ML20064K314

Discusses Revised Assumptions Re Calculations to Support 30- Degree Open Position of Reactor Bldg Purge Valves.Reactor Bldg Purge Valves Capable of Closing Under LOCA Conditions. Responses Re Purge & Vent Operability Encl

ML20064K314
Person / Time
Site:	Crane
Issue date:	01/13/1983
From:	Hukill H GENERAL PUBLIC UTILITIES CORP.
To:	Stolz J Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.E.4.2, TASK-TM 5211-82-307, NUDOCS 8301180358
Download: ML20064K314 (12)

Text

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GPU Nuclear g

QQgf P.O. Box 480 Middletown, Pennsylvania 17057 717-944-7621 Writer's Direct Dial Number January 13, 1983 5211-82-307 Office of Nuclear Reactor Regulations Attn: John F. Stolz Operating Reactors Branch No. 4 U. S. Nuclear Regulatory Commission Washington, D.C.

20555

Dear Sir:

Three Mile. Island Nuclear Station, Unit 1 (TMI-1)

Operating License No. DPR-50 Docket No. 50-289 Reactor Building (RB) Purge Valves (NUREG 0737 II.E.4.2)

In response to your letter of November 2, 1982, GPUN has further refined its calculations concerning purge valve opening in order to provide a basis for operability using more realistic assumptions during a design basis accident (DBA). Presently, the purge valves are restricted to 30 open based on extremely conservative assumptions of instantaneous pressurization of con-tainment and 1,strument response time.

We have prepared revised calculations to support a 30 open position. These revised calculations are based on assumptions below, and supercede those in our submittal of March 22, 1981.

Revised Assumptions:

1.

Receipt of the containment isolation signal a 4 psig occurs at about.50 seconds into the DBA.

(See FSAR, figure 14-66) 2.

A one second instrument response time occurs between the 4 psig isolation signal and the time the motor uperated valves responds to the closure signal.

(See Attachment 3) 3.

The closure time for the motor operated valves from 30 open is 1.33 seconds.

(The requirements to have a motor operated valve close is worst case since the motorized valves close at a higher pressure due to their longer closure time.)

The detailed calculations are available onsite for NRC review.

Based on the above and the attached responses to NRC concerns, we conclude that the TMI-1 Reactor Building Purge valves are capable of closing under LOCA conditions. For LOCA conditions it is nevertheless preferred to operate with the Reactor Building Purge valves closed. Based on this, GPUN proposes to operate E301100358 830113 PDR ADOCK 05000289 P

PDR GPU Nuclear is a part of the General Pubhc Utihties System

. 5211-82-307 Mr. J. F. Stolz when the reactor is critical (except as necessary under emergency conditions) with the Reactor Building Purge valves closed. If purging is performed under emergency conditions the purge valves will be limited to 30 open. Uader shutdown conditions, we propose to purge as necessary with no limitation on purge valve opening. The TMI-1 resident inspector will be notified of any purging under emergency conditions.

Emergency conditions are defined as those conditions where it is necessary to enter containment durlug power operation to:

(1) investigate, prevent, or correct potential equipment damage (excluding routine maintenance)

(2) protect the health and/or safety of the public or TMI personnel.

It should be recognized that the above proposal will inhibit routine Reactor Building entries, due to personnel health and safety considerations related to temperature and/or radiation exposure. As a result, the frequency of surveillances of fire hose stations (TS 4.18.6), snubbers (TS 4.17.2), containment personnel airlock doors interlocks (TS 4.4.1.6), and radiation monitors (TS 4.1.1 table 4.1-1 item 28), which are required by existing Technical Specifications must be adjusted. Since the proposed restrictions will prevent containment entry for compliance with the above Technical Specification surveillance requirements, purging will be conducted to perform the required surveillances until the sur-veillance frequencies are revised by Technical Specification amendment. In addition, inspections performed pursuant to our response to IE Bulletin 80-24

" Prevention of Damage Due to Water Leakage Inside Containment" (TLL-694 dated January 22, 1981) will be limited accordingly. Finally, depending on Reactor Coolant activity and leakrate, post shutdown access to the Reactor Building may be significantly delayed due to noble gas and iodine / particulate activity buildup.

Upon NRC concurrence with the above purging restrictions, GPUN will implement the new restrictions and a Technical Specification change to address the restrictions will be submitted to incorporate the restrictions.

Also note that we ate currently investigating options to install a mini-purge system, as described in NRC letter of April 30, 1982, at some future outage.

Based on this we do not view the above commitment to foreclose implementing the mini-purge option at some future date.

Sincerely,

,--1(f.

\\%)

H. D.'Hukill HDH:CWS:jrg Director, TMI-l Attachment cc:

R. Conte J. Van Vliet

4 RESPONSES TO'NRC CO$CERNS* IDENTIFIED IN THEIR SER 70R PURGE AND VENT VALVE OPERABILITY TOR TM:-1 Item 1:

The allowable loads under shear for the shaft key and disc pins were much higher than acceptable. While these components did not appear to be overstressed the margins were much less than shown. The allowable shear loads was indicated to be 90% of yield strength.

1 i

Response

I The stress calculations the NRC reviewed have been re-examined by GPUN and found to be ov'erly conservative.

Based on more appropriate analysis methodology the stress level is predicted to be f

6,724 psi for the shaft key (allowable is 34,680 psi per Table 2) 9,221 psi l

for the disc pins (allowable is 12,000 psi per Table 2), and 14,338 psi for the shaft (allowable is 27,000 psi per Table 2).

4 l

Stress allowables used are appropriate since the low probability of coincident SSE and LOCA induced stresses justifies greater allowable limits.

See: Table 2 for revised stresses on the valves.

4 ltem 2:

The materials listed in the GPU report were inconsistent with the Pratt drawing and bill of materials. For example, the body material is listed in Table 2 as-ASTM-A-36, in the Bill of Materials as ASTM-A515 Grade 70 and on the Pratt drawings as ASTM-285 Grade C.

Response

The body material was. incorrectly identified as ASTM-A-36.

Originally the valve manufacturer intended to use ASTM-A-285 Gr. C as indicted on the drawings and bill of material. Later the manufacturer chose to substitute ASTM-A-515 Gr-70 a more modern carben steel with superior mechanical properties.

Evidence of use of ASTM-A-515 Gr. 70 is revealed on bill of material (See Table 1) as revised by issue 5.

Item 3:

GPU's submittal does not contain information on installation configurations, Upstream bends or elbows, separation distances, shaft orientations relative to i

upstream bends, disc closure direction and flow direction all have an effect on l

torque loads.

No comparison between actual installations and the Pratt test configuration were made to justify the torque loads used in the analysis. The straight pipe configuration believed to be the applicable test configuration j

does not normally yield the most conservative loads.

j

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Response

5 The TMI-l arrangement is a planar configuration as discussed in our conversation of November 23, 1982 with representatives of GPU, Brookhaven National Labs, and NRC.

Based on that discussion a factor of 1.5 has been applied to the calculated torque valves.

Item 4:

GPU did not discuss the details of how it glans to limit the valve opening on a long-term basis. A tolerance of plus 1.75 for valves AH-V-1A and AH-V-ID and 3.29 for AE-V-1B and AH-V-lC was progosed. No justification was provided for extendingthetolerancebeyondthe30,especiallyinvgewofthefactthatthe valve analysis shows the valve to be overstressed at 30.

Response

The Reactor Building Purge and. Vent valves AH-V-1A/B/C/D have been restricted to 300 open. A tolerance of +1.75 for valves AH-V-1AED was selected by interpolating an air operator torque output of 42,650 inch pounds between the operating torque at 30 and 35.

Similarly, a tolerance of +3.29 for valves AH-VlB&lC was selected by interpolating the motor operator torque output of 49,000 inch pounds between the total operating torque at 30 and 35. These tolerances permit reasonable field adjustments / measurements without unnecessarily restricting valve position and ventilation system flow. The maximum tolerance does not represent an over-1 stress condition.

i L

Item 6:

Periodic inspection of valve seats was discussed but not the maintenance program for the anti-friction roller bearings used on these valves. This area should be addressed in assuring operability.

t I

Response

The anti-friction roller bearings will be lubricated on a 12 month basis. Whenever i

a work function requires the bearings to be removed, they will be inspected and conditions noted in the machinery history.

i Item 5:

I GPU addressed a leakage problem for these valves at outside ambient temperatures below 60 F.

GPU's response to this issue is that the valve would be above 60 F in the event of a LOCA.

While the valve temperatures would increased to above 60 F in a LOCA event this should not be expected to occur instantaneously and some leakage would therefore l

be expected.

In addition, valve leakage may occur undesireably at times other than LOCA's.

GPU should take positive steps to clicinate this concern. The present method appears to be adjusting or replacing seats when the valve fails a l

leakage test.

This solution does not preclude a leakage problem between periodic leakage checks.

_.m-1

Response

The air temperature' surrounding the purge valves is maintained greater than 60 F.

Inaddition,heatersareprovidegtoheat the_ incoming air to maintain j

purge valve temperature greater than 60 F.

k'ith our proposed increased surveillance frequency of valve leakage (see Tech Spec Change Request 116, dated August 13, 1982) and our proposed reduced use of the purge valves the likelihood of leakage problems between tests is reduced. The redundancy of the valves further minimizes any potential leakage under accident conditions.

4 Item 7:

The air actuators are expected to have solenoid valves to vent the air. The qualification and air quality of these valves was not discussed. Solenoid valve failures are often the cause of air operator valves failures.

Response

The valve operators on the valves (AHV-1A&D) located outside of the Reactor Building are spring return _ sir cyclinders with the spring driving the valve to the closed position. Each valve is controlled with two 3-way solenoid valves, either one capable of permitting the valve to close even from the fully open position within 2 seconds. The purge valves will automatically close en loss of control air pressure or loss of electrical power.

I The Instrument and Conrol Air System delivers clean, dry air at 100 psig (-40 F i

dewpoint, filtered to 0.9 micron).

Item 8:

i Environmental and seismic qualification of the valve operators was not addressed.

Response

The pressure retaining parts and bolts meet material and nendestructive tests requirements of USAS B.31.7 Class I and meet Seismic Class 1 requirement (See Table 2 for specific SSE values). The environmental qualification of the valve operators is addressed in the August 28, 1981 revision to our response to IEB 79-01B.

Any environmental qualification concerns identified by the NRC will be addressed in response to the NRC SER on Environmental Qualification of Electrical Equipment which GPUN received on December 28, 1982.

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TABLE 1 - MATERIALS FOR VALVE COMPONENTS l

)

VALVE COMPONENTS MATERIAL TYPICAL ALL VALVES BODY A-515 GR. 70 DISC A-285 GR. C

~

SHAFT 18-8 TYPE 304 S.S SHAFT KEY AISI C 1.045 C.D. STEEL DISC PINS 18-8 TYPE 304 S.S.

BOTTOM COVER PLATE 126 CL.B CARB. STL. CASTING THRUST BEARING 18-8 TYPE 304 S.S.

OPERATOR BOLTS (1)

CARBON STEEL TRUNNION BODY A-285 CR.C TRUNNION BOLTS (1)

CARBON STEEL (1) Assumed Material of Bolts.to be Lowest Carbon Steel 193 B7.

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

4 n

_ TABLE 2 - SCilEDULE OF STRESSES 1

t I

i STRESS LEVEL (PSI)

ALLOWABLE STRESS DESTCNATION STRESS (PSI)

C PONENT SYMBOL AH-V-1A,-1D All-V-1B,-1C PRIMARY MEMBRANE Pm 99q 990 Sm = 22500 PRIMARY + SECONDARY STRESS DUE TO INTERNAL QP 2970 2970 Sm = 22500 l

PRESSURE a

l Ped 2542 2542 1.5Sm=33750

• BODY PIPE AXIAL REACTION BENDING Peb 9164 9164 1.5Sm=33750 j

STRESS TORSION Pet 4773 4773 1.5Sm=33750 TIIERMAL SECONDARY Qt 1197 1197 Sm = 22500 i

STRESS PRIMARY + SECONDARY Sn 13428 13428 3Sm = 67500 STRESS

'i

• SEISMIC STRESSES IN TIIE BODY ARE FOUND-TO BE NEGLIGIBLE.

4

i l

TABLE 2 - SCllEDULE OF STRESSES (CONT'D)

STRESS LEVEL (PSI)

ALLOWABLE VALVE STRESS (PSI)

COMPONENT STRESS DESIGNATION SYMBOL AH-V-1 A, -D All-V-lB, -lC (A) 88 (A) 88 '

DISC COMBINED BENDING STRESS S(l)

(B) 4563 (B) 4563

.9Sy = 27000 ON DISC CENTERLINE (C) 4651 (C) 4651 (A) 0 (A) 0 TORSIONAL SilEAR STRESS S(9)

(B) 3278 (B) 3278

.6Sm = 12000 (C) 3278 (C) 3278 COMBINED SilEAR STRESS S(6)

SHAF'I 3 6

)

56

.6Sm = 12000 (C) 3964 (C) 3929 (A) 687 (A) 465 COMBINED STRESS SilEAR &

S(4)

(B) 13651 (B) 13651

.95y - 27000 BENDING (C) 14338 (C) 14116 SIIAFT SilEAR STRESS ON KEY S(16)

B 6 24 B) 6 24

.6Sm = 34680 (C) 6724 (C) 6724 (A) 830 (A) 562 DISC PIN SilEAR STRESS ON PINS S(17)

(B) 8391 (B) 8391

.6Sm = 12000 (C) 9221 (C) 8953 BEARING STRESS ON TilRUST S(22) 0

)

0

.9Sy = 27000 CO W R (C) 92 (C) 169 (A) 0 A

SilEAR STRES5 ADJUSTING S(27)

)

B 0

.6Sm = 13440 TilRUST (C) 460 (C) 843

) 3325 (A)6096 COMBINED STRESS S(28)

)

RETAINER B01.TS (C) 3325 (C)6096

[ (A) 472 (A) 866 SIIEAR TEAR OUT 07 TilRUST S(31)

(B)

O'~

(B) 0

.6Sm = 13440 RETAINER Bol.TS (C) 472 (C) 866

O TABIE 2 - SCIIEDULE OF STRESSES (CONT'D.)

VALVE STRESS LEVEL (PSI)

ALLOWABLE COMPONENT STRESS DESIGNATION SYMBOL All-V-1 A,-lD AH-V-1B,-1C SHEAR TEAR OUT OF (A) 168 (A) 307 l

TAPPED 110LES (C) 1097 (C) 1237 COVER BOLTS THRU S(33)

(B) 929 (B) 930

.6Sm = 13440 l

SilEAR TEAR OUT OF (A) 125 (A) 229 COVER BOLT HEAD S(34)

(B) 693 (B) 693

.6Sm = 13440 BOTT0ti THRU COVER (C) 818 (C) 922 COVER PLATE COMBINED STRESS S(38)

(A) 322 (A) 440 IN COVER (P) 352 (B) 508

.6Sm = 12400 (C) 674 (C) 948 SHEATTEAR OUT OF (A) 1065 (A) 751 TRUNNION BOLTS IN S(42)

(B) 0 (B) 0 6Sm = 13440

" " ^

,ES (C) 1065 (C) 751 BEARING STRESS OF TRUN-(A) 1864 (A) 690 NION BOLT ON TAPPED S(43)

(B) 979 (D) 979

.9Sy = 94500 HOLE IN TRUNNION (C) 2843 (C) 1669 (A) 6038 (A) 4259 TENSION IN BOLT ON S(47)+

OPERATOR

()

0 (B) 0

@ " %W TOP OF TRUNNION S(48)

MOUNTING (C) 6038 (C) 4259 SilEAR DUE TO TORQUE (A) 2706 (A) 893 ON TRUNNION BOLTS S(50)

(B) 2157 (B) 2156

.6Sm = 13440 (C) 4863 (C) 3049 COMBINED STRESS IN (A) 6348 (A) 4747 TRU!alION BOLTS S(46)

(B) 2157 (B) 2156

.9Sy = 94500 (C) 8505 (C) 6903 COMBIMED STRESS IN (A) 7423 (A) 4273 i

OPERATOR BOLTS S(53)

(B) 2746 (B) 2746

.9Sy = 94500 (C) 10164 (C) 7010 (A)

STRESSES DUE TO SEISMIC EV!:NT (SSE)

(B)

STRESSES DUE TO I.0CA INCLUDINC FACTOR OF 1.5 DN DYNAMIC TORQUE REQUESTED BY NRC (C)

COMBINED STRESSES

INSTRUMENT RESPONSE DELAY TIME 4 PSIG SIGNAL TO REACTOR BUILDING PURGE VALVES l.

Impulse tubing' response - 70' of tubing with pressure rise j

traveling at 20G'/sec.

Delay:

.35 sec.

4 2.

Transmitter response

" response time" of these transmitters for step inputs is estimated as 2' seconds. For a ramp input, the time constant added to the transmitter dead time is a conservative approximation of delay.

I Delay:

.415 sec.

i 3.

Buffer amplifier response

" response time" of these amps is stated as.6 sec.

For a ramp input, the time constant is a conservative approximation of delay.

a Delay:

.12 sec.

i 4.

Bistable response - as above, " response time" =.065 sec.

Delay:

.013 sec.

5.

Relay response - Delay:

.1 sec.

Total response time:

.998 sec.

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