Text

Forwards Comments on NRC Draft Evaluation of SEP Topic IV-4. Util Recently Reviewed & Provided Info to NRC Re Containment Isolation Sys in Response to TMI Category a Lessons Learned Items in NUREG-0578
	ML18046A867
Person / Time
Site:	Palisades
Issue date:	08/10/1981
From:	Vincent R; CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:	Crutchfield D; Office of Nuclear Reactor Regulation
References
	RTR-NUREG-0578, RTR-NUREG-578, TASK-06-04, TASK-6-4, TASK-RR NUDOCS 8108140239
	Download: ML18046A867 (19)
	v • d • e

...

consumers Power company General Offices: 212 West Michigan Avenue, Jackson, Ml 49201 * (617) 788-0660 August 10, 1981 Director, Nuclear Reactor Regulation Att Mr Dennis M Crutchfield, Chief Operating Reactors Branch No 5 U S Nuclear Regulatory Commission Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT - SEP TOPIC VI-4, CONTAINMENT ISOLATION SYSTEM By letter dated June 9, 1981,. the NRC t;&ismitted.for comment a draft evaluation of SEP Topic VI-4 for the Palisades Plant; Attached are the Consumers Power comments on that report.

Robert A Vincent Staff Licensing Engineer CC Director, Region III, USNRC NRG.Resident Inspector-Palisades 8108140239 810810 PDR ADOCK 05000255 P

PPR L

GENERAL COMMENT

S PALISADES PLANT EVALUATION REVIEW COMMENTS SEP Topic VI-4, Containment Isolation System

1.

Some penetrations in classes Al, A2, Bl, C2 and C3 differ from the current

explicit requirements of the General Design Criteria in that both contain-ment isolation valves are outside containment.

It must be noted that this design complied with criteria which were applicable at the time of construc-tion, predated current design criteria, and is still in compliance with the licensing basis for the Palisades Plant.

This subject was addressed in Amendment 4 to the Application for Reactor Construction Permit and Operating License dated November 29, 1966.

As dis-cussed in Question 25, the criteria applicable to Palisades design were:

A.

"Lines which penetrate containment and are open to the external atmos-

.phere or to systems designed for less than containment design pressure shall be protected by redundant, automatic* isolation valves if they fulfill any of the following conditions:

1) They are connected to the primary system.

2) They are normally open to containment atmosphere.

3) They are certain to be ruptured in the event of an MHA.

Exceptions:

Lines which must remain open subsequent to an MHA may be protected by not less than one remote-manual valve and one check valve.

. *Check valves are considered to be automatic valves."

B.

"Ventilation lines shall be isolated upon receipt of* 'Safety Injection' signals."

(Note:

Exception was taken to this criteria on the basis that contain-ment high radiation and pressure rather than safety injection signals were utilized to assure "isolation in the event of a primary coolant leak which is not of sufficient magnitude to require actuation of the safety injection system but of.sufficient magnitude to require contain~

ment isolation.")

C.

"Lines which have a low probability of rupture during an MHA (e.g.,

certain secondary system lines) shall be protected by at least one automatic valve external to containment."

D.

"Instrumentation *and control circuits associated with automatic valve closure shall fail safe ( initiate closure) upon loss of vol t"age and/ or control air.

Circuits which control redundant automatic* valves shall be redundant in the sense that no single failure shall preclude isolation."

SEP Topic VI Comments Page Two The AEC Safety Analysis dated Februai-y 7, 1967 found the Palisades design for containment isolation to be acceptable, and stated, From our review, we are satisfied that the applicant's plans for containment isolation and testing. Will. provide a reliable Containment envelope, II Subsequently during plant construction, the AEC issued proposed "General Design Criteria for Nuclear Power Plant. Construction Permits."

The cri-.

terion which pertained to containment isolation was Criterion 53 of the AIF redraft issued *by AEC Press Release No. K-:-172 on July 10, 1967.

This cri-terion states:

"Penetrations that require closure for the containment function shall be protected by redundant valving and. associated apparatus."

As discussed in.Appendix I of the FSAR, th~ Palisades design was determined to be in compliance with the intent of this criterion.

In the years which have passed since Palisades construction, the AEC/NRC philosophy toward containment isolation systems has changed somewhat.

However, there do.not appear to have been any significant technological changes or advances in the state-of-the-art which would invalidate the con-tainment isolation design of Palisades.

Present General Design Criteria 54-57 have not been retroactively imposed as the licensing basis for Pal-isades, and there is no apparent safety reason why they should be imposed now.

Notwithstanding the above discussion, the present containment isolation design*

at Palisades meets the intent of the present General Design Criteria.

The piping

between each penetration can be viewed simply as an.extension.of the containment barrier itself and offers protection equivalent to the standard GDC configuration.

This conclusion is based on the following considerations:

A.

As a plant design basis, the piping between the containment and the containment isolation valves is rated for at least twice*

.containment. design pressure (FSAR 5.l.6.2(b)).

Isolation valves

are similarly rated.

B.

Piping runs between the containment penetrations and the containment

isolation valves have be.en kept as short as possible (Amendment 1, CP&OL Application).

c.

All piping penetrations are solidly anchored to the containment wall... External guides, stops, increased pipe thickness or other means are provided where required to limit motion and moments to prevent ruptures by making the penetration the strongest part of the system.

In addition, all penetrations and anchorages are de-signed for forces and moments which might result from postulated pipe ruptures ( FSAR 5.1. 5. 3 and Appendix A).

D.

All piping penetrations are located in areas which are protected from tornado missiles (FSAR 5.1.5.1).

SEP Topic VI Comments Page Three In summary, it is apparent that the quality of the containment piping pene-trations is commensurate with their safety functions, and that the Palisades external isolation valve configuration offers integrity equivalent to the current GDC arrangement wi<th one valve inside and one outside.

2.

In some cases check valves are used as containment isolation valves outside containment.

This has been interpreted by the NRC reviewers as being unac-ceptable in light of the current General Design Criteria which only allows check valves to be used as isolaticn valves inside containment.

To fully address this deviation, three basic issues must be discussed.

A.

The first issue concerns the acceptability of using check valves at all for containment isolation valves.

As discussed in comment l above, check valves were considered by the staff to be acceptable automatic isolation valves when Palisades was built.

Current criteria.also ex-plicitly 'recognize the acceptability of check valves as containment.

isolation valves.

Current criteria, therefore, have not changed, and this issue is not in contention.

At Palisades in order to ensure con-tinued functionability of containment isolation check valves, testing is routinely addressed in the ASME B&PV Code,Section XI test program

.and/or in the 10CFR50 Appendix J. test program.

B.. The second issue. concerns the.* acceptability of using* a check valve for isolation outside containment in light of the current General De-sign. Criteria provision that check valves only be used inside.

As dis-cussed in General Comment l above, the containment penetration piping up to the isolation valves is designed as a direct extension of the containment boundary with at least twice the design pressure integrity.

From this standpoint it is immaterial whether the check valve is inside or outside containment.

It would appear that the purpose of the GDC provision is to ensure that the check valve is used as the first of two series valves rather than to simply prohibit the use of a check valve outside containment.

In light of General Comment 1, therefore, it is concluded that Palisades' series valve arrangements which use a check valve as the isolation valve nearest to containment are* acceptable and meet the intent of current criteria.

C.. The third issue concerns the acceptability of using a check valve as the outboard of two series containment isolation valves.

A total of twelve penetratio!ls at Palisades have this arrangement, although not all explicitly depend on the check valve as an automatic containment isolation valve.

In general terms, there is little practical difference between using a check valve as*the inboard or the outboard valve in a series contain-ment isolation valve arrangement.

Series valves are provided for redundancy to ensure that isolation is provided in spite of a valve failure to close.

If a check valve is the outboard valve of the two, failure of the inboard valve to close would still leave the operable check valve to provide isolation.

With the opposite arrangement, if an inboard check valve failed to close, the outboard conventi0nal valve would still provide isolation.

According to WASH-1400, the probability A

SE1' Topic VI~4 -

Comments Page Four of a check valve failing open is approximately 7.2 x lo-6/day, and

. the 4probability that an air-operated valve will fail to operate is 3 x 10- /day.

Check valves are more reliable than powered valves, and their failiire probabilities can be further reduced by periodic tests.

From.the standpoint of*testing.effects on check valve failure rates, a distinct advantage exists when the check valve is the outboard of two series isolation valves.

For non-essential systems, this configuration allows a functionability test to be performed on a routine basis by sim-ply pressurizing the line between the check and the inboard series iso-lation valve.

At Palisades this check valve closure functionabili ty test is performed on a quarterly basis for most penetrations which can be isolated during plant.operation.

These routine functionability tests would not be practical if the check valves were inboard of the second isolation valve. *These tests, therefore, provide better assurance of check valve operability, and therefore safety, than a requirement to use a check valve only as an inboard isolation valve which would generally only be testable during plant outages.

Of the twelve penetrations with check valves as the outboard isolation valves, Technical Specification Surveillance Test Q~ll tests check valve closure funct ionabili ty on five ( Penet:r:ations 11, 37, 41, 42 & 67).on a

. quarterly basis.

This test is also performed on penetration 39 when the check valve is installed (normal configuration during operation is with the check valve removed and the line blank flanged).

Four of the check v8.lves are on systems which cannot be isolated during plant operation (Penetrations 14, 30:, 31 & 65), and are therefore tested during refueling outages.

The remaining two pt;!netrations (10 & 26) have their second iso-lation valves normally closed during operations, and do *not normally rely on the* check valve. for isolation.

Check valve closure functionability is tested at least each refueling outage.

SPECIFIC COMMENTS

l. Page 9, Penetration Class Al:

Pen #1 (Purge Air Supply) - This penetration is now blanked off outside containment with a blind flange.

The blind flange is sealed with double O-rings.

There is a test tap between the 0-rings so that leak tightness can be measured.

Pen #4 (Purge Air Exhaust) - This penetration is blanked off in the same manner as Pen #1.

Pen #4A, 52 & 68:

See General Comment No. 1.

2.

Page 10, Penetration Class A2:

Pen #27 (ILRT Fill Line) - This penetration consists of a blind flange in-side containment and a motor operated valve (MOV-Pl) outside.

The MDV is the secdnd isolation valve and is verified closed each month under techni-.

cal specification surveillance procedure M0-29.

SEP Topic VI Comments Page Five Pen #10 (Service Air)- See General Comment No. 2.

The service air system is a closed syst.em inside containment.which is designed for a pressure greater than containment design pressure.

The manual containment isolation valve is normally locked closed during reactor operation.

Check valve clo-sure functionability ~s verified quarterly tinder Tech Spec Surveillance Procedure Q0-11.

In addition, the line up to the locked manual isolation valve is normally pressurized to approximately 80 psig which is above con-tainment design pressure.

Pen #30 & #31 (CSS into Containment)

See General Comment No. 1.

Pen #65 (Instrument Air) - See general comments regarding location of isola-tion valves.

The check valve is considered automatic, so there is automa-tic containment isolation for a pipe break upstream of the check valve.

In addition, the instrument air. system is a closed system with both design and working pressures greater than containment design pressure.

Thus, there would be flow into containment.

Also, although instrument air is not an "essential system", it still remains a convenient system to have to provide maximum operating flexibility to recover from any unplanned event.

3.

Page 12, Penetration Class Bl:

Pen #36 (Letdown to Purification Ion Exchang~ )- See General Comme.nt No. l.

The first isolation valve for this penetration, CV-2009, closes automati-cally on CIS.

The second isolation valve is a parallel set of CV-2012 and CV-2122 (not CV-2022).

These valves do not close on CIS, but mainta-in a back pressure in the line upstream of the letdown heat. exchanger in the containment.

Thus, for a pipe break in the letdown line inside containment, CV-2012.and CV-2122 would ramp closed in attempting to maintain pressure.* This provides a means of penetration isolation which provides no less protection than a CHP trip.

This penetration would only provide a potential leak path from the containment atmosphere to the containment exterior in the event of a letdown line break inside containment.

Pen #40 - See General Comment No. 1.

Pen #45 (Charging Pump Discharge) - See General Comment No. l. The charging system is an essential system for post-DEA.

Thus, it is important that CV-2111 not be automatically isolated. In the event of a break in the charg-ing line outside containment, the check valve will provide automatic isolation.

4.

Page 13, Penetration Class Cl:

Pen #2 & #3 (Main Steam) - The ~solation valves for these penetrations, CV-0510 and CV-0501, (MSIV's) *are swing check valves opened and closed by air operators.

These valves automatically close on CHP or steam generator low pressure.

The check valve prohibits the blowdown of the nonruptured S/G following an MSLB.

Since this requires rapid valve closure, a check valve is appropriate because of its speed.and reliability. *Also, the main steam line is open to the containment only for an MSLB inside containment.

For this accident, there is no radioactive release and thus, any MSIV check valve leakage would not produce any releases outside the containment.

gEP Topic VI Comm.en~

Page Six Pen #7 & #8 (Main Feedwater) - The steam generators provide the preferred method of heat removal during a small LOCA.

Thus, the feedwater isolation valves should not be arbitrarily closed on CIS.. The feedwater regulating valves close *on steam generator low pressure, thus providing automatic iso-lation of feedwater for an MSLB.

Analysis shows that the present system will.mitigate the consequences of an MSLB.

Thus, there is no advantage to having automatic feedwater isolation valves while there is the disadvantage that the likelihood of losing feedwater during a small LOCA increases.

Pen #16 & #55 (Surface Blowdown) - The isolation valves for these penetra-tions meet the requirements of GDC 57.

5..

Page 14, Penetration Class C2:

Pen #5, 6, 15, 25, 38, 46, 49 & 69 - See General Comment No. 1.

Pen #11, 14, 26, 37, 41, 42 & 67 - See General: Comments 1 & 2.

Pen #39 (Containment Heating Steam) - During plant operation t.he check valve is normally replaced with a blank flange.

See General Coi:nment No. 1.

Pen #44 (Primary Coolant Pump Controlled Bleed) - Primary cqolant passing through this line first passes through several pressure-reducing stages in the. primary coolant pump seals, and then through a throttle valve downstream of the automatic.containment isolation valve.

Tot~l flow through this line is only appro~imately four gpm under normal PCS pressure conditions.

6.

Page 15, Penetration Class C3:

Pen #33 & 40A.,.. Se.e *General Coinment No. 1.

7.

Page 16, Penetration #21, 29 & 73:

Standard design practice for containment penetrations is to design the piping and valves to R.G. 1.26, Quality Group B (ASME Class 2) standards.

This is also stated in paragraph II.10.a of SRP 6.2.4.. According to the ASME Boiler

& Pressure Vessel Code,Section III, Subsection NC, threaded or compression fittings as well as flanged connections are allowed in ASME Class 2 piping.

There appears., therefore, to be no basis for the staff' s contention that

threaded pipe caps and blank flanges are unacceptable isolation barriers.

Pipe caps and blank flanges do comply with ASME requirements, and are

-therefore acceptable under the SRP.

8.

Page 16, Penetrations 12 & 13:

These comments apply to penetration 13 only.

With respect to the pipe caps and flow element, see Specific Comment No. 7.

9.

Page 16, Penetrations 17 & 48:

See Specific Comment No. 7.

SEP'Topic VI Comments Page Seven

10.

Page 16, Penetrations 19, 50 & 51:

See Specific Comment No. 7.

11.

Page 17, Penetration 28:

See Specific Comment No. 7.

12.

Page 20, Conclusion 1:

See General Comment No. 1.

13.

Page 202 Conclusion 2:

See General Comment No. 2.

For penetrations 7 & 8, see Specific Comment No.

14.

Page 212 Conclusion 3:

See Specific Comment No. 7.

15.

Page 22, Conclusion 6:

\\ '-

See Specific Comment No. 5.

16.

Page 22, Con~lusion 7:

See Specific Comment No. 7..

17.

Page 23, Conclusion 9:

A.. A complet.ed Table 1 is attached.

- B.

Consumer.s Power Company has recently reviewed and provided information to the NRC on containment isolation systems in response to TMI Category A, Lessons Learned, Items in NUREG 0578.

Pertinent information was submitted to the NRC in. CPCo letters dated 10/17/79, 12/27/79, 02/27/80, and 03/04/80.

By letter dated April 6, 1980, the NRG.transmitted its evaluation of Consumers Power Company response to Item 2.1.4,.Contain-ment Isolation.

This evaluation concluded that Palisades containment isolation design met the pertinent requirements, including diversity and essential/nonessential systems considerations, and was therefore acceptable subject to verification of the CHR detector locations.

This.

verification was completed and pertinent information was submitted in CPCo letters of 5/20/80 and 5/27/80 to resolve the issue.

4.

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