l power operation is per=issible .

only during the succeeding seven days.

3. If the conditions in'1.or 2 above cannot be met, an orderly shutdown

- shall be initiated and the reactor

+

shall be in a Cold Shutdown Condi- ..,

, tien within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

D. Safety and Relief Valves D. Safety and Relief Valves L. During reactor power operating 1. At least one safety valve and two conditions and prior to reactor relief / safety valves shall be startup from a Cold Condition, or checked or replaced with bench -

whenever reactor coolant pressure checked valves once per operating is greater than 104 psig and tem- cycle. All valves will be tested perature greater than 340 F, both every two cycles.

safety valves and the safety modes of all relief valves shall be op- The set point of the safety valves erable.

shall be as specified in Specifi-2.

cation 2.2.

If Specification 3.6.D.1 is not met, an orderly shutdown shall be in- 2. At least one of the relief / safety itiated and the reactor coolant valves shall be disassenbled and pressure shall be below 104 psig inspected each refueling outage, within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

3. 3. Whenever the safety relief valves If the temperature of any safety are required to be operable, the relief discharge pipe exceeds 212 0F during normal reactor power operation, discharge pipe temperature of each safety relief valve shall be a Report shall be issued per T.S. logged daily. ~

Section 6.9.B.1 which shall address -

the actions that have been taken or a 4. Instrumentation shall be calibrated schedule of actions to be taken, and checked as indicated in Table 4.2.F.

4. The limiting conditions of operation for the instrumentation that monitors tail pipe temperature are given in Table 3.2.F.

il 4 .,

126

.p -

c!

i; -

Surveillance Instrumentation Table 3.2.F. (Continued) 9 Minimum # of i

Operable Instrument Instrument Type Indication Channels # Instrument and Range Notes 1/ Valve See Note (6) Tail Pipe Temperature Thermocouple (6)

Indication i

4 4

1 4

1 1

l 58a

l o

' ~

ll I

l NOTES FOR TABLE 3.2.F_

g .

(1)

From and after the date that one of thest parameters is reduced t.

(' to one indication, continued operation is permissible during the i

succeeding thirty days unless such instrumentation is sooner made .

4 operable. '

• Trom and after the date that one of these parameters is not indi-(2) cated in the control room, continued operation is permissible

- h instrumentation is

, during the succeeding seven days unless suc sooner made operable.

(3) If the requirements of notes (1) and (2) cannot be set, an orderly shutdown shall be initiated and the reactor shall be in a Cold Shutdown Condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

(4) These surveillance instruments are considered to be redundant to each other. ,

At a minimum, the primary or back-up* parameters shall Withbe operable pricaryfer

. (5) both each and valve when the valves are required to be operable. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. backup to operable status within 31 days or be in a shutdown mode within The following instruments sre associated with the safety / relief & safety valves:

s

• Secondary Primary Valve Tail Pipe Temperature Thernocouple Acoustic Monitor ,

TE6271-B 203-3A ZT-203-3A TE6272-B 203-3B ZT-20 3-3B i

\t TE6273-B 203-3C ZT-203-3C TE6276-B 203-3D ZT-203-3D TE6274-B 203-4A ZT-203-4A TE6275-B 203-4B ZT-20 3-4B

/

• See Note (6)

At a minimum, the above listed SRV tail pipe temperature, one of the

. (6) dual thermocouples, will be operable for each valve when the valves If a thermocouple becomes inoperable, it are required to be operable.

shall be returned to an operable condition within 31 days or the reactor snall be placed in a shutdown mode within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

I' A=endment No. 27 59

'g w --

7 - , . -

g .w. , *

/: ,,. ,

..- y 3.6.D and b.6.D ,

h Safety and Relief Valves As discussed in Subsection 4.4.6 of the Final Safety Analysis, Report, design of the nuclear system pressure relief system is intended to protect the nuclear system from,overpressurization in the event of the safety valve sia.ing transient.JJLn in, direct scram is assumed because.ASME Boiler and' Pressure Vessel Code,Section III, requires that protection systems directly related to the valve sizing transient must not be credited with action in determin4ng valve relieving capacity. Atotalof4 relief /safetyvalvesand2safetyvalvesis provided by the design. -

/ ,

Experience in safety valve operation shows that a testing of at least 50% of the safety valves per refueling outage is adequate to detect fad ures or deterioration. The tolerance value of +1% is in accor-

. . . . ith Section III of the ASME Boiler and Pressure Vessel Code.

An anQ.is ca.., been performed which shows that with all safety valves set 1% higher, the reactor coolant pressure safety limit of 1375 psig is not exceeded.

l Therelief/safetyvalveshavetwofunctions;i.e.,powerreliefor

~

self-actuated by high pressure. Power relief is a solenoid actuaced

- f.

\.

function (Autooatic Pressure Relief) in which external instrumen-tation signals of coinci. lent hi h 6drywell pressure and low-los water

- level initiate the valves to open. This function is discussed in Specification 3 5.D.. In addition,. the valves can be operated manually . . , ,

Pilgrim's ' experience with 2 stage safety / relief valves has demonstrated that minimum leakage exists when the tailpipe temperature is 215 Farenheit.

Therefore, a reporting requirement triggered by a temperature of 212 " is conservative, and assures timely reporting before leakage reaches sip'_f ~ ~

eant proportions.

1

!l 145 C, .

e

'__ , -_ _ - - - - - _ - ~

_~y , , _ ,- . . - - - , _ _ - , , . , , - ..,--.,-,_,,-,,-.-,--_,_,,,-,---.,--_-.e,,.