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Forwards Revised Response to NUREG-0737 Action Item II.E.4.2 on Containment Isolation Dependability.Encl Closes Out SER Open Item 84
	ML18026A365
Person / Time
Site:	Susquehanna
Issue date:	06/05/1981
From:	Curtis N; PENNSYLVANIA POWER & LIGHT CO.
To:	Schwencer A; Office of Nuclear Reactor Regulation
References
	RTR-NUREG-0737, RTR-NUREG-737, TASK-2.E.4.2, TASK-TM PLA-835, NUDOCS 8106110334
	Download: ML18026A365 (12)
	v • d • e

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ACCESSIOV NBA;8106110334 OOC.DATE! 81/Ob/05 NOTARIZED:

NO DOCKETACIL:50-387 Susquehanna Steam Electric Station<

Unit 1> Pennsylva 50"388 Susquehanna Stea~ Electric Station<

Unit 2~ Pennsy'lva 050003~

AUTH BYNAME AUTHOR AF F ILIATI ON CUR T I S < V. v'.

Pennsylvania Power 4 Liqht Co ~

REC IP, VA".E RECIPIENT AFFILIATION SCHviENCEH+A ~

Licensing Branch 2

SUB,JECT:

Forwards revised response to NUREG 0737 Action Item II'D 4 '

on containment isolation deoendability,Encl closes out'ER Ooen Item R4 ~

DISTR IBUT I VN CODE:

8001'8 COP IES RECE IVFD: LTR J ENCL SI'l E:

TITLE:

PSALM/FSAR ANOTS and Related Correspondence.

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Send IPE 3 COpieS FSAP 8 all amendS.i Cy:RNR-LRG PM(L.RIB)

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TWO NORTH NINTH STREET, ALLENTOWN, PA. 18101 hlORhfAN W. CURTIS Vice President

~ Engineerinp th Construction-Nuclear 770.53$ t PHONEr (215) 770-5151 J<//$/f/>~.

V June 5, 1981 Mr. A. Schwencer, Chief Licensing Branch No.

2 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C.

20555 Docket Nos.

50-387 50-388 SUSQUEHANNA STEAM ELECTRIC STATION REVISED RESPONSE TO CONTAINMENT ISOLATION DEPENDABILITY SER OPEN ITEM NO.

84 ER 100450 FILE 841-2, -12

Dear Mr. Schwencer:

Attached is a revised response to NUREG 0737, requirement II.E.4.2.

This response completes our action and will allow close out of open item no. 84.

Very truly yours, N.

W. Curtis Vice President-Engineering a Construction-Nuclear DPM/mks Attachment cc:

R.

M. Stark NRC gO01 8

~~ Ll X 6 6 f $ Q 9>+'.

P'E.'NiNiS Y-LYA)N~IA~ Po WE.R'>> LI G H T C 0 AiNiY

X.1.29.3 Statement of Response (1)

Containment isolation signals are actuated by several sensed parameters (refer to Table 3.3.2-1 in the Technical Specifications).

This complies with SRP Subsection 6.2.4, Paragraph IX-6.

(2)

Each process line penetrating containment was reviewed to determine whether it is an essential or non-essential line for purposes of isolation requirements.

The classification for each line is given in Table X.1.29-1.

Justification for the classification as an essential or non-essential line was also developed and is provided in Table X.1.29-2.

Systems identified as essential are those which may be required to perform an indispensable safety function in the event of an accident.

Non-essential systems are those not required during or after an accident.

Since instrument lines are not governed by isolation signals but are equipped with a manual isolation valve followed by an excess flow check valve outside the containment, the review of these lines was limited to ensure compatibility with the penetration listing in Table 6.2>>12a.

(3)

All lines to non-essential systems are provided with isolation capability.

All isolation valves in these lines, except the reactor water clean-up system (RWCU) discharge valves (G33-iF042 and 1F104 receive auto-isolation signals. (refer to Table X.1.29-1).

The isolation function for the RWCU discharge lines is provided by three series check valves (141-1F010A,B, HV-14107A,B and G33-1F039A,B) which prevents back flow from the reactor vessel.

The RWCU discharge isolation valves are not closed to prevent the loss of the filter cake in the RWCU filter demineralizer system and injection of resin into the vessel on restart of the RWCU system.

(4)

All containment isolation valves, except those listed below, will not automatically open on logic reset.

Some valves require corrective action to comply with this requirement.

All such actions will be completed prior to fuel load.

An overide of any isolation signal will not cause automatic opening of any isolation valve.

a)

The following valves-in the Liquid Radwaste, Reactor Water Sample, and Reactor Building Chilled Water systems are normally open valves.

and will close upon a containment isolation signal.

HV-16116 HV-16108 HV-18781 HV-18782 HV-18791 HV-18792 B31-1F019 B31-1F020 Al 6 A2.

Al G,A2, Al 6 A2 6 Bl 6 B2 A1

& A2 6 B1 6 B2 Al 6 A2 6 B1 6 B2 A1 6 A2 6 Bl 6 B2 When the containment isolation logic is reset the above valves would have reopened.

The logic for these valves will be modified by fuel load to ensure that they will not reopen on logic reset.

Table X.1.29-1 reflects the modified. configuration of these valves.

b)

The RCIC and HPCI turbine steam supply line isolation valves (HV-lF007, HV-1F008, HV-1F002 and HV-1F003) are normally open valves and will close upon a steam line break isolation signal.

These valves are essential valves and do not receive a containment isolation signal.

Reopening of these valves will occur if the hand switches are not placed in the closed position by the operator prior to actuation of the reset switch and the isolation parameters have cleared.

These valves are equipped with key-locked maintained contact switches to insure that these valves are open during ECCS initiation. If a pipe break condition were detected, then these valves will be auto-matically closed.

After the pipe break problems are cleared, these valves can be reopened to their normal emergency positions by deliberate operator action using the key-locked reset switches for each system.

c)

The inboard HPCI and RCIC isolation valves each have a pressure equalization valve (HV-1F100 and HV-1F088) around them.

The equalization valves are normally closed and are only used to equalize the pressure around the inboard isolation valve in order to open them. If open, the valves will close upon a steam line break isolation signal.

Reopening of these valves will occur if the hand switches are not placed in the closed position by the operator prior to actuation of the reset switch and the isolation parameters have cleared.

As with the HPCI/RCIC isolation valves the equalization valves will reopen upon deliberate manual logic reset using the key-locked reset swithces.

These valves must open in order to allow the inboard isolation valves to reopen to their normal emergency positions when the pipe break problems have cleared.

If the equalization valve switches are not in the open position the operator must manually open them to equalize the pressure around the inboard HPCI/RCIC valves.

d)

The RHR containment isolation valves (HV-1F016 A, B, and HV-1F028A,B) associated with the drywell and suppression pool spray lines will reopen if their handswitches.are placed in the open position prior to actuation of the reset switch, the LPCI injection signals are clear, and the LPCI injection valves are closed.

These spray line valves are normally closed and are provided key-locked hand switches and receive an isolation signal as described, in Tables X.l.29-1 and X.l.29-3. If the valves were open before an LPCI injection event, these valves will automatically close and can not be reopened if

~

the LPCI'njecti'on signals. still exist or the LPCI injection valves are still open.

This is to insure that the LPCI injection function will not be inadvertently jeopardized by opening of the spray line isolation valves.

If these spray line valves were closed before the LPCI injection event, the valves will remain closed after reset even after all injection signals are clear and the LPCI injection valve are closed.

As noted in Table X.1.29-1 only the outermost valve is considered a

containment isolation valve for these penetrations.

The three inboard valves HV-1F021A, HV-1F027A and HV-1F024A are spring return to "AUTO" switches and will not automatically reopen after logic reset and all signals clear.

These inboard valves have not been considered containment isolation valves because they can not be leak tested in the "forward" direction.

Since these valves effectively function as containment isolation valves, a logic reset will not automatically result in a breach of containment integrity for these penetrations.

(5)

The BUR Owners'roup has performed a generic analysis which is summarized as follows.

The containment isolation analytical setpoint pressure for Mark I, II, and IIIcontainments is approximately 2 psig (drywell pressure).

Under normal operating conditions, fluctuations in the atmospheric barometric pressure as well as heat inputs (from such sources as pumps) can result in containment pressure increases on the order of 1 psi.

Consequently, the isolation setpoint of 2 psig provides a

1 psi margin above the maximum expected operating pressure.

The 1 psi margin to isolation has proved to be a suitable value to minimize the possibility of spurious containment isolation.

At the same time, it is such a low value (particularly in view of the small drywell volume of Mark I, II, and III containments) that it provides a very sensitive and positive means of detecting and protecting against breaks and leaks in the reactor coolant system.

No change of the setpoint is necessary for these containment types.

PP&L concurs with'his position.

Therefore, no modifications to the containment isolation pressure setpoint are necessary in response to this requirement.

(6)

The design of the containment atmosphere purge values was reviewed against Branch Technical Position CSB6-4.

On the basis of this review the following valves will be administratively maintained sealed closed when the reactor is in OPERATIONAL CONDITIONS 1, 2 or 3, except as provided is Technical Specifications 3.6.1.8.

Operations Instruction OPWI-012, "Locked Components",

implements the administrative controls for sealed closed valves.

VALVE P&ID M-157 COORDINATES HV-15704 HV-15714 HV-15721 HV-15722 HV-15723 HV-15724 HV-15725 C-7 E-7 D-3 D-4 D-2 C-2 C-4 Technical Specification 3.6,1.8 will be revised to require this sealed closed requirement, to be verified once per 92 days per Specification 4.6.1.8.

(7)

Two redundant safety grade radiation monitors are installed down stream of the Standby Gas Treatment System.

A high radiation level will trip the Standby Gas Treatment System.

This signal will be used to close the following containment isolation valves in the vent and purge system:

HV-15705, HV-15713, HV-15703, HV-15711, SV-15736A, SV-15737, SV-15767 and SV-15776A.

The radiation setpoint will be set to so that the 10CFR 100 limits are not exceeded.

The high radiation alarm for these detectors is annunciated on the control room front row panel 1C653.

The radiation level measured by these detectors is recorded on control room backrow panel 1C600.

These modifications will be complete by fuel load.

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